Text

Proposed Tech Spec Section 3/4.3.1,revising Specified Surveillance Intervals & out-of-svc Times for Reactor Protection Sys Instrumentation
	ML20138C752
Person / Time
Site:	Callaway
Issue date:	10/16/1985
From:	; UNION ELECTRIC CO.
To:	;
Shared Package
ML20138C733	List: ML20138C728; ML20138C752;
References
	NUDOCS 8510230029
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3/4.3 N TRUMENTATION

,^.

3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION I

J 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of; Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.

I APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

s SURVEILLANCE REQUIREMENTS 4.3.1.1.Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERA 8LE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3-1.

3

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4. 3.1. 2 The REACTOR TRIP SYSTEM' RESPONSE TIME of each Reactor trip function-

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shall be demonstrated to be within its limit at least once per 18 months.

Each. test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times la months where N.is the total number of redundant channels in a specific Reactor trip function as shown in the

" Total No. of Channels" column of Table 3.3-1.

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l 1

8510230029 851016 PDR ADOCK 05000483 P

PDR 4

N CALIAWAY - UNIT 1 3/4 3-1 j

l l

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O TABLE 3.3-1 h

REACTOR TRIP SYSTEM INSTRUMENTATION, c

HINIMUM TOTAL NO.

CilANNELS CilANNELS APPLICABLE FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE H0 DES ACTION E

.q

'l.

Manual Reactor Trip 2

1 2

1, 2 1

2 1

2 3^, 4^, 5*

10 g

2.

Power Range, Neutron Flux a.

liigh Setpoint

'4 2

3 1, 2 2#

b.

Low Setpoint 4

2 3

1###, 2 2#

4 2

3 1, 2 2s 3.

Power Range, Neutron Flux High Positive Rate t-4.

Power Range, Heutron Flux, 4

2 3

1, 2 2#

i y

High Hegative Rate i

+

y 5.

Intermediate Range, Neutron Flux 2

1 2

1###, 2 3

I 6.

Source Range, Heutron Flux a.

Startup 2

1 2

2##^^

4 b.

Shutdown 2

l' 2

3**,

4, 5 5

i 7.

Overtemperature AT Four Loop Operation 4

2 3

1, 2 6#

8.

Overpower AT i

Four Loop Operation 4

2 3

1, 2 6#

9.

Pressurizer Pressure-tow 4

2 3

1 6#

10.

Pressurizer Pressure-High 4

2 3

1, 2 6#

m _,

p n

}

l TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEN INSTRUMENTATION C

6 MINIMUM TOTAL H0.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE HDDES ACTION 4

11. Pressurizer Water Level-High 3

2 2

1 6R e

12. Reactor Coolant flow-Low r

a.

Single Loop (Above P-8) 3/ loop 2/ loop in 2/ loop in 1

64 j

any oper-each oper-ating loop ating loop b.

Two Loops (Above P-7 and 3/ loop 2/ loop in 2/ loop 1

6/s below P-8) two e,,er-each oper-ating loops ating loop 13.

Steam Generator Water

'4/sta. gen.

2/sta. gen.

3/sta. gen.

1, 2 6# (8)

Level-tow-Low in any oper-each oper-w d,

ating sim.

gen.

14. Undervoltage-Reactor Coolant Pumps 4-2/ bus 2-1/ bus 3

1 6#(s)

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

1 6#

16. Turbine Trip a.

Low fluid Oil Pressure 3

2 2

1 6 d#

b.

Turbine Stop Valve Closure.

4 4

1 1

11#

17.

Safety injection Input from ESF 2

1 2~

1, 2 9

l

.~.

TABLE 3.3'-1 (Continued) 9 REACTOR TRIP SYSTEM INSTRtMENTATION HININUH N

TOTAL NO.

CHANNELS CilANNELS APPLICABLE g

FUNCTIONAL P:elT OF'CilANNELS 10 TRIP OPERAALE H0 DES ACTION G

18. Reactor Trip System Interlocks g

a.

