Text

Amends 184 & 161 to Licenses DPR-53 & DPR-69,respectively, Revises TSs by Relocating Tables of Response Time Limits for Reactor Protection Sys & Engineered Safety Features Actuation Sys Instruments from TSs to Updated FSAR
	ML20067B997
Person / Time
Site:	Calvert Cliffs
Issue date:	02/10/1994
From:	Capra R; Office of Nuclear Reactor Regulation
To:	;
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ML20067C001	List: ML20067B997; ML20067C005;
References
	NUDOCS 9402250237
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k UNITED STATES I

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NUCLEAR REGULATORY COMMISSION ihgl

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WASHINGTON, D.C. 20555-0001 Y. s ]

BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET N0. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.184 License No. DPR-53 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated November 11, 1993, complies with the standards 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; l

D.

The issuance of this amendment will not be inimical to the common-defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-53 is hereby amended to read as follows:

9402250237 940210 PDR ADOCK 05000317 P

PDR 1

1 r

__ _ _ _ _-_ - - ______ _ ___ - _____ _ __ _ _- (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 184, are hereby incorporated in the license. The licensee shall operate the fat.ility in accordance with the Technical Specifications.

3.

Ti.is license amendment is effective as of the date of its issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION l

U O-Robert A. Capra, Director Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 10, 1994 l

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k UNITED STATES 3.!i^

j NUCLEAR REGULATORY COMMISSION "g

WASHINGTON, D.C. 205'4 0001 o

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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.161 License No. DPR-69 1.

The Nuclear Regulatory Commission (the Commission) has found that:

P A.

The application for amendment by Baltimore Oas and Electric Company (the licensee) dated November 11, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; C.

There is reasonable assurance (i) that the activities authorized 7

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 Comission's regulations; D.

The issuance of this amendment will not be. inimical to the common i

defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, t

and paragraph 2.C.2 of Facility Operating License No. DPR-69 is hereby amended to read as follows:

2-(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.161,, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION h-Robert A. Capra,~Di ector Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 10, 1994

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. IR4 FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO.161 FACILITY OPERATING LICENSE NO. DPR-69 QQCKET NOS. 50-317 AND 50-318 Revise Appendix A as follows:

Remove Paaes Insert Paaes IV IV 3/4 3-1 3/4 3-1 3/4 3-6 through 3-8*

3/4 3-6 through 3-8*

3/4 3-9 3/4 3-9 3/4 3-10 through -61* (DPR-53) 3/4 3-10 through -61* (DPR-53) 3/4 3-10 through -60 (DPR-69) 3/4 3-10 through -60* (DRP-69) i 83/4 3-1 B3/4 3-1 I

Rollover pages vertical line at page number nr.ly.

i a

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TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION...................

3/4 3-9 l

3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-23 Incore Detectors 3/4 3-27

+

Seismic Instrumentation...............

3/4 3-30 Meteorological Instrumentation 3/4 3-33 Remote Shutdown Instrumentation...........

3/4 3-36 Post-Accident Instrumentation............

3/4 3-39 Fire Detection Instrumentation 3/4 3-43 Radioactive Gaseous Effluent Monitoring Instrumentation...................

3/4 3-48 l

Radioactive Liquid Effluent Monitoring Instrumentation...................

3/4 3-53 l

3/4.4

' REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION STARTUP And POWER OPERATION.............

3/4 4-1 HOT STANDBY.....................

3/4 4-2 Shutdown 3/4 4-4 3/4.4.2 SAFETY VALVES....................

3/4 4-6 3/4.4.3 RELI EF VALVES....................

3/4 4-7 3/4.4.4 PRESSURIZER.....................

3/4 4-8 l

3/4.4.5 STEAM GENERATORS 3/4 4-9 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems..............

3/4 4-16 Reactor Coolant System Leakage 3/4 4-18 3/4.4.7 CHEMISTRY......................

3/4 4-20 3/4.4.8 SPECIFIC ACTIVITY..................

3/4 4-23 CALVERT CLIFFS - UNIT 1 IV Amendment No. 184

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1.1 As a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE.

l APPLICABILITY: As shown in Table 3.3-1.

ACTION: As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each reactor protective instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-1, 4.3.1.1.2 The logic for the bypasses shall be demonstrated OPERABLE prior to each reactor STARTUP unless performed during the preceding 92 days. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation.

4.3.1.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function

shall be demonstrated to be within its limit at least once per l

18 months.

Each test shall include at least one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.

Neutron detectors are exempt from response time testing.

I CALVERT CLIFFS - UNIT 1 3/4 3-1 Amendment No. 184

g TABLE 4.3-1 R

G REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS w

g b

CHANNEL MODES IN WHICH q

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED h

h ll 1.

Manual Reactor Trip NA NA S/U )

NA Z

2.

Power Level - High y

a.

Nuclear Power S

D(2) g(3) q n)

M 1, 2 D ),R H

1 U

b.

AT Power S

3.

Reactor Coolant Flow - Low S

R H

1, 2 R

4.

Pressurizer Pressure - High S

R H

1, 2 h

5.

Containment Pressure - High S

R H

1, 2 6.

Steam Generator Pressure - Low S

R H

1, 2 7.

Steam Generator Water Level -

S R

H 1, 2 Low 8.

Axial Flux Offset S

R H

1 9.

a.

Thennal Margin / Low Pressure S R

H 1, 2 Fg b.

Steam Generator Pressure S

R H

1, 2 Difference - High

10. Loss of Load NA NA S/U )

NA II Ei a

, _. - -., - _ _. _ _ _ _ _ _ _ _ _ _ -. _ - _ _ - _ __ _ _ _ _ _ _ _ - ' + _ _ _ _ _ _ _ _ _

.=

$2 TABLE 4.3-1 (Continued) it

[2 f*

Sg REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS

'd CHANNEL MODES IN WHICH

R CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE EE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED M

i ac

11. Wide Range Logarithmic Neutron Flux S

RIO S/U(O 1, 2 52 and, 3, 4, 5

{j c:j" Monitor

12. Reactor Protection System Logic NA NA M and S/U(U 1, 2 Matrices

13. Reactor Protection System Logic NA NA M and S/U(U 1, 2 Matrix Relays

14. Reactor Trip Breakers NA NA M

1, 2 and

Wb i!T n

an M

l

.---- --- ------a

J 3/4.3 INSTRUMENTATION i

TABLE 4.3-1 (Continued)

TABLE NOTATION With reactor trip breakers in the closed position and the CEA drive system capable of CEA withdrawal.

(1)

If not perfomed in previous 7 days.

l (2)

Heat balance only, above 15% of RATED THERMAL POWER; adjust " Nuclear Power Calibrate" potentiometers to make the nuclear power signals agree with calorimetric calculation if absolute difference is > 1.5%.

During PHYSICS TESTS, these daily calibrations of nuclear power and AT power may be suspended provided these calibrations are perfomed upon reaching each major test power plateau and prior to proceeding to the next major test power plateau.

(3)

Above 15% of RATED THERMAL POWER. recalibrate the excore detectors which monitor the AXIAL SHAPE INDEX by using the incore detectors or restrict THERMAL POWER during subsequent operations to 5 90% of the maximum allowed THERMAL POWER level with the existing Reactor Coolant Pump combination.

(4)

Above 15% of RATED THERMAL POWER, adjust "AT Pwr Calibrate" potentiometers to null " Nuclear Pwr - AT Pwr." During PHYSICS TESTS, these daily calibrations of nuclear power and AT power may be suspended provided these calibrations are performed upon reaching each major test power plateau and prior to proceeding to the next j

major test power plateau.

(5)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

j m

CALVERT CLIFFS - UNIT 1 3/4 3-8 Amendment No. 184 l

3/4.3 INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and bypasses shown in Teble 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.

l APPLICABILITY: As shown in Table 3.3-3.

ACTION:

a.

With an ESFAS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4. declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted i

consistent with the Trip Setpoint value.

b.

With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

SURVEILLANCE REQUIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-2.

4.3.2.1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation.

4.3.2.1.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.

Each test shall include at least one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.

CALVERT CLIFFS - UNIT 1 3/4 3-9 Amendment No. 184

g TABLE 3.3-3 g

G ENGINEEP.ED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION w

g b

MINIMUM q

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION k

=

b 1.

SAFETY INJECTION (SIAS)'

y 3

C

[

a.

Manual (Trip Buttons) 2 1

2 1,2,3,4 6

E b.

Containment Pressure - High 4

2 3

1,2,3 7*

f c.

Pressurizer Pressure - Low 4

2 3

1, 2, 3 ')

7" g

2.

CONTAINMENT SPRAY (CSAS) a.

Manual (Trip Buttons) 2 1

2 1,2,3,4 6

o b.

Containment Pressure - High 4

2 3

1,2,3 11 3.

CONTAINMENT ISOLATION (CIS)'

a.

Manual CIS (Trip Buttons) 2 1

2 1,2,3,4 6

[

b.

Containment Pressure - High 4

2 3

1,2,3 7*

a m

. m-.

m..%..m..-

im.--

--m

..-mma m

g TABLE 3.3-3 (Continued) w G

g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION EE n

C MINIMUM

!Q R

TOTAL NO.

CHANNELS CHANNELS APPLICABLE E

w FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES _

ACTION i5i e

x c

4.

MAIN STEAM LINE ISOLATION W

d a.

Manual (MSIV Hand Switches 1/ valve 1/ valve 1/ valve 1, 2, 3, 4 6

E and Feud Head Isolation Hand Switches) b.

Steam Generator Pressure -

4/ steam 2/ steam 3/ steam 1, 2, 3M 7*

Low generator generator generator 5.

CONTAINMENT SUMP RECIRCULATION (RAS) w b

a.

Manual RAS (Trip Buttons) 2 1

2 1,2,3,4 6

b.

Refueling Water Tank - Low 4

2 3

1,2,3 7*

N a,

r+

E

+

x

,mme

g TABLE 3.3-3 (Continued)

R G

g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION w

w b

MINIMUM Q

TOTAL NO.

CHANNELS CHANNELS APPLICABLE E

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION M

b 6.

CONTAINMENT PURGE VALVES h

ISOLATION y

a.

Manual (Purge Valve Control 2/ Penetration 1/ Penetration 2/ Penetration 6**

8 Switches) b.

Containment Radiation -

High Area Monitor 4

2 3

6**

8 R

7.

LOSS OF POWER a.

4.16 kv Emergency Bus 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 7*

~

Undervoltage (Loss of Voltage) b.

4.16 kv Emergency Bus 4/ Bus 2/ Bus 3/ Bus 1,2,3 7*

Undervoltage (Degraded Voltage)

N 8

$a M

m-

.- a--

.- e-

. - m

g TABLE 3.3-3 (Continued)

R G

g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION w

EE n

C MINIMUM 7

TOTAL NO.

CHANNELS CHANNELS APPLICABLE E

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION g

c 8.

CVCS ISOLATION 3!

5 d

a.

Manual (CVCS Isolation E

Valve Control Switches) 1/ Valve 1/ Valve 1/ Valve 1,2,3,4 6

b.

West Penetration Room / Letdown Heat Exchanger Room Pressure - High 4

2 3

1,2,3,4 7*

9.

AUXILIARY FEEDWATER ACTUATION SYSTEM (AFAS)

U a.

Manual (Trip Buttons) 2 sets of 2 per 1 set of 2 2 sets of 2 1,2,3 6

S/G per S/G per S/G b.

Steam Generator Level - Low 4/SG 2/SG 3/SG 1,2,3 7

c.

Steam Generator AP High 4/SG 2/SG 3/SG 1, 2, 3 7

E n

ro if M

w m

-. m

3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

TABLE NOTATION Containment isolation of non-essential penetrations is also initiated by SIAS (functional units 1.a and 1.c).

When the RCS temperature is:

(a) Greater than 375 F, the required OPERABLE HPSI pumps must be able to start automatically upon receipt of a SIAS signal, (b) Between 375 F and 355 F, a transition region exists where the OPERABLE HPSI pump will be placed in pull-to-lock on a cooldown and restored to automatic status on a heatup.

(c) At 355 F and less, the required OPERABLE HPSI pump shall be in i

pull-to-lock and will not start automatically.

The provisions of Specification 3.0.4 are not applicable.

Must be OPERABLE only in MODE 6 when the valves are required OPERABLE and they are open.

(a)

Trip function may be bypassed in this MODE when pressurizer presture is < 1800 psia; bypass shall be automatically removed when pressurizer pressure is > 1800 psia.

