ML19324C285

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Proposed Changes to Tech Spec Index Covering Limiting Conditions for Operation & Surveillance Requirements for Reactivity Control Sys,Power Distribution Limits,Boron Dilution Mitigation Sys & RCS
ML19324C285
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 10/30/1989
From:
DUKE POWER CO.
To:
Shared Package
ML19324C283 List:
References
NUDOCS 8911160077
Download: ML19324C285 (7)
v • d • e


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ATTACllMENT I  ;

PROPOSED CHANGES TO TIIE TECIINICAL SPECIFICATION INDEX f

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8911160077 891030 PDR ADOCK 05000413 P PDC

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1 l-i LIMITING CON 0!TIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS l .

I SECTION PAGE 3/4.0 APPLICABILITY............................................... 3/4 0-1 3/4.1 REACTIVITY CONTRflL S'fSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - 13 ,9 > 200'F........................... 3/4 1-1 Shutdown Margin - T,yg 5 200*F........................... 3/4 1-3 Moderator Temperature Coefficient........................ 3/4 1-4

. Minimum Temperature for Criticality...................... 3/4 1-6 3/4.1.2 BORATION SYSTEMS Flow Path - Shutdown..................................... 3/4 1-7 Flow Paths - Operating................................... 3/4 1-8 Charging Pump - Shutdown ......................... ...... 3/4 1-9

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' Charging Pumps - Operating............................... 3/4 1-10

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Borated Water Source - 3ht.tdown. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-11 Borated Water Sources - Operating........................ 3/4 1-12

3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height................ ............................ 3/4 1-14 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRIhG REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LdNGTH R00................... 3/4 1-16 Posi tion Indication Systems - Operating. . . . . . . . . . . . . . . . . . 3/4 1-17 Position Indication System - Stutdown.................... 3/4 1-18 Rod Drop Time............................................ 3/4 1-19 Shutdown Rod Insertion Limit.... ........................ 3/4 1-20 Control Bank Insertion Limits............................ 3/4 1-21

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FIGURE 3.1-1 ROD BANK INSERTION LIMITS VER$US THERMAL POWER FOUR LOOP 0PERATION...................................... 3/4 1-22 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE................ .................. 3/42-1

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FIGURE 3.2-1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL P0WER...................................... 4 2-)( 3 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F q (Z)..................... /4 2-CATAWBA - UNITS 1 & 2 IV

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LIMITING CON 0!TIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE ,

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TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION............. 3/4 3-60 TA8LE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......................................... 3/4 3-61 Remote Shutdown Systes................................... 3/4 3-62 TA8LE 3.3-9 REMOTE SNUTD0WN MONITORING INSTRUMENTATION............ 3/4 3-63 .;

TABLE 4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............l.................. 3/4 3-64 Accident Monitoring Instrumentation...................... 3/4 3-65 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION.................. 3/4 3-66 TA8LE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................. 3/4 3-68 Chlorine Detection Systems............................... 3/4 3-70 Fire Detection Instrumentation........................... 3/4 3-71 I TABLE 3.3-11 FIRE DETECTION INSTRUMENTATION ...................... .

  • 3/4 3-73
  • Loose-Part Detection System..............'................ 3/4 3-?% ~19 Radioactive Liquid Effluent' Monitoring Instrumentation... 3/4 3-)E do TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4 3-34: 81 TABLE 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................ 3/4 3-$6 fE5 Radioactive Gaseous Effluent Monitoring Instrumentation.. 3/4 3-JDL 6#

TABLE 3.3-13 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.......................................... 3/4 3NBC ShG l

TABLE 4.3-9 RADI0 ACTIVE GASE0US EFFLUENT MONITORING '

__ INSTRUMENTATION SURVEILLANCE REQUIREMENTS................ 3/4 3-JDs 90 3/4.3.4 'TUR8INE OVERSPEED PR0TECTION.............................. 3/4 3-)( 93

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3N 3-922 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation.............................. 3/4 4-1 Hot Standby.............................................. 3/4 4-2 Hot Shutdown............................. ............... 3/4 4-3 Cold Shutdown - Loops F111 ed. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-5 Cold Shutdown - Loops Not F111ed......................... 3/4 4-6 CATAWBA - UNITS 1 & 2 VI

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$l LIMITING' CON 0!TIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i

SECTION PAGE di a: 8 TABLE 3.7-3. FIRE H0SE STATIONS.................................... 3/4 7-34 gl8 3/4 7-36

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1 3/4.7.11 FIRE BARRIER PENETRATIONS................................

