ML20197F399

Proposed Tech Specs Providing Changes to Index

ML20197F399
Person / Time
Site:	McGuire, Mcguire
Issue date:	06/03/1988
From:	DUKE POWER CO.
To:
Shared Package
ML20197F391	List: ML20197F386 ML20197F399
References
NUDOCS 8806130094
Download: ML20197F399 (25)

Text

{{#Wiki_filter:' Alv Ch,nye.s INDEX OEFINITIONS ~~ EAGE SECTION 1.0 OEFINITIONS 1-1 1.1 ACTI0N........................................................

1. 2 ACTUATION LOGIC TEST..........................................

1-1

1. 3 ANALOG CHANNEL OPERATIONAL TEST..................

1-1

1. 4 AXIAL FLUX 01FFERENCE.........................................

1-1

1. 5 CHANNEL CALIBRATION..........................

1-1

1. 6 CHANNEL CHECK.................................................

1-1 1-2

1. 7 CONTAINMENT INTEGRITY...

1.8 C O NT R O L L ED L EA KAG E........................................... 1-2 1-2

1. 9 CORE ALTERATION...

1.10 COSE EQUIVALENT I-131......................................... 1-2 1.11 E-AV E R AG E D I S INT EG RATION EN E RGY............................... 1-2 1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME...................... 1-3 l 1.13 FREQUENCY N0TATION......................... 1-3 1.14 I D E NT I F I E D L EA KAG E.......................................... 1-3 1.15 MASTER RELAY TEST............... 1-3 1.16.uEMBER(5) 0F THE PUBLIC............... 1-3 1.17 0FF SITE 00SE CALCU LATION MANUAL.............................. 1-4 1.18 OPERABLE - OPERABILITY.... 1-4 1.19 OPERATIONAL MODE - M00E.............................. 1-4 1.20 PHYSICS TESTS................................................. 1-4

1. 21 P R E S SU R E BO U N D ARY LE A KAG E.....................................

1-4 1.22 PROCESS CONTROL PROGRAM...................................... 1-4 Amendment No.1 (Unit 2) McGUIRE - UNITS 1 and 2 I Amendment No. 20 (Unit 1) 4/13/8? 8806130094 880603 PDR ADOCK 05000369 P DCD

,) / V E L l M 'f r/ e s INDEX OEFINITIONS PAGE SECTION 1-5 1.23 PURGE - PURGING......... 1-5 1.24 QUADRANT POWER TILT RATIO....... 1.25 PATED THERMAL POWER.......... 1-5 1.26 REACTOR BUILDING INTEGRITY.. 1-5 1.27 REACTOR TRIP SYSTEM RESPONSE TIME.......... 1-5 1.28 REPORTABLE EVENT 1-5 1.29 SHUT 00WH MARGIN.. 1-6 1.30 SITE BOUNDARY...... 1-6 1.31 SLAVE RELAY TEST..... 1-6 1.32 SOLIDIFICATION................. 1-6 4 1.33 SOURCE CHECK........................... 1-6 1.34 STAGGERED TEST BASIS.......... 1-6 1.35 THERMAL P0WER............... 1-6 1.36 TRIP ACTUATING OEVICE OPERATIONAL TEST......................... 1-7

1. 3 7 U N I D E N T I F I E D L E A KA G E......................................

1-7 1.38 UNRESTRICTED AREA...... 1-7

1. 39 VENTILATION EXHAUST TREATMENT SYSTEM.......

1-7 1.40 VENTING..................... 1-7 1.41 WASTE GAS HOLOUP SYSTEM..... 1-7 TABLE 1.1, FREQUENCY N0TATION....................... 1-8 TABLE 1.2, OPERATIONAL M00ES........ 1-9 I l l l i McGUIRE - UNITS 1 and 2 II Amendment No. 32 (Unit 1) Amendment No.13 (Unit 2)

/}S SubrDIMeI //7/07 INDEX SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 REACTOR CORE..... 2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE... 2-1 T!CU"E 2.1-12 U"IT 1 "CACTOT,.CC": CAFETY L!"I' - ICU". LOOPC 49b-9EEilA MON......... 2 2-land 2. FIGURE 2.1-{( UNIbf REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION........ 2-2a FIGURE 2.1-2 (BLANK)..... 2-3 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS........ 2-4 TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS..... 2-5 i BASES SECTION PAGE 2.1 SAFETY LI' TITS i 2.1.1 REACTOR CORE..... B -l 2.1.2 REACTOR COOLANT SYSTEM PRESSURE......... B 2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS.... B 2-3 McGUIRE - UNITS 1 and 2 III Ameddment No. (Unit 1) Amendment No. (Unit 2) ..m