(C)

Trip function may be bypassed in this MODE below 785 psia; bypass shall be automatically removed at or above 785 psia, i

CALVERT CLIFFS - UNIT 1 3/4 3-14 Amendment No. 184 l

3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

ACTION STATEMENTS With the number of OPERABLE channels one less than the Total ACTION 6 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 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 7 With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in either the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

For the purposes of testing and maintenance, the inoperable channel may be bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months from time of initial loss of OPERABILITY; however, the inoperable channel shall then be either restored to OPERABLE status or placed in the tripped condition.

b.

Within one hour, all functional units receiving an input from the inoperable channel are also placed in the same condition (either bypassed or tripped, as applicable) as that required by a. above for the inoperable channel.

c.

The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while performing tests and maintenance on that channel provided the other inoperable channel is placed in the tripped condition.

ACTION 8 With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge valves are maintained closed.

ACTION 11 -

With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is demonstrated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ; one additional 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.

CALVERT CLIFFS - UNIT 1 3/4 3-15 Amendment No. 184 l

g TABLE 3.3-4 R

G g

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES w

E n

C FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES m

n

?

1.

SAFETY INJECTION (SIAS)

E i

=

c-a.

Manual (Trip Buttons)

Not Applicable Not Applicable W

~

5 d

[

b.

Containment Pressure - High 5 4.75 psig 5 4.75 psig E

c.

Pressurizer Pressure - Low 1 1725 psia 2 1725 psia 2

CONTAINMENT SPRAY (CSAS) a.

Manual (Trip Buttons)

Not Applicable Not Applicable b.

Containment Pressure - High 5 4.75 psig 5 4.75 p=4g w!.

3.

CONTAINMENT ISOLATION (CIS)'

cn a.

Manual CIS (Trip Buttons)

Not Applicable Not Applicable b.

Containment Pressure - High 5 4.75 psig 5 4.75 psig 4.

MAIN STEAM LINE ISOLATION g

a.

Manual (MSIs aand Switches and Not Applicable Not Applicable g

Feed Head Isolation Hand Switches)

&g b.

Steam Generator Pressure - Low 1 685 psia 1 685 psia

,o

.E g

Containment isolation of non-essential penetrations is also initiated by SIAS (functional units 1.a and 1.c).

m

. m a-m

=sr-h

$;2 TABLE 3.3-4 (Continued)

R G

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES w

g b

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 7

E m

x i

5.

CONTAINMENT SUMP RECIRCULATION (RAS) g c

a.

Manual RAS (Trip Buttons)

Not Applicable Not Applicable b.

Refueling Water Tank - Low 1 24 inches above tank i 24 inches above tank bottom bottom 6.

CONTAINMENT PURGE VALVES ISOLATION a.

Manual (PURGE Valve Control Not Applicable Not Applicable g

Switches) b.

Containment Radiation - High Area 5 220 mr/hr 5 220 mr/hr O

Monitor 7.

LOSS OF POWER a.

4.16 kv Emergency Bus Undervoltage 2/50 1 105 volts with a 2450 1 105 volts with a (Loss of Voltage) 2 1 0.2 second time delay 2 1 0.2 second time delay b.

4.16 kv Emergency Bus Undervoltage 3628 1 25 volts with a 3628 1 25 volts with a k

(Degraded Voltage)

U i 0.4 second time delay 8 1 0.4 second time delay n

!!F a

--n

I~

l l

l g

TABLE 3.3-4 (Continued)

R i

G l

g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES w

b FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

?

E w

x 8.

CVCS ISOLATION g

c 5

West Penetration Room / Letdown Heat 5 0.5 psig 5 0.5 psig d

[

Exchanger Room Pressure - High E

9.

AUXILIARY FEEDWATER ACTUATION SYSTEM (AFAS) a.

Manual (Trip Buttons)

Not Applicable Not Applicable b.

Steam Generator (A or B) Level -

-149 inches to -194 inches

-149 inches to -194 inches Low (inclusive)

(inclusive) 5 c.

Steam Generator AP - High 5 135.0 psi 5 135.0 psi (SG-A > SG-B) d.

Steam Generator AP - High 5 135.0 psi 5 135.0 psi (SG-B > SG-A)

F 9

8-an W

w e-

~- -

,m, u--

g TABLE 4.3-2 R

r-ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS U

b CHANNEL MODES IN WHICH q

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED k

"i c-g 1.

SAFETY INJECTION (SIAS) y

=

~

a.

Manual (Trip buttons)

NA NA R

NA b.

Containment Pressure - High S

R H

1,2,3 c.

Pressurizer-Pressure - Low S

R IOg)(3) 1, 2, 3 d.

Automatic Actuation Logic NA NA M

1, 2, 3 2.

CONTAINMENT SPRAY (CSAS)

R a.

Manual (Trip buttons)

NA NA R

NA

^

Y b.

Containment Pressure - High-S R

H 1, 2, 3 G

c.

Automatic Actuation Logic NA NA M(u(6) 1, 2, 3 3.

CONTAINMENT ISOLATION (CIS)'

a.

Manual CIS (Trip buttons)

NA NA R

NA b.

Containment Pressure - High S

R M

1, 2, 3 c.

Automatic Actuation Logic NA NA MIDI")

1, 2, 3 ka ita EF M

4 T

w-g

...e u.

.-.-~.-..me-r

,cr,

.-e.

-- i w

- e s--. -,.. - - - -

e r

r e

w -

.=,,--v-

.----,.me-..*

g---r--.-.=m

,=m a

T g

TABLE 4.3-2 (Continued)

R G

g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUNENTATION SURVEILLANCE REQUIREMENTS w

b CHANNEL MODES IN WHICN q

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED k

C*

4.

MAIN STEAM LINE ISOLATION (SGIS) a.

Manual SGIS (MSIV Hand Switches NA NA R

NA and feed Head Isolation Hand Switches) b.

Steam Generator Pressure - Low S

R M

1, 2, 3 c.

Automatic Actuation Logic NA NA MIU(5) 1, 2, 3 g

5.

CONTAINMENT SUMP RECIRCULATION (RAS)

't' a.

Manual RAS (Trip Buttons)

NA NA R

NA 8

b.

Refueling Water Tank - Low NA R

yI 1, 2, 3 M) 1, 2, 3

~

c.

Automatic Actuation Logic NA NA 6.

CONTAINMENT PURGE VALVES ISOLATION a.

Manual (Purge Valve Control NA NA R

NA Switches) b.

Containment Radiation - High Area S

R H

6**

pg Monitor a

.if M

?

.-.,e..a c.-. -

w r

u~

-....--e.-.

3---.

r,c.

+r--

.e-s-es e

g TABLE 4.3-2 (Continued)

R G

g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS w

n

=

C CHANNEL MODES IN WHICH k'"

q CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED n

C 7.

LOSS OF POWER y

=

a.

4.16 kv Emergency Bus Undervoltage NA R

H 1, 2, 3 (Loss of Voltage) b.

4.16 kv Emergency Bus Undervoltage NA R

H 1,2,3 (Degraded Voltage) 8.

CVCS ISOLATION R

West Penetration Room / Letdown NA R

H 1, 2, 3, 4 Y

Heat Exchanger Room Pressure - High 9.

AUXILIARY FEEDWATER a.

Manual (Trip Buttons)

NA NA R

NA b.

Steam Generator Level - Low S

R H

1,2,3 1, 2, 3 c.

Steam Generator AP - High S

R Mg) d.

Automatic Actuation Logic NA NA 1, 2, 3 N

a 8-an m

a...-

m 2

r-rw

3/4.3 INSTRUMENTATION TABLE 4.3-2 (Continued)

TABLE NOTATION Containment isolation of non-essential penetrations is also initiated by SIAS (functional units 1.a and 1.c).

Must be OPERABLE only in MODE 6 when the valves are required OPERABLE and they are open.

(1)

The logic circuits shall be tested manually at least once per 31 days.

(2)=

SIAS logic circuits A-10 and B-10 shall be tested monthly with the exception of the Safety Injection Tank isolation valves. The SIAS logic circuits for these valves are exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.

(3)

SIAS logic circuits A-5, and B-5 are exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.

(4)

CIS logic circuits A-5 and B-5 are exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.

(5)

SGIS logic circuits A-1 and B-1 are exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.

(6)

CSAS logic circuits A-3 and B-3 are exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.

Monthly tests not required on A-10 and B-10 until EDG logic circuit modifications completed. Modifications to be completed during or before Unit 1 Refueling Outage Number 10.

CALVERT CLIFFS - UNIT 1 3/4 3-22 Amendment No. 184 l

3/4.3 INSTRUMENTATION.

f 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitorina Instrumentation LIMITING CONDITION FOR OPERATION l

3.3.3.1 The radiation monitoring instrumentation channels shown in-l Table 3.3-6 shall be OPERABLE with their alarm / trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

i a.

With a radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint 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 inoperable.

b.

With one or more radiation monitoring channels inoperable, take J

the ACTION shown in Table 3.3-6.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST, operations during the MODES and at the frequencies shown in Table 4.3-3.

i i

CALVERT CLIFFS - UNIT 1 3/4 3-23 Amendment No. 184 l

g TABLE 3.3-6 g

G g

RADIATION MONITORING INSTRUMENTATION w

b MINIMUM q

CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT g-INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION e-1.

AREA MONITORS m

5 d

[

a.

Containment E

i.

Purge & Exhaust Isolation 3

6 5 220 mr/hr 10 10* mr/hr 16 b.

Containment Area High Range 2

1, 2, 3, & 4 5 10 R/hr 1 - 10 R/hr 30 8

2.

PROCESS MONITORS R

a.

Containment Y'2 1.

Gaseous Activity a)

RCS Leakage Detection 1

1, 2, 3, & 4 Not 10' - 10' cpm 14 Applicable ii. Particulate Activity 5

a)

RCS Leakage Detection 1

1. 2, 3, & 4 Not 10 - 10' cpm 14 g

Applicable g

b.

Noble Gas Effluent Monitors

~

1.

Main Vent Wide Range 1

1, 2, 3, & 4 10-' to 105 Ci/cc 30' y

11. Main Steam Header 2

1, 2, 3, & 4 10-8 to 10 R/hr -

30 5

i l

l

- - - ~

. -... - - - - -.. -. ~.

-=

3/4.3 INSTRUMENTATION i

TABLE 3.3-6 (Continued)

TABLE NOTATION Alarm setpoint to be specified in a controlled document i

(e.g., setpoint control manual).

i ACTION STATEMENTS ACTION 14 -

With the number of channels OPERABLE less than required by

'the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

j ACTION 16 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 30 -

With the nunber of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, initiate the preplanned alternate method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) either restore the inoperable channel (s) to OPERABLE' status within 7 days of the event, or 2) prepare and submit a Special Report to the Commission pursuant to ' Specification 6.9.2 within -30 days following the event, outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to CPERABLE status, i

l CALVERT CLIFFS - UNIT 1 3/4 3-25 Amendment No. 184 l

g TABLE 4.3-3 R

u-RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

'w b

CHANNEL MODES IN WHICH q

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REQUIRED k

c-1.

AREA MONITORS 5

[

a.

Containment E

i. Purge & Exhaust Isolation S

R M

6 b.

Containment Area High Range S

R M

1, 2, 3, & 4 2.

PROCESS MONITORS R

a.

Containment Y

Z

i. Gaseous Activity a)

RCS Leakage Detection S

R H

1, 2, 3, & 4 ii. Particulate Activity a)

RCS Leakage Detection S

R H

1, 2, J. & 4 k

b.

Noble Gas Effluent Monitors E

1.

Main Vent Wide Range S

R H

1, 2, 3, & 4 2

11. Main Steam Header S

R H

1, 2, 3, & 4 M.

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Incore Detectors LIMITING CONDITION FOR OPERATION 3.3.3.2 The Incore Detection System shall be OPERABLE with at least one OPERABLE detector segment in each core quadrant on each of the four axial elevations containing incore detectors and as further specified below:

a.

For monitoring the AZIMUTHAL POWER TILT:'

At least two quadrant symmetric incore detector segment groups at each of the four axial elevations containing incore detectors in the outer 184 fuel assemblies with sufficient OPERABLE detector l

segments in these detector groups to compute at least two AZIMUTHAL POWER TILT values at each of the four axial elevations containing incore detectors.

b.

For recalibration of the Excore Neutron Flux Detector System:

1.

At least 75%" of all incore detector segments, 2.

A minimum of 9 OPERABLE incore detector segments at each detector segment level, and 3.

A minimum of 2 OPERABLE detector segments in the inner 109 fuel assemblies and 2 OPERABLE segments in the outer 108 fuel assemblies at each segment level.

c.

For monitoring the UNRODDED PLANAR RADIAL PEAKING FACTOR, the UNRODDED INTEGRATED RADIAL PEAKING FACTOR, or the linear heat rate:

For Unit 1 Cycle 11 only, the following requirements shall be substituted for Limiting Condition for Operation 3.3.3.2.a:

l i

At least eight quadrant symetric incore detector segment groups containing incore detectors in the outer 184 fuel assemblies with sufficient OPERABLE detector segments in these detector groups to compute at least one AZIMUTHAL POWER TILT value at each of the four axial elevations containing incore detectors and at least two AZIMUTHAL POWER TILT values at three axial elevations containing incore detectors.

