Text

Amends 199 & 176 to Licenses DPR-53 & DPR-69,respectively, Deleting TSs 3/4.3.3.3,6.9.2.b,6.9.2.d & Bases 3/4.3.3.3, Which Provide Requirements for Operation & Testing of Seismic Monitoring Instrumentation
	ML20076K746
Person / Time
Site:	Calvert Cliffs
Issue date:	10/21/1994
From:	Marsh L; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20076K749	List: ML20076K746; ML20076K756;
References
	NUDOCS 9411020078
	Download: ML20076K746 (62)
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ef,""4(g 4

UNITED STATES g*)

NUCLEAR REGULATORY COMMISalON

- WASHINGTON, D.C. 20555-0001

@ l BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317

_ALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 199 s

License No. DPR-53 1.

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

A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated August 4, 1994, 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, 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 (1) 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 Comission'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 j

51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

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

J 9411020078 941021 PDR ADDCK 05000317 p

PDR

{

.. 2.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.199, 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 Ledyard B. Marsh, Director.

Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: October 21, 1994

f."CW g

y-

-t UNITED STATES j

j NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D.C. 2055!HX)01 49.....,o BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.176 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 August 4, 1994, 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 (1) 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 te 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 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:

. 2.

Technical Specifications,

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 176, 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 C0FtMISSION Ledyard B. Marsh, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: October 21, 1994 i

i

ATTACHMENT-TO LICENSE AMENDMENTS AMENDMENT NO. 199 FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 176 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NOS. S'0-317 AND 50-318 Revise Appendix A as follows:

Remove Paaes Insert Paaes DRP-53 DRP-53 IV.

IV 3/4 3-27 thru 3-29 3/4 3-30 thru 3-54 3/4 3/27 thru 3-51*

B 3/4 3-2 B 3/4 3-2 B 3/4 3-3 thru 3-4 8 3/4 3-3*

6-26 6-26 DRP-69 DRP-69 IV IV 3/4 3-27 thru 3-29 3/4 3-30 thru 3-53 3/4 3-27 thru 3-50*

B 3/4 3-2 8 3/4 3-2 B 3/4 3-3 thru 3-4 8 3/4 3-3*

6-26 6-26

Rollover pages - vertical line at amendment number indicating rollover page with ne technical specification changes.

4

)

l i

TABLE 0F 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 Meteorological Instrumentation 3/4 3-27 Remote Shutdown Instrumentation...........

3/4 3-30 Post-Accident Instrumentation............

3/4 3-33 Fire Detection Instrumentation 3/4 3-37 Radioactive Gaseous Effluent Monitoring Instrumentation..............-.....

3/4 3-42 l

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

3/4 3-47 l

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION 1

STARTUP And POWER OPERATION.............

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

3/4 4-2 Shutdown 3/4 4......................

1 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 CALVERT CLIFFS - UNIT 1 IV Amendment No. 199

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 Commirsion pursuant to Specification 6.9.2 within the next 10 days outi ning the cause of the malfunction and the i

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 3-27 Amendment No. 199 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. 60H 1

2.

WIND DIRECTION a.

Nominal Elev.10M 1

b.

Nominal Elev. 60M 1

3.

AIR TEMPERATURE - DELTA T (10M-60M) 1 CALVERT CLIFFS - UNIT 1 3/4 3-28 Amendment No. 199 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 3-29 Amendment No. 199 l

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.g, 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 shell 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 1 3/4 3-30 Amendment No. 199 l

t 9

TABLE 3.3-9 R

G

g REMOTE SHUTDOWN MONITORING INSTRUMENTATION w

b

. MINIMUM q

READ 0UT MEASUREMENT CHANNELS y

INSTRUMENT LOCATION RANGE OPERABLE k

1.

Wide Range Neutron Flux IC43*

0.1 cps-200% power

1*

g Z

2.

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

[o Room 3.

Reactor Coolant Cold Leg 1C43 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 m

h 7.

Steam Generator Level IC43

-401 to +63.5 inches 1/ steam generator 1

l l

N l

E l

m i?

=

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 l

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

3 u

s

- -a 4

t-nu 6

e

1 s

?

