ML20092H518
| ML20092H518 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 02/07/1992 |
| From: | ILLINOIS POWER CO. |
| To: | |
| Shared Package | |
| ML20092H488 | List: |
| References | |
| NUDOCS 9202210178 | |
| Download: ML20092H518 (127) | |
Text
{{#Wiki_filter:Attachment 3 to U-601884a LS-91-004 Page 1 of 127 INDEX DEFINITIONS SECTION PAGE 1.24 MEMBER (5) 0F THE PUBLIC.'....................................... 1-4 1.25 MINIMUM CRITICAL POWER RATI0................................... 1-5
- 1. 26 0FFSITE DOSE CALCULATION MANUAL (00CM). . . . . . . . . . . . . . . . . . . . . . . . . 1-5 1.27 OPERABLE - -
0PERABILITY......................................... 5
. l'. 28 OPE RATIONAL CONDITION - CONDITION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1,29 PHYSICS TESTS.................................................. 1-5 1.30 PRESSURE BOUNDARY LEAKAGE...................................... 1-5 1.31 PRIMARY CONTAINMENT INTEGRITY.................................- .
f 1.32 PROCESS 50NTROLPROGRAM(PCP)..................................1-6 1.33 PURGE - PURGING................................................ 1-6 1.34 RATED THERMAL P0WER...........................z................ 1-6 1.35 REACTOR PROTECTION SYSTEM RESPONSE TIME........................ -t-h I ~l 1.36 REPORTABLE EVENT............................................... def _____ l-7 1.37 R00 0ENSITY.,,................................................. 1-7 1.38 SECONDARY CONTAINMENT INTEGRITY..............I................ 1-7 1.39 SELF TEST SYSTEM............................................... 1-7 1.40 SHUTOOWN MARGIN................................................ 1-8 1.41 SITE B00NDARY.................................................. 1-8 1.42 DetETE0......................... .............................. 1-8 1.43 DELETE 0........................................................ 1-8 1.44 STAGGERED TEST BASIS........................................... 1 1.45 THERMAL P0WER..................'................................ 1-8 \ 1.46 TURBINE BYPASS SYSTEM RESPONSE TIME....................... .... 1-8 1.47 UNIDENTIFIED LEAKAGE........................................... 10 b3 [i; ' 9202210178 920207 PDR P ADOCK 05000461 g PDR t a CLINTON_- UNII.t ii Amendment No. 40 m.
Attachment 3
- to U-601884a LS-91-004 Page 2 of 127 INDEX OEFINITIONS '
SECTION - - - PAGE 1,48 UNRESTRICTED AREA....................................-.... .... 1-9 1.49 0ELETED........................................................ 1-9 1.50 VENTING...................... ................................. 1-9 Table 1.1 Surveillance Frequency Notation. . . . . . . . . . . . . . . . . . . . . . . . . . 1-10 Table 1.2 Operational Conditions..........',........................ 1-11 2.'0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS THERMAL. POWER, low Pressure or Low F1ow. . . . . . . . . . . . . . . . . . . . 2-1 .... THERMAt. POWER, High Pressure and High F1ow. . . . . . . . . . . . . . . . .2-1 .... Reactor Coolant System Pressure................................ 2-1 Reactor Vessel Water Level..................................... 2-1
- 2. 2 LIMITING SAFETY SYSTEM SETTINGS Reactor Protection System Instrumentation Setpoints. . . . . . . . . . . , 2-2 Table 2.2.1-1 Reactor Protection System Instrumentation Setpoints.. 2-3 BASES 2.1 SAFETY LIMITS Introduction................................................... B 2-1 THERMAL POWER, low Pressure or Low F1ow........................ B 2-1 THERMAL. POWER , High Pres sure and High Flow. . . . . . . . . . . . . . . . .B. .2-2 .,
- Reacto r Coolant Sys tem Pres s ure. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B. 2-2
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Attachment 3 to U-601884a LS-91-004 Page 3 of 127 INDEX BASES SECTION PAGE SAFETY LIMITS (Continued)
-- 0 L E T C 0 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... ..... . 0 ;
Reactor Vessel Water Level........... ......................... B 2-5 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Protection System Instrumentation Setpoints............ B 2-6 3.0/4.0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 A.PPLICABILITY........... .................................... 3/4 0-1 3/4.1 REACTIVITY-CONTROL SYSTEMd 3/4.1.1 SHUTDOWN MARGIN....................................... .. 3/4 1-1 3/4.1.2 REACTIVITY AN0MALIES...................................... 3/4 1-2 3/4.1.3 CONTROL R005 - Control Rod Operability............. ................. ... 3/4 1-3 Control Rod Maximum Scram Insertion Times................. 3/4 1-6 Control Rod Scram Accumulators............................ 3/4 1-9 Control Rod Drive Coupling................................ 3/4 1-11 Control Rod Position Indication......... ................, 3/4 1-13 Control Rod Drive Housing Support. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-15 3/4.1.4 -CONTROL ROD PROGRAM CONTROLS Control Rot Withdrawal.................................... 3/4 1-16 Rod Pattern Control System................................ 3/4 1-17 CLINTON - UNIT 1 iv Amendment No. 18 A
Attachment 3 to U-601884a
, ,. 1.S-91-004 Pane 4 of 127 INDEX_
LIMITING. CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREME SECTION PAGE _-INSTRUMENTATION (Continued)
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............ . 2/* -05 Accident Monitoring Instrumentation....................... 3/4 3-86 Table 3.3.T.5-1 Accident Monitoring Instrumentation................ 3/4 3-87 Table 4.3.7.5-1 Accident Monitorin Requirements.............g Inscrumentation Surveillance
................................. 3/4 3-89 Source Range Monitors..................................... 3/4 3-90 Traversir.g In-Core Probe System........................... 3/4 3-91
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CLINTON - UNIT 1 viii Amendment No. 40
Attachment 3 to U-60188ta
. LS-91-004 Page 5 of 127 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE REACTOR COOLANT SYSTEM (Continued) 3/4.4.6 PRESSURE / TEMPERATURE LIMITS............................... 3/4 4-22 Figure 3.4.6.1-1 Reactor Vessel Pressure Versus Minimum Reacto Vessel Metal Temperature....................................r .... 3/4 4-24
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_: v _ ( Reactor Steam Dome........................................ 3/4 4-26 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES. . . , . . . . . . . . . . . . . . . . . . . . . . s 3/4 4-27 3/4.4.8 S T RUC TU RA L I N T EG R I TY. . . . . . . . . . . _3/4 . . . .MB
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3/4.4.9 RES100AL HEAT REMOVAL Hot Shutdown.......................T...................... 3/4 4-29 Cold Shutdown............................................. 3/4 4-31 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ECCS - 0PERATING.......................................... 3/4 5-1 3/4.5.2 ECCS - SHUTD0WN........................................... 3/4 5-5 3/4.5.3 SUPPRESSION P00L.......................................... 3/4 5-7 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Primary Containment Intetcity .......................... 3/4 6-1 Primary Containment Leakage.
........................... 3/4 6-2 Primary Containment Air Locks............................. 3/4 6-5 MSIV Leakage Control System...............................
3/4 6-7 Containment Structural Integrity................... ...... 3/4 6-9 vontainment Internal Pressure............................. 3/4 6-10 i CLINTON - UNIT 1 x Amendment No. 51 ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ - . _ _ . _ _ _ _ - _ _ . _ . _ . _ . _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ . ._._.____m
.- Attachment 3 to U 601884a
. LS 91-004 Page 6 of 127 INDEX LIM 111NG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTIO 3 PAGE
, CONTAINMENT SYSTEMS (Continued) ,
Primtry Containment Average Air Temperature. . . . . . . . . . . . . . . 3/4 6-11 Jontainment Building Ventilation and Purge Syctems........ 3/4 6-12 3/4.6.2 DRYWELL ' Drywell Integrity............................'............. 3/4 6-14 Drywell Bypass Leakage.................................... 3/4 6-15 D rywe l l A i r Lo c ks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-16 Orywell Structural Integrity.............................. 3/4 6-18 Drywell Internal Pressure................................. 3/4 6-19 D rywel l Ave ra ge Ai r Tempe ra ture . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-20 Orywell Vent and Purge System............................. 3/4 6-21 3/4.6.3 DEPRESSURIZATION SYSTEMS Suppression P001.......................................... 3/4 6-23 Containment Sprey......................................... 3/4 6-26 Suppr e " i on Pool Cool i ng. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-27 * (y@_ MA RD Supp p s ion Pool Hakeup Sys tem. . . . . . . . . . . . . . . 3/4 . . . 6-28......... 3/4.6.4 n CONTAINMENT ISOLATION VALVES.............................. 3/4 6-29 m,u m,_ , h. . ,w m .c. - - o . d. ...s . . .,7,. ,. m a. . , mz. ......................... y, . c
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. 3/4.6.5 DRYWELL POST-LOCA VACUUM RELIEF VALVE 5.................... 3/4 6-69 4 4l ,)
3/4.6.6 SECONDARY CONTAINMENT i l i Secondary Containment Integrity........................... [ 3/4 fr49-(o M Figure 4.6.6.1-1 Secondary Containment Orawdown Time for 1500 CFM Boundary Leakage. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6&r (n 45 SecondaryContainmentAutomaticIsolationDampers........( 3/4-9 4 ~& I v_ CLINTON - UNIT 1 xi Amendment No. 21
Attachment 3 to U-601884 a
. 4 l.S-91-004 Page 7 of 127 INDEX LIMITING CON 0!TIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE CONTAINMENT SYSTEMS (Continued)
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3/4.6.7 ATHOSPHERE CONTROL h, 3 i ! Containment Hydrogen Recombiner Systems. . . . . . . . . . . . . . . . . . . / 3/4 ++>(e-H i
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Containment /0rywell Hydrogen Mixing Sys tem. . . . . . . . . . . . . . . . - (13/4 4-+9-(e Primary Containment /Orywell Hydrogen Ignition System...... 3/4 fr-hr 6-N b 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Shutdown Service Water System (Loops A, B, C)............. 3/4 7-1 Ultimate Heat Sink........................................ 3/4 7-2 3/4.7.2 CONTROL ROOM VENTILATION SYSTEH........................... 3/4 7-3 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEH. . . . . . . . . . . . . . . .3/4 . . . 7-7 3/4.7.4 SHUBBERS.................................................. 3/4 7-9 Figure 4.7.4-1 Sample Plan for Snubber Functional Test. . . . . . . . . . . . . 3/4 7-14 3/4.7.5 SEAL.E0 SOURCE CONTAMINATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . .3/4 .. 7-15 3/4.7.6 MAIN TURBINE BYPASS SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.7-17 .. 3/4.7.7 LIQUI D ' ST ORAG E TANKS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .3/4 . . . 7-18 3/4.7,8 MAIH COHOENSER OFFGAS HONITORING Of fgas - Explosive Gas Mixture. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-19 Offgas - Noble Gas Radioactivity Rate..................... 3/4 7420' 3/4.8 ELEC12ICAL POWER SYSTEMS 3/4.8.1 AC SOURCES AC Sources - Operating.............. . ................'..... 3/4 8-1 CLINTON - UNIT 1 xil Amendment No. 40 . 4
Attachment 1 to U 601334a
, . LS-91-004 INDEX Page 8 of 127 LlHITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIRE
=
_SECTION PAGE i 3/4.8 ELECTRICAL _ POWER SYSTEMS (Continued) Table 4.8.1.1.2-1 Diesel Generator Test Sched AC Sources - Shutdown................ule................... 3/4 8-10
..................... 3/4 8 11 3/4.8.2 OC SOURCES DC Sourc6s - Operating.................................... 3/4 8-12 Table 4.8.2.1-1 Battery Surveillance Requitidents.................. 3/4 8-15 DC Sources -
Shutdown..................................... 3/4 8-16 3/4.8.3 ONSITE POWER O!STRIBUTION SYSTEMS Distribution - Operating.................................. 3/4 8-17 Distribution - Shutdown................................... 3/4 8-21 3/4.8.4 ELECTRICALEQUIPHENTPROTECTIVEDEVICES Containment Pene 0evices..........tration Conductor Overcurrent Protective m- - - - ,
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3/4 8-24 Dat:fr ;nt P:ncir:tt::
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........................... 3/i 0 00-Motor Operated Valves Thermal Overload Protection.......h 3/4-B-%- 8
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Reactor Protection System Electric Power Honitoring....... 3/4 8'N 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR H0DE SWITCH.......................................- 3/4 9-1 3/4.9.2 INSTRUMENTATION........................................... 3/4 9-3 3/4.9.3 CONTROL R00 POSIT!0N............,,........................ 3/4 9-5 3/4.9.4 DECAY TIME.............. ................................. 3/4 9-6 3/4.9.5 COMMUNICATIONS..........,................................. 3/4 9-7 CLINTON - UNIT 1 xiii Amendment No. 40
Attachment 3 to U 601884 a 1.S-91 004 INDEX page 9 of 127 p- w+ ,, --
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Attachme.it 3 t o U 601884 a LS 91-004 Page 10 of 127 INDEX BASES SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION................. B 3/4 3-1 3/4.3.2 CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM... B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYS7t A ACTUATION INSTRUMENTATION... B 3/4 3 3 3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMCdTATION......... B 3/4 3-3 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION........................................... B 3/4 3-4 3/4.3.6 CONTROL ROD BLOCK INSTRUMENTATION......................... B 3/4 3-5 3/4.3.7 MONITORING INSTRUMENTATION Radiation Moni toring Instrumentation. . . . . . . . . . . . . . . . . . . . . . B 3/4 3-5 Seismic Monitoring Instrumentation........................ B 3/4 3-5 Meteorological Monitoring Instrumentation................. B 3/4 3-5 Remote Shutdown Monitoring Instrumentation................ B 3/4 3-6 Accident Monitoring Instrumentation....................... B 3/4 3-6 Source Range Monitors..................................... B 3/4 3-6 Traversing In-Core Probe System........................... B 3/4 3-6 Chlorine Detection System................................. B 3/4 3-7
- ht::th: 5:tr:nteth: (d:ht:d)............ ..... O;/4;]
Loose-Part Detection System............................... B 3/4 3-7 CLINTON - UNIT 1 xvii
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' Attachment 3
' t o U-601884 a
.
- LS-91-004 l'a!;c 11 of 127 BASES PAGE j SECTION INSTRUMENTATION (Continued) .
Main Condenser Offgas Treatment System Explosive Gas Honitoring Instrumentation............................ B 3/4 3-8 3/4.3.8 h bi( f':kITj0Di'h hi d.).h5].h......... B 3/4 3-8 3/4.3.9 PLANT SYSTEMS ACTUATION INSTRUMENTATION................... B 3/4 3-8 3/4 3.10 NUCLEAR SYSTEM PROTECTION SYSTEH - SELF TEST SYSTEM....... B 3/4 3-9 Bases Figure B 3/4.3-1 Reactor Ves sel Water Leve1. . . . . . . . . . . . . . . . . . . B 3/4 3-10 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEH...................................... B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES...................................... B 3/4 4-3 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems................................. B 3/4 4-3 Ope ra ti onal Le a kag e. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.4.4 CHEMISTRY................................................. B 3/4 4-4 3/4.4.5 SPECIFIC ACTIVITY......................................... (B [3/4 h h - 3/4.4.6 PRESSURE / TEMPERATURE LIMITS............................,,, B 3/4 4-5 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES. . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-G 3/4.4.8 STRUCTURAL INTEGRITY...................................... B 3/4 4-7 3/4.4.9 RESIDUAL HEAT REM 0 VAL..................................... B 3/4 4-7 Bases Table B 3/4.4.6-1 Reactor Vessel Toughness Values. . . . . . . . . . . . B 3/4 4 Bases Figure'B 3/4.4.6-1 Fast Neutron Fluence (E>l Hev) at I.D.- surf ace as a function of -Service Li f e. . . . . . . . . . . . . . . . , . . . . B 3/4.4-10 Figure B 3/4.4.6-2 0ELETED......................................... B 3/4 4-11 B xviii Amendment'No; 51
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Attachment 3 to U-601884a LS-91-004 Page 12 of 127 INDEX BASES SECTION PAGE CONTAINMENT SYSTEMS (Continued) 3/4.6.6 S E COND A R Y CON TAI NMEN T. . . . . . . . . . . . . . . . . . . . .B. .3/4 . . .6-8 ........... 3/4.6.7 ATMO S PH E R E CONT R0 L. . . . . . . . . . . . . . . . . . . . . . . . . B . .3/4
. . . 6-8 ..........
3/4.7 PLANT SYSTEMS 3/4.7.1 SHUTOOWN SERVICE VATER SYSTEM............................. B 3/4 i-1 3/4.7.2 CONTROL ROOH VENTILATION SYSTEH........................... 8 3/4 7-1 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM. . . . . . . .B. .3/4 . . .7-1 ........ 3/4.7.4 SNUBBERS.................................................. B 3/4 7-2 3/4.7.5 SEALED SOURCE CONT 6MINATION............................... B 3/4 7-3 3/4.7.6 MAI'N TURBINE BYPASS SYSTEH..........................s..... B 3/4 7-3 3/4.7.7 LIQUID STORAGE TANKS...................................... B 3/4 7-3 3/4.7.8 MAIN CONDENSER OFFGAS MONITORING
- -~a - h Of fgas - Explosive Ga s Mixture. . . . . . . . . . . . . . . . . . . . . . . . . . . . [3/4 9-+h Offgas - Noble Gas Radioactivity Rate..................... B 3/4 7-4 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1,
- 3/4.8.2, AC SOURCES. DC SOURCES, AND ONSITE POWER and DISTRIBUTION 3/4.8.3 SYSTEMS...................................... B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES................... B 3/4 8-2 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH......................................, B 3/4 9-1 3/4.9.2 INSTRUMENTATION........................................... B 3/4 9-1 3/4.9.3 CO NT RO L R00 P0S I T I ON. . . . . . . . . . . . . . . . . . . . . . . . . . . .B. .3/4 . . . 9-1 .....
CLIST0H-UNIT 1 'xx Amendment No. 40
At t a c hnw n t 3 to U-601884a 1,S-91-004 l' age 13 of 127 IHOEX BASES SECT 10!! PdGE REFUELING OPERATIONS (Continued) 3/4.9.4 DECAY TIME...'............................................. B 3/4 9-1 3/4.9.5 COMMUNICATIONS............................................ B 3/4 9-1 3/4.9.6 FUEL NANDLING EQUIPMENT................................... B 3/4 9-1 3/4.9.7 CRANE TRAVEL - SPENT AND HEW FUEL STORAGE AND CONTAINMENT FUEL P00LS........................ UPPER
............ B 3/4 9-2 3/4.9.8 WATER LEVEL - REACTOR VESSEL and WATER and' LEVEL - SPENT FUEL STORAGE AND 3/4.9.9 FUEL P00LS. . . . . . . . . . ............................
. . . . . . . . . . UPPER CONTAINHENT B 3/4 9-2 3/4.9.10 CONTROL R00 REM 0 VAL....................................... B 3/4 9-2 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION............. B 3/4 9-2 3/4.9.12 INCLINED FUEL TRANSFER SYSTEM.............................
B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY /0RYWELL INTEGRITY........... B 3/4 10-1 3/4.10.2 R00 PATTERN CONTROL SYSTEM................................ B 3/4 10-1 3/4.10.3 GNUT00WN MARGIN DEMONSTRATIONS............................ B 3/4 10-1 3/4.10.4 R EC I RCU LAT IO N L00 P S . . . . . . . . . . . . . . . . . . .B.3/4 . . .10-1 3/4.10.5 TRAINING STARTUPS......................................... B 3/4 10-1 3/4.10.6 SPECIAL INSTRUMENTATION - INITIAL CORE LOADING............ 8 3/4 10-1
-3/1.11 0:leted-CLINTON - UNIT 1 xxi Amendment No. 40
Attachment 3 to U-601884a
, LS-91-004 Page 14 of 127 INDEX
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' l 5.1 SITE a
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Exclusion Area...............................................,.. 5-1 low Population Zone............................................ 5-1 Map Defining Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid'Erfluents....................... 51 5.2 CONTAINHENT Configur'ation.................................................. 5-1 Design Temperature and Pressure................................ 51 . Figure 5.1.1-1 Exclusion Area...............................~....... 5-1 Figure 5.1.2-1 Low Pop ul at i on Zo ne. . . . . . . . . . . . . . . . . . . . . . . . . . 5-3 Figure 5.1.3-1 Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents.................. 5-4 Secondary Containment.......................................... 5-5 4 CLINTON - UNIT 1 xxii Amendment No. 40
Attachment 3 t o U-601884 a l.S.91 004 Page 15 of 127 DESIGN FEATURES _SECTION PAGE 5.3 REACTOR CORE Fuel Assemblics...'.......................................'...... 5-5 Control Rod Assemblies........................a................ 5-5 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature......,.......................... 5-5 Volume......................................................... 5-5
- 5. 5_ _ MET EOROLOGICAL TOWER LOCAT10H. . . . . . . . . . . . . . . . . . . . . . . . . . . .5-6 ......
- 5. 6 FUEL STORAGE Criticality.............................. ....................'. 5-6 0rainage.............................................. w .v.T. 5-6 Capacity....................................................... 5-6 5.7 COMP 0HEHT CYCLIC OR TRANSIENT L1 HIT. . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-6 Table 5.7.1-1 Component Cyclic or Transient Limits. . . . . . . . . . . . . . . . . 5-7 6.0 ADMINISTRATIVE CORTROLS 6.1 RESPONSIBILITY................................................. .
6-1
. 6.2__
ORGANIZATION................................................... 6-1
-6.2.1 0FFSITE AND OHSITE ORCAH11AT10HS............................ . 6-1 6.2.2 UNIT STAFF................................................... 6-10.
Figure 6.2.1-1 0 E L ET ED . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-3 Figure 6.2.2-1 DELETED............................................. 6-4 Table 6.2.2-1 Minimum Shif t Crew Composition Single Unit Facility.. 6-5 CLINTON - UNIT 1 xxiii Amendment No. 34
_~.- .. .- - .-- _-. - - - -._. _ _ _ _ _ _ _ - . . _ , - Attachtwnt 3 t o U-601804 a
. l.S 91-004 Page 16 of 127 Of f IN_l110f(S I
CONTAINMENT AND PEACTOR VESSEL ISOLATION CONTROL SYSTEM RESPONSE 11ME 1.7 The CONfAINMENT AO REAC10R VLSSEL ISOLATION AND CONTROL SYSTLM (CRVICS) RESPONSE 11ME shall be that time interval from when the monitored parameter exceeds its isolation actuation setpoint at the channel sensor until the isolation valves travel to their required positions. Times shall include diesel generator starting and sequence loading delays where applicabic. The r,esponse time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measurci CORE ALTERATION 1.8 CORE ALTERATION shall be the addition removal, relocation or movement of ; fuel, sources, or reactivity controls withIn the reactor pressure vessel with the vessel head removed and fuel in the vessel. Hovement, including undervessel replacement, of the SRMs, IRMs, LPRMs, Tips, or special movabic detectors is e not considered a CORE ALTERATION. Suspension of CORE ALTERATIONS shall not pre-clude completion of the movement of a component to a safe conservative position. _ CORE OPERATING LIMITS RLPORT
- 1. 9 The CORE OPERATIrG LIMITS REPORT is the Clinton-specific document that provides core operating limits for the current operating reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.9t plant operation within these operating limits is addressed in individ'ual Specifications.