For Unit 1 Cycle 11 only, the following requirement shall be substituted for Limiting Condition for Operation 3.3.3.2.b.1:

At least 60% of all incore detector segments, CALVERT CLIFFS - UNIT 1 3/4 3-27 Amendment No. 184 l

3/4.3 INSTRUMENTATION LIMITING CONDITION FOR OPERATION (Continued) 1.

At least 75%*** of all incore detector locations, 2.

A minimum of 9 OPERABLE incore detector segments at each detector segment level, and.

3.

A minimum of 2 OPERABLE detector segments in the inner 109 fuel assemblies and 2 OPERABLE segments in the outer 108 fuel assemblies at each segment level. An OPERABLE incore detector segment shall consist of an OPERABLE rhodium detector constituting one of the segments in a fixed detector string.An OPERABLE incore detector location shall consist of a string in which at least three of the four incore detector segments are OPERABLE.

An OPERABLE quadrant symmetric incore detector segment group shall consist of a minimum of three OPERABLE rhodium incore detector segments in 90 symetric fuel assemblies.

APPLICABILITY: When the Incore Detection System is used for:

a.

Monitoring the AZIMUTHAL POWER TILT, b.

Recalibration of the Excore Neutron Flux Detection System, or c.

Monitoring the UNR0DDED PLANAR RADIAL PEAKING FACTOR,'the UNR0DDED INTEGRATED RADIAL PEAKING FACTOR, or the linear heat rate.

ACTION: With the Incore Detection System inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

For Unit 1 Cycle 11 only, the following requirement shall be substituted for Limiting Condition for Operation 3.3.3.2.c.1:

At least 60% of all incore detector locations, CALVERT CLIFFS - UNIT 1 3/4 3-28 Amendment No. 184 l

i i

3/4.3 INSTRUMENTATION

~

SURVEILLANCE REQUIREMENTS 4.3.3.2 The Incore Detection System shall be demonstrated OPERABLE:

a.

By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to its' l

use and at least once per 7 days thereafter when required for:

-l 1.

Monitoring the AZIMUTHAL POWER TILT.

2.

Recalibration of the Excore-Neutron Flux Detection System.

3.

Monitoring the UNRODDED PLANAR RADIAL PEAKING FACTOR, the y

UNRODDED INTEGRATED RADIAL PEAKING FACTOR, or the linear heat

=

l' rate.

'l b.

At least once per REFUELING INTERVAL by performance of a CHANNEL

{

CALIBRATION operation which exempts the neutron detectors but includes all electronic components. The neutron detectors shall i

be calibrated prior to installation in the reactor core.

h i

l l

l i

i l

i I

(

CALVERT CLIFFS - UNIT 1 3/4 3-29 Amendment No. 184 l-l o

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Seismic Instrumentation LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a.

With one or more seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Comission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-4.

4.3.3.3.2 Each of the above seismic monitoring instruments actuated during a seismic event shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CALIBRATION perfomed within 5 days following the seismic event.

Data shall be retrieved from actuated instruments and analyzed to detemine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Comission pursuant to Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum and resultant effect upon facility features important to safety.

CALVERT CLIFFS - UNIT 1 3/4 3-30 Amendment No. 184 l

i L

3/4.3~ INSTRUMENTATION TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION MINIMUM MEASUREMENT INSTRUMENT INSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE 1.

Triaxial Time-History Strong Motion Accelographs i

a.

0-YE-001 Unit 1 Containment Base 0-1g 1

b.

0-YE-002 Unit 1 Containment 69' 0-Ig 1

c.

0-YE-003 Auxiliary Bldg. Base 0-1g 1

)

d.

0-YE-004 Intake Structure 0-19 1

e.

0-YE-005 Free Field 0-1g 1

2.

Triaxial Seismic Switches a.

0-YS-001 Unit 1 Containment Base NA 1

b.

0-YS-002 Unit 1 Containment 69' NA 1

l 3.

Seismic Acceleration Recorder a.

0-YRC-001 Control Room NA 1

b.

0-YR-001 Control Room NA 1

P h

t CALVERT CLIFFS - UNIT 1 3/4 3-31 Amendment No. 184 l

~

3/4.3 INSTRUMENTATION TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL CHANNEL FUNCTIONAL INSTRUMENTS AND SENSOR LOCATIONS CHECK" CALIBRATION TEST 1.

Triaxial Time-History Strong Motion Accelographs a.

0-YE-001 Unit 1 M*

R SA Containment Base b.

0-YE-002 Unit 1 M*

R SA Containment 69' c.

0-YE-003 Auxiliary Bldg.

M*

R SA Base d.

0-YE-004 Intake Structure M*

R SA e.

0-YE-005 Free Field M*

R SA 2.

Triaxial Seismic Switches a.

0-YS-001 Unit 1 M

R SA Containment Base b.

0-YS-002 Unit 1 M

R SA Containment 69' 3.

Seismic Acceleration Recorder a.

0-YRC-001 Control Room M

R SA b.

0-YR-001 Control Room M

R SA Verify instrument energized.

Except seismic trigger.

CALVERT CLIFFS - UNIT 1 3/4 3-32 Amendment No. 184 l

i 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Meteorological Instrumentation 1

LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a.

With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Comission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status, i

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

1 SURVEILLANCE REQUIREMENTS l

4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL

)

CHECK and CHANNEL CALIBRATION operations at the frequencies shown in i

Table 4.3-5.

)

CALVERT CLIFFS - UNIT 1 3/4 3-33 Amendment No. 184 l

f 3/4.3 INSTRUMENTATION l

TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION l

MINIMUM CNANNELS INSTRUMENT

-OPERABLE 1.

WIND SPEED a.

Nominal Elev.10M 1

b.

Nominal Elev. 60M 1

j 2.

WIND DIRECTION a.

Nominal Elev.10M 1

b.

Nominal Elev. 60M 1

3.

AIR TEMPERATURE - DELTA T (10M-60M) 1 it i

l CALVERT CLIFFS - UNIT 1 3/4 3-34 Amendment No. 184 l

1

l 3/4.3 INSTRUMENTATION TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l

CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.

WIND SPEED a.

Nominal Elev.10M D

SA b.

Nominal Elev. 60M D

SA 2.

WIND DIRECTION a.

Nominal Eley. 10M D

SA b.

Nominal Elev. 60M D

SA 3.

AIR TEMPERATURE - DELTA T (10M-60M)

D SA CALVERT CLIFFS - UNIT 1 3/4 3-35 Amendment No. 184 l

i 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Remote Shutdown Instrumentation l

LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the Control Room.

l APPLICABILITY: MODES 1, 2 and 3.

s r

ACTION:

a.

With the number of OPERABLE remote shutdown monitoring channels less than required by Table 3.3-9, either restore the inoperable channel to 0PERABLE status within 30 days, or be in NOT SNUTDOWN

-within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.5 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CNECK and CHANNEL l

CALIBRATION operations at the frequencies shown in Table 4.3-6.

i I

i

)

i i

CALVERT CLIFFS - UNIT 1 3/4 3-36 Amendment No. 184 l

g TABLE 3,3-9 R

G g

REMOTE SHUTDOWN MONITORING INSTRUMENTATION w

b MINIMUM A

READOUT MEASUREMENT CHANNELS E

INSTRUMENT LOCATION RANGE OPERABLE i!j h

m:

1.

Wide Range Neutron Flux IC43*

0.1 cps-200% power

1*

Z 2.

Reactor Trip Breaker Indication Cable Spreading OPEN-CLOSE 1/ trip breaker j

Room 3.

Reactor Coolant Cold Leg IC43 212-705 F 1

Temperature 4.

Pressurizer Pressure IC43 0-4000 psia 1

g 5.

Pressurizer Level 1C43 0-360 inches 1

6.

Steam Generator Pressure IC43 0-1200 psig 1/ steam generator m

b 7.

Steam Generator Level 1C43 401 to +63.5 inches 1/ steam generator N

@e z

?

When the IC43 instrumentation is inoperable, the wide range neutron flux monitors located in the auxiliary feedwater pump room may be utilized to meet this requirement. During the period when E

the instruments are utilized to meet the above requirement, they will be subject to the surveillance requirements of Table 4.3-6.

m w

a s

- m m

t 3/4.3 INSTRUMENTATION TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS i

t CNANNEL CNANNEL i

INSTRUMENT CHECK CALIBRATION 1.

Wide Range Neutron Flux M

NA 2.

Reactor Trip Breaker Indication M

NA 3.

Reactor Coolant Cold Leg. Temperature M

R 4.

Pressurizer Pressure M

R 5.

Pressurizer Level M

R i

6.

Steam Generator Level (Wide Range)

M R

7.

Steam Generator Pressure M

R i

l CALVERT CLIFFS - UNIT 1 3/4 3-38 Amendment No. 184 l

-.~

I 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Post-Accident Instrumentation LIMITING CONDITION FOR OPERATION

(*

3.3.3.6 The post-accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

i APPLICABILITY: MODES 1, 2 and 3.

j ACTION:

a.

As shown in Table 3.3-10.

b.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS l

l 4.3.3.6 Each post-accident monitoring instrumentation channel shall be demonstrated OPERABLE by perfomance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-10.

~?

l l

i 1

i CALVERT CLIFFS - UNIT 1 3/4 3-39 Amendment No. 184 l

g TABLE 3.3-10 R

G g

POST-ACCIDENT MONITORING INSTRUMENTATION

-e b

MINIMUM q

CNANNELS INSTRUMENT OPERABLE ACTION k

1.

Containment Pressure 2

31 g

Z 2.

Wide Range Logarithmic Neutron Flux Monitor 2

31 y

3.

Reactor Coolant Outlet Temperature 2

31 4.

Pressurizer Pressure 2

31 5.

Pressurizer Level 2

31 6.

Steam Generator Pressure 2/ steam generator 31 m

7.

Steam Generator Level (Wide Range) 2/ steam generator 31 g

8.

Auxiliary Feedwater Flow Rate 2/ steam generator 31 9.

RCS Subcooled Margin Monitor 1

31

10. PORV/ Safety Valve Acoustic Flow Monitoring 1/ valve 31

11. PORY Solenoid Power Indication 1/ valve 31

12. Feedwater Flow 2

31 k

13. Containment Water Level (Wide Range) 2 32, 33 g

14. Reactor Vessel Water Level 2*

34, 35 5

15. Core Exit Themocouple System 2 locations / core quadrant 31 E'

h A channel has eight sensors in a probe'. A channel is OPERA 8LE if four or more sensors, one or 2

more in the upper three and three or more in the lower five, are OPERA 8LE.

m

~ ---m

.am e

w

+

_pr-w-e.-

--e e-m<-

3/4.3 INSTRUMENTATION l

TABLE 3.3-10 (Continued)

ACTION STATEMENTS 1

ACTION 31 -

With the number of OPERABLE post-accident monitoring channels less than required by Table 3.3-10, either restore the inoperable channel to OPERABLE status within 30 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 32 -

With the number of OPERABLE post-accident monitoring l

channels one less than the Minimum Channels OPERABLE requirement in Table 3.3-10, operation may proceed provided I

the inoperable channel is restored to OPERABLE status at the next outage of sufficient duration.

ACTION 33 -

With the number of OPERABLE post-accident monitoring channels two less than required by Table 3.3-10, either restore one inoperable channel to OPERABLE status within l

30 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 34 -

With the number of OPERABLE post-accident monitoring channels one less than the Minimum Channels OPERABLE requirement in Table 3.3-10, either restore the system to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report i

to the Commission pursuant to Specification 6.P ' within 30 days following the event, outlining the act.,n caken, the cause of the inoperability and the plans and senedule for restoring the system to OPERABLE status.

l ACTION 35 -

With the number of OPEP.ABLE channels two less than required by Table 3.3-10, either restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months if repairs are feasible without shutting down or:

1.

Initiate an alternate method of monitoring for core and Reactor Coolant System voiding; 2.

Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and 3.

Restore the system to OPERABLE status at the next scheduled refueling.

CALVERT CLIFFS - UNIT 1 3/4 3-41 Amendment No. 184 I

g TABLE 4.3-10 w

G P

POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w

g b

CHANNEL CHANNEL

]

INSTRUMENT CHECK CALIBRATION E

1.

Containment Pressure M

R g

E 2.

Wide Range Logarithmic Neutron Flux Monitor M

NA

[

3.

Reactor Coolant Outlet Temperature M

R E

4.

Pressurizer Pressure M

R 5.

Pressurizer Level M

R 6.

Steam Generator Pressure M

R g

7.