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

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 i

CALVERT CLIFFS - UNIT 1 3/4 3-32 Amendment No. 199 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 perfomance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-10.

CALVERT CLIFFS - UNIT 1 3/4 3-33 Amendment No. 199 l

g TABLE 3.3-10 R

G P

g POST-ACCIDENT MONITORING INSTRUMENTATION w

n lii!

C MINIMUM 4

CHANNELS E

INSTRUMENT OPERABLE ACTION ili 6

lK 1.

Containment Pressure 2

31

[:

g U

2.

Wide Range Logarithmic Neutron Flux Monitor 2

31 y

3.

Reactor Coolant Outlet Temperature 2

31 4.

Pressurizer Pressure 2

31 5.

Pressurizer Level 2

31 6.

Steam Generator Pressure 2/ steam generator 31 m

7.

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

8.

Auxiliary Feedwater Flow Rate 2/ steam generator 31 9.

RCS Subcooled Margin Monitor 1

31

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

11. PORY Solenoid Power Indication 1/ valve 31

12. Feedwater Flow 2

31 k

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

14. Reactor Vessel Water Level 2*

34, 35 5

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

A channel has eight sensors in a probe. A channel is OPERABLE if four or more sensors, one or 8

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

l

7

'3/4.3' INSTRUMENTATION j

i TABLE 3.3-10 (Continued)

ACTION STATEMENT $

ACTION 31 -

With the number of OPERABLE post-accident monitoring...

l channels less than required by Table 3.3-10, either restore the inoperable channel to OPERABLE status within 30 days or be in NOT 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 0PERABLE requirement in Table 3.3-10, operation may' proceed provided the inoperable channel is restored to 0PERABLE status at the next outage of sufficient duration.

i i

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 0PERABLE status within l

30 days or be in HOT SHUTD0WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l ACTION 34 -

With the number of OPERABLE post-accident monitoring i

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 p npare 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 0PERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months if repairs are feasible i

without shutting down or:

1.

Initiate an alternate method of monitoring for core and 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 3-35 Amendment No. 199 l

9 TABLE 4.3-10 R

G

?

g POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w

e b

CHANNEL CNAl81EL

]

INSTRUMENT CHECK CALIBRATION E"

i 1.

Containment Pressure M

R E

2.

Wide Range Logarithmic Neutron Flux Monitor M

NA

[

3.

Reactor Coolant Outlet Temperature M

R-E f

4 4.

Pressurizer Pressure M

R l

S.

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

9.

RCS Subcooled Margin Monitor M

R

10. PORV/ Safety Valve Acoustic Nbnitor NA R

11. PORY Solenoid Power Indication NA NA

12. Feedwater Flow M

R

13. Containment Water Level (Wide Range)

M R

14. Reactor Vessel Water level M

NA

15. Core Exit Thermocouple System M

R*

5 The perfonnance of a CNANNEL CALIBRATION operation exempts the Core Exit Thennocouple but

-3 includes all electronic components. The Core Exit Thennocouple shall be calibrated prior to j

installation in the reactor core.

1 l

l

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

APPLICABILITY: Whenever equipment in that fire detectio. 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 alamed 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 alam 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 Commission pursucnt 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 25Ss of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE by perfomance of a CHANNEL FUNCTIONAL TEST.

Detectors selected for testing shall be selected on a rotating basis such CALVERT CLIFFS - UNIT 1 3/4 3-37 Amendment No. 199 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 OPERA 8LE 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 OPERA 8LE at least once per 31 days.

)

CALVERT CLIFFS - UNIT 1 3/4 3-38 Amendment No. 199 l

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 Famp Room 3

118/122 ECCS Pump Room 7

119/123 ECCS Pump koom 7

200/202 Corridors, &

209/210 Corridors &

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

216 Reactor Coolant Make-up Pumps 1

217 Boric Acid Tank & Pump Room 2

218 Volume Control Tank Room 1

220 Degasifier Pump Room 1

221/326 West Piping Penetration Room 2

3 222 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 perfonnance of Type A Containment Leakage Rate Tests.