Interniediate Range Neutron Flux, P-6 2

1 2

2##

8 b.

Low Power Reactor Trips Block, P-7P-10 Input 4

2 3

1 8

~

or P-13 I,nput 2

1 2

1 8

c.

Power Range Neutron Flux, P-8 4

2 3

1 8

d.

Power Range Neutron Flux, P-9 4

2

-3 1

8 e.

Power Range Neutron Flux, P-10 4

2 3

1, 2 8

f.

Turbine Impulse Chainber Pressure, P-13 2

1 2

1 8

19. Reactor Trip Breakers 2

1 2

I 2 9

2 1

2 3g 4*, 58 10

20. Automatic Trip and Interlock Logic 2

1 2

I 2 9

2 1

2 3g 4*, S*

10

,6

A TABLE 3.3-1 (Continued) 7 TABLE NOTATIONS

Only if the Reactor Trip System breakers happen to be in the closed position and the Control Red Drive System is capable of rod withdrawal.

""The boron dilution flux doubling signals may be blocked during reactor startup in accordance with approved procedures.

The provisions of Specification 3.0.4 are not applicable.

1. Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

1. 1. Below.the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

~

ACTION STATEHENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum

Channels OPERABLE 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 be in HOT STANDBY within s

the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 2 - 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 W hour,4 4

(

b.

The Minimum Channels OPERABLE requirement is met; owever, the inoperable channel may be bypassed for up to hours 4

for surveillance testing of other channels per Specification 4.3.1.1, and c.

Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Intermediate Range Neutron Flux interlock)

Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THEPP.AL POWER above the P-6 Setpoint; or b.

Above the P-6 (Intermediate Range Neutron Flux interlock)

Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.

2 v

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y-aplica.ble NobES a.nd A2770M sic}<med Cet.lfasa channa(,,

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~T/re nc[ed in Tc.ble.5. 3-5 a.re mots resbriclue a.11l -$dere %rs, ayylicable.

^

l CALLAWAY - UNIT 1 3/4 3-5

' TABLE 3.2-1 (Continued)

ACTICN STATEMENTS (Centinued)

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

~

ACTION 5 - a.

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the in-operable ch'annel 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, suspend'all opirations 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 s

within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and verifi'ed to be closed and secured in position every 14 riays.

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:

The inoperable channel is placed in the tripped cordition a.

within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and 6

b.

The Minimum Channels OPERABLE requirement is met; howevei, the inoperable channel may be bypassed for up to $ hours for surveillance testing of other channels per T

Specification 4.3.1.1.

ACTION 7 -iliS +he number of OPERABLE channels one less than th Numberhaub,M and/or POWE may proceed h*IeIch until performance of the yun ed wat nG CHANNEL OPERATIONAL TEST provi perable channel is placed in Inv-trfpp-d on within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

e ACT' ION 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 requiLred state for the existing plant condition, or apply Specification 3.0.3.

With the number of OPERABLE channels one less than the Minimum ACTION 9 Channels OPERABLE requirement, be in at least HOT STANDBY -

within 6 hcurs; 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 number of OPERABLE channels one less than the Minimum Channels OPERABLE 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 - W.ith the number of OPERABLE channels less than the Total Number of Channels, operation may continue prov[ded the inoperable.

channelsareplacedinthetrippedconditionwithinEhoug?

la 3/43-6 CALL /.WAY - UNIT 1

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TABLE 3.3-2 r2 f;

REACTOR TRI'P SYSTEM INSTRUMENTATION RESPONSE TIMES t

a e

FUNCTIONAL UNIT.

RESPONSE TIME EE 1.

Nanual Reactor Trip N.A.

.-i r4 2.

Power Range, Neutron Flux.

5 0.5 second*

3.

Power Range, Neutron Flux, liigh Positive Rate N.A.

4.

Power. Range, Heutron Flux, liigh Negative Rate

$ 0.5 seconda 5.

Intermediate Range, Neutron Flux N.A.

j' 6.

Source Range, Heutron Flux N.A.