1 CRITICAL POWER RATIO 1.10 The CRITICAL p0WER RATIO (CPR) shall b[ the ratto of that power in the assembly which is calculated by application of an approved General Electric Critical Power correlation to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power. DOSE EQUIVALENT I-131 1.11 DOSE EQU1 VALENT I-131 shall be that concentration of.1-131, microcuries per gram, which alone would produce the same thyroid dose as the. quantity and
, isotopic mixture of I-131, I-132, I-133,1-134, and I-135'actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance factors for Power and lest Reactor Sites." DRYWELL INTEGRITY 1.12 DRYWELL INTEGRITY shall exist when:
- a. All drywC) penetrations required to be closed during accident conditions are either:
- 1. Capable of being closed by an OPERABLE drywell automatic isolation system or .
- 2. Closed by at least one manual valve, blind flangor_ drac_tivated tomatic yalve _securedanJtL closed position, cmpt ~^
c; pr; idQ
-ic h l C.,. m 5f-Specificati;n E .'.- a m_ -
- b. The drywe equipment hatch is closed and sealed,
- c. The drywell atriock is OPERABLE pursuant to Specification 3.6.2.3.
CLINTON - UNIT 1 1-2 Amendment,No. 32
Attachment 3 to if-601884a !
. 1.S 91 004 Page 17 of 127 ;
l DEFINITIONS !
- PRIMARY CONTAINMENT INTEGRITY 1.31 PRIMARY P N M fNMENT INTEGRITY thall exist when!
4 DthsC a. All containment penetrations required to be closed during accident condi-tions are either: 1., Capable of being closed by an OPERABLE containment automatic isolation system or
- 2. Closed by at least one manual valve, blind flange, or deactivated out mg ic valvsts.ccured in its closed position, except as provided i X 5 M M -D 5pecification 3.6.4.
"PfMat
- b. ~~All contd nment equipment hatches are closed and sealed.
pMLtG
- c. Each3 contailiment air lock is in compliance with the requirements of Specificatian 3.6.1.3. i MiiMef fD
- d. The n conTalnnient leakage rates are within the limits of Specification 3.6.1.2. i
- e. The suppression pool is in compliance with the requirements of Specification 3.6.3.1.
- f. The sealing mechanism associated with each primary containment penetra-tion, e.g., welds, bellows or 0-rings, is OPERABLE.
PROCESS CONTROL PROGRAM (PCP) - 1,32 The PROCESS CONTROL PROGRAM shall contain the current formula, sampling analyses, tests, and determinations to be made to ensure that the processing, and packaging of solid radioactive wastes based on demonstrated )rocessing of actual or simulated wet solid wastes will be accomplished in suc1 a way as to assure compliance with 10 CFR Part 20 10 CFR Part 61 10 CFR Part 71 and Federal and State regulations, burial, ground requireme,nts and other require-ments governing the disposal of the radioective waste.. '
-_ PURGE - PURGING
=.
1.33 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition in such a manner that replacement air or gas is required to purify the confinement. RATED THERMAL POWER 1.34 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2894 Kdt. I' l- . l l CLINTON - UNIT 1 1-6 Amendment No. 40 L
Attachment 3 I to U+601884a , . - LS-91+004 Page 18 of 127 , DEFINITIONS REACTOR PROTECTION SYSTEH RESPONSE TIME 1.35 REACTOR PROTECTION SYSTEM RESPONSE TIME shal,1 be- the time interval from
.- when the monitored parameter exceeds its trip setpoint at the channel sensor i until deenergitation of the scram pilot valve solenoids. The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.
REPORTABLE EVENT l 1.36 A REPORTABLE EVENT shall be any of those conditions specified in
- Section 50.73 to 10 CFR Part 50. ;
5 _R00 0ENSITY J 1.37 R00 DENSITY shall be the aumber of control rod notches inserted as a fraction of the total number of control rod notches. All rods fully inserted are equivalent to 100% R00 DENSITY. ;
)
SECONDARY CONTAINHENT INTEGRITY
+
4 1,38 SECONDARY CONTAINMENT INTEGRITY shall exist when: a. All secondary containment penetrations required to be closed during accident conditions are either i
- 1. t Capable of being closed by an OPERABLE secondary containment automatic '
isolation. system or ' 2. Closed by at least one manual valve blind flange, or deactivated i automatic valve or damper an annuca, bit tacured in its closed posi-tion, except as provided InQ.J.J.gy. pecification 3.6.6.2. ' b. All secondary containment equipment hatches are closed and sealed. 1 c. The standby gas treatment system is in compliance with the requirements of Specification 3.6.6.3. d. At least one door in each access to the second'ary_ containment is closed.- except for normal entry and exit. e. The sealing mechanism associated with each secondary containment penetra-tion, e.g. , welds, bellows or 0-rings, is OPERABtE. , f. The pressure within the secondary containment is less than oc equal to the value required by Specification 4.6.6.1.a. SELF TEST SYSTEM ' 1.39 The SELF TEST SYSTEM (STS) shall be that automatic test system designed to continually monitor the solid state nuclear system protection system (NSPS) functional circuitry by injecting short duration pulses into.cfrcuits and _. verifying proper circuit response to various -input combinations. . The SELF TEST CLINTON - llNIT 1- 1-7_ Amendment No. 40 . !
,_ 1. c. ;, . . . .. _._ - _ _ _ _ . . _ . . ,_._.._. _ _ _. _ . _ ;_._-,... _ .a _ _
_-_- . _ . _. - - -- _ ~ _ - - Attachment 3 t o U*601884 a t . 1.S-91-004 Page 19 of 127 Z O w W U o so m ch o m m 4 41 N N A CN to m so m 60 N N N N N m st) m on NN NN NN NN NN J Z ' en O 4 m *O
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W H CLINTON - UNIT 1 - 3/4 3-13 Amendment No. 50
p TABLE 3.3.2-1 (Continued)
=
Q CRVICS INSTRLMENTATION
=
HINIMLM CPERACLE APPLICA5LE
$ ISOLATI iMiNELS FER TRIP OPERATICNAL y TRIP FUNCTION SIGNA .. YSTEM CONDIi!CN Ac;;cy 1.' Main Steas Line Radiatica - Iligh C (a) 1, 2, 3 23
- m. Fuel Guilding Exhaust (b)(f)(J) 2(a) 1, 2. 3 25 Radiation - Illgh a 73
- n. Manual Initiatica R(b)('f) 1 1,2,3 :s R :5 APPLICABLE
, ISOLATION APPLICABLE OPERATIONAL g 2. MAIN STEA51 LINE ISOLATION t SIC'IAL TABLE NOTES COMITIONS ACTIcy w a. Reactor Vessel Water Level-Lew 0
^
Low Low, level 1 U NA 1, 2* 3 0
- b. Main Steam Line Radiation - Iligh C d 1, 2 3 33
- c. Main Steas Line Pressure - Lov H NA 1 23
- d. Main-Steas Line Flew - High D NA 1,2,3 23
- c. Condenser Vacuus - Lcw J~ NA 1, 2 * * , 3.
- 23
- f. Main Steam Line Tennel Terp.
- High E NA 1,2,3 23
- g. Main Steam Line Tunnel ti Terp.
- High F NA 1, 2, 3 23
- h. Main Steam Line Turbine Bldg.
Icep. - High G P 1, 2. 3 23 p i. Manual Initiation R NA 1,2,3 22 3 a .
?5EE
's?:
5E$$ O! eE;;
- g-
,3 =w
~
TABLE 3.3.2-1 (Continued) . E CRVICS INSTRUMENTATION EE o"
- MINIMUM OPERABLE APPLICABLE '
150LATIO CHANNELS PER TRIP CPERATIONAL CGNDITION ACTION E TRIP FUNCTION SIGNA _ (g) . SYSTEM
- 3. REACTOR WATER CLEANUP SYSTEM ISOLATION 27
- a. a Flow - High 1 7 k
I* 2* 3 X 1 1, 2, 3 27
- b. a Flow Timer
- c. Equipment Area Temp. - High g I, 2, 3 27
- 1. Pu:::p Rooms - A, B, C N 1/ room
- 2. Heat Exchanger Rooms - East. 27 N 1/ room (k) I, 2, 3 West
- d. Equipment Area a Temp. - High g) I, 2, 3 27
- 1. Pump Rooms - A, B, C 2 1/ room !
l
- 2. Heat Exchanger Rooms - East, 1, 2, 3 27
. West 2 1/ room (k)~
- e. Reactor Vessel Water 2 II w 1, 2, 3 29 D Level - Low Low, Level 2 8
# 25 w
0
- f. Main Steam Line Tunnel I I) 1, 2, 3 27
-Ambient. Temp. - High E
- g. Main Steam Line Tunnel 1
g 1,2,3 27 ATenip. - High g F l X 1 1, 2, 5
- 27
- h. SLCS Initiation ,g)g) 1,2,3 26
- i. Manual Initiation R 1
# 25
- 4. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION ^
1( } 1, 2, 3 27 E a. RCIC Steam Line Flow - High V , E b. RCIC Steam Line Flow - High I) 27 X I I, 2, 3 . _ , , ,
$ Timer awo-C
& c. RCIC Steam Supply 27 3 ; g' y V(h) 1(k) 1, 2, 3
' 1 Pressure - Low
.o,E s,3-
- d. RCIC Turbine Exhaust Diaphragm Pressure - High V 2
) I, 2, 3 27 g**
n TABLE 3.3.2-1 (Continued) . . C g CRVICS I.4STRUMENTATION - E E MINIHUM OPERASLE APPLICABLE E ISOLATION -- CHANNELS PER TRIP OPERATIONAL TRIP FUNCTION SIGNA f SYSTEM CONDITION ACTION l
- 4. REACTOR CORE ISOLATION CCOLING SYSTEM ISOLATION (Continued)
- c. RCIC' Equipment Room Ambient Temp. - High -
V 1(k) 1,2,3 27
- f. .RCIC Equipment Room -
A Teep. - High V 1(k) 1,2,3 27
- g. . Main Steam Line Tunnel g Ambient Temp. - High E -
1(k) 1, 2, 3 27 s w h. Main Steam Line Tunnel j A Temp. - High F I I) 1, 2, 3 27
- i. Main Steam Line Tunnel Te=perature Timer X 1( ) 1, 2, 3 27
,. Drywell Pressure - High L(h) 1(k) 1, 2, 3 27
- k. Manual Initiation R 1( ) 1, 2, 3 26
- 1. RHR/RCIC Steam Line Flow - High V l I) 1, 2, 3 27
- m. RHR Heat Exchanger A, B T 1/ room (N) 1, 2, 3 28
{ Ar.bicnt Temperature - High
~
% n. RHR Heat Exchanger A, 8 S 1/ room I) 1, 2, 3 28 g?*;>
~ . - , .
=
e
. A Temp. - High * $ ? *,
[ - 2 E;a y-y ,w
~4
e !
- ~ :
1 l n . TABLE 3.3.2-1 (Continued) , r-
. o$ ,
CRVICS INSTRUMENTATION
- x APPLICABLE h ISOLAT 4 MINIMUM OPERABLE CHANNELS PER TRIP OPERATIONAL
, ?! . .
~
TRIP FUNCTION- . SIGNA SYSTEM CONDITION ACTION
] t
- 5. RHR SYSTEM ISCLATION
- a. RHR Heat Exchanger A, B .
g) Ambient Temperature.- P.igh - Tt 1/ room 1, 2. 3 28 l 1
~
I b. RHR Heat Exchanger A, B '. : "! I) ATemp. - High f, . . Je - l ~ 5; _ : :1/rcom 1, 2. 3 28 i _
.w c. Reactor Ve'ssel Water' y- ' -
E *^ C
~
[ 'c:
<2g ,)
.), -
Level - Low, Level 3 r; t.; g 1, 2. 3 28 i
, , t . . . - , 1
! ,5 d.- Reactor Vessel WatiEi.evel - Low Low Low;-Level 1 - U. I*# 2(k) . 1, 2, 3 28 l t e.. Reactor Yessel (RHR Cut-in ? . Permissive) Pressure - High X- 2(*) 1, 2, 3 28
- f. .Drywell Pressure - High;.. *
, .- .. ,. e
. .f,
. <". .~ .. .
t p
- 1) RHR Testi Lines * . 3 L :.3 2(k) -
1, 2, 3 28 i
- 2) Fuel Pool Cooling- ~
- f. ' L U.e
. 2g) ' -
1, 2, 3 . 28 !
- a . * ; -
q , tv f.
~
t l'!- g. Manual Initiation ' ~ ' t . .. JR T. "; . ' 1 . . 1,2.3 26 ! F ,
,- . y ; .
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Attachment 3 to U 601884a LS-91 004 Page 24 of !?7 TABlf 3.3.2-1 (Continued
~tkVl W IN5TisN[TilATION )
TABLE 140TATIONS
# When handling irradiated fuel in the primary or secondary containment and during CORE AllERATIONS and operations with a potential for draining the reactor vessel.
## When handling irradiated fuel in the primary containment (building) and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
- With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2. ..
^^ When any ' turbine stop valve is greater.than 95'4 open or the reactor mode switch is in the run position.
t Main steam line isolation trip functions have 2-out-of-4 isolation logic. except for the main steam line flow - high trip function which has 2-out-of-4 isolation logic for each ma_in steam line. t " :E!p::PhatIn 3.5.' hb6 ? O-1 hr 6 6: 7ki:r:% tdt d
-t M i(a'aty n g!;= h _ _
(a) A channel liiay be:placed in an inoperable status for up to 2 hours for.
^
required surveillanc'e without placing the trip system in the tripped con-dition provided .at least one other OPERABLE channel in the same trip, system is monitoring that parameter. i:- (b) Also actuates the standby gas treatment system, h.. t-(c) Deleted dj $ .' (d) Also trips.andJsolates the mechanical vacuum pumps. S.li s ., (c) Isolates RWCU valves 1G33-F001 and 1G33-F004 only. secondary containment ventilation isolation dampersh (f)@Also itetuat2E'; A E R i-(0) Hanual Switch closes RVCU system inboard isolation valves F001. W8, F053, F040 and outboard isolation valves F004, F039, F034 and F0$4. (h) Vacuum breaker-isolation vaives require RCIC. system steam supply pressure low coincic'ent'with drywell. pressure hiDh for isolation of vacuum breaker isolation vulves. ..-
~
(i) A single manal isolation switch isol'ates outboard steam supply line isolation valve (F064) and the RCIC pump suction from suppression pool valve (f031) only following a manual or automatic (Reactor Vessel Water Level 2) RCIC system initiation. (j) Dnly ghats pqondary containnent ventf ation isolitton dag j 1 % 0.0.E.q-). T:p (I ': = 1: @ hjb -__r: th k Q F @ (k) A channel may be placed in an inoperable status for up to 2 hours for . required survetilance without placing the trip system in the trip con-dition provided that the redundant trip system is OPERABLE and monitoring that parameter. (1) Not required to be OPERABLE when valves IVR002A,0 and IVQ006A,0 are scaled closed in accordance with Specification 3.6.4. Amendment No. 48 CLINTON - UNIT 1 3/4 3-18
.\ttachment 3 t o U401884a
, 1,s 91 004 Page ?$ of 127 I
TAutf 3.3.2-1 (Continued) llNTf$7Ii5TE{IMENIATION TABLE NOTATIONS 1 (m) Four reactor vessel water icvel trip channels are logically combined in a one out of-two twice configuration. For'the purposes of the associated ACTION, each one out-of-two logic is defined as a separate trip system. 4 (n) Four drywell pressure trip channels are-logically combined in a one-out-of-two twice configuration. For the purposes of the associated ACTION, i each one out-of two logic is defined as a separate trip system, j (o) One trip system is associated with the A and 8 monitors; the other trip l system is associated with the,C and 0 nionitors. ' i (p) Each channel consists of five temperatura modules and their associated sensors. A channel is OPERABLE if and only if.five temperature modules l and their associated ,- sensors are OPERABLE. _ (.g) 791 don 5tgnal de$cd Hon 5 b ** 5'imbI5 '*99"'I"3 in 4be TeMHon Spa column cWeTwed below: , hrn6) h 'PHo^ A Reactor Vessel Water Level low (Level 3) B i l 8 Reactor Vessel Water Level low (Level 2) C Main Steam Line Rad.-High and Inop D Hain Steam Line High Flow E F Main Steam Tunnel Temp. High Main Steam Tunnel Differential Temp. High j)f G Main Steam in Turbine Building Temp. High \ H Turbine Inlet Pressure Low J ' ' Condenser Vacuum Low-L Drywell Pressure High , ,d M Containment Exhaust Duct High Rad. - 1 N RWCtl High Temp.. ,) P Containment Pressure-High 1l R CRVICS Manual Initiation Pushbuttons - 5 I S RHR Heat Exchanger Rooms A, B High Differential Temp. T RHR-Heat Exchanger Rooms A, B High Temp. - k u - Reactor' Water' Level Low (Level 1) j V RCIC High Steam Line Space Temp. j RCIC Low. Steam Line Pressure T RCIC High Steam Flow High Turbir.c Cxhcust l'.aw o-PCIC Area High Temp.. (} RCIC Area High Differential Temp. y X Permissively Interlocked with Other Equipment. l Z High Rad. in Containment Refueling Pool Exhaust Duct 1 RWCU Equipment High Differential Flow 2 ' RWCU Vent High Differential, Temp.
,5- Containment Purge Duct High Radiation
. CLINT@ - UNIT 1
_=__m- -b e , 3/4 3-10a Amendment No, 50 - l l. p
Attachment 3 to U-6n1884 a 1.S-91 004 Page 26 of 127 2 INSTRUMENTATION 1 REMOTE SHU1DOWN MONITORING IN$1RUMENTAT10N 4 LIMITING CONDITION FOR OPERATION pJ.3.L4_ j l2J.1 M _IhtI;.72. rimoleMutdhnavttom G M .Q hall be OPERABLE. istumentation and controlh'.: - ~~ APPLICABILITY: 0PERAT!0NAL CONDITIONS 1 and 2. ACTION:
.c.ne, e rco'.<cA
< . _ . er rne r , ene m m ,.
,emo utdown system instrumentation channels inepenbte -- the :: 9 :d b" ?:i': E?.je _,
W@ERABLfitWuGhhTnWa'ys or tie'inrestore at least HOT the inoperable SHUTDOWNchannel within the (s) next 12 tours. uJ t hene; :._d b e7;; .' O";^ *.:' ce ' ' o e shutdown system control restore the inoperable cont inopuabwoO. r. 7; .i. ;; f5 17'i }ii T d 0FEdRE'sta swt n ayi or be in at least HOT SHUTDOWN (5) ; within the next 12 hours. .
- c. The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS , 4.3.7.4.1 Each of the above required remote shutdown syste
$39QQa},ygfgggggB gpe_rfofmg'.Q; y 0 gmeggt,jon t , -.. . ~ . _ f. 'i
. 4.3.7.4.2 Each of the above 1 switches and control i circuits'shall be demonstrated OPERABLE by verifying its capability to perform its ' intended function (s) at least once per 18 months.. ,
,emmmm -- .mm l
- o. CHnwuct CHECK ai leasi once per 31 dculs csnc9 cs C.ll AN N6L C6ttagnTicN at lepst ig~,%%w .
i N - _ V ~v y ,- y v v v v v 7 7 YC Scope oT 4hese. carates exctectes %csc assoc,ceea was
'IhC MHR 5%tn con (f en$ing mode., a W
m y_ CLINTON - UNIT 1 3/4 3-81 1
,_._.m,-_..--,._-, _
d M - r-( e _ .
. Et t .
., _ TABLE 3.3.7.4-1 r-EiE REMOTE SHUTDOWN MONITORING INSTRUMEPRATION o~ }
1 7 DIVISION I DIVISION II l' E MINIMUM.' HINIMUM - M (. EQUIPMENT CHANNELS EQUIPMENT CHArciELS b
} INSTRUMENT NUMBER OPERABLE NUMBER OPERABLE (A- l
\.
- 1. SRV 510 Temp. ,~ Supp.
Pool Temp. IC61-R506 1 1 -R513 1 {(h a i 32 7 SIC Temp., Supp. - i Pool Temp. IC -R507 1
'@a 1 IC61-R514 1
,f 3. SRV SIG Temp. , Supp.
>3
. Pool Temp.. ' .1C61-R5 1- IC61-R512 . q l
' 1 g oL 4.. Supp._ Pool.'Lvl.. IC61-R504 1 1C61-RS11 1 j t I
~1).5. , o Y 6.
RPV Lvl. RPV Press.' . 1C51-R010 IC51-R011 - IC61-R509 IC61-R510
. 1 1
g{ f7. . Upper DW Temp. 1C61-R501 1
=:: (
tm 6
- 8. Lower DW Te=p. IC61-R5 1 9.
NA E, SX Strnr. Dsch. i
-\
Outlet. Press. 1 -R503 1 1PI-SX024B 1 h'f
- 10. RCIC Cond. Storage '
> G~ i j Tnk.' Lv1. IC61 ,R505 1 1 HA E!
j 11. RHR Loop Flow IC61-R005- 1 IElc 0038* 3
- 1. )y f 12. RCIC Terb.' Sp d 1C61-R003- 1 tiA r
a r
- 13. RCIC Pump ow i IC6.1-R001 1 NA h 14. RCIC T Flow Cntl. 'IC61-R001 1 NA S I
~
_" l g *f ~~
~ .
? *D ',, * ?, =-
sion II RHR pump flow is determined by RHR pu=p discharge pressure instru- .
~
- e ntation at panel IH22-P021. ~gSg oe*"
aw
. ~
+
L
~
.-_.-_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _._..m . .- _ _ . _ . _ _ _ _ . _ _ _ _ . . _ _ . _
Attachment 3
- = - - - t o V.601884 a ,j q c *i n t e n t o n d r _- _ *_ _ M a '_' b "* '
Page 78 of 127 i b TABLE 3.3.7.4-2 RfMOTE SHUTDOWN SYSTEM CONTROLS EQUIPMENT MINIMUM CHANNELS OPERABJE C0hROL NUMBER DTVITION 1 DTVT5r0 FIT r
)
1
- 1. h Pmp IE12-C002A/D 1
- 2. RH, Supp. Pool suction V1v IE12-F004A/8 1 1 ,.
