ML19325F348

Proposed Tech Spec Index

ML19325F348
Person / Time
Site:	Catawba
Issue date:	11/10/1989
From:	DUKE POWER CO.
To:
Shared Package
ML19325F347	List: ML19325F346 ML19325F348
References
NUDOCS 8911200189
Download: ML19325F348 (8)

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.s LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PME 3/4.0 APPLIMll @...............................................

3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORAT!0N CONTROL Shutdown Margin - T,y > 200'F...........................

3/4 1-1 Shutdown Margin - T,,g,$,200*F...........................

3/4 1-3 Moderator Temperature Coef ficient........................

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 - Shutdown.........................

3/4 1-11

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Borated Water Sources - Operating........................

3/4 1-12 3/4.1.3 MOVABLE CONTROL ASSEMBLIES 2

Group Height.............................................

3/4 1-14 l

TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN IN0PERABLE FULL-LENGTH ROD...................

3/4 1 l Position Indication Systems - Operating..................

3/4 1-17 Positien Indication System - Shutdown....................

3/4 1-18 Rod Drop. Time............................................

3/4 1-19 l

Shutdown Rod Insertion Limit.............................

3/4 1-20 1

Control Bank Insertion Limits............................

3/4 1-21 FfGURE 3.1-1 R00 BANK INSERTION LIMITS VERSUS THERMAL POWER FOUR LOOP OPERAT!0N......................................

3/4 1-22 3/4.2 POWER DISTRIBUTION LIMITS i

3/4.2.1 AXIAL FLUX DIFFERENCE....................................

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

3/42-X3 L

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

3/4 2-5 9

l CkTAWBA - UNITS 1 & 2 IV

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LIMITING Cm DITIONS FOR OPERATION AND SURVE!LLANCE REQUIREMENTS SECTION PAfd TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION.............

3/4 3-60 N

TABLE 4.3-5 METEOROLOGICAL MUNITORING INSTRUMENTATION SURVEILLANCE U~

REQUIREMENTS..........................................

3/4 3 61 8

Remote Shutdown System...................................

3/4 3-62 W

TABLE 3.3-9 REMOTE SNUT00WN MONITORING INSTRUMENTATION............

3/4 3-63

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TABLE 4.3-6 REMOTE SHUT 00WN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................................

3/4 3 64 m

Accident Monitori ng Instrumentation......................

3/4 3-65 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION..................

3/4 3-66 TABLE 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 g

TABLE 3.3 11 FIRE DETECTION INSTRUMENTATION......................

3/4 3-73 A

Loose-Part Detection System..............................

3/4 3-X M Radioactive Liquid Effluent Monitoring Instrumentation...

3/43-)(80

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TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4 3-)( 8 I

'Ty TABLE 4.3 8 RADI0 ACTIVE LIQUID EFFLUENT NONITORING op INSTRUMENTATION SURVEILLANCE REQUIREMENTS................

3/43-%83 E

. Radioactive Gaseous Effluent Monitoring Instrumentation..

3/4 3-M S S E

TABLE 3.3-13 RAD 10 ACTIVE GASEOUS EFFLUENT MONITORING

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INSTRUMENTATION..........................................

3/4 3-k K6 E

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TABLE 4.3-9 RADI0 ACTIVE GASE0US EFFLUENT MONITORING 3/4 3 At 90

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]INSTRUMENTATIONSURVEILLANCEREQUIREMENTS................

0 3/4.3.4 TURBINE OVERSPEED PROTECTION..............................

3/4 3-M 9 3 g

6 3/4.4 REACTOR COOLANT SYSTEM m

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3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation..............................

3/4 4-1 i

Not St.ndhy..............................................

3/4 4-2

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I Hot Shutdown.............................................

3/4 4-3

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Col d Shutdown - Loop s F i 11 ed..........................'...

3/4 4-5 Cold Shutdown - Loops Not Fi11ed.........................

3/4 4-6 CATAWBA - UNITS 1 & 2 VI p

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LIMITING ColeITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS Divider Barrier Personnel Access Doors and Equipment Matches........'..............................

3/4 6-47 Containment Air Return and Hydrogen Skimmer Systems......

3/4 6-44 Floor Drains.........................*....................

3/4 6-50 t

Refueling Canal 0 rains...................................

3/4 6-51 to-ONiderBarrierSea1.....................................

3/4 6-52 i

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TABLE 3.6-3 O!VIDER BARRIER SEAL ACCEPTABLE PHYSICAL PROPERTIES...~ 3/4 6-53 t

3/4.6.6 CONTAINMENT VALVE INJECTION WATER SYSTEM................

3/4 6-54 3/4.7 PLANT SYSTEMS 3/4.7.1 TURSINE CYCLE Safety Va1ves............................................

3/4 7-1 u,o TA8LE 3.7-1 MAXIMUM ALLOWA8LE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP 0PERATION......................................

3/4 7-2 g

TABLE 3.7-2 STEAM LINE SAFETY VALVES PER L00P.....................

3/4 7-3 g

Aux 1 M a ry Feehate r Sy s tem...............................

3/4 7-4 Specific Activity........................................

3/4 7-6 T

TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE

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AND ANALYSIS PR0 GRAM.....................................

3/4 7-7 O

Main Steam Line Isolation Va1ves.........................