CALVERT CLIFFS - UNIT 1 3/4 3-39 Amendment No. 199 l

3/4.3 INSTRUMENTATION TABLE 3.3-11 (Continued) l FIRE DETECTION INSTRUMENTS 1

l UNIT 1 MINIMUM INSTRUMENTS OPERABLE

ROOM / AREA AUX BLDG.

INSTRUMENT LOCATION HEAT FLAME SM0KE 306/1C Cable Sp, reading Rm & Cable Chase 2

10 308 N/S Corridor 6

315 Main Steam Piping Area 6

317 Switchgear Ropp, 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 Arp,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 Switchgep,r Room Elev 45'-0" 8

439 Refueling Water Tank Pump Rm 2

441 Spent Resin Metering Tank Rm 1

Elev 45'-0" Switchgear Vent Duct 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 3-40 Amendment No. 199 l

3/4.3 INSTRUMENTATION TABLE 3.3-11 (Continued)

FIRE DETECTION INSTRUMENTS i

UNIT 1 MINIMUM INSTRUMENTS OPERABLE

R0OM/ AREA.

AUX BLDG.

INSTRUMENT LOCATION HEAT FLAME SM0KE i

Elev 69'-0" Control Room Vent Duct "A" 1

Elev 69'-0" Cable Spreading Room Vent 1

Duct i

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, 1

591 Clothing Disposal, and 523/594 Corridors 20 520 Spent 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 1

Rm 3

Elev 83'-0" Cable Tunnel 4

603 Auxiliary Feedwater Pump Rm 2

Containment Blda.

i U-1 RCP Bay East

16 U-1 RCP Bay West J*6 U-1 East Electric Pen Area" i

U-1 West Electric Pen Area i

Intake Structure Elev 3'-0" Unit 1 Side 24 Detection instruments located within the containment are not required i

to be OPERAELE durino the performance of Type A Containment Leakage i

Rate Tests.

Monitored by four r. M.e:to wires.

i CALVERT CLIFFS - UNIT 1 3/4 3-41 Amendment No. 199 l

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radioactive Gaseous Effluent Monitorina 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 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 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 5etpoint 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.*.9 Each radioactive gaseous effluent monitoring instrumentation i

channel shall be demonstrated dPERABLE by performance 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 3-42 Amendment No. 199 l

Q TABLE 3.3-12 R

G

?

g RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION

<d E

n C

MINIMUM CNANNELS

!Q

]

INSTRUMENT OPERABLE APPLICABILITY ACTION E

i 1.

WASTE GAS HOLDUP SYSTEM j

c 5

a.

Noble Gas Activity Monitor - Providing 1

35 d

Alam and Automatic Termination of E

~

Release b.

Effluent System Flow Rate Measuring 1

36 Device 2.

MAIN VENT SYSTEM a.

Noble Gas Activity Monitor 1

37 Y

i; b.

Iodine Sampler 1

38 a

c.

Particulate Sampler 1

38 j

g g-

+

i an

(

W o

_s-

.v----

w,-

---._.%-,..+v.---

.--,m w

a er

. c

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 i

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.

l Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 -

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

ACTION 37 -

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

ACTION 38 -

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

CALVERT CLIFFS - UNIT 1 3/4 3-44 Amendment No. 199 l

g TABLE 4.3-11 w

G g

RADI0 ACTIVE GASEOUS EFFLUENT NONITORING INSTRUNENTATION SURVEILLANCE REQUIRENENTS w

E n

C MODES IN

'Q q

CNANNEL WNICH E

CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE R

INSTRUNENT CHECK CHECK CALIBRATION TEST REQUIRED 5

c-i'i d.

[

1.

WASTE GAS HOLDUP SYSTEM E

a.

Noble Gas Activity Monitor -

P P

R(3)

SAID Providing Alann and Automatic Termination of Release b.

Effluent System Flow Rate DN NA R

NA m2 Measuring Device

'r' 2.

MAIN VENT SYSTEM

=*

R)

SA )

I3 I2 a.

Noble Gas Activity Monitor D

M b.

Iodine Sampler W

NA NA NA c.

Particulate Sampler W

NA NA NA N

B n

l

A 3/4.3 INSTRUNENTATION TABLE 4.3-11 (Continued)

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

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

1.