- 3. RHR iutdown Cooling Supply Viv IE12 F006A 1 NA '
h4. RiiR Sh tdown Cooling Sply Otbd T Isol v IE12-F008 1 NA
! 5. RHR HX By ss V1v IE12-F048A/0 1 1 [(
- 6. RHR Test L Viv to Supp. Pool IE12-F024A/B 1 /1 1 v IE12-F003A/0 1 1 I RHR HX Osch f 7. 8. RCIC Steam In1 Viv to RHR HX IE12-F052A/B" 1*
- 9. RHR HX Inlet V1v 1E12-F047A/B e -. 1
- 10. RHR HX SX Outlet v IE12 F068A/B 1 / 1 I h 11. RHR Shutdown Coolin Return Viv IE12-F053A/0 1 1
- 12. RHR RPV Inboard Injec Viv 1E12-F042A/D 1 / 1
- 13. RHR RPV Outboard Inject lv IE12 F027A 1 NA t 14. RHR Cnmt spray V1v IE12-F028A 1 NA i
- 15. RHR HX 1A Condesate Dump V 1E12-F01
- 1* NA
- 16. RHR HX 1A RCIC Shutoff Viv IE12-F A* 1* NA t RHR FP/FC Sply Viv 1E12- 37A 1 NA
' f 17. 18. RHR Pump Hin Flow Recirc Viv
- IE F064A/0 1 1
)
-r 19. RHR HX 1A SX Dypass Viv 1 173A < 1 NA 1 g 20. RHR RR Sply Inbd Isol Viv 12-F006B NA 1 f 21. Shutdown Cooling Inbd 1501 Viv IE12-F009 NA 1 1
- 22. RPV Head Spray Viv , IE12-F023 NA . I y
- 23. RCIC Stm Byps Viv 51-F095 1 NA ,
RCIC Pump Cond Stg Tnk Suction V 1.'rF010 1 NA f 24.25. RCIC Supp Pool Suction Viv IES:. 031 1 NA
- 26. RCIC First Test Line Isol. V1 i i to RCIC Storage Tank 1E51-F0 1 NA f 27. RCICInjectViv IE51 F013 .1 NA
- 28. RCIC Min Flow Recrc Viv IE51-F019 1 NA J
- 29. RCIC Second Test line sol Viv e k to RCIC Stg Tnk IE51-F059 1 NA 4
- 30. RCIC Turbine L.O. ol Vtr Sply Vive,.} 1E51-F046 1 NA 1
- 31. RCIC Gland Seal r Cmpsr -
IE51-C002F 1 NA
- 32. RCIC Outbd Vac r Viv 1E51-F077 NA
- 33. RHR RCIC Sta ly Otbd Isol Viv IE51-F064 1 NA 1 i 34. RCIC Turb S Sply Viv IE51-F045 1 / NA f 35. RCIC Turb hst Stop Viv IE51-F068 1 NA J
- 36. RCIC Tri / Throttle Viv IE51-C002E 1 NA J k _ 37. RCIC T b Stm Supply Warm-up Viv '
1E51-F076 NA 1
- 38. SRV ' C 1821-F051C 1 1 SR 10 IB21-F0510 1 1
) 39.40. S SIG 1B21-F051G - 1 .
- 41. CIC Stm Flow Cntrl NA 1 l 42. RCIC Turb Trip NA 1 1$
NA 4 DG 1A Vent Fan IV001CA 1 NA _ -_ =__- - _ CLINTON - UNIT 1 3/43-83 Amendment No. 55.
-.,y - -w._
. x.-...- , - , , ._-#_. ,,,,,,.,_,,,,,,-,,.,_.,.,.m _.,_.y ,,,,._..-.7,____,,-._.,.,,,E..r-- . ,_ -,,,_ ___, _m ..
__ _ _- % Attachment 3
$t 'M*UL N b UN7E"
%M PA Page 29 of 127 TABLE 3.3. 7.4-2 (Continued) 3 RIMOTE SHUTDOWN SYSTfM CONTROLS EQUIPMENT HIN1 HUH CHANNELS OPER/f LE CQNTROL NUMBER flV1510N1 Div8TpFFIT
- 44. DG 1A Oil Rm A Xhst Fan IV002CA 1 4A k 45.
46. v I Switchgear Heat Removal Vent Fan IVXO3CA Da tery Rm 1A1 Xhst Fan IVX05CA 1 1 NA NA I[j g 47. SX n Pa Sply ran IVH01CA/0 1 1 ,
- 48. RHR P. Rm 1A Sply Fan IVYO2C ,
1 NA
- 49. RHR Ht hg Rm A Sply Fan IVYO3C 1 NA 51. OG 1A Ckt kr 252-DGKA 1 14A i
- 52. DG 1A Fuel 0 Trnsfr Pmp 10001PA NA
- 53. SX Pmp iSX01PA/0 1 1
) 54. SX/WS ! sol V1v 15X014A/B 1 q
1
- 55. DG 1A Outlet Viv ISXO63A 1 NA I $6. SX 1A Strnr Inlet V ISX003A 1 NA j
- 57. SX 1A Strnr Outlet V1 ISX004A
- 58. SX 1A Strnr Oypass Viv ISX008A f 59. SX Xtie Viv ISX011A 1 NA
- 60. RHR Ht Xchg 1A Ocmin Wtr S V1v ISXO82 1 NA Gl. Fuel Pool Ht Xchg 1A SX Sply IV ISX01 1 NA f 62. Fuci Pool,Ht Xchg 1A SX Dsch v ISX 2A 1 NA
- 63. Fuel Pool H U SX Sply Viv . ,, 15 16A 1 NA 64 SX-SGTS Charcoal Bed Train A f Deluge Viv ISX073A 1 NA k
- 65. Cnt) Rm HVAC Recirc Unit A Deluge V1 ISXO76A 1 NA
- 66. Cnt1 Rm HVAC H/V Unit A Deluge Viv ISX107A 1 NA g 67. RHR HX C1g Wtr Sply Viv 4' 12-F014A/B 1 1
- 68. RCIC Inbd Vac Okr Viv 1 -F078 NA 1 q' k 69. RCIC Stm Sply Inbd Isol Viv 1ES F063 NA- 1
- 70. Remote Transfer Switch IC61- 501 NA NA
- 71. Remote Transfer Switch IC61-H 2 NA NA
- 72. Remote Transfer Switch IC61-HS5 NA NA .
. 73. Remote Transfer Switch IC61-HS509 NA NA
\ 74. Remote Transfer Swite IC61-HSS10 NA NA /
I 75. Remote Transfer Swi i IC61-HS$11 NA NA i ( 76. Remote Transfer Sw ch IC61-HS527 NA NA l i 77. . Remote Transfer ' itch IC61-HS001 NA NA f
- 78. Remote Transfe Switch 1C61-HS002 NA NA 1
- 79. Remote Trans r Switch IC61-HS003 NA
- 80. Remote Tran er Switch .
IC61-HS004 NA NA J
- 81. Remote Tr sfer Switch IC61-HS005 NA NA
- 02. Remote T ansfer Switch IC61-HS006 NA NA j r( 83. Remote ransfer Switch IC61-HS007 NA NA 84 I Remo Transfer Switch IC61-HS000 NA NA Re. te Transfer Switch IC61-HS009 NA NA (I 85.semote Transfer Switch 86.
87. R ote Transfer Switch IC61-HS010 NA NA ) l IC61-HS011 NA 4A
- 80. Remote Transfer Switch IC61-HS012 NA NA
- 89. Circuit Dreaker 252 ATIAA) IC61-HS565 1 NA CLINTON - UNIT 1 3/4 3-84 Amendment No. 18 e
i (0 84 a gf()CV6, h A1**Id l.S 91-004 gg g,; l'a r.e 30 of 127
~%
p TABLE 3.3.7.4-2 (Continued) REMOTE SHUTDOWN SYSTEM CONTR0_
/
l TA . 40TN406 f
- These controls ot required to be OP s E or tested as operation of the aJ ated valves is precluded in accor e with Illinois Po Kompany's comitment to not utilize the steam densing mode the residual heat removal system.
,,;;y : <
CLINTON - UNIT 1 3/4 3-84a Amendment No.55
r
- -- -_ Att 3 Tha pqe in+enenn H{Q,_ g.;attiment ;;ggaa e -- ' -- h - __
page 33 gg 377 TABLE 4.3.7.4-1 5 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEltt ANCE REQUIREP l CHANNEL CHANNEL INSTRU, q CHECK CAL 10RA ON h 1. SRV $ Temp, supp Pool Temp H , R -
;. ]
- lI 2. $RV $1C T , supp Pool Temp H R f I
H R
- 3. SRV $1G Temp H R I
- 4. Supp Pool Level '
H R 8 RPV Level l l H R
- 6. RPV Press UP DW Temp H R 7.
R l , 8. L0 DW Temp H R
- 9. . 5X 5ttnr Outlet ress H
,l H R
- 10. RCIC Cond 5, rage ink Lvl ,
R
. f 11. RHR F1 H~
Turb Speed M R
- 12. RC 13 RCIC Pump Flow H H R
- 14. RCIC Turbine Flow Control
^
M- - 4
+
CLINTON - UNIT 1 3/4 3-85 \ .
t
.~.
o TABLE 3.3.7.5-1
.C ACCIDENT MONITORING INSTRUMEFTATION
, , MINIMUM APPLICABLE e .
REQUIRED NUMBER CHANNELS OPERATIONAL OF CHA!NELS OPERABLE CONDITIONS ACTION 35 INSTRUMENT
- 1. Reactor Vessel Pressure 2 1 -
1,2,3 80
- 2. Reactor Vessel Water Level 2 1 1,2,3 80
- 3. Suppression Pool Water Level 4 '
2 1,2,3 80
- 4. Suppression Pool Water Te=perature 2/quadrantt 1/quadrantt 1,2,3 80
- 5. Drywell Pressure 2 1 1,2,3 80
- 6. Drywell Ai- Teeperature 2 ~
1 1,2,3 80
- 7. Drf.< ell / Containment Hydrogen and Oxygen Concentration Analyzer and Monitor 2 1 1,2,3 83
- 8. Containment Pressure ## 2/ division 1/ division 1, 2, 3 80 w 9. Containment Tc=perature 2 . 1- 1,2,3 80 1 10. Safety / Relief Valve Acoustic Monitor 1/ valve *** . 1/ valve *** 1,2,3 80 w 11. Contain=ent/Drywell High Range Gross Ga:ma s Radiation Monitors 4** . 2* 1,2,3 81
" 12. HVAC Stack High Range Radioactivity Monitor # 1 1 1,2,3 81
- 13. SGTS Exhaust.High Range Radioactivity Monitor # ~
1 1 1,2,3 81
- 14. Primary ,Contafrusent Isolation Valve Position .
Indication it . 2/vafvefff: 1/valvefff- 1,2,3 82 TABLE NOTATIONS .
- One each for contain=ent and dryvell. .
** Two each for containment and drywell.:
*** Thermocouples in the SRV discharge line can serve as backup to the acoustic tall pipe Eonitors indication ir should one channel of the po'sition indication beco=e inoperable. .
3 # High range noble gas conitors and iodine / particulate sa=pler. ' 8- ## For Divisions I and II only. w&- >
'3 ### Not applicable if valve position indication is unavailable because the valve was deliberately deactivated
- 5Y C provided the valve is in the isolated position and administrative contrals are in place to ensure that th '$?E control roca operators can determine the valve's position, if nee'ded.. Valves closed in accordance with
'& these conditions may be reopened on an inter =lttent basis under administrative controls. U$$5 d i These instruments monitor suppression pool water te=perature when pool water level is below instru=ents' ' o S5E
~
of Specification 3.6.3.1
%~
C "" tt One channel consists of the open lief * <witfh -f~f *he other_ chanWonsists_3_fTthe clesed limit switch-for each automatic isolation valveh _T Q: ?.1. ti f:rti "ffp;t L:]::]:ti:g ift ap."]
"l
Attachment 3 to U 601884a 1.5-91-004 Page 33 of 127 REACTOR COOLANT SYSTEM PRES $URE/ TEMPERATURE L1 HITS SURVE!LLANCE REQUIREMENTS (Continued) , 4.4.6.1.3 The reactor coolant system temperature and pressure shall be deter-
- mined to be to the right of the criticality limit line of Figurn 3.4.6.11 curve within 15 minutes prior to the withdrawal of control rods to bring the reactor to criticality.
4.4.6.1.4 The reactor vessel material specimens shall be rettoved and examined to determine char jes in reactor pressure vesse'. material properties as a _ function oflime and THFtMAt _POWrR atriouf rid by 10 CFR 50, Appendix H,@ Q:#7W;:VTh rh; dyd J- M ? Z C F B The results of these examin5tfons sha'T IFe used Lo adgust the curves of Figure 3.4.6.1-1. 4.4.6.1.5 DELETED. 4.4.6.1.6 The reactor. vessel flange and head flange temperature shall be verified to be > 70'F when vessel head bolting studs are under full tension:
- a. In OPERATIONAL CONDITION 4 when reactor coolant system temperature is:
1.- < 90'F, at -least once per 12 hours.
- 2. 580'F.atleastonceper30 minutes.
- b. Within 30 minutes prior tu and at least once per 30 minutes during tensioning of the reactor vessel head boltin0 studs- except 10 percent of the bolting studs may be fully tensioned at ,> 20*F but < 70"F. ,
CllNTON UNIT 1 3/4 4-23 Amendment No. 51
( ~
, n .
TABLE'4.'4.6.1-1 n C' .
- . . .r; --
I.
; =, N' REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM-WITHDRAVAL SCHEDULE I . >
- o. ^
{- . (A ;- .
=
CAPSULE SEL L WITHDRAWAL TIME -~
' e {f p..M l E NUMdER. ~LOCA OR at.'I.D. (EFPY) l j
m g-1 10
- 1. Capsule 1 3'- 0.67
- /- l (g :
l 2.: . Capsul 177* 0.67 20 - I-()- .
** ~
- l 5 a3 .I t-f 2- n );p _
4 R 9 42
= fl k ,
& \
I
>-.I c
g-. 1 iaA -3
. ft .
y .. 8
&' gggi
~
g e - g ;, g
-- -.n-
~
O w ,6 ? G a
~
gn
- n. w -
- - - - - - - - - - - - - ' - - - - - ' " ' ' - ' ' " " ' ~ " ' '
. _ _ . _ , . .-.-.m- - . . . . . . - . . - - - . . . . . - - - . . . . - - - - - - - - - - -
^"''']
Attachmsnt 3 to U-601884 a .
. . LS-91-004 Page 35 of 127 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT '
PRIMARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION - 3.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained. APPLICABILITY: OPERATIONAL CONDITIONS 1, 2^, and 3. ACTION: , . Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINHENT INTEGRITY vithin 1 hour or be in at least HOT SHUIDOWN within the next 12 hours and in - !Q COLD SHUTDOWN within the following 24 hours. SURVEILLANCE REQUIREMENTS '
- 4 .
4.6.1.1 PRIMARY. CONTAINMENT.INTEGRI1Y shall be demonstrated: -
- a. ,After each closing of.each penetration subject to : Type 8 testing, except
.the primary, containment.iair locks. if opened following: Type.A or 8 test,
.by. leak., rate, testing the seals e with gas:at Pa, S.0 psig,,and verifying that when the measured leakage rate for these seals.;is a'dded.to the leakage rates determined pursuant to Surveillance Requirement 4.6.1.2.d for all other Type B and.c penetrations, the' combined leakagei. rate'is tless-than or equal to 0.60 La. ___
- b. .
M timktD At least once per 31 days by verifying that all,contalriment penetrations ** not capable of being closed by OPERABLE containment automatic isolation' l valves and requir(d to be closed during accident conditions are closed by valves, blind flanges.mr_deactivataQutomatic valves secured in position, except as provided iQgySpecification 3.6.4.
- c. By verifying each primary containment air. lock is in compliance with the requirements of Specification 3.6.1.3.
- d. By verifying the suppression pool is in compliance with _the requirements of Specification 3.6.3.1.
*See Special Test Exception 3.10.1
**Except valves 1HG016 and 1HG017 and valves, blind flanges, and deactivated autpmatic valves which are located inside the primary containment, ' steam tunnel, or drywell, and are locked, scaled or otherwise secured in the closed position. These penetrations shall-be verified closed during each COLO SHUTDOWN except such verification need not be performed more of ten than once per 92 days. '
CLINTON - UNIT 1 3/4 6 Amendment.No. 40' l
Attachment 3 to U-6018842 CONTAINMENT SYSTEMS 3 of 127 PRIMARY CONTAINMENT LEAKAGE , LIMITING CONDITION FOR OPERATION
==
- 3. 6.1. 2 Primary containment leakage ra+,e shall be limited to: ,
- a. An overall integrated leakest rate of less than or equal to:
- 1. La 0 9.8 ps.6f%
ig, by weight of the containment air per 24 hours at Pa,
' b.# A combined leakage rate of less than or cual to 0.60 La, for all penetra-tions and all valves subject to Type B anc C tests when pressurized to Pa, 9.0 ps10.
c.* Less than or equal to 28 scf per hour for any one main steam line through the isolation valves when tested at Pa, 9.0 psig. dd# A combined Inakace_r$ Rit1 taKMs~S E ofYi"551"idi.T'ibse,condary itss thartoteout1_ to 0.0B La (J"Tbypass me (co^nOln*for al when pressur';Wtb Fg.D~psig.
- c. A combined leakage rate of less than or equal to 1 gpa times the total bar Af r
^^r M^ . gent..m isolation valves in hydrostatically tested lines
. O Pa, 9.9 psYwhich penetrate the primary containment, when tssted at APPLICABILITY: OPERATIONAL CONDITIONS 1, 1**, and 3.
ACTION: With:' a. The measured overall integrated primary containment leakage rate exceeding 0.75 La, or
- b. The measured combined leakage rate for all penetrations and all valves subject to Type B and C tests exceeding 0.60 La, or
- c. The measured leakage rate exceeding 28 scf per hour for arty one main steam line through the isolation valves, or
- d. The combined leakage rate for all penetrations secondary containment bypass leakage paths exceedTng 0.0U Uti or
~
~
~
l
- e. The measured combined leakage a fit al13cntainment isolation valves in hydrostatically tested line ^:t410Mhhtch penetrate the primary l containment exceeding 1 gpm . s'tneYtal nux.ber of such valves, restore:
" Exemption to Appendix J of 10 CFR S0. '
**See Special Test Exception 3.10.1.
#The leakage rates of valves 1821-F032A and B are not required to bs included until startup from the third refueling outage in accordance with an approved exemption to Appendix J of 10 CFP.50.
##The leakags rates of valves 1821-F032A and B are not required to be included until startup from the third refueling outage, s
CLINTON - UNIT 1 - 3/4 6-2 Amendment No. 57 l
Att.:hment 3 to U-6018840 LS-91-004 Page 37 of 127 CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION (Continued) 3.6.1.2 ACTION (Continued):
. a. The overall integrated leakage rate (s) to less than or equal to 0.75 La, ,
and
- b. The combined leakage rate for all penetrations and all valves subject to Type B and C tests to less than or equal to 0.60 La, and
- c. The leakage rate to less than 28 scf per hour for any one main steam line through the isolation valves, and .
- d. The combined leakage rate for all penetration En [$h2.5.M-ee secondary containment bypass leakage paths to less tTan or equal To 0.08 La, and
- e. The combined leakage rate _foril nntagent isolation valves in hydro-statically tested lines,@ _TgiER shich penetrate the primary con- l tainment to less than or~ EqTaal To 1 gJmNimes the total number of such valves prior to increasing reactor coolant system temperature above 200'F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fled in Appendix J of 10 CFR 50 using the methods and provisions of ANSI ' H45.4-1972 and BN-TOP-1 and verifying the result by the Mass Point Metho-l dology described in ANSI /ANS H56.8-1981,
- a. Three Type A Overall Integrated Containment Leakage Rate tests chall be conducted at 40110 month intervals during shutdown at Pa, 9.0 psig
, during each 10 year service per'iod. The third test of each set shall be l conducted during the shutdown for the 10 year plant inservice inspection,
- b. If any periodic Type A test fails to meet 0.75 La the test schedule for .
subsequent Type A tests shall be reviewed and approved by the Commission. l If two consecutive Type A tests fail to meet 0.75 La a Type A test shall be performed at least every 18 months until two ::onsecutive Type A tests meet 0.75 La at which time the above test schedule may be resumed.
- c. The accuracy of each Type A test shall be verified by e uppfemental test which:
- 1. Confirms the accuracy of the test by verifying that the difference i between the supplemental data and the Type A test data is within 0.25 La. The formula to be used is : [Lo + Lam - 0.25 La] < Lc < ~
[Lo + Lam + 0.25 La] where Lc = supplemental test result, Lo = superimposed leakage and Lam = measured Type A leakage. CLINTON - UNIT 1 3/4 6-3 -
4 Attachment 3-to U-601884o LS-91-004' C'ONTAINMENT SYSTEMS Page 38 of 127 PRIMARY CONTAINMENT LEAKAGE d SURVEILLANCE RE0UIREMENTS (Continued) 4.6.1.2 (Continued)
- 2. Has duration sufficient to establish accurately the change ir leakage rate between the Type A test and the supplemental test. ,
- 3. Requires, the quantity of- gas injected into the primary containinent or bled from the primary containment during the supplemental test to be between 0.75 La and 1.25 La.
- d. Type B and C tests shall be conducted with gas at Pa, 9.0 ih at inter-vals no greater than-24 months except for tests involving. .
- 1. Air locks, ,
- 2. Main steam line isolation valves,
- 3. < Penetrations using continuous leakage monitoring systems, '
- 4. ontainment is'olation' valves in hydrostatically tested linesh Td k J.g g which penetrate the primary containment, and
- 5. Purge supply",and exhaust isolation v&lves with resilient material seals, '
- e. Air locks shall be tested and demonstrated OPERABLE-per Surveillance
- Requirement 4.6.1.3. g.ggg3{ggg -
- f. Mainsteamline.isolationvalvesshalT5eleaktestedla,tleastonceper 18 monthst
- g. Type B tests fer penetrations employing a continuous _ leakage monitoring system shall be conducted at Pa, 9.0 psig, at every other rea_ctor shutdown
[ for refueling, but in-no case at intervalgreater thanQg _;=M3 years.
- h. All containment' isolation valves 1,n hydrostatically tested line C.Ulwhich penetrate the primary sontainment shall be -leak tested ag 3 east once per 18 months. Q l 1. Purge supply and exhaust isolation valves with resilient mater.ial seals i shall be tested and demonstrated OPERABLE per Surveillance Requir'e-
- ment 4.6.1.8.3. .
l
- j. The provisions of Specification 4.0.2 are not applicable to Specifica-tions 4.6.1.2 a, 4.6.1.2.b, 4.6;1.2.d, and 4.6.1.2.g.
k$ __
**T; . m$u; . -... ..t.
vf it.O sc;i ficeth.- fr :h:: if2-ICO ,1:51 ICb, l 1:01 IOZ,1C1 IZO, 'C1 IZ1,1:12.IOC1,1:12 TCO2, onu 121 T^10 -;;; 3 it.m - fi. w .mfomi.uw wutoum. et em complewa until p. !e. tv e a.
