Text

Amend 64 to License NPF-30,revising TS to Extend Allowable out-of-svc Times & Surveillance Test Intervals for Analog Channels of ESFAS
	ML20085G428
Person / Time
Site:	Callaway
Issue date:	10/09/1991
From:	Lynch M; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20085G433	List: ML20085G428; ML20085G437;
References
	NUDOCS 9110250027
	Download: ML20085G428 (35)
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7 UNITED STATES

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i NUCLEAR REGULATORY COMMISSION o,

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WASHINoToN. D C. 20t65 UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKETNO.STN50-43 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 64 License No. NPF-30 1.

The l'uclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment filed by Union Electric Company (UE, the licensee) dated March 19, 1991, complies with the standard; and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be ini;uical to the common defense and security or to the health 4.nd safety of the public; and E.

The issuance of this amendinent is in accordance with 10 CFR Part 51 of the Commissien'> regulations and all applicable requirements have been satisfied, 2.

Accordingly, the license u amended by changes to the Tecnnical Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Opercting License No. NPF-30. is hereby amended to read as follows:

91102S0027 911009 PDR ADOCK 05000403 P

PDR

\\

.p.

(?) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, or revised through Amendment No. 64, and the Environ.aental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. UE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY C0ftlSS10t!

A M. D. Lynch, Sr. Project Manager Project Directorate !!!-3 Division of Resctor Projects Ill/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Spacifications Date of issuance:

October 9, 1991 4

ATTACHMENT TO LICENSE AMENDMENT NO. 64 OPERATING LICENSE NO, NPF-30 DOCKET NO. STN 50-483 Revise Appendix A Technical Specifications oy removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain trarginal lines indicating the area cf change. Corresponding overleaf pages are provided to maintain document completeness.

REMOVE INSERT 3/4 3-3(a) 3/4 3-3(a) 3/4 3-4 3/4 3-4 3/4 3-5 3/4 3-5 3/4 3-6 3/4 3-6 3/4 3-6(a) 3/4 3-6(a) 3/4 3-9 3/4 3-9 3/4 3-10 3/4 3-10 3/4 3-12a 3/4 3-12a 3/4 3-14 3/4 3-14 3/4 3-16 3/4 3-16 3/4 3-17 3/4 3-17 3/4 3-18 3/4 3-18 3/4 3-18(a) 3/4 3-18(a) 3/4 3-20 3/4 3-20 3/4 3-21 3/4 3-21 3/4 3-21(a) 3/43-21(a) 3/4 3-21(b) 3/4 3-33 3/4 3-33 3/4 3-34 3/4 3-34 3/4 3-35 3/4 3-35 3/4 3-36 3/4 3-36 3/4 3-36(a) 3/4 3-36(a) 3/4 3-37 3/4 3-37 3/4 3-39 3/4 3-39 3/4 3-40 3/4 3-40 B 3/4 3-1 B 3/4 3-1 B 3/4 3-2 B 3/4 3-2 B 3/4 3-2(a)

B 3/4 3-2(a)

TABLE 3.3-1 (Continued) h REACTOR TRIP SYSTEM INSTRUMENTATION E

MINIMUM y

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT _

0F CHANNELS TO TRIP OPERABLE MODES ACTION l

9 l

p 14.

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

1 6#

Pumps 15.

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

1 6#

Pumps 16.

Turbine Trip l

a.

Low Fluid Oil Pressure 3

2 2

1 6#

k' b.

Turbine Stop Valve Closure 4

4 1

1 11#

k 17.

Safety Injection Input 2

1 2

1, 2 31 l

from ESF 3

11 e

n O.

TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION O,-

G MINIMUM TOTAL NO.

CHAi4NELS CHANNELS APPLICABLE OF CHANNELS TO TRIP OPERABLE MODES ACTION FUNCTIONAL UNIT E

Q 18.

Reactor Trip System Interlocks I

2 1

2 2M 8

l w

a.

Intermediate Range Neutron Flux, P-6 b.

Low Power Reactor P-10 Input 4

2 3

1 8

Trips Block, P-7 P-13 Input 2

1 2

1 8

or 4

2 3

1 8

Power Range Neutron R

c.

Flux, P-8 Y

4 2

3 1

8 d.

Power Range Neutron Flux, P-9 4

2 3

1, 2 8

c.

Power Range Neutron Flux, P-10 f.

Turbine Impulse Chamber 1

2 1

8 l

2 Pressure, P-13 2

1 2

1, 2 9,12 2

1 2

3*, 4*, 5*

10 19.

Reactor Trip Breakers E

~

2 1

2 1 2 31 I

Automatic Trip an6 Interlock Logic 1

2 3, 4*, 5*

10 "g

20.

2 4

i TABLE 3.3-1 (Continued)

[

TABLE NOTATIONS

0nly if the Reactor Trip System breakers happen to be in the closed position and the Control Rod 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.

(1) The applicable MODES for these channels noted in Table 3.3-3 are more restrictive and, therefora, applicable.

ACTION STATEMENTS 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 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

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

Either, THERKAL 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 - W.th 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 THERMAL 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.

l CALLAWAY - UNIT 1 3/4 3-5 Amendment No. /J7,64

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

. -. ~

~.. - -

. ~

4 4:

-TABLE 3.3-1.jContinued)

ACTION STATEMENTS (Continued).

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

ACTION 5 - a.

With the 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, suspend all-operations 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 corpliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within I hour and every 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 closed and secured in position within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and verified to be closed and secured in position every 14 days.

+

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

a.

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

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

ACTION 7 - With an inoperable delay timer in the Trip Time Delay circuitry, STARTUP and/or POWER OPERATION may proceed provided that the

- Vessel Delta-T -(Power-1, Power-2) channels in the affected protection sets are placed in the tripped condition within f hours.

ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within

-1 hour determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0 3.