Steam Generator Level (Wide Range)

M R

8.

Auxiliary Feedwater Flow Rate M

R w

0 9.

RCS Subcooled Margin Monitor M

R

10. PORV/ Safety Valve Acoustic Monitor NA R

11. PORV Solenoid Power Indication NA NA

12. Feedwater Flow M

R

13. Containment Water Level (Wide Range)

M R

g

14. Reactor Vessel Water level M

NA o.

8

15. Core Exit Thermocouple System M

R*

A E

b The perfonnance of a CHANNEL CALIBRATION operation exempts the Core Exit Thermocouple but T

includes all electronic components. The Core Exit Themocouple shall be calibrated prior to installation in the reactor core.

m v

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Fire Detection Instrumentation LIMITING CONDITION FOR OPERATION 3.3.3.7 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY: Whenever equipment in that fire detection zone is required to be OPERABLE.

ACTION: With one or more of the fire detection instrument (s) shown in Table 3.3-11 inoperable:

a.

Within I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect the containment at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least.once per hour at the locations listed in Specification 4.6.1.5; or unless the instrument (s) is located in fire detection zones equipped with automatic wet pipe sprinkler systems alarmed and supervised to the Control Room, then within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, inspect the zone (s) with inoperable instruments and verify that the Automatic Sprinkler System, including the water flow alarm and supervisory system, is OPERABLE by CNANNEL FUNCTIONAL TEST.

b.

Restore the inoperable instrument (s) to OPERABLE status within I

14 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining 1

the action taken, the cause of the inoperability and the plans' and schedule for restoring the instrument (s) to 0PERABLE status.

r c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

[

SURVEILLANCE REQUIREMENTS 4.3.3.7.1 At least once per 6 months, at least 25% of the above required fire detection. instruments which are accessible during plant operation shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST.

Detectors selected for testing shall be selected on a rotating basis such I

i CALVERT CLIFFS - UNIT 1 3/4 3-43 Amendment No. 184 l

i

3/4.3 INSTRUMENTATION SURVEILLANCEREQUIREMENTS-(Continued) that all detectors will be tested over a two year period.- If in any detection zone there are less than four detectors, at-least one different detector in that zone shall be tested every six months.

For each detector found inoperable during functional testing, at least an additional 10% of all detectors or 10 detectors, whichever is less, shall also be tested.

i Fire detectors which are inaccessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST 1

during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed during the previous six months.

j 4.3.3.7.2 The NFPA Code 72D Class B supervised circuits supervision associated with the detector alarms of each'of the above required fire detection instruments shall be demonstrated OPERABLE at least'once per-6 months.

4.3.3.7.3 The non-supervised circuits, associated with detector alarms, between the instrument and the Control Room shall be demonstrated OPERABLE at least once per 31 days.

l

+

d CALVERT CLIFFS - UNIT 1 3/4 3-44 Amendment No. 184 l

m _

i 3/4.3 INSTRUMENTATION l

TABLE 3.3-11 i

i FIRE DETECTION INSTRUMENTS UNIT 1 MINIMUM INSTRUMENTS OPERABLE

ROON/ AREA AUX BLDG.

INSTRUMENT LOCATION HEAT FLAME SM0KE 100/103/

104/116 Corridors - Elev (-)10"-0" 5

l 110 Coolant Waste Rec.& Mon. Tk 2

Pp Rm 111 Waste Processing Control Rm 1

112/114 Coolant Waste Rec Tank 4

113 Misc. Waste Receiver Tank 1

Room 115 Charging Pump Room 3

~

118/122 ECCS Pump Room 7

119/123 ECCS Pump Room 7

200/202 Corridors, &

209/210 Corridors &

212/219 Corridors 13 207/208 Waste Gas Equip Rm 3

216 Reactor Coolant Make-up Pumps 1

217 Boric Acid Tank & Pump Room 2

218 Volume Control Tank Room 1

220 Degasifier Pump Room 1

221/326 West Piping Penetration Room 2

3 j

222 Hot Instrument Shop 2

223 Hot Machine Shop 4

224 East Piping Area 10 i

225 Rad Exhaust Vent Equip Rm 4

226 Service Water Pump Rm 3

6 227/316 East Piping Penetration Rm 3

5 228 Component Cooling Pump Rm 8

301/304/300 Battery Room & Corridor 3

l Detection instruments located within the containment are not required to be OPERABLE during the performance of Type A Containment Leakage i

Rste Tests.

i i

CALVERT CLIFFS - UNIT 1 3/4 3-45 Amendment No. 184 l

)

l 3/4.3 INSTRUMENTATION i

l TABLE 3.3-11 (Continued)

FIRE DETECTION INSTRUMENTS UNIT 1 i

MINIMUM INSTRUMENTS ~

OPERABLE

l ROOM / AREA AUX BLDG.

INSTRUMENT LOCATION HEAT FLAME SM0KE 306/1C Cable Sp, reading Rm & Cable Chase 2-10 308 N/S Corridor 6

315 Main Steam Piping Area 6

i 317 Switchgear Room, Elev 27 '-0""

6 l

318 Purge Air Supply Room 2

319/325 West Passage and Vestibule 6

t 320 Spent Fuel Heat Exchanger Room 3

323 Passage 27' Valve Alley &

Filter Rm.

3 324 Letdown Heat Exchanger Rm 1

l Elev. 27'-0" Switchgear Vent Duct 1

j IA Cable Chase 1A 1

IB Cable Chase IB 1

405 Control Room 6

i 410 N/S Corridor 4

417/418 Solid Waste Processing 2

3 413/419/420 Cask and Equip Loading Area &

424/425/426 Cask and Equip Loading A p,a 3

22 421 Diesel Generator No. (12,,

2 422 Diesel Generator No. (11 2

423 West Electrical Pen Rm 3

428 East Piping Area 7

429 East Electrical Pen Rm

'3 l

430 Switchgep,r Room Elev 45'-0" 8

439 Refueling Water Tank Pump Rm 2

441 Spent Resin Metering Tank Rm 1

Elev 45'-0" Switchgear Vent Duct I

Detection instruments located within the containment are not required i

~

to be OPERABLE during the perfomance of Type A Containment Leakage Rate Tests.

Detectors which automatically actuate Fire Suppression Systems.

1 CALVERT CLIFFS - UNIT 1 3/4 3-46 Amendment No. 184 l

l

-I

3/4.3 INSTRUMENTATION TABLE 3.3-11 (Continued)

FIRE DETECTION INSTRUMENTS UNIT 1 MINIMUM INSTRUMENTS OPERABLE

ROOM / AREA AUX BLDG.

INSTRUMENT LOCATION HEAT FLAME SMOKE Elev 69'-0" Control Room Vent Duct "A" 1

Elev 69'-0" Cable Spreading Room Vent 1

Duct 512 Control Room HVAC Equipment 4

586/588/589/590 Radiation Chemistry Area, 592/593 Radiation Chemistry Area, 595/596/597 Radiation Chemistry Area, 587 Frisker Area, 591 Clothing Disposal, and 523/594 Corridors 20 520 Spent Fuel Pool Area Vent

uip Rm 2

524 Main Plant Exhaust Equip Rm 8

525 Cntmt Access Area 3

529 Electrical Equip. Room 3

530/531/533 Spent Fuel Pool Area 5

17 536/537 Misc Waste Evaporator & Equip Rm 3

Elev 83'-0" Cable Tunnel 4

603 Auxiliary Feedwater Pump Rm 2

Containment Bldo.

U-1 RCP Bay East

16 U-1 RCP Bay West

J"6 U-1 East Electric Pen Area" U-1 West Electric Pen Area Intake Structure Elev 3'-0" Unit 1 Side 24 Detection instruments located within the containment are not required to be OPERABLE during the perfomance of Type A Containment Leakage Rate Tests.

Monitored by four protecto wires.

CALVERT CLIFFS - UNIT 1 3/4 3-47 Amendment No. 184 l

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radioactive Gaseous Effluent Monitorina Instrumentation LIMITING CONDITION FOR OPERATION I

3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alam/ trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alam/ trip setpoints of these channels shall be detemined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3-12.

ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alam/ trip setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by perfomance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION dnd CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-11.

CALVERT CLIFFS - UNIT 1 3/4 3-48 Amendment No. 184 l

g TABLE 3.3-12 R

G g

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION U

b MINIMUM CHANNELS

]

INSTRUMENT OPERABLE APPLICABILITY ACTION E

1.

WASTE GAS HOLDUP SYSTEM g

c 5

a.

Noble Gas Activity Monitor - Providing 1

35 d

Alarm and Automatic Temination of E

Release b.

Effluent System Flow Rate Measuring 1

36 Device 2.

MAIN VENT SYSTEM a.

Noble Gas Activity Monitor 1

37

't' O

b.

Iodine Sampler 1

38 c.

Particulate Sampler 1

38 N

a n

rt E

l e

3/4.3 INSTRUMENTATION TABLE 3.3-12 (Continued)

TABLE NOTATION At all times.

ACTION STATEMENTS ACTION 35 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment:

a.

Using the main vent monitor as a backup and recording RMS readings every 15 minutes during the release, or b.

Provided that prior to initiating the release, at least two independent samples of the tank's contents are analyzed, and at least two technically qualified members of the Facility Staff independently verify the release rate calculations and two qualified operators verify the discharge valve lineup.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 37 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided either (1) grab samples are taken and analyzed for gross activity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or (2) an equivalent monitor is provided.

ACTION 38 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected as required in Table 4.11-2 with auxiliary sampling equipment.

CALVERT CLIFFS - UNIT 1 3/4 3-50 Amendment No. 184 l

i g

TABLE 4.3-11 M

G RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS g

b MODES IN h

y CHANNEL WNICH g

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE m

INSTRUMENT CNECK CNECK CALIBRATION TEST REQUIRED 5

C D

5 2

[

1.

WASTE GAS HOLDUP SYSTEM E

R)

SAW I3 a.

Noble Gas Activity Monitor -

P P

Providing Alarm and Automatic Tennination of Release b.

Effluent System Flow Rate DN NA R

NA r

my Measuring Device 2.

MAIN VENT SYSTEM u,

a.

Noble Gas Activity Monitor D

M RW SAW b.

Iodine Sampler W

NA NA NA c.

Particulate Sampler W

NA NA NA N

a g

E l

3/4.3 INSTRUMENTATION TABLE 4.3-11 (Continued)

TABLE NOTATION At all times other than when the line is valved out and locked.

III The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolation of this pathway and/or Control Room alarm annunciation occurs if the appropriate following condition (s) exists:

1.

Instrument indicates measure levels above the alarm / trip setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

(2)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

(3)

The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system within its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration can be used.

i The CHANNEL CHECK shall consist of verifying indication of flow I4) during periods of release and shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which effluent releases are made.

i CALVERT CLIFFS - UNIT 1 3/4 3-52 Amendment No. 184 l

l

= _ _ _. -_. _

4 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radioactive Licuid Effluent Monitorino Instrumentation LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alam/ trip.

setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the 0FFSITE DOSE CALCULATION MANUAL (0DCM).

APPLICABILITY: At all times.

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel alam/ trip setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

Exert best efforts to' return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the'inoperability_was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

. SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12.

CALVERT CLIFFS - UNIT 1 3/4 3-53 Amendment No. 184 l

3/4.3 INSTRUMENTATION TABLE 3.3-13 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION' 1.

GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.

Liquid Radwaste Effluent Line 1

28 b.

Steam Generator Blowdown Effluent 1

29 Line 2.

FLOW RATE MEASUREMENT DEVICES a.

Liquid Radwaste Effluent Line 1

30 b.

Steam Generator Blowdown Effluent 1

30 Line 9

1 CALVERT CLIFFS - UNIT 1 3/4 3-54 Amendment No. 184 l

3/4.3 INSTRUMENTATION TABLE 3,3-13 (Continued)

ACTION STATEHENTS ACTION 28 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

a.

At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and two qualified operators verify the discharge valve line up.

ACTION 29 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gama) at the lower limit of detection defined in Table 4.11-1:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131.

b.

At least once per 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT I-131.

ACTION 30 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

Pump performance curves may be used to estimate flow.

l CALVERT CLIFFS - UNIT 1 3/4 3-55 Amendment No. 184 l

g TABLE 4.3-12 R

r-

=

RADI0 ACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS U

b CHANNEL q

CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST k

b 1.

GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM h

]

AND AUTOMATIC TERMINATION OF RELEASE y

R)

SA )

I2 U

~

a.

Liquid Radwaste Effluent Line D

P R)

SA )

I2 U

b.

Steam Generator Blowdown Effluent Line D

P 2.

FLOW RATE MEASUREMENT DEVICES M

a.

Liquid Radwaste Effluent Line D(3)

NA R

NA h

b.