/\\h 0W)f5 INDEX LIMITING CONDITIQNS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY................. 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL ^ Shutdown Margin - T, g > 200*F....................... 3/4 1-1 P Shutdown Margin - T,yg < 200* F... 3/4 1-3 Moderator Temperature Coefficient......................... 3/4 1-4 FIGURE 3.1-0 MODERATOR TEMPERATURE COEFFICIENT VS POWER LEVEL...... 3/4 1-Sa 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 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height....... 3/4 1-14 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE 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 O rop T ime (Uni ts 1 and 2).......................... 3/4 1-19 Shutdown Rod Insertion Limit... 3/4 1-20 McQUIRE - UNITS 1 and 2 IV Amendment No. 60 (Unit 1) Amendment No. 41 (Unit 2)

b3 Sab(DI tieN 2ft 7f8~) INDEX LIMITING CONDITIONS FOR OPERATION AN0 SURVEILLANCE REQUIREMENTS PAGE SECTION Control Rod Insertion Limits..... 3/4 1-21 R E l. A Ti v &~ l FIGURE 3.1-1 R00 BANK INSERTION LIMITS VERSUS tasast24-P0wtR I FOUR LOOP OPERATION.. 3.4 1-22 F IG"W 3.1-2 ( 0 L.""' )... .. - F4-1-n-3/4.2 POWER OISTRIBUTION LIMITS 3/4.2.1 AXIALFLUXDIFFERENCE..(OflO.. 3/4 2-1 [ FIGURE ?.2-1 AXIAL FLUX OIFFERENCE LIMITS AS A FUNCTION OF R RMED THERMAL POWER............................ 3/4 E-3

)?

3/4.2.2 HEAT FLl4 HOT CHANNEL FACTOR - F (Z)....... 3/d 2-6 q FIGURE 3.2-2g K(i) - NORMALIZED F (Z) AS A FUNCTION OF CORE HEIGHT q 9 ij. 1).. 3/4 2-12 MCt#t& tit:2WK(-EW2LIIE044&2t:Ae 1 :: = ^ " n -m --- - ""T- -(4R: L 4.. ....... =-3 f a ' ' ' 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR..... 3/4 2-14 -3," : 10 IICURE L2-3: RCSJES-FLOW RATU!ERSUS R (Unit-1}; FIGURE 3.2-W RCS FLOW RATE VERSUS Rt M - FOUR LOOPS h IN OPERATION (% M )..... 3/4 2-17 >F I f Ext:f-+- W CW EF%iMS : ;wH9tt-4E SUENUP (ttntd.

,2 :-13 3/4.2.4 QUADRANT POWER TILT RATIO.....

3/4 2-19 3/4.2.S DNB PARAMETERS..... 3/4 2-22 j TABLE 3.2-1 DNB PARAMETERS. 3/4 2-23 3/4.3 INSIRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.. 3/4 3-1 McGUIRE - UNITS 1 and 2 V Amendment No. (Unit 1) Amendment No. (Unit 2)

f}s Su bou H< Cl 2/17l?7 _INDEX LIMIT!NG CONDITICNS FOR OPERATION AND SURVEILLANCE RECUI nGE SECTION 3/4 3-2 REACTOR TRIP SYSTEM INSTRUMENTATION.. TABLE 3.3-1 3/4 3-9 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES. TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE 3/4 3-U. TABLE 4.3-1 REQUIREMENTS. ENGINEERED SAFETY FEATURES ACTUATION SYSTEM 3/4 3-15 3/4.3.2 INSTRUMENTATION. ENGINEEREO SAFETY FEATURE 5 ACTUATICN SYSTEM 3/4 3-16 TABLE 3.3-3 INSTRUMENTATION. ENGINEERED SAFETY FEATURES ACTUATICN SYSTEMN Ts ~ABLE 3.3-4 lN STRO MEN TATICN TR\\ P 5 ET Pc (Inseer Amcfed) 3/4 3-45 Movaele Incore Cetectors. 3/4 3-46 Seismic Instrumentation. 3/4 3-47 ~4BLE 3.3-7 SE!$MIC MONITORING INSTRUMENTATICN. 5EISMIC MONITORING INSTRUMEN'ATION SUR.EILLANCE 3/4 3-48 TABLE 4.3-4 REQUIREMENTS. 3/4 3-49 Meteorological Instrumentation. 3/4 3-50 "ETECR0 LOGICAL MONITORING *NSTRUMENT4*I N. TABLE 3.3-3