ACTION 9 - With the number of OPERABLE Reactor Trip Breakers one less-than the Minimum Channels _0PERABLE requirement, be in at least H0T STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one breaker may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for breaker surveillance testing per Specification 4.3.1.1, provided the other breaker is OPERABLE.

P CALLAWAY - UNIT 1 3/4 3-6 Amendment No. J7, A3,64

.i i

i C

i

TABLE 3.3-1 (Continued)

(

-ACTIO1 STATEMENTS (Continued)

-3 ACTION l10 - With the number of OPERAB'E' channels one less than the Minimun Channels OPERABLE requirs<ent, restore the inoperable channel to OPERABLE status within 48 hoges or open the Reactor trip breakers within the next hour..

ACTION 11 - With the number of OPERASLE channels less than the Total-Number

~

of Channels, operation may coitinue provided the inoperable e

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 (Unde foltage or Shunt Trip Attachment): inoperable, restbre it to UPERABLE status 1

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 G. -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 Number of Channels,1STARTUP 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 .

(NOTE: ACTION ETATEMENTS 14 THROUGH 30 ARE LOCATED ON OTHER TABLES.)

l

ACTION 31f-1With the number of OPERABLE channels one less than the Minimum

. Channels:0PERABLE requirement be in at least HOT 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 bypassed, for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for-logic surveillance testing per Specification 4.3.1;1, provided -

the other channel is CPERABLE.

b i

CALLAWAY - UNIT 1 3/4 3-6(a)

Amendment No. 19, 17, 64

...~.... __

'..i

~.

TA8LE 4.3-1--

n REACTORTRIPSYSTEMIN5TRUNENTATIONSURVEILLANCEREQUIREMENTS E

si TRIP

' ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH E

CHANNEL CHANNEL OPERATIONAL OPERATIONAL

' ACTUATION-SURVEIt' T E G

FUNCTIONAL UNIT-CHECK CALIBRATION TEST TEST.

LOGIC TEST IS REQb.xED s-1.

Manual Reactor Trip M.A.

N.A.

, M.A.

R(16)

N. A.'

1, 2, 3*, 4 *,

5*

2.

Power Range, Neutron Flur a.

High Setpoint S

O(2, 4),

Q N. A.

M.A.

1, 2 g..

M(3,4),

Q(4,6),

R(4, 5) b.

Low Setpoint 5

R(4)

S/U(1)

N.A.

1###, 2 R

3..

Power Range, Neutron Flux,

$1. A.

R(4)

Q N.A.

N.A.

1, 2 l'

High Positive Rate Y

4.

Deleted 5.

Intermediate Range, S

R(4, 5)

S/U(1)

N.A.

1###, 2 Neutron Flux g

6.

Source Range, Neutron Flux 5

R(4, 5, 12)

S/U(1),Q(9)

N.A.

M.A.

2##, 3, 4, 5 7.

Overtemperature AT S

R Q

N.A.

1, 2 8.

Overpower AT S

R Q

N.A.

1, 2

~

.N.A.

N.A.

1-9.

Pressurizer Pressure-Low S

R Q

i.~

-i

(

10.

Pressurizer Pressure-High 5

R Q

N.A.

1.-2 j*

N 11.

Pressurizer Water Level-High 5

R Q

N.A.

N. A.

I h

l 12.

Reactor Coolant Flow-Low 5

R Q'

N.A.

1 j

i

T'ABLE 4.3 1 (Continued) g

. REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

-F TRIP p

ANALOG ACTUATING MODES R

CHANNEL.

DEVICE FOR WilICH CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE CHANNEL c

C11ECK CALIBRATION TEST TEST L_0GIC TEST. ISl REQUIRED 5

. FUNCTIONAL-UNIT 4

13.

Steam Generator' Water Level I.ow-Low I

a.

Steam Generator' Water..

S R

Q (15)

N.A.

1, 2 Level Low-Low (Adverse Containment Environment) b.

Steam Generator Water S

R Q (15)

N.A.

1, 2 '

m2 Level Low-Low (Normal Containment Environment) m c.

Vessel AT (Power-1, S

R

.Q (15)

N.A.

1, 2 '

Power-2) d.

Containment Pressure-S R

Q (15)

N.A.

N.- A.

1, 2 Environmental Allowance Modifier 14.

Undervoltage - Reactor N.A.

R N.A.

Q N.A.

-1

.l

[

Coolant Pumps 3

h

15. Underfrequency - Reactor N.A.

R N.A.

Q' N.A.

1 l

Coolant Pumps y

O b

16.

Turbine Trip m

a.' Low Fluid Oil Pressure

.N.A.

R N.A.

S/U (1,10)

N.A.

I h

b.

Turbine Stop Valve N.A.

R N.A.

S/U {1,10)

N.A.

l'

~

o,

^

Closure

4 TABLE 4.3-1{ Continued)

_T_ABLE _NLOTAT!0NS (10) Setpoint verification is not required.

(11) Following maintenance or adjustment of the Reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verifi-cation of the Undervoltage and Shant trips, a

(12) At least once per 18 months during shutdown, verify that on a simulated Boron Dilution Doubling test signal the normal CVCS discharge valves will close and the centrifugal charging pumps suction valves from the RWST will open within 30 seconds.

(13) Deleted (14)

Deleted (15) The surveillence MODES specified for these channels in Table 4.3-2 are more restrictive and, therefore, applicable.

(16) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall indeper.dently verify the OPERABILITY 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.

(18) Automatic Undervoltage Trip.

3 J

7 CALLAWAY - UNIT 1 3/4 3-12a Amendment No.19, /Za/l',5//,64 1

INSTRUM[NTATION 3/4.3.2-LNGINEERED SAFELY flATURES ACTUATION SYSTEM INSTRUMENTATION i lMlllNG 00NDil10N FOR OPERATION 3, J. / The Engineered Safety Features Actuation System (E5FAS) instrumentation channelv and interlocks shown in Tdble 3.3 3 shall be OPERABLE with their Trip Setpoints set consistent with the values shown in tne Trip Setpoint calumn of f able 3. 3 4 and with RESPONSE TIME 5 as shown in Table 3.3-5.

