Text

Proposed Tech Spec Tables 3.3-1,4.3-1,3.3-1 & 4.3-2 Re ESFAS Optimization
	ML20070P707
Person / Time
Site:	Callaway
Issue date:	03/19/1991
From:	; UNION ELECTRIC CO.
To:	;
Shared Package
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References
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ULNRC-2 3 81 ATTACHMENT 3 DRAFT TECHNICAL SPECIFICATION MARK-UPS FOR ESFAS OPTIMIZATION Table 3.3-1 pp. 3/4 3-3(a) 3/4 3-4 3/4 3-5

-3/4 3-6 3/4 3-6(a)

INSERT A

' Table 4,3-1 pp. 3/4 3-9 3/4 3-10 3/4 3-12(a)

. Table 3.3-3 pp. 3/4 3-14 3/4 3-16 3/4 3 3/4 3-18.

3/4 3-18(a) 3/4-3 INSERT B 3/4.3-21 3/4 3-21(a)

INSERTS C, D,

E Table 4.3-2 pp. 3/4 3-33 3/4_.3-34 3/4 3-35 3/4 3-36 3/4_3-36(a)_

3/4-3-37 ale 3.3-6 pp. 3/4 3-39 3/4 3-40 BASES 3/4.3.1 and 3/4.3.2 p.- B 3/4 3-1 INSERTS F, G

-9103280034 910319 PDR ADOCK 05000483 P

PDR Hv

i s

w TABLE 3.3-1 (Continued) 2 REACTOR TRIP SYSTEM INSTRUMENTATION 5'

i i

f; T11NIMt#1 TOTAL NG.

CilANTIELS CllANNELS APPLICABLE i

rufiCT10tlAL UNIT OF CllAN!!ELS TO TRIP OPERABLE MODES _

ACTION h

14.

Undervoltage-Reactor Coolant 4-2/ bus 2-1/ bus 3

1 6f M Pumps A

i 15.

Underfrequency-Reactor Coolant 4-2/ bus 2-1/ bus 3

^

1 6f Pumps 16.

Turbine Trip a.

Low Fluid Oil Pressure 3

2 2

1 6f

~t' b.

Turbine Stop Valve Closure 4

4 1

1 lif t'

17.

Safety Injection Input 2

1 2

1, 2 31 from ESF A

9 ?I

?*

11 n n CL a+

O

w TABLE 3.3-1 (Continued) r>#

REACTOR TRIP SYSTEM INSTRUMENTATION C6 HINIMUM TOTAL NO.

EllANNELS CilANNELS APPLICABLE FUNCTIONAL UNIT Of CilANNELS TO TRIP OPERABLE HODES ACil0N E

Q 18.

Reactor Trip System Interlocks

~

a.

Intermediate Range Neutron flux, P-6 2

1 2

2N 8

b.

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

2 3

1 3

or P-13 Input 2

1 2

1 8

R c.

Power Range Neutron Flux, P-8 4

2 3

1 8

s'

i' a

d.

Power Range Neutron Flux, P-9 4

2 3

1 8

e.

Power Range Heutron Flux, P-10 4

2 3

1, 2 8

f.

Turbine Impulse Chandier Pressure, P-13 2

1 2

1 8

19.

Reactor 1 rip Breakers 2

1 2

I 2 9,12 l

g 2

1 2

3, 4 *, 5*

10 g

h 20; Automat'ic Trip and Interlock togic 2

1 2

I 2 31 g

g 2

1 2

3, 4 *, 5*

10 A O

l 4

i TABLE 3.3 1 (Continued)

TABLE NOTATIONS

0nly if the Reactor Trio System breakers happen to be in the closea position and the Control Rod Drive System is capable of rod withcrawal.

- The boron dilution flux doubling signals may be blocked during reactor startup in accorcance with approved procecures.

The provisions of Specification 3.0.4 are not applicable.

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

NBelow the P 10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

The applicable M00ES - '"'"" r-Yr these channels notec (1) in Table 3.3-3 are more restrictive and, therefore, applicable.

ACTICN STATEMENTS ACTION 1 -'With the number of OPERABLE channels one less than the Minimum Channels OPERABLE recuirement, restore the inoperable enannel to OPERADLE status within 48 hovrs or be in HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTIM 2 - With the number of OPERABLE channels one less than the Total Numcar 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 , l

b.

The Minimum Channels OPERABLE recuirement is met; however, the inoperable channel-may be bypaused 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, 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 ecual to 85% of RATED THERMAL POWER within a hours; or, the QUADRANT POWER TILT RAT'O 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 With the number of channels OPERABLE one less than the Minimum Channels'CPERABLE requirement and with the' THERMAL F0WER level 4 a.

._Below the P-6 (Intermediate Range Neutron Flux interlock)

Setooint, restore the inocersole channel to OPERABLE status orior_ to increasing THERMAL POWER sbove the P-6 Setooint; or b.

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

Setooint but oelow 10?', of RATED THERMAL POWER, restore the inoceraole channel to OPERABLE status crior to increasing THERMAL' POWER aoove 10% of RATED THERMAL 30WER.

CALLAWAY - UNIT 1 3/4 3-b Amencment No. 17

_. _ - - - ~.

O TABLE 3.3 1 (C:ntieve n af 0N !? ?Ew!N?$ (~:etieueel ACT:;N 4 +.iith tee mueter of 0FEVELE :tannels tre 'ess then t e viemm Channels CPEUBLE recuirement sus;ene all o;erations inv: M ng ootitive reactivity enanges.

ACTION 5 a.

With the numter of OPEMBLE.nannels one lets tnan tre Minimum Channels OPEUBLE recuireme.1t, restore tne inoperable channel to OPEMBLE status d hin 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or coen the Reactor trip treakers, suspend all 0;eratiens involving positive reactivity changes anc verify Valves BG V17B and BG V601 are closed and secured in positien witnin the next hour.

b.

