Text

Amend 158 to License DPR-69,revising TS 3/4.2,Power Distribution Limits & 3/4.3,Instrumentation, to Relax Requirements for Number & Distribution of Operable in-core Detectors for Remainder of Operating Cycle 10
	ML20056G278
Person / Time
Site:	Calvert Cliffs
Issue date:	08/23/1993
From:	Capra R; Office of Nuclear Reactor Regulation
To:	;
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	NUDOCS 9309020351
	Download: ML20056G278 (38)
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UNITED STATES i'Eg4 F NUCLEAR REGULATORY COMMISSION

( '.v

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WASHfNGTON, D.C. 205 5-0001 BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318

_(ALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.158 License No. DPR-69 1.

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

A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated July 16, 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; 4

l 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; j

D.

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

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-69 is hereby amended to read as follows:

9309020351 v30823 PDR ADOCK 05000318 p

PDR-

i i

(2) Technical Specifications

^

The Technical Specifications contained in Appendices A and B, as l

revised through Amendment No.158, are hereby incorporated in the I

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 to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION YN O. 0p Robert A. Capra, Director i

Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i

Attachment:

Changes to the Technical Specifications Date of Issuance: August 23, 1993 i

1 t

I

l ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.158 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318 Revise Appendix A as follows:

Remove Paaes Insert Paagt 3/4 2-2 3/4 2-2 3/4 2-6 3/4 2-6 3/4 2-11 3/4 2-11 3/4 2-12 3/4 2-12 3/4 3-31 3/4 3-31 3/4 3-32 3/4 3-32 3/4 3-33 thru 3-59*

3/4 3-33 thru 3-59*

s 1

2 I

I

These pages are text rollover pages with no changes as the result of this amendment. The amendment number appears at the bottom of the page to indicate a shift in text.

l

3/4.2 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Conti::end)

I c.

Verifying at least once per 31 days that the AXIAL SHAPE INDEX is maintained within the limits of Figure 3.2.1-2, where 100 percent of the allowable power represents the maximum THERMAL POWER allowed by the following expression:

MxN i

where:

1.

M is the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combination.

2.

N is the maximum allowable fraction of RATED THERMAL POWER as detemined by the FL curve of Figure 3.2.1-3.

4.2.1.4 Incore Detector Monitorina System - The Incore Detector Monitoring l

System may be used for monitoring the core power distribution by verifying that the incore detector Local Power Density alarms:

i a.

Are adjusted to satisfy the requirements of the core power.

[

distribytton map which shall be updated at least once per 31 days of accumulated operation in MODE 1.

l l

b.

Have their alam setpoint adjusted to less than or equal to the i

limits shown on Figure 3.2.1-1 when the following factors are appropriately included in the setting of these alarms:

.j 1.

A measurement-calculational-uncertainty factor of 1.062.**

l j

2.

An engineering uncertainty factor of 1.03.

3.

A linear heat rate uncertainty factor of 1.002 due to axial j

fuel densification and thermal expansion, and 1

4.

A THERMAL POWER measurement uncertainty factor of 1.02.

l l

t For Unit 2 Cycle 10 only, when the percentage of OPERABLE incore detector locations (e.g., strings) falls below 75%, this surveillance shall be performed at least once per 15 days of accumulated operation in MODE 1.

For Unit 2 Cycle 10 only, when the percentage of OPERABLE incore detector locations (e.g., strings) falls below 75%, the measurement-calculational uncertainty factor on linear heat rate shall be increased by 1% (from 1.062 to 1.072) prior to comparison with the Technical Specification limit.

CALVERT CLIFFS - UNIT 2 3/4 2-2 Amendment No. 158 i

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACTOR - FI, LIMITING CONDITION FOR OPERATION 3.2.2.1 The calculated value of P shall be limited to 51.70.**

l y

APPLICABILITY: MODE 1*.

ACTION: With P > 1.70, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either :

y a.

Withdraw and maintain full length CEAs at or beyond the Long Term Steady State Insertion Limits of Specification 3.1.3.6 and reduce THERMAL POWER as follows:

1.

Reduce THERMAL POWER to bring the combination of THERMAL POWER and F within the limits of Figure 3.2.2-1, or y

2.

Reduce THERMAL POWER to less than or equal to the limit established by the Better Axial Shape Selection System (BASSS) as a function of P; or y

b.