Steam Generator Blowdown Effluent Line D(3)

NA R

NA

s n

r+

EF i

l

3/4.3 INSTRUNENTATION i

TABLE 4.3-12 (Continued)

{

TABLE NOTATION (1)

The CHANNEL FUNCTIONAL TEST sha?1 also demonstrate that automatic isolation of this pathway and/or Control Room alam annunciation

}

occur if the appropriate following condition (s) exists:

l 1.

Instrument indicates measured levels above the alam/ trip setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

(2)

The initial CHANNEL CALIBRATION shall be performed using one or more l

o' reference standards traceable to the National Bureau of S

Js or using standards that have been obtained from suppliers ti..,.articipate in measurement assurance activities with NBS. These l

standards shall permit calibrating the system within its intended range of energy and measurement range.

For subsequent CHANNEL l

CALIBRATION, sources that have been related to the initial calibration can be used.

j (3)

CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per "ours on days on which effluent releases are made.

l t

h i

i i

l l

i CALVERT CLIFFS - UNIT 1 3/4 3-57 Amendment No. 184 l

5

3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF)

INSTRUMENTATION The OPERABILITY of the protective and ESF instrumentation systems and bypasses ensure that 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint, 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to pemit a channel to be out of service for testing or maintenance, and 4) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests perfomed at i

the minimum frequencies are sufficient to demonstrate this capability.

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident 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. The response time limits are contained in UFSAR Chapter 7, and updated in accordance with 10 CFR 50.71(e).

3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitoring Instrumentation The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.

CALVERT CLIFFS - UNIT 1 B 3/4 3-1 Amendment No. 184

l TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION 3/4 3-1 l

3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM I

INSTRUMENTATION..................

3/4 3-9 l

i 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-23 Incore Detectors 3/4 3-27 Seismic Instrumentation..............

3/4 3-30 Meteorological Instrumentation 3/4 3-33 Remote Shutdown Instrumentation..........

3/4 3-36 Post-Accident Instrumentation...........

3/4 3-39 Fire Detection Instrumentation 3/4 3-43 Radioactive Gaseous Effluent Monitoring Instrumentation..................

3/4 3-47 l

Radioactive Liquid Effluent Monitoring Instrumentation..................

3/4 3-52 l

l 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION STARTUP and POWER OPERATION............

3/4 4-1 HOT STANDBY....................

3/4 4-2 Shutdown 3/4 4-4 3/4.4.2 SAFETY VALVES...................

3/4 4-6 3/4.4.3 RELIEF VALVES...................

3/4 4-7 3/4.4.4 PRESSURIZER....................

3/4 4-8 3/4.4.5 STEAM GENERATORS 3/4 4-9 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE l

Leakage Detection Systems.............

3/4 4-16 Reactor Coolant System Leakage 3/4 4-18 3/4.4.7 CHEMISTRY.....................

3/4 4-20 i

3/4.4.8 SPECIFIC ACTIVITY.................

3/4 4-23 i

l CALVERT CLIFFS - UNIT 2 IV Amendment No. 161

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1.1 As a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE.

l APPLICABILITY: As shown in Table 3.3-1.

4 ACTION: As shown in Table 3.3-1.

h SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each reactor protective instrumentation channel shall be demcastrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-1.

4.3.1.1.2 The logic for the bypasses shall be demonstrated CPERABLE prior to each reactor STARTUP unless performed during the preceding 92 days. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation.

4.3.1.1.} hall be demonstrated to be within its limit at least once per The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function s l

18 months.

Each test shall include at least one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.

I Neutron detectors are exempt from response time testing.

l CALVERT CLIFFS - UNIT 2 3/4 3-1 Amendment No. 161

I g

TABLE 4.3-1 R

i G

g REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS U

b CHANNEL MODES IN WHICH q

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED k.

h h

1.

Manual Reactor Trip NA NA S/U )

NA II Z

2.

Power Level - High j

ro a.

Nuclear Power S

D(2) g(3) 9(s)

M 1, 2 b.

AT Power S

D(*), R H

1 3.

Reactor Coolant Flow - Low S

R M

1, 2 g

4.

Pressurizer Pressure - High S

R H

1, 2 5.

Containment Pressure - High S

R H

1, 2 y

6.

Steam Generator Pressure - Low S

R H

1, 2 7.

Steam Generator Water Level -

S R

H 1, 2 Low 8.

Axial Flux Offset S

R M

1 9.

a.

Thennal Margin / Low Pressure S R

M 1, 2 N

g b.

Steam Generator Pressure S

R M

1, 2 g

Difference - High

' E.

10. Loss of Load NA NA S/UIll NA r

. g t

~m m

mm

.m-2

.. mm...i mmm-....

-.--m u

m m -

- -_,___m.__

mmwv.

w

-.-ae-

>e-v-w

,e

-oy e

e s,m,e.,

wwe-

-w w

,.p.e-,-mm-

i g

TABLE 4.3-1 (Continued) w G

P g

REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS' w

b CHANNEL MODES IN WHICH q

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED k

=

11. Wide Range Logarithmic Neutron Flux S

R(5)

S/UIll 1, 2 y

and, 3, 4 -5 y

c-Monitor

12. Reactor Protection System Logic NA NA M and S/UIll 1, 2

- to Matrices

13. Reactor Protection System Logic NA NA M and S/UIII 1, 2 Matrix Relays

14. Reactor Trip Breakers NA NA M

1, 2 and

w wb m

a F.

w-r-

~-r va- - -w- - - - -

,e 3

v

--r-m-

w

=-

-w#

e-

--w-w-e-

,--.-e-a-

- = -

a e--

-e 4,en

,.e.

,-*w

3/4.3 INSTRUMENTATION TABLE 4.3-1 (Continued)

TABLE NOTATION With reactor trip breakers in the closed position and the CEA drive -

system capable of CEA withdrawal.

(1)

If not performed in previous.7 days.

(2)

Heat balance only, above 15% of. RATED THERMAL POWER; adjust " Nuclear -

Power Calibrate" potentiometers to make the nuclear power signals agree with calorimetric calculation if absolute difference is > 1.5%.

During PHYSICS TESTS, these daily calibrations of nuclear power and AT power may be suspended provided these calibrations are perfonned upon reaching each major test power plateau and prior to proceeding

'4 to the next major test power plateau.

(3)

Above 15% of RATED THERMAL POWER, recalibrate the excore detectors which monitor the AXIAL SHAPE INDEX by using the incore detectors or i

restrict THERMAL POWER during subsequent operations to 5 90% of the maximum allowed THERMAL POWER level with the existing Reactor Coolant Pump combination.

4 (4)

Above 15% of RATED THERMAL POWER, adjust "AT Pwr Calibrate" potentiometers to null " Nuclear Pwr - AT.Pwr." During PHYSICS TESTS, these daily calibrations of nuclear power and AT power may be suspended provided these calibrations are performed upon reaching i

each major test power plateau and prior to proceeding to the next i

major test power plateau.

(5)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

t i

l

.l CALVERT CLIFFS - UNIT 2 3/4 3-8 Amendment No. 161 l

3/4.3 INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and bypasses shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.

l APPLICABILITY: As shown in Table 3.3-3.

ACTION:

a.

With an ESFAS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

SURVEILLANCE REQUIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the perfonnance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-2.

4.3.2.1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation.

The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation.

4.3.2.1.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.

Each test shall include at least one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.

CALVERT CLIFFS - UNIT 2 3/4 3-9 Amendment No. 161

f g

TABLE 3.3-3 R

j G

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION g

I b

MINIMUM h

k" 7

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION m:

c 1.

SAFETY INJECTION (SIAS)'

5!

5 d

]

a.

Manual (Trip Buttons) 2 1

2 1,2,3,4-6 E

b. -Containment Pressure - High 4

2 3

1,2,3 7*

c.

Pressurizer Pressure - Low 4

2 3

1, 2, 3(*)

7*

g 2.

CONTAINMENT SPRAY (CSAS) y a.

Manual (Trip Buttons) 2 1

2 1,2,3,4 6

o b.

Containment Pressure - High 4

2 3

1,2,3 11 3.

CONTAINMENT ISOLATION (CIS)#

a.

Manual CIS (Trip Buttons) 2 1

2 1,2,3,4 6

[

b.

Containment Pressure - High 4

2 3

1,2,3 7'

E 2a

.?

(>*

4

_v.,.,,

_._y

,,,w.

..,.n w..,._.,,..,

y

g TABLE 3.3-3 (Continued)

R G

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 5d g

HINIMUM E

n C

TOTAL NO.

CHANNELS CHANNELS APPLICABLE

'Q q

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION E

co x

4.

MAIN STEAM LINE ISOLATION Q

c-5 a.

Manual (MSIV Hand Switches 1/ valve 1/ valve 1/ valve 1,2,3,4 6

d and Feed Head Isolation E

Hand Switches) b.

Steam Generator Pressure -

4/ steam 2/ steam 3/ steam 1, 2, 3(')

7*

Low generator generator generator 5.

CONTAINMENT SUMP RECIRCULATION R.

(RAS)

Y a.

Manual RAS (Trip Buttons) 2 1

2 1,2,3,4 6

~

b.

Refueling Water Tank - Low 4

2 3

1,2,3 7*

S*

a an M

---__a-------___---________----,---------__-------___z-

g TABLE 3.3-3 (Continued)

R Gg ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION w

N MINIMUM E

C TOTAL NO.

CHANNELS CHANNELS APPLICABLE 4

7 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION E

<n x

6.

CONTAINMENT PURGE VALVES E

c-ISOLATION is!

i'i M

a.

Manual (Purge Valve Control 2/ Penetration 1/ Penetration 2/ Penetration 6**

8 E

Switches) b.

Containment Radiation - High Area Monitor 4

2 3

6**

8 R

7.

LOSS OF POWER a

'f a.

4.16 kv Emergency Bus 4/ Bus 2/ Bus 3/Bu';

1,2,3 7*

C Undervoltage (Loss of Voltage) b.

4.16 kv Emergency Bus 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 7*

Undervoltage (Degraded Voltage) 3' a

n E

h

g TABLE 3.3-3 (Continued)

R G

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION w

g 3

MINIMUM ji!

n C

TOTAL NO.

CHANNELS CHANNELS APPLICABLE Q

}

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION "E'

8.

CVCS ISOLATION j

i C

5 a.

Manual (CVCS Isolation d

[

Valve Control Switches) 1/ Valve 1/ Valve 1/ Valve 1,2,3,4 6

E b.

West Penetration Room / Letdown Heat Exchanger Room Pressure - High 4

2 3

1,2,3,4 7*

R 9.

AUXILIARY FEEDWATER ACTUATION SYSTEM (AFAS) w a.

Manual (Trip Buttons) 2 sets of 2 per 1 set of 2 2 sets of 2 1,2,3 6

S/G per S/G per S/G b.

Steam Generator Level - Low 4/SG 2/SG 3/SG 1, 2, 3 7

c.

Steam Generator AP High 4/SG 2/SG 3/SG 1, 2, 3 7

ia E

- - = -

pwt.-,r

-Y-w *g W

r'V' W

F

+

W'-

9' 8--wIV-"

"-d'ad--t*&#

v a

3

F-'*-

wwe'

+ e e-

-,,ea,g

-Psi

-m e,

-w 1

W

3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

TABLE NOTATION Containment isolation of non-essential penetrations is also initiated by SIAS (functional units 1.a and 1.c).

When the RCS temperature is:

fa) Greater than 350 F, the required OPERABLE HPSI pumps must be able-to start automatically upon receipt of a SIAS signal, i

(b) Between 350 F and 305 F, a transition region exists where the i

OPERABLE HPSI pump will be placed in pull-to-lock on a cooldown and restored to automatic status on a heatup.

(c) At 305 F and less, the required OPERABLE HPSI pump shall-be in pull-to-lock'and will not start automatically.

The provisions of Specification 3.0.4 are not applicable.

Must be OPERABLE only in MODE 6 when the valves are required OPERABLE and they are open.

(a)

Trip function may be bypassed in this MODE when pressurizer pressure is < 1800 psia; bypass shall be automatically removed when pressurizer pressure is > 1800 psia.

(c)

Trip function may be bypassed in this MODE below 785 psia; bypass shall be automatically removed at or above 785 psia.

3 r

CALVERT CLIFFS - UNIT 2 3/4 3-14 Amendment No. 161 l-

3/4.3 INSTRUMENTATION TABLE 3.3-3 (Continued)

ACTION STATEMENTS ACTION 6 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 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 7 With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in either the bypassed or tripped condition within I hour.

For the purposes of testing and maintenance, the inoperable channel may be bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months from time of initial loss of OPERABILITY; however, the inoperable channel shall then be either restored to OPERABLE status or placed in the I

tripped condition, b.