}*

7.

Overtemperature AT 5 6.0 seconds

8.

Overpower AT 1 6.0 seconds" 9.

Pressurizer Pressure-l.ow 1 2.0 seconds 10.

Pressurizer Pressure-liigh 5 2.0 seconds 11.

Pressurizer Water Level-liigh N.A.

" Neutron detectors are exempt from response time testing. Response time of the neutron flux signal portion of the channel shall be measured from detector output or input to first electronic component in channel.

1

~n TABLE 3.3-2 (Continued) 9 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES r-C

.a A

[

FUNCTIONAL UNIT RESPONSE TIME k

12. Reactor Coolant Flow-Low

-i

~

w a.

Single Loop (Above P-8)

$ 1.0 second b.

Two Loops (Abova 9-7 and below P-8) 5 1.0 second 13.

Steam Generator Water Level-Low-Low 1 2.0 seconds

^

14. Undervoltage-Reactor Coolant Pumps 1 1.5 seconds

15. Underfrequency-Reactor Conlant Pumps 1 0.6 second 16.

Turbine Trip i,

1 a.

Low Fluid Oil Pressure N.' A.

~

b.

Turbine Stop Valve Closure N.A.

y ce 5

17. Safety Injection Input from ESF N.A.

18. Reactor Trip System Interlocks N.A.

N.A.

19. Reactor Trip Breakers 20.

Automatic Trip and Interlock Logic N.A.

i l

4 4

-l i

l n,

'S 7

~

[

TABLE 4.3-1 9

h REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP

'd ANALOG ACTUATINC NODES FOR i'

CHANNEL DEVICE Wii!Cil U

E CilANNEL CilANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE ye FUNCTIONAL UNIT CilECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED 1.

Manual Reactor Trip '

N.A.

R N.A.

1, 2, 3*, 48, 5*

2.

Power Range, Neutron Flux a.

High Setpoint S

D(2,4),

Jt'G(t#)

N.A.

1, 2

4 H(3, 4),

Q(4,6),

R(4, 5) b.

Low Setpoint S

R(4)

XS/0[s).

N.A.

1###, 2 3..

Power Range, Neutron Flux, N.A.

R(4)

E Q (/V)

N.A.

1, 2

.m

)

liigh Positive Rate 4.

Power Range, Neutron Flux, N.A.

R(4)

M-Q(/1)

N.' A'.

N.A.

1, 2 Nigh Negative Rate 5.

Intermediate Range, S

R(4; S)

S/U(1),)(

N.A.

1###, 2 Neutron Flux 6.

Source Range, Hautron Flux 5

R(4,5,12)

S/U(1),

N.A.

2##, 3, 4, 5 I

7.

Overtemperature AT S

R(13)

.W Q (/4)

H.A.

N.A.

1, 2 8.

Overpower AT S

R

)( Q C4)

N.A.

1, 2 9.

Pressurizer Pressure-Low S

R AIQ(/V)

N.A.

l

~

)

10.

Pressurizer.*ressure-High 5

R

,M' Q(/4)

N.A.

1, 2

11. Pressurizer Water Level-Nigh S

R Jt'Q(14)

N.A.

I

12. Reactor Coolant flow-Low S

R gQ(/4)

H.A.

N.A.

I 1

I

^

TABLE 4.3-1 (Continued) 9 REACTOR TRIP SYSTEN INSTRun..lTATION SURVEILLANCE REQUIRENENTS e-h

~

TRIP R

ANALOG ACTUATING MODES FOR CilANNEL DEVICE WillCH c

CilANNEL CilANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CilECK CALIBRATION TEST

. TEST LOGIC TEST IS REQUIRED H

H

13. Steam Generator llater Level-S R

EQ(/p,/5)

H.A.

N.A.

1, 2 Low-Low

14. Undervoltage - Reactor Coolant N.A.

R N.A.

XQ[1V,id)

N.A.

I

~

. Pumps

15. Underfrequency - Reactor N.A.

R N.A.