Be in at least HOT STANDBY.

SURVEILLANCE REQUIREMENTS 4.2.2.1.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.1.2 FI shall be calculated by the expression P = F, (1+T ) when F is determinecI with a non-full Core Power Distribution Mapp[ng Sy, stem and y

y shall be calculated as P =

Distribution Mapping SysEem.F when determined with a full Core Power yP shall be detemined to be within its limit y

at the following intervals:

)

a.

Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading, For Unit 2 Cycle 10 only, when the percentage of OPERABLE incore detector locations (e.g., strings) falls below 75%, the calculated value of P shall be increased by 1% prior to comparison with the y

limit.

See Special Test Exception 3.10.2.

CALVERT CLIFFS - UNIT 2 3/4 2-6 Amendment No. 158

3/4.2 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 31 days

of accumulated operation in MODE 1, l

and Within four hours if the AZIMUTHAL POWER TILT (T,) is > 0.030.

c.

4.2.2.1.3 FI shall be dete'rmined each time a calculation is required by using the inc, ore detectors to obtain a power distribution map with all full length CEAs at or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump combination. This determination shall be limited to core planes between 15% and 85% of full core height inclusive and shall exclude regions influenced by grid effects.

4.2.2.1.4 T shall be determined each time a calculation of FL is made usinganonlullCorePowerDistributionHappingSystemandthevalueofT, used to determine FI, shall be the measured value of T,.

For Unit 2 Cycle 10 only, when the percentage of OPERABLE incore detector locations (e.g., strings) falls below 75%, this surveillance shall be performed at least once per 15 days of accumulated operation in MODE 1.

CALVERT CLIFFS - UNIT 2 3/4 2-7 Amendment No. 158

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - Fi LIMITING CONDITION FOR OPERATION 3.2.3 The calculated value of F, shall be limited to 51.70.**

l APPLICABILITY: MODE 1*.

ACTION: With P, > 1.70, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

a.

Be in at least HOT STANDBY, or

}

b.

Withdraw and maintain the full length CEAs at or beyond the Long i

Tenn Steady State Insertion Limits of Specification 3.1.3.6 and i

reduce THERMAL POWER as follows:

1.

Reduce THERMAL POWER to bring the combination of THERMAL POWER and F, within the limits of Figure 3.2.3-1, or 2.

Reduce THERMAL POWER to less than or equal to the limit I

established by the Better Axial Shape Selection System (BASSS) as a function of F,.

When the THERMAL POWER is detennined from Figure 3.2.3-1, it shall be used to establish a revised upper THERMAL POWER LEVEL limit on Figure 3.2.3-2 (i.e., Figure 3.2.3-2 shall be truncated at the allowable fraction of RATED THERMAL POWER determined by Figure 3.2.3-1).

Subsequent operation shall be maintained within the reduced acceptable operation region of Figure 3.2.3-2.

1 SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 P, shall be calculated by the expression P = F, (1+T when F, is I

detennined with a non-full Core Power Distribution happing Sys,) tem and sha be calculated as P, = F, when determined with a full Core Power For Unit 2 Cycle 10 only, when the percentage of OPERABLE incore detector locations (e.g., strings) falls below 75%, the calculated value of F, shall be increased by 1% prior to comparison with the limit.

See Special Test Exception 3.10.2.

I CALVERT CLIFFS - UNIT 2 3/4 2-11 Amendment No. 158 i

4 3/4.2 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) t Distribution Mapping System.

P, shall be determined to be within its limit at the following intervals:

l a.

Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading, b.

At least once per 31* days of accumulated operation in M0DE 1,-

l and j

Within four hours if the AZIMUTHAL POWER TILT (T,) is > 0.030.

c.

4.2.3.3 P, shall be detemined each time a calculation is required by using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Tenn Steady State Insertion Limit for the existing Reactor Coolant Pump combination.

4.2.3.4 T shall be determined each time a calculation of P, is made using l

a non-full, Core Power Distribution Mapping System and the value of T, used to determine P, shall be the measured value of T,.

j

)

t i

l l

For Unit 2 Cycle 10 only, when the percentage of OPERABLE incore detector locations (e.g., strings) falls below 75%, this surveillance shall be perfonned at least once per 15 days of accumulated operation in MODE 1.