Instrument indicates measure levels above the alam/ trip setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

(2)

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

1.

Instrument indicates measured levels above the alann 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 htye been obtained from suppliers that participate in measurement assarance 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 madh.

i CALVERT CLIFFS - UNIT 1 3/4 3-46 Amendment No. 199 l

i 3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radioactive Licuid Effluent Monitorino Instrumentation LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their 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 alarm / trip setpoint less conservative than required by the above Specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

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

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

c.

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

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 3-47 Amendment No. 199 l

3/4.3 INSTRUMENTATION TABLE 3.3-13 RADI0 ACTIVE LIQUID EFFLUENT N0NITORING INSTRUMENTATION MINIMUM CNANNELS INSTRUMENT OPERABLE ACTION 1.

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

Liquid Radwaste Effluent Line 1

28 b.

Steam Generator Blowdown Effluent 1

29 Line 2.

FLOW RATE MEASUREMENT DEVICES a.

Liquid Radwaste Effluent Line 1

30 b.

Steam Generator Blowdown Effluent 1

30 Line e

CALVERT CLIFFS - UNIT 1 3/4 3-48 Amendment No. 199 l

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

ACTION STATEMENTS 1

ACTION 28 -

With the number of channels OPERABLE less. than required by the Minimum Channels 0PERABLE 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 0PERABLE less than required by the Minimum Channels 0PERABLE 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 microcuric/ gram DOSE EQUIVALENT I-131.

ACTION 30 -

With the number of channels 0PERABLE less than required by the Minimum Channels 0PECABLE 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.

t CALVERT CLIFFS - UNIT 1 3/4 3-49 Amendment No. 199 l-

g TABLE 4.3-12 R

G g

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w

E n

C CNANNEL

!Q Q

CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST b

1.

GROSS RADIOACTIVITY MONITORS PROVIDING ALARM h

}

AND AUTOMATIC TERMINATION OF RELEASE y

a.

Liquid Radwaste Effluent Line D

P R(2)

SA )

U

~

b.

Steam Generator Blowdown Effluent Line D

P R(2) 34 )

0 2.

FLOW RATE MEASUREMENT DEVICES R

a.

Liquid Radwaste Effluent Line D(3)

NA R

NA h

b.

Steam Generator Blowdown Effluent Line D)

NA R

NA I3 a

an W

M

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

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

1 1.

Instrument indicates measured levels above the alarm / trip.

setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

(2)

The initial CHANNEL CALIBRATION shall be 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 ptrticipate in measurement assurance activities with NBS. These standards shall permit calibrating the system within its intended-range of energy and measurement range.

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

(3)

CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which effluent releases are made.

l i

P f

5 CALVERT CLIFFS - UNIT 1 3/4 3-51 Amendment No. 199 I

-3/4.3 INSTRUMENTATION BASES

.o 3/4.3.3.4 Meteoroloaical Instrumentation The OPERASILITY 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 recommendations 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."

The Subcooled Margin Monitor (SMM), the Heated Junction Thermocouple (HJTC), and the Core Exit Thermocouples (CET) comprise the Inadequate Core Cooling (ICC) instrumentation required by Item II.F.2 NUREG-0737, the Post TMI-2 Action Plan.

The function of the ICC instrumentation is to enhance the ability of the plant operator to diagnose the approach to, and recovery from ICC. Additionally, they aid in tracking reactor coolant inventory.

These instruments are included in the Technical Specifications at the request of NRC Generic Letter 83-37. These instruments are not required by_

the accident analysis, nor to bring the plant to NOT STANDBY or COLD SHUTDOWN.

l I

i CALVERT CLIFFS - UNIT 1 B 3/4 3-2 Amendment No. 199

3/4.3 INSTRUMENTATION BASES In the event more than four sensors in a Reactor Vessel Level channel are inoperable.. repairs may only be possible during: an, extended COLD,SHUTD9WN.

This is because the sensors are accessible only after the plant has been cooled down and drained, and the missile shield has been moved.

If only one channel is iroperable, it should be restored to OPERABLE status,in accordance with the schedule outlined in a Special Report.