APPLICABillTY; As snown in Table 3.3 3.

AC,1103 a.

With an ESFA5 Instrumentation or Interlock Trip Setpoint less conservative than the value shown in the Trip 5etpoint column but more conservative than the value shown in the Allowable Value cnlumn of Table 3.3-4 adjust the Setpoint consistent with the Trip Netpuint value D.

Nith an ESF AS Instrumentation or interlock T rip 5etpoint less tenservative than the value shown in the Allowable Values column of lable 3.3-4. either:

1, Adjust the Setpoint consistent with tne Trip Setpoint value of lable 3.3-4 and determine within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that Equatiot: 2.2-1 way satisfied for the affected channel, or 2.

Declare the channel ir. operable and apply the applicable ACTION statecent requirements of Table 3.3.3 until the channel is aestorsd to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.

(quation 2.2-1 Z + R + 5 < TA Where; I

Ihe value from Column 2 of Table 3.3-4 for the affected

channel, R = the "as measured" value (in percent span) of rack error for the affected channel.

Either the "es measured" value (in percent span) of the e

sensor error, ce the value f rom Column 5 (Senior Error) of Table 3.3-4 for the affected channel, and TA = The value from Calumn TA (Total Allowance) of Table 3.3-4 for the affected channel, c.

With an f5fA5 instrumentation channel or interlock inoperable, take the ACllON shown in Table 3,3-3, URVilttANCE REQU'REMENTS Il 3. 2.1 f ach ESF AS-instrumentation channel an.d interlock and the automatic dCluattun IOQ1C and relay 5 shall be demonstrated OPERABLE by the performance of t he (51 A5 Instrumentation Surveillance Requirements specified in Table 4.3-2.

4 L?/ The LNGINfERED SAFETY FEATURE 5 RESPONSE TIME of each ESFA5 function shall be clemonstrated to be within the limit at least once per 18 months.

Each test shall include at least one train such that both trains are tested at least otue per 1b months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant chan-nels in a specific ESTAS f unction as shown in the " Total No. of Channels" Column nt fable 3.1-3.

CALLAWAY - UNIT 1 3/4 3-13

A' ii -

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8 4

3 3

3 8

4' 6

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4 4

L BS r

AE 3

3 3

' 3 3

3 3

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CD O

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2 2

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t a n

I eI '.bMD a

s iu uu n

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s i3 Er N

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y" i a uoe oi t,

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f aot eeegt no T

ah saempna C

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3

TABLE 3.3-3 (Continued)

ENCINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION n

N9 6

HINIMUM TOTAL NO, CHANNELS CHANNEES APPLICABLE FUNCTIONAL UNIT OF CHANNEL 5 TO TRIP OPERABLE MODES ACTION E

a 3.

Containment Isolation a.

Phase "A" Isolation 1)

Manual Initiation 2

1 2

1, 2, 3, 4 18 2)

Automatic Actuation 2

1 2

1, 2, 3, 4 14 Logic and Actuation Relays (SSPS) 3)

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

Y b.

Phase "B" Isolation Y

t; 1)

Manual Initiation 2 pair 1 pair 2 pair 1, 2, 3, 4 18 operated s-simultaneously 2)

Automatic Actuation 2

1 2

1, 2, 3, 4 14 Logic and Actuation Relays (55PS) 3)

Containment 4

2 3

1, 2, 3 16 Pressure-High-3 c.

Containment Purge Isolation 1)

Manuai Initiation 2

1 2

1, 2, 3, 4 17

l l

TABLE 3.3-3 (Continued) l l

ENGlHEERED SAFETY FEATURES AC10AT10N SYSTEM INSTRUMENTATION MINIMUM Q

T01AL NO.

CHANNELS CHANNELS APPLICABLE jg FUNCTIONAL UNIT OF CHANNELS 10 TRIP OPERABLE MODf5__

ACTION

>)

3.

Containment Isolation (continued) k 2)

Automatic Actuation 2

1 2

1, 2, 3, 4 17 togic and Actuation Relays (55PS) 3)

Automatic Actuation Lojic and Actuation Relays (BOP ESF AS) 2 1

2 1, 2, 1, 4 Il 4)

Phase "A" Isolation See item 3.a.

for all Phase "A" Isolation initiating functions and requirements.

4.

Steam Line Isolat. ion 5*

a.

Manual Initiation w

[g 1)

Individual 1/ steam 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 J

34 l

Logic and Actuation Relays (55PS) 3r c.

Containment Pressure-3 2

2 1, 2. 3 33*

l g

High-2 d.

Steam Line 3/ steam line 2/ steam line 2/ steam line 1, 2, 3#

33*

czl Pressure-Low any steam r+

line z

P os e.

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

33*

l Negative Rate-High any steam I i ne-

.-.n...

TABLE 3.3-3 (Continusd):

l ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION nW MINIMUM s

TOTAL NO.

CHANNELS CHANNELS APPLICABLE

]

FUNCTIONAL thiIT' 0F ~ CHANNELS. TO TRIP OPERABLE MODE 5 ACTION

~'

\\

E 5.

Feedwater Isolation & Turbine Trip.

G a.

Automatic' Actuation Logic-2-

1 2

1, 2 27 and Actuation Relay (SSPS) 4

-b.

Steam Generator.. Water 4/stm. gen.

2/stm. gen.

~3/stm. gen.

1, 2 33*

.l

' Level High-High-in any oper-in each oper-l ating stm.

atir,9 stm.

~!

gen.

c.

Safety Injection

. See. Item"1. above for all Safe'.y injection initiating functions '

.and requirements.

w i

1 6.

Auxiliary Feedwater j

'a.

Manual Initiation 3(1/ pump) 1/ pump 1/ pump 1,2,3 2a 6.