• E7EOROLOG! CAL MONITORING INSTRUMENTA*::N 3, 4 3-51

~aSLE 4.3-5 SURVEILLANCE REQUIREMENTS.. 3/ 4 3-52 Remote Shutdown Instrumentation. 3/4 3-53 REMOTE SHUTCO'aN MONITORING INSTRUMENT 4~~0N. ~ABLE 3.3-9 Amendment No. (Unit 1) VI McGUIRE - UNITS 1 and 2 Amencment No. (Unit 2)

/lH-achnan7 t~c: p tI 2/> 7 /? 7 / TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES.............................. 3/4 3-30 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS................... 3 / 4 3_3 4 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING FOR PLANT OPERATIONS... 3/4 3-40 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS........................ 3/4 3-41 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PIANT OPERATIONS SURVEILLANCE R EQU IREMENT S................................ 3 / 4 3 -4 3 l

Nc Clwnges INDEX ( LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE TABLE 4.3-6 REMOTE SHUT 00WN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......................... 3/4 3-54 Accident Moni toring Ins trumentation....................... 3/4 3-55 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION.................. 3/4 3-56 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......................... 3/4 3-57 Fire Detection Instrumentation........................... 3/4 3-58 TABLE 3.3.11 FIRE DETECTION INSTRUMENTATION....... 3/4 3-60 Radioactive Liquid Effluent Monitoring Instrumentation.... 3/4 3-66 TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.................................... ~3/4 3-67 TABL 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......... 3/4 3-69 Radioactive Gaseous Effluent Monitoring Instrumentation... 3/4 3-71 TABLE 3.3-13 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION.................................... 3/4 3-72 TABLE 4.3-9 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......... 3/4 3-75 Loose-Part Detection Sys tem................... 3/4 3-78 3/4.3.4 TURBINE OVERSPEE0 PROTECTION..... 3/4 3-79 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION I 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 l VII McGUIRE - UNITS 1 and 2

kC O M'r2$ jA_ INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE ~- SECTION 3/4 4-6 Cold Shutdown - Loops Not Fi11ed......................... 3/4.4.2 SAFETY VALVES 3/4 4-7 Shutdown.............................. 3/4 4-8 0perating.......................................... 3/4 4-9 3/4.4.3 PRESSURIZER.............................................. 3/4 4-10 3/4.4.4 RELIEF VALVES........................................... 3/4 4-11 3/4.4.5 STEAM GENERATORS......................................... TABLE 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS T0 dE INSPECTE0 OURING INSERVICE INSPECTICN............. 3/4 4-16 TABLE 4.4-2 STEAM GENERATOR TUSE INSPECTION..................... 3/4 4-17 w 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE j 3/4 4-18 Leakage Detection Systems......................... 3/4 4-19 Operational Leakage...................................... TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES.... 3/4 4-21 3/4 4-22 3/4'. 4. 7 CHEMISTRY. TABLE 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS............. 3/4 4-23 TABLE 4.4-3 REACTOR CCOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS......................... 3/4 4-24 3/4 4-25 3/4.4.S SPECIFIC ACTIVITY.......................................... FIGURE 3.4-1 COSE EQUIVALENT I-131 REACTOR CCOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE REACTOR COOLANT SPECIFIC ACTIVITY > 1 pCi/ gram DOSE EQUIV ALENT I-131................ 3/4 4-27 TABLE 4.4-4 REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS3/4 4-29 PR0 GRAM............................................ McGUIRE - UNITS 1 and 2 VIII Amendment No. 32 (Unit 1) Amendment No.13 (Unit 2)

/Yc ([h0/Igf GJ INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.4.9 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System.................................... 3/4 4-30 FIGURE 3.4-2a UNIT 1 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS - APPLICABLE UP TO 10 EFPY......................... 3/4 4-31 FIGURE 3.4-2b UNIT 2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS-APPLICABLE UP TO 10 EFPY......................... 3/4 4-32 FIGURE 3.4-3a UNIT 1 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS - APPLICABLE UP TO 10 EPFY............................ 3/4 4-33 FIGURE 3.4-3b UNIT 2 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS-APPLICABLE UP TO 10 EPFY............................ 3/4 4-34 TABLE 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - WITH0RAWAL SCHE 0VLE.................................. 3/4 4-35 Pressurizer.............................................. 3/4 4-36 Overpressure Protection Systems.......................... 3/4 4-37 3/4.4.10 STRUCTURAL INTEGRITY.................................. 3/4 4-39 3/4.4.11 REACTOR VESSEL HEAD VENT SYSTEM.............. 3/4 4-40 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS Cold Leg Injection........................................ 3/4 5-1 (0eleted]................................................. 3/4 5-3 3/4 5-5 3/4.5.2 ECCS SUBSYSTEMS - T,yg > 350 F............................. 3/4.5.3 ECCS SUBSYSTEMS - T,yg 5 350*F............................. 3/4 5-9 3/4.5.4 [0eleted]........................ 3/4.5-11 3/4.5.5 REFUELING WATER STORAGE TANK............................... 3/4 5-12 McGUIRE - UNITS 1 and 2 IX . Amendment No. 82 (Unit 1) Amendment No. 63 (Unit 2)