If both.,

i channels are inoperable, the system shall be restored to OPERABLE status in the next refueling outage.

3/4.3.3.7 Fire Detection Instrumentation OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program, i

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.

j 3/4.3.3.9 Radioactive Gaseous Effluent Monitoring Instrumentation The radioactive gaseous effluent instrumentation is provided to mcnitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alam/ trip setpoints for these instruments shall be calculated and adjusted I

in accordance with the methodology and parameters in the ODCM to ensure that the alam/ trip will occur prior to exceeding the limits of Specification 3.11.2.1.a based on average annual X/Q. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.3.10 Radioactive Licuid Effluent Monitoring Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

The alam/ trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

I J

CALVERT CLIFFS - UNIT 1 B 3/4 3-3 Amendment No. 199 l

)

6.0 ADMINISTRATIVE CONTROLS (c)

Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated February 7,1989, "Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket 50-318, Request for Amendment, Unit 2 Ninth Cycle License Application" (d)

Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated January 10, 1990, " Safety Evaluation Report Approving Unit 2 Cycle 9 License Application" c.

The core operating limits shall be detemined such that all applicable limits (e.g., fuel themal mechanical limits, core themal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the NRC Regional Office within the time period specified for each report.

These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

I c.

Inoperable Meteorological Instrumentation, Specification 3.3.3.4.

I e.

Core Barrel Movement, Specification 3.4.11.

f.

Fire Detection Instrumentation, Specification 3.3.3.7.

g.

Fire Suppression Systems, Specifications 3.7.11.1, 3.7.11.2, 3.7.11.3, 3.7.11.4, and 3.7.11.5.

h.

Penetration Fire Barriers Specification 3.7.12.

i. Steam Generator Tube Inspection Results, Specification 4.4.5.5.a and c.

J.

Specific Activity of Primary Coolant, Specification 3.4.8.

CALVERT CLIFFS - UNIT 1 6-26 Amendment No. 199

1 l

TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE l

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

3/4 3-30 Post-Accident Instrumentation...........

3/4 3-33 Fire Detection Instrumentation 3/4-3-37 Radioactive Gaseous Effluent Monitoring Instrumentation..................

3/4 3-41 l

Radioactive Liquid Effluent Monitoring Ins:rumentation..................

3/4 3-46 l

3/4.4 kEACTOR C0OLANT SYSTEM 3/4.4.1 COOLANT LOOPS AhD COOLANT CIRCULATION STARTUP and POWER OPERATION............

3/4 4-1 NOT 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 3/4.4.8 SPECIFIC ACTIVITY.................

3/4 4-24 i

CALVERT CLIFFS - UNIT 2 IV Amendment No. 176

,. _. -,_~

. ~. -, _

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

CALVERT CLIFFS - UNIT 2 3/4 3-27 Amendment No. 176 l

3/4.3 INSTRUMENTATION TABLE 3.3-8 METEOR 0 LOGICAL MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE 1.

WIND SPEED NominalEiev.10M 1

a.

b.

Nominal Elev. 60M 1

2.

WIND DIRECTION a.

Nominal Eley.10M 1

b.

Nominal Elev. 60M 1

3.

AIR TEMPERATURE - DELTA T (10M-60M) 1 CALVERT CLIFFS - UNIT 2 3/4 3-28 Amendment No. 176 l

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

WIND SPEED a.

Nominal Eley. 10M D

SA b.

Nominal Elev. 60M D

SA 2.

WIND DIRECTION a.

Nominal Eley.10M D

SA b.

Nominal Elev. 60M D

SA 3.

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

D SA i

CALVERT CLIFFS - UNIT 2 3/4 3-29 Amendment No. 176 l

w

1 l

'3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Remote Shutdown Instrumentation j

j LIMITING CONDITION FOR OPERATION i

3.3.3.5 The remote shutdown monitoring instrumentation channels shown in l

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 l

channel to OPERAF.LE status within 30 days, or be in H0T SHUTDOWN within the next :2 hours.

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 3-30 Amendment No. 176 l

g TABLE 3.3-9 R

G REMOTE SHUTDOWN MONITORING INSTRUMENTATION w

n MINIMUM E

C READOUT MEASUREMENT CHANNELS 4

q INSTRUMENT LOCATION RANGE OPERABLE E

I 1.

