ML20059C457

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Proposed Tech Specs Re Incore Detector Sys
ML20059C457
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 10/27/1993
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20059C452 List:
References
NUDOCS 9311010163
Download: ML20059C457 (12)
v • d • e


Text

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PROPOSED TECHNICAL SPECIFICATION CHANGES i

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9311010163 931027 PDR P

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1HDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE' REQUIREMENTS SECTION EAGE l

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE..........

'3/4 2-1 l

3/4.2.2 RADIAL PEAKING FACT 0RS..................................

3/4-2 4 3/4.2.3 AZIMUTHAL P0WER' TILT....................................

3/4i2-5 3/4.2.4 DNBR MARGIN.............................................

3/4 2-7 3/4.2.5 RCS FLOW RATE.....................

-3/4 2.l 3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE....................

3/4s2-12 l

3/4.2.7 AXIAL SHAPE INDEX.......................................

3/4 2.

3/4.2.8 PRESSURIZER PRESSURE....................................

3/4 2 3/4.3 INSTRUMENTATION f

3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION................

3/4 3-1

.3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION,......................................

3/4 3 -l 3/4.3.3 MONTI0 RING INSTRUMENTAION Radiation Monitoring Instrumentation....................

3/4-3-24

-i' 1

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

3/4'3-30 7

Meteorological Instrumentation..........................

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

3/4 3-36

3'4 3-39.

?

/

Post-Accident Instrumentation...

1 Chlorine Detection Systems...............................

3/4 3 l Fire Detection Instrumentation...................

3/4 3-43.

i Radioactive Gaseous Effluent Monitoring Instrumentation........................................

3/4 3 ;

t ARKANSAS - UNIT 2 V

Amendment No. 34,60-l I

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2 ARKANSAS - UNIT 2 3/4 3-28 Amendment No. M, M4, 4 4 -

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3/4.3 INSTRUMENTATION-l 1

BASES 3/4.3.3 MONITORING INSTRUMENTATION q

3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1)-

the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or. automatic action is initiated when the radiation level trip setpoint is exceeded.

l The PURGE as defined in the definitions section is a release under a purge permit, whereas continuous ventilation is defined as operation of the purge system after the requirements of the purge permit have been_ satisfied..

When securing the containment purge system'to meet the ACTION requirements of this Specification, at least one supply valve and one exhaust valve _is to be closed, and the supply and exhaust fans secured.

3/4.3.3.2 DELETED 3/4.3.3.3 SEISMIC INSTRUMENTATION I

The OPERABILITY of the seismic instrumentation ensures that 3

' sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.

This capability is required to permit comparison of the measured response to that used in the design basis for the f acility to determine if plant shutdown is required pursuant to Appendix "A" of 10 CFR Part 100.

The instrumentation is consistent with the recommendations _of Safety Guide

12. " Instrumentation for Earthquakes " March, 1971.

3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION 4

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 i

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," Feburary 1972.

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION

-l The OPERABILITY of the remote shutdown instrumentation ensures:that

)

sufficient capability is available to permit shutdown and maintenance of-HOT STANDBY of the f acility from locations outside of the control room.

l This capability is required in the' event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.

ARKANSAS - UNIT 2 B 3/4 3-2 Amendment No. 33.444, 130 l

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l SPECIAL TEST EXCEPTIONS CENTER CEA MISALIGNMENT i

LIMITING CONDITION FOR OPERATION 3.10.4 The requirements of Specifications 3.1.3.1 and 3.1.3.6 may-be suspended during the performance of PHYSICS TESTS to' determine the _

isothermal temperature coefficient, moderator' temperature _ coefficient and power coefficient provided:

a.

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

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

APPLICABILITY:

MODES I and 2.

l AC110N:

With any of. the limits of Specification 3.2.1 being exceeded while the-1 requirements of Specifications 3.1.3.1 and 3.1.3.6 are suspended. either:

a.

Reduce THERMAL POWER sufficiently to satisfy the requirements of

_l Specification 3.2.1 or b,

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

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

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

of Specification 3.2.1 by monitoring it continuously with the incore detection system during PHYSICS TESTS above 5% of RATED THERMAL POWER in which the requirements of Specifications 3.1.3.1 and/or 3.1.3.6 are suspended.

l i

J ARKANSAS UNIT 2' 3/4 10-4 Amendment No.

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MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS'

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11G11 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE........................................

3/4 2-1 l

3/4.2.2 RADIAL PEAKING FACT 0RS..................................

3/4 2.

3/4.2.3 AZIMUTHAL POWER TILT....................................

3/4 2-5 3/4.2.4 DNBR MARGIN.............................................

3/4 2-7 3/4.2.5 RCS FLOW RATE..................

3/4 2-11 3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE....................

'3/4.2 12:

3/4.2.7 AXIAL SHAPE INDEX.......................................

3/4 2-13 3/4.2.8 PRESSURIZER PRESSURE....................................

3/4 2-141 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 3-10 3/4.3.3 MONTIORING INSTRUMENTAION Radiation-Monitoring Instrumentation....................

