Text

Amends 191 & 168 to Licenses DPR-53 & DPR-69,respectively, Removing TS That Have Been Applicable to Incore Instrument Sys
	ML20072L373
Person / Time
Site:	Calvert Cliffs
Issue date:	08/24/1994
From:	Kuo P; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20072L377	List: ML20072L373; ML20072L387;
References
	NUDOCS 9408310233
	Download: ML20072L373 (78)
	v • d • e

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t UNITED STATES

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j NUCLEAR REGULATORY COMMISSION

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f WASHINGTON, D.C. 20565-0001

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' BALTIMORE GAS AND ELECTRIC COMPANY u-DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.191 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 3, 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; 8.

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

The issuance of this amendment will not be 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 Comission's regulations and all applicable requirements j

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:

I 9408310233 940824 PDR ADOCK 05000317 P

PDR i

l

. 2.

Technical Soecifications The Technical Specificati,ons contained in Appendices A and B, as revised through Amendment No.191, 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 01 ~ cl.

P o-Tsin Kuo, Acting Director P oject Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 24, 1994 1

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[9 UNITED STATES

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j NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D.C. 20555-0001 o

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s, BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-313 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 168 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 November 3, 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; 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 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, and paragraph 2.C.2. of Facility Operating License No. DPR-69 is hereby amended to read as follows:

l r

. 2.

Technical Soecificationi The Technical 3pecifications contained in Appendices A and B, as revised through Amendment No.168, 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 Oe./

P o-Tsin Kuo, Acting Director P oject Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 24, 1994

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 191 FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 168 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NOS. 50-317 AND 50-318 Revise Appendix A as follows:

DPR-53 Remove Pages Insert Paaes Table of Contents IV Table of Contents IV 3/4 2-2 3/4 2-2 3/4 2-3 3/4 2-3 3/4 2-4 3/4 2-4*

3/4 2-5 3/4 2-5 3/4 2-6 3/4 2-6*

3/4 3-27 3/4 3-28 3/4 3-29 3/4 3 3/4 3-57 3/4 3 3/4 3-54*

3/4 10-2 3/4 10-2 3/4 10-4 3/4 10-4 8 3/4 3-2 B 3/4 3-2 DRP-69 Remove Paaes Insert Paoes Table of Contents IV Table of Contents IV 3/4 2-2 3/4 2-2 3/4 2-3 3/4 2-3 3/4 2-4 3/4 2-4*

3/4 2-5 3/4 2-5

)

3/4 2-6 3/4 2-6*

3/4 3-27 3/4 3-28 3/4 3-29 3/43-30-3/43-56 3/4 3 3/4 3-53*

3/4 10-2 3/4 10-2 3/4 10-4 3/4 10-4 8 3/4 3-2 B 3/4 3-2

Pages affected by rollover.

i I

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 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-23 Seismic Instrumentation...............

3/4 3-27 Meteorological Instrumentation 3/4 3-30 Remote Shutdown Instrumentation-...........

3/4 3-33 Post-Accident Instrumentation............

3/4 3-36 Fire Detection Instrumentation 3/4 3-40 Radioactive Gaseous Effluent Monitoring Instrumentation...................

3/4 3-45

-l Radioactive Liquid Effluent Monitoring Instrumentation...................

3/4 3-50 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 Shutdown 3/4 4......................

3/4.4.2 SAFETY VALVES....................

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

3/4 4 3/4.4.4 PRESSURIZER.....................

3/4 4-9 3/4.4.5 STEAM GENERATORS 3/4 4-10 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems..............

3/4 4-17 Reactor Coolant System Leakage 3/4 4-19 3/4.4.7 CHEMISTRY......................

3/4 4-21 3/4.4.8 SPECIFIC ACTIVITY..................

3/4 4-24 i

i a

i CALVERT CLIFFS - UNIT 1 IV Amendment No. 191

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

Verifying at least once per 31 days that the AXIAL SHAPE INDEX is maintained within the limits provided in the COLR, where 100' percent of the allowable power is the maximum allowable.

fraction of RATED THERMAL POWER as determined by the G, limit provided in the COLR.

4.2.1.4 Incore Detector Monitorina System - The Incore Detector Monitoring System may be used for monitoring the core power distribution by verifying that the incore detector Local Power Density alarms:

a.

Are adjusted to satisfy the requirements of the core power distribution map which shall be updated at least once per 31 days l

of accumulated operation in MODE 1.

b.

Have their alarm setpoint adjusted to protect the linear heat rate limit provided in the COLR when the uncertainty factors provided in the COLR are appropriately included in the setting of l

these alarms.

1 i

l i

1 CALVERT CLIFFS - UNIT 1 3/4 2-2 Amendment No. 191

i 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACTOR - FTy LIMITING CONDITION FOR OPERATION 3.2.2.1' The calculated value of P shall be within the limit provided in y

the COLR.

l APPLICABILITY: MODE 1*.