Wide Range Neutron Flux

2C43 0.1 cps-200%

1 E

E 2.

Reactor Trip Breaker Indicativa Cable Spreading OPEN-CLOSE 1/ trip breaker 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/stcam generator li EI a

a&

I t

2 P

When the 2C43 instrumentation is inoperable, the wide range neutron flux monitors located in the l

auxiliary feedwater pump room may be utilized to meet this requirement. During the period when l

E the instruments are utilized to meet the above requirement, they will be subject to the l

surveillance requirements of Table 4.3-6.

i

3/4.3 INSTRUMENTATION TABLE 4.3-6 REMOTE SHUTDOWN N0'41TORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS e

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

'l R

4 0

CALVERT CLIFFS - UNIT 2 3/4 3-32 Amendment No. 176 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 instrumentatinn 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 0PERABLE by perfonnance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-10.

CALVERT CLIFFS - UNIT 2 3/4 3-33 Amendment No. 176 l

g TABLE 3.3-10 w

G P

g POST-ACCIDENT MONITORING INSTRUMENTATION w

m n

=

C MINIMUM

!Q Q

CHANNELS E

INSTRUMENT OPERABLE ACTION ili"i 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

7.

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

8.

Auxiliary Feedwater Flow Rate 2/ steam generator 31 9.

RCS Subcooled Margin Monitor 1

31

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

11. PORY Solenoid Power Indication 1/ valve 31

12. Feedwater Flow 2

31 k

13. Containment Water Level (Wide Range)-

2 32, 33 h

14. Reactor Vessel Water Level 2*

34, 35 k

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 s

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

3/4.3 INSTRUMENTATION TABLE 3.3-10 (Continued)

ACTION STATEMENTS E

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 NOT SHUTD0WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 32 -

With the number o' f OPERABLE post-accident monitoring channels one less than the Minimum Channels OPERABLE requirement in Table 3.3-10, operation may proceed provided i

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

ACTION 33 -

With the number of OPERABLE post-accident monitoring channels two less than required by Table 3.3-10, either restore one inoperable channel to OPERxBLE status within 30 days or be in NOT 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 0PERABLE requirement in Table 3.3-10, either restore the system to 0PERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Rengt to the Commission pursuant to Specification 6.9.2 within M days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to 0PERABLE 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 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 r

l CALVERT CLIFFS - UNIT 2 3/4 3-35 Amendment No. 176 l

g TABLE 4.3-10 w

G P

g POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w

b CHANNEL CHANNEL

?

INSTRUMENT CHECK CALIBRATION E

w x

i 1.

Containment Pressure M

R y

E 2.

Wide Range Logarithmic Neutron Flux Monitor M

NA

[

3.

Reactor Coolant Outlet Temperature M

R E

4.

Pressurizer Pressure M

R 5.

Pressurizer Level M

R 6.

Steam Generator Pressure M

R g

7.

Steam Generator Level (Wide Range)

M R

8.

Auxiliary Feedwater Flow Rate M

R w

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

13. Containment Water Level (Wide Range)

M R

g

14. Reactor Vessel Water Level M

NA k

15. Core Exit Thermocouple System M

R*

A 2

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

installation in the reactor core.

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

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

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

a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrt..o 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 alamed 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 3-37 Amendment Na. 176 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 3-38 Amendment No. 176 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 SM0XE 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-Eley (-)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 Cab 1p, 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

Eley. 27'-0" Switchgear Vent Duct 1

2A Cable Chase 2A 1

2B Cable Chase 28 1

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

Detectors which automatically actuate Fire Suppression Systems.

CALVERT CLIFFS - UNIT 2 3/4 3-39 Amendment No. 176 l

ql 3/4.3 l

INSTRUMENTATION TABLE 3.3-11 (Continued)

FIRE DETECTION INSTRUMENTS UNIT 2 MINIMUMINSTRI)MENTS 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 Contairaent Access 3

532 Electrical Equip Rm 3

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

Elev. 83'-0" Cable Tunnel 4

605 Auxiliary Feedwater Pump Rm 2

Containment B1do.