With no ;hannels OPERABLE, open the Reactor Trio Breakers, susLend all operations involving positive reactivity changes and verify compliance with the $HUTDOWN KARGIN 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 ever.v 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereaf ter, and verify valves BG V178 and BG V601 are efosed 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 Numter of Channels, $TARTUF and/or POWER OPERATION may proceec provided the following concitions are satisfiedt a.

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

The Minimum Chant 41s OPERABLE requirement is met; he' wever, 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 for surveillance testing of other channels per Specification 4.3.1.1.

ACTION 7 With an inoperable delay timer in the ' lp Time Delay circuitry, STARTUP and/or POWER OPERATION may p>.<eed provided that the Vessel Delta T (Power 1, Power-2) channels in the affected protectn sets are placed in the tripoed condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 8 - With less than the Minimum Number of Channels CPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of thy associatec permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification No w h e 9,y $ m krer V

ACTION 9 With the number of CPERABLE W

': Sne less than the Minimum Channels CPERABLE recuirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one :t: n ' 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 tesdng per pecification 4.3.1.1, provided the etergir:!isOPWBLE.

j,,,j,,

A I

domkoe a

brea ker CALLAWAY UNIT 1 3/4 3 6 Amendment No. 17, 43 j

_- -.- -.~.---

l:

l i

)

TABLE 3.3-1 (Continued) i ACT!0N STATEMENTS (Continued) i ACTION 10 - With the number of OPERABLE channels one less than the Minimu I

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.

3-ACTION 11 - With the number of OPERABLE channels less than the Total Num of Channels, operation may continue provided the inoperable 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 12 - With one of the diverse trip features (Undervoltage or Shunt Trip Attachment) inop'erab1'e. rest' ore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the affected breaker 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 perfonning maintenance to restore the breaker to OPERABLE status.

ACTION 13 - With the number of OPERABLE channels less than the Total Num of Channels STARTUP and/or POWER OPERATION may proceed provided l

that the Containment Pressure Environmental Allowance Modifier channels in 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 .

,4 9

lynyg : A c rzoN trATCmCNYS /+ THAbHGH 30 AM LocArch on oraa rue.c.r.)

.rNSERT* A I

]

CALLAWAYL. UNIT 1 3/436(a)

Amendment' No.19, 43 1

... a _._, _ _ _,... _,. _... _ _ _ _ _

INSERT A With the number of OPERABLE channelo one lene ACTION 31 than the Minimu n Channeln OPERABLE require-ment, be in at least 11oT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; however, one channel may be bypassed, with the associated reactor trip breaker bypanned, for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for logic nurvei13ancc testing per specification 4.3.1.1, provided the other channni in OPERABLE.

TA8tE 4.3-1 h

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

TRIP

' ANALOG ACTUATING M00E5 FOR CHANNEL DEVICE WHICH E

CHANNEL CHAISIEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANC[

Z FUNCTIONAL UNIT CHECK CALIBRATION TEST TESI t0GIC TEST 15 REQUIRfD 1.

Manuel Reactor Trly M.A.

M.A.

, M.A.

R(16)

M.A.

1, 2, 3*, 4*, S s-2.

Power Range, Neutron Flux a.

High Setpoint 5

D(2,4),

Q(1";"-

N.A.

M.A.

1, 2 M(3,4),

A Q(4, 6),

R(4, 5) b.

Low Setpoint 5

R(4) 5/U(1)

M.A.

1888, 2 R

3..

Power Range, Neutron Flux, M.A.

R(4)

Q( !")"-

M.A.

1, 2 A

High Positive Rate T

4.

Deleted 5.

Intermediate Range, S

R(4. 5)

SN(1)

M.A.

Iffs, 2 Neutron Flux g

S 6.

Source Range, Neutron Fluu 5

R(4,5,12) 5/U(1) Q(9)4+) 8 N A.

M.A.

2ff, 3, 4, 5 a

b 5

7.

Overtemperature ai 5

R Q( " } "

M.A.

1, 2 l

8.

Overpower AT 5

R Q(!") "

M.A.

1, 2

^

M.A.

1

~

g*-

9.

Pressurtzer Pressure-tow 5

R 10.

Pressurizer Pressure-High 5

R Q(!")"-

M.A.

1, 2

^

~

11.

Pressurizer Water level-Migh 5

R Q(1";"-

M.A.

M A.

1 A

12.

Reactor Coolant F10w-Low 5

R Q(I') E M. A.

M.A.

I A

TA9LE 4.3-1 (Continued)

{

g

_ REACTOR TRIP SYSTEM INSTRUpKMTATION SURVEILLANCE REQUIREMENTS E

j g

1 RIP 3

ANALOG ACTUATING MODES CHANNEL DEYICE FOR WHICil c

CHANNEL CliANNEL OPERAT10NAL OPERAT10NAL ACTUATION SURVLIlLANCE z

FUNCTIONAL UNIT CIECK CALIBRATION TEST TEST LOGIC TEST IS REQtilRID

)

13. Steam Generator Water i

Level Low-Low a.

Steam Generator Water 5

R Q M S)

N.A.

I, 2 i

Level Low-Low (Adverse A

[

Containment Environment) b.

Steam Generator Water S

R Q (44t15)

N.A.

1, 2 u)

Level Low-Low (Normal A

Containment Environment) w c.

Vessel AT (Power-1, 5

R Q ( M S)

N.A.

1, 2 Power-2)

A d.

Containment Pressure-S R

Q ( 4 5)

N.A.

1, 2 Environmental Allowance A

l Modifier i

k

14. Undervoltage - Reactor N.A.

R N.A.

Q ( ! ', N "_

N.A.

1 Coolant Pumps A

4

.R g

15. Underfrequency - Reactor N.A.

R M.A.