.MQ(v/)

N.A.

1

~

Coolant Pumps 16.

Turbine Trip m

N a.

Low Fluid Oil Pressure N.A.

R N.A.

S/U(1, 10)

H.A.

I u4 b.

Turbine Stop Valve N.A..

R H.A. -

S/U(1, 10)

N.A.

1 o

Closure 17.

Safety Injection Input from N.A.

N.A.

N.A.-

R N.A.

1, 2 ESF 18.

Reactor Trip System Interlocks a.

Intermediate Range

~

Neutron Flux, P-6 N.A.

R(4)

X8 N.A.

N. A.

2##

r i.

,_.n_.__o_.._._

~ UpUidN H J..

"(4)

M(e)

9. A.

H.A 1

b,ef Power Range Neutron Flux, P-8 N.A.

R(4)

(87 8 N.A.

N.A.

1 c JE Power Range Neutron Flux, P-9 N.A.

R(4)

Ji(878 N.A.

N.A.

1

.PI 4

% f 9'

..s

.g

'i s

I

/

TABLE 4.3-1 (Continued)

~

h REACTOR TRIP SYSTEM INSTRUMENTATION SURVEII. LANCE REQUIREMEriTS G

f TRIP H00E5 FOR ANALOG ACTUATING CHANNEL DEVICE milch E

CNANNEL CNANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE Q

FUNCTIONAL UNIT CilECK CALIRRATION TEST TEST LOGIC TEST 15 REQUIRE 0 e

18.

Reactor Trip' Systes Interlocks (Continued) de Power Range Neutron flux, P-10 N.A.

R(4)

WR N.A.

N.A.

1, 2 e4 Turbine Impulse Chamber Pressure, P-13 N.A.

R

.N(BT8 H.A.

N.A.

I g

19.

Reactor Trip Breaker N.A.

N.A.

H (7, 11)

N.A.

1, 2, 3*, 48, 5*

20.

Automatic Trip and p

Interlock Logic H.A.

N.A.

M(7) 1, 2, 3", 4*, 5" g-6

?

. - ~...

- ?

l l

TABLE 4.3-1 (Continued)

TABLE NOTATIONS "Only if the Reactor Trip System breakers happen to be closed and the Con-trol Rod Drive System is capable of rod withdrawal.

WBglow P-6 (Intermediate Range Neutron Flux interlock) Setpoint.

M#Below P-10 (Low Setpoint Power Range Neutron Flux interlock) Setpoint.

(1) Ifnotperformedinprevioushdays.

(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER. Adjust excore channel gains consistent with calorimetric power if aosolute difference is greater than 2%. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15% of RATED THERMAL POWER.

Recalibrate if the absolute difference is greater than or equal to 3%.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5) Detector plateau curves shall be obtained, evaluated and compared to manufacturer's data. For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE.2 or 1.

(6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER. The

(

- MODE 2.or 1.

provisions of Specification 4.0.4 are not applicable for entry into N,

~

1 J.

l

(' ) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(8) 2 " n=ar areater than or equal to the ' interlock Setpoint the r=q"b d ---

e ANALOG CHANNEL OPERAUunm. TEST -?-' 'cc--i J verifying that the inter-hcIcf8 1 ~- ' S in a required state by observing the pemissive annunci W.

i r. ':1 e x %.,I-e. tsurveillance in MODES 3*,4*, and 5" shall also include verification (9) that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

Quarkrly Memy surveillance shall include verification of the Baron Dilution Alarm Setpoint "of less than or equa.1 to an increase of twice the count rate within a 10-minute period.

(10) Setpoint verification is not required.

(11) At least once per 18 months and following maintenance or adjustment of the Reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verification of the Undervoltage and Shunt trips.

(12) At least once per 18 months during shutdown, verify that on a simulated Baron Dilution Doubling test signal the normal CVCS discharge val' will close and the centrifugal charging pumps suction valves from the J.

will open within 30 seconds.

(13) CHANNEL CALIBRATION shall include the RTD bypass loops flow rate.