CALVERT CLIFFS - UNIT 2 3/4 2-12 Ameadment No. 158

i e

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION l

Incore Detectors LIMITING CONDITION FOR OPERATION 3.3.3.2 The Incore Detection System shall be OPERABLE with at least one OPERABLE detector segment i.n 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 ascemblies 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, l

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 symmetric incore detector segment groups t

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 3-31 Amendment No. 158

=

_ _ = -

k 1

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

For monitoring the UNRODDED PLAMAR RADIAL PEAKING FACTOR, the i

UNRODDED INTEGRATED RADIAL PEAKING FACTOR, or the linear heat rate-1.

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

A minimum of 9 OPERABLE incore detector segments at each detector segnient 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 i

detector constituting one of the segments in a fixed detector string, j

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

1 t-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:

i a.

Monitoring the AZIMUTHAL POWER TILT, i

b.

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

Monitoring the UNRODDED PLANM 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.

}

F For Unit 2 Cycle 10 only, the following requirement shall be 3

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 3-32 Amendment No. 158-i r~,

,w,

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

b.

At least once per REFUE!.ING INTERVAL by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but includes all electronic components.

The neutron detectors shall be calibrated prior to installation in the reactor core.

t CALVERT CLIFFS - UNIT 2 3/4 3-33 Amendment No. 158

l 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Seismic Instrumentation I

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 Commission 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 i

applicable.

1 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 iristruments 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 determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission 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 2 3/4 3-34 Amendment No. 158 l

3/4.3 INSTRUMENTATION TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION MINIMUM MEASUREMENT INSTRUMENT i

INSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE l

i 1.

Triaxial Time-History Strong Motion

}

Accelographs l

1 a.

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

l b.

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

c.

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

l d.

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

e.

0-YE-005 Free Field 0-19 1

l 2.

Triaxial Seismic Switches a.

0-YS-001 Unit 1 Containment Base NA 1

i b.

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

3.

Seismic Acceleration Recorder a.

0-YRC-001 Control Room NA 1

)

b.

0-YR-001 Control Room NA 1

i l

CALVERT CLIFFS - UNIT 2 3/4 3-35 Amendment No. 158

4 3/4.3 INSTRUMENTATION i

TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL CHANNEL FUNCTIONAL INSTRUMENTS AND SENSOR LOCATIONS CHECKI' CALIBRATION TEST

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 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 I Containment Base M

R SA b.

0-YS-002 Unit 1 Containment 69' M

R SA l 3. Seismic Acceleration Recorder i

a.

0-YRC-001 Control Room M

R SA i

b.

0-YR-001 Control Room M

R SA l

l 1

- Verify instrument energized.

Except seismic trigger.

CALVERT CLIFFS - UNIT 2 3/4 3-36 Amendment No. 158 l

I

__)

t 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Meteorological Instrumentation J

~

LIMITING C6HDITION 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 Commission 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, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 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 Table 4.3-5.

i i

CALVERT CLIFFS - UNIT 2 3/4 3-37 Amendment No. 158

1 i

l 3/4.3 INSTRUMENTATION TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE 1.

WIND SPEED a.

Nominal Elev.10M 1

b.

Nominal Elev. 60M 1

2.

WIND DIRECTION a.

Nominal Elev.10M 1

b.

Nominal Elev. 60M 1

I 3.

AIR TEMPERATURE - DELTA T (10M-60M) 1 CALVERT CLIFFS - UNIT 2 3/4 3-38 Amendment No. 158 l

9 3/4.3 INSTRUMENTATION TABLE 4.3-5 HETEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.

WIND SPEED a.

Nominal Elev.10M D

SA b.

Nominal Eley. 60M D

SA 2.

WIND DIRECTION a.

Nominal Elev.10M D

SA b.

Nominal Elev. 60M D

SA 3.

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

D SA CALVERT CLIFFS - UNIT 2

-3/4 3-39 Amendment No. 358

4 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 SHUTDOWN 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.

CALVERT CLIFFS - UNIT 2 3/4 3-40 Amendment No. 158 l

52 TABLE 3.3-9 ta CE f*

gg REMOTE SHUTDOWN MONITORING INSTRUMENTATION

'd

~n c3 HINIMUM E:

READOUT MEASUREMENT CHANNELS q

INSTRUMENT LOCATION RANGE OPERABLE E

1 1.

