ML19324B844

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Proposed Tech Specs Re Administrative Changes
ML19324B844
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 10/30/1989
From:
DUKE POWER CO.
To:
Shared Package
ML19324B843 List:
References
NUDOCS 8911080380
Download: ML19324B844 (7)
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'ATTACllMENT I p.

PROPOSED CllA!'1ES TO THE i

TECIINICAL SPEC 1tICATION INDEX

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8911080380 891030 PDR. ADOCK 05000369 P.

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

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SECTION PAGE l

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

3/4 0-1 i

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL 1

Shutdown Margin - T,yg >

200'F...........................

3/4 1-1 L

Shutdown Margi n - T,yg <, 200'F...........................

3/4 1-3 Moderator Te>aperature Coe f ficient....................'....

3/4 1-4 Minimum Temperature for Criticality......................

3/4 1-6 3/4.1.2 B0 RATION 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 1

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

3/4 1-12 l

3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height.............................................

3/4 1-14 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE I

EVENT OF AN INOPERABLE FULL-LENGTH R00...................

3/4 1-16 Position Indication Systems - Operating..................

3/4 1-17 Position Indication System -

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

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 R00 BANK INSERTION LIMITS VERSUS THERMAL POWER 1

FOUR LOOP 0PERATION......................................

3/4 1-22 j

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX 01FFERENCE....................................

3/4 2-1 l

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

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

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' CATAWBA - UNITS 1 & 2 IV

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION.............

3/4 3 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................................

3/4 3-61 Remote Shutdown System...................................

3/4 3-62 TABLE 3.3-9 REMOTE SNUT00WN MONITORING INSTRUMENTATION............

3/4 3-63

' TABLE 4.3-6 REMOTE SNUT00WN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................................

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 SURVEZLLANCE REQUIREMENTS.............................................

3/4 3-68 Chlorine Detection Systems...............................

3/4 3-70 Fi re Detection Instrumentati on...........................

3/4 3-71 TABLE 3.3-11 FIRE DETECTION INSTRUMENTATION......................

3/4 3-73 Loose-Part Detectio.n System..............'................

3/4 3-5 H Radioactive Liquid Effluent Monitoring Instrumentation...

3/4 3-)4 do TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4 3-M 61 TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................

3/4 3- % 83 Radioactive Gaseous Effluent Monitoring Instrumentation..

3/4 3-AE. 8 #

TABLE 3.3-13 RADIOACTIVE GASEOUS EFFLUENT MONITORING 1.

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

3/4 3.94 B' TABLE 4.3-9 RADI0 ACTIVE GASEQUS EFFLUENT MONITORING

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

3/4 3-M 90 3/4.3.4 ' TURBINE OVERSPEED PROTECTION..............................

3/4 3.M 93 s,..n %4ron x6 4 sp6....

.g9 3-922 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION L

Startup and Power Operation..............................

3/4 4-1 Hot Standby..............................................

3/4 4-2 Hot Shutdown.............................................

3/4 4-3 Cold Shutdown - Loops Fi11ed.............................

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

3/4 4-6 l'

s CATAWBA - UNITS 1 & 2 VI

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS I

q1 yjl SECTION PAGE 3/4 7-34

, TABLE I.7-3 FIRE HOSE STATIONS....................................

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

3/4 7-36 N'

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 i g,

' 'l 3/4.8.1

'A.C.

SOURCES d'

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

3/4 8-1 E,i TABLE ~4.8-1 DIESEL GENERATOR TEST SCHEDULE........................

3/4 8-9 eT'*-

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

3/4 8-10 v.g [.

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

3/4 8-11 3/4.8.2 0.C. SOURCES

)$

0perating................,................................

3/4 8-12

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

3/4 8-15

[

t p-Shutdown.................................................

3/4 8-16 Pg

$w 3/4.8.3 ONSITE POWER DISTRIBUTION

-$3 y3 0perating................................................

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

3/4 8-18 mM 3e 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES 1 3' Containment Penetration Conductor Overcurrent 11 Protective Devices.....................................

3/4 8-19 h

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

3/4 8-21 g

4 F

3/4.9 REFUELING OPERATIONS i 3/4.9.1 BORON CONCENTRATION......................................

3/49-ilE p

3/4.9.2 INSTRUMENTATION..........................................

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 3'/4.9.6 MANIPULATOR CRANE........

3/4 9-8 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL SUILDING..........

3/4 9-9 CATAWBA - UNITS 1 & 2 X

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.sp BASES-1 I~ 'SECTION PAGE 1

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'3/4.0-APPLICABILITY...............................................

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 80 RAT I ON CONTR0 L..........................................

B 3/4 1-1 3/4.1.2 30 RATION SYSTEMS..........................................

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

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

B 3/4 2-1

.3/4.2.1 AXIAL FLUX 01FFERENCE.....................................

B 3/4 2-1 3/4;2.2 and'3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and REACTOR.

COOLANT SYSTEM FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT 0R............................................

B 3/4 2j2 2.2L J.id5AMMr+0WeR- :.....................................

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3/4. 2. 4 - QUADRANT POWER TI LT RATI0.................................

B 3/4 2-5 3/4.2.5 DNB PARAMETERS............................................

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 COO LANT 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 CATAWBA - UNITS 1 & 2 XIII

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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 SHIFT 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 3/4.4.11 REACTOR COO LANT SYSTEM VENTS.............................

B 3/4 4-17 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 A C C UMU LA TO R S..............................................

B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS...............................

B 3/4 5-/ 2-3/4.5.4 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 l

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

B 3/4 6-5 i

3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE.............................................

B 3/4 7-1 l

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

B3/47-/2.E I

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 STANDBY NUCLEAR SERVICE WATER PON0........................

B 3/4 7-1 3 EL 3/4.7.6 CONTROL ROOM AREA VENTILATION SYSTEM......................

B 3/4 7-1 311.

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 j

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 STANDBY SHUT 00WN SYSTEM...................................

B 3/4 7-8 l

l CATAWBA - UNITS 1 & 2 XIV

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ADMINISTRATIVE CONTROLS SECTION PAGE Annual Reports............................................

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

6-16

. Semiannual Raaioactive Effluent Release Report............

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

6-19 Radial Peaki ng Factor Limi t Report........................

1 1

6.9.2 SPECIAL REP 0RTS...........................................

6-)dtZ.0 6.10 RECORD RETENTION...........................................

6-;bK Z.0 6.11 RADIATION PROTECTION PR0 GRAM...............................'

6-21 6.12 HIGH RADIATION AREA........................................

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

6-22 l

1' 6.14 0FFSITE DOSE CALCULATION MANUAL (00CM).....................

6-23 6.15 MAJOR CHANGES TO LIQUID, GASEOUS. AND SOLIO RA0 WASTE TREATMENT SYSTEM5..........................................

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1 7.0 SPECIAL TEST PR0 GRAM........................................

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CATAWBA - UNITS 1 & 2 XIX

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