Automatic Actuation Logic.

2 1

2 1,2,3 34

'j and Actuation Relays-(SSPS)-

E j

c.

Automatic' Actuation Logic 2

1 2

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

ESFAS) d.

. Steam Generator Water Level Low-Low i

g h

1). Start Motor-Driven Pumps i

a) Steam' Generator Water 4/stm. gen.

2/stm. gen.

3/stm.' gen.

1, 2, 3 33*, 35

-l.

~

Level Low-Low in any oper-in each

-(Adverse Containment.

ating stm.

operating Environmen t) gen.

sim. gen.

t

+

e

,m 4

..e

..v..

,+.

-. ~,.. -

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTE?1 IN;TR". MENTATION n?

G

. TOTAL NO.

. CHANNELS-CHANNELS APPLICABLE MINIMUM y

FUNCTIONAL UNIT-0F CHANNELS TO TRIP-OPERABLE.

NODES

-ACTION E

6.

Auxiliary Feedwater (Continued) l Q

d. - Steam Generator Water Level'

~

Low-Low.(Continued)"

1). Start Motor-Driven Pumps

-(Continued) b) -Steam Generator Water 4/stm. gen.

2/stm. gen.

3/stm. gen.

1, 2, 3

.35, 36*

Level Low-Low in ' any. o'per-in each (Normal Containment ating stm.

operating Environment) gen.

stm. gen.

M c) Vessel AT (Power-1, 4

2 3

1, 2, 3 '

37*

^

Y Power-2) d) Containment Pressure-4 2

3 1,2,3 37*

l Environmental Allowance Modifier

2) Start Turbine-Driven Pump I -'

I R

a) Steam Generator Water 4/stm. gen.

2/stm. gen.

3/stm. gen.

1, 2, 3 33*, 35 j

Level Low-Low in any oper-in each (Adverse Containment ating stm.

operating y

Environment)-

gen.

stm. gen.

g b) Steam Generator' Water 4/stm. gen.

2/stm. gen.

3/stm. gen..

., 2, 3 35, 36*

Level Low-Low in any oper-in each D

(Hormal Containment ating stm.

operating Environment) gen.

stm. gen.

E c) Vessel 6T (Power-1, 4

2 3-1, 2. -3 37*

Power-2) y

M em,.,

^s e e w

_,s a

l l

N

.O s

n d

I n

T o

a C

7 i

2 9

5 4

2 A

3 t

2 1

1 1

3 s'

c n

n o

u i

f t

E 4

4 c ~

L g

n BS n

', u AE 3

i 3

3 3

3 f CD t

4 I O a

, g LM 2

i 2

2 2

2 2 n P

t i

P i

, t A

1 n

1 1

1 a

i i

t n

i N

o n

O i

i I

t T

SE c

n A

MLL e

o T

UEB j

i N

MNA 3

n 2

3 2

2 3 t E

I NR I

c M

NAE e

U I HP y

j R

MCO t

)

n T

e n

I S

f o

i f

a i

y I

S nt t

i a e

M l

r f

E l

pa a

)

T S

a mp S

d S

LP ue e

Y EI r

ps r

u S

.f R

2 o

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/

2 1

2 o n

NT f

1 e f

i N

A

( m l

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iO es a

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I CT vt 2s v

o T

on o

C A

b e b

(

U am as

.S T

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L 1 r

)

1 n A

.OE p

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3 NN mu m

mm S

N eq u

ee 3

E

_A t e p

t r l

R AH 4

I r 2

/

3 2

4 I i E

U TC 2

u L

T O

ed

(

eq B

A

.TF en ee A

E O

Sa 4

Sr T

F ec Y

n T

a E

ew F

)l ro

)

A d e ul r

S S

ev n

sl p

en cP ue e

sA

.s m

t e p

i S D

nL v

e p

u av m

gS E

i i

rl m

P wi u

o(

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t r) r)

P a u

r d r P

L t

E nedDd t

P en eD w

s we E

ot e-e t n we e-ro o

ny of N

Caueu ne

.n ov f r eL t

oa La I

(Wnnn emr e

Pi o

t

-)

il S

mne nv r

nt aeW r

t e w

G iii N

rrtbt noi oi eD i o wrS e

aR oh i rf i r t -

aM d uE v

u Lt E

eonrn tt ouo aii tD i e M

es o

t n i

aaCTC t vd c -

sn t

eso hp co

- W wr(

(

nno er fi l r f et cm Ai de t

oEM j o fb l a r

t u t

l t enwrp C

nt Or at yP r iS ca enn I o

- u S

r e

w iu veo eeoam T

FGLt u M

fT f -

anf St tt edi I

SP

)

y o

o ios n

ac Lit N

ymw d

tt

- t ss li n ce mA cc U

rao er sr ppp ita im o

T ne aeL) f a sa i mm xcr t n td Sij L

it 2

at ot ruu uuT ai un Won A

lS SS LS TPP AS(

ma Aa RCI N

i ot O

x t n uo I

u T

Ad e

f 9

h AC a

b C

N U

F 6

7 n?EE[ EZ -

y AE

@$@,e E { t,. hE

~

TABLE _3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM If4STRUMENTATION 9

MINItcM E

TOTAL NO.

CHANNELS CHANNELS APPLICABLE r

5 FUfiCTIONAL UNIT _

0F CHANNELS _

TO TRIP OPERABLE MODES ACTION h

8.

Loss of Power 5

a.

4 kV Bus Undervoltage 4/ Bus 2/ Bus 3/ Bus 1, 2, 3, 4 19*

[

-Loss of Voltage b.

4 kV Bus Undervoltage 4/ Bus 2/ Bus 3/ Bus 1, 2, 3, 4 19*

-Grid Degraded Voltage 9.

Control Room Isolation a.

Manual Initiation 2

1 2

All 26 b.