4 CALL 4WAY - UNIT 1 1/a a p-1

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f&CEch cluuml s ab le<O every N day on a..SWCGEAEb TEST BRSIS l) QS) %

.wveillanea fee

$ted Le N*'*

c}>a.nnels in % hic 4.3b<aq ad/u t'] ODES gecan non l

l Q

i. p.

N4. ; INSIRUMENTAIICN SASES 3/4.3.1 and 3/4.-3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION The OPERABILITY of the Reactor Trip System and the Engineered Safety Features Actuation System inst' umentation and interlocks ensures that: (1) the r

associated action and/or Reactor trip will be initiated when the parameter monitored by each channel or comoination thereof reaches its setpoint, (2) the specified coincidence logic is maintained, (3) sufficient redundancy is main-tained to permit a channel to be out of service for testing or maintenance, and (4) sufficient system functional capability is available from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation.of accident and transient conditions.

The integrated operation of each of these systems is consistent with 'the '

assumptions used in the safety analyses.

The Surveillance Requirements specified for these systems ensure that the overall system functional capability is main-tained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this lj. '

capability. (Sas JCvsaxfi)

' ~

5 7

The Engineered Safety Features Actuation System Instrumentation Trip Setpoints specified in Table 3.3-4 are the nominal values at which the s,

bistables are set for each functional unit. A Setpoint is considered to be adjusted consistent with the nominal value when,the "as measured" Setpoint is withi,n the band allowed for calibration accuracy.

To accommodate the instrument drift assumed to, occur between operational tests and the accuracy to which setpoints can be measured and calibrated, Allowable Vaiues for the Setpoints have been specified in Table 3.3-4.

Operation with Setpoints less conservative than the Trip Setpoint but within 4

the Allowable Value is acceptable since an allowance has been made in the safety analysis to accommodate this error. An optional provision has been included for determining the OPERASILITY of a channel.when its Trip Setpoint is found to exceed the Allowable Value. The methodology of this option utilizes the "as measured" deviation from the specified caf fbration point fur rack and sensor components in conjunction with a statistical combination of the other uncertainties of the instrumentation to measure the process variable l

and the uncertainties in calibrating the instrumentation.

In Equation 3.3-1, Z

R + S < TA, the interactive ef fects of the errors in the rack and the sensor, and the "as measured" values of the errors are considered.

Z, as specified in Table 3.3-4, in percent span, is the statistical summation of errors assumed in the analysis excluding those associated with the sensor and rack drif t and the accuracy of their measurement. TA or Total Allowance is in percent span, between the Trip Setcoint and the value used the difference.

in the analysis for the actuation. R or Rack Error is the *as measured" in percent span, for the affected channel from the specified Trip deviation, s...

CALLAWAY - UNIT 1 83/43-1

INSERT 1 Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271, " Evaluation of Surveillance Frequencies and Out of Service cines for the Reactor Protection Instrumentation System," supplements to that report, and the NRC's Safety Evaluation dated February 21, 1985.

Surveillance intervals and out of service times were determined based on maintaining an appro-priate level of reliability of the Reactor Protection Systcm and Engineered Safety Features instrumentation.

s 4

3 e

h y

f s -

INSTRUMENTATICN 9ASES REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continuec)

Setooint. 5 or Sensor Error is either the "as measured" deviation of the sensor frem its calibration point or the value specified in Table 3.3-4, in percent span, frem the analysis assumptions.

The methodology to derive the Trip Setpoints is based upon combining all of the uncertainties in the channels.

Inherent to the determination of the Trip Setpoints are the magnitudes of these channel uncertainties. Sensor and rack instrumentation utilized in these channels are expected to be capable of operating within the allowances of these uncertainty magnitudes. Rack drift in excess of the Allowable Value exhibits the behavior that the rack has not 2

met its allowance. Being that there.fs a small statisitical chance that this will happen, an infrequent excessive drift is expected. Rack or sensor drift, in excess of the allowance that is more than occasional, may be indicative of more ser'ious problems and should ' warrant further investigation.