Q () " -

M.A.

I Coolant Pumps A

x

?

16. Turbine Trip mw a.

Low Fluid Oil Pressure M.A.

R M.A.

S/U (1,10)

N.A.

I b.

Turbine Stop Valve N.A.

R N.A.

S/U (1,10)

N.A.

I Closure I

a

TABL E 4.31 (Continued)

TABLE NOTAT!ONS (10)

Setpoint verification is not required.

(11)

Following maintenan:e nr adjust ient of the React:r trip creakers, the T.!P ACTUAi!NS DEv!CE OPEDATIONAL TEsi sna11 include in:e:encent verifi.

ation of tne Uncervoltage and Snunt trips.

(IE)

At least once per 15 months during shutdown, verify that on a simulated Boron Dilution Doubling test signal tne normal CVCS discharge valves veill close anc the centrifugal charging pumps suctic'i valves from the RaST will open witnin 30 secones.

(13)

Deleted n:! ' t-te;t+4-+t-4eest-eve *y-9E-6eys on e ET AGGE*1:0 TEST A (14) - E::" :ncee! :d g C A;!; c be /efe (15)

Tne surveillance 4r:;.:m:f ad/ r %0 DES specified for these channels in Table 4.3 2 are more restrictive and, therefore, applicable.

(16)

The TRIP ACTUATING DEV!CE OPERATIONAL TEST shall independently verify the OPERABILITY of the Undervoltage and Shunt Trip cir:uits for the Manual Reactor Trip function.

The test shall also verify the OPERABILITY of the Bypast Breaker trip circuit.

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

(18)

Automatic Undervoltage Trip.

i l-CALLAWAY - UN!i 1 3/4 3-12a Amendment No. M. M /M.

D,'

l f.,

. 1 TA8tE Y 3-3 Et4GitdERED sAFEin FEATURE 5 ACTUAIION SYSTEH It:STRtetENIATiOh O;-

>(

HINIMUM E

10iAL 740.

t StAMELS CHANNELS APPLICABLE fut4CTIUf4AL UNIT OF CW.NiiELS T.

T'd IP OPERA 8tE N00E5 ACIION 1.

Saf ety Injection (Reactor

~*

Irip, Phase "A" Isolation, Feedsater Isolation, Compo-nent Cooling Water, Turbine Trip. Auxi liary f eedwater-Moto. -

Driven Pump. Emergency Diesel Generator Operation, Contain-ment Cooling, and Essential Service Water Operation) a.

Manual Initiation 2

1 2

1, 2, 3, 4 18 b.

Automatic Actuation 2

1 2

1, 2, 3, 4 14

^

Logic and Actuation T

Relays (55PS)

Z c.

Cont a iteent 3

2 2

1, 2, 3

-W"- 33 Pressure-High-1 A

l d.

Pressurizer 4

2 3

1, 2, 3#

W 33 Pressure - Low

^

e.

Steam Line Pressure-3/ steam line 2/ steam line 2/ steam line I, 2, 3#

-MS-33 tow any steam A

line 2.

Cont a i ra >esit Spray a.

Manual Initiation 2 pair I pair 2 pair

1. 2, 3, 4 18 M

operated M

simultaneously

~

Cn b.

Aotonatic Actuation 2

1 2

1, 2, 3, 4 14 y

logic and Actt;ation Relays (55PS) c.

Cantairvoeot Pressure-4 2

3 1, 2, 3 16 til gh-3 9

e

y TABtE 3.3-3 (Continued)

ENGINEFFID SATElf FEATURES ACTUATION SYSTEM INSTRUMENTATION n3 HININUM p

TOTAL NO.

CilANNELS CHANNELS APPLICABLE g

FUNC T 10:4At ulill 0F CilANNELS TO IRIP OPERABLE H00E5 ACTIO:1 E

3.

Containment Isolation (continued)

.A 3

2:

Automatic Actuation 2

1 2

1, 2. 3. 4 11 a

Logic and Actuation

~

Relays (55PS) 3)

Automatic Actuation Logic and Actuation Relays (BOP E5FAS) 2 1

2 1,2.3,4 11 4)

Phase "A" Isolation See Item 3.a. for all Phase "A" Isolation initiating iunctions and requirements.

4.

Steam Line Isulationi R

6 a.

Manual Initiation Yg

1) Individual 1/s'eam line 1/ steam line 1/ operating 1, 2, 3 23 steam line

2) System 2

1 2

1,2,3 22 b.

Automatic Actuation 2

1 2

1. 2, 3

-M togic and Actuation Relays (55PS)

A c.

Contairment Pressure-3 2

2 1, 2, 3 M 33

~

iligh-2 A

d.

Steam Line 3/ steam line 2/ steam line 2/ steam line

1. 2. 3#

M F3 Pressese-tow any steae A

2 1ine "3

e.

Steam iine Pressure-3/ steam line 2/ steam line 2/ steam line 3##

M 73 CD e

flegative Rate-fligh any steam A

y line g

6 Ie8 i

1 1

m TABLE 3.3-1 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION o?

E MINIMUM

. 5 TOTAL NO.

C1!ANNELS OIANNELS APPLICABLE FUNCTIONAL UNIT OF CIIANNELS TO TRIP OPERABLE MODES ACTIOf(

E 5.

Feedwater Isolation & Turbine Trip

~

-4 a.

Automatic Actuation Logic 2

1 2

1, 2 21 s

and Actuation Relay '55PS) b.

Steam Generator Water 4/stm. gen.

2/stm. gen.

3/stm. gen.

1. 2 49^-33 Level liigh-fligh in any oper-in each oper-A ating stm.

ating stm.

gen.

5 c.

Safety Injection See Item 1. above for all Safety injection initiating functions and requirements.

w 6.

Auxiliary Feedwater I

a.