,rtofolio.. - -
3/4 6-4 _ Amendment No. 1 CLINTON - UNIT 1
-e- ,we , * - - , . ,os- ,-,.w- ai--y .-.. i.-emy m--n- g i, yv,.. . w w w - r - -y- v
Attachment 3 j to U-601884 a j LS-91-004 l Page 39 of 127 ) CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AVERAGE AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.6.1.7 Primary containment. average air temperature shall not-exceed 122*F. APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. ACTION: With the primary containment average air temperature greater than 122*F, reduce the average air temperature to within the limit within 8 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following.24 hours. . SURVEILLANCE REQUIREMENTS Th1L primarv containment _ avelane air temperature _ shall be,
; q =,m;;;*3f Ott :,;r5Jt ftl.i fME2cTE :TREOff.;" b ; /
determined to Fe ~within trie Tiiiit'aT Teast once per 24 hourW - - Elevation Azimuth Divisfon -
- a. 778' - 0" 82* I
- b. ' - 0" 105*
- c. 77 - 0" 170* II
- d. 778' - " 190* II
- c. 778' - 0 262* I
- f. 778' - 0" 284* II
- g. 778' - 0" ~
335* I
- h. 778' - 0" 29* II l
l [ e arithmetical average shall consist of at least one reading fro ne loca- [tionperquadrantoftheabovelocations. However, all available ins ments i should be used in determining the arithmetical average. CLINTON - UNIT 1 3/4 6-11
Attachment 3-to U-601884 a
. LS-91'004 -
Page 40 of 127 [. CONTAINMENT SYSTEMS ' DRYWELL AVERAGE AIR TEMPERATURE LIMITING CONDITION FOR OPERATION , 3.6.2.6 Drywell average air temperature shall not exceed 135 F. APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. ACTION: With the drywell average air temperature greater than 135'F, reduce the average air temperature to within the limit within 8 hours or be in at least HOT SHUTDOWN - within the next 12 hours and in COLD SHUTDOWN within the following 24 hours. SURVEILLANCE REQUIREMENTS _416c2.6 The drWall_avaruejir tennerature sha.ll be/3ND .liNM C, ;f'S 5 3t;.'h= tt 20:=2 '=yx: '7 : T1 thin tIFe Timit aT TeiFstinte~per 24 hoursD ~;t;" --1 JgdetermTned to be _,f
/ (
-Instrument Number a.
b. c. TE-VP033A VP0338 Elevation 729'-0"# 775'-0" 741'-0" Azimutb
.160*
45' l I l d. e. ITE-ITE-VPO., ITE-VP033E 3C 772'-0" 802'-0"- 130' 0' ()
- f. ITE-VP033F 746'-0" 307*- {O
- g. ITE-VP033G 794'-0" O' I
- h. ITE-VP034A 732'-0"# 225 .
- 1. ITE-VP0348 775'-0" 230*
- j. ITE-VP034C 741' 220*
- k. ITE-VP0340 -0" 235*-
- 1. ITE-VP034E- 02'-0" 180*
- m. -ITE-VP034F '-0"" 135' I n. ITE-VP034G 794 .180*
4-i I
. l l .
I). * .- The ari etical average shall consist of at least one reading from ch of: f the ve listed elevations. -However, all available instruments shoul e l in determining the arithmetical average. , I The instruments at a. and'h. are considered to be at the same elevatio 7 -- t CLINTON
- UNIT 1- 3/4 6-20
-g '
. , , , , . , . ..i
Atttchhitht' $ - to'U-601884a-
'LS-91-004
. CONTAINMENT _SYST_ EMS 3/4.6.'4 NT ISOLATION VALVES LIMITING CONDITION FOR'0PERATION
^
^3 g geg pdmg. r - - ,- - , , , , , , = - -
- 3.6.4I-The(containment $ solation valve; =d tr.; 'n;trx; ,tc.tha ',in _xu h229_ f h:2 ,2 h _ U{ U 1,0 ( ,shall be 0PERABLE.7t t{ S;'-th- t'n:
q . p.-- . 3 p y _. _. . . ., . . . - , , , , n . -- APPLICABILITY: ". 3,5,, l a Mk 3. 5.M ' ' an&3 ged w cenwnenent istaiton vaWes'And ACTION: nrieNAL oveRat coubmens MAL copbmous i \,'L.3 and ww Gr se Wes %wt &) ate, seconder,3 conio\nd opcdIr b E Y b7T m-n - .n Mand s'**o hn.V,ahe5 M bi** ** E**WE - n== -
- a. With one ur more or tne contammem, noiation vTlvesC.;cT5105 0.1.'3 inoperable, maintain at least one isolation valve OPERABLE in eacTi affecte~d penetration that is open an thin 4 hours either:
6 mar
- 1. Restore the inoperable va ve(s) to OPERABLE status, or
- 2. Isolate each affected penetration by use of at least one deactivated automatic valve secured in the isolated position,*t or
- 3. Isolate each affected penetration by use of at least one closed manual valve or blind flange.*t The provisions -of Specification 3.0.4 are not applicable provided the affected penetration is isolated in accordance with ACTION a.2 or a.3 above, and provided the associated system, if applicable, is declared inoperable or appropriate ACTION statements for that system are performed.
Otherwise be in at least HOT SHUTDOWN within-the next 12 hours and in COLD SHUTDOWN within the following 24 hours. Otherwise, in OPERATIONAL-CONDITION **,-suspend all operations involving CORE ALTERATIONS, handling irradiated fuel in the secondary' containment, or with a potential .- for draining the reactor vessel. The provisions of Specification 3.0.3~are not applicable.
" Isolation valves closed to satisfy these. requirements may be reopened on an intermittent basis:under administrative controls. i
""When handling irradiated. fuel in the secondary containment and during CORE M TritATinNS and onerations with a notential fo_r draiaint the twtne._unn al _
IM(as cor*Tel Ad G16drafNippl\'.cibigh n'ng @nts1hd femotedje5 fjec%ked;on 3.%I0.1 TcontammTnt iso 1auun yaives can naverana nuncaons Tn InaT.Tney TirTviae # 3?dh. - both containment isolation and Emergency Core Cooling functions. -Any inoperable dual function valve could degrade the_valveTO other function _
"CE 55 iPJ 5 h5 if EntItiI.: f:[T55 [E. " . LocEed of 5eded C\eSed vatve{ma be opened on an inittm'.t+ent . htM under adm'nhmg C_ontcol, CLINTON - UNIT 1 3/4 6-29 AMENDMENT NO. 2
.- - . . - - - . . -- . - . . - . - . .. . . . --. - - . - - . . _ . = - -_
. Attachment 3 '
to U-601884 a
- LS-91-004 av f 127 CONTAINMENT SYSTEM 5 timW MENT ISOLATION VALVES LIMITING CONDITION'FOR OPERATION (Continued) 3.6.4 ACTION (Continued):
@._ _ _ , . _ga% cc>nWinment i$ebMen)
~
- b. gWitor more_of_ he instrumentation line excess flos checkkvalves L ;Mg. j - I:t Tf 3. 5._ inoperable, operation may continue provided that
~w Tthin 4 hours-either:
- 1. The inoperable valve is returned to OPERABLE status, or
- 2. The instrument line is isolated and the associated instrument is
_ declared _ inoperable. _ _ _ _ _ _ _ _ - - 6he provisiona eO5cecif:ca+:eo 1.o A are ned @pikabh 0~therwise, be in atleast HOT SRUTDOWN+within the next 12 hours and in
~
COLD SHUTDOWN within the following 24, hours. v SURVEILLANCE REQUIREMENTS WasnEREC _- _ 4.6.4.1@Eachlisolation valven.E jr_T:Mq 2.5.'-Vshall be demonstrated l OPERABLE prior to returning the' dive'to service after ma'intenance, repair, or replacement work is performed on the valve or its associated actuator, control, or power circuit by cycling the valve _through at least one complete cycle of full travel and verifying the@M'@ isolation time. . l Cnsm ioW 4.6.4.2 -Each automaticlisolation valveCi6. ir.f;EU :.U3]sha11 be demon - strated OPERABLE during COLD SHUTDOWN or REFUEL.ING at least once per 18 months plation valve __ by verifying that on an isolation test signal each automaticg4""WaW'"'"*"U actuates to its isolation position. _ Gh,nacq conknrnent i'aiatfeib -
~
M4.3 The isolation time of each post operiTed or automaticlvalveGj@4JD ~ H 3.s.t-Dshall be determined to be within its limit when tested pui'suant kJp'to Specification 4.0.5. . - ______
$6cc.nwCnicini F4 6o3
~
4.6<4_.4_ _ Ea_ch instrumentation Jine excess flow checMvalveGh0.3D - CAji}.S.f "shall be demonstrated OPERABLE at least once per 18~ months by _ veri ~fying that the valve actuates within the dif_ferential pressure rangg UNNOM (egb' red) j l 4 CLINTON - UNIT 1 3/4 6-30 _ _ , ,, .~ . . . . _ , _ __
.3 ;j
~
; m TABLE 3.6.4-1 [
l n. CONTAINMENT ISOLATION VALVES .
) '{
c ' HAXIMUM CONDARY-hk CONTAlfEENT - TEST APPLICABLE ISOLATI g-OPERATIONAL TIME ISOLATION (psig)* BYPASSPATH.P PENETRATION _ onds) (Yes/No) VALVE CONDITIONS. e NUMBER SIGt!Att
-5 NUMBER-a
~ - 1. Automa*'c Isolation V e s_ -
1,2 No 9.0 i g-Hain ~ceam Line C 5 3-5 '
- 1) 'C,D,E F,G,H,J,U,R,X 1821-F022C C.D.E.F,G,H,J,U,R, 3-5 1821-F028C C,0,E,F,G,H,J,U ,X 14 -
1821-F067C , 1,2,3 No 9.0 6 . 3-5
- 2) "Hain Steam Line A C,D,E.P ,H,J,U,R,X 1821-F022A - C,D . ,G,H,J,U,R,X 3-5' 1821-F028A . ,E F,G,H.J,U,R,X- 14
~ g IB21-F067A 1,2,3 - No 9. 0 ' , 7: .
,J,U,R,X 3-5 i' 3) 'Hain Steam Line D C,D,E,F, s- 1821-F0220 C.D.E F G, , U,R,X 3 .5
.-1821-F028D - C.D E.F.G,H,J, R,X 14 1821-F0670-2,3 -No 9.0 ~
8 3-5
- 4) Hain Steam Line B C,D,E,F,G,H J,U,R,X -
1821-F0228 ' C,0,E,F.G,H,J,U,R,X' 3 - 1821-F0288 C,D,E,F,G,H J,U,R,X . 14 IB?1-F067B N-ne A - 9 1,2,3' No 9.0 . 5)- Feedwater/RHP A,5,T,X,R
- 9.0 1E12-F053A _1,2,3_,#- NA Yes 8,L,R .
.1821-F0 - g N
F ater/RHR Line B 10. 1,2,3 65 9.0 m e. ,, > . A.S T,X,R
. 6) .
E12-F053B B,L,R ~ 1,2,3,#;. NA - Yes 9.0 y { * {.
'.1821-F0328 k8 g e aw
~
~b N '
- a. - . . _ , .
~
in / . TABLE 3.6.4-1 (Continued) - CONTAINMENT ISOLATION VALVES
'f y<O p ! (T) j ,
O MAXIMUM SECONDAi h APPLICABLE ISOLATION CONTA AEtiT TEST l ~ ~ j , c- VALVE PENETRATION ISOLATION OPERATIONAL: TIME BY a5 PATH'PRESSUREIhj (Seconds) Yes/No) (psig)* { y NUMBER NUMBER SIGNAtt CONDITIONS _ 1 . i d Automatic Isolation Valves Continued) RilR Shetdown Cooling 14
- 1,2,3 No 9.0 $
- 7) At5,T,X,R 54 1E12-F008
.1E12-F009- A, S, T,.X,.R . 54 -
RHR A To Fuel Pool Cooling 15 1 ,3- No 9.0 8)_ 95 1E12-F037A. A,S,T,L R RilR B To Fuel Pool Cooling 16 1,2,3 No 9.0
- 9) , T. L, 95' w IE12-F037B , - -
) 18 1, 2,.3 No 9.9 I m 10) . RHR A/LPCS Test Line 117 J. IE12-F024A L.
" 33 1E12-F011A 90 1E21-F012 ,U 19 2, 3 No '9.9
- 11) RHR C Test Line. LU 123 .
IE12-F021 . 0 . 1, 2, 3 No 9.9 l 12) RHR B Test Line L, U 117 IE12-F0248.. IE12-F0118 . L, U
-28 .
a 1, 2, 3 . No 99
- 13) RCIC Suction V,S,T,'X,Btt,Rtt, 48
! 1E51-F031
- E, F
- i. m r* * >
manual isolation switch (R) isolates outboard steam supply line isolation valve (F064) and the RC umpk$hk'f ttA sin on from suppression pool valve (F031) only following a manual or automatic Reactor Vessel Water Level 2( , RCIS y ag. ' suc tem initiation. og og
~ .E*sE i -
. Ow.
l
~;
i
.h
.mI I
TABLE 3.6.4-1 (Continued) , [ b C0!4TAINMENT ISOLATION VALVES i I a m o.
,p -. j
~ MAXIMUM S NDARY I t
[ APPLICABLE ISOLATI0ft ONTAINMENT TEST
$ VALVE PENETRATION ISOLATIO!! OPERATIONAL TIME BYPASS PATH .PRESSURS (psia)*
Q( 1
+
NUMBER NUMBER
~
SIGNAlt CONDITIONS (Sec us)' (YES/NO) p,, Automatic Isolation Valves (Con " ued) g
- 14) HPCS Test Line 1, 2,, 3 No 9.9 1E22-F023 B, L , 68
- 15) Supp. Pool Cleanup Suction - 34 2, 3,# Yes 9. 9 ISF004. 8, L,- R 84
- 16) RCIC 41 g 1 , 2 , 3' No 9.0
,g 1E51-F077 L, 21 7 17) RHR Head Spray 42 1,2,3 No. 9. 0 y 1E12-F023 A, T, X, 39
- 18) RCIC Steam Supply... 43 .
1,2,3 no 9,o
.1E51-F063 V, 5, T, E, F.. X 41 1E51-F064 V, S, T, Rtt, Btt, E, 41 F, X IE51-F076 V,5,T,E,F,X 8
- 19) RCIC Turb Vac Bkr Line 44 1,2,3 No 9.0 g 1E51-F078 L, V,gg
- 20) Main Steam Drain Line- 45 1,2,3,#CI) Yes 9.0 g' '1821-F016 ..C, D, E, G, H. J, 26.
r- U, X, F, R
- g: 1821-F019 C,D,E,G,H,J, 26 ,e,,>.
- .0, X, F. R g ? o ;;
$ ?
g S Aa;if itA sing manual isolation switch (R) isolates outboard steam supply line isolation ' valve (F064) and the RCIC pump 3, S h k suc ' n from suppression pool valve (F031) only following a manual or automatic Reactor Vessel Water Level 2(B) RCII 7m .. in lation. . 4 da
~
.m
. i I '9TJ3O~)6I (b
. TABLE 3.6.4-1 (Continued) 1 LA &5O -3' n CONTAINMENT ISOLATION VALVES -
@ c. ,
C z O l $ MAXIMUM SECONDARY APPLICABLE ISOLATION CONTA " TNT TEST c VALVE . PENETRATION ISOLATION OPERATIONAL TIME BYP' s PATH PRESSURE = NUMBER NUMBER SIGNAlt CONDITIONS (Seconds) rES/NG) (psic)* --i
- Automatic Isolation Va s (Continued)
- 21) Comp. Cooling Water S ly 46 1, 2, 3,5 yes 9.0 1CC049 B, L R 66 1CC050 B, L. R 45 1CC127 B, L, R 61
- 22) Comp'. Cooling Water Return 47 , 2, 3,# Yes 9.0~
'ICC053 B,L,R 45 ICC054 B, L. R 89 R 1CC060 B, L R 61 s
T 23) Breathing Air 49 . 1, 2, 3,# Yes 9.0 w ORA 026 B, , NA ^ ORA 027 , L, R NA
- 24) Make-up Condensate 50 -
1, 2, 3.# Yes 9.0 GMC009 B,L,R 35 OMC010 B, L. R 35
- 25) Fuel Pool Cool / Cleanup -
Supply 52 1, 2, No 9. 0 IFC036 B, L, R 59 1FC037 B, L, R c9
- 26) Fuel Pool. Cool /C' nup Retur6 53 1,2,3 No 9.0 IFC007 B, L, R 66 ,,,,
IFC008 . . B, L, R 66 =mwg aeea
- 27) F Protection 56 -
1, 2, 3,# Yes 9g)[ h h B, L, R B7 1FP051 FP052 B, L R 66 x%, g gng .
- aw M
TABLE 3.6.4-1 (Continued) -
- &v o
e
-7 g ;
n ! i CONTAINMENT ISOLATION VALVES w E %
@ &\l
- 1 1'
, MAXIMUM SECONDARY %
APPLICABLE c- VALVE PENETRATION ISOLATION CONTAI' . NT TEST D 4 }; ISOLATION OPERATIONAL TIME BYP 5_, NUMBER HUMBER SIGNAlt PATH PRESSURE. ! CONDITIONS (Seconds) ' ES/NO) (psic)*-
" Automatic Isolation Valve Continued)
- 28) Instrument Air Supply .
57 1, 2, 3,# 11A005- Yes 9,0
'U '20 IIA 006 U 4
~ 20 -t
- 29) Instrument Air Bottles SB , 3,#.
.i 11A0128 Yes 9. 0 L, B, R
' 19 i
i 30) Service Air Supply 59 1, 2, 3,# i R ISA030 Yes 9. 0 t 1SA029
.R~ 16
.m B, ,
16 t h.31) RVCU Suction Line 60 1, 2, S**
.IG33-F001 B , F , N , 1, , E, No 9.0 ,
20 X, R 1 IG33-F004 B, F, N, 1, 2, E, 20 X, R l 32) RWCU Return to Filter 61 1, 2, No 9. 0 1G33-F053 8, F X,R,N,1,2,E, 21 I 1G33-F054 B,.F, N, 1, 2. E, 2 .t X, R
- 33) Hydrogen Reco ner Supply 62 ,
1, 2, 3,# i 1HG008.. 8, . L, R Yes 9.0 -t 117
. ,,,y .
n, m o e
- 34) RWC o RHR/FW 64- 1,2,3 i
-F040 B,F,N,1,2,E, No 9.0 % a c: " - '
X, R 21 .# M 9 i 1G33-f039 8,F,N,1,2,E'
*gog *
, 21 2,
- g g i X, R n
p : + 1 . 4 . 4 4 + , .cw...
i y:7 % TABLE 3.6.4-1 (Continued) a CONTAItiMENT ISOLATION VALVES sb' i C Ei I '.E. MAXIMUM SEC G ARY
. APPLICABLE ISOLATION " oAINMENT TEST e OPERATIONAL TIME oYPASS: PATH' PRESSURE PENETRATION ISOLATION (psig)*
5* VALVE HUMBER SIGNAtt CONDITIONS (Seco (YES/NO) NUMBER
'e Automatic Isolation Valves "ontinued) 3. :
- - .1, 2, 3 Yes 9.0 ,
65 '
.35) RWCU Trarisfer To Radwaste B L. R 2 1WX019 8. L, R 2 1WX020 1, 2, 3,# NA Yes 9,0
- 36) Process Sampling 68 .
B, L, R
-1PS016 B, L, R ta 1PS017 B, L R TJ 1P5022- L, R m 195023 8,
<, 1PS034 B ,
-* 1P5035- , ~
, L, R ,
. 1P5055' B, L, R IP5056 B, L, R 1P5069 B, L. R :
1P5070 3 n 1 ,3- No 9.0
- 37) DW/ Cont.-Equip. Drain B, L. R 16
. IRE 021 8, L, R 16 1RE022.
1,2,3 No- 9,o - 70' ._
-1
'38) DW/ Cont. Floor Drain BE;L,- R-
- F 1RF021- ** 5,
- B, L, R 16
-3
- -IRF022 es 9,0
'& 39) Hydrogen ecombiner' Supply. 71 1, 2, 3,#
117 _ lf g o,, g
- s" ' '
.B; L, R t, , n 1HG00 . - . .
g 1, 2,'3,# .yes o %?EL
~)
- 40) drogen Recombiner. Return 72 B, L, R - 117 mg$[
6' 1HG004 ?, * : a L ta la8 Li [
~.
I h h bl
&@ T- m TA8LE 3.6.4-1 (Continued) I
^
- l CONTAINMENT _
ISOLATION VALVES n C "i MAXIMUM SECONDARY
@ APPLICA8LE ISOLATION CONTAIF. NT TEST OPERATIONAL TIME 8YP PATH PRESSURI PENETRATION ISOLATION (psig)*
c- VALVE SIGNAlf CONDITIONS (Seconds) iES/NO)
= NUMBER NUMBER " Automatic Isolation Valves ntinued) 1,2,3 No 9.0 !
- 41) SX To Recir. Pump 78 ;
L, U 35 ICC074 35 ( ICC073 L, U 1 , 3,# Yes 9.0
- 42) Supp. Pool Cleanup Return 79 8.L,R 68 ISF001
- 8, L, R 68 f ISF002 .
1, 2, 3,# Yes 9.0 81 R
- 43) Fire Protection 8. L, 48 IFP050 8, 48 S' 1FP092
~ 1, 2, 3,# Yes 9.0 82
- 44) Fire Protection 8 L. R 68 -
l 1FP053 8, L R 68 1FP054 9.0 1, 3# Yes
- 45) Cycle Condensate 8 44 1CY017
- 8. L. R 44 8, L. R 1CY016 1, 2, 3,# Yes 9.0 86
- 46) RwCU Letdown 8, F, N, 1, 2, E, 1G33-F028 X, R 8,F,N,1,2,E, 24 1G33-F034, j G G j.
X, R
. e e e n.
1,2,3 No 9M E
- 47) SX F m Recir. Pump 88 LU 35- 28SR 71 L, U 35 o"yE CC072 _
nw
~
-.-...ha.
~
. (I JfR 2.% I '
TABLE 3.6.4-1 (Continued)
' g & k> %
S n CONTAINMENT ISOLATION VALVES t C
- 5 MAX} M SECON-4
- g , APPLICABLE ISOLATION CD INMENT TEST ;
PENETRATION ISOLATION OPERATIONAL TIAE PASS PATH PRESSUR VALVE (YES/NO) (psig)*_ t [ z- NUMBER SIGNAtt CONDITTONS_ (Second
- j. typ[R
-w u Automatic Isolation Valve (Eontjnueo) ,
t l','2, 3,# Yes 9. 0 - ~
- 48)- Copt3 nmenti HVAC Supply '101 j 8.L,M.Z,5,R .4 4
lyEQO1A - B, L, M. Z, 5, R 4 i Ivsp018. 2(g) . 16 : P ,
- '1VROQ2A,B(,)
3I9) 4,I9) ,# t ! 1, 2, 3,# Yes 9. 0 -
- 49) 'Coptainment'HVAC Exhaust 102 .
B L, .M , 5, ' R 10 1$tQ004A ~L , Z, 5, R 10 , s l t* IVQO04B I') P if9)'2I9) , 16 IVg006A,B ' 3(9)'4(9) ,'# - ,
- to 1, 2, 3,#. Yes 9.0 !
i 50) Plgnt Chilled Water Supply 103- 44 L, U ! IWQ001A 44 L, ..U j IW0001B 1, , 3,# Yes 9.0 - i i 104 i 51) Plant Chilled Water Return L, U 4A
.lyQ0p2A L, U 44 lyg002B
- 1, 2, 3,# Yes- 9.0-IVAC 106 i- 52) Containment Bld B, L, M,.Z, 5, R .
) E ly'Rp07B B, L. M, I, 5. R 6 { 9 ly,Rp07A 1,2,3 No -B eo - > ' E 53) Oy 11ediWater Supply 107 L, U 74 5? [yy$ < 0048 74 L, U . ooos-l 5, 1VP0058 . 1,2,3 No . ,9 % [ , l. j-
"54) DW Chilled Water Return IVP0148-108.