YC C O/?$M LIMITING CONDITIONS FOR OPFRATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT 3/4 6-1 Containment Integrity............. 3/4 6 2 Containment Leakage............................... TABLE 3.6-1 SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS............. 3/4 6-5 3/4 6-10 Containment Air Locks..................................... 3/4 6-12 Internal Pressure............. 3/4 6-13 Air Temperature..... Containment Vessel Structural Integrity... 3/4 6-14 3/4 6-15 Reactor Building Structural Integrity.................. Annulus Ventilation System.. 3/4 6-16 3/4 6-18 Containmer.t Ventilation System. 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4 6-20 Containment Spray System........ 3/4 6-22 3/4.6.3 CONTAINMENT ISOLATION VALVES... TABLE 3.6-2 CONTAINMENT ISOLATION VALVES........ 3/4 6-24 3/4.6.4 COM8USTIBLE GAS CONTROL 3/4 6-31 Hydrogen Monitors......................................... 3/4 G-32 Electric Hydrogen Recombiners.......................... 3/4 6-33 Hydrogen Control Distributed Ignition System........ 3/4.6.5 ICE CONDENSER 3/4 6-34 Ice 8ed................................................... X McGUIRE - UNITS 1 and 2

New Changes i INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4 6-36 ce Bed Temperature Monitoring System............. 3/4 6-37 Ice Condenser Doors....................................... Inlet Door Position Monitoring System..................... 3/4 6-39 Divider Barrier Personnel Access Doors and 3/4 6-40 Equipment Hat:hes....................................... Containmen?. Air Return and Hydrogen Skimmer System....... 3/4 6-41 3/4 6-42 Floor Orai.4.............................. 3/4 6-43 Refueli g Canal Crains................ n 3/4 6-44 Divider Barrier Seal.................................... TABLE 3.6-3 OIVIDER BARRIER SEAL ACCEPTABLE PHYSICAL PROPERTIES.... 3/4 6-45 3/A.7 PLANT SY."EMS 3/4.7.1 TL4BINE CYCLE 3/4 7-1 Safety Valves........ TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTx0H FLUX MIGH SETPOINT WITH INOPERABLE STEAM LIhE SAFETY VALVES l DURING FOUR LOOP 0PERATION........................ 3/4 7-2 l l 3/4 7-2 l TABLE 3.7-2 (BLANK)................... l TABLE 3.7-3 STEAM LINE SAFETY VALVES PER LOOP..... 3/4 7-3 f 3/4 7-4 Auxiliary Feedwater System............... 3/4 7-6 Spnific Activity..................................... TABLE 4.7-i 4CC': .Y COUL"4T SYSTEM SPECIFIC ACTIVITY SAMPLE 3/4 7-7 A c: *NALYSIS A 9 RAM.............................. Mai. o talves................. 3/4 7-8 yk 3/4.7.2 571 '., * ' F. fEMPERATURE LIMaiATION.......... 3/4 ?-9 4 SYSTEM......'........ 3/4 7-10 N 3/4.7.3 COMPO'A sA 4 3/4 7-11 <c* EAR SERVICL d .4 SYSTEM................. i J/4..- b FIC,; J/a '1 -l NUCLEnR SERVICE wh TER. S1 STEM.. 3/4 7 -ll cu X' McGUIRE - UNITS 1 ano 2 SN -