Manual Initiation 3(1/ pump) 1/ pump 1/purrp 1, 2, 3 24 b.

Automatic Actuation Logic 2

1 2

1. 2. 3

&3f and Actuation Relays (55PS)

A E

c.

Automatic Actuation Logic 2

1 2

1,2,3 21 and Actuation Relays (BOP 2

ESFAS) n d.

Steam Generator Water Level Low-Low u

1) Start Motor-Driven Pumps Ws N a) Steam Generator Water 4/stm. gen.

2/stm. gen.

3/stm. gen.

1,2,3

--".27{u}

Level Low-Low in any oper-in each A

(Adverse Containment ating sim.

operating Environment) gen.

stm. gen.

u TABLE 3.3-3 (Continued)

ENGINEERED $4FETY FLATURES ACTUATION SYSTEM INSTRUMENTATION oP MINIMUM E

ji T 9 T A', N O.-

OIANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT

'0F CHANNELS TO 1 AIP_

OPERABLE MODES ACTION E

6.

Auxiliary feedwater (Continued)

Q

- d.

Steam Generator Water Level Low-tow (Continued) 1)- Start Motor-Driven Purps (Continued) 35,34e b) Steam Generator Water 4/sta. gen.

2/sta. gen.

3/sta. gen.

1. 2, 3 27(d. 27(t)"

Level Low-tow in any oper-in each A

(Normal Containment sting stm.

' opera ting Environment) gen.

stm. gen.

c) Vessel AT (Power-1, 4

2 3

1, 2. 3 27 (d' Sf A

Power-2) d) Containment Pressure-4 2

3 1, 2, 3

-27 (d ^ 57" A

Environmental Allowance Modifier

2) Start Turbine-Driven y

Pump 33*;35 a)' Steam Generater Water 4/stm. gen.

2/sta. gen.

3/sta. gen.

1, 2, 3 20^. 27(e) g Level Low-Low in any oper-in each A

(Adverse Containment ating sim.

operating Environment) gen.

stm. gen.

35, 34 g

b) Steam Generator Water 4/sta. gen.

2/sta. gen.

3/stm. gen.

I,2,3 2Md. 27(M' i.evel Low-Low in any oper-in each A

(Normal Containment-ating stm.

operating w

Enyironment) gen.

s tm. gen.

c) Vessel.ai (Power-1, 4

2 3

1,2,3 07(#M A

Power-2)

.= ___ -....

~

TABLE 3.3-3 (Continued)

ENGifiEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION o?

E MINIMUM s

TOTAL NO.

CIIANNELS CilANNELS APPLICABLE

[

FUNCTIONAL UNIT OF CPIANNELS TO TRIP OPERABLE MODES ACTION E

6.

Auxiliary Feedwater (Continued)

U d.

Steam Generator Water Level Low-Low (Continued)

2) Start Turbine-Driven Pump (Continued) 37, d) Containment Pressure-4 2

3 1,2,3 L'( c)'

Environmental Allowance A

Modifier e.

Safety Injection See Item 1 above for all Safety Injection initiating functions Start Motor-Driven Pumps and requirements.

saL f.

Loss-of-Of fsite Power-l Start Turbine-9 riven Pump 2

1 2

1,2,3 22 m

g.

Trip of all Fain Feedwater.

4-(2/ pump)** 2-(1/ pump in 3

1, 2###

19 A Pumps -Start Motor-Driven same separation)

Pumps E

h.

Auxiliary feedwater Pump 3

2 2

1,2,3 1S*

i i

Suction Pressure-Low E.

(Transfer to ESW) r 5

7.

Automatic Switchover to

{

Contalrunent Sump m

a.

Automatic Actuation Logic 2

?

2 1,2,3,4 I4

~

0 and Actuation Relays (SSPS) b.

RWST Level - Low-Low 4

2 3

1,2,3,4

-3+- 33 A

Coincident With Safety See Item 1 above for Safety Inj.ection initiating functions and Injection requirements.

TABLE 3.3-3 (Continued)

)

IABLE NOTATION e

(Trip function r.ay be blocked in this MODE below the P-11 (Pressuri:er Pressure Interlock) Setpoint.

pirip function automatically blocked above P-ll and may be blocked below I

A P-11 when Safety IrQection on low steam line pressure is not blocked.

f fTrip function may be blocked just before shutdown of the last operating main feedwater pump and restored just after the first main feedwater pump is put into service (following its startup trip test).

'The provisions of' Specification 3.0.4 are not applicable.

"One in Separation Group 1 and one in Separation Group 4.

M *.T N S C /tT* 8 ACTION STATEMENTS ACTION 14 - With the number of OPERABLE channels one les chan the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within

/2 hours and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; A however, one channel may be bypassed for up to hours for surveil-lance testing per Specification 4.3.2.1, provid the other channel is OPERABLE.

f ACTION 15, With the number of OPEMBLE channels one less than the Total Number g

f cf Channels, operation may proceed until perfomance of the next required ANALOG CHANNEL OPEMTIORAL. TEST provided the inoperable channel is placed in the tripped condition within 1. hour.

PTION 16 - With the nu:.ber of OPERABLE channels one less.than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypass condition and the Minimum Channels OPERABLE requirement is met.

One additional channel may be bypassed for up to-hhours for su 1111ance testing per Specification 4.3.2.1.

+

ACTION 17 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the contairunent purge supply and exhaust valves are maintained closed.

ACTION 18 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirwnent, 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 at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 19 - With the neber 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 I hour, and p

CALLAWAY - UNIT 1 3/4 3-20 Amendment No. 26

I INSERT B The de-energization of one train of BOP-ESFAS actuation logic and actuation relays renders two of the four channeln inoperable. Action Statement 21 applies to both Functionn)

Units 6.c and 6.g in this cane.