Automatic Actuation 2

1 2

1, 2, 3, 4 26 M

Logic and Actuation

,]

Relays (SSPS)

Automatic Actuation Logic 2

1 2

All 26 i

c.

and Actuation Relays (BOP ESFAS)

See Item 3.a above fcr all Phase "A" Isolation initiating functions d.

Phase "A" Isolation and requirements.

10.

Solid-State Load Sequencer 2-1/ Train 1/ Train 2-1/ Train 1, 2, 3, 4 25 11.

Egnineered Safety Features Actuation System Interlocks a.

Pressurizer Pressure, 3

2 2

1,2,3 20 P-il

'b.

Reactor Trip, P-4 4-2/ Train 2/ Train 2/ Train 1, 2, 3 22 i

i

i TABLE 3.3-3 (Continued)

TABLE NOTATION

Trip function may be blocked in this MODE below the P-il (Pressurizer Pressure Interlock) Setpoint.

/

HTrip function automatically blocked above P-ll and may be blocked below P-ll when Safety Injection on low steam line pressure is not blocked.

4 Trip function may be blocked jus +. before shutdown of ene last operating

?

main feedwater pump and restored just after the first main feedwater pump is put into service (following its startup trip test).

U

The provisions of Specification 3.0.4 are not applicable.

3

- 0ne in Separation Group 1 and one in Separation Group 4, 7

- - The de-energization of one train of BOP-ESFAS actuation logic and actuation relays renders two of the four cnsnnels inoperable.

Action Statement 21 applies to both Functional Units 6.c and 6 9 in this case.

A_C, TION STATEMLNTS ACTION 14 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveil-lance testing per Specification 4.3.2.1, provided the other channel is OPERA 3LE, 4

ACTION 15 - With the number of GPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the r. ext required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within I hour.

ACTION 16 - With the number of OPERABLE channels one less than the Total Number of Channels, operation mqy 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 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.

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

ACTION 18 - 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 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 SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 19 - 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and CALLAWAY - UNIT 1 3/4 3-20 Amendment No. 26,64

4 w

TABLE 3.3-3 fContinued)

AC110N CTATEMENTS (Continued) b.

The Minimum Channels CSERABLE requirement is met; however, the troperable channel may be bypasted for upEto 2 f.ours for surveillance testing of other r.nannels per Specification 4.3 2.1.

I ACTION 20 - With less than the Minimum Channels 0PERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 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 h0T SHUT 00WN within the fellowing 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 nu.nber 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 the next E hours and in at least HOT SHUTCOWN within the following 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 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 af fected 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 Minimua, Channels OPERABLE requirement, declare the af fected diesel generator and of f-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 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; however, one 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 per Specification 4.3.2.1 provided the other channel is OPERABLE.

(NOTE:

ACTION STATEMENTS 28 THROUGH 31 ARE LOCATED ON OTHER TABLES.)

CALLAWAY - UNIT 1 3/4 3-21 Amendment ho. 64

'e n

=

TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

LACTION 32 - With the number of OPERABLE channels one less then-the Total Number of Channels, 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 satisfied:

a.

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

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specifica-tion 4.3.2.1.

Restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-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 .

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 surveillance testing per Specification 4.3.2.1.

ACTION 33 - 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.

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

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specifica-tion-4. 3. 2.1.

ACTION 34 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in at least HOT SHUTDOWN 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 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1 provided the 6

other channel is OPERABLE.

ACTION 35 - With an inoperable delay timer in the Trip Time Delay circuitry, l'

STARTUP and/or POWER OPERATION may proceed provided that tr.e Vessel AT -(Power-1, Power-2) 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 .

}

/

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

Amendment No. 63,64 I

TABLE 3.1-3(Continaedl ACTl_0N STATE'4ENTS LCantinued)_

ACTION 36 - With the number of OPERABIC channel: : ss than the Total l

J Number of Channels, STARIUP and/or POWER OPERATION nay proceed provided that..ho Containment Pressure-Environmental Allowance Modifier channels in the affected protection sets

.sre placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 37 - With the number of OPERABLE channels less than the Total l

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

\\

i l

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

Amendment No.64 l

TABLE 4.3-2 9

E ENGINEfRED SATETY FEATURES ACTUATION SYSTEM INSTRUNENT ATION l'

SURVEILLANCE REQUIREMENTS g

TRIP ANALOG ACTUATING NODES E

CHANNEL DEVICE MASTER SLAVE' IOR milch Q

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RE L AY

' RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION 1EST

_ 1EST IOGIC TEST TIST il_ '. I 15 RfQUIRil!

1.

Safety injection (Peactor Trip, Phase "A. Isolation, Fee 6<ater Isolation, Turbine Trip, Component Cooling Water Auxiliary feedwater-Motor-Driven Pump, Emergency Diesel Generator Operation, Containment

.t' Cooling, and Essential Service Water Operation) a.

Manual Initiation N.A.

"N.A.

N.A.

R#

'N.A.

N.A.

1, 2, 3, 4

[

b.

Automatic Actuation H.A.

N.A.

N(1)

M(1)

Q(3) 1, 2, 3, 4 Logic and Actuation Relays (SSPS) c.

Containment Pressure-5

.R Q

N.A.

-N.A.

N.A.

1, 2, 3 l

High-1 F

d.

Pressurizer Pressure-S R

Q N.A.

N.A.

I, 2, 3 l

Low e.

Steam Line Pressure-S R

Q N.A.

N.A.

1, 2, 3 l

k 3

Low g

2.

Containment Spray a.

Manual Initiation N.A.

H.A.

R#

H.A.

N.A.

H.A.

1, 2, 3, 4

{

b.

Automatic Actuation N.A.

H.A.

N.A.

M(1)

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

Logic and Actuation Relays (SSPS) c.

Containment "ressure-S R

Q N.A.

N.A.