' L, U , 74 74 -
C
; **' g L. U u
T 1158 '-8
'g
. s k M w e e w ee--'----.-muJ_-.__
' TABLE 3.6.4-1 (Cone.inued)
Q. $ - r .C ' CONTAINMENT ISOLATION VALVES , 5
@ MAXIMUM . SECONDARY 4
.. APPLICABLE ISOLATION' CONTAINMENT .EST. .
c- . VA PENETRATION ISOLATION OPERATIONAL- TIME SYPASS P * . ri . PRESSURE 3w NUMB NUMBER SIGNAlt CONDITIONS (Seconds) . (YES/ a) :(psig)*- ' H Automatic Isolat Valves (Continued) +
- 55) DW Chilled Water ly 109 1,2,3 No 9. 0 IVP004A- L. U 74 ,
.-1VP005A : L, U j f -56). DW Chilled Water Return 110 1, 2, 3 no 9. 0 [
-IVP014A. -
LU 74 ! 1VP015A ' . . L, U 74
.u
' -} 57)~ Cont. B1dg. HVAC 113- 1, 2, 3,# Yes 9.0 .
. IVR006A. B. L, M. Z, 5 6 .
J, 1VR006B L.:M. Z, .R 6 !
=
58): Cont. Monit. 153- - 1, 2, , 3 NA No 9.0. " ICM022." 8, ,R , , .ICM023 ' L, R ' i ICM025 6 L, R ' -
'g
'1CM026 - 'B. L. R !
59). Hydrogen Recombiner Supply 166 . 1, 3,# yes+ ;g,o ., B, L, R - 1HG005- 117 , l' * , 60) Containment HVAC 169 . 1, 2, 3 - 'fA No 9.0
)
;g 1VR035..
IVR036: B, L, M, 2, 5. R B,'.L, M, Z, 5, R' i g- IVR040 8,L.M,Z,S.R , g- IVR041 B, L, M. I, 5, R A " . . EGGk i: y '61) ' Cont..Monit zi73 1, 2,.3 NA No 9.0E E c: E I w 7 & g. i 4
.1CM048 B,L,R
~8SX g' O 1CM047' B, .L. R. .
-1 B,'t, R P, P 3 ?,R
..F 012 i B, L, R - 7w1 w 1 e 1 l r
f I
&& ' l 9
TABLE 3.6l4-1 (Cone.inued) @D $ $ CONTAINMENT ISOLATION VALVES
'b 3 MAXIMUM SEC saRY- .
.- @ JTAINMENT TEST :
APPLICABLE ISOLATION OPERATIONAL TIME BYPASS PATH _ PRESSURE--
- c. PENETRATION' ISOLATION (Sa u ds) (YES/NO) '(psig)*~
5' d VALVE
- NUMBER.
NUMBER .SIGNAlt . CONDITIONS
.g -
ed)
. Automatic ' Isolation Valves -(Cont Yes 9.0 1 , 3,#
19
- 62) Instrume.t' Air' Bottles . L . B ,- P.
11A0138' 9.0' 1,.2,-3,# 'NA. Yes 210
- 63) Process Sampling ,LR
-1P5038 . -
'1PS037 8 .,
w IPSO 48 , L, y -1PSO47 B, L, R . l ~. .m IP5004 8, L, R i
'1 IPS005 .
8 L, R-o 1PS010 B,'t, R ., IPS009 B, L, R -- IPS031 B, L, R - 1PS032 6 8-g- yggy 8
" 2 4 c ".
l- .w'T4,E I.' o - h b k. g a
~ _ ,s 3 "
i i'
M
. 9 . .;,- ,
Q' E TABLE 3.6.4-1 (Continued) -1 , f2 CONTAINMENT ISOLATION VALVES .
- a. y -
r MAXIMUM SECONDARY
- APPLICABLE ISO ON ' CONTAINMENT TEST-E y
. VALVE NUMBER PENETRATION NUMBER-ISOLATION SIGNAlt QPERATIONAL.
CONDITION E:- (Seconds) BYPASS PATH PRESSURE (YES/NO) (psig)*
- 2. Manual Isolation Valves ;
- 1) RHR/LPCI A Injection NA 1, 2, 3(a) NA No 9.0-15 i IE12-F044A -
- 2) RHR/LPCI B' Injection A -1, 2, 3(a) NA No 9.0 1E12-F044B 16 -
, 3) Containment Monitoring 152' HA 1,2,3 NA No .9.0-m ICH080A
} ICH0808- -
4,
'1CM080C-i ICM081A
! O ICM0818 l ICH081C . 4
-t t
I I , I e 8 9
% ac;-
i 35$l g_gg ,
- - Ow.
. S 4
+- -
p . tre 3 -e :
~
-- TABLE 3.6.4-1 (Continued) .
di . .
^
f3 CONTAINMENT ISOLATION VALVES F l = MAXIMUM SEC0F otY
- APPLICABLE ISOLATION INMENT -TEST
~ '
VALVE PENETRATION ISOLATI0ft OPERATIONAL TIME PASS PATH PRESSURE" NUMBER NUMBER SIGNAtt CONDITIONS (Secon (YES/NO) (psig)*- :
- 3. Test' Connections V *s, and Drains (a) ,
'1) Main Steam Line C 5 NA 1,2,3 NA No 9. 0 - l 4
1821-F025C ; i 1E32-F327C' - 1E32-F330A ! j 2) -Main Steam-Line'A -6 NA 1,2,3 ~ NA No 9.0 i i R
- 1821-F025A- ^
1E32-F327A
- T' 1E32-F329A 4 0 . .
] 3): Main Steam Line 0- 7 a 1, 2, 3 NA No 9. 0 l 1821-F0250~ 1E32-F3270 . i 1E32-F330C .; 4)- Main Steam Line B NA 1,2,3 NA No 9.0 1821-f0258 ! F 1E32-F3278 ' . @ 1E32-F329C i i . l s" 5) Feedwater/RHR Lin ' 9 NA . NA 9.0 ~. 1B21-F063A- 1, 2, 3,# Yes 1 i IB21-F030A' , 1, 2, 3 No. 1E12-F0' 1, 2, 3 No j ygg3 i
- 1E12- 49A' -
1,2,3 No EacE
% g][ ,
O dm3-m C0 et , i - ~ .,u. , a
- N I
I ~> TABLE 3.6.4-1 (Continued) - Q$c @ { CONTAINMENT ISOLATION VALVES ' 5 O
' MAXIMUM SECONDARY APPLICABLE ISOLATION CONTAINW a TEST E VALVE PENETRATION ISOLATION OPERATIONAL TIME Z NUMBER BYPAS" ATH PRESSURE fiUMBER SIGNAlt CONDITIONS (Seconds) (v JN3) (psic)*
Test Connections, Vents, an rains ( ) (Continued)
- 6) Feedwater/RHR Line B 10 NA 1821-F0638 9.0 1, 2, 3,# Yes 1821-F0308 1,2,3 No 1E12-F0588 1,2,3 No 1E12-F3498 1, 2 No 1G33-F057 1 ,3 No R
^
- 7) RHR A Suction 11 1,2,3 NA No 9.9' 1E12-F334A T 1E12-F335A 0 *
- 8) RHR 8 Suction 12 NA 1,2,3 NA No 9.9 1E12-F334B -
IE12-F3358 - *
- 9) RHR C Suction 13 NA 1, 3 NA No 9.9 IE12-F334C 1E12-F335C
- 10) RHR Shutdown Cooling 14 NA 1,2,3 NA No 9.0 1E12-F001 N -
8 11) RHR/LPCI A Injection 15 NA 1,2,3 NA No 9.0
& 1E12-F107A ~
@ 1E12-F331A IE12-F329A & ;y g g R
- 12) RHR/LP
= 1El 07B Injection 16 NA 1,2,3 NA No 9.02 ,4y 4eg.;
- wooa 1 -F331B o35E E12-F329B E[
I' { h I. l! C n TABLE 3.6.4-1 (Continued) CONTAINMENT ISOLATION VALVES kg . { "
. t a-i 7 -
*~
e HAkIL$f IcCONDARY ' ' 5 . VALVE APPLICABLE ISOLATI CONTAINMENT TEST-PENETRATION ISOLATION OPERATIONAL TIME ! NUMBER NUMBER BYPASS PATH PRESSURE-
] SIGNAtt CONDITIONS _(S nds) (YES/NO) .g Q Test connections,' Vents and Dra s(a) (Continued)
- 13) RHR/LPCI C InDetion 7 NA 1, 2, NA- No 1E12-F056C 9.0 1E12-F351 --
1E12-F4568 . l t
- 14) RHR A Test Line 18 A 1,2,3 u IE12-F365A- NA No 9.0 1 IE12-F366A ^
.& IE21-F346 IE21-F347 N' .1E12-F414 1E12-F415 4 IE12-F418. . ;
1E12-F419 . 1E12-F420 1E12-F421 i
- 15) 'RHR C Test Line 19 NA 1,2,3 NA 1E12-F353 No 9.0 1E12-F354' '
IE12-F428 , I-o 1E12-F429 S' 20' NA ' 1, 2, 3 . E' 16) RNR 1E12-F365B B Test Li HA No 9'. 0 . E 1E12-F36 2CEF . F 1E12-F 6 14eE i 1E 427 . v, ;" a F; t
*824 .
y - R*gi t g .9 ,
~ ,
, p
f % 3Q LA I 3 .\ D $1D1 TABLE 3.b.4-1 (Continued) . ; l2 CONTAINMENT ISOLATION VALVES E l MAXIMUM SECONDARY APPLICABLE ISOLATION CONTAINMEP" TEST E VALVE PENETRATION ISOLATION OPERATIONAL TIME BYPASS H PRESSURE Q NUMBER . NUMBER SIGNAtt CONDITIONS (Seconds) (Y , 40) (psig)* Test Connections, Vents an ains(a) (Continued) 9.0
- 17) RHR HX 24 NA 1, 2, 3 No 1E12-F432A 1E12-F433A
- 18) RHR HX 26 NA '1, 2, NA No 9.0 1E12-F4328 1E12-F433B R
- 19) RCIC Pump Suction 28 NA 1,2,3 NA No 9.9
? IE51-F336 e IE51-F337
- 20) RCIC Suction Release ..
Discharge . 31 1 1,2,3 NA No 9.9 IE12-F436 1E12-F437
- 21) LPCS Pump Suction 32 NA 1,2,3 NA No 9.9 IE21-F331 IE21-F344 F 22) HPCS Test To Supp. Pool 33 NA 1, 2, 3 NA No 9.9
@ 1E22-F376
& ;f C, E R
@ 23) Supp. Pool Clear Pump
" Suction 34 NA 1, 2, 3 NA No 9.9 % 4 e ;
E ISF034 m ';" a 9 L~ "8S%
*??
- lw
1 fw; 8 TABLE 3.6.4-1 (Continued) s <- i t C CONTAINMENT ISOLATION VALVES
. @ )i '
5 E ' MAXIMUM SEC0F.,dY e APPLICABLE ISOLATION C0" INMENT TEST 5 VALVE PENETRATION ISOLATION OPERATIONAL TIHE NUMBER : PASS ?ATH PRESSURE s NUMBER -SIGNAtt CONDITIONS _(Second (psig)* (YES/NO) Test Connections, Vents and Dr ns(a) (Continued)
- 24) HPCS Pump Discharge 35' NA 1, 2, 3 IE22-F021
, UA No 9.0 1E22-F3668
- 25) LPCS Pump' Discharge. 35 NA , 2, 3 1E21-F013 NA No 9.0 w IE21-F358 m
1E21-F356A i* 26) RCIC 41 NA 1, 2, 3 NA No 9.0 IE51-F041
- 27) Head Spray 42 .iA 1,2,3 NA. No
.1E51-F034- 9. 0 IE51-F391 1E12-F061-1E51-F367
- 28) RCIC Turb Steara Supply ,43 NA 1,2,3
'1E51-F399 - -
NA No 9.0 1E51-F072 k IE51-F401
. 29) RCIC.Turb - Vacuu., reaker 44 NA ~ .1, 2, 3 NA No 9. 0
- g. 1E51-F080 1E51-F082
'Y 1E51-F3 2C~R IE51- 6 "a 4 c " 1 -F083 v jgy1 t' g gg.
- g-
- ,m
^
~
_.i:.i...- ' " " ' ^ ' ' ' ' ' ' - - - '" " ' ' ' " ' w
If TABLE 3.6.4-1 (Continued)- j g>' d9
~4 . 1'
- Qw CONTAINMENT ISOLATION VALVES Y
8 Ei o MAXIMUM SECONDARY
'7 . APPLICABLE' ISOLATION CONTAINMEt iEST 1
'E VALVE PENETRATION ISOLATION OPERATIONAL TIME. BYPASS
,0) ti PRESSURE (psig)^
Q NUMBER NUMBER SIGNAtt CONDITIONS (Seconds) (Y_ ,
. Test Connections, Vents and Dr
- s(a) (Continued) ;
45 NA 1,2,3 ' No' 9.0
- 30) Main Steam Drain Line
. 1821-F017- . 31). CCW Supply 46 NA 1, 2, NA 9.0 No 1CC164-ICC266' , 2, 3,,g Yes-
- 47. NA 1,2,3 NA No 9.'O g 32) CCW Return
# 1CC165 cn S 33) Makeup Condensate 50 NA 1, 2, 3 NA- No 9.0 1MC011 -
- 34) Fuel Pool Cool / Cleanup. 9.0 i ~SupplyL 52 'NA 1, 3 NA No-IFC092
- 35) Fuel Pool Cool / Cleanup Return 53 NA' .1, 2, 3 NA 'No 9. 0
!- 1FC093 g es 56 NA 1,2,3 NA No '9.0 E 36) Fire Protectio
~j IFP127 c+
NA 1,2,3 NA No 9.0
- - = 37) Instr ent' Air 57 ;f M g b i F 1 9 2ac;
' Og v=a' h -;
' g w
- j.
- l
- . . . __. -=.
v g: 9 tab'.E 3.6.4-1 (Continued) . Q hW: .Si
. . . l h'
CONTAINMENT ISOLATION VALVES : 5 o [
' ~
l 7 .. MAXIMUM SECONDAR '(
.c APPLICABLE ISOLATION CONTA ".ENT TEST' !
- '$ VALVE PENETRATION ISOLATION OPERATIONAL TIME BYP' S PATH . PRESSURE f
{ H NUMBER' . NUMBER SIGNAM _ CONDITIONS (Seconds) .ES/NO)- (psig)^ -l
^
Test. Connections, Ven and Orains(a) (Continued} , 38) Service Air Line 59 NA 1,2,3 NA No 9.0-
~
. ISA046 . j
- 39) RWCU Puinp Suction 0 NA 1, 3 NA- No 9. 0 [
1G33-F002 . i m 40) RWCU^ Return 61 NA 1,2,3 NA tio 9. 0 ' ! j y 1G33-F061
~
1 41) Hydrogen Recombiner 62 - tu -
. 1,'2, 3 NA No " 9.01 i m- 1HG019 l .
- 42) CR0 Pump Discharge . 61 .i A . .
- 1. 2, 3 NA No 9.0 ;
- IC11-F128 .
-43) RWCU Return - 64 NA 1, 2, 3 NA No ,9. 0 ,
IG33-FOSS l
= ,
.p
! 44) Containment Pressurization (test penet.) 67 NA 1,2,3 NA -No 9. 0 ' ' 1SA129 - . .
? p
[45) Hydrogen Recombi . 71 NA 1, 2, ;3 ,Ns No 9. 0 . , a 1HG016 l 1 E 1HG020 -[ l- ."_. ' 2 5' ; Y ' l g,4e g. !
! y46) Hydr en Recombiner 72 UA - 1,2,3 NA No
; - 1 17
'o
~ 47 !
- i
^ HG021 .%osg!
% g " '!
=w. j
~
1 I l - - - - .= . . -. . . _ _ _ -.
TABLE 3.6.4-1 (Continued) ,- ep C0f4TAltiMENT ISOLATION VALVES { 2; o
- MAXIMUM SECONDARY
' APPLICABLE ISOLATION CONTAIrrr.i TEST-E VALVF PENETRATION ISOLATI0tl OPERATIONAL TIME . BYPAS t'ATil PRESSURE Z NUMBtR NUMBER SIGNAlt . CONDITIONS (Seconds) (' a/NO) (psig)*
Test Connections, Vents . Orains-I ) (Continued)
- 47) SX To Recir.. Pump 78 NA 1, 2, . 3 NA No 9.0 1CC170
- 48) Supp. Pool Cleanup Return 7 NA' 1, 2 NA No 9. 0 15,F023
- 49) Fire Protection
~
81 NA 1,2,3 flA No 9.0 R 1FP129 T 50) Fire Protection 82 NA '1,2,3 NA flo 9.0
$ 1FP128 ,
~
- 51) Cycle Condensate 85 a '
1, 2, 3 NA No 9.0 1CY019
- 52) RWCU Letdown 86 NA 1, 3 ftA lio 9.0 1G33-F070
- 53) SX From Recir. Pump 88 NA 1, - 2 , ' 3 NA No 9.0 ICC171 ,
y,- 101 NA ~ 1, 2, 3 NA No 9.0 i'54) Containment HVAC Su '
@ IVR003 t 1, 2, 3 NA' No 9.0 y g g )
@ 55) Containmen /AC Return 102 NA IVQOO7 g4eg
- 56) C ainment HVAC 106 ilA -
1,2,3 NA No 9. < 3 g , VR011 g ga O:="
~
l t> c TABLE 3.6.4-1 (Continued) - CONTAINMENT ISOLATION VALVES' h , 5 E- MAXIMUtt SECONDAF"
- APPLICABLE ISCLATICM CONTA' 3Erli ' TEST ISCLATI0tt OPERATIONAL TIME BY^ 25 PATH PEESSURE E VALVE- '
PENETRATION CONDITIONS (Seconds) (YES/t:0) (psig)* Z NUMBER NUMBER SIGnAtt _ - Test Connections, Vent nd Drains (a) (Continued) i NA 1, 2, 3 NA No 9.0 '
. 57) Drywell Chilled Water - 107
- IVPO448 IVP077D . .
- 10. NA , 2, 3 MA no 9.0
- 58) Drywell Chilled Water -
IVPO478 IVP0778 . s 109 'i 1,' 2, 3 ' NA No 9.0 [ 59) . Drywell Chilled Water e IVPO44A E IVP077C - 1, 2, 3 NA No NA NA
- 60) Drywell Chilled Vater 110 IVP047A
- IVP077A NA 1, 3 NA No 9.0 13
- 61) Containment HVAC
. IVR012!
NA 1, 2, 3 NA No 9.0
- 62) Standby Liquid Control 116 1C41-F3408 - -
,E 1C41-F3418 o 1, 2, 3 NA 'To 9.0 S 63) Hydrogen P ombiner. 166' NA ygg3 g IHG018 5 Ec;
-= . ;' ? g
? .
"8Si
.~~ -
- m *E5"
- s.
~ ~
s
@W 3 7x W
i "A, \ i TABLE 3.6.4-1 (Centicued) Q & '@ - n C CONTAINMENT ISOLATION VALVES 1 5 , MAXIMLM SECCNOARY
'E -
APPLICABLE ISOLATION CCNTAi?. MENT .tST VALVE FENETRATION ISCLATION OPERATIONAL TIME SYFASS P*~ frE55U?C
- c. -
(yEs / .,) z NUMBER trJMBER SIGMAtt CONDITIONS (Seconds) (psig)*
-4
- Test Connections, vents and -ains(a) (Continued)
- 64) Drywell Pressure . NA 1, 2, 3 NA No
- 9. 0
- ICM076 151 1CM077 '3
~65) Reactor Pressure 151 NA 1, 2, 3 NA No 9.c
. ICM072 -
ICM073 .
- 66) Reactor Pressure 1G0 .i , 2, '3 NA No "O
^
t 1CM074 2 1CM075 [67) Equfpment Hatch 1 NA 1, 2, 3 . NA n3 9g
- ICM099 ..
- 68) Suppression g l Level . 177^ N" 1, 2, 3 NA No 9. c '
IE51 - F437A ' 1E51 - F437B . 179 NA 1, 2, a NA tio 9.0
- 69) Suppression [gelLevel #
1E22 - F381A Ih3 1E22-{g1B ' ISM 027A(h)
~
ISM 027B 181 NA 1, 2, 3 NA *:3 9.0 y70) SuppresgonPoolLeve # o ISM 026A ' E ISM 026B I) . s . 183 FA 1, 2, 3 NA No o0 -- F " > S 71) Suppres{or rool Level *
~~
$T ;*
[ ICM100A .
& ICHI . ) * $, e?.~.
Y "Off
- R*ES e
= ="
. - ~
i 9
- - . - . . . . . . . . . . . ii--.---- -
v- - 9
! zy> 2-TABLE 3.6.4-1 (Continued) t ^@ $ ,
I b CONTAINMENT ISOLATION VALVES . 5 E -
~FAXIMUM SECONDARY c APPLICABLE ISOLATION CONTAI?r " TEST 3 VALVE PENETRATION ISOLATION. OPERATIONAL- TIME BYPASS NTH PRESSURE t a NUMBER NUFSER SIGNAlt CONDITIONS (Seconds) (Y~ / NO) (psic)* [
4 a :
- , Other Isolation Valves (Con 'ed)'
;4. Other Isolation Valves ; l 1
- 1) Main Steam Line C- 5 1,2.3 NA No 9.0 !
1E32-F001J- NA I!
- 2) -Main Steam Line A 6 7 , 3, NA No 9.0 IE32-F001A . l r
. u, 1 3) Main Steam'Line D 7 1,2,3 NA No 9.0 { m 1E32-F001N NA - th .' . 1,2,3
- " 4) _ Main Steam Line B 8 -
NA No 9.0
- 1E32-F001E-
- 5) :Feedwater/RHR Line A- 9 NA 1, , NA Yes 9.0 1821-F010A !