-,. ~,

FABLE 3.3-3 (Continued)

)

ACT!0N STATEMENTS (Continued) i 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.

ACTION 20 - With less than the Minimum 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.

l ACTION 21 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT $HUTDOWN within the following 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 4.3.2.1 provided the other channel is OPERABLE.

ACTION 22 - With the number of OPERABLE channels one less than the Total Number of Channels, 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 at least HOT STANDBY within V/,a nex-/

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following A

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

ACTION 23.- With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE g

4 status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.

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

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

ACTION 26 - 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 initiate and maintain opera-tion of the Control Room Emergency Ventilation System.

AC110N 27 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within4r hours; however, one channel may be bypassed for up to f + hours or surveillance testing per Specification 4.3.2.1 provide the other channel is OPERABLE.

L.2

/

(N6TE :

A CMN nnrcAcMrs.:?r THRoyGH 3/ ME ocwrEb m vrnex n9&cs.)

CALLAWAY UNIT 1 3/4 3-21

1 TABLE 3.3-3 (Continued).

ACTION STATEMENTS (Continued) y1NZE&TJ C, b, E ACTION s44+)

With an incperable delay timer in the Trip Time Delay g

yg circuitry, STARTUP and/or POWER OPERATION may proceed provided that the Vessel t,T (P r-1, Power-2) channels in the affected protection s t placad in the tripped condition within 6 h ACTION G Mbt - With the number of OPERABLE channels less than the y

Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided that the Containment Pressure.

Environmental Allowance Modifier channels in 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 .

ACTION i!4e-)- With the number of OPERABLE channels less than the Total 3

37 Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l

]

CALLAWAY - UNIT 1 3/4 3-21(a)

Acendment No. 43

I 11#1RT C i

I With the number of OPERABLE channelt ono less ACTION 32 than the Total Number of Chennela, except for testing, STARTUP and/or POWER OPERATION may proceed for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided the following conditions are natinfied:

a.

The inoperable channel in pinced in the tripped condition within 6 hourn, and

b. The Minimum Channeln OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hourts for surveillance testing of other channeln per Specification 4.3.2.1.

Rectore the inoperable channel to OPERABLE status within 72 hourn or be in at least !!OT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SIIUTDOWN within the following 30 hourn.

With the number of OPERABLE channels one less than the Total Number of Channels due to testing of a channel, that channel may be tripped for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillan'-

testing por Specification 4.3.2.1.

m._

J 4

INSERT D ACTION 33 With the number of OPERABIE channels one less than the Total Nutrbor of Jhannels, STARTUP and/or POWER OPERA'!!Ot* m y proceed provided the followins 7onditionn are sttisfied;

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

b. The Minimum Channels OPERABLC requirement is mets 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 for sur-veillance testing of other channels por Specifica tion 4.3. 2.1.

i 1'

I l

. r

-W TW ww't-,-et-9fyurirg-',www-rt' e

-+vw mie +wr - w,e re ev-y

g, e erwu-1w w e-a v'-ww-+w h W w aeg-r k

ey--

,M-w1'-

4 WWT tt+ " P**'*'WD N#'e-#W.-t4AW-tPN*1r*rWW Et--MF

"?W 't*F"OT"*$'

j

i-IllSEDT E With the number of OPEPRE chatunels one lens ACT1014 34 than the tiinimum Channo 2 s <>}'ERADI.E requiro-ment, be in at least !!OT STA!IDBY wi t.hin 12 hourn and in at least 110T SHUTDOW11 within the following 6 houro; however, one channel may be bypastad for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for curve 111ance tenting per Specification 4.3.2.1 provided the other channel 3s OPERABLE.

i I

l' TAS(E 4.3-2 i

O IIIGINEftf8 SAFEif FEAluRES ACluATIGIf SYSIfM INSTRUNIslAll0N

~E Sutivta$tANCE REQUIRflENIS g

IRIP i

M00f5 AcidAlllIG

" AIIALOG CNANNEL DEVICE MA51[R STAVE IGR WillCN c

'N CHANIIIL CHAleifL ~

OPfRAll00lAt OP(RATICIIAL AC11MII006.

RELAY RELAY SURViIl1A01CE

-CHECK CALIBRAllell IEST TEST 10Glc IESI IISI Its) 15 atqulMD

'I'UNCIIONAL UNil 1

$ately injection (4teactor Irip.

Phase 'A Isolation, l'eenbeater Isolation, lurbine Irly, Component i

Cooling Water Auxillary feetheater-Hator-Driven fump, foergency Diesel Coptalsmeent Generatou.GperationlalService Cooling,'and Essent i

Water D eration) 1, 2, 3, 4 l P

a.

Manual Initiation N.A.

N.A.

M NJ N.A.

M.A.

N b.

Automatic Actuation M.A.

N.A.

'N.A.

N.A.

N(1)

M(1)

Q(3) 1, 2, 3, 4 O

logic amt Actuatlon

o Relays (SSP 5) c.

Contallment Pressure-5 R

AQ N.A.

M.A.

N.A.

I, 2, 3 x

A Iligle-1 d.

Psessurizer Pressure-5 R

AG N.A.

N.A.

M.A.

1, 2, 3 A

low e.

Steam Line Pressure-5 A

4-Q N.A.

N.A.

h.A.

N.A.

' 1, 2, 3 p

A low

[

1, 2, 3, 4 l 2.

Contaisnept 5 prey 4

Manual Initiation N.A.

N.A.

M N.A.

N.A.

b.

Automatic Actisation N.A.

N.A.

N(1)

Q(3) 3, 2, 3, 4

. Iogic and Attuation Relays (5S?$)

j f

c.

' Containment Pressure-5 R

AS II. A.

N.A.

M.A.

N.A.

