ML20071P453

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Proposed Tech Specs 3/4.3.3.3 Re Seismic Monitoring Requirements
ML20071P453
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 08/04/1994
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20071P444 List:
References
NUDOCS 9408090330
Download: ML20071P453 (14)
v • d • e


Text

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ATTACIIMENT (1)

UNIT 1 l MARKED-UP TECIINICAL SPECIFICATION PAGES IV 3/4 3-30 3/4 3-31 3/4 3-32 B 3/4 3-2 6-26 l

l 9400090330 940804 PDR ADOCK 05000317 PDR

l TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION ......... 3/4 3-1 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 Incore Detectors .................. 3/4 3-27 Seite.i Instru :r.tation . . . . . . . . . . . . . .~. 3/4 3-30 Meteorological Instrumentation ........... 3/4 3-33 Remote Shutdown Instrumentation . . . . . . . . . . . 3/4 3-36 Post-Accident Instrumentation . . . . . . . . . . . . 3/4 3-39 ,

Fire Detection Instrumentation ........... 3/4 3-43 Radioactive Gaseous Effluent Monitoring Instrumentation . . . . . . . . . . . . . . . . . . . 3/4 3-48 Radioactive Liquid Effluent Monitoring Instrumentation . . . . . . . . . . . . . . . . . . . 3/4 3-53 3/4.4 REACTOR COOLANT SYSTEM I

.sm i 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 i

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 l 3/4.4.5 STEAM GENERATORS .................. 3/4 4-10 l 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 uddMISTRY . . . . . . . . . . . . . . . . . . . . . . 3/4 4-21 l 3/4.4.8 SPECIFIC ACTIVITY . . . . . . . . . . . . . . . . . . 3/4 4-24 l l

CALVERT CLIFFS - UNIT 1 IV Amendment No. 188 i

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3/4.3 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION Seismic Instrumentation LIMITING C,0NDITION FOR OPERATION 3.3.3.3 The eismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.

APPLICABILITY: A all times.

~

ACTION: ..

a. With one or m e seismic monitoring instruments inoperable for more than 30 da , prepare and submit a Special Report to the '

Commission pursua t to Specification 6.9.2 within the next 10 days outlining e cause of the malfunction and the plans for restoring the instru nt(s) to OPERABLE status, i l'

b. The provisions of Speci cations 3.0.3 and 3.0.4 are not applicable.

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

4.3.3.3.2 Each of the above seismic monitoring instrum ts actuated during a seismic event shall be restored to 0PERABLE status with n 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CNANNEL CALIBRATION performed within 5 days following the ismic event.  !

Data shall be retrieved from actuated instruments and analyz to determine the magnitude of the vibratory ground motion. A Special Repo shall be  !

prepared and submitted to the Commission pursuant to Specificat n 6.9.2 within 10 days describing the magnitude, frequency spectrum and r ultant effect upon facility features important to safety.  ;

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

l 43/4.3 INSTRUMENTATION TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION MINIMUM MEASUREMENT INSTRUMENT i INSTRUMENTS ANB[ SENSOR LOCATIONS RANGE OPERABLE

1. Triaxial Tim tory Strong Motion >

Accelographs

a. 0-YE-001 Unit I ntainment Base 0-1g 1
b. 0-YE-002 Unit 1 Con inment 69' 0-1g 1
c. 0-YE-003 Auxiliary Bldg. Base 0-1g 1 1
d. 0-YE-004 Intake Structure 0-19 1
e. 0-YE-005 Free Field 0-1g 1
2. Triaxial Seismic Switches
a. 0-YS-001 Unit 1 Containment Base NA 1 I
b. 0-YS-002 Unit 1 Containment 69' NA 1
3. Seismic Acceleration Recorder
a. 0-YRC-001 Control koom NA 1
b. 0-YR-001 Control Room NA 1 >

4 CALY:RT CLIFFS - UNIT 1 3/4 3-31 Amendment No. 184 l

l 3/4.3 INSTRUMENTATION TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL CNANNEL FUNCTIONAL INSTRUMENTS If SENSOR LOCATIONS CH ECK** CALIBRATION TEST  ;

1. Triaxial Ti -History Strong Motion Accelo aphs
, c  ; ,

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a. 0-YE-001 Uni 1 M* R SA ,

Containment Ba e

b. 0-YE-002 Unit 1 M* R SA Containment 69'
c. 0-YE-003 Auxiliary B1 . M* R S 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. U-YR-001 Control Room M R SA
  • _ t r t.

l .

t i <

fr .