ACTION: With P outside the limit provided in the COLR, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months y

either:

a.

Withdraw and maintain the CEAs at or beyond the Long Tenn 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 FI, within the limits provided in the COLR, or 2.

Reduce THERMAL POWER to less than or equal to the limit established by the full core power distributMn monite-ing system 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 P shall be determined to be within its limit at the following y

intervals:

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 MODE 1, and l

Within four hours if the AZIMUTHAL POWER TILT (T,) is outside the c.

limit provided in Specification 3.2.4.

d.

At least once per 3 days of accumulated operation in MODE 1 when monitoring linear heat rate using the Excore Detector Monitoring System per Surveillance 4.2.1.3.

1 See Special Test Exception 3.10.2.

CALVERT CLIFFS - UNIT 1 3/4 2-3 Amendment No. 191

3/4.2 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.2.1.3 G shall be determined each time a calculation is required by using the inco,re detectors to obtain a power distribution map with all CEAs at or above the Long Term Steady State Insertion Limit. 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.

CALVERT CLIFFS - UNIT 1 3/4 2-4 Amendment No. 191 l

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - F!

LIMITING CONDITION FOR OPERATION

~

6 3.2.3 The calculated value of P, shal t the limits provided in t, e.

the COLR.

l APPLICABILITY: MODE l'.

ACTION: With P, outside the limits provided in the COLR, 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 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 P within the limits provided in the COLR and maintain th,e peripheral axial shape index within the DNB axial flux offset control limits provided in the COLR, or 2.

Reduce THERMAL POWER to less than or equal to the limit established by the full core power distribution monitoring system as a function of P,.

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

4.2.3.2 P

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

-)

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, and l

Within four hours if the AZIMUTHAL POWER TILT (T,) is outside the c.

limit given in Specification 3.2.4.

See Special Test Exception 3.10.2.

CALVERT CLIFFS - UNIT 1 3/4 2-5 Amendment No. 191

3/4.2 POWER DISTRIBUTION LIMITS SUAYEILLANCE REQUIREMENTS (Continued) 4.2.3.3 F, shall be determined each time a calculation is required by using the incore detectors to obtain a power distribution map with all CEAs at or above the Long Term Steady State Insertion Limit.

i l

l CALVERT CLIFFS - UNIT 1 3/4 2-6 Amendment No. 191 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.

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.

t 4.3.3.3.2 Each of the above seismic monitoring instruments actuated during a seismic event shall be restored to 0PERABLE 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 1

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.

i CALVERT CLIFFS - UNIT 1 3/4 3-27 Amendment No. 191 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 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-Ig i

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

3.

Seismic Acceleration Recorder a.

0-YRC-001 Control Room NA 1

b.

0-YR-001 Control Room NA 1

CALVERT CLIFFS - UNIT 1 3/4 3-28 Amendment No. 191 l

3/4.3 INSTRUMENTATION j

TABI.E 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 3-29 Amendment No. 191 l

l

1 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION

]

Meteoroloaical Instrumentation LIMITING COND TION 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.

CALVERT CLIFFS - UNIT 1 3/4 3-30 Amendment No. 191 l

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

WIND SPEED j

a.

Nominal Elev.10M 1

b.

Nominal Elev. 60M 1

2.

WIND DIRECTION 4

a.

Nominal Elev.10M 1

b.

Nominal Elev. 60M 1

3.

AIR TEMPERATURE - DELTA T (10M-60M) 1 CALVERT CLIFFS - UNIT 1 3/4 3-31 Amendment No. 191 l

3/4.3 INSTRUMENTATION TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 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 Elev.10M D

SA b.

Nominal Elev. 60M D

SA 3.

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

D SA CALVERT CLIFFS - UNIT 1 3/4 3-32 Amendment No. 191 l

7

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 sht11 be 4

demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6.

i CALVERT CLIFFS - UNIT 1 3/4 3-33 Amendment No. 191 l

-- 9

I

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g TA8LE 3.3-9 R

r,-

a g

REMOTE SHUTDOWN MONITORING INSTRUMENTATION

'w b

MINIMUM [

Q READOUT MEASUREMENT CHANNELS E

{

INSTRUMENT LOCATION RANGE OPERABLE E

=

1.

Wide Range Neutron Flux 1C43" 0.1 cps-200% power

1*

g g

Q 2.

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

Room 3.

Reactor Coolant Cold Leg IC43 212-705 F 1

Temperature 4.

Pressurizer Pressure IC43 0-4000 psia 1

g 5.

Pressurizer Level IC43 0-360 inches 1

6.

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

h 7.

Steam Generator Level IC43

-401 to +63.5 inches 1/ steam generator N

an 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 S

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

I

~

3/4.3 INSTRUMENTATION TABLE 4.3-6 REMOTE SHUTDOWN MONI'0 RING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL-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 6.