C [ 00, INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS .. ;c CECTION PAGE 3/4.7.5 STANDBY NUCLEAR SERVICE WATER PON0............ 3/4 7-12 s 3/4.7.6 CONTROL AREA VENTILATION SYSTEM............ 3/4 7-13 3/4.7.7 AUXILIARY BUILDING FILTEPED VENTILATION EXHAUST SYSTEM... 3/4 7-16 3/4.7.8 SNUBBERS.......... 3/4 7-18 TABLE 3.7-4a SAFETY-RELATED HYORAULIC SN'J8BERS (UNITS 1 AND 2).... 3/4 7-23 TABLE 3.7-4b SAFETY-RELATED MECHANICAL SNUBBERS (UNITS 1 AND 2)... 3/4 7-26 FIGURE 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST.......... 3/4 7-29 3/4.7.9 SEALED SOUPCE CONTAMINATION..... 3/4 7-30 i 3/4.7.10 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System....... 3/4 7-32 Spray and/or Sprinkler Systems............ 3/4 7-34 Halon Systems.......................................... 3/4 7-36 Fire Hose Stations........................................ 3/4 7-37 TABLE 3.7-5 FILE HOSE STATIONS....... 3/4 7-38 3/4.7.11 FIRE BARRIER PENETRATIONS.................. 3/4 7-40 3/4/7.12 AREA TEMPERATURE MONITORING....... 3/4 7-42 TABLE 3.7-6 AREA TEMPERATURE MONITORING............. 3/4 7-43 3/4.7.13 G R O')N OWAT E R L EV E L.................................... 3/4 7-44 TAPI.F. 3.7-7 'UN0 WATER LEVEL MONITORING STATIONS... 3/4 7-46 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCIS Operating..... 3/4 8-1 TABLE 4.8-1 b!ESEL GENERATOR TEST SCHEDULE..... 3/* 8 o XII McGUIRE - UNITS 1 and 2

I kC $bOOQd5' INDE,X LIMITING CONDITIONS FOR OPERATION ANO SURVEILLANCE REQ PAGE SECTION 3/4 8-9 TABLE 4.8-2 LOAD SEQUENCING TIMES............................... 3/4 3-10 Shutdown...................... 3/4.8.2 0.C. SOURCES 3/4 8-11 Operating..................................... 3/4 8-14 TABLE 4.8-3 BATTERY SURVEILLANCE R2QUIREMENTS................... 3/4 8-15 Shutdown (Units 1 and 2)................................. 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS 3/4 8-16 Operating...................................-............ 3/4 8-17 Shutdown...................... 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent 3/4 8-18 Protective 0evices...................................... UNIT 1 CONTAINMENT PENETRATION CONOUCTOR TABLE 3.8-la 3/4 8-20 OVERCURRENT PROTECTIVE DEVICES............. UNIT 2 CONTAINMENT PENETRATION CONDUCTOR 3/4 8-59 TABLE 3.8.lb OVERCURRENT PROJECTIVE DC11CES............. 3/ 4. 9 REFUELING OPERATIONS 3/4 9-1 3/4.9.1 BORON CONCENTRATION................................... 1 3/4 9-2 3/4.9.2 I N ST RtlME':T AT IO N......................................... i 3/4 9-3 3/4.9.3 DECAY TIME............. 1 3/4 9-4 3/4.9.4 CONTAINMENT BUILDINC PENETRATIONS........................ 3/4 9-E 3/4.9.5 COMMUNICATIONS........................................... 3/4 9-7 3/4.9.6 M AN I P U L4TO R C RAN E........................................ J/4 9-8 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING.......... 3/4.9.7 3/4 9-9 FIGURE 3.9-1 REQUIRED PATH FOR MOVEMENT OF TRUCK CASKS........... XIII McgUIRE - UNITS 1 and 2 l- _j

h&W b bClO f_. Frcan 2 li 7 l5 7 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.9.8 RESIOUAL HEAT REMOVAL AND COOLANT CIRCULATION High Water Leve1......................................... 3/4 9-10 Low Water Leve1.......................................... 3/4 9-11 3/4.9.9 WAT E R L EV E L - R EACTO R V E S S E L............................. 3/4 9-12 3/4.9.10 WAT E R L EVE L - STO RAG E P00 L.............................. 3/4 9-13 3/4.9.11 FUEL HANDL 3/4 9-14 f ( /ns en A? Mach cQ{NG VENTILATION EXHAUST SYSTEM........ 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.......................................... 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER OISTRIBUTION LIMITS... 3/4 10-2 3/4.10.3 PHYSICS TESTS............................................ 3/4 10-3 3/4.10.4 REACTOR COOLANT LOOPS.................................. 3/4 10-4 3/4.10.5 POSITION INDICATION SYSTEM - SHUT 00WN.................... 3/4 10-5 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4 11.1 LIQUID EFFLUENTS Concentration............................................. 3/4 11-1 TABLE 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PR0 GRAM................................... 3/4 11-2 i 0ose........................................ 3/4 1.1-5 l Liquid Radwaste Treatment System.......................... 3/4 11-6 Liquid Holdup Tanks......................... 3/4 11-7 ~ Chemical Treatment Ponds......... 3/4 11-8 3/4.11.2 GASEOUS EFFLUENTS Dose Rate................................................. 3/4 11-9 XIV McGUIRE - UNITS 1 and 2