Within one hour, all functional units receiving an input from the inoperable channel are also placed in the same condition (either bypassed or tripped, as applicable) as that required by a. above for the inoperable channel.

c.

The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months while performing tests and maintenance on that channel provided the other inoperable channel is placed in the tripped condition.

ACTION 8 With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge valves are maintained closed.

ACTION 11 -

With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is demonstrated within I hour; one additional 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.

CALVERT CLIFFS - UNIT 2 3/4 3-15 Amendment No. 161 l

g TABLE 3.3-4 R

g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES w

w b

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES m

=

Q 1.

SAFETY INJECTION (SIAS)

E S

c-a.

Manual (Trip Buttons)

Not Applicable Not Applicable 5

d

[

b.

Containment Pressure - High 5 4.75 psig 5 4.75 psig E

c.

Pressurizer Pressure - Low 1 1725 psia 1 1725 psia 2.

CONTAINMENT SPRAY (CSAS) a.

Hanual (Trip Buttons)

Not Applicable Not Applicable R

b.

Containment Pressure - High 5 4.75 psig 5 4.75 psig w

cL 3.

CONTAINMENT ISOLATION (CIS)#

cn a.

Manual CIS (Trip Buttons)

Not Applicable Not Applicable b.

Containment Pressure - High 5 4.75 psig 5 4.75 psig 4.

MAIN STEAM LINE ISOLATION y

a.

Manual (MSIV Hand Switches and Not Applicable Not Applicable g

Feed Head Isolation Hand Switches)

&g b.

Steam Generator Pressure - Low 1 685 psia

.t 685 psia E.

g Containment isolation of non-essential penetrations is also initiated by SIAS (functional units 1.a and 1.c).

~

g TABLE 3.3-4 (Continued)

R G

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES w

b FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

~

m E

co 5.

CONTAINMENT SUMP RECIRCULATION (RAS) g i

C a.

Manual RAS (Trip Buttons)

Not Applicable Not Applicable

{

b.

Refueling Water Tank - Low 1 24 inches above tank i 24 inches above tank bottom bottom 6.

CONTAINMENT PUP.GE VALVES ISOLATION a.

Manual (Purge Valve Control Not Applicable Not Applicable R

Switches)

'f b.

Containment Radiation - High 5 220 mr/hr 5 220 mr/hr O

Area Monitor 7.

LOSS OF POWER a.

4.16 kv Emergency Bus Undervoltage 2450 1 105 volts with a 2450 1 105 volts with a (Loss of Voltage) 2 1 0.2 second time delay 2 1 0.2 second time delay b.

4.16 kv Emergency Bus Undervoltage 3628 1 25 volts with a 3628 1 25 volts with a 1

(

(Degraded Voltage) 8 1 0.4 second time delay 8 1 0.4 second time delay E

Ra af

l t

l l

9 R

i q

TABLE 3.3-4 (Continued) m w

N ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES m

?

5 N

FUNCTIONAL UNIT TRIP SETP0 INT ALLOWABLE VALUES t

b 8.

CVCS ISOLATION a

~5 d

West Penetration Room / Letdown Heat 5 0.5 psig 5 0.5 psig E

Exchanger Room Pressure - High 9.

AUXILIARY FEEDWATER ACTUATION SYSTEM (AFAS) a.

Manual (Trip Buttons)

Not Applicable Not Applicable h

b.

Steam Generator (A or B) Level -

-194" to -149"

-194" to -149" Low (inclusive)

(inclusive) c.

Steam Generator AP-High 5 130.0 psid 5 130.0 psid (SG-A > SG-B) d.

Steam Generator AP-High 5 130.0 psid 5 130.0 psid y

(SG-B > SG-A) a a.

a i

E i

, ~ _. _ _

t t

k g

TABLE 4.3-2 R

G g

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS U

w n

E C;

CHANNEL MODES IN WHICH 4

Q CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE g

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED m

5 c-1.

SAFETY INJECTION (SIAS) d 2

a.

Manual (Trip buttons)

NA NA R

NA b.

Containment Pressure - High S

R H

1,2,3 c.

Pressurizer Pressure - Low S

R M)g)(3) 1,2,3 U

d.-

Automatic Actuation -Logic NA NA 1, 2, 3 2.

CONTAINMENT. SPRAY (CSAS) t' a.

Manual (Trip buttons)

NA NA R

NA

?*

b.

Containment Pressure - High S

R H

1,2,3 3

c.

Automatic Actuation Logic NA NA M(UB) 1, 2, 3 3.

CONTAINMENT ISOLATION (CIS)'

I a.

Manual CIS-(Trip buttons)

NA NA R

NA b.-

Containment Pressure - High S

R M

1,2,3 c.

Automatic Actuation Logic NA NA M(U B) 1,2,3 T

E3 if M

i s

1,

s

..m 2

.- n

-m w

m

-m m

6 c

er w+w i

g TABLE 4.3-2 (Continued)

R G

f g

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS n

m:

C CHANNEL MODES IN WHICH

!Q q

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE E

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED M

2'i c-g 4.

MAIN STEAM LINE ISOLATION (SGIS) a.

Manual SGIS (MSIY Hand Switches NA NA R

NA and Feed Head Isolation Hand Switches) b.

Steam Generator Pressure - Low S

R M

1, 2, 3

'c. Automatic Actuation Logic NA NA M(U(9 1,2,3 g

5.

CONTAINMENT SUMP RECIRCULATION (RAS)

Y a.

Manual RAS (Trip Buttons)

NA NA R

NA b.

Refueling Water Tank - Low NA R

1,2,3 Ng) c.

Automatic Actuation Logic NA NA 1, 2, 3 6.

CONTAINMENT PURGE VALVES ISOLATION a.

Manual (Purge Valve Control NA NA R

NA Switches)

M 6**

b.

Containment Radiation - High 5

R k

Area Monitor E

R a

F M

I a

l

I l

l Q

TABLE 4.3-2 (Continued)

R G

g ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS w

b CHANNEL MODES IN WHICH I

A CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED s

C 5

7.

LOSS OF POWER d

E a.

4.16 kv Emergency Bus Undervoltage NA R

M 1,2,3 (Loss of Voltage) b.

4.16 kv Emergency Bus Undervoltage NA R

H 1,2,3 (Degraded Voltage) 8.

CVCS ISOLATION R

West Penetration Room / Letdown NA R

H 1, 2, 3, 4

%d Heat Exchanger Room Pressure - High 9.

AUXILIARY FEEDWATER a.- Manual (Trip Buttons)

NA NA R

NA b.

Steam Generator Level - Low S

R M

1, 2, 3 c.

Steam Generator AP - High S

R MgI 1, 2, 3 d.

Automatic Actuation Logic NA NA 1, 2, 3 Y

aa a

r+

E

=

- m. -

-auao---

m m-1 m

r

-e-e.

+-

-w-w r -sa 7--er---

-M-w t e

r-i Wv--V-

3/4.3 INSTRUMENTATION TABLE 4.3-2 (Continued)

TABLE NOTATION Containment isolation of non-essential penetrations is also initiated by SIAS (functional units 1.a and 1.c).

Must be OPERABLE only in MODE 6 when the valves are required OPERABLE and they are open.

(1)

The logic circuits shall be tested manually at least once per t

31 days.

(2)*

SIAS logic circuits A-10 and B-10 shall be tested monthly with the exception of the Safety Injection Tank isolation valves. The SIAS logic circuits for these valves are exempted from testing during i

operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.

(3)

SIAS logic circuits A-5 and B-5 are exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.

(4)

CIS logic circuits A-5 and B-5 are exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.

(5)

SGIS logic circuits A-1 and B-1 are exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.

(6)

CSAS logic circuits A-3 and B-3 are exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown.

i Monthly tests not required on A-10 and B-10 until EDG logic circuit modifications completed. Modifications to be completed during or before Unit 2 Refueling Outage Number 9.

CALVERT CLIFFS - UNIT 2 3/4 3-22 Amendment No. 161 l

i

-J

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitorino Instrumentation LIMITING CONDITION FOR OPERATION i

3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm / trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a.

With a radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint 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 inoperable.

b.

With one or more radiation monitoring channels inoperable, take the action shown in Table 3.3-6.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-3.

i CALVERT CLIFFS - UNIT 2 3/4 3-23 Amendment No. 161 l

g TABLE 3.3-6 r-RADIATION MONITORING INSTRUMENTATION n

MINIMUM E

C CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT

!Q

]

INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION E"

i 1.

AREA MONITORS c-g a.

Containment y

=

i. Purge & Exhaust Isolation 3

6 5 220 mr/hr 10 10' mr/hr 16 b.

Containment Area High Range 2

1, 2, 3, & 4 5 10 R/hr 1 - 10 R/hr 30 8

2.

PROCESS MONITORS y

a.

Containment

i. Gaseous Activity a)

RCS Leakage Detection 1

1, 2, 3, & 4 Not 10' - 10' cpm 14 Applicable

11. Particulate Activity a)

RCS Leakage Detection 1

1, 2, 3, & 4 Not 10' - 10' cpm 14 Applicable b.

Noble Gas Effluent _ Monitors

. g

(

1.

Main Vent Wide Ratige 1

1, 2, 3, & 4 10 to 10 pC1/cc 30 4

5 (D

A

11. Main Steam Header 2

1, 2, 3, & 4 10 to 10 R/hr 30 4

5 5

I e

i--e.-

w

---...m._=or,-

A

=--.i--..+,v, w r r,

=

-mm w-m v-

-w.

=e-,-

-w~

m.

- =.

-.c y----.-

-w

3/4.3 INSTRUMENTATION TABLE 3.3-6 (Continued)

TABLE NOTATION Alann setpoint to be specified in a controlled document (e.g., setpoint control manual).

ACTION STATEMENTS ACTION 14 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 16 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 30 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, initiate the preplanned alternate method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) either restore the inoperable channel (s) to OPERABLE status within 7 days of the event, or 2) prepare and submit a Special Report to the Comission pursuant to Specification 6.9.2 within 30 days following the event, outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system to OPERABLE status.

CALVERT CLIFFS - UNIT 2 3/4 3-25 Amendment No. 161 l

g TABLE 4.3-3 R

Gg RADIATION MONITORING INSTRUNENTATION SURVEILLANCE REQUIREMENTS

'w N

CHANNEL MODES IN WNICN E

C CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE 5

.]

INSTRUNENT CHECK CALIBRATION TEST REQUIRED E

1.

AREA MONITORS g

i C

a.

Containment y

a i

i. Purge & Exhaust Isolation S

R M

6 b.

Containment Area High Range S

R M

1, 2, 3, & 4 2.

PROCESS MONITORS R

a.

Containment a

w 1.

Gaseous Activity M

a) RCS Leakage Detection S

R M

1, 2, 3, & 4 ii. Particulate Activity a)

RCS Leakage Detection S

R H

1, 2, 3, & 4 b.

Noble Gas Effluent Monitors E-1.

Main Vent Wide Range S

R M

1, 2, 3, & 4 l

$5

11. Main Steam Header S

R H

1, 2, 3, & 4

?'

l w

l l

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Incore Detectors LIMITING CONDITION FOR OPERATION 3.3.3.2 The Incore Detection System shall be OPERABLE with at least one OPERABLE detector segment in each core quadrant on each of the four axial elevations containing incore detectors and as further specified below:

I a.

For monitoring the AZIMUTHAL POWER TILT:'

At least two quadrant symmetric incore detector segment groups at each of the four axial elevations containing incore detectors in the outer 184 fuel assemblies with sufficient OPERABLE detector segments in these detector groups to compute at least two AZIMUTHAL POWER TILT values at each of the four axial elevations containing incore detectors.

b.

For recalibration of the Excore Neutron Flux Detection System:

1.

At least 75%** of all incore detector segments, 2.

A minimum of 9 OPERABLE incore detector segments at each detector segment level, and 3.

A minimum of 2 OPERABLE detector segments in the inner 109 fuel assemblies and 2 OPERABLE segments in the outer 108 fuel assemblies at each segment level.

For Unit 2 Cycle 10 only, the following requirements shall be substituted for Limiting Condition for Operation 3.3.3.2.a:

At least eight quadrant symetric incore detector segment groups'

[

containing incore detectors in the outer 184 fuel assemblies with sufficient OPERABLE detector segments in these detector groups to compute at least one AZIMUTHAL POWER TILT value at each of the four axial elevations containing incore detectors and at least two AZIMUTHAL POWER TILT values at three axial elevations containing.

incore detectors.

For Unit 2 Cycle 10 only, the following requirement shall be substituted for Limiting Condition for Operation 3.3.3.2.b.1:

At least 60% of all incore detector segments, CALVERT CLIFFS - UNIT 2 3/4 3-27 Amendment No. 161 l

3/4.3 INSTRUMENTATION LIMITING CONDITION FOR OPERATION (Continued) c.