Steam Generator Level (Wide Range)

M R

7.

Steam Generator Pressure M

R CALVERT CLIFFS - UNIT 1 3/4 3-35 Amendment No. 191 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.

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.

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.

CALVERT CLIFFS - UNIT 1 3/4 3-36 Amendment No. 191 l

g TABLE 3.3-10 w

G g

POST-ACCIDENT MONITORING INSTRUMENTATION w

b MINIMUM T;

CHANNELS E

INSTRUMENT OPERABLE

' ACTION R

I 2

+

1.

Containment Pressure 2

31 g

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

s*

7.

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

1E. Core Exit Thermocouple System 2 locations / core quadrant 31 5

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 OPERABLE.

1

3/4.3 INSTRUMENTATION 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 ir. operable channel to OPERABLE ttatus 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 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 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 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 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; and 3.

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

CALVERT CLIFFS - UNIT 1 3/4 3-38 Amendment No. 191 l

b Q

TABLE 4.3-10 R

G g

POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS U

b CHANNEL CHANNEL q

INSTRUMENT CHECK CALIBRATION E

v, x

1.

Containment Pressure M

R g

E 2.

Wide Range Logarithmic Neutron Flux Monitor M

NA D

[

3.

Reactor Coolant Outlet Temperature M

P.

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 y

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

Ng

14. Reactor Vessel Water level M

NA k

15. Core Exit Thermocouple System M

R*

5 E

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

m

=

i-l l

3/4.3 _ INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Fire Detection Instrumentation LIMITINGCOND5TIONFOROPERATION 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 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 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 CHANNEL FUNCTIONAL TEST.

b.

Restore the inoperable instrument (s) to CPERABLE status within 14 days or prepare and submit a Special Report to the Commission 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 1 3/4 3-40 Amendment No. 191 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 j

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 at least once per 31 days.

l i

CALVERT CLIFFS - UNIT 1 3/4 3-41 Amendment No. 191 l

i

3/4.3 INSTRUMENTATION TABLE 3.3-11 FIRE DETECTION INSTRUMENTS UNIT 1 MINIMUM INSTRUMENTS OPERABLE

ROOM / AREA AUX BLDG.

INSTRUMENT LOCATION HEAT FLAME SM0KE 100/103/

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

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 Cor-idors &

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

3 222 Hot Instrument Shop 2

223 Hot Machine Shop 4

224 East Piping Area 10 225 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

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

CALVERT CLIFFS - UNIT 1 3/4 3-42 Amendment No. 191 l

3/4.3 INSTRUMENTATION i

TABLE 3.3-11 (Continued)

FIRE DETECTION INSTRUMENTS UNIT 1 MINIMUM INSTRUMENTS OPERABLE

ROOM / AREA AUX BLDG, INSTRUMENT LOCATION HEAT FLAME SMOKE 306/1C Cable Sp, reading Rm & Cable Chase 2

10 308 N/S Corridor 6

315 Main Steam Piping Area 6

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

6 318 Purge Air Supply Room 2

319/325 West Passage and Vestibule 6

320 Spent Fuel Heat Exchanger Room 3

323 Passage 27' Valve Alley &

Filter Rm 3

324 Letdown Heat Exchanger Rm 1

Elev. 27'-0" Switchgear Vent Duct 1

1A Cable Chase 1A 1

IB Cable Chase IB 1

405 Control Room 6

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 Are,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

430 Switchgear 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 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 automatically actuate Fire Suppression Systems.

CALVERT CLIFFS - UNIT 1 3/4 3-43 Amendment No. 191 l

3/4.3 INSTRUMENTATION TABLE 3.3-11 (Continued) j FIRE DETECTION INSTRUMENTS UNIT 1 MINIMUM INSTRUMENTS OPERABLE

ROOM / AREA AUX BLDG.

INSTRUMENT LOCATION HEAT FLAME SM0KE 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 Spant Fuel Pool Area Vent Equip 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 performance of Type A Containment Leakage Rate Tests.

Monitored by four protecto wires.

CALVERT CLIFFS - UNIT 1 3/4 3-44 Amendment No. 191 l

i 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radioactive Gaseous Effluent Monitorino Instrumentation l

LIMITINGCONDITIONFOROPERATION 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 and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-11.

CALVERT CLIFFS - UNIT 1 3/4 3-45 Amendment No. 191 l

l

t g

TABLE 3.3-12 R

G

^

g RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION w

H n

C E

C MINIMUM CHANNELS i

q INSTRUMENT OPERABLE APPLICABILITY ACTION E

m z

i 1.

WASTE GAS HOLDUP SYSTEM g

c a.

Noble Gas Activity Monitor - Providing 1

3S d

Alarm and Automatic Termination of E

Release b.

Effluent System Flow Rate Measuring 1

'36 Device 2.

MAIN VENT SYSTEM t'

a.