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 i

Detection instruments located within the containment ure 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 3-40 Amendment No. 176 l

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Radioactive Gaseous Effluent Monitorina 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 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 00CN.

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 rele.se 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 1.0.3 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 performance of the CHANNEL CHECK, SCURCI CHECK, CNANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-11.

i l

i i

c CALVERT CLIFFS - UNIT 2 3/4 3-41 Amendment No. 176 l

4 g

TABLE 3.3-12 R

G g

RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION w

b MINIMUM CNANNELS

]

INSTRUMENT OPERABLE APPLICABILITY ACTION E"'

1.

WASTE GAS HOLDUP SYSTEM g

c 5

a.

Noble Gas Activity Monitor - Providing 1

35 d

Alam and Automatic Temination of E

Release b.

Effluent System Flow Rate Measuring 1

36 Device 2.

MAIN VENT SYSTEM M

a.

Noble Gas Activity Monitor 1

.37 e

b.

Iodine Sampler 1

38 c.

Particulate Sampler 1

38 T

['

~

a 7

a m

-me.,

c

,-e w

w

3/4.3 INSTRUMENTATION

[

TABLE 3.3-12 (Continued)

TABLE NOTATION.

At all times.

ACTION STATEMENTS ACTION 35 -

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

a.

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

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

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 -

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

ACTION 37 -

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

ACTION 38 -

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

CALVERT CLIFFS - UNIT 2 3/4 3-43 Amendment No. 176 l

g TABLE 4.3-11 R

c; g

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS w

MODES IN

$2 n

C CHANNEL WHICH 5

7 CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED km C

1.

WASTE GAS HOLDUP SYSTEM y

^

a.

Noble Gas Activity Monitor -

P P

R(3)

SA(U Providing Alam and Automatic Temination of Release b.

Effluent System Flow Rate DN NA R

NA Measuring Device mA 2.

MAIN VENT SYSTEM a.

Noble Gas Activity Monitor D

M R(3)

SA(2) b.

Iodine Sampler W

NA NA NA c.

Particulate Sampler W

NA NA NA N

n a

.I C

cn m

m+

m-s t---

u v

m 4+

3/4.3 INSTRUMENTATION TABLE 4.3-11 (Continued)

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

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

1.

Instrument indicates measure levels above the alam/ 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 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 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.

l CALVERT CLIFFS - UNIT 2 3/4 3-45 Amendment No. 176 l

3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION j

Radioactive Licuid Effluent Monitorina Instrumentation LIMITING CONDITION FOR OPERATION 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in T6hle 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 l

0FFSITE DOSE CALCULATION MANUAL (00CM).

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.

j 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 provisiont of Specifications 3.0.3 and 3.0.4 are not applicable.

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

i CALVERT CLIFFS - UNIT 2 3/4 3-46 Amendment No. 176 l

t 3/4.3 INSTRUMENTATION TABLE 3.3-13 l

RADI0 ACTIVE LI0'JID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION 1.

GROSS RADIOACTIVITY 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 3-47 Amendment No. 176 l

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.

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

ACTION 29 -

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

a.

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

b.

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

ACTION 30 -

With the number of channels OPERABLE less than required by the Minimum Channels CPERABLE 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 3-48 Amendment No. 176 l

9 TABLE 4.3-12 R

G P

g RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS w

b CHANNEL SOURCE CHANNEL FUNCTIONAL

]

INSTRUMENT CHECK CHECK CALIBRATION TEST "E

i 1.

GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM E

AND AUTOMATIC TERMINATION OF RELEASE g

a.

Liquid Radwaste Effluent Line D

P R(2)

SA(1)

E R)

SA(1)

IZ b.

Steam Generator Blowdown Effluent Line D

P 2.

FLOW RATE MEASUREMENT DEVICES a.

Liquid Radwaste Effluent Line D(3)

NA R

NA g

D)

NA R

NA I3 b.

Steam Generator Blowdown Effluent Line 5

&eR

~_

3/4.3 INSTRUNENTATION TABLE 4.3-12'(Continued)

TABLE NOTATION (1)

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

1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

4 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 i

Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system within its intended range of energy and measurement range.