For monitoring the UNRODDED PLANAR RADIAL PEAKING FACTOR, the UNRODDED INTEGRATED RADIAL PEAKING FACTOR, or the linear heat rate:

l 1.

At least 75%* of all incore detector locations, 2.

A minimum of 9 OPERABLE incore detector segments at each detector segment level, and 3.

A minimum of 2 OPERABLE detector segments in the inner 109 fuel assemblies and 2 OPERABLE segments in the outer 108 fuel assemblies at each segment level.

An OPERABLE incore detector segment shall consist of an OPERABLE rhodium detector constituting one of the segments in a fixed detector string.

An OPERABLE incore detector location shall consist of a string in which at least three of the four incore detector segments are OPERABLE.

An OPERABLE quadrant symmetric incore detector segment group shall consist of a minimum of three OPERABLE rhodium incore detector segments in 90 symmetric fuel assemblies.

APPLICABILITY: When the Incore Detection System is used for:

a.

Monitoring the AZIMUTHAL POWER TILT, b.

Recalibration of the Excore Neutron Flux Detection System, or c.

Monitoring the UNRODDED PLANAR RADIAL PEAKING FACTOR, the UNRODDED INTEGRATED RADIAL PEAKING FACTOR, or the linear heat rate.

ACTION: With the Incore Detection System inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

For Unit 2 Cycle 10 only, the following requirement shall be substituted for Limiting. condition for Operation 3.3.3.2.c.1:

At least 60% of all incore detector locations, CALVERT CLIFFS - UNIT 2 3/4 3-28 Amendment No. 161 l

l 3/4.3 INSTRUMENTATION SURVEILUUICE REQUIREMENTS 4.3.3.2 The Incore Detection System shall be demonstrated OPERABLE:

a.

By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to its use and at least once per 7 days thereafter when required for:

1.

Monitoring the AZIMUTHAL POWER TILT.

2.

Recalibration of the Excore Neutron Flux Detection System.

3.

Monitoring the UNRODDED PLANAR RADIAL PEAKING FACTOR, the UNR0DDED INTEGRATED RADIAL PEAKING FACTOR, or the linear heat rate.

b.

At least once per REFUELING INTERVAL by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but includes all electronic components. The neutron detectors shall i

be calibrated prior to installation in the reactor core.

i t

i l

\\

E i

CALVERT CLIFFS - UNIT 2 3/4 3-29 Amendment No. 161 l

?

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Seismic Instrumentation LIMITING CONDITION FOR OPERATION i

3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall t

be OPERABLE.

APPLICABILITY: At all times.

ACTION:

l a.

With one or more seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the i

Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the mc1 function and the plans for restoring the instrument (s) to OPERABLE status.

I b.

The provisions of Specifications 3.0.3 and 3.0.4 are not i

applicable.

i i

t SURVEILLANCE REQUIREMENTS l

4.3.3.3.1 Each of the above seismic monitoring instruments shall be demonstrated OPERABLE by the perfomance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown

-l in Table 4.3-4.

4.3.3.3.2 Each of.the above seismic monitoring instruments actuated during a seismic event shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CALIBRATION performed within 5 days following the seismic event.

Data shall be retrieved from actuated instruments and analyzed to detemine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Comission pursuant to Specification 6.9.2 i

within 10 days describing the magnitude, frequency spectrum and resultant i

effect upon facility features important to safety.

i CALVERT CLIFFS - UNIT 2 3/4 3-30 Amendment No. 161 l

i 3/4.3 INSTRUMENTATION TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION MINIMUM MEASUREMENT INSTRUMENT INSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE 1.

Triaxial Time-History Strong Motion Accelographs i

i a.

0-YE-001 Unit 1 Containment Base 0-1g 1

b.

0-YE-002 Unit 1 Containment 69' 0-Ig 1

c.

0-YE-003 Auxiliary Bldg. Base 0-1g 1

d.

0-YE-004 Intake Structure 0-1g 1

e.

0-YE-005 Free Field 0-1g 1

2.

Triaxial Seismic Switches j

a.

0-YS-001 Unit 1 Containment Base NA 1

b.

0-YS-002 Unit 1 Containtient 69' NA 1

3.

Seismic Acceleration Recorder a.

0-YRC-001 Control Room NA 1

b.

0-YR-001 Control Room NA 1

l i

f i

s e

1 1

i CALVERT CLIFFS - UNIT 2 3/4 3-31 Amendment No. 161 l

+.-m

~

n

=

,s

i 3/4.3 INSTRUMENTATION i

TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS j

CHANNEL l

CHANN[}.

CHANNEL FUNCTIONAL INSTRUMENTS AND SENSOR LOCATIONS CHECK CALIB. RATION TEST i

1. Triaxial Time-History Strong Motion

)

Accelographs a.

0-YE-001 Unit 1 Containment Base M*

R SA b.

0-YE-002 Unit 1 Containment 69' M*

R SA c.

0-YE-003 Auxiliary Bldg. Base M*

R SA l

d.

0-YE-004 Intake Structure M*

R SA

)

e.

0-YE-005 Free Field M*

R SA i

f

2. Triaxial Seismic Switches a.

0-YS-001 Unit 1 Containment Base M

R SA b.

0-YS-002 Unit 1 Containment 69' M

R SA

3. Seismic Acceleration Recorder a.

0-YRC-001 Control Room M

R SA l

b.

0-YR-001 Control Room M

R SA

-l i

4 s-i

- Verify instrument energized.

f Except seismic trigger.

f CALVERT CLIFFS - UNIT 2 3/4 3-32 Amendment No. 161 l

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Meteoro1ocical Instrumentation LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE.

APPLICABILITY. At all times.

ACTION:

a.

With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Comission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the j

plans for restoring the channel (s) to OPERABLE status, i

i b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

i j

l SURVEILLANCE REQUIREMENTS 4.3.3.4 Each of the above meteorological monitoring instrumentation i

channels shall be demonstrated OPERABLE by the perfonnance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in' l

Table 4.3-5.

l l

CALVERT CLIFFS - UNIT 2 3/4 3-33 Amendment No. 161 l

.~

i 3/4.3 INSTRUMENTATION h

TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE l

1.

WIND SPEED a.

Nominal Elev.10M 1

I b.

Nominal Eley. 60M 1

2.

WIND DIRECTION a.

Nominal Elev.10M i

b.

Nominal Elev. 60M 1

3.

AIR TEMPERATURE - DELTA T (10M-60M) 1 i

l CALVERT CLIFFS - UNIT 2 3/4 3-34 Amendment No. 161 l

t i

3/4.3 INSTRUMENTATION TABLE 4.3-5 t

METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l

CHANNEL CHANNEL f

INSTRUMENT CHECK CALIBRATION 1.

WIND SPEED a.

Nominal Eley. 10M D

SA b.

Nominal Elev. 60M D

SA 2.

WIND DIRECTION a.

Nominal Elev.10M D

SA j

b.

Nominal Elev. 60M D

SA 3.

AIR TEMPERATURE - DELTA T (10M-50M)

D SA t

t i

i l

)

i CALVERT CLIFFS - UNIT 2 3/4 3-35 Amendment No. 161 l

f

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Remote Shutdown Instrumentation LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the Control Room.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

With the number of OPERABLE remote shutdown monitoring channels less than required by Table 3.3-9, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDDWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.5 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6.

i 3

1 CALVERT CLIFFS - UNIT 2 3/4 3-36 Amendment No. 161 l

1

g TABLE 3.3-9 R

E g

REMOTE SHUTDOWN MONITORING INSTRUMENTATION w

j n

MINIMUM li; C

i 7

READ 0UT MEASUREMENT CHANNELS INSTRUMENT LOCATION RANGE OPERABLE.

E w

i 1.

Wide Range Neutron Flux

2C43 0.1 cps-200%

1 g

E 2.

Reactor Trip Breaker Indication Cable Spreading OPEN-CLOSE 1/ trip breaker Room g

3.

Reactor Coolant Cold Leg 2C43 212-705 F 1

Temperature 4.

Pressurizer Pressure 2C43 0-4000 psia 1

5.

Pressurizer Level 2C43 0-360 inches 1

6.

Steam Generator Pressure 2C43 0-1200 psig 1/ steam generator i'

7.

Steam Generator Level 2C43

-401 to +63.5 inches 1/ steam generator

.O 3

a ae When the 2C43 instrumentation is inoperable, the wide range neutron flux monitors located in the auxiliary feedwater pump room may be utilized to meet this requirement. During the period when

-O the instruments are utilized to meet the above requirement, they will be subject to the surveillance requirements of Table 4.3-6.

m..

. u m

m :..-m..

m

--&__-___m_________________________-__,-w wws-e v-a

-*mW ar w

s-

i 3/4.3 INSTRUMENTATION f

TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.

Wide Range Neutron Flux H

NA 2.

Reactor Trip Breaker Indication M

NA 3.

Reactor Coolant Cold Leg Temperature M

R 4.

Pressurizer Pressure M

R i

5.

Pressurizer Level M

R i

6.

Steam Generator Level M

R 7.

Steam Generator Pressure M

R i

i i

CALVERT CLIFFS - UNIT 2 3/4 3-38 Amendment No. 161 l

l 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Post-Accident Instrumentation LIMITING CONDITION FOR OPERATION 3.3.3.6 The post-accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

l APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a.

As shown in Table 3.3-10.

b.

The provisions of Specification 3.0.4 are not applicable.

t i

SURVEILLANCE REQUIREMENTS 4.3.3.6 Each post-accident monitoring instrumentation channel shall be demeristrated OPERABLE by perfonnance of the CHANNEL CHECK and CHANNEL CALIBAATION operations at the frequencies shown in Table 4.3-10.

l i

l CALVERT CLIFFS - UNIT 2' 3/4 3-39 Amendment No. 161 l

t g

TABLE 3.3-10 R

G

?

g POST-ACCIDENT MONITORING INSTRUMENTATION w

b MINIMUM h

I q

CNANNELS k""

INSTRUMENT OPERABLE ACTION

=

1.

Containment Pressure 2

31 y

g Z

2.

Wide Range Logarithmic Neutron Flux Monitor 2

31 y

3.

Reactor Coolant Outlet Temperature 2

31 4.

Pressurizer Pressure 2

31 5.

Pressurizer Level 2

31 6.

Steam Generator Pressure 2/ steam generator 31 mS 7.

Steam Generator Level (Wide Range) 2/ steam generator 31 w

g 8.

Auxiliary Feedwater Flow Rate 2/ steam generator 31 9.

RCS Subcooled Margin Monitor 1

31

10. PORV/ Safety Valve Acoustic Flow Monitoring 1/ valve 31

11. PORY Solenoid Power Indication 1/ valve 31

12. Feedwater Flow 2

31 k

13. Containment Water Level (Wide Range) 2 32, 33 h

14. Reactor Vessel Water Level 2*

34,'35 k

15. Core Exit Thennocouple System 2 locations / core quadrant 31 E

b A channel has eight sensors in a probe. A channel is OPERABLE if' four or more sensors, one or more in the upper three and three or more in the lower five, are OPERA 8LE.

l l

e

.m

+.w.

____-..-,-w-.r---_

.-e w.--,ew- - -,,,-eu.

=m.

-w---

e 2

+-

am4-e v-- e m.

,, * -.. > ' + - > + -, - =. -

e-r %

3/4.3 INSTRUNENTATION 1

TABLE 3.3-10 (Continued)

ACTION STATEMENTS ACTION 31 -

With the number of OPERABLE post-accident monitoring

+

channels loss than required by Table 3.3-10, either restore the inoperable channel to OPERABLE status within 30 days or j

be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 32 -

With the number of OPERABLE post-accident monitoring channels one less than the Minimum Channels OPERABLE requirement in Table 3.3-10, operation may proceed provided the inoperable channel is restored to 0PERABLE status at the next outage of sufficient duration.

ACTION 33 -

With the number of OPERABLE post-accident monitoring i

channels two less than required by Table 3.3-10, either restore one inoperable channel to OPERABLE status within 30 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 34 -

With the number of OPERABLE post-accident monitoring channels one less than the Minimum Channels OPERABLE l

requirement in Table 3.3-10, either restore the system to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

ACTION 35 -

With the number of OPERABLE channels two less than required by Table 3.3-10, either restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months if repairs are feasible i

without shutting down or:

1.

Initiate an alternate method of monitoring for core and i

Reactor Coolant System voiding; j

2.

Prepare and submit a Special Report to the Comission i

pursuant to Specification 6.9.2 within 30 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and 3.

Restore the system to OPERABLE status at the next scheduled refueling.

CALVERT CLIFFS - UNIT 2 3/4 3-41 Amendment No. 161 l

1 l

g TABLE 4.3-10 R

G P

g POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w

b CHANNEL CHANNEL

]

INSTRUMENT CHECK CALIBRATION E

i 1.