Noble Gas Activity Monitor 1

37 t'

b.

Iodine Sampler 1

38 c.

Particulate Sampler 1

38 E

a an g

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 I

pathway.

ACTION 36 -

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

via this pathway may continue provided the flow rate is i

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 3-47 Amendment No. 191 l

g TABLE 4.3-11 g

G g

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w

b M00 IN q

CHANNEL WHICH E

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE E

INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED 5

E D

~

1

-~*

I.

WASTE GAS HOLDUP SYSTEM E

a.

Noble Gas Activity Monitor -

P P

R(3)

SA )

U Providing Alam and Automatic Termination of Release D)

NA R

NA U

b.

Effluent System Flow Rate m2 Measuring Device Y

2.

MAIN VENT SYSTEM a.

Noble Gas Activity Monitor D

M R(3)

SA(2) f b.

Iodine Sampler W

NA NA NA c.

Particulate Sampler W

NA NA NA E

a R

ao f

==musam w-w

=

~

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.

i 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.

I3)

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.

(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.

r f

CALVERT CLIFFS - UNIT 1 3/4 3-49 Amendment No. 191 l

i

=

e 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radioactive Licuid Effluent Monitorina 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 alarm / 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 OFFSITE DOSE CALCULATION MANUAL (0DCM).

APPLICABILITY: At all times.

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel alann/ 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 3-50 Amendment No. 191 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 Birwdown Effluent 1

30 Line CALVERT CLIFFS - UNIT 1 3/4 3-51 Amendment No. 191 l

l

l 1

\\

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 i

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 perfomance curves may be used to estimate flow.

CALVERT CLIFFS - UNIT 1 3/4 3-52 Amendment No. 191 l

i 52 TABLE 4.3-12 E;

Eg f*

gg RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIRENENTS w

b$

CHNNNEL

'l CHANNEL SOURCE CHANNEL FUNCTIONAL E

y' INSTRUMENT CHECK CHECK CALIBRATION TEST gj c:

1.

GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM 52 y}

AND AUTOMATIC TERMINATION OF RELEASE

[j a.

Liquid Radwaste Effluent Line D

P RUO SAIU b.

Steam Generator Blowdown Effluent Line D

P RUO

'SAIU 2.

FLOW RATE MEASUREMENT DEVICES 10 a.

Liquid Radwaste Effluent Line D(3)

NA R

NA

[,*

$3 b.

Steam Generator Blowdown Effluent Line D)

NA R

NA I3 N

R n

e+

.if I

m a-.

-a

--w w

--P 4

-w-4 tr-w Tua

3/4.3 INSTRUNENTATION TABLE 4.3-12 (Continued)

TABLE NOTATION (1)

The CHANNEL FUNCTIONkL TEST shall also demonstrate that automatic I

isolation of this pathway and/or Control Room alam annunciation 1

occur if the appropriate following condition (s) exists:

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 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 range of energy and measurement range.

For subsequent CHANNEL o

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.

1 CALVERT CLIFFS - UNIT 1 3/4 3-54 Amendment No. 191 l

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.2 MODERATOR TEMPERATURE COEFFICIENT. CEA INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The moderator temperature coefficient, the CEA insertion and the power distribution limits of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.5, 3.1.3.6. 3.2.2, 3.2.3, and 3.2.4 may be suspended during the perfomance of PHYSICS TESTS provided:

a.

The THERMAL POWER is restricted to below 85% of RATED THERMAL POWER, and b.

The limits of Specification 3.2.1 are maintained and determined as specified in Specification 4.10.2.2 below.

APPLICABILITY: MODES I and 2.

ACTION: With any of the limits of Specification 3.2.1 being exceeded while the requirements of Specification 3.1.1.4, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, and 3.2.4 are suspended, either:

a.

Reduce THERMAL POWER sufficiently to satisfy the requirements of Specification 3.2.1, or b.

Be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

1 SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be detemined at least once per hour during PHYSICS TESTS in which the requirements of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.5, 3.1.3.6. 3.2.2, 3.2.3, or 3.2.4 are suspended and shall be verified to be within the test power plateau.

4.10.2.2 The linear heat rate shall be determined to be within the limits of Specification 3.2.1 by monitoring it continuously with the Incore Detector Monitoring System pursuant to the requirements of Specification 4.2.1.3 during PHYSICS TESTS above 5% of RATED THERMAL POWER in which the requirements of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, or 3.2.4 are suspended.

CALVERT CLIFFS - UNIT 1 3/4 10-2 Amendment No. 191

1 3/4.10 SPECIAL TEST EXCFPTIONS 3/4.10.4 CENTER CEA MISALIGNMENT LIMITING CONDITION FOR OPERATION

~

3.10.4 ~The requirements of Specifications 3.1.3.1 and 3.1.3.6 may be' suspended during the performance of PHYSICS TESTS to determine the isothermal temperature coefficient and power coefficient provided:

a.