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

(3)-

CHANNEL CHECK shall' consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made at.least once per.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which effluent releases are made.

i b

-CALVERT CLIFFS - UNIT 2 3/4 3-50 Amendment No. 176 -

l

3/4.3 INSTRUMENTATION BASES 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 1

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 infomation 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."

The Subcooled Margin Monitor (Sffi), the Heated Junction Thermocouple (HJTC), and the Core Exit Themocouples (CET) comprise the Inadequate Core Cooling (ICC) instrumentation required by Item II.F.2 NUREG-0737, the Post THI-2 Action Plan.

The function of the ICC instrumentation is to enhance the ability of the plant operator to diagnose the approach to, and recovery from. ICC. Additionally, they aid in tracking reactor coolant inventory.

These instruments are included in the Tcchnical Specifications at the request of NRC Generic Letter 83-37. These instruments are not required by the accident analysis, nor to bring the plant to HOT STANDBY or COLD SHUTDOWN.

CALVERT CLIFFS - UNIT 2 B 3/4 3-2 Amendment No. 176

o 3/4.3 INSTRUMENTATION BASES In the event more than four sensors in a Roctor Vessel Level channel are inoperable, repairs may only be possible during an extended COLD SHUTDOWN.

This is because the sensors are accessible only after the plant has been cooled down and drained, and the missile shield has been moved.

If only one channel is inoperable, it should be restored to OPERABLE status in accordance with the schedule outlined in a Special Report.

If both channels are inoperable, the system shall be restored to 0PERABLE status in the next refueling outage.

3/4.3.3.7 Fire Detection Instrumentation OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is rostored to OPERABILITY.

3/4.3.3.9 Radioactive Gaseous Effluent Monitorina Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alam/ trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alam/ trip will occur prior to exceeding the limits of Specification 3.11.2.1.a based on average annual X/Q. The OPERABILITY and use of this instrumentation is consistent with the requirements of,10 CFR Part 50, Appendix A, General Design Criteria 60, 63, and 64.

3/4.3.3.10 Radioactive Liould Effluent Monitorina Instrumentation The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part

20. The OPERABILITY and use of this instrumentation i.s consistent with the requirements of 10 CFR Part 50, Appendix A, General Design Criteria 60, 63, and 64.

CALVERT CLIFFS - UNIT 2 B 3/4 3-3 Amendment No. 176 l

A

6.0 ADMINISTRATIVE CONTROLS (c)

Letter from Mr. G. C. Creel (BG&E) to NRC' Document Control Desk, dated February 7,1989, "Calvert Cliffs' Nuclear Power Plant Unit No. 2;-Docket 50-318 Request for Amendment, Unit 2 Ninth Cycle License Application" (d)

Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated January 10, 1990, " Safety-Evaluation Report Approving Unit 2 Cycle 9 License Application"

~

The core operating (e.mits shall be detennined such that all l

li c.

applicable limits g., fuel thermal mechanical limits, core thennal hydraulic limits. Emergency Core Cooling Systems:(ECCS) limits, nuclear limits such as SDM, transient analysis limits.

and accident analysis limits) of the safety analysis are met.-

d.

The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

SPECIAL REPORTS 6.9.2.Special reports shall be submitted to the Regional Administrator of-the NRC Regional Office within the time period specified for each report.

These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a.,

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

l c.

Inoperable Meteorological Instrumentation, Specification 3.3.3.4.

I e.

Core Barrel Movement, Specification 3.4.11.

f.

Fire Detection Instrumentation Specification 3.3.3.7.

g.

Fire Suppression Systems, Specifications 3.7.11.1, 3.7.11.2, 3.7.11.3, 3.7.11.4, and 3.7.11.5.

h.

Penetration Fire Barriers. Specification 3.7.12.

1.

Steam Generator Tube Inspection Results, Specification 4.4.5.5.a and c.

j.

Specific Activity of Primary Coolant, Specification 3.4.8.

I k.

Containment Structural Integrity, Specification 4.6.1.6.

CALVERT CLIFFS - UNIT 2 6-26 Amendment No. 176

-

ML20076K746

Text

Attachment:

Attachment:

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