Containment Pressure M

R g

E 2.

Wide Range Logarithmic Neutron Flux Monitor M

NA

[

3.

Reactor Coolant Outlet Temperature M

R E

4.

Pressurizer Pressure M

R 5.

Pressurizer Level M

R 6.

Steam Generator Pressure H

R g

7.

Steam Generator Level (Wide Range)

M R

8.

Auxiliary Feedwater Flow Rate M

R w

O 9.

RCS Subcooled Margin Monitor M

R

10. PORV/ Safety Valve Acoustic Monitor NA R

11. PORY Solenoid Power Indication NA NA

12. Feedwater Flow M

R

13. Containment Water Level (Wide Range)

M R

Eg

14. Reactor Vessel Water Level M

NA a

2

15. Core Exit Thennocouple System M

R*

5 k

The perfonnance of a CHANNEL CALIBRATION operation exempts the Core Exit Thennocouple but includes all electronic components. The Core Exit Thennocouple shall be calibrated prior to

-0 installation in the reactor core.

a w

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Fire Detection Instrumentation LIMITING CONDITION FOR OPERATION 3.3.3.7 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE.

APPLICABILITY: Whenever equipment in that fire detection zone is r qaired to be OPERABLE.

ACTION: With one or more of the fire detection instrument (s) shown in Table 3.3-11 inoperable:

a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect the containment at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5; or unless the instrument (s) is located in fire detection zones equipped with automatic wet pipe sprinkler systems alanned and supervised to the Control Room, then within I hour and at least per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, inspect the zone (s) with inoperable instruments and verify that the Automatic Sprinkler System, including the water flow alann and supervisory system, is OPERABLE by CHANNEL FUNCTIONAL TEST.

b.

Restore the inoperable instrument (s) to OPERABLE status within 14 days or prepare and submit a Special Report to the Comission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.7.1 At least once per 6 months, at least 25% of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST.

Detectors selected for testing shall be selected on a rotating basis such CALVERT CLIFFS - UNIT 2 3/4 3-43 Amendment No. 161 l

3/4.3 INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued) that all detectors will be tested over a two year period.

If in any detection zone there are less than four detectors, at least one different detector in that zone shall be tested every six months. For each detector found inoperable during functional testing, at least an additional 10% of all detectors or 10 detectors, whichever is less, shall also be tested.

Fire detectors which are inaccessible during plant operation shall be demonstrated OPERABLE by the perfonnance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless perfomed during the previous six months.

4.3.3.7.2 The NFPA Code 720 Class B supervised circuits supervision associated with the detector alanns of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

4.3.3.7.3 The non-supervised circuits, associated with detector alanns, between the instrument and the Control Room shall be demonstrated OPERABLE at least once per 31 days.

i CALVERT CLIFFS - UNIT 2 3/4 3-44 Amendment No. 161 l

3/4.3 INSTRUMENTATION 4

TABLE 3.3-11 FIRE DETECTION INSTRUMENTS UNIT 2 l

MINIMUMINSTRyMENTS OPERABLE i

ROOM / AREA AUX BLDG.

INSTRUMENT LOCATION HEAT FLAME SM0KE 101/120 ECCS Pump Room 7

102/121 ECCS Pump Room 7

105 Charging Pump Room 3

106 Misc Waste Monitor Tank 1

107/109 Coolant Waste Monitor Tank 4

108 Pump Room-Elev (-)10'-0" I

i 201 Component Cooling Pump Rm 9

203 East Piping Area 10 204 Rad Exhaust Vent, Equip Rm 4

205 Service Water Pump Rm 3

6 206/310 East Piping Pen Rm 3

5 211/321 West Piping Pen Rm 2

3 213 Degasifier Pump Rm 1

214 Volume Control Tank Rm 1-215 Boric Acid Tank & Pump Rm 2

216A Reactor Coolant Make-up Pumps 2

302/2C U2 Cab 1p, Spreading Rm & Cable Chase 2

10 305/307/303 U2 Battery Rm & Corridor 3

i 309 Main Steam Piping Area 6

311 Switchgear Rm, Elev. 27'-0" 6

312 Purge Air Supply Rm 2

322 Letdown Heat Exchanger Rm 1

Elev. 27 '-0" Switchgear Vent Duct 1

2A Cable Chase 2A 1-2B Cable Chase 28 1

Detection instruments located within the containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate Tests.

Detectors which autcmatically actuate Fire Suppression Systems.

CALVERT CLIFFS - UNIT 2 3/4 3-45 Amendment No. 161 l

M

~

3/4.3 INSTRUMENTATION TABLE 3.3-11 (Continued) i i

FIRE DETECTION INSTRUMENTS UNIT 2 MINIMUM INSTRUMENTS OPERABLE

ROOM / AREA AUX BLDG.

. INSTRUMENT LOCATION HEAT FLAME SM0KE 407 Switchgear Rm, Elev 45'-0"**

8 I

408 East Piping Area 7

409 East Electrical Pen Rm 3

414 West Electrical Pen Rm 3

416 Diesel Generator No. (21)**

2 440 Refueling Water Tank Pump Rm 2

Elev. 45'-0" Switchgear Vent Duct 1

526 Main Plant Exhaust Equip Rm 8

527 Containment Access 3

532 Electrical Equip Rm 3

Elev. 69'-0" Cable Spreading Room Vent Duct 1

Eley. 83'-0" Cable Tunnel 4

605 Auxiliary feedwater Pump Rm 2

Containment Blda.

UNIT 2 RCP Bay East

16 UNIT 2 RCP Bay West 16 UNIT 2 East Electric Pen Area

l 3

UNIT 2 West Electric Pen Area, Intake Structure Elev 3'-0" Unit 2 Side 24 Detection instruments located within the containment are not required I

to be OPERABLE during the performance of Type A Containment Leakage Rate Tests.

Detectors which automatically actuate Fire Suppression Systems.

+

Honitored by four protecto wires.

CALVERT CLIFFS - UNIT 2 3/4 3-46 Amendment No. 161 l

E 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radioactive Gaseous Effluent Monitorino Instrumentation LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alam/ trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alam/ trip setpoints of these channels shall be detemined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3-12.

ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alam/ trip setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS i

4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-11.

i 1

CALVERT CLIFFS - UNIT 2 3/4 3-47 Amendment No. 161 l

9 TABLE 3.3-12 R

E g

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION w

b MINIMUM CHANNELS

]

INSTRUMENT OPERABLE APPLICABILITY ACTION g

i 1.

WASTE GAS HOLDUP SYSTEM g

C 5

a.

Noble Gas Activity Monitor - Providing 1

3S d

Alam and Automatic Tennination of E

Release b.

Effluent System Flow Rate Measuring 1

36 Device 2.

MAIN VENT SYSTEM M

^

a.

Noble Gas Activity Monitor 1

37 i's b.

Iodine Sampler 1

38 c.

Particulate Sampler 1

38 E

a an u

m

3/4.3 INSTRUNENTATION TABLE 3.3-12 (Continued)

TABLE NOTATION At all times.

ACTION STATEMENTS ACTION 35 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment:

I a.

Using the main vent monitor as a backup and recording RMS readings every 15 minutes during the release, or b.

Provided that prior to initiating the release, at least two independent samples of the tank's contents are analyzed, and at least two technically qualified members of the facility Staff independently verify the release rate calculations and two qualified operators verify the discharge valve lineup.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 37 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, ef fluent releases via this pathway may continue provided either (1) grab samples are taken and analyzed for gross activity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or (2) an equivalent monitor is provided.

ACTION 38 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are continuously collected as required in Table 4.11-2 with auxiliary sampling equipment.

CALVERT CLIFFS - UNIT 2 3/4 3-49 Amendment No. 161 l

g TABLE 4.3-11 R

G

?

RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w

g MODES IN E

1 n

C CHANNEL WNICN

!Q q

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE g

INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED "i

C D

1.

WASTE GAS HOLDUP SYSTEM d

E a.

Noble Gas Activity Monitor -

P P

R(3)

SAW Providing Alarm and Automatic Termination of Release b.

Effluent System Flow Rate DN NA R

NA Measuring Device wS 2.

MAIN VENT SYSTEM a.

Noble Gas Activity Monitor D

M RW SAW

^

b.

Iodine Sampler W

NA NA NA c.

Particulate Sampler W

NA NA NA a

o.

a F

m

= u v+ ' "

a

-e--mw'-

't e

w e

<a s--a w

w,-n

~

a--

m.

-+ - -

3/4.3 INSTRUMENTATION TABLE 4.3-11 (Continued)

TABLE NOTATION At all times other than when the line is valved out and locked.

(1)

The CHANNEL FUNCTIONAL TEST shall also demonstrate the automatic isolation of this pathway and/or Control Room alarm annunciation occurs if the appropriate following condition (s) exists:

1.

Instrument indicates measure levels above the alarm / trip setpoint.

2.

Circuit failure.

3.

Instrument indicates a downstale failure.

(2)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that Control Room alam annunciation occurs if any of the following conditions exist:

1.

Instrument indicates measured levels above the alam setpoint.

2.

Circuit failure.

]

3.

Instrument indicates a downscale failure.

(3)

The initial CHANNEL CALIBRATION shall be perfomed using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall pemit calibrating the system within its intended I

range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration can be used.

(4)

The CHANNEL CHECK shall consist of verifying indication of flow during periods of release and shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which effluent releases are made.

CALVERT CLIFFS - UNIT 2 3/4 3-51 Amendment No. 161 l

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radioactive Licuid Effluent Monitorino Instrumentation LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alam/ trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the t

0FFSITE DOSE CALCULATION MANUAL (0DCM).

APPLICABILITY: At all times.

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by perfomance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-12.

CALVERT CLIFFS - UNIT 2 3/4 3-52 Amendment No. 161 l

3/4.3 INSTRUMENTATION TABLE 3.3-13 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CNANNELS INSTRUMENT OPERABLE ACTION 1.

GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.

Liquid Radwaste Effluent Line 1

28 b.

Steam Generator Blowdown Effluent 1

29 Line 2.

FLOW RATE MEASUREMENT DEVICES a.

Liquid Radwaste Effluent Line 1

30 b.

Steam Generator Blowdown Effluent 1

30 Line I

A 5

Q

3/4.3 INSTRUMENTATION TABLE 3.3-13 (Continued)

ACTION STATEMENTS-ACTION 28 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

a.

At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and two qualified operators verify the discharge valve line up.

ACTION 29 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases t

via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at the lower limit of detection defined in Table 4.11-1:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131.

b.

At least once per 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOSE EQUIVALENT I-131.

ACTION 30 -

With the number of channels 0PERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

Pump performance curves may be used to estimate flow.

CALVERT CLIFFS - UNIT 2 3/4 3-54 Amendment No. 161 l

9 TABLE 4.3-12 R

G

?

g RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w

b CHANNEL SOURCE CHANNEL FUNCTIONAL

'a

]

INSTRUMENT CHECK CHECK CALIBRATION TEST g

i 1.

GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM g

.AND AUTOMATIC TERMINATION OF RELEASE g

g a.

Liquid Radwaste Effluent Line D

P R(2)

SA )

fl b.

Steam Generator Blowdown Effluent Line D

P R(2)

SA )

il 2.

FLOW RATE MEASUREMENT DEVICES a.

Liquid Radwaste Effluent Line D(3)

NA R

NA g

't' b.

Steam Generator Blowdown Effluent Line D(3)

NA R

NA E

g ita

.E i

i 1

4

.m

..-..,v

,.<.e-~.

-e

q 3/4.3 INSTRUMENTATION TABLE 4.3-12 (Continued)

TABLE NOTATION (1)

The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and/or Control Room alarm annunciation occur if the appropriate following condition (s) exist:

1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

(2)

The initial CHANNEL CALIBRATION shall be perfonned using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system within its intended range of energy and measurement range.

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration can be used.

(3)

CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which effluent releases are made.

l CALVERT CLIFFS - UNIT 2 3/4 3-56 Amendment No. 161 l

l

i 3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF)

INSTRUMENTATION The OPERABILITY of the bypasses ensure that 1) protective and ESF instrumentation systems and the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combihation thereof exceeds its setpoint, 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to pennit a channel to be out of service for testing or maintenance, and 4) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the l

overall system functional capability is maintained comparable to the original design standards.

The perici surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each j

channel is completed within the time limit assumed in the accident analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable.

1

Response

le may be demonstrated by any series of sequential, overlapping or total criannel 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. The response time limits are contained in UFSAR Chapter 7, and updated in accordance with 10 CFR 50.71(e).

3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 Radiation Monitoring Instrumentation The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2)~ the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.

CALVERT CLIFFS - UNIT 2 B 3/4 3-1 Amendment No. 161

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ML20067B997

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