Wide Range Neutron Flux

2C43 0.1 cps-200%

1 gj ll 2.

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

[]

-4 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

hh 6.

Steam Generator Pressure 2C43 0-1200 psig 1/ steam generator t'

7.

Steam Generator Level 2C43

-401 to +63.5 inches 1/ steam generator C

L' aR a

co 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

i E3 the instruments are utilized to meet the above requirement, they will be subject to the surveillance requirements of Table 4.3-6.

~_._

r r-w-w p-A w

y-

-m-w-r w

we J-w

-%v-w-

-- --+

-mc ww--,-

w

-r r-

-~e

4 3/4.3 INSTRUMENTATION TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION i

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 r

5.

Pressurizer Level M

R 6.

Steam Generator Level M

R 7.

Steam Generator Pressure M

R i.

i CALVERT CLIFFS - UNIT 2 3/4 3-42 Amendment No. 158 l

3/4.3 INSTRUMENTATION 3/4.3.3 MONITCRING INSTRUMENTATION Post-Accident Instrumentation I

LIMITING CONDITION FOR OPERATION 3.3.3.6 The post-accident monitoring instrumentation channel; shown in Table 3.3-10 shall be OPERABLE.

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.

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

t i

CALVERT CLIFFS - UNIT 2 3/4 3-43 Amendment No. 158

g TABLE 3.3-10 R

G POST-ACCIDENT MONITORING INSTRUMENTATION w

b MINIMUM

)"

A CHANNELS E

INSTRUMENT OPERABLE ACTION M

i z

1.

Containment Pressure 2

31 y

g Q

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. PORV 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 IG more in the upper three and three or more in the lower five, are OPERABLE.

,.-a..

a ~,.

m

3/4.3 INSTRUMENTATION I

TABLE 3.3-10 (Continued)

ACTION STATEMENTS 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 channels one less than the Minimum Channels OPERABLE requirement in Table 3.3-10, operation may proceed provided the inopertele channel is restored to OPERABLE status at the next outagt of sufficient duration.

ACTION 33 -

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

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 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 1

by Table 3.3-10, either restore the inoperable channel (s) to j

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 follcwing 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 3-45 Amendment No. 158 l

g TABLE 4.3-10 w

G P

g POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w

b CHANNEL CHANNEL q

INSTRUMENT CHECK CALIBRATION E

w x

1.

Containment Pressure M

R y

E 2.

Wide Range Logarithmic Neutron Flux Monitor M

?!A

[

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

w 8.

Auxiliary feedwater Flow Rate M

R 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

Eg

14. Reactor Vessel Water Level M

NA k

15. Core Exit Themocouple System M

R*

z I

P The perfomance of a CHANNEL CALIBRATION operation exempts the Core Exit Themocouple but includes all electronic components. The Core Exit Themocouple shall be calibrated prior to installation in the reactor core.

..y..

,3._

-. ~

,-.yw..-,...w.

,__v,

____.__.,__m m..

w,.m-

~

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Fire Detection Instrumentation LIMITING CONDITION FOR OPERATION l

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 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 Spec 4 fication 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 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 alarm 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 3-47 Amendment No. 158

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 performance 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 performed during the previous six months.

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 i

at least once per 31 days.

l i

1 i

1 1

1 J

CALVERT CLIFFS - UNIT 2 3/4 3-48 Amendment No. 158 l

3/4.3 INSTRUMENTATION TABLE 3.3-11 FIRE DETECTION INSTRUMENTS UNIT 2 4

i MINIMUM INSTRUMENTS OPERABLE

l ROOM / AREA AUX BLDG.

INSTRUMENT LOCATION HEAT FLAME SM0KE i

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

i 108 Pump Room-Eley (-)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

l 215 Boric Acid Tank & Pump Rm 2

l 216A Reactor Coolant Make-up Pumps 2

302/2C U2 Cable, Spreading Rm & Cable i

Chase 2

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

309 Main Steam Piping Area 6

i 4

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 I

2A Cable Chase 2A 1

l 2B Cable Chase 2B 1

l 6

Detection instruments located within the containment are not' required j

to be OPERABLE during the perfomance of Type A Containment Leakage 1

Rate Tests.

l j

. Detectors which automatically actuate Fire Suppression Systems.

[

CALVERT CLIFFS - UNIT 2 3/4 3-49 Amendment No. 158

)

j l

e.