Only the center CEA (CEA #1) is misaligned, and The limits of-Specification 3.2.1 are maintained and determined o

as specified in Specification 4.10.4.2 below.

APPLICABILITY: H0 DES 1 and 2.

ACTION: With any of the limits of Specification 3.2.1 being exceeded while the requirements of Specifications 3.1.3.1 and 3.1.3.6 are suspended,-

either:

a.

Reduce THERMAL POWER sufficiently to satisfy the requirements of Specification 3.2.1, or b.

Be in NOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.10.4.1 The THERMAL POWER shall be determined at least once per hour during PHYSICS TESTS in which the requirements of Specifications 3.1.3.1 and/or 3.1.3.6 are suspended and shall be verified to be within the test power plateau.

4.10.4.2 The linear heat rate shall be determined to be within the limits.

of Specification 3.2.1 by monitoring it continuously with the Incore-Detector Monitoring System pursuant to the requirements of Specification 4.2.1.3 during PHYSICS TESTS above 5% of RATED THERMAL POWER in which the requirements of Specifications 3.1.3.1 and/or 3.1.3.6 are suspended.

l CALVERT CLIFFS - UNIT 1 3/4 10-4 Amendment No. 191

3/4.3 INSTRUMENTATION BASES 3/4.3.3.3 Seismic Instrumentation The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly detennine the magnitude of a seismic event and evaluate the response of those features important to safety.

This capability is required to permit comparison cf the measured response to that used in the design basis for the facility and is consistent with the recomendations of Regulatory Guide 1.12 " Instrumentation for Earthquakes," April 1974.

3/4.3.3.4 Meteorological Instrumentation The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.

This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs," February 1972, as supplemented by Supplement 1 to NUREG-0737.

3/4.3.3.5 Remote Shutdown Instrumentation The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the Control Room.

This capability is required in the event Control Room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR Part 50.

3/4.3.3.6 Post-Accident Instrumentation The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recomendations of Regulatory Guide 1.97,

" Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975, and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

CALVERT CLIFFS - UNIT 1 B 3/4 3-2 Amendment No. 191

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 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-23 Seismic Instrumentation..............

3/4 3-27 Meteorological Instrumentation 3/4 3-30 Remote Shutdown Instrumentation..........

3/4 3-33 Post-Accident Instrumentation...........

3/4 3-36 Fire Detection Instrumentation 3/4 3-40 Radioactive Gaseous Effluent Monitoring Instrumentation..................

3/4 3-44 l

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

3/4 3-49 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 4-9 3/4.4.5 STEAM GENERATORS 3/4 4-10 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems.............

3/4 4-17 Reactor Coolant System Leakage 3/4 4-19 3/4.4.7 CHEMISTRY.....................

3/4 4-21 3/4.4.8 SPECIFIC ACTIVITY.................

3/4 4-24 1

CALVERT CLIFFS - UNIT 2 IV Amendment No. 168 J

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

Verifying at least once per 31 days that the AXIAL SHAPE INDEX is maintained within the limits provided in the COLR, where 100 percent of the allowable power is the maximum allowable

-' fraction of RATED THERMAL POWER as determined by the P limit y

provided in the COLR.

4.2.1.4 Incore Detector Monitorino System - The Incore Detector Monitoring System may be used for monitoring the core power distribution by verifying that the incore detector Local Power Density alarms:

a.

Are adjusted to satisfy the requirements of the core power distribution map which shall be updated at least once per 31 days l

of accumulated operation in MODE 1.

b.

Have their alam setpoint adjusted to protect the linear heat rate limit provided in the COLR when the uncertainty factors provided in the COLR are appropriately included in the setting of l

these alams.

CALVERT CLIFFS - UNIT 2 3/4 2-2 Amendment No. 168

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACTOR - FT, LIMITING CONDITION FOR OPERATION 3.2.2.1 The calculated value of P shall be within the limit provided in y

the COLR.

l APPLICABILITY: MODE 1*.

ACTION: With P outside the limit provided in the COLR, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months y

either:

a.

Withdraw and maintain the 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 POWERandFLwithinthelimitsprovidedintheCOLR,or 2.

Reduce THERMAL POWER to less than or equal to the limit established by the full core power distribution monitoring systemasafunctionofFL;or 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 P shall be determined to be within its limit at the following y

intervals:

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 MODE 1, and l

Within four hours if the AZIMUTHAL POWER TILT (T,) is outside the c.

limit provided in Specification 3.2.4.

d.

At least once per 3 days of accumulated operation in MODE 1 when monitoring linear heat rate using the Excore Detector Monitoring System per Surveillance 4.2.1.3.

See Special Test Exception 3.10.2.

