ML19325F348

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Proposed Tech Spec Index
ML19325F348
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 11/10/1989
From:
DUKE POWER CO.
To:
Shared Package
ML19325F347 List:
References
NUDOCS 8911200189
Download: ML19325F348 (8)
v • d • e


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PROPOSED CHANGES TO THE' '

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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 '

Borated Water Sources - Operating........................ 3/4 1-12

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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

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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 3/4 3-63 TABLE 3.3-9 REMOTE SNUT00WN MONITORING INSTRUMENTATION............

{m TABLE 4.3-6 REMOTE SHUT 00WN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................................ 3/4 3 64 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

3/4 3-73

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

A Loose-Part Detection System.............................. 3/4 3-X M

  1. Radioactive Liquid Effluent Monitoring Instrumentation... 3/43-)(80 TABLE 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4 3-)( 8 I

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'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

+ INSTRUMENTATION.......................................... 3/4 3- k K6

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

}0 ]INSTRUMENTATIONSURVEILLANCEREQUIREMENTS................

3/4 3-M 9 3 3/4.3.4 TURBINE OVERSPEED PROTECTION..............................

g 6 3/4.4 REACTOR COOLANT SYSTEM W m 1 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation.............................. 3/4 4-1 Not St.ndhy.............................................. 3/4 4-2 i ~~

I Hot Shutdown............................................. 3/4 4-3 Col d Shutdown - Loop s F i 11 ed. . . . . . . . . . . . . . . . . . . . . . . . . .'. . . 3/4 4-5

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Cold Shutdown - Loops Not Fi11ed......................... 3/4 4-6 CATAWBA - UNITS 1 & 2 VI p ,

a 7 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 2*

% 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 u,

Safety Va1ves............................................ 3/4 7-1 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

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I TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE E 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.............................

f 3/4 7-12 y 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

, g 3/4.7.7 AUXILIARY SUILDING FILTERED EXHAUST SYSTEM............... 3/4 7-17

.S 3/4.7.8 SNU88ERS................................................. 3/4 7-19 l h FIGURE 4.7-1 SAMPLE PLAN 2) FOR SNU88ER FUNCTIONAL TEST........... 3/4 7-24 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

l F i re Ho s e S ta ti o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-33 l l

CATAWBA - UNITS 1 & 2 IX i

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LIMITIM ColSITIONS FOR OPERATION AND' 50RVEILLANCE REOUIREMENTS -  :

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h*a TABLE'3.7-3J FIRE HOSE STAT!0NS.................................... 3/4 7-34

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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 T

  • a ,* 3/4.8' ELECTRICAL POWER SYSTEMS  !

I 3/4.8.1 - A.C. SOURCES o

  • 3/4 8-1 t.* .

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

TASLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE.................'....... 3/4 8-9

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

2 . Shutdown.................................................

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y. Operating................,................................ 3/4 8-12 P *
  • TABLE 4.8-3 BATTERY SURVEILLANCE REQUIREMENTS..................... 3/4 8-15 I

4 Shutdown................................................. 3/4 8-16  !'

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W 3/4.8.3 ONSITE POWER DISTRIBUTION w $ 0perating................................................ 3/4 8-17

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Shutdown................................................. 3/4 8-18 e 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES . i 2 W 1 m Containment Penetration Conductor Overcurrent 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 w 3/4.9.3. DECAY TIME............................................... 3/4 9-3 '

N 3/4.9.4- CONTAINMENT BUILDING PENETRATIONS........................ 3/4 9-4 b 3/4.9.S COMMUNICATIONS........................................... 3/4 9-7 d

-- J 3/4.9.6 MANIPULATOR CRANE........................................ 3/4 9-8 3/4.9.7- CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING.......... 3/4 9-9 CATAWBA - UNITS 1 & 2 X l .

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SECTION  :

B 3/4 0-1  ;

3/4.0 APPLICABILI7Y...................:...........................

J  ;

0 3/4.1 REACT!v!TY CONTROL SYSTEMS '

B 3/41-1 3/4.1.1 BORAT!0N CONTR0L..........................................

B 3/4 1-2 3/4.1.2 B0 RAT 10N SYSTEMS..........................................

ASSEMBLIES................................ B 3/4 1-3 l 3/4.1.3 MOVABLE CONTROL i B 3/4 2-1  !

3/4.2 POWER DISTRIBUTION LIMITS................................... - t DIFFERENCE..................................... B 3/4 2-1 '{

3/4.2.1 AXIAL FLUX ,

3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and REACTOR l COOLANT SYSTEM FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT 0R............................................ B3/42-/2.0 l

. . . . _ _ .. _ . . . _ . . . , . . ....m,,,-_ , _ ,. ._. .,, ,. . .. ... ... _. _ ,. -, , _

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B 3/4 2-5 ,

3/4.2.4 QUADRANT POWER TILT RATI0................................. '

B 3/4 2-6 3/4.2.5 DNS PARAMETERS............................................

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l 3/4.3 INSTRUMENTATION l

3/4.3.1 and,3/4.3.2 REACTOR TRIP 3YSTEM and ENGINEERED SAFETY B 3/4 3-1 -

FEATURES ACTUATION SYSTEM INSTRUMENTATION...............

B 3/4 3-3  !

3/4.3.3 MONITORING INSTRUMENTATION................................

PROTECTION.............................. S 3/4 3-7 j 3/4.3.4 TURBINE OVERSPEED e

3/4.4 REACTOR COOLANT SYSTEM t B 3/4 4-1 3 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION.............

B 3/4 4-1 i i 3/4.4.2 SAFETY VALVES.............................................

B 3/4 4-2 3/4.4.3 PRESSURIZER................................................

l 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 4-3 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE......................

B 3/4 4-5 3/4.4.7 CHEMISTRY.................................................

B 3/4 4-5 3/4.4.8 SPECIFIC ACTIVITY............................,............

LIMITS...............................

B 3/4 4-7 3/4.4.9 PRESSURE / TEMPERATURE CATAWBA - UNITS 1 & 2 XIII

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TABLE B 3/4.4-1 REACTOR VESSEL T00GHNE'55.......................... B 3/4 4-9 .

FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E>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 [

i 3/4.4.11 REACTOR C00LANT SYSTEM VENTS............................. B 3/4 4-17 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 i

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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 6-19 I Radial Peaki ng Factor Limit Report. . . . . . . . . . . . . . . . . . . . . . . .

6.9.2 SPECIAL REP 0RTS............................................ 6-jg( 7_()  !

6.10 RECORD RETENTION........................................... 6 jg; 2. t) l 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 SYSTEM 5.......................................... 6-23 .

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l 7.0 SPECIAL TEST OR0 GRAM........................................ 7-1 i L  !

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CATAWBA - UNITS 1 & 2 XIX

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