1, 2, 3 j

High-3

~j TABLE 4.3-2 (Continued)

E~

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM !dSTRUMENTATION SURVEILLANCE REQUIREMENTS a

TRIP i

ANALOG ACTUATING-MODES c

CF.ANNEL DEVICE MASTER. SLAVE-FOR IdHICH-

-i U

CHANNEL CHANNEL

-OPERATIONAL OPERATIONAL ACTUATION RF t AY '

RELAY-SURVEftiANCE z

PUNCTIONAL UNIT CHECK _ ' CALIBRATION TEST

.1EST LOGIC IEST TEST it si 15 REQUIRfD 3.

Containment Ist.lation L

a.

Phase "A" Iso 9 tion

1) Manual Initiation M.A.

N.A.

R:

N.A.

1, 2, 3, 4

2) Automatic Actuation M.A N.A.

N.A.

M(1).

M(1)

Q(3) 1 ?,3, 4 g

logic and Actuation x

[

Relays (SSPS)

II

3) Safety. Injection See Item 1. above for all Safety Injection Survel11ance Requirements, b.

Phase "B" Isolatfor,

1) Manual Initiation

.N.A.

N.A.

Rf M.A.

N.A.

-6 1, 2. 3. 4

2) Automatic Actuation N.A.

N.A.

N. A.

N.A.

M(1)

Q 1, 2, 3, 4 Logic and Actuation Relays (SSPS)

3) Containment 5

R Q

N.A.

M.A.

h.A.

-1, 2, 3 l

Pressure-High-3 F

c.

Containment Purge Isolation k

1) Manual Inttiation

'N.A.

M.A.

R N.A.

N.A.

1, 2, 3, 4 h

2) Automatic Actuation N.A.

N.A.

M.A.

N.A.

.M(1)

M(1)

Q(3) 1,2,3,4

' Logic and Actuation o

Relays (SSPS) z O

3) Automatic Actuation

~

Logic'and Actuation Relays (BOP ESFAS)

N.A.

M(1)(2)

N. A.

.N.A.

1., 2. ?, 4 g

4) Phase "A" See Iten 3.a. above for all Phase "A" Isolation Surveillance Requirements.

Isolation

. ~

.m_

~3 TABLE 4.3-2 (Continued) h_

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRtPeENTATION

. SURVEILLANCE REQUIRENENTS TRIP ANALOG ACTUATING MODES E

CHANNEL DEVICE MASTER SLAVE FOR WHICH U

CHANNEL. CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAf SURVEILLANCE-

- FUNCTIONAL UNIl CHECK CALIBRATION TEST-TEST.

LEIC TEST TEST TEST 15 REQUIRED 4.

Steam Line Isolation a.

Manual Initiation M.A.

N.A.

M.A.

R M.A.

M.A.

1, 2, 3 b.

Automatic Actuation N.A.

N.A.

ii. A.

N.A.

M(1)

Q 1, 2, 3.

Logic and Actuation Relays (SSPS) c.

Containment Pressure-5 9

Q N.A.

M.A.

N.A.

1, 2, 3 J.'

High-2 w1 d.

Steam Line Pressure-5 R

q N.A.

M.A.

M.A M.A.

jt, 2, 3 l

Low w

i;;

e.

Steam Line Pressure-5 R

Q N.A.

M.A.

N.A.

3 l

Negative Rate-High 5.

Feedwater Isolation & Turbine Trip a.

Automatic Actuation N.A.

N.A.

M.A.

N.A.

M(1) 84( 1 )

Q(3).

1, 2 Logic and Actuation Relays (55PS) t If b.

Steam Generator Water S

'R Q

N.A.

M.A.

1, 2

]

g Level-High-High g

c.

Safety Injection See Item 1. above for all Safety Injection Surveillance Require wnts.

[ 6.

Auxiliary feedwater P

Manual Initialinn M.A.

N.A.

R N.A.

N.A.

M.A.

1, 2, 3 a.

b.

Automatic Actuatica N.A.

N.A.

h.A.

M.A.

M(1)

M(1}'

Q 1, 2, 3 Logic and Actuation Relays (SSPS) n -

w

+<

w

L 1

Q TABLE 4.3-2_{ Continued) 5&

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 2-7 SURVEILLANCE REQUIREMENTS i.

E-TRIP i

q ANALOG ACTUATING MODES

-m CHANNEL DEVICE MASTER SLAVE FOR WHICH

'CHAhNEL CHANNEL OPERATICMAL OPERATIONAL AC UATION RFLAY RELAY SURVEILLANCE.

i FUNCTIONAL UNIT ~

_ CHECK _. CAL?BRATION TEST TEST

. LOGIC TEST TEST TEST IS REQUIRED

I 6.

Auxiliary Feedwater '(Continued) i t

c.

Automatic Actuation Logic and Actuation i

Releys (B0P ESFAS)

N.A.

N. A.'

N.A.

M(1)(2s N.A.

N.A.

1, 2, 3 f

w 2

d.

Steam Generator Water level Lo;-Low m

1) Steam Generator i'

Water Luel Low-Low (Adverse Containment j

E.w ironment)

S R

Q N.A.

N.A.

M.A.

N. A.

1, 2. 3

-l l

2) Steam Generator Water Level Low-Low (Nonnal Containroent l

k Environment)

S R.

Q N.A.

N.A.

P.A.

1, 2, 3 l

l

~

R jg

').. Vessel AT l

s.,

(Power-1, Power-2)

S R

Q N.A.

N.A.

1, 2, 3 l

l

\\

x j

.o

4) Containment Pressure -

Environmental Allowance I

. Modifier S

R Q

N.A.

N. L I, 2, 3 l

l m

e.

Safety Injection See Item 1 above for all Safety I,

. ion Surveillance Requirenents.

l i

s

I i

S1 EI TABLE 4.3-2 (Continued)

E 32 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM IftSTRUMENTATION SURVEILLANCE REQUIREMENTS E

TRIP

e ANALOG ACTUATIf*G MODES CHANNEL DEVICE MASTER SLAVE FOR WHICH l

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ArTUATION RELAY RELAY SURVE1LLANCE 1

FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST _

TEST IS REQUIRED 6.