1 3/4.9.12 FUEL STORAGE - SPENT FUEL POOL.................... 3/4.9-16 TABLE 3.9-1 MINIMUM BURNUP vs INITIAL ENRICHMENT FOR REGION 2 STORAGE............................. 3/4 9-17

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4 I i I

i t o kO l WQN INDEX l \\ LIMITING CON 0!TIO.NS FOR OPERATION ANO SURVEILLANCE REQUIREMENTS PAGE i SECTION TABLE 4.11-2 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND 3/4 11-10 j ANALYSIS PROGRAM....... 3/4 11-13 Oose - Noble Gases........ Dose - Iodine-131 and 133. Tritium, and Radioactive Materials in Particulate Form............................. 3/4 11-14 Gaseous Radwaste Treatment System......................... 3/4 11-15 Explosive Gas Mixture..................................... 3/4 11-16 Gas Storage Tanks......................................... 3/4 11-1/ 3/4.11.3 SOLIO RADIOACTIVE WASTE................................... 3/4 11-18 3/4.11.4 TOTAL 00SE................................................ 3/4 11-20 i 1 3/4.12 RADIOLOGICAL ENVIRONMENTAL HONITORING 3/4.12.1 MONITORING PR0 GRAM....................................... 3/4 12-1 TABLE 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM........ 3/4 12-3 i TABLE 3.12-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES....................... 3/4 12-9 TABLE 4.12-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF 3/4 12-10 DETECTION (LLO)..... 3/4.12.2 LAND USE CENSUS.,....... 3/4 12-13 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM.. 3/4 12-15 l l i l i I XV l McGUIRE - UNITS 1 and 2

c. b/ete (ld/K (0 Fg,y 2//7 INDEX BASES PAGE SECTION B 3/4 0'1 3/4.0 4PPLICABILITY................ 3,/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL.......... B 3/4 1-1 B 3/4 1-2 3/4.1.2 BORATION SYSTEMS...... 3/4.1.3 MOVABLE CONTROL ASSEMBLIES............................... B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX OIFFERENCE................ B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR....... B 3/4 2-2 FICURE S /4.2-1 '""! CAL IN0!C?TED 'XIEL "LUX-OtTT:T,:NCC -VER5U5-4ne---L 00U:2............................. A 1/4 ?-1 I' 3/4.2.4 QUADRANT POWER TILT RATI0................................. B3/42-/6 3/4.2.5 DNB PARAMETERS.......................................... B3/42-/6 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP and ENGINE 5 RED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.... B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION....... B.1/4 3-2 3/4.3.4 TURBINE OVERSPEED PROTECTION................ B 3/4 3-5 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 4-2 3/4.4.3 PRESSURIZER..... B 3/4 4-2 3/4.4.4 RELIEF VALVES............... B 3/4 4-3 3/4.4.5 STEAM GENERATORS............................ B 3/4 4-3 McGUIRE - UNITS 1 and 2 XVI Amendment No. (Unit 1) Amendment No. (Unit 2)

e Mc Choncpo INDEX BASES PAGE SECTION 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE........................... B 3/4 4-4 B 3/4 4-5 3/4.4.7 CHEMISTRY................................................. B 3/4 4-5 3/4.4.8 SPEC' TIC ACTIVITY..................................... 3/4.4.9 PRESSURE / TEMPERATURE LIMITS............................... B 3/4 4-7 TABLE B 3/4.4-1 REACTOR VESSEL TOUGHNESS (UNIT 1).................. B 3/4 4-9 REACTOR VESSEL TOUGHNESS (UNIT 2)................. B 3/4 4-11 FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E > 1 MeV) AS A FUNCTION OF EFFECTIVE FULL POWER YEARS................... B 3/4 4-12 FIGUP.E B 3/4.4-2 EFFECT OF FLUENCE AND COPPER CONTENT ON SHIFT OF RT FOR REACTOR VESSELS EXPOSED TO 550*F TEMPEkkIURE..................................... B 3/4 4-13 B 3/4 4-17 3/4.4.10 STRUCTURAL INTEGRITY,......... 3/4.4.11 REACTOR VESSEL HEAD VENT SYSTEM..................... B 3/4 4-17 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS........................................... B 3/4 5-1 3/4 5.2 and 3/4.5.3 ECCS SUBSYSTEMS............... B 3/4 5-1 B 3/4 5-2 3/4.5.4 [0eleted]................. 1 3/4.5.5 REcuELING WATER STORAGE TANK.. B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6 PRIMARY CONTAINMENT....................................... B 3/4 6-1 3/4.6.2 OEPRESSURIZATION 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 B 3/4 6-5 3/4.6.5 ICE CONDENSER............................................. 3/4.7 PLANT SYSTEMS B 3/4 7-1 3/4.7.1 TURBINE CYCLE............................................. McGUIRE - UNITS 1 and 2 XVII Amendment No. 76 (Unit 1) Amendment No. 57 (Unit 2)