CALVERT CLIFFS - UNIT 2 3/4 2-3 Amendment No. 168

3/4.2 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.2.1.3 6 shall be determined each time a calculation is required by using the inc, ore detectors to obtain a power distribution map with all CEAs at or ab'ov~e the Long Term Steady State Insertion-Limit. 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.

l 9

1 i

CALVERT CLIFFS - UNIT 2 3/4 2-4 Amendment No. 168 l

\\

l

-=

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR - FJ LIMITING CONDITION FOR OPERATION Ti$e~ calculated value of P, shall be within the limits provided 'in 3.2.3 the COLR.

l APPLICABILITY: MODE 1*.

ACTION: With P, outside the limits provided in the COLR, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

a.

Be in at least NOT STANDBY, or b.

Withdraw and maintain the 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 P, within the limits provided in the COLR, and maintain the peripheral axial shape index within the DNB axial flux offset control limits provided in the COLR, or 2.

Reduce THERMAL POWER to less than or equal to the limit established by the full core power distribution monitoring system as a function of P,.

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

4.2.3.2 P intervals, shall be detennined to be within its limit at the following a.

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

i b.

At least once per 31 days of accumulated operation in MODE 1, and l

c.

Within four hours if the AZIMUTHAL POWER TILT (T,) is outside the limit given in Specification 3.2.4.

See Special Test Exception 3.10.2.

l CALVERT CLIFFS - UNIT 2 3/4 2-5 Amendment No. 168

1 s

3/4.2 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.3.3 F, shall be determined each time a calculation is required by using the incore detectors to obtain a power distribution map with all CEAs at or above the Long Term Steady State Insertion Limit.

i CALVERT CLIFFS - UNIT 2 3/4 2-6 Amendment No. 168 l

i 3/4.3 INSTRUMENTATION i

1 3/4.3.3 MONITORING INSTRUMENTATION Seismic Instrumentation LIMITINGCONDITIONFOROPEitATION 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 applicable.

t i

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 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.

l CALVERT CLIFFS - UNIT 2 3/4 3-27 Amendment No. 168 l

E

3/4.3 INSTRUMENTATION I

TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION j

MINIMUM MEASUREMENT INSTRUMENT INSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE 1.

Triaxial Time-History Strong Motion Accelographs a.

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

b.

0-YE-002 Unit 1 Containment 69' 0-19 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-Ig i

2.

Triaxial Seismic Switches a.

0-YS-001 Unit 1 Containment Base NA 1

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

CALVERT CLIFFS - UNIT 2 3/4 3-28 Amendment No. 168 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 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 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 b.

0-YR-001 Control Room M

R SA

- Verify instrument energized.

Except seismic trigg u.

CALVERT CLIFFS - UNIT 2 3/4 3-29 Amendment No. 168 l

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Meteorological 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 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 perfonnance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-5.

CALVERT CLIFFS - UNIT 2 3/4 3-30 Amendment No. 168 l

l 3/4.3 INSTRUMENTATION TABLE 3.3-8

,

METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE 1.

WIND SPEED a.

Nominal Eley. 10M 1

b.

Nominal Elev. 60M 1

2.

WIND DIRECTION a.

Nominal Elev.10M 1

b.

Nominal Elev. 60M 1

3.

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

I I

I CALVERT CLIFFS - UNIT 2 3/4 3-31 Amendment No. 168 l

3/4.3 INSTRUMENTATION TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 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 Elev.10M D

SA b.

Nominal Elev. 60M D

SA 3.

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

D SA 1

l CALVERT CLIFFS - UNIT 2 3/4 3-32 Amendment No. 168 l

l

i 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 H0T 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 3-33 Amendment No. 168 l

9 TABLE 3.3-9 w

G P

g REMOTE SHUTDOWN MONITORING INSTRUMENTATION w

n HINIMUM i.

E C

READOUT MEASUREMENT CHANNELS <

El

?

INSTRUMENT LOCATION RANGE OPERABLE E

I x

1.

Wide Range Neutron Flux

2C43 0.1 cps-200%

1 9

E 2.

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

$w w

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 Y

7.

Steam Generator Level 2C43

-401 to +63.5 inches 1/ steam generator F

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

m

=.

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

Steam Generator Level M

R 7.

Steam Generator Pressure M

R CALVERT CLIFFS - UNIT 2 3/4 3-35 Amendment No. 168 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.

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.

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

i l

i CALVERT CLIFFS - UNIT 2 3/4 3-36 Amendment No. 168 l

9 TABLE 3.3-10 w

G P

g POST-ACCIDENT MONITORING INSTRUMENTATION w

n E

C MINIMUM Ej Q

CHANNELS E

INSTRUMENT OPERABLE ACTION i5i 8

2-1.

Containment Pressure 2

31 g

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 Nbnitor 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

[

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

14. Reactor Vessel Water Level 2*

34, 35

?

15. Core Exit Thermocouple System 2 locations / core quadrant 31 5

h 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 OPERABLE.

-,_m.____-.

3/4.3 INSTRUMENTATION 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 I

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 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 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 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.