I' 3/4.7.12 GROUN0 WATER LEVEL........................................ 3/4 7-38 3/4.7.13 STANDBY SHUTDOWN SYSTEM..................................- 3/4 7-40

'3/4.8 ' ELECTRICAL' POWER SYSTEMS g4

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- 3/4.8.1 A.C. SOURCES Operating................................................ 3/4 8-1

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p , TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE. . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-9 eT

  • TABLE 4.8-2 LOAD SEQUENCING TIMES................................. 3/4 8-10 c.

[# Shutdown..... ........................................... 3/4 8-11

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3/4.8.2 D.C. SOURCES 3/4 8-12

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    • M Operating................,................................

. TABLE 4.8-3 BATTERY SURVEILLANCE REQUIREMENTS..................... 3/4 8-15 ,

t> 3/4 8-16 g Shutdown.................................................

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. a, 3/4.8.3 ONSITE POWER DISTRIBUTION

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l g3 0perating................................................ 3/4 8-17

! Shutdown................................................. 3/4 8-18

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l M e 3m 3/4.9.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES .

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Containt.wnt Penetration Conductor Overcurrent Ti Protective 0evices..................................... 3/4 8-19 ,

l O TABLE 3.8-lh ONTAINMENT PENETRATION CONOUCTOR OVERCURRENT t

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u PROTECTIVE DEVICES....................................... 3/4 8-21

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l *@ t 3/4.9 REFUELING OPERATIONS

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3/4.9.1 BORON CONCENTRATION...................................... 3/4 9-i l %

1 l 3/4.9.2 INSTRUMENTATT0N.......................................... 3/4 9-2

,_ 3/4.9.3 DECAY TIME............................................... 3/4 9-3 3/4.9.4. CONTAINMENT BUILDING PENETRATIONS........................ 3/4 9-4 .,

3/4.9.5 COMMUNICATIONS........................................... 3/4 9-7 l 3/4.9.6 MANIPULATOR CRANE........................................ 3/4 9-8

4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING.......... 3/4 9-9 1

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CATAWBA - UNITS 1 & 2 X

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SECTION PAGE l

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3/4.0 APPLICABILITY....................................,.......... B 3/4 0-1

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,, 3/4.1 REACTIVITY CONTROL SYSTEMS q 1 l

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'3/4.1.1 80 RATION CONTR0L.......................................... B 3/4 1-1

! -3/4.1.2 B0 RATION SYSTEMS.......................................... B 3/4 1-2  ;

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L 3/4.1.3 MOV AB LE CONTRO L AS S EMB LI ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 1-3 l l

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l 3/4.2 POWER DISTRIBUTION LIMITS................................... B 3/4 2-1

l 3/4.2.1 AXIAL FLUX DIFFERENCE..................................... B 3/4 2-1 '

i l 3/4.2.2 and 3/4.2.3 HEAT. FLUX HOT CHANNEL FACTOR and REACTOR E C0OLANT SYSTEM FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT 0R............................................ B3/42-Af1E.0L

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'3/4.2.4 QUADRANT POWER TI!.T RATI0................................. B 3/4 2-5 3/4.2.5 DN8 PARAMETFRS............................................ B 3/4 2-6 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION............... B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION................................ B 3/4 3-3

~3/4.3.4 TURBINE OVERSPEED PROTECTION.............................. B 3/4 3-7 >

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3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION. . . . . . . . . . . . . B 3/4 4-1 3/4.4.2 SAFETY VALVES............................................. B 3/4 4-1 3/4.4.3 PRESSURIZER............................................... B 3/4 4-2 3/4.4.4 RELIEF VALVES............................................. B 3/4 4-2 3/4.4.5 STEAM GENERATORS.......................................... B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE. . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-3 3/4.4.7 CHEMISTRY................................................. B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY............................,............ B 3/4 4-5 3/4.4.9 PRESSURE / TEMPERATURE LIMITS............................... B 3/4 4-7 C TAWBA - UNITS 1 & 2 XIII

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  • SECTION PAGE l  ?