e b Ci'org e INDEX BASES PAGE SECTION , e epernh ce L am. rn m., g y y-3 l 3/*b 7<1 Sren m Genem rt e Fre1.are / T* s B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM.................. B 3/4 7-3 3/4.7.4 NUCLEAR SERVICE WATER SYSTEM.............................. B 3/4 7-3a 3/4.7.5 STANDBY NUCLEAR SERVICE WATER PON0........................JL Vf5 R % ?-]b MNC D 'TABL E R.% 7-/ M Ct C8R Q RytCE WMItX H.s 7m/ B 3/4 7-4 3/4.7.6 CONTROL AREA VENTILATION SYSTEM........................... B 3/4 7-4 AUXILIARY BUILDING FILTERED VENTILATION EXHAUST SYSTEM.... 3/4.7.7 B 3/4 7-5 3/4.7.8 SNUBBERS..... B 3/4 7-6 3/4.7.9 SEALED SOURCE CONTAMINATION............................ B 3/4 7-6 3/4.7.10 FIRE SUPPRESSION SYSTEMS.................................. B 3/4 7-7 3/4.7.11 FIRE BARRIER PENETRATIONS................................ B 3/4 7-7 3/4.7.12 AREA TEMPERATURE MONITORING............................... B 3/4 7-8 3/4.7.13 GROUN0 WATER LEVEL............... 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.B.2 and 3/4.B.3 A.C. SOURCES, D.C. SOURCES AND B 3/4 8-1 ONSIT E POWER DISTRIBUT ION SY STEMS........................ B 3/4 8-3 3/4.8.4 ELECTRICAL EQUIPMEN' PROTECTIVE DEVICES................... 3/4.9 REFUELING OPERATIONS B 3/4 9-1 3/4.9.1 BORON CONCENTRATION..................................... B 3/4 9-1 3/4.9.2 INSTRUMENTATION......................................... B 3/4 9-1 3/4.9.3 DECAY TIME........................................... B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS......................... B 3/4 9-2 3/4.9.5 COMMUNICATIONS............................................ B 3/4 9-2 3/4.9.6 MANIPULATOR CRANE......................................... B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL LIORAGE POOL BUILDING........... B 3/4 9-2 3/4.9.8 RESIDUAL HEAT dEMOVAL AND COOLANT CIRCULATION............. 3/4.9.9 ar,d 3/4.9.10 WATER LEVEL - REACTOR VESSEL and B 3/4 9-3 STORAGE P00L............................................ XVIII

y New Ckupe INDEX BASES PA9E SECTION B 3,* i-3 1 3/4.9.11 FUEL NANDLING VENTILATION EXHAUST SYSTEN................. a J/3 g 3 FUet S reR A Gr Pc t L.. 3/4.9. s 2. Feet S TCR AGE - 6 PEN T 3/4.10 SPECIAL TEST EXCEPTIONS B 3/4 10-1 3/4.10.1 SHUTDOWN MARGIN........................................... 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS.... B 3/4 10-1 B 3/4 10-1 3/4.10.3 PHYSICS TESTS............................................. 8 ?/4 10-1 3/4.10.4 R EACTO R COO LANT L00 PS..................................... B 3/4 10-1 3/4.10.5 POSITION IN0! CATION SYSTEM - SHUTD0WN..................... 3/4.11 RADI0 ACTIVE EFFLUENTS B 3/4 11-1 3/4.11.1 LIQUID EFFLUENTS.............. _........................ B 3/4 11-3 3/4.11.2 GASEQUS EFFLUENTS........................................ B 3/4 11-7 3/4.11.3 SOLID RADIO ACTIVE WASTE.................................. B 3/4 11-7 3/4.11.4 TOTAL 00SE............................................... 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING B 3/4 12-1 3/4.12.1 MO N ITO R I NG P R0G RAM....................................... B 3/4 12-2 3/4.12.2 LAND USE CENSUS.......................................... B 3/4 12-2 3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM....................... XIX

