ML19324C285

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
Issue date:	10/30/1989
From:	DUKE POWER CO.
To:
Shared Package
ML19324C283	List: ML19324C282 ML19324C285
References
NUDOCS 8911160077
Download: ML19324C285 (7)

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ATTACllMENT I PROPOSED CHANGES TO TIIE TECIINICAL SPECIFICATION INDEX f

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8911160077 891030 PDR ADOCK 05000413 P

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

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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 - 1,9 > 200'F...........................

3/4 1-1 3

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

' Charging Pumps - Operating...............................

3/4 1-10 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 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 FIGURE 3.2-1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF 4 2-)( 3 RATED THERMAL P0WER......................................

3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F (Z).....................

/4 2-q CATAWBA - UNITS 1 & 2 IV

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'0 LIMITING CON 0!TIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 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 TABLE 4.3-9 RADI0 ACTIVE GASE0US EFFLUENT MONITORING l

__ INSTRUMENTATION SURVEILLANCE REQUIREMENTS................

3/4 3-JDs 90 3/4.3.4 'TUR8INE OVERSPEED PR0TECTION..............................

3/4 3-)( 93 been 'D'!u.4ren $4ip.4 Syde..

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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( k ikr LIMITING' CON 0!TIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i

$l di SECTION PAGE a: 8 TABLE 3.7-3. FIRE H0SE STATIONS....................................

3/4 7-34 gl8 3/4.7.11 FIRE BARRIER PENETRATIONS................................

3/4 7-36 1

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

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Operating................................................

3/4 8-1 TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE........................

3/4 8-9 p,

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• TABLE 4.8-2 LOAD SEQUENCING TIMES.................................

3/4 8-10 c.[#

Shutdown................................................

3/4 8-11 3/4.8.2 D.C. SOURCES

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Operating................,................................

3/4 8-12

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. TABLE 4.8-3 BATTERY SURVEILLANCE REQUIREMENTS.....................

3/4 8-15 Shutdown.................................................

3/4 8-16 g

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3/4.8.3 ONSITE POWER DISTRIBUTION

. a, l g3 0perating................................................

3/4 8-17 Shutdown.................................................

3/4 8-18 l

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

e Containt.wnt Penetration Conductor Overcurrent Ti Protective 0evices.....................................

3/4 8-19 O

TABLE 3.8-lh ONTAINMENT PENETRATION CONOUCTOR OVERCURRENT l E PROTECTIVE DEVICES.......................................

3/4 8-21 t

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= = = * -

3/4.9 REFUELING OPERATIONS t

3/4.9.1 BORON CONCENTRATION......................................

3/4 9-i l %

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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

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3/4.0 APPLICABILITY....................................,..........

B 3/4 0-1 l

l 3/4.1 REACTIVITY CONTROL SYSTEMS 1

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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 l

4 L

3/4.1.3 MOV AB LE CONTRO L AS S EMB LI ES................................

B 3/4 1-3 l

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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rievo...,...

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<wwn v u, s n m........ _.

J.W5AMM0WER m......................................

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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 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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- BASES SECTION PAGE l

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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 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 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 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 SECTION PAGE Annual Reports............................................

6-16 i

Annual Radiological Environmental Operating Report........

6-16 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 SYSTEM5....!.....................................

6-23 L

7.0 SPECIAL TEST PR0 GRAM........................................

7-1 CATAWBA - UNITS 1 & 2 XIX i-

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