1, 2, 3 2,-

i A

g liigli-3 i

5-

.s N

IABtf 4.M2 (Continesed) i 9

ENGitIEERED SAfflY ffAIURf 5 ACIMATICII SYSIfM INSIRIF1Aj.Ji[

e-L SuRVtittanCE RtquiRfwNis g

i 1 RIP ANALOG

' ACIMATIllG i.:N5 CHANNEL 9tVICE Mailer 51AVC Ihittalitet U

CHAsedEL ColAIRl[4 OPENAll0IIAL '~ OPtRAIIGIt4L AC10AIlON Illt 4Y WE1AY SultVEILi AIICE z

ertlin:linHAt UNil

.CHfCK CAtlbtAII006. IESI 1ESI 80GIC it5l. 115!

IESI 15 atquists

.- 3.

Coot 41mment isolatlos Phase "A" isolation 4.

l i) Hanual lnltlation M.A.

N.A.

R N.A.

M.A.

N. 4.

I, 2, 3, 4

2) Automatic Actuation N.A

'N.A.

M.A.

N.A.

M(1)

Q(3) 1, 2, 3, 4 169 C asut Actuations I

Nelays (55PS)

See Ites 1. above fotr all Safety Injection Surveillance Requirements.

3) Safety Injectioni

!N b.

Phase "B" Isolation 1, 2, 3, 4 l

'M

1) Manual Initiation N.A.

M.A.

N. A.

Si N.A.

M.A.

N.A.

2) Automatic Actuation N.A.

N.A.

M(1)

Q I, 2, 3, 4 iouic asid A*.tualion Relays (55PS)'

N.A.

M.A.

N.A.

1, 2, 3

3) Contaiemment 5

R gQ-Pressure-liigle-3 A

Contaliument Purge Isolatiosi c.

1) Manual luitiation N.A.

N.A.

M.A.

R N.A.

M.A.

N.A.

1, 2, 3, 4

2) Automatic Actuation M.A.

M.A.

N.A.

M(1)

Q(3) 1, 2, 3, 4 l

togic'azul Actuation Relays (55P5) g 3

3) Automatic Actientiosi f) togic anal Actuatloss l

3 Helays (BOP iSIA5)

N.A.

M(1)(2)

N.A.

I, 2, 3, 4

[.

4) Phase "A" See Ites 3.a. above (or 411 Please "A" Iselation surveillance Neapsirements.

P Isoldt iosi I

TABLE 4.3-2 (Continueo) 9 ENGINEERED SAFEIY FEATUP'is ACTUATION SYSTEK INSTRUNENTATION

$Ur.dEILLANCE REQUIRENENTS 2-TRIP ANALOG

' ACTUATING NGOES E

CNANNEL DEVICE NASTER SLAVE' FOR 14tICN U

CHANNEL CHANNEL OPERATIONAL DPERATIONAL ACluATION RELAY RELAY SURVEILLANCE FUNCIIONAL UNil CHECK CALIBRATION TEST TEST LOGIC IEST IEST

-TEST IS REQUIRED e

4.

Steam tine Isolation Nnual Initiation

'N.A.

M.A.

R H.A.

N.A.

1, 2, 3 4,

b.

Autematic Actuation M.A.

N.A.

M.A.

N.A.

N(1)

'M(1)

Q I, 2, 3 togic and Actuation Relays (55PS) c.

Contalsment Pressure-5 R

gM N.A.

M.A.

1, 2, 3 A

High-2 1

d.

Steam Line Pressure-S R

f M N.A.

M.A.

N. A.

M.A.

1, 2, 3 w

A Lou u

e.

Stea<a Line Pressare-S R

,.4-M-@

N.A.

M.A.

3 in Negat' ave A

Rate-liigh 5.

Feedwater Isolation & Turbine Trip a.

Automatic Actuation M.A.

N.A.

M.A.

W.A.

N(1)

Q(3) 1, 2 Logic and Actuation Relays (55PS)

N.A.

M.A.

1, 2 b.

Steam Generator Water 5

R gQ level-liigin-liigh A

q c.

Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

M Tv1 6.

Auxiliary feedwater a.

Flanual leiltiation N.A.

N.A.

M.A.

R N.A.

N.A.

I, 2, 3 b.

Automatic Actuation N.A.

N.A.

M.A.

N.A.

N(1)

Q 1, 2, 3 y v

logic and Actuationi Relays (55PS)

~

.m.__

.__ow

4 TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTAT10N

]-

E SURVEILLANCE REQUIREMENTS TRIP g

ANALOG AC10ATING MODES q

CHANNEL DEVICE MASTER SLAVE _ FOR 1811011 CilANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RtLAY SURVEILL ANCE FUNCTIONAL UNIT CllECK CAllBRATION TEST TEST LOGIC IEST_

TEST TEST 15 REQUIRED 6.

Auxiliary feedwater (Continued) c.

Automatic Actuation

' Logic and Actuation Relays (BOP ESTAS)

N.A.

M.A.

N.A.

M(1)(2)

N.A.

1, 2. 3 d.

Steam Generator Water Level Low-Low m

5

1) Steam Generator Water Level Low-Low (Adverse Containment gG N.A.

M.A.

N.A.

M.A.

1, 2, 3 Environment)

S R

A

2) Steam Generator Water Level Low-Low (Nonnal Containment k

Environment)

S R

,g49--@

N.A.

M.A.

N.A.

1, 2, 3 A

a 2

3) Vessel AT N.A.

N.A.

M.A.

1. 2. 3 g Q^

3 (Power-1. Fower-2)

S R

R z

P

4) Containment Pressure -

Environmental Allowance N.A.

N.A.

f4. A.

1. 2, 3 gG Modifier S

R A

e.