Auxiliary feedwater (Continued) f.

Loss-of-Offsite Power N.A.

R N.A.

M N.A.

N.A.

1,2,3 9

irip of All Main N.A.

N.A.

R N.A.

N.A.

1, 2 feedwater Pumps R

h.

Auxiliary feedwater S

R M

N.A.

1, 2, 3

^

T' Pump Suction Pressure-jy low w

7.

Automatic Switchover to Containment Sump a.

Automatic Actuation N.A.

N.A.

ff(l)

M(1)

Q(3) 1, 2, 3, 4 Logic and Actuation Relays (SSPS) b.

RWST Level - Low-Low S

R Q

N.A.

A.

N.A.

1, 2, 3, 4 l

F m

E Coincident With Safety Injection See Item I above for all Safety Injection Surveillance Requirements.

A 8.

Loss of Power

=?

Q3 a.

4 kV Undervoltage-N.A.

R N.A.

M N.A.

N.A.

1, 2, 3. 4 Loss of Voltage b.

4 kV Undervoltage-Grid Degraded Voltage N.A.

R N.A.

M N.A.

N.A.

1, 2, 3, 4

- +

+

TABLE 4.3-2 (Continued) g ENGINEERED SAFETY FCATURES ACTUATION SYSTEM INSTRUNENTATION E

SURVEILLANCE REQUIREMENTS I

E TRIP ANALOG ACTUATING MODES E

CHANNEL DEVICE MASTER SLAVE' TOR WNICH I

O CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE yFUNCTIONAL UNIT CHECK CALIBRAT!DM TEST TEST LOGIC TEST TEST TEST 15 REQUIRED t

i 9.

Control Room Isciation a.

Manual Initiation N.A.

N.A.

M.A.

R M.A.

M.A.

AlI i

i b.

Automatic Actuation M.A.

N.A.

M.A.

N.A.

M(1)

Q(3) 1, 2. 3, 4 Logic and Acte tion Relays (SSPS) s c.

Automatic Actuation Logic and Actuat~on Relays (BOP ESFAi)

N.A.

M.A.

M(1)(2)

N.A.

M.A.

All l

i w

w d.

Phase "A" Isolation See Item 3.a. above for all Phase "A" Isolation Surveillance Requirements.

l 10.

Solid-State load Sequencer N.A.

M.A.

N.A.

M(1)(2)

N.

M.A.

1, 2, 3, 4 f

11.

Engineered Safety Features i

Actuation System Interlocks

(

- a.

Pressurizer Pressure, M.A.

R Q

M.A.

1, 2, 3 l

f P-11 t

b.

Reactor Trip, P-4 N.A.

M.A.

R N.A.

M.A.

1, 2, 3 l

R TABLE NOTATIONS I

1 3

~

A (1) fach train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

z (2) Continuity check ray be excluded from the ACTUATION LOGIC TEST.

?

(3) Except Relays K602, K620, K622. K624, K630. K740, and K741, which shall be testes at least once per 18 month-t 2q during refueling and during each COLD SHUIDCWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless they have been tested within the previous 90 days.

j T

F The specified 18 month frequency may be waived for Cycle I provided the surveillance is performed prior to j

restart following the first refueling outage or June 1,1996, whichever occurs first.

The provisions of Specification 4.0.2 are reset from performance of this surveillance.

l b

n,,

a-

,-- -,,-. - + - - - -.

-s v.

_lN51RUME N,f Ai!ON 3 /.4..h 3 UO.NI.I031_NO _ INSTRUMENT Afl0N RADIAll0N MON!l0 RING 10R PLANT OPERat!ONS LIMITING CON 0it!CN FOR OPERATION 3.3.3.1 the radiation monitoring instrumentation channels for plant operations shown in Table 3.3 6 thall be OPERABLE with their Alarm / Trip 5etpoints within the specified limits.

APPLICABilliY:

As shown in Table 3.3 6.

ACTION:

a.

Wi a radiation monitoring channel Alarm / Trip 5etpoint for plant ope t' ions exceeding the value shown in Table 3.3 6, adjubt the Set vs nt to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inop.rable.

b.

With one or more radiation monitoring channels for plant operations inoperable, take the ACTION shown in Table 3.3-6.

C, The provisions of Specifications 3.0.3 and 3.0.4 are not 50plicable.

SURVEILLANCE REQUIREMEN'S 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CAllBRA110N and ANALOG CHANNEL OPERATIONAL TEST for the MODES and at the f requencies shown in Table 4. 3 3.

CALLAWAY - UNIT 1 3/4 3-38

TA8tE 3.3-6 RADIATION MMITORING INSTRIMNTATIOe! FOR PLANT OPERATIONS 5

c MINIMtM i

E CHANNELS CHANNELS.

APPLICA8tE

' ALARM / TRIP FUNCTIONAL UNIT TO TRIP /ALAHM OPERA 5tE N00ES SETPOINT ACTION 4

- e

]

1.

Containment l

a.

Gaseous Radioactivity-RCS Leakage Detection M.A.

I 1, 2, 3, 4 M.A.

29 l

(GT-RE-31 & 32) i l

b.

Particulate-N.A.

I 1,2,3,4 M.A.

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

Fuel Building w1 a.

Fuel Building Exhaust-Gaseous Radioactivity-1 2

30 w

0 High (GG-RE-27 & 28) e b.

Criticality-High Radiation Level

1) Spent Fuel Pool 1

1 1 15 mR/b 28 (SD-RE-37 or 38)

^

2) New Fuel Pool 1

1 1 15inR/h 28 i

(SD-RE-35 or 36) 3.

Control Room "k

Air Intake-4seous Radioactivity-High 1

2 All 33 l

(GK-RE-04 & 05)

.E 9

4

=

1 g' ' _

f..

sR.