3/4.3-24 heefe-Detec4or s.

2/d 3-24 Seismic Instrumentation....

3/4 3-30 Meteorological Instrumentation........................

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

3/4.3-36 Post-Accident Instrumentation...........................

3/4 3-39 Chlorine Detection Systems..............................

3/4 3-42 Fire Detection Instrumentation..........................

3/4 3-43 Radioactive Gaseous Effluent Monitoring.

Instrumentation.......................................

3/4 3-45 ARKANSAS UNIT 2 V

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_m ARKANSAS - UNIT 2 3/4 3-28 Amendment No. 63,-144, 41 l

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l 3'/4.3 INSTRUMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RA0!ATION MONITORING INSTRUMENTATION i

The OPERABILITY of the radiation monitoring channels ensures that l) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.

The PURGE as defined in the definitions section is a release:under.a purge permit, whereas continuous ventilation is defined as operation of the purge system after the requirements of the purge permit have been satisfied.

When securing the containment purge system to meet the ACTION requirements. of this Specification, at least one supply valve and one exhaust valve is to be closed, and the supply and exhaust fans secured.

3/4.3.3.2 4EC4E DETECTORSDELETED The OPERABILITV cf the 4ncore detector

-zith the spec!'ied ~4-4 mum complement of equipment enswe: that the measurements-obtai cd from ute of thic Oystem-escurately repretent the pati:1 neutron #1ux dict-ibutiono0f

'l th e re a c to r c-seer f

3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude-of-a seismic event and evaluate the response of those features important to safety.

This capability is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix "A" of 10 CFR Part 100.

The instrumentation is consistent with the recommendations-of Safety. Guide

12. " Instrumentation for Earthquakes," March, 1971.

3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION l

)

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 j

of radioactive materials to the atmosphere.

This capability.is required i

to evaluate the need for initiating protective measures to protect the i

health and safety of the public and is consistent with the recommendations j

of Regulatory Guide 1.23 "Onsite Meteorological Programs," Feburary 1972..-

l

'l 3/4.3.3.5 REMOTE SHUT 00WN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentmtion 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 50.

ARKANSAS UNIT 2 B 3/4 3-2 Amendment No. 33,140, 430 l

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SPECIAl' TEST EXCEPTIONS CENTER CEA MISALIGNMENT

,j LIMITING CONDITION FOR OPERATION 3.10.4 The. requirements of Specifications 3.1,3.1 and 3.1.3.6 may be suspended during the performance of PHYSICS TESTS-to determine the isothermal temperature coefficient, moderator temperature coefficient and.

power coefficient provided:

a.

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

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

l APPI TCABl.LIll:

MODES 1 and 2.

ACIlHN:

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

1 a.

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

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

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

4.10.4.2 The linear heat rate shall be determined to be within the limits of Specification 3.2.1 by monitoring it continuously with the incore ~

detectiondetecter "on44er-4*9 system pursuant to the requirements cf Spec 4f4c4t44n 3.3.2.2 during PHYSICS TESTS above 5% of RATED THERMAL POWER in which the.

requirements of Specifications 3.1.3.1 and/or 3.1.3.6 are suspended.

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ARKANSAS - UNIT 2 3/4 10-4 Amendment _fhe l

Revised ANO-2 Safety Anaivsis Reoort Pagg (Insert in Section 7.7.1.1.7 between pages 7,7-8 and 7.7-9) l i

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q ARKANSAS NUCLEAR ONE Unit 2

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1 When the incore instmmentation system is used to perform the functions listed above, it -

must consist of:

1. At least 75% of all incore detectors operable (165 detectors) with at least one incore detector in each quadrant at each level, and J

J

2. At least 75% of all incore detector locations operable (33 locations), and
3. Suflicient operable incore detectors to perform at least six tilt estimates with at least one tilt estimate at each of three levels.

1 NOTE: For the remainder of Fuel Cycle 10 the incore instrumentation system may be used to perform the functions listed above with <75% and 250% of all incore detectors (<165 and 2110 detectors) and detector locations (<33 and 222 locations) provided appropriate penalties (based on a full 1.0% increase in overall uncertainty on the CECOR Fxy measurement) are applied to the COLSS and CPCs, If these minimum conditions are not met, the incore instrumentation system is not used for the above listed applicable monitoring or calibration functions.

An operable incore detector location consists of a fuel assembly containing a fixed detector string with a minimum of three operable rhodium detectors.

A tilt estimate can be made from two sets of symmetric pairs ofincore detectors. Two sets of symmetric pairs ofincore detectors are formed by two pairs of diagonally opposite j

symmetric detectors, one incore detector per quadrant.

)

Operability of the incore instrumentation is demonstrated by the performance of a channel J

check within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to use and at least once per 7 days thereafler when required for monitoring the azimuthal power tilt, radial peaking factors, local power density _or DNB margin. In addition, operability is demonstrated at least once per 18 months by the performance of a channel calibration operation which exempts the neutron detectors, but includes all electronic components.

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

Amendment No. 11 7.7-Ba

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