The measurement of response time at the specified frequencies provides assurance that the Reactor Trip and the Engineered Safety Features actuation associated with each -hannel is completed within the time limit assumed.in the

. safety analyses. No credit was taken in the analyses for those channels with response times indicated as not appifcable. Response time ~may.be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as ' defined.

g

!(t'7N

)'

." ~

Sensor response time verification may be. demonstrated by either:

(1) in place, onsite, or offsite test measurements or (2) utilizing replacement sensors with certified response times.

The Engineered Safety Features Actuation System senses selected plant parameters and determines whether or not predetermined limits are being exceeded.

If they are, the signals are combined into logic matrices sensitive to combina-tions indicative of various accidents, events, and transients. Once the.

required logic combination is completed, the system sends actuation signals to those Engineered Safety Features components whose aggregate function best serves the requirements of the condition. As an example, the following actions may be initiated by the Engineered Safety Features Actuation System to mitigate i

t.he consequences nf a steam line break or loss-of-coolant accident:

(1) Safety injection pumps start and automatic valves position, (2) Reactor trips, (3) Feedwater System isolates, (4) the emergency diesel gene' ators start, r

(S) containment spray pumps start and automatic valves position, (6) contain-ment isolates, (7) steam lines isolate, (8) Turbine trips, (9) auxiliary f eedwater pumps start and automatic valves position, (10) containment cooling f ans start and automatic valves position, (11) essential service water pumps start and :atomatic valves position, and (12) isolate normal control room ventilatian and start Emergency Ventilation System.

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CAllAWAY - UNIT 1 8 3/4 3-2

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Encineered Safetv Features Actuation Svstem Interlocks The Engineered Safety Features Actuation System interlocks perform the following functions:

P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater valves on T,yg below setpoint, prevents the opening of the main feedwater valves which were closed. by a Safety Injection or High Steam Generator Water Level signal, allows Safety Injection block so that components can be reset or tripped.

Reactor not tripped prevents manual block of Safety Injection.

P-11 1 On increasing pressure P-11 automatically reinstates Safety Injection actuation on low pressurizer pressura and low steam line pressure and automatically blocks steam line isolation on negative steam line pressure rate. On decreasing pressure, P-11 allows'the manual block of Safety Injection on low pressurizer pressure and low steam line pressure and allows steam line isolation on negative steam line pressure rate to become active upon manual block of low steam line pressure SI.

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i 3/4.3.3 MONITORING INSTRUMEh/ATION 3

3/4.3.3.1 RACIATION MONITORING FOR P'LANT OPERATIONS The OPERABILITY of the radiation _ monitoring instrumentation for plant operations ensures that: (1) the associated action will be initiated when the radiation level monitored by eacn channel or combination thereof reaches its setpoint, (2) the specified coincidence logic is maintained, and (3)~ sufff-cient redundancy'is maintained to permit a channel to be out of service for testing or maintenance. The radiation monitors for plant operations sonsta radiation levels in selected plant systems and locations and determines whether or not predetermined limits are being exceeded. If they are, the signals are combined into logic matrices sensitive to combinations indicative of various accidents and abnormal conditions. Once the required logic combination is completed, the system sends actuation signals to initiate alarms or automatic isolation action and acutation of Emergency Exhaust or Control Room Emergency Ventilation Systems.

3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERASILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the core. The OPERASILITY of this system is demonstrated by irradiating l

each detector used and determining.the acceptability of its voltage curve.

For the purpose of ressuring F (Z) or F" a full incore flux map is used.

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Quarter-core flux maps. a:s defined in WCAP-8648, June 1976, may be used in recalibration of the E.xcore Neutron Flux Oetection System, and full incare

>9 flux maps or symmetric incere thimbles may be used for monitoring the QUA0 RANT l

POWER TIL1 RATIO when one Power Range Neutron Flux Channel is inoperable.

CALLAWAY - UNIT 1 8 3/4 3-3

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