TABLE 3.3-6(Continuedl TABLE NOTATIONS

With fuel in the respective fuel storage pool.

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

Trip Setpoint concentration value (uCi/cm ) is to be established such 3

that the actual submersion dose rate would not exceed 2 mR/h in the control room, i

l

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

ACTION STATEMtjlT_S (NOTE:

ACTION STATEMENTS 26 and 27 ARE LOCATED ON OTHER TABLES.)

ACT10f1 28 - With less than the Minimum Channels OPERABLE requirement, operation may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alarm Setpoint is provided in the fuel area.

Restore the inoperable monitors to OPfRABLE 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...l.

ACT10f1 30 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE ccquirement, isolate the Fuel Building Ventilation Sy5 tem 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 I hour.

ACTION 38 - With the number of OPERABLE'chonnels one less than the Minimum l

Channels OPERABLE requirement, isolate the Control Room Emergency Ventilation System and initiate operation of the Control Room Emergency ventilation System in the recirculation mode within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or with no CPr.RA3LE channels within I hour.

(NOTE:

ACTION STATEMENTS 31 THROUGH 37 ARE LOCATED ON OTHER TABLES.)

l CALLAWAY - UNIT 1 3/4 3-40 Amendment No. 20,p,64 m

3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES AETITATION SYSTEM Ih5TRUMENTATION The OPERA 81Lilf of the Reactor Trip Syst=m and the Engineered Safety features Actuation tystem instrumentation and interlocks ensures that:

(1) the associated action and/or Reactor trip will be initiated when the parameter monitored by each channel or combination 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.

l 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 s/ stem functional capability is main-l tained comparable to the original design standards.

The periodic rueveillance tests performed at the minimum frequencies are sufficient to demonstrate this-capabilit).

Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271 and its Supple-l uent 1. " Evaluation of Surveillance Frequencies and Out of Service times for the l

Reactor Protection Instrumentation System," the NRC's Safety Tvaluation dated February 21,198S WCAP-10271 Supplement 2 and WCAP-10271-P-A Supplement 2, Revision 1, " Evaluation of Surveillance Frequencies and Out of Service Times for the Engineered Safety Features Actuation System," the NRC's Safety Evalua-tion dated February 22, 1989, and the NRC's Supplemental Safety Evaluation dated April 30, 1990.

Surveillance intervals and out of service times were determined based on maintaining an appropriate level of reliability of the Reactor Protection System and Engineered Safety Features instrumentation.

With the exception of the containment pressure High-3 analog channels j

for containment spray actuation and phase'B containment isolation, Callaway does not have the capability to perfonn surveillance testing on a routine basis with an analog instrumentation channel in a bypassed condition.

Action Statements 2, 6, 19, 32 and 33 allow an inoperable analog chanrcel to be by-l passed for surveillance testing.

This allowance is based on an interpretation that this applies to cases 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 f ailure is such that its _ bistable is not tripped.

The Engineered Safety Features Actuation System Instrumentation Trip Setpoints specified-in Table 3.-3-4 are the nominal values at which the bistables are set for each functional unit.

A Setpoint is considered to be adjusted consisteat with the nominal value when the "as measured" Setpoint is within the band allowed for calibration accuracy.

)

l CALLAWAY - UNIT 1 B 3/4 3-1 Amendment No, U,64

INSTRUMENTATION BASES REACTOR TRIP SYSTEP and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)

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

Operation with setpoints less conservative than the Trip Setpoint but within 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 detertrJning the OPERABILITY 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 calibration point

.for rack and sensor components in conjunction with a statistical combination of the other uncertainties of the instrumentation to measure the process variable and the uncertainties in calibrating the instrumentatir in Equation 3.3-1, Z + R + 5 < TA, the interactive effects of the errors in the rack and the sensor, an'd the "as measured" values of the errors are censidered.

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 drift and the accuracy of their measurement.

TA or Total Allowance is the difference, in percent span, between the Trip Setpoint and the value used in the analysis for the actuation.

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

S or Sensor Error is eithe

the "as measured" deviation of the sensor from its calibration point or the value specified in Table 3.3-4, in percent span, from 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 -instr' mentation utilized in these channels are expected to be capable of u

operating within the allowances of these uncertainty ma;nitudes.

Rock drift in excess of the Allowable Value exhibits the behavior that the rack has not met its allowance.

Being that there is a small statistical chance that this will happen, an infrequent excessive drift is expected.

Rack or sensor drif t, in excess of the allowance that is more than occasional, may be indicative of more serious 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 channel 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 applicable, 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.

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.

CALLAWAY UNIT 1 B 3/4 3-2 Amendment No. 17,22,64

INSTRUMENTATION BASES REACTOR Trip SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTfM INSTRUMENTATION (Continued)

Engineered Safety features response time specified in Table 3.3-5 which include sequential operation of the PWST and VCT valves (Notes 3 and 4) are based on values assumed in the non-LOCA safety analyses.

These analyses take credit for injection of borated water from the RWST.

Injection of borated water is assumed not to occur until the VCT charging pump suction valves are closed following oDening of the RWST charging pump suction valves. When the sequential operation of the RWST and VCT valves is not included in the response times (Note 7), the values specified are based on the LOCA analyses.

The LOCA analyses take credit for injection flow regardless of the source.

Verification of the response time specified in Table 3.3-5 will assure that the assumptions used for the LOCA and non-LOCA analyses with respect to operation of the VCT and RWST valves are valid.

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 these 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 the consequences of a steam line break or loss-of-coolant accident:

(1) Safety In ection pumps start and automatic valves position, (2) Reactor trips.

(3 feedwater System isolates. (4) the emergency diesel generators start.

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

CALLAWAY - UNIT 1 B 3/4 3-2(a)

Amendment No. J/.??.04 T

.-n.

e

.,w

-1 y

~

g---

-- - - - ~ -, - -

,

ML20085G428

Text

Attachment:

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