TABLE B 3/4.4-1 REACTOR VESSEL T0VGNNESS.......................... B 3/4 4-9 FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E>1MeV) AS A FUNCTION OF FULL POWER SERVICE LIFE.................................. B 3/4 4-11 FIGURE B 3/4.4-2 EFFECT OF FLUENCE AND COPPER CONTENT'ON SNIFT OF RT FOR REACTOR VESSELS EXPOSED TO 550*F............ B 3/4 4-12 NOT ,

3/4.4.10 STRUCTURAL INTEGRITY..................................... B 3/4 4-16 3/4.4.11 REACTOR COOLANT SYSTEM YENTS............................. B 3/4 4-17 L 3/4.5 EMERGENCY CORE COOLING SYSTEMS

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3/4.5.1 A C C UMU LATO R S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS............................... B3/45-Jf2.

3/4.5.4 REFUELING WATER STORAGE TANK.............................. B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS

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3/4.6.1 PRIMARY CONTAINMENT....................................... B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.......... ........... B 3/4 6-4 3/4.6.3 CONTAINMENT ISO LATION VALVES. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-4 3/4.6.4 COMBUSTIBLE GAS CONTR0L................................... B 3/4 6-4 3/4.6.5 ICE CON 0ENSER............................................. B 3/4 6-5 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE............................................. B 3/a 7-1

, 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION........... B 3/4 7-/'7. 0L 3/4.7.3 COMPONENT COOLING WATER SYSTEM............................ B 3/4 7-3 3/4.7.4 NUCLEAR SERVICE WATER SYSTEM.............................. B 3/4 7-3 3/4.7.5 STANOBY NUCLEAR SERVICE WATER PON0........................ B 3/4 7-13 EL 3/4.7.6 CONTROL ROOM AREA VENTILATION SYSTEM...................... B 3/4 7-1 31%,

3/4.7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM................ B 3/4 7-4 3/4.7.8 SNUBBERS....................................... .......... B 3/4 7-4 3/4.7.9 SEALED SOURCE CONTAMINATION............................... B 3/4 7-6

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3/4.7.10 FIRE SUPPRESSION SYSTEMS.................................. B 3/4 7-6 3/4.7.11 FIRE BARRIER PENETRATIONS................................. B 3/4 7-7 3/4.7.12 GROUN0 WATER LEVEL......................................... B 3/4 7-7 3/4.7.13 STANOBY SNUT00WN SYSTEM................................ .. B 3/4 7-8 CATAWBA - UNITS 1 & 2 XIV

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t ADMINISTRATIVE CONTROLS - ,

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Annual Reports............................................ 6-16 i

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Annual Radiological Environmental Operating Report........ 6-16 l

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Sesiannual Radioactive Effluent Release Report............ 6-17 Monthly Operating Reports................................. 6-19 Radi al Feaki ng Factor Limi t Report. . . . . . . . . . . . . . . . . . . . . . . . 1 6.9.2 SPECIAL REPORTS....... ................................... 6-)dt E.0 6.10 RECORD RETENTION................... ....................... 6-3K 2.0 6.11 RADIATION PROTECTION PR0 GRAM............................... 6-21 6.12 H I GH RAD I AT I ON AR E A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-21

6. ~43 PROCESS CONTR01 PROGRAM (PCP).............................. 6-22  :

6.14 0FFSITE 00SE CALCULATICN MANUAL (00CM). . . . . . . . . . . . . . . . . . . . . 6-23 6.15 MAJOR CHANGES 70 LIQutD. GASEOUS. AND SOLIO RADWASTF. ,

TREATMENT SYSTEM 5....!..................................... 6-23

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L 7.0 SPECIAL TEST PR0 GRAM........................................ 7-1

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CATAWBA - UNITS 1 & 2 XIX i- . . _ . . _ . _ . _ . _ _ _ _ _ _ __ _

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