1821-F055A ,
- 6) Feedwater/RHR Line B 10 NA '1, 2, 3,# h. Yes 9.0 .f
- IB21-F010B if 1821-F065B l l 8 t
& 7) RHR A Suction' Lina 11 NA 1,2,3 NA' No 9.9 !
o ! a 7 1E12-F004A(*) mene
- 8) RHR B ion Line. 12 NA 1,'2, 3 NA No 9.("4 f 004Bf ')
} 1E e7aE! c # 8 S!i l R
- Ei e
- -N N t x . . i i
r , E l 4 i ? j
...._e..._
, g pW '
TABLE 3.6.4-1 (continued) O 9 "v.k b I i c. C CONTAI!NENT ISOLATION VALVES
~
k D.1O ! _~ }
, 5 ~
I 52 ' j 1-7 MAXIlm SEC0Nt e c APPLICABLE ISCLATION CONTAI?NENT tS , 4 5
-4 VALVE PENETRATION ISOLATION OPERATIONAL TIME BYPASS Pf'. PRESSURE l NUMBER fEBER SIGNAlt CONDITIONS (Seconds) (YES ) (esig)* l } i Other Isolation Valves (Contint._ [
]' 9) RHR C Suction Line 3 FM 1, 2, 3 No 9. 9 i i 1E]?< '.05 ! c i j 10) Rh4 A Shutdown Cooling 14 NA 1,2,3 NA No 9.0 ' l 2 1E12-F475
- 1. r w 11) RHR/LPCI A Injection 15 , 2, 3 NA No 9.0
- } 1E12-F027A l 2
c., 1E12-F042A ! J, IE12-F028A ! i
- 12) RHR/LPCI B Injection l ,16 NA 1, 2, 3 NA No 9.0 j
- 1E12-F027B . ;
i 1E12-F042B t ! 1E12-F028B ; i 13) RHR/LPCI C Injection 17 NA 1, 2, 3 74 No 9.0 2 1E12- F042C . IE12-F041C., i
- 1E12-F301C ;
k= 14) RHR A/LPCS Test Line. .1B NA 1, 2, 3 14 No 9.9 1E21-F011 [ w. 1E12-F054A t [ [ 15) RHR C Line 19 NA 1,2,3 FM No 9. 9 ;fGgE[
.P -1E ' .064C i a c " j-
- O . .
e7asi i 1 RHR B Test Line 20 NA 1, 2, 3 NA No 9.9
- g o!;
1E12-F064B R#3E:
- i S u!
4 : [ i i
________- _ - _ _ _ . . . . . . - . = . .
~l
&D%.
TABLE 3.6.4-1 (Continued)
$ c. ,p p CONTAffmENT ISOLATION VALVES
~
3; g-z
' fuxItet SECONDARY APPLICABLE g VALVE *ENETRATION ISOLATION ISCLATION CONTAI?? di TEST OPERATIONAL TIME BYP ". PATI; FRESSURE O FPJMBER EDGER SIGNAtt CONDITICNS (Seconds) tS/tc) (psic)* !
'Other Isolation Valves (Con '"ued)
- 17) RHR A Suction Reifef 21 NA 1, 2. J 'A IE12-F017A No 9.9 )
- 18) RHR Shutdown Cool Relief 23 NA 1 1E12-F005' NA No 9.9
- 19) RHR A HX Relief Line 24 1,2,3 !
.w IE12-F055A NA No ' 9.9
'h
. 20) . RHR 8 Suction Relief 25 NA 1,2,3-J, -
~IE12-F0178 NA No 9.9 m
- 21) RHR B HX Relief Line 26 'A 1, 2, 3 Nk No IE12-F055B 9.9
- 22) RHR/LPCI 8 Inj. Relfef 27 NA 12, MA No
. 1E12-F0258 9.0
- 23) RHR C Suction Relief 29 NA 1, 2, 3 ' 'A IE12-F101 No 9.9 -[
24)' RHR/LPCI C Inj. Re1 ef 30 NA 1,2,3 NA 'o
-IE12-F025C 9.9 !
- 25) RHR To RCIC Suction Rellef 31 NA 1,2,3 1E12- 6 NA No 9.9 7 g g E!
- 26) CS Suction Line 32 NA 1, 2, 3 NA 1E21-F001 -
No 9.9 ogj
~
6
., "EE!
~
I'! L *
, , , , w ,_ _ . _ _ _ _ _ - _ _ . - - _ - - - - - - - " " - -' - -^^- -
&y ,3 Qk e> .
~ t. l TABLE 3.6.4-1 (Continued) . @D )~1 d b- CONTAIhMENT ISOLATION VALVES e ;
5 i e ^ MAXIFLH SECONDARY
-. APPLICABLE ISOLATION CONTAI!a'r TEST ,
e VALVE PENETRATION ISOLATION OPERATIONAL TIME BYPAS rATH PRESSURE ' 5 NUMBER- NUMBER SIGNAtt CONDITIONS (Seconds) (v a/ht) (psig)* Other Isolation Valves (Cont ed)
- 27) HPCS Test Line & Relief 33 NA 1,2,3 No 9.9 ;
- 1E22-F014 1E22-F035. I 1E22-F039 IE22-F012 ;
- 28) HPCS Injection Line. 35 NA , 2, 3 - NA No 9.0 i 1E22-F004 ;
t* IE22-F005 - l IE22-F304 1 29) LPCS Injection Line 36 NA 1,2,3 NA No 9.0 I
*- 1E21-F005 .
IE21-F005 ! 1E21-F340 .
- 30) HPCS Suction Line 37 NA 2, 3 NA No 9.9 i 1E22-F015 j L31) LPCS Pump Relief Line NA 1, 2, MA No 9.9 1E21-F018 '
IE21-F031 -
- 32) RCIC Min. Flcw Relief 40 NA 1, 2, 3 .. No 9.9 j y ' IE51-F090 g 1E51-F019 ,
- o. .
!<+33). RCIC Turbi exhaust 41 NA 1, 2, 3 NA No 9.9 ,,,,
IE51-F0 =ao-: ,p IE51- 40 % ye"! e , c =- i w
- 34) . IC Head Spray 42 NA 1, 2, 3 NA No " 8 3 !! !
1E51-F013: . 3. *' E E 1E51-F066 -
'1E51-F316 T 7w i
4 i W 3
- d~ .
I Q N II oc !
- . t i l
TABLE 3.6.4-1 (Continued) j n CONTAINMENT i' C ISCLATION VALVES 5 E
. MAXIMUM SECONDARY !
c VALVE APPLICABLE- ISOLATION CCNTAI' diT TES: s FENETRATION ISOLATION
- 5 NUMBER NUMBER OPERATIONAL TIME BYP " .3 PATH PRESSURE ,
SIGNAL.1 CONDITIONS (Seconds) ES/NO) (psic)* s'Other Isolation Valves (Cont . d) j Primary Containment (Continued) , t I
- 35) SX To Containment Cooler 48 HA 1,2,3 i: ISX089A NA No 9.0
- l. ISX088A l
- 35) Instrument Afr 4' 57 -
1,2,3 i
' IIA 175 NA No S.O i w 37) Instrument Air Bottles 58 NA 1, 2, 3,#
t l 1 11A0428 NA Yes 9.0 l 1 e IIA 012A - - J.
- J, '
- 38) CRD G3 NA 1, 7 NA 1C11-F122 , Yes 9.0 4
IC11-F083 2
- 39) RHR Flush Line 76 NA 1,2,3 Na 1
4 IE12-F030 No 9.9 i i
- 40) RHR/LPCI A Injec. R. ef 87 NA 1,2,3 t
j IE12-F025A NA No 9. 0 i { l
- 41) RHR HX A V. 89 NA 1,2,3 i ygggj NA No
! IE12-F ..
i -
' q 4e;;
j .7 a 9[ 4 "8 S!! O dm3; p. g = N
, i e -
. . . . . _ - + . ..m -
- - ^ ' ^ ~
A . 3 b t lI TABLE 3.6.4-1 (Continued) dsg. i ISOLATION VALVES
+
CONTAINMENT i
- n r-
- E MAXIMUM SECONDA P
. TNT TEST U APPLICABLE ISOLATION CONTA -
CPERATIONAL TIME BY 25 FATH PRESSURE 7 VALVE PENETRATION ISOLATION CONDITIONS (Seconds) YES/NO) (psig)* c NUMBER ~ _ SIGNAlt _ ; 5 NUMBER ed) [ Other Isolation Valves (Con Primary Containment (Continued) 1, 2, 3 NA No 9.0 NA t
-42) DW Chilled Water Relief IVP0238 .
, 2, 3 NA No 9.0 ;
108 NA
- 43) DW Chilled Water Relief' j
IVP0278 l
~ 1, 2, 3 NA No 9.0 !
109 NA
- 44) DW Chilled Water Reller IVP023A g
l
-1, 2, 3 NA No 9.0 -
110 - g* 45) DW Chilled Water .
- g. IVP027A g, g4 2, 3 >1<15(b) 150 NA
- 46) Containment Press ICM003A IC)Id) -
>1<30ID) No f;A NA 1,2,3 151
- 47) Drywell Pressure -
l
.ICMOS1(c)(d) ,
NA i 1, 2,. 3 >1<5 No
' 151 NA ~
- 48) Reactor Pressur '
ICM066 fC)Id}' ,
~
1,2,3 >1<30 fD) f.o NA 156 NA ;
- 49) Cont rit Bldg. HVAC
- ;f g g > '
056B(c)(d)- . 44c;; 55b5$ osa:
- g ." ,
O ="l
~
i
M )
- 3_. yl TABLE 3.6.4-1 (Continued) hC.Q CONTAINMENT ISOLATION VALVES n .
C
=
SECONDARv MAXIMUM d
^
APPLICABLE ISOLATION CONTAI?NEhT ' 2T TIME BYPASS PA PRE 551;EE ISOLATION CPERATIONAL VALVE PENETRATION CONDITIONS (Seconds) (YESP a (psig)* NUMBER SIGNAtt NUMBER
- Other Isolation Valves' (Conti d)
Primary Contairment (Continued) (15(b) g, g3 NA 1, 2, 3
- 50) Suppression Pool Level 1 ICIId)
^
1CM002A ICM003B(c)(d) 3, 34 160 .R , 2, 3 -->1<5(b)
- 51) Reactor Pressure w IC'067(c)(d)
M _ fD) No NA 164 NA 1,2,3 -->1<15 m 52) Suppression Pool Level b 1SM010(c)(d) . fD) NA L '3 No 165 NA 11130
- 53) Containment Bldg. HVAC IVR016A ICIId)
IVR016B ICIId)
~ yygoig4(c)(d).
- 1, 2, 3 No rtA
. 167 NA 11330
- 54) Containment' Bldg. HVAC -
IVG057B CC)Id)
- 55) Contain= int g. HVAC 3 f ) - 168 NA 1, 2, 3 ' 11130(b) y, IVR01aa # . 'c; No PIA 171 NA 1,2,3 11115(b) ';~ E E'
- 56) ression Pool-
-15M009(CIId)
"8SX
- ?,*gE
,m
- .u
- ~
r% m 7
9 f D 3 Lh ~
~
D%e O.p i I
. TABLE 3.6.4-1 (continued)'
CONTAi!NENT ISOLATION VALVES n i C . 5 . MAXIMUM SECCNCARY E APPLICABLE ISCLATION CONTAI!7 i TEST l ISOLATION OPERATIONAL TIME BYPA" ATH PRESSURE ! VALVE FENETRATION ; e . NUMDER SIGNAtt CONDITIONS (Secer.ds) ./No) (esiq)* 5: NUM3ER' - l
-4 -
" Other Isolation Valves (Coritinued !
Primary Containment (Continued) - 172 - NA . 1, 2, 3 NA no 3.9 - :
- 57) RHR HX Vent B 1E12-F074B
,3 >1<21(b) p, ,;3
- 58) Suppression Pool level 177 I 1E51-F377B IC)(d) I 179 NA 1,2,3 >1<21 CD} No m w 59). Suppression Pool level *
<- 2 1E22-F332 fC)(d) -
~
i IC}Id) ism 011 , y,
= . . .
g, g3 [ 180 IA 1, t 3 >1<15(b)
- 60) HPCS- .
l 1E22-F330 fC)(d) - NA- 1,2,3 (21(b) No M
- 61) Suppression Pool level IP _
ICIId) - ' . - 15M00C l l NA - 1 2,3 >1<21(b) ., 33
- 62) Suppression Pool level 183 IC)Id) - .- i ICM002B .
+ 200 NA 1,2,3 >1<15(b)
No NA i
- 63) RCIC -
. IES1-F37 (d) ,
- me,3 203 HA 1, 2, 3 >' 30 lD) No NA *?*"!
- 64) D 1 Pressure -
0?E CMOS3 fC)Id) 548F'
~
. o E ;;;; '
g;
. g .w
L
^
h%
& 3. .
4 l-TABLE 3.6.4-1 (Continued) , Q g.~ I . 8 CONTAINMENT ISOLATION VALVES
^
.MAXIMLH SECONDARY :
APPLICABLE ISOLATION CONTAINMENT _3T
'E' ii VALVE PENETRATION ISOLATION 0PERATIONAL TIME BYPASS PP- .. ' PRESS'J ! ) :Z NUMBER PEBER SIGNAtt CONDITIONS (Seconds) (Yr ~ . ,0 ) (psig)*
l - ! j Other Isolation Valves (Co .
- ued) ,
l Primary Containment (Continued) j
- 65) SX Return NA 1, 2, NA N3 9. 0 i 1SXO96B 4 ISXO97B .j
- 66) SX Supply 205 -
1 , 2 , 3'- NA No 9.0 1SX0888.- f j 1SX0898 .. . T 67) Instrument Air Bottles 206 NA 1, 2, 3,y NA Yes 9.0 8 IIA 042A IIA 013A !
- 68) SX'Frcm Cont. Cir. 208 NA 1, 2 NA No 9.0 ISXO96A i ISXO97A
- b. Drywell I i No NA NA NA NA . NA j r.'
t I h i Wac"i i
- =n.
- ul i
.~ _ = t p
l ,,
to t!-601884a
. 1emon E#8_ f6 ll;t;rg,,,,
TABLE 3.6.4-1 (Continued) CONTAINMENT ISOLATION VALVES TABLE NOTATIONS (a) May be opened on an intermittent basis under administrativ control durin(. oplicable OPERATIONAL CONDITIONS. l (b) Excess flc check valve actuation differential pressur . (c) Isolation va ing for instrument lines wh'ich pe'notr o the containment con-form to the re irements of NRC Regulatory Guide 11. The in-service in* spection progra. will provide assurance of the o >rability and integrity of these isolatio provisions. Type "C" testin will not he performed on the instrument lins isolation valves. The in rument lines will be within the boundaries of th Type "A" test, open to he media (containment atmo-sphere or suppression ool water) to which .iey will be exposed under pos-tulated accident condit ns. Instrument < ps from the process line located between the process isol ion valves' and/h penetration, and not them- , selves penetrating contai ent, will be/ Type "A" and/or "C" tested along with the process line isola on valve . (d) Excess flow check valve; (e) The RHR system may be operating the shutdown cooling mode 'N'ing +.he Type A test. These valves ~are es d using water but the results are not
' required to be added to the T e A t st results. The LPCS HPCS, and RHR ,
may be aligned in the norma standby injectionmode'duringtheTypeA test. This will expose th closed loo outside containment to containment pressure through the supp .ession pool, is is the closest valve alignment to the post-LOCA alignm t possible. Typ C water test results on these suction valves will no be added to the Typ A test results. , (f) Valves shall be clor>d in accordance with SEC ARY CONTAINMENT INTEGRITY. (g) Ives shall be " ealed closed" by utilizing mect nical devices to seal or lock the val closed or to prevent power from .ing supplied to the valve operator (h) OPERABILITY f,these valves is not required until comp ' tion of correspon ng plant modification.
# When ha dling irradia*ted fuel in secondary containment and uring CORE ALTER 10NS and operations with a potential for draining the cactor vessel.
## 150 ates on RCIC low steam line cressure only. -
t solation signal descriptions are provided in Table 3.6.4-2. For test pressure = 9.0 psig, the valve (s) shall be pressurized usin air cr nitrogen, and for test pressure = 9.9 psig, the valve (s) shall be , pressurized using water. With any control rod withdrawn. Not appli. cable to any control rods removed per Specification 3.9.10.1 or 3.9.10.2. CLINTON - UNIT 1 3/4 6-61 Amendment No.14
+ .
.. Attechmint 3
' 16 move Gn6,? ToJ6)
' ~' -
t;.,i:::!*"' TAILE3.6.42 Page 74 of 127 CONTAlleiENT ISOLATION TRIP SIGNAts Abbi'v. Description ' A Reactor Vessel Water level Low (Level 3 B Reactor Vessel Water Level Low (Level . C Main Steam Line Rad.-High and inop D Main Steam Line High riow .
.E Main Steam Tunnel Temp. High
. F Main Steam Tunnel Differential T . High G Hain Steam in Turbine Building ;mp. High H Turbine Inlet Pressure Low J ' ' Condenser Vacuum Low L Orywell Pressure liigh . M Containment Exhaust Duct h Rad. - N RWCU High Temp. P ontainment Pressure-Hi . R 'VICS Manual Initiati n Pushbuttons . S RH Heat Exchanger R ms A, B High Diffe.rential Temp. T RHR .at Exchanger oms A, 8 High Temp. - U React Water Lev Low (Level 1) V RCIC Hi. Steam ne Space Temp. RCIC Low team A ne Pressure RCIC High te m Flow
!!!gh Turbit. .xhaust .areasur.
RCIC Area g Temp, r RCIC Area igh ifferential Temp. X Permissi ely Int locked with Other Equipment .e Z High R . in Cent 'nment Refueling Pool Exhaust Duct 1 - RWCU uipment High ifferential Flow - 2 RWCV ent High Diffe ntial Temp. S Co ainment Purge Duct ligh Radiation - 4 9 e e CLINTON - UNIT 1 3/4 6-62
Attetic7nt 3 to U 601884a 1.5 91 004 l' age 7 $ of 127 C0t41AINMEf4T SYSTEMS 3/4.6.5 ORYWELL p0ST-LOCA VACUUM R[ LIEF VALVf5 LlHITING CONDITION FOR OPERATION
. 3.6.5 All drywell post-LOCA vacuum relief valves shall be OPERABLE and closed.
APPLICABILITY: OPERATIONAL CON 0lTIONS 1, 2*, and 3. ACTION:
- a. With one drywell post-LOCA vacuum relief valve inoperable for opening but known to be closed, restore the inoperable vacuum. relief valve to OPERABLE status within 72 hours or be in at 1 cast it0T SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours,
- b. With one drywell post-LOCA vacuum relief valve open, restore the open vacuum relief valve to the closed position within 1 hour or be in at least HOT SHUT 00WN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
- c. With the position indicator of an OPERADLE drywell post-LOCA vacuum relief valve inoperable, verify the vacuum relief valve to be closed at least once per 24 hours by visual inspection. Otherwise, be in at least HOT ,
SHUTDOWN within the next 12 hours and in COLD SHUT 00WH within the fol- -
. , lowing 24 hours. ,
SURVEILLANCE REQUIREMENTS 4.6.5 Each drywell post-LOCA vacuum relief valve shall- be: -.
- a. Verified closed at least once per 24 hours.
- b. Demonstra'ted OPERABLE:
- 1. At least once per 31 days by:
a) Cycling the vacuum relief valve through at least one complete cycle of full travel, b) Verifying the position indicator OPERABLE by observing expected valve movement during the cycling test.
- 2. At least once per 18 months by; a) . Verifying the pressure dif ferential required to open the vacuum relief valve, from the closed position, to be < 0.2 psid, and
*5ee Spe'cial Test Exception 3.10.1.
CLINTON - UNIT 1 ,
/ 6
Attachm2nt 3 to ll-601864a v
- LS-91-004 Par.c 76 of 127 C0t4T AltiM[t4T SYST[Pj5
@NEtt POST *l0CA VACllVM F:El1[F val.VES
$URVElltAt4CE REQUIREMEtlTS (Continued) 4.6.5 (Continued) ,
b) Verifying the position indicator OPERABLE by per'formance of a CHANNEL CALIBRATION. 4 6 7 b e e
. I s
- m. -
m i
Attachment 3 l to U-6018840 j , , 1.5-91 004 CdNTAINMENTSYSTEMS 3/4.6.6 SECONDARY CONTAINMENT l SECONDARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION . 3.6.6.1 SECONDARY CONTAINMENT INTEGRITY shall be maintained. APPLICABillTY: OPERAT!hNAL CONDITIONS 1, 2, 3, and
- liCT10N:
- Without SECONDARY CONTAINMENT INTEGRITY:
- a. In OPERATIONAL CONDITION 1, 2, or 3 restore SECONDARY CONTA!NMENT INTEGRITY within 4 hours or be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours. ,
- b. In OPERATIONAL CONDITION *, suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS, and operations with a potential for draining the reactor vessel. The provisions of Specification 3.0.3 are not applicable.
- HRVEILLANCEREQUIREMENTS _._
4.6,0.1 SECONDARY CONTAINMENT INTEGRITY shall be demonstrated by:
- a. Verifying at least once per 24 hours that the pressure within the secondary containment is greater than or equal to 0.25 inches of vacuum water gauge.
- b. Verifying at least once per 31 days that:
- 1. All secondary containment equipment hatches are closed and sealed.
- 2. At least one door in each access to the secondary containment is c.losed, except during normal entry and exit, i
- 3. All secondary containment penetrations not capable of being closed by OPERABLE secondary containment automatic isolation dampers / valves re-quired to be closed during accident conditions are closed by valves, ,
blind flanacs or deactivated autorna_ tic damnerl/ valves _ secured in positio[N.Cpt]AQcsided jn Epicif[ tio 7,G,6
*When irradiated fuel is being handled in,the secondary containment and during , CORE AL1 ERAT 10NS and operations with a potential for draining the reactor
,t, vessel. I CLINTON
- UNIT 1 3/4 6-fd 3 3 e----ae* , -r--w4-y-g*w -4e *ege-+ar4-ey wry -esyetwg g r- ga.-seek ww ei,gaw- rew-wgg9a,9<.yy-- w A t'imy 4 met e W e&sy-'v s W1- w sv T b'9*T- -fi--'-i sy* - -s- P
- - - - . . - _ - ~ - -_ -- . . . . - - _ _
Attochment 3 to U-601884 o
* ' LS 91 004 '
Page 78 of 127 CONTAINMENT SYSTEMS SECONDARY CONTAINMENT INTEGRITY SURVEILLANCEREQUIREMENTS(continued) 4.6.6.1 (Continued) c, At least,once per 18 months by verifying that:
- 1. Each standby gas treatment subsystem will draw down the secondary ;
containment to greater than or equal to 0.25 inches of vacuum water I gauge from the test start pressure in less than or equal to the time period corresponding to the measurt flow rate specified in Figure 4.6.6.1-1.
- 2. By operating each standby gas treatment subsystem for one hour and maintaining > 0.25 in. of vacuum water gauge in the secondary con-tainment at a flow rate not exceeding 4000 cfm i 10L t
. 9 l CLINTON - UNIT 1 3/46-f(3Y Amendment No.21 = - - - - - - 1 w , . - , - - y w -e 7 ,--c.- -----g -
gy. , - v.,.,- m-e,,94w -
--nymy-Y e e r -S- "1r"- et"rs y
o , h 74 h ! z - \ NOTE: Carve shewn is cpplicobis to condiflocs Corr *sponding to power 70 operation with the turbee Building f z
\ venfliction system in operoflon and 4 66 \ wind s eeds less then or equal to lo ApPH.
_ \ . 62
\
14 g se 9 34
\\ UNACCEPTABLE (k c,Igi \: -
i 50 A L jW a %
.w 1E 4s
\
.tn g \
o
, g 42 5
ACCEPTABLE T(A o s,8 3 34 x w 30 . g - E f ' - I 2s j 2800 300o 32o0 3400 asco seco 400o 4200 4400 j??! STANDBY GAS TREATMENT SYSTEM AIRFLOW (CFM) *3?E
& 3aET h FIGURE 4.6.6.I-I oEhk
{m SECONDARY CONTAINMENT DRAWDOWN TIME _ FOR 1500 CFM B0!!NDARY 1.EAKAGE 5 D . L._____m
Attochment 3 to U-601884 a LS 91 006 Page 80 of 127 Y P 4 CONTAINMENT SYS1fM$ , SECONDARY CONTAINMENT AUTOMATIC !$0LATION DAMPER $ i j i LlHITlHG CONDITION FOR OPERATION 3.6.6 containmentventilationsysttmaut$malicisniation dampt.f n 1 :- : :_:_5_mhaL1 be OPERAB h= 1;n.nvi- G,; Q
;r; :.-;-;- _nagrg g pc ; ;p; ' ! ' .U ._ p --
APPLICABILITY: OPERATIONAL CON 0!TIONS 1, 2, 3, and *. ACTION: > With one or more oflht ;ecomiev cantainment ventilation system automatic isolation damper C M = 122._ ninoperable, maintain at least one l .