[ ivr r Sr Verify instrument energized.

Except seismic trigger.

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

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'3/4.3 INSTRUMENTATION BASES 3/4.3.3.2 Incore Detectors The OPERABILITY of the incore detectors with the sper.ified minimum complement of equipment ensures that the measurements obtained from use of l this system. accurately represent the spatial . neutron flux distribution of  !

the reactor core. 1 M/ .3.3 Seismic Instrumentation l The OPERABILITY 4Qhe seismic instrumentation ensures that sufficient capability is availabird romptly detemine the magnitude of a seismic event and evaluate the respon those features important to 4afety. l This capability is required to pemi rison of the measured response '

to that used in the design basis for the fac nd is consistent with the recomendations of Regulatory Guide 1.12 " Instr tion for Earthquakes," April 1974.

l 3/4.3.3.4 Meteorolooical Instrumentation The OPERA 8ILITY of the meteorological instrumentation ensures that I sufficient meteorological data is available for estimating potential  ;

radiation doses to the public as a result of routine or accidental release '

of radicactive materials to the atmosphere. This capability is required to evaluate the need for initiatf ag protective measures to protect the health and safety of the public and is consistent with the recomendations 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 Instrument 'im l The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to pemit shutdown and maintenance of  !

HOT STAND 8Y 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. '

l 3/4.3.3.6 Post-Accident Instrumentation  !

The OPERABILITY of the post-accident instrumentation ensures that i 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-Tem '

Recomendations."

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CALVERT CLIFFS - UNIT 1 B 3/4 3-2 Amencment No. 169  !

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, 6.0 ADMINISTRATIVE CONTROLS i

(c) Letter from Mr. G. C. Creel (BG&E) to NRC Document l Control Desk, dated February 7,1989, "Calvert Cliffs 1 Nuclear Power Plant Unit No. 2; Docket 50-318, Request '

for Amendment, Unit 2 Ninth Cycle License Application" l

.(d) Letter from Mr. S. A. McNeil, Jr. (NRC) to i fir. G. C. Creel (BG&E), dated January 10,1990, " Safety !

Evaluation Report Approving Unit 2 Cycle 9 License I

  • Application"
c. li The core operating applicable limits (e.mits shall g., fuel be determined thermal mechanicalsuch thatcore limits, all thermal hydraulic limits, Emergency Core Cool.ing 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.

l SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of I 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. InopereMc Scismic Monitorfeg-bstrumcatction,-

-Spee+f4est4en 3.3.3.3. -

c. Inocerable Meteorological Instrumentation, Specification 3.3.3.4.

dr-Sehde-Event Anclysis, Spcci ficctica 4.3.3.3.2.

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. 186

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ATTACIIMENT (2) l l

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i UNIT 2 MARKED-UP TECIINICAL SPECIFICATION PAGES i l

IV  !

3/4 3-30 3/4 3-31 3/4 3-32 1

B 3/4 3-2 6-26

TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION. ........ 3/4 3-1 l 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION . . . . . . . . . . . . . . . . . . 3/4 3-9 I l

3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation ....... 3/4 3-23 Incore Detectors .................- 3/4 3-27 i Sei smic-Instrument ati er . . . . . . . . . . . . . . 3/4 3 30 i Meteorological Instrumentation .......... 3/4 3-33 Remote Shutdown Instrumentation . . . . . . . . . . 3/4 3-36 Post-Accident Instrumentation . . . . . . . . . . . 3/4 3-39 Fire Detection Instrumentation .......... 3/4 3-43 Radioactive Gaseous Effluent Monitoring Instrumentation . . . . . . . . . . . . . . . . . . 3/4 3-47 Radioactive Liquid Effluent Monitoring Instrumentation . . . . . . . . . . . . . . . . . . 3/4 3-52 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 l 3/4.4.5 STEAM GENERATORS ................. 3/4 4-10 l 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 l 3/4.4.8 SPECIt'IC ACTIVITY . . . . . . . . . . . . . . . . . 3/4 4-24 l CALVERT CLIFFS - UNIT 2 IV Amendment No. 165

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

APPLICABILITY: At 11 times.

ACTION: ,,

a. With one or mor eismic monitoring instruments inoperable for more than 30 days repare and submit a Special Report to the Commission pursuant o Specification 6.9.2 within the next 10 days outlining the ause of the malfunction and the plans for restoring the instrume (s) to OPERABLE status,
b. The provisions of Specific ions 3.0.3 and 3.0.4 are not applicable.

m SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above seismic monitoring ins ruments shall be demonstrated OPERABLE by the performance of the CHAN L CHECK, CHANNEL ,

CALIBRATION and CHANNEL FUNCTIONAL TEST operations at e frequencies shown i in Table 4.3-4.