Safety injection See Ittse 1 above for all Safety injection Surveillance Requirements.

y 9

IAllLE4.3-2(Continued)

' 'I '

.ENGINEERLD SAIETY-TEAIURES ACTUATION SYSTEM INSIRUMENTATION x

SURVEILLANCE REQUIREMENTS

=

IRIP

'i MOOLS ANALOG ACTUATING CNAM4r4c:;;n #-

ptyICC MASILR SLAVE FOR WillCII CilANNEL CilANNEL OPERATIONAL OPLHATIONAL ACTUATION RELAY RELAY SURVEILLANCE filNCTIONAI. IINIT CifLCK CAlillRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRfD, l

6.

Auxiliary feedwater (Continued)-

f.

L oss-of-Of f site Power N.A.

R N.A.

M N.A.

N.A.

1. 2. 3 9

Irip of All Main M.A.

N.A.

R N.A.

N.A.

M.A.

1. 2 Ieedwater Pumps 1^'

h.

Auxiliary feedwater S

R M

N.A.

1. 2. 3

'f Pump Suction' Pressure-IN Low

(

/. Autantiatic Switchover to

~

Coritairmient. Sump AtllOmatic Actuation N.A.

N.A.

M(1)

Q(3)

1. 2. 3, 4 i

a.

Logic and Actuation Relays (S5PS)

N.A.

1, 2. 3. 4 gG a 3-

!; lJ b.

ItWSI Level - Low-low 5

R

.] $

Coincident With A.

l f; Af Safety Injection See Iten I above for all Safety injection Surveillance Requirements.

?

a.

nn 8.

Ioss of Power x

l 3

a.

4 kV.Undervoltage-N.A.

R N.A.

M N.A.

N.A.

1. 2. 3. 4 '

P i

Ioss of Voltage-l Grid Degraded Voltage _'

N.A.

R N.A.

M N.A.

N.A.

I. 2, 3. 4 j

b.

4 kV lindervoltage-l l

_ = _. =.,..

L

^

IAstE 4.3-2 (Continued)

.Q fleGlatEfRf8 5AfEIY ffAltlRES~ACluAll001 SYSTIM IN51RUNtNlAfl0N E:

1 RIP SuRvfitiAsiCE Reauist><Nis t

N ANAt0G ACiuAllin; noors

.E CHAldN(L DEVICE MA5I[R STAVE IDR lA6ICH Q

CHAlelft. CHAf80[L OPEltAlloNAL DefRAlleIIAL AtluAll081 REiAY RtiAV SDIlvfitt AIICE lHNCIl0HAL UNil_

CitECK CAtlBRAll006 1[5I IEST LOGIC ll5I IESI lisi 15 RfquitfD g

9.

Control floos isolatlosi r

4.

Manuel Initiation M.A.

pl. A.

N. A.-

A N.A.

M.A.

N.A.

AII b.

Automatic Actuation M.A.

N.A.

M(1)

Q(3)

I, 2, 3, 4 togic and Actuation lielays (55PS) c.

Autoestic Actuatiost i

t*

logic asul Actuation lleidys (80F E5fAS)

N.A.

M.A.

00(1)(2)

N.A.

M.A.

All N *i' Nj] y d.

Phase "A" laolettosi See Itesi 3.a. above, for all Phase "A" Isolation Survallbye Rearstrements.

x lo. Solid-State load Seipsencer M.A.

M.A.

N.A.

M(1)(2)

II. A.

k 4.

1. 2, 3, a 11.

fugleiecred Safety f eatures Actasation System Interlocks Pressurlier P essure, M.A.

R gd

11. A.

N.A.

M.A.

1, 2. 3-4.

l-Il A

g b.

lleactor Irlp, P-C N.A.

N.A.

u.n.

E N.A.

N.A.

1, 2, 3 a

IAstE 1101All0Its k"

(1) l'ach tralg sliall be tested 4L least every 62 days on a SIAGGEEED TESI DA515.

(2) Continuity 4.lieck e4y be excluded f ree the AciuAII0el 10GIC IESI.

?

(3).Except Relays K602, E620. E622, g624, g630. E740, ased K741. tdalch shall be tested at least oewe per 18 monthe

{

2 daaring ref acting asui durlog each 00(0 Silul00641 exceedlag 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless they have been tested inithin the

.u j

preylous 90 days.,

line specilled la month frequency may be walveel for Cycle I provided the.surveillaswe is performed 3rior to t

- restart following the first refuellog outage or Jamie I,1986, whichever o4. curs first. Ilse provisions of Spec lficdtless 4.0.7 are resci (ros performance of this 6aarvelllance.

.[

t i

i L

i.

', ' ^

1 v

s w

TABLE 3.3-6

~

h

' RADIATION HONITORING INSTRUMENTATION FOR PLANT OPERATIONS E

E

MINIMUM:

CHANNELS CilANNELS ' APPLICABLE

' ALARM / TRIP

' FUNCTIONAL UNIT TO TRIP / ALARM-OPERABLE MODES SETPOINT ACTION

-e

-E 1.

Containment-a.

Gaseous Radio'ctivity-RCS Leakage Detection N.A.

1

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

29 (GT-RE-31 & 32) b.

Particulate-N.A.

I 1, 2, 3. - 4 N.A.

29 l

Radioactivity-RCS Leakage Detection (GT-RE-31 & 32) 2.

Fuel Building w1 a.

Fuel Building Exhaust-Gaseous Radioactivity-1 2

w g

fligh (GG-RE-27 & 28) 30 b.

Criticality-liigh Radiation Level i

1) Spent Fuel-Pool

'1 1

(SD-RE-37 or 38)

-< 15 mR/h 28

2) New Fuel Pool 1

1 (50-RE-35 or 36)

-< 15 mR/h 28 p

3.

Control Room E

Air Intake-Gaseous S

Radioactivity-fligh 1

2 All

-N-38 5

(GK-RE-04'& 05) z A

.o

^ ' - * ' - - ' '

e' TABLE 3.3-6 (Continued)

TABLE NOTATIONS

)

With fuel in the respective fuel storage pool.