~
isolation damper OPERAULE 1h GacD aUecteo panetration that is open, and Within 0 hours either: ,
- a. Restore the inoperable damper to OPERABLE status, or .
- b. Isolate each affected penetration by use of at least one deactivated automatic damper secured in the isolation position, or
- c. Isolate each affected penetration by use of at least one closed manusi valve or blind flange.
The provisions of Specification 3.0.4 are n'ot applicable provided the affected . penetration is isolated in accordance with ACTION b and/or c above, and pro'v ided , the appropriate system, if applicable, is declared inoperable and the t: propriate
~
ACTION statements for that system are performed. Otherwise, in OPERATIONAt. CONDITION 1, 2 or 3, be in at least HOT SHUTDOWN ~ within the next 12 hours and in COLD SHUTDOWN within the following 24 hours. Otherwise, in OPERATIONAt. CONDITION *, suspend handling of irradiated fuel ib the secondary containment, CORE ALTERATION 5 and operations with a potential for i draining the reactor vessel. The provisions of Specification 3.0.3 are not applicable. l
*When irradiated fuel 1s being handled in the secondary containment and during ,
CORE ALTERATIONS and operations with a potential for draining the reactor vessel. ( _ CLINTON -' UNIT 1 , 3/4 6 [ h l _'f
. _ . . _ _ _ . _ . _ . _ . _ _ . . _ . _ . _ - _ . _ . _ _ _ _ .7 Attachmsnt 3
- 4 to U.601884a lS.91 004 Pace 81 of ]n CONTAINHIN1 $YST[H$
SICONDARY CONTAINMENT AUTOMAllC ISOLATION DAMP (Q
$URVilLLANCC REQUIREHEHTS '
I
~
f 4.6.fi.? E2& tsfondary30nuinment ventilation system automatic isolation damper @ -5 9 .m shall be demonstrated OPERABLE:'
- a. Prior to returning the damper to service af ter maintenance, repair or replacement work is performed on the damper or its associated actuator, control or power circuit by cycling the damper thrnunh at least one isolation time, complete cycle of full travel and verifying th
- b. DuHno to D $HUTDOWN or REFUELING at least once per 18 months by verifying - _ _
that on 4 containment isolation test signal each 1splation damper actuatts hcEn'sagConkiinNgaMJi
~
to its isolation position. QCO -
- c. At least once per 92 days by verifying the isolation time to be within its limit when tested.
9 9 4 9 9 4 i e t CLINTON - UNIT 1 3/4 6-.- M >
- n n,-- . , - . , , , , e. ,, ,,y-- , - . , . , , - - . . ~ , - , - -- , ,---.-c.~ . -n , , - ,e.-
- Attachment 3 g%CG8 h OIlId e 4[6 to U.601684e LS-91 004 Page 82 of 127 T ABLt 3.6. 6. 2-1
$ 'OfiDARY CONTAINMEf4T VEf4TilAT10N SYS1[M AUTOMATIC ISOLATION DAMPERS HAX1 MUM .
150LAT10f IME DAMPFR F . TION ($ce idt )
- 1. fuel Du ding Supply Damper. .
Outboard, IVf004Y - 4
- 2. Fuel Buildi Supply Damper, Inboard, IVF' Y
- 3. Fuel Building Ex ust Damper, 4 Outboard, IVf09Y
- 4. Fuel Building Exhaus Damper, 4 Inboard, IVF07Y t
e 4 e i. 9 9 9 4 4 9 CLINTON - UNIT 1 - - 3/4 6-69
, . . - . ~ -
~.n - -
,, y,n.. ,,,4 - - . ,, ,e nn .-~ . . - .- ,--...,.. , -
At tachtnent 3 to U.601884 a 1,S-91-004 Page 83 of' 127 CONTAINMENT SYSTEMS ST ANDBY GAS TREATHENT $YSTIM LIMITING CONDITION FOR OPERATION 3.6.6.3 Two independent standby gas treatment subsystems shall be OPERABLE. APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, and *. ACTIOP!:
- a. With one standby gas treatment subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days, ort
- 1. In OPERATIONAL CONDITION 1, 2, or 3, be in at least HOT $ HUT 00VN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours.
* , suspend handling of irradiated fuel in '
- 2. In OPERATIONAL CONDITION the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel. The provisions of Specification 3.0.3 are not applicable.
- b. With both standby gas treatment subsystems inoperable in OPERATIONAL CONDITION *, suspend handling of irradf ated fuel in the secondary contain-ment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel. The provisions of Specification 3.0.3. are not applicable, o.. -
SURVE1LLANCE REQUIREMENTS 4.6.6.3 Each standby gas treatment subsystem shall be, demonstrated OPERABLE: .
- a. At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the.
subsystem operates for at least 10 hours with the heaters OPERABLE. At kan once per 18 months or (1) after any structural maintenance on' the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the subsystem by: , 5% irradiated fuel' is being handled in the secondary containment and during COM ALTERATIONS and operations with a potential for draining the reactor vessel. Sc 3/4 6 Ct1NTON - UNIT 1, e
+4 dua L. -
)
Attachment 3 to t!-601384a LS 91 004
, Page 84 of 127 CONTAINHENT SYSTEMS
, STANDBY GAS TREATHENT SYSTEM l I j
$URVEILLANCE REOUIREMENTS (Continued)
?
- 4.6.6.3 (Continued) 1
- 1. Verifying that the subsystem satisfies the in-place penetration and
, bypass leakage testing acceptance criteria of less than 0.05% and uses the test procedure guidance in Regulatory Positions C.S.a. C.S.c and C.S.d of Regulatory Guide 1.52 Revision 2, March 1978*, and the syr :m flow rate is 4000 cfm i 10%..
- 2. Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample-obtained in accordance with Regulatory Harch 1978*, meets Position the laboratory C.6.b of Regulatory testing criteria of Regulatory Guide 1.52, LositRevision 2lon C.6.a of Re tory Guide 1.52, Revision 2. March 1978*, for a methyl iodide penetra-tion of less than 0.175%*
methods, with the followIn.when g parameters: tested in accordance with ASTM D3803-79 a) Bed Depth - 4 inches b) Velocity 40 fpm c) Temperature - 80*C
+
d) Relative Humidity - 70% 4 and l , 3.' . Verifying a subsystem flow rate of 4000 cfm i 10% during system operation when tested in accordance with ANSI H510-1980.
- c. After every 720 hours of charcoal adsorber operation, by verifying, within .
31 days after removal, that a laboratory analysis of a representative n carbon sample obtained in accordance with Regulatorf Position C.6.b of
- Regulatory Guide 1.52. Revision 2, Harch 1978*,' meets the laboratory test-fing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52 - . .
c Revision 2 March 1978".- for a methyl todide' penetration of less than 0.175%;. in accordance with ASTM D3803-79 methods, with the following parameters:
- a) Bed Depth -
4 inches- ' b) Velocity - 40 fpm c) Temperature - 80*C-d) Relative Humidity - - 70%. .
+
- ANSI H510-1980 shall be used in place of ANSI H510-1975 as referenced in Regulatory GJide 1.52 Revision 2, March 1978.
1 _ ^^s '
- h CLINTON - UNIT ,1 3/4 6- [ h - Amendment No. 15
-- - - . _ _ . - ~ . _ _ . _ _ _ . _ . _ . _ . _ . _ _ . _ _ _ _ _ _ _ _ . _ -
Attachment 3 to U 601884 a l.S 91-004 Page 65 of 127 l l CONTAINHEtiT SYSTEMS STAT 4DilY GAS TREATHEtiT SYSTEM SURVEILLANCE REQUIRfMENTS (Continued) 4.6.6.3 (Continued)
, d. At least once per 18 months by:
- 1. Performing a system functional test which includes simulated auto-matic actuation of the system throughout its emergency operating 4 sequence for the a) LOCA, and b) Fuel handling accident. l
- 2. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6.0 inches Water Gauge :
while operating the filter train at a flow rate of 4000 cfm i 101 ;
- 3. Verifying that the filter train starts and isolation dampers open on-receipt of the following test signals:
a) Hanual initiation from the control room, and i b) Simulated automatic initiation signal. i
- 4. Verifying that the filter cooling bypass dampers can be manually opened and the fan can be manually started. i S. Verifying that the heaters dissipate at least 18.0 LV when tested in accordance with ANSI H510-1980. ,
- e. After each complete or partial- replacement of a HEPA filter bank, by verify-ing that the HEPA filter bank satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI H510-1980 while operating the system at a flow rate of 4000 cfm i 104 f.- After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the in place penetra-tion and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI H510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 4000 cfm i 10L 4
I
^~
Amendment No.55 CLINTON - UNIT 1 _w 3[46 M O) 3
- ,._r.,. ., ,.a -- q7- _ . .,y-4 y ,,,y.- y...%. .,- . . _ . ,,,v, . __w. w..,..m. ,_ . . , _ . . . , . in. . . , ,,,u , , . . _,.m, s o s -, ,. ..#-,
l Attachment 3 to U-601884 a
' ' LS-91 004 i Par,e 86 of 127 f CONTAINMENT SYSTEMS 3/4.6.7 ATHOSPHERE CONTROL CONTAINHENT HYOROGEN RECOMBINER SYSTEMS L1HITING CONDITION FOR OPERATION 3.6.7.1 ho indelsendent containment hydrogen recombiner systems shall be ,
OPERABLE. APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2. ACTION: With one containment hydrogen recombiner sy6 tem inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours.
$_tLRVE1LLANCEREQUIREHENTS
.7.1 Each containment hydrogen reco'mbiner system shall be demonstrated OPERABLE:
~
- a. At least once per'6 months by verifying during a recombiner system fune.
tional test that the heater sheath tempdrature increases to greater than
- or equal to 600*F within 60 minutes and maintains greater than or equal to 600*F for at least 2 hours.-
- b. At least once per 18 months by: .
- 1. Performing a CHANNEL CALIBRATION of all recombiner operating instru-mentation and control circuits.
- 2. Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiner enclosure; i.e. loose wiring or structural connections, deposits of foreign materials, etc.
P
- 3. Verifying the integrity of all heater electrical circuits by performing a resistance to ground test within 2 hours following the above required functional test. The resistance to ground for any heater phase shall be greater than or equal to 10,000 ohms'.
- 4. Verifying during a recombiner system functional test that the reac*
tion chamber temperature increase to be > 1150*F within.2 hours and is maintained between 1177'F and 1223*F Tor at least 2 hours. 4 CLINTON - UNIT 1 3/4 6-h I
Attachment 3 to U 601884 a LS 91 004
' I' age 87 of ]?7 CONTAINHENT SYSTEMS gtlTAINMENT HYOROGEN RECOMBINER SYSTEMS SURVEILLAt1CE REQUIREMENTS (Continued) 4.6.7.1 (Continued) .
- c. By measuring the leakage rate:
- 1. As a part of the integrated leakage rate test required'by Specification 3.6.1.2, or
- 2. Of the system outside of the containment isolation valve at Pa.
9.0 psig, on the schedule required by Specification 4.6.1.2, and including the measured leakage as a part of the leakage determined in accordance with Specification 4.6.1.2. t 4 e S 4 ( CLINTON - UNIT 1 3/4 6- 1 e= 4
.. . . . . . . - -.............--.-....--....mi-w.m
i- . Attachment 3 to U 6018844 LS-91-004 Page 88 of 127 j l l J CONTAINMENT SYSTEMS CONTAINMENT /DRYWEtt HYOR0 GEN MIXING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.7.2 Two independent containment /drywell hydrogen mixing systems shall be OPERABLE.
. APPLICABILITY: OPERATIONAL CONDITION $ 1 and 2.. .
ACTION: With one containment /drywell hydrogen mixing system inoperable, restore the' inoperable system to OPERABLE status within 30 days or be in at least HOT ' l
- SHUTOOWN within the next 12 hours.
SURVEILLANCE RE001REMENTS 4.6.7.2 Each containment /drywell hydrogen mixing system shall be demonstrated CPERABLE:
- a. At least once per 92 days by:
- 1. Starting the system from the control rooia, and r,
- 2. Verifying that the system operates for at least,15, minute.s. .
?- b. At least once per 18 months by verifying a system flow rate of at least .
800 scfm. i e 9 4 7 4 9 e e A
~
i 3 4
-U -+,-.w.sq -,-e,+,#.,w.- ---rw,.w. y .w w w s , e.,-*re- e+ -m w -w--ne'**v'*-*w's
.. _. - -__ _ _ _ . -. . - _ = . .
- Attachment 3 to U 601884a LS 91 004 Pace 89 of 127 CONTAINMENT SYSTEMS PR1HARY CONTAINM(NT/ORYWELL HYOROGEN 1GNIT10N $YSTEM ,
LlHITING CONDITION FOR OPERAi!ON 3.6.7.3 The primary containment /drywell hydrogen ignition system, consisting
- of two independent primary containment /drywell hydrogen ignition subsystems shall be operable with no more 'than two igniter eachconsistingofsixcircuits}t,iterassenbliesinoperable.no assemblies inoperable per circu per subsystem, and no adjacent ign more th APPLICAB11.1TY: OPERATIONAL CONDITIONS I and 2.
ACTION:
- a. With one primary containment /drywell hydrogen ignition subsystem and/or circuit inoperable, restore the ir. operable subsystem and/or circuit to OPERABLE status within 30 days or be in at least HOT $HUTDOWN within the .
next 12 hours.
- b. With any adjacent igniter assemblies inoperable, restore all igniter assemblies adjacent to ari inoperable igniter assembly to OPERABLE status within 30 days or be in at least HOT SHUW.WN within the next 12 hours.
StjRVEILLANCE REQUIREMENTS 4.6.7.3 The prima containment /drywell hydrogen' ignition system shall be - den.onstrated OPERAB E
- a. At least once per 184 days by energizing all the igniter assemblies and performing current / voltage measurements of each circuit.
- 1. If more than three igniter assemblies on either subsystem are deter-mined to be inoperable, Surveillance Requirement 4.6.7.3.a shall be performed at least once pe'r 92 days until this condition no longer exists. '
- 2. If more than one igniter assembly on each subsystem are determined to be inoperable, determine if the inoperable igniter assemblies are adjacent. *
- b. At least once per 18 months, by energizing each igniter assembly, verifying a surface temperature of at least 1700*F for each of the accessible igniters and verifying by measu ement sufficient current / voltage to develop 1700*f surface temperature for those igniter assemblies in inaccessible areas.
CLINTON - UNIT 1 3/4 6-) [ % i i _ _ _ _ _ _ _ _ . . _ _ . ~ _ . ,
-m wt _ -As m . - , - , - - Attachment 3 asse,c;McA waw ench penor3 ccnicnnrnent elecWiced ;cnewa_ 7 Mon d(tuh to U-601884 a
' .SMB bc C3I'ER hELE , The Se cPC C8 ihese predec%Ve cScy;ces exclde% LS-91-004 Pa,e 90 of 12; 4 h e,6c c.irco M5 L wh'ich Credib\e SnoH corrend uwold rwt Citteed She.
t\ecwicA peneWJcn s' deu.grv raungs. _ # _ _ __ ^ ~ ELECTRICAL POWER SYSTEMS t 3/4.8.4 ELECTRICAL E0UIPMENT PROTECTIVE DEVICES , CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 1, 8.4,
' Vma<ilnaL%
qTibiinMrCuenetrat_ionfonductor overcurrent protective devices Q .M . . . . _ , ,. ., . . . . . ! : = : ; n O R ." 'H Q g APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3. ACTION:
- a. With ole or more of lheJoTntainii1ent nenetration conductor overcurrent pro-tective devicesD ir i n :0:t U._f.2 '_linoperable, declare the affected systt.m or compohEhr moperable and apply the appropriate ACTION statement '
for the affected system and: .
- 1. For 6.9-kV circuit breakers, de-energize the 6.9-kV circult(s) by tripping the associated redundant circuit breaker (s) within 72 hours
?nd verify the redundant circuit breaker to be tripped at least once per 7 days thereafter. *
- 2. For lower volt' age circuit breakers, remove the inoperable circuit breakerW from service by racking out the breaker within 72 hours and it. . sy +- fnoperable breaker (s) to be racked out at least once per 7 % aereafter.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours,
- b. The provisions of Specification 3.0.4 are not applicable to overcurrent devices in 6.9-kV circuits which have their redundant circuit breakers-tripped or to lower voltage circuits which have the inoperable circuit breaker racked out..
SURVEILLANCERE,q,IREMENTS U ni6.& 4.8.4.1 .a of the co i e t penetration conductor overturrent protective devices-: M r. S. !. m .T.$ .7_,shall be demonstrated OPERABLE: ssv_ _
- a. At least once per 18 months:
- 1. By verifying that the medium voltage 6.9-kV circuit breakers are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers and performing:
a) A CHANNEL CALIBRATION of the associated protective relays, and CLINTON - UNIT 1 3/4 8-24 l i
_ _ _ - , . , p N f 884 a I
, , O h4%dde U 9-91-*4
% cone,num _onty ,
Page 91 of 127 ELECTRICAL POWER SYSTEMS . CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES
- SURVEILLANCE REOUIREMENTS (Continued) 4.8,4.1 (Continued) b) An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and overcurrent control cir-cuits function as designed.
c) For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be func-tionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
- 2. By selecting and functionally testing a representative sample of et least 10% of each type of lower voltage circuit breakers. Circuit breakers. selected for functional testing shall be selected on a rotating basis. Testing of these circuit' breakers shall consist of injecting currents in excess of the breaker's nominal setpoint and measuring the response time of the long time delay and short time delay trip elements and setpoint of the instantaneous element where applicable. The measured response-time shall be compared to the manufacturer's data to ensure that it-is less than or equal to a value specified by the manufacturer. Circuit breakers found inoper-able during functional testing rhall be restored to OPERABLE status prior to resuming operation. For each circuit breaker found inoper-able during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable ..
type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
- b. At least once per 60 months by subjecting each circuit breaker to an inspec-tion and preventive maintenance in accordance. with procedures prepared in conjunction with its manufacturer's recommendations.
O CLINTON - UNI,T I 3/4 8-25
Attachment 3 to u-601884a 1 8T()OV 6 i LS-91-004 t
*g Page 92 of 127 A TABLE 3.8.4.1-1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PR- ECTIVE DEVICES DEVI ~ NUMBER AND L ^ATION
- a. 6. kV Circuit Breakers .
Reactor Re tc. Pump 1A Penetr ion IEE01E Penetrat on conductor size 1/c-1000 M per 0 Normal Operatio Protection 6.9-kV Swgr. ocation 121, AH, (R C); El 781 ft. Two identical ircuit breakers n series with identical otective rel s. -11 relays for phase overcurrent Westinghouse Typ COM-5 and
. protection Westinghouse Type C-T r - ays for ground fault protection low Frequency Operation Pr t tion 6.9-kV Swgr. Locatio 1 ', AH, AV (R,C); El. 781 ft. Breaker 2A e IJCV relays for phase overcurrent with (IRR01ED) with thre GE voltage restraint. Relays are located in LFMG relay panel B33-P001A. '
Reactor Recirc. Pump Penetration IE 2E Penetration c ductor size 1/c 000 MCM per 0 Normal Operatio rotection 6.9-kV S r. Location 105, AH (R.C), El 781 ft. Two ide ical circuit breakers in se es with identi 1 protective relays. Westi ghouse Type COM-5 and CO-11 relay for phase overcurrent pro ction We inghouse Type SSC-T relays for ground ault protection Low.F quency Operation Protection 6.9-kV Swgr. Location 105, AH (R,C); El 781 ft. Breaker 28 (IRR02ED) with three GE Type IJCV relays for phase overcu ent with voltage restraint. Relays are located in LFMG relay pan B33-P0018.
_.,__...._-.._._.,...._.-.m.__._.. - _ . _ . _ . . . _.._._._m______. __ __.__.m.._, . W % Attachment 3 i 9emove 6n4;ce e tQ-@l884 a LS-91-004-j Page 93 of 127-
-a TABLE 3.8.4.1-1 (Continued)-
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE D ICES
- b. L ver Voltage Circuit Breakers: .
p.
- 1. Typ Holded Case Auxiliary Building MCC IF'(1AP41E) '.
Location'119, Y (R,C); El 762 ft Eac Compartment listed below has two 1 ntical - circuit breakers in series. EgUTPM"T - PENETRATION g ,- aERVICE- NUMBER , 1E RLC118- IEE03E
; ILL18EA 1D LC115- ' 1EE03E L16EA 30 5 Pum 1A 1EE05E 1RE0 ,
5A Sump? 1EEOSE
.cs 1R PA SB p Pump 1EEOSE ^
RF03PA SC -Sump' Pump . 1EEOSE 1RF07PA-- - 88, RWCU Viv Mtr 1EEOSE-IG33-F102-E .7A RWCU Viv Mtr EEOSE L 1G33-F031-B RWCU Viv Mtr- 1EE E-1G33-F042A-
-7C RWCU Viv Mtr IEE05E -
IG33-F044 2A Head Vent Viv- 1EE07E-1821-F001- . 28 Head Vent Viv 1EE07E
, 1B21-F005 ,
F CLINTON - UNIT 1. 3/4 8-27 e
~ ~
-Attachment 3 Temovc En+ ire' Pass ^ ^
t;.;;! g*" P ge 94 of 127 TABLE 3.8.4.1-1 (Continued) CONT,i1NMENT PENETRATION CONDUCTOR OVERCURRENT PROTEC VE DEVICES AuxiliaryBuildingMCdIF(1AP41E)(Con nued)
. EQUIPMENT ENETRATION COMPT SERVICE NUMBER 2C . Wtr Press Cont 1EE07E VLV IC11-F003 3C Space Htr IEE07E 1833-C001A 4 Suct Viv Htr IEE07E 1833-F023A ,
f 4A WINCH- IEE05E 1F42-E0 68- Disc C Viv IEE07E 183 F067A 8A CUSuht- IEE07E IG33-F100
- IB- IF15 005 , IEE07E 8C J/B -
IEE07E 1HC69G-l . 8D
~
Shield Door - 1EE07E ~ 1 1HC71G-
-4 011 Pump Mtr IEE36E-1833-D003A 50 Fan Motor IEE36E 1833-0003A 3B- Fan Motor 1 36E.
-IVR12C e
e O CLINTON - UNIT 1 3/4 8-28 ,
= , + - e- 4- -.--i- , , ew-.-,. ~ , , , , . y -,+g, .,,.p .,,_ ., ,,, .--g ,,yy ,e, -y---$,.m, , - -,_~%..y-,,_.p.,.