4.3.3.3.2 Each of the above seismic monitoring instruments ctuated during a seismic event shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and a l CHANNEL CALIBRATION performed within 5 days following the seism e event. l Data shall be retrieved from actuated instruments and analyzed t determine I the magnitude of the vibratory ground motion. A Special Report sh 1 be l prepared and submitted to the Commission pursuant to Specification .2 within 10 days describing the magnitude, frequency spectrum and result nt effect upon facility features important to safety.

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

l N 3/4.3 INSTRUMENTATION TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION MINIMUM MEASUREMENT INSTRUMENT INSTRUMENTS AN sSENSOR LOCATIONS RANGE OPERABLE

1. Triaxial Time- istory Strong Motion Accelographs
a. 0-YE-001 Unit 1 ontainment Base 0-19 ,

1

~

b. 0-YE-002 Unit 1 Con inment 69' 0-1g 1
c. 0-YE-003 Auxiliary Bldg. Base 0-1g 1 l
d. 0-YE-004 Intake Structure 0-19 1
e. 0-YE-005 Free Field 0-1g 1 l
2. Triaxial Seismic Switches j
a. 0-YS-001 Unit 1 Containment Base NA 1
b. 0-YS-002 Unit 1 Containment 69' A 1
3. Seismic Acceleration Recorder
a. 0-YRC-001 Control Room NA 1
b. 0-YR-001 Control Room NA 1 i

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

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.. . . _ . . . _ _ . = = . - _- . .

(3/4.3 INSTRUMENTATION TABLE 4.3-4 MEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL CHANNEL FUNCTIONAL INSTRUMENTS AND ENSOR LOCATIONS CHECK" CALIBRATION TEST

1. Triaxial Time-H ry Strong Motion Accelographs
a. 0-YE-001 Unit 1 Con inment Base M* R SA
b. 0-YE-002 Unit 1 Contai .ent 69' M* R SA
c. 0-YE-003 Auxiliary Bldg. B te 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 e.s
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 A
    • Verify instrument energized.

Except seismic trigger.

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

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3/4.3 INSTRUMENTATION 1

BASES 3/4.3.3.2 Incore Detectors The OPERA 8ILITY of the incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system. accurately represent the spatial. neutron flux distribution of the reactor core.

7 /4.3, N 3.3 Seism [cInstrumentation The OPERA 8ILITTbf42e seismic instrumentation ensures that sufficient capability is available7r1momptly detemine the magnitude of a seismic, event and evaluate the response of-t e features important to-safety.

This capability is required to permit com 74sa of the measured response i to that used in the design basis for the facility consistent with '

the recomendations of Regulatory Guide 1.12. "Instrumenta or Earthquakes," April 1974.

3/4.3.3.4 Meteoroloaical Instrumentation The OPERA 8ILITY 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 recomendations 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 OPERA 8ILITY of the remote shutdown instrumentation ensures that sufficient capability is available to pemit shutdown and maintenance of HOT STAND 8Y 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 l sufficient infomation is available on selected plant parameters to monitor I 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 i NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

CALVERT CLIFFS - UNIT 2 B 3/4 3-2 Amendment No. 149

i

' I i

I 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" l (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 determined such that all ,

applicable limits (e.g., fuel themal mechanical limits, core i themal hydraulic limits. Emergency Core Cool'ing Sy. stems (ECCS) j limits, nuclear limits such as SDM, transient analysis limits, 4 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 i 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.

+r--4nopera M e-Seh mic-MonMo eing-Inst rument a t i e r. ,

-Spectficetion-3r3v3r3. l

c. Inoperable Meteorological Instrumentation Specification 3.3.3.4.
d. Scismic Scat Analysis, Specificetion 4.3.3.3.2.
e. Core Barrel Movement, Specification 3.4.11. j
f. Fire Detection Instrumentation, Specification 3.3.3.7.  !

i

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.

l

1. Steam Generator Tube Inspection Results, Specification 4.4.5.5.a  ;

and c. I

j. Specific Activity of Primary Coolant, Specification 3.4.8. I
k. Containment Structural Integrity, Specification 4.6.1.6.

l CALVERT CLIFFS - UNIT 2 6-26 Amendment No. 163 l

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