3/4.3 INSTRUMENTATION TABLE 3.3-11 (Continued)

FIRE DETECTION INSTRUMENTS UNIT 2 MINIMUM INSTRUMENTS OPERABLE

ROOM / AREA AUX BLDG.

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

8 408 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

Elev. 83'-0" Cable Tunnel 4

605 Auxiliary Feedwater Pump Rm 2

Containment Bldg.

UNIT 2 RCP Bay East

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

UNIT 2 West Electric Pen Area" Intake Structure Elev 3'-0" Unit 2 Side 24 Detection instruments located within the containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate Tests.

Detectors which automatically actuate Fire Suppression Systems.

+

Monitored by four protecto wires.

CALVERT CLIFFS - UNIT 2 3/4 3-50 Amendment No. 158

4 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radioactive Gaseous Effluent Monitoring Instrumentation l

LIMITING CONDITION FOR OPERATION l

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

APPLICABILITY: As shown in Table 3.3-12.

ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm / 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 i

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.

t SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRA1'rN and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 1-11.

CALVERT CLIFFS - UNIT 2 3/4 3-51 Amendment No. 158

g TABLE 3.3-12 R

Q RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION w

b MINIMUM CHANNELS q

INSTRUMENT OPERABLE APPLICABILITY ACTION E

u, 1.

WASTE GAS HOLDUP SYSTEM y]

C 3>

5 a.

Noble Gat Activity Monitor - Providing 1

35 d

Alann 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

'f

)0 b.

Iodine Sampler 1

38 c.

Particulate Sampler 1

38 N

an M

i I

3/4.3 INSTRUMENTATION i

TABLE 3.3-12 (Continued)

TABLE NOTATION i

At all times.

l 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.

i CALVERT CLIFFS - UNIT 2 3/4 3-53 Amendment No. 158

I g

TABLE 4.3-11 R

G g

RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS u

e MODES IN E.

n C

CHANNEL WHICH 7

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED k

n e

5 1.

WASTE GAS HOLDUP SYSTEM d

E a.

Noble Gas Activity Monitor -

P P

R(3)

SA(U Providing Alarm and Autcmatic Temination of Release b.

Effluent System Flow Rate D(*)

NA R

NA Measuring Device w

2.

MAIN VENT SYSTEM

~

R)

SA(2)

I3 a.

Noble Gas Activity Monitor D

M b.

Iodine Sampler W

NA NA NA c.

Particulate Sampler W

NA NA NA N

a 8n m

. ~ -..

j

^

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 alann 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 exist:

1.

Instrument indicates measured levels above the alarm setpoint.

l 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 pennit 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.

(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 3-55 Amendment No. 158

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radioactive Liouid Effluent Monitoring Instrumentation LIMITING CONDITION FOR OPERATIGN 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 alam/ trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCH).

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.eturn 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 1

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 i

channel shall be demonstrated OPERABLE by perfomance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at I

the frequencies shown in Table 4.3-12.

CALVERT CLIFFS - UNIT 2 3/4 3-56 Amendment No. 158 o

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 i

l CALVERT CLIFFS - UNIT 2 3/4 3-57 Amendment No. 158

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:

l a.

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

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 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 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.

CALVERT CLIFFS - UNIT 2 3/4 3-58 Amendment No. 158

~-

g TABLE 4.3-12 R

r-RADI0 ACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS U

b CHANNEL SOURCE CHANNEL FUNCTIONAL h

]

INSTRUMENT CHECK CHECK CALIBRATION TEST g

i 1.

GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM g

g g

AND AUTOMATIC TERMINATION OF RELEASE a.

Liquid Radwaste Effluent Line D

P R(2)

SA(1)

E

[

R)

SA )

C2 fl b.

Steam Generator Blowdown Effluent Line D

P 2.

FLOW RATE MEASUREMENT DEVICES a.

Liquid Radwaste Effluent Line D(3)

NA R

NA g

b.

Steam Generator Blowdown Effluent Line D(3)

NA R

NA a

8~

1 in m

3/4.3 INSTRUMENTATION TABLE 4.3-12 (Continued) l 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 appropri. ate 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 CRANNEL 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.

(3)

Cl!ANNEL 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.

1 CALVERT CLIFFS - UNIT 2 3/4 3-60 Amendment No. 158

ML20056G278

Text

Attachment:

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