- With irradiated fuel in the fuel storage areas or fuel building.

Trip Setpoint concentration value (uC1/cm3) is to be established such that the actual submersion dose rate would not exceed 2 mR/h in the control room.

1. Trip Setpoint concentration value (uCi/cm3) is to be established such that the actual submersion dose rate would not exceed 4 mR/h in the fuel building.

ACTION STATE *iENTS (NOTE: AermW frATEA!EM7T D8 ANb 27 ARE LACATEb

-ACT!0" 20 - Oeieted.

oN rrNc4 TAdect,)

ACTIONp - With the number of OPERABLE channels one less than the Minimum

]l 37 Channels OPEFABLE requirement, isolate the Control Room Emergency Ventilation System and initiate operation of the Control Room Emergency Ventilation System in the recirculatien mode within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or with no OPERABLE channels within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 13 - With less than the Minimum Channels OPERABLE requirement.

s operation may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alann Setpoint is provided in the fuel area.

Restore the inoperable monitors to OPERABLE status within 30 days or suspend all operations involving fuel movement in the fuel building.

ACTION 29 - Must satisfy the ACTION requirement for Specification 3.4.6.1.

ACTION 30 - Nith the number of OPERABLE channels one less than the Minimum thannels OPERABLE requirement, isola,te the Fuel Building l

Ventilation System and initiate operation of the Emergency Exhaust System to maintain the fuel building at a negative pressure within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or with no OPERABLE channels within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

(Ns YE : A cred Er$YEMENrs 3/ rxxsHGH 39 Axe LocArab DN 6TMEA TA8&ct.)

y m

4 l

l s

CALLAWAY - UNIT 1 3/4 3-40 Amendment No.

L' 49 l

l l

u n..

I f

3/4.3 IKSTRUMENTATION i

BASES F'i 3/4.3.1 and 3/a.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION $YSTEN !NSTRUMENTATION The CPERABILITY of the Reactor Trip System and the Engineered Safety Features Actuation System instrumentation and interlocks ensures that:

(1) the 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 pemit a channel to be out of service for testing or maintenance, and (4) sufficient system functional capability is available from diverse

' P 5 "* " * " 5 -

W/dr 47b,,4 /,

The OPERABILITY of these systems is required to provide th e overall reliability, reduncancy, and diversity assumed available in the facility I

design for the protection and mitigation of accident and transi rnt conditions.

The integrated operation of each of these systems is consistent with the assumptions used in the safety analyses.

The Surveillance Requ ;rements specified for these systees ensure that the overall system functional capability is main-tained comparable to the original design standards.

The period c surveillance l

tests' perfomed at the minimum frequencies are sufficient to denonstrate this capacility. Specif!ad surveillance intervals and surveillance end maintenance outage times have been determined in accordance with WCAP-10271v " Evaluation of

' <@v Surveillance Frequencies and Out of Service times for the Reactor Protection

- Instrumentation Systead r T r-":

^^N' m rt, d the NRC's Safety Surveillance intervals and out of service Evaluation dated February 21,198Sy times were determined based on mair ining an appropriate level of reliability i

'of the Reactor Protection System a Engineered Safety Features instrumentation.

--+

XNSEW )

IWJ5F The Engineered Safety Features Actuation System Instrumentation Trip S*** i"t* 5 5'ci fi'd i a 7'b l

3 3-'

r* th* " *1"*i * * "' ** *^1ch th' G bistacles are set for sach functional unit. A Setpoint is considered to be

. adjusted consistent with the nominal value when the "as measured" Setpoint

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is within the band allowed for calibration accuracy.

. To accommodate the instrument drift assumed to occur between operational i.

I tests and the accuracy to vnich setooints can be measured and calibrated, A11cwable Values for the Setpoints have been specified in Table 3.3-a.

Operation with Setpoints less conservative than the Trip Setpoint but within the Allowaole Value is acceptable since an allowance nas been made in the safety analysis to accommodate this error; An optional provision nas been included for determining the OPERABILITY of a enannel unen its Trip Setpoint is found to exceed the Allowable Value.

The methocology of this cotion utili:es the "as measured" deviation from the specified calibration point for rack and sensor components in conjunction with a statistical comoinatica of the otner uncertainties of the instrumentation to measure the process variable

' q J

and the uncertainties in calibrating the instrumentation.

In Equation 3.3-1, Z + R + 5 < TA, the interactive effects of the errors in the rack and the sensor, anc the "as measurec" values of the errors are considered.

Z, as specified in Tacle 3.3-4, in percent span, is the statistical summation of 1,

errors assumed in the analysis excluding those associated with the sensor and g

CALLAWAY - UNIT 1 a 3/4 3-1 Amencment No. U

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INSERT F WCAP-10271 S applement 2 and WCAP-10271-P-A Supplerrent 2 Revision 1,

" Evaluation of Surveillance Frequencies and out of Service Times for the Engineered Safety Features Actuation System," the NRC's Safety Evaluation dated February 22, 1989, and the NRC's Supplemental Safety Evaluation dated April 30, 1990.

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INSERT G i

With the exception of the containment pressure High-3 analog channels for containment spray actuation and phase B containment isolation, Callaway does not have the capability to perform surveillance testing on a routine basis with an analog instrumentat.4 on channel in a bypassed condition.

Action Statements 2, 6,

19, 32 and 33 allow an inoperable analog channel to be bypassed for surveillanco testing. This allowance is based on an interpretation that this applies to canes where the bypassed condition is the state when a failed channel can be taken out of the test mode (in which a channel trip was forced on the protection system) and returned to operation. Due to the failed nature of the channel, the channel cannot be considered to be OPERABLE and is, therefore, considered to be in a state of bypass when the channel failure is such that its bistable is not tripped.

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ML20070P707

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