3/4 7-8 h

u Condensate Storage System................................

3/4 7-9 j

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........

3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM...........................

3/4 7-11 h

3/4.7.4 NUCLEAR SERVICE WATER SYSTEM.............................

3/4 7-12 fy 3/4.7.5 STAN08Y NUCLEAR SERVItE WATER PON0.......................

3/4 7-13 j

3/4.7.6 CONTROL ROOM AREA VENTILATION SYSTEM.....................

3/4 7-14 3/4.7.7 AUXILIARY SUILDING FILTERED EXHAUST SYSTEM...............

3/4 7-17 g

.S 3/4.7.8 SNU88ERS.................................................

3/4 7-19 h

FIGURE 4.7-1 SAMPLE PLAN 2) FOR SNU88ER FUNCTIONAL TEST...........

3/4 7-24 l

3/4.7.9 S EALED SOURCE CONTAMINATION..............................

3/4 7-25 3/4.7.10 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System............................

3/4 7-27 Spray and/or Sprinkler Systems...........................

3/4 7-29 C0: Systems..............................................

3/4 7-31 l

F i re Ho s e S ta ti o n s.......................................

3/4 7-33 CATAWBA - UNITS 1 & 2 IX i

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TABLE'3.7-3J FIRE HOSE STAT!0NS....................................

3/4 7-34 ag.

3/4J.i1 FIRE BARRIER' PENETRATIONS............................,...

3/4 7-36 T

3/4.7.12' GROUNDWATER' LEVEL........................................

3/4 7-38 3

3/4.7.13~ STANDBY'5HUTDOWN SYSTEM..................................

3/4 7-40 i

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3/4.8' ELECTRICAL POWER SYSTEMS I

3/4.8.1 - A.C. SOURCES o

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0perating................................................

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

3/4 8-9 l

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

3/4 8-10 t

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

3/4 8-11 2

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

3/4 8-12 P

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

3/4 8-15 I

4 Shutdown.................................................

3/4 8-16 D.

W 3/4.8.3 ONSITE POWER DISTRIBUTION 0perating................................................

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

3/4 8-18 E*

e 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES i

2 W1 Containment Penetration Conductor Overcurrent m

p Protective 0evices.....................................

3/4 8-19 dd TABLE 3.8-1A CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT D$

PROTECTIVE DEVICES.4.....................................

3/4 8-21 sE 3/4.9 REFUELING OPERATIONS d

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

3/49-)l1 N,o 3/4.9.2 INSTRUMENTATION.........................................

3/4 9-2 3/4.9.3.

DECAY TIME...............................................

3/4 9-3 w

N 3/4.9.4-CONTAINMENT BUILDING PENETRATIONS........................

3/4 9-4

1MeV) AS A FL'NCTION OF FULL POWER SERVICE LIFE..................................

B 3/4 4-11 l

FIGURE B 3/4.4-2 EFFECT 0F FLUENCE AND COPPER CONTENT ON SN!FT' l

0F 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

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3/4.4.11 REACTOR C00LANT SYSTEM VENTS.............................

B 3/4 4-17 i

3/4.5 EMERGENCY CORE COOLING SYSTEMS l

3/4.5.1 AC C UMU LATO R S..............................................

B'3/4 5-1 l

3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS...............................

B 3/4 5-lt 2.

3/4.5.4 REFUELING WATER STORAGE TANK..............................

B 3/4 5-2 3/4.6 COMTAINMENT 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 ISOLATION VALVES..............................

B 3/4 6-4 3/4.6.4 COMBUSTIBLE GAS CONTR0L...................................

B 3/4 6-4 l

3/4.6.5 ICE CON 0ENSER.............................................

B 3/4 6-5 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE..........

B 3/4 7-1 3/4.7.2. STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...........

B3/47-)f2L3.

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 l

3/4.7.5 STANDBY NUCLEAR SERVICE WATER PON0........................

B 3/4 7-X 3il 3/4.7.6 CONTROL ROOM AREA VENTILATION SYSTEM......................

B 3/4 7-X 32L 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 STAN0BY SHUTDOWN SYSTEM...................................

B 3/4 7-8 CATAWBA - UNITS 1 & 2 XIV

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ADMINISTRATIVE. CONTROL 5 j

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Annual Reports............................................

6-16 l

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

6-16 i

i Seeiannual F,adioactive Ef fluent Release Report............

6-17 Monthly Operating Reports.................................

5-19 I

I Radial Peaki ng Factor Limit Report........................

6-19 6.9.2 SPECIAL REP 0RTS............................................

6-jg( 7_()

6.10 RECORD RETENTION...........................................

6 jg; 2. t) i 6.11 RADIATION PROTECTION PR0 GRAM...............................

6-21 l

6.12 ' H I GH RAD I AT I ON A R E A........................................

6-21 6.13 PROCESS CONTROL PROGRAM (PCP)..............................

6-22 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM).....................

6-23 l

6.15 MAJOR CHANGES TO LIQUID, GASEOUS. AND SOLID RADWASTE TREATMENT SYSTEM5..........................................

6-23 f

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l 7.0 SPECIAL TEST OR0 GRAM........................................

7-1 i

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Y CATAWBA - UNITS 1 & 2 XIX

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