r e k60 NGL INDEX DESIGN FEATURES ~~ SECTION PAGE 5.1 SITE 5.1.1 EXCLUSION AREA............................................... 5-1 5.1. 2 LOW PO P U LAT I O N Z0 N E.......................................... 5-1 5.1. 3 MAP DEFINING UNRESTRICTED AREAS FOR RADI0 ACTIVE GASEQUS AND LIQUID EFFLUENTS............................... 5-1 FIGU.1E 5.1-1 EXCLUSION AREA....................................... 5-2 FIGURE 5.1-2 LOW PO PU LAT IO N 20N E.................................. 5-3 FIGURE 5.1-3 SITE BOUNDARY FOR GASEOUS EFFLUENTS.................. 5-4 FIGURE 5.1-4 SITE BOUNDARY FOR LIQUID EFFLUENTS................... 5-5 5.2 CONTAINMENT 5.2.1 CONFIGURATION................................................ 5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE.............................. 5-6 5.3 REACTOR CORE 5.3.1 F U E L A S S EMB L I E S.............................................. 5-6

5. 3. 2 CONT RO L RO D -AS S EM8 L I E S.......................................

5-6 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE.............................. 5-7 5.4.2 V0LUME....................................................... 5-7

5. 5 METEO RO LOGI CA L TOWE R LOCAT!0N..................................

5-7 5.6 FUEL STORAGE 5.6.1 CRITICALITY.................................................. 5-7 5.6.2 0RAINAGE................ 5-7 5.6.3 CAPACITY..................................................... 5-7 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT............................ 5-7ct / TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS................... 5-8 XX McGUIRE - UNITS 1 and 2

r l 6 c C/vngc INDEX ADMINISTRATIVE CONTROLS PAGE SECTION 6-1 6.1 RESPONSIBILITY.................................. 6.2 ORGANIZATION 6.2.1 0FFSITE............... 6-1 6.2.2 UNIT STAFF..................................... 6-1 FIGURE 6.2-1 (0eleted)............................................ 6-3 FIGURE 6.2-2 (0eleted)............................................ 6-4 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION....................... 6-5 6.2.3 STATION SAFETY REVIEW GROUP (SSRG) Function.................................................. 6-7 Composition............................................... 6-7 Responsibilities.......................................... 6-7 Authority................................................. 6-7 Records............................................. 6-7 6.2.4 SHIFT TECHNICAL ADVIS0R..................... 6-7 6.3 UNIT STAFF QUALIFICATIONS...................................... 6-7 6.4 TRAINING....................................................... C-7 6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL Activities................................................ 6-8 4 McGUIRE - UNITS 1 and 2 XXI Amendment No. 52 (Unit 1) Amendment No. 33 (Unit 2)

7_ e C onpe'. INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB) Function.................................................. 6-9 Organization............................................. 6-10 Review................................... 6-11 Audi.ts.................................................... 6-11 Authority................................................. 6-12 Records.................................................. 6-13 6.6 REPORTABLE EVENT ACTI0N........................................ 6-13 6.7 SAFETY LIMIT VIOLATION.......................... 6-13 6.8 PROCEDURES AND PROGRAMS........... 6-14 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS............................,............ 6-16 Startup Report.................... 6-16 Annual Reports............... 6-17 Annual Radiological Environmental Operating Report...... 6-18 Semiannual Radioactive Effluent Release Report............ 6-18 Monthly Operating Reports................................ 6-20 Peaki ng Facto r Limi t Repo rt............................... 6-21 McGUIRE - UNITS 1 and 2 XXII ' Amendment No. 73 (Unit 1) Amendment No. 54 (Unit 2)

e o o b'I 10/)ft INDEX ADMINISTRAT VE CONTROLS SECTION PAGE REPORTING REQUIREMENTS (Continued) 6.9.2 SPECIAL REP 0RTS.............................................. 6-21 6.10 RECORD RETENTION.............................................. 6-22 6.11 RA0!ATION PROTECTION PROGRAM....... 6-23 6.12 HIGH RADIATION AREA........................................... 6-23 6.13 PROCES3 CONTROL PROGRAM (PCP)................... 6-24 6.14 0FFSITE 00SE CALCULATION MANUAL (00CM).......... 0-25 6.15 MAJOR CHANGES TO RADI0 ACTIVE LIQUIO, GASEOUS, AND SOLIO WASTE TREATMENT............................................. 6-26 McGUIRE - UNITS 1 and 2 XXIII ' Amencment No. 32 (Unit 1) Amendment No.13 (Unit 2) _}}