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 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 l

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.

l CALVERT CLIFFS - UNIT 2 3/4 3-38 Amendment No. 168 l

l

4 9

TABLE 4.3-10 g

G g

POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w

b CHANNEL CH EL q

INSTRUMENT CHECK CALIBRA*. ION E

v, x

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 R

7.

Steam Generator Level (Wide Range)

M R

a

=

w 8.

Auxiliary Feedwater Flow Rate M

R M

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 t

13. Containment Water Level (Wide Range)

M R

Ng

14. Reactor Vessel Water Level M

NA

15. Core Exit Themocouple System M

R*

z The perfomance of a CHANNEL CALIBRATION operation exempts the Core Exit Themocouple but includes all electronic components. The Core Exit Therinocouple shall be calibrated prior to

-8 installation in the reactor core.

h y

n_- _

__o.

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Fire Detection Instrumentation LIMITING'COND5TIONFOROPERATION 3.3.3.7 As a minimum, the fire detection instrumentation for each fire i

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 alanned 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 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 3-40 Amendment No. 168 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 at least once per 31 days.

CALVERT CLIFFS - UNIT 2 3/4 3-41 Amendment No. 168 l

3/4.3 INSTRUMENTATION TABLE 3.3-11 FIRE DETECTION INSTRUMENTS

~

UNIT 2 MINIMUM INSTRUMENTS OPERABLE

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" 1

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 Cable, Spreading Rm & Cable Chase 2

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

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 2B 1

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

Detectors which automatically actuate Fire Suppression Systems.

CALVERT CLIFFS - UNIT 2 3/4 3-42 Amendment No. 168 l

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

El ey. 45'-0" Switchgear Vent Duct 1

526 Main Plant Exhaust Equip Rm 8

527 Containment Access 3

532 Electrical Equip Rm 3

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

Elev. 83'-0" Cable Tunnel 4

605 Auxiliary Feedwater Pump Rm 2

j Containment Bldo.

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 E;ev 3'-0" Unit 2 Side 24

[

F 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.

4

+

Monitored by four protecto wires.

CALVERT CLIFFS - UNIT 2 3/4 3-43 Amendment No. 168 l

3/4.3 INSTPf*3TATION 3/4.3.3 MONUORING INSTRUMENTATION Rajioactive 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 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 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 OPERAR'" by perfomance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-11.

CALVERT CLIFFS - UNIT 2 3/4 3-44 Amendment No. 168 l

.1 r

g TABLE 3.3-12 R

G g

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION w

E n

C MINIMUM CHANNELS Q

INSTRUMENT OPERABLE APPLICABILITY ACTION E-en 1

i 1.

WASTE GAS HOLDUP SYSTEM G5 c-5 a.

Noble Gas Activity Monitor - Providing 1

35 d

i Alann and Automatic Tennination of E

Release b.

Effluent System Flow Rate Measuring 1

36 Device 2.

MAIN VENT SYSTEM R

^

a.

Noble Gas Activity Monitor 1

37 i

Y$

b.

Iodine Sampler 1

38 c.

Particulate Sampler 1

38 E

a R

en E

ea

.z-ro

.m_,_

~

~..m

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 ".hannels OPERABLE requirement, the contents of the tank (s) m;y 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 2 3/4 3-46 Amendment No. 168 l

1

-j g

TABLE 4.3-11 R

G g

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w

n MODES IN E

1 C

CHANNEL-WHICH A

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE.

E INSTRUMENT CHECK CNECK CALIBRATION TEST REQUIRED R

i g

C 5'i 1.

WASTE GAS HOLDUP SYSTEM d

E' R)

SA )

I3 U

a.

Noble Gas Activity Monitor -

P P

Providing Alam and Automatic Temination of Release D)

NA R

NA U

b.

Effluent System Flow Rate Measuring Device mA 2.

MAIN VENT SYSTEM

+

k I3 R)

SA(2) a.

Noble Gas Activity Monitor D

M b.

Iodine Sampler W

NA NA NA c.

Particulate Sampler W

NA NA NA p

a a.

E m

t l

l

i

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

For subsec;uent 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 3-48 Amendment No. 168 l

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radioactive Liauid Effluent Monitorina Instrumentation LIMITINGCOND5TIONFOROPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / 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 OFFSITE DOSE CALCULATION MANUAL (ODCM).

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 2 3/4 3-49 Amendment No. 168 l

3/4.3 INSTRUMENTATION TABLE 3.3-13 RADIDACTIVE 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 CALVERT CLIFFS - UNIT 2 3/4 3-50 Amendment No. 168 l

l 3/4.3 INSTRUMENTATION TABLE 3.3-13 (Continued)

ACTION STATEMENTS ACTION 2 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 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 3-51 Amendment No. 168 l

52 TABLE 4.3-12 kg Ci f'

gg RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

'3 BE c,

E; CHANNEL SOURCE CHANNEL FUNCTIONAL tl 01 INSTRUMENT CHECK CHECK CALIBRATION

_ TEST E!

u, an I.

GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM Q

i gg AND AUTOMATIC TERMINATION OF RELEASE j{

f a.

Liquid Radwaste Effluent Line D

P RUO SA(U

!E b.

Steam Generator Blowdown Effluent Line D

P RDO IU

,SA 2.

FLOW RATE MEASUREMENT DEVICES 4

a.

Liquid Radwaste Effluent Line DIU NA R

NA

'j b.

Steam Generator Blowdown Effluent Line DID NA R

NA M

i a

Bn m

i 5

e

=

3/4.3 INSTRUMENTATION TABLE 4.3-12 (Continued)

TABLE NOTATION II)

The CHANNEL FUNCTION L 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.

i 2.

Circuit failure.

3.

Instrument indicates a downscale failure.

(2)

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.

j (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.

CALVERT CLIFFS - UNIT 2 3/4 3-53 Amendment No. 168 l

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.2 MODERATOR TEMPERATURE COEFFICIENT. CEA INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPEP.;iION 3.10.2 The moderator 'e'.erature coefficient, the CEA insertion and the 1

power distribution lim,-

?.' Specifications 3.1.1.4, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, and 3.2.4 may be suspended during the perfomance of PHYSICS TESTS provided:

a.

The THERMAL POWER is restricted to below 85% of RATED THERMAL POWER, and b.

The limits of Specification 3.2.1 are maintained and determined as specified in Specification 4.10.2.2 below.

l APPLICABILITY: MODES 1 and 2.

ACTION: With any of the limits of Specification 3.2.1 being exceeded while the requirements of Specification 3.1.1.4, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, and 3.2.4 are suspended, either-a.

Reduce THERMAL POWER sufficiently to satisfy the requirements of Specification 3.2.1, or b.

Be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be detemined at least once per hour during PHYSICS TESTS in which the requirements of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, or 3.2.4 are suspended and shall be verified to be within the test power plateau.

4.10.2.2 The linear heat rate shall be determined to be within the limits of Specification 3.2.1 by monitoring it continuously with the Incore Detector Monitoring System pursuant to the requirements of Specification 4.2.1.3 during PHYSICS TESTS above 5% of RATED THERMAL POWER in which the requirements of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, or 3.2.4 are suspended.

CALVERT CLIFFS - UNIT 2 3/4 10-2 Amendment No. 168

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.4 CENTER CEA MISALIGNMENT LIMITING CONDITION FOR OPERATION 3.10.4 ~The requirements of Specifications 3.1.3.1 and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS to determine the isothermal temperature coefficient and power coefficient provided:

a.

Only the center CEA (CEA #1) is misaligned, and b.

The limits of Specification 3.2.1 are maintained and determined as specified in Specification 4.10.4.2 below.

APPLICABILITY: MODES 1 and 2.

ACTION: With any of the limits of Specification 3.2.1 being exceeded while the requirements of Specifications 3.1.3.1 and 3.1.3.6 are suspended, either:

a.

Reduce THERMAL POWER sufficiently to satisfy the requirements of Specification 3.2.1, or b.

Be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.10.4.1 The THERMAL POWER shall be determined at least once per hour during PHYSICS TESTS in which the requirements of Specifications 3.1.3.1 and/or 3.1.3.6 are suspended and shall be verified to be within the test power plateau.

4.10.4.2 The linear heat rate shall be determined to be within the limits of Specification 3.2.1 by monitoring it continuously with the Incore Detector Monitoring System pursuant to the requirements of Specification 4.2.1.3 during PHYSICS TESTS above 5% of RATED THERMAL POWER in which the requirements of Specifications 3.1.3.1 and/or 3.1.3.6 are suspended.

CALVERT CLIFFS - UNIT 2 3/4 10-4 Amendment No. 168

3/4.3 INSTRUMENTATION BASES 3/4.3.3.3 ~

~

Seismic Instrumentation The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.

This capability is required to permit comparison of the measured response to that used in the design basis for the facility and is consistent with the recomendations of Regulatory Guide 1.12 " Instrumentation for Earthquakes," April 1974.

3/4.3.3.4 Meteoroloaical Instrumentation The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, "Onsite Meteorological Programs," February 1972, as supplemented by Supplement I to NUREG-0737.

3/4.3.3.5 Remote Shutdown Instrumentation The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to pennit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the Control Room.

This capability is required in the event Control Room habitability is lost 4

and is consistent with General Design Criteria 19 of 10 CFR Part 50.

3/4.3.3.6 Post-Accident Instrumentation The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recomendations of Regulatory Guide 1.97

" Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident," December 1975, and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

l CALVERT CLIFFS - UNIT 2 B 3/4 3-2 Amendment No. 168

.

ML20072L373

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