, x- C Attachment 3.
&fnOU$ b0 $ 1 -
Pa 'e 95 of 127 TABLE 3.8.4.1-1kContinued) CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT P TECTIVE DEVICES Auxiliary Building MCC 1F (1AP41E) Continued) EQUIPMENT PEHETRATION
. COMPT SERVICE NUMBER 1F SRM/IRM IEE05E Drives 1EE05E 1H22-P008 1EE05E 1EE05E 1EEOSE IEEOSE 1EE05E 1EE05E 1EE05E-IEE05E 1EE05E 1EE05E 6C W85JX 1EE07E 1EE07E
# W505JY 1EE07E 1EE07E IWS JU IEE07E 9 IEE07E 9 IVP01CE 1EE05E B IVP01CG 1EE05E e
O
-A CLINTON - UNIT 1 , 3/4 8-29
. _~...s-. . .. ,.
. . - . -. ~ . . . - . -. . - . - - _ -.- .. - .-- -
, s ~
w w-
'
- Attachment ~3 6 @ V6 hMhs(d (D] 6 o4 Page 96 of 127 TABLE 3.8.4.1-1 (Continued)
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DE'VICEy Auxiliary Building MCC IG (1AP42E) Location 106, Y (R,C); El 762- f t-Each Compartment listed below has two identic
- circuit breakers in series. -
EQUIPMENT PEN TION MPT SERVICE BER IE Ltg Pn1 117 E04E ILL7EA ID Ltg Pn1 115 IEE04E ILL15EA 4A Sump Pump 1EE06E-1RE03PB 4C ump Pump. 1EE06E 03PB 4D S P pI '< JEE06E 1Rrn 60 V - IEE06E . 33-F04 5B Agitator IEE06E 1G36-A001
~
4B Sump Pump . 1EEb6E-1RE05PB l 5A Fan 1EE06E ' IB33-0003B IB Hyd Sys 1EE08E 1F42-D002 3A Wnt Valve IE 8E
- 1821-F002 ,
20 Space Htr IEE08 1833-C001B . 3C Suct Valve IEE08E l 1B33-F0238 l ( CLINTON - UNIT 1 3/4 8-30
, + _.,.,--,.#. . - - - - - - . - . - - _ y , -,-,..r,., , , . y .y-,-
e.v,-- ~, y w y -.+
T ' ~ " - - Attachment 3 r%- - to U-601884 a
@pg h[)f((8 Q 6 LS-91-004 Page 97 of 127 i
. TABLE 3.8.4.1-1 (Continued)
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIDEVICES Auxiliary Building MCC 1G (1AP42E) (Conti ued) EQUIPMENT P NETRATION COMPT NUMBER _ SERVICE A Disch Viv IEE0BE 1833-F0678 38 Oil Pump 1EE04E IB33-D003B 50 Demin Pump IEE08E IG36-C0018 SC Agitato IEE08E IG36- 2 6B JT 1EE06E 7A P CF 1EE06E IVP09 IEE06E w 78
^
7C IVP091B ' IEE06E 8A IVP01CH 1EE06E l l [ l I 4
+
. CLINTON - UNIT 1 3/4 8-31 w
1- m -m y- w- * * - - - - 9 -
-g = - w,y y y 3 w +~e' e-n--
- m. . . _ . . . . _ - _ .. .. _ __ .._ _ ._--_.m.. _. __-. . _ _ _ - - -
" * ~
- ' Attachment 3 A
. ernous.
+A _
E nWe]a3
^
_M e- c:."M2**
- Page 98 of 127 TABLE 3.8.4.1-1 (Continued)
CONTAINMENT PENETRATION CONOUCTOR OVERCURRENT PROTECTI DEVICES Auxiliary Building MCC 1A2 (IAP73E Location 121, V (R,C); El 781 ft Each Compartment listed below has. tw identical - circuit breakers in seri . EQUIPMENT PENETRATION COMPT SERVICE NUMBER RHR Valve IEE09E 1E12-F037A 13C IIA 0128 IEE09E Auxil try Bui ingMCC1A1(1AP72E) Locat' n 12 , Y (R,C); El 781 ft
. Each Compartmen listed below has two identical-cir i breakers in series.
2BL SL 58 1EE03E ILLS 10 Drywelt Fan ~ 1EE05E IVP01CA Drywell Fa IEE05E IVP01CC IC Comb Gas' IEE09E Compressor 1HG02CA 3A -Stby Liq Pmp. IEE09E IC41-C001A l . CLINTON - UNIT 1, 3/4 8-32 i
, ,- , ,--.,- , .w -- ,,,,v. ,n-,c. ,- ,vn--- ,--,,---n,,- ,,m,-m.--
Attachment 3
. . ernove En+WeTag & ls.4%"**"
Page 99 of 127 TABLE 3.8.4.1-1 (Continued) CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE 0' / ICES Auxiliary Building MCC 1A3 (IAP74E) Location 121, V (R,C); El 781 ft Each Compartment listed below has two id tical circuit breakers in series. EOUIPMENT ENETRATION COM SERVICE NUMBER SC Sample Pump IEE07E 1P508P 4B Sample Pump 1EE07E 1PS06P 40 mple Pu 1EE07E 1P 7P 20 Samp Pump IEE07E
- 1P50
~
w 13B $ t.off ve IEE09E M002A 4 13A Shutoff Valve IEE09E ISM 001A 13C Spray Valve IEE09E 1E12-F042A IB Isol Valve EE09E 1FP078 140 Supply Fan IEE E IVR08C CLINTON - UNIT 1 3/4 8-33
W , rw . w Temove En+ ire Ta3e- mms'. W LS-91-004 P ge 100 of 127 , TABLE 3.8.4.1-1 (Continued) CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT rROTECTIVE EVICES Auxiliary location 121, Building V Y R(MCC C); El1A4 781 (IAP93E) ft Each Compartment listed below has two i ntical circuit breakers in series. EQUIPMENT ENETRATION C PT SERVICE NUMBER 10B Spray Valve IEE09E 1E12-F028A , . 7C Isol Vilve IEE09E ICYO21 10A Suct Valve IEE09E G009A 9A I 1 Val e IEE09E IS 5 98 Isol Ivi' 1EE09E ICC 7 . 9C T ol Valv IEE09E J,CC128 IOC Outlet Valve IEE09E-IC41-F001A . 7A Isol-Valve IEE37E , 1SX089A 78 Isol Valve EE37E ISX096A C IV0551A 1E 7E 8B 1WO552A 1EE37 BC 1C11-F370 1EEOSE' e i Ct.INTON - UNIT 1 3/4 8-34
- - , - -+ ,--,% gw-2 m e . , - - , . ,,y c.w.-g g--,ar-- e-. i----r ---a ,-y+-*w- ,r*--,, ..--.--,ci
, e -
y-.y-_ _ Attachment.3-b.. to U-601884 a
$ M'OY6 .hd iI6- (O ~
Q - LS-91-004. Page 101 of-127 TABLE 3.8.4.1-1-(Continued)- CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTEC VE DEVICES Auxiliary Building HCC 181 (1AP7 Location 105, X (R.C); El 781
- Each Compartment listed below has- o identical circuit breakers in ser' s. -
EQUIPMENT PENETRATION C0 SERVICE NUMBER 2C Cool Fan IEE06E-IVP01CB 3A Cool-Fan 1EE06E IVP01CD . tby ump 4A 1EE10E C001B 2A apr - IEE11E GO 4 2B Supply n. -1EE11E wv IVR11C
-T 9
4
-+4 m
O 9 9 CLINTON - UNIT 1 3/4 8-35 - i
.ii.w. , , . .
cw- - 6 884 a-
@O Yb LS-9 004 Pag- 102'of 127 TABt.E 3.8.4.1-1 (Continued)_ ,
CONTAINMENT PENETRATION C01400CTOR OVERCURRENT PROTECTIVE D.ICES Auxiliary Building MCC 182 (1AP76E) Location 106, V (R.C); El 781 ft Each Compartment listed below has two ide. tical circuit breakers in series. EQUIPMENT NETRATION C PT SERVICE NUMBER Isol Valve 11 - 1EE10E 1C41-F001B 2B Inlet Valve IEE10E 1CC068 , IB Inlet Valve IEE10E 10C065 2C tiet V ve IEE10E 1 70 - 2A . Out1 Valve IEE10E IC 6 4 0 '
' 10C Pool '1v IEE11E E12-F073 11B Isol Valve '
IEE11E ISXO95B 10A- Suct Valve .1EE11E_ 1HG0098 1 - Sup Pool Viv IEE11E
,1E12-F073B:
4B Spray Valve 1 11E
'1E12-F028B 10B- Upper Pool IEE11 Univ IE12-F037B u
I CLINTON - UNIT 1 3/4 8-36 4 _.____._____--____-___..__._______.__._.___._.__._,_______._._m.____-___-._..__.l______.___...__.__.____-.__________._-__,_______ _-__________m___.s
vvy ~
~
b';"Giikd Remove En+We Pace ' LS-91-004 Page 103 of 127 TABLE 3.8.4.1-1'(Continued)- CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE JEvlCES Auxiliary Building MCC IB3 (IAP77E) location-106, V (R C); El 781 ft
- Each Compartment listed below has two i entical circuit breakers in series, ',
EQUIPMENT- PENETRATION COMPT SERVICE NUMBER A~ Isol Valve IEE10E 10C050 2B Isol Valve' IEE10E ICC053
- 3B Isol Valv 1EE10E ICC071 3C IsolMye. 1EE10E 10C0 3A Valve - 1EE10E 060 s
4A Isol alve IEE10E '- - ICC12 4C Isol' Val 1EE10E 1CY017
~ '
SA Iso 1 ~ Valve IEE10E 1CYO20 Isol Valve -1EE10E-1FC007 SC Isol Valve IEE10E 1FC037
.10A
'Isol Valve
- EllE
-1E51-F063 14A RCIC Valve- -1EE1 E
.1E51-F076 .
10B Isol Valve '1EE11E . 1G33-F001 CLINTON - UNIT 1 3/4 8-37
, y yg.
Attachment 3 hdb[6-g@G6 _ A j _g 4]O
~
to U 601884a LS-91-004 Pag 104.of 127 TABLE 3.8.4.1-1 (Continued) CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE VICES Auxiliary Building MCC 183 (1AP77E) (Continu , EQUIPMENT PENET T10N COMPT SERVICE _ N ER. IOC Isol Valve 'l 1E 1G33-F028 Isol Valve IEEnE 1G33-F040 MB Isol Valve IEEIE ' 1G33-F053-8A Isol Valve IEE11E-IE12-F009 BC Spray Val 1EE11E
- E12-F04 7B I 1V ve IEEnE OM !
7C Is lve IEEnE
' 21-F 6-12B Isol Val - 1EEnE ISXO89B 13A- Is01 Valva 1EEnE ISX096B-13B Iso 1' Valve IEE11E IVQ006B Isol Valve IEE11E IIA 0138 14B Isol Valve EllE IWB001B 14C -Isol Valve IEE1 IWOOO2B
' ~
13C Isol Valve 1EE11E IVR002B
=
Ct.INTON - UNIT 1 3/4 8-38 4 a
-- -. - . . - - _ .. . . ~ . . _ , . . . - - . - - . - _ . . - - . . . -.- .
m .y ,v , Attachment 3
~
$ h6 h[)ff M 4 h to U-601884 a LS-91-004
)
4 Page 105 of 127
- TABLE 3.8.4.1-1 (Continued)
VICES CONTAINMENT PENETRATION CONDUC10R OVERCURRENT PROTECTIVE Auxiliary Building MCC 183 (1AP77E) (Continue EQUIPMENT PENET TION
- COMPT- SERVICE N - ER Isol Valve 1 1E ,
6A IFP052 6B Isol Valve IEE11E 1FP053 1 Isol Valve IEE11E 1FP079 uxiliary Buildin CC 184~(1AP94E) ocation 105,-X R.C); El 781 ft Each Comp tment 11 ed below has two identical rcuit enkers in series. 8C off Valve IEE11E - 4 . 1 0018-lt .
' - 9A Shut ff Valve IEE11E ISH00
. . ^
SB Is01 Va. e 1EE11E
- IFP050 7A Isol Valve - IEE11E IVP005A
' Isol Valve IEE11E
'1VP0058 ,
7C Isol Valve IEE11E IVP014A i 8A Isol Valve EllE L IVP014B I 1B IWO5528 1EE1
~
10A' 1WO551B 1EE11E 4 4 e CLINTON - UNIT 1 3/4 8-39 e
,.y-v-...-.---i ry -,,e,-,m-,--,,-,--w<--- ---,m.4m--e,--c..rme- m.--ww- .--,,y.. -.,<._,4-,-.--.<.* v.-.+p.r..v-r,+--,,yv-gr--yw-y er-++r- .-.*i---wm w-m w y 9ev+---
. - . - . ~ .
. - . - . _ - . - _ _ . . . - - ~ . . _ - - %ve En+ ire %Q ^ ~
4 ggy;yng; LS-91-004 Page 106 of 127 TABLE 3.8.4.1-1 (Continued)
- CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT FROTECTIVEVICE S --
Auxiliary Building MCC 1H (1AP95E) location 119, I.(R :C); El 762 ft Each Compartment listed below has two i ntical circuit breakers in series. . EQUIPMENT'- PENETRATION-CD T SERVICE NUMBER
- 70 Welding IEE03E '
1EWO2E ~ , 2C Supp Pool IEEOSE Fill Valve-ISM 004 3C RWCU 1EE05E WX01PA
^
2A U IEE05E-IG - 07 .) 3A R ;, IEE05E
. 1 6-C 1A- ~
7B onorail - IEE05E 1821-E300 7F Hatch Shield 1EE07E Door 1HC68G r 5A- Circuit 7 -1EE07E-1F42-E001L 6B . Refuel Plat IEEDSE 1F15-E003-4 4A- Air Hand Fan E07E IWOOSSF -
' 4B Air Hand Fan IEE0 IW2055H-40 Air Hand Fan IEE07E .
-1 WOO 55M 4C Air Hand Fan ,
IEE07E IW8055K CLINTON-UNIT 1l , 3/4 8-40 4 , I 0
.re--,-- ,,.wy,-- p , ,. rww -w-.nw 3- w -e-== +w-y= g----+ .--=- % , - + w e
-,hu -- .,. # -
e-e- +e., 3-- -r ww wr , . yr .
W 7-. ~
$YAOU$ b -
f( 84a LS-91-004 Page 107 of 127 TABLE 3.8.4.1-l'(Continued) CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT-PROTEC VE DEVICES , Auxiliary Building MCC 1H (1AP95E) (Con nued) EQUIPMENT- ENETRATION COMPT SERVICE NUMBER-30 Air Hand Fan IEE05E . 1 WOO 55B
. 6 011 Pump 1EE36E IB33-0003A
-2B Mixing Htr. IEE36E 1C41-D003 3B Tnk Htr - 1EE36E 1C41-D0 2 7A r IEE36E ,
IB 0003A
.- .7C ea olers IEE07E
, IEE07E
** IEE07E .
1EE07E
* -1EE07E-
, IEE07E 1EE07E 1EE07E
~
IB IVP090A 1EE05E-IVP091A 1EE05E , 10 1F15-E003EC E07E 7E 1F15-E003EA 1EE E
\
h 9B 4 CLINTON.- UNIT 1 3/4 8-41 D Ma -- -- . - . - . . - - -' - - -
~ .
. MOYb ~ h A 60 4a LS-91-004 Phge 08 of 127 TABLE 3.8.4.1-1 (Continued)
CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEV1 ES Auxiliary Building MCC II (1AP96E) ' t.ocation 167, I (R,C); El 762 f t Each Compartment listed below has tho ident al-circuit breakers in series-, . PE RATION EQUIPMENT. COM SERVICE _ UMBER 6C Welding EE04E 1EWO3E , 6B Welding IEE04E 1EV15EA thru EF IB rn Valve . 1EE06E
'l 3-F101 l-10 Tan Pump 1EE06E IWX0 B ,
6E Jib c . 1EE06E
,1HC6)G' ,
3B Fp Motor 1EE06E B33-0003B SC 011 Pump 1EE06E 1B33-0003B IC Precoat Pump IEE00E 1G36-C002 6F - Crane IEE06E 1833-E300 A Fan Motor 1 6E IWOOSSC SB Suct Valve IEE08 1G33-F106 SA Bypass Valve IEE08E - 1G33-F104 2B Fan Motor '1EE08E IWOOSSG CLINTON - UNIT 1 3/4 8-42 es mi . - in- - -
- . - . . -. . - - ..- - - _~ . _ . _. ~-
0 0-LS-91-004 ha Page.109 of 127 TABLE 3.8.4.1-1 (Continued) C0 TAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE / EVICES Auxiliary Building MCC 11 (1AP96E) (Contin d) ' EQUIPMENT PE RATION , C0 T SERVICE MBER 2C Fan Motor E08E IWOOSSJ 3A Fan Motor 1EE08E IWOO5SN 20 Fan Motor IEE08E 1WB05SL 6A ea Cooler IEE08E 1 055R 1EE08E IV SSS 1EE08E 1EE08E 1EE08E 1EE08E IEE08E IEE08E 125-V 0 CC 10 (IDC15E)
-Location 25, (3,C); El 781 ft ch compartment liste below has two. identical circuit break s in series.
EQUIPMENT PENETRATION COMPT SERVICE NUMBER 4C Emerg IEE04E Lighting ILL63E . 4 e CLINTON - UNIT 1 3/4 8-43 -
. . - = _ _ . - ._ . - = _ . .. - . . ..._. .- . . - - . . -
'"T' _-
, h% 6 k. A b 6 84a LS-91-004--
Page 110 of 127 TABLE 3.8.4.1-1 (Continued) 4 ONTAINHENT PENETRATION CONDUCTOR OVERCURRENT PROTECT - DEVICES DEVICE NU. R AND LOCATI0t
- 2. Type Switch r .
Polar Crane - Penet tionIE503E Penetration conductor s e 2-350MCM pe Unit Substation IA Compt. (R C)- 1 781 ft Primary Protection BBE Solid State Trip vice T S514 , Current Sens, 600A L.T. Setti 1.1 X TAP ST Setti 10 X TAP 5econdaryPro tion , West house Type CO-8 Relay , 6 9 4 I \ . t l e CLINTON - UNIT 1 3/4 8-44 y-4,, , , w .-..3 r..- ---.-,s, , -- _ , , - - , -v-. - -e y yy,a g, -
-.Tw- r --wv --
Attachment 3 to U-601884 a LS-91-004 Page 111 of 127 iri safh % @ en% wim @ ELECTRICAL P'0WER SYSTEMS hpa% device (s) .ntegrat Wim +he. rnetw hetec
" ^- -
'^-
MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION tIMITING CONDITION FOR OPERATION 3.B.4.2 The therrnal overload protec_ttort o.f_each valv n;.3 5 T.bT; 10. " . 2 . Shall _x=
- bt a :.1 bynassedLcontinuouslM3 A""G^F.E hp '_~d:; he !^t:;'_- 1 " tf W
'"~ ' " ' GZ Qt'M3'%cTipsyrpqhy {agperErros on acTfe_%aWQco% ' - -
APPLICABILITY: Whenever the motor operated valve is required to be OPETABLE.
- - _ - z _-
ACTION: _- efa\ds TEeQd9.ceen(Q ___ - ~ With the thermal overload protection fo. one o. more rf the aho e ired valves not bypassed continuousig:.._;r n r.. 1 E fa:R-O M _;;f ;. :;;
~
continuously bypass-thepthermal 3ver16ad' within 8'h6urs or~dellEFe Uie affected valve (s) inoperable and appiv the_anpropriate ACTION statement (s) for the affected system (s). ppe',(,p SURVEILLANCE REQUIREMENTS _ _
- Rin_mes_ owed safe 6 dWcHerM3D 4.8.4 2.1 The thermal overload protectionirot ne 2onv. mu,ren vuvg shall -
deler_ified to helyonssed corttindously y, ..,....m... .......... .,r... ...... L, .;; " yTa f ..... .... ....._.. f;!rl:L- :ntrt?= f t 4;rnd fr- t"n th:r 21
.... leed; t.i 7, .. . ..atin . ;l, type.;;d ;;d t;. e;r;.ril3 pl.nd"- t b;-
Srn :ni., g
~~I'~"} @ __ y O-_-L;.-_-_;A- & .
k .= _s ; h $ h i & Lt^^ =; & l -
- 4. _At least _ortet per _18 months (fe; the.; tl... ;l e..ileed; !. ;t. ;r un
{;.. .,.;', L,y!...; ..4 t.!p,....-ilj p h a d i , '; ;, .r.13 P.;. !!.. .;1 ,
=t n ;n und;. ph; p;rkdh ;r -i.t;r.;... 1...l.... , an d -
- b. Following maintenance on the motor starter.
. _4.8.4.2_2 - The t_hermal_ourlo_ad_protecti3n for _the above reauhd valves _
nN rf n r r:C % ":'-"C't-7:CrVp 5n f ' 1;.;_ n' _ : . N --
,.;16 ;;^er_ h_ .-A r;. '_n;_p;rtdh ; _x'-;;;nn 2-2.--isfiall be veri fied to Ve D 'paTsrn riowTng pe71cu)CormaIntTnalicelesT ng during which the thermal overload tection was temporarily placed in force.
A _ = _ a hhehn 6 CLINTON - UNIT 1 3/4 8-/ 2.(,
..a...u........am..a. m mm ...w.n a... . . . , _ . ...6
" Attachment 3 hMb b b . 04 Page 112 of 127 4
TABLE 3.8.4.2-1 MOTOR OPERATED VALVE'S THERMAL OVERLOAD PROTECT 70N BYPASS DIRECTION SYSTEM (S) AFFE ED VALVE NO. 1B21-F016 Continuous Close. Nuclear Boi r 1B21-F019 Continuous Close Nuclear Bo er Continuous Open/Close Nuclear iler 1821-F065A 1821-F065B Continuous Open/Close Nuclear oiler Continuous Close Nucle Boiler 1B21-F067A 1821-F0678 ontinuous Close Nuc1 r Boiler 1821-F067C ntinuous Close Nuc ar Boiler-1821-F0670 Co tinuous Close N ear Boiler IB21-F068 Con nuous Close clear Boiler 1821-F098A Conti uous Close uclear Boiler 1821-F09BB Contin us Close Nuclear Boiler 1821 r098C Continu s Close Nuclear Boiler 1B21-F0980 Continuou Close Nuclear Boiler Continuous Close Component Cool Water 1CC049 Continuous Close Component Cool Water ICC050 continuous Close Component Cool Water ICC053 Continuous close Component Cool Water ICC054 Continuous Close Component Cool Water ICC057 Component Cool Water ICC060 Continuous los
-Component Cool Water
(
. ICC065 Continuous _- -
C e Component Cool Water . ICC067 Cor)tinuous Continuous o Component Cool Water ICC068 Continuous lose Component Cool Water ICC070 Continuous Open/C se Component Cool Water ICC071 ICC072 Continuous Open/Clo . Component Cool Water Continuous Open/ Clos Component Cool Water ICC073 ICC074 Continuous Open/Close Component Cool Water ,,, Continuous Close . Component Cool Water ICC075A Continuou Close Component Cool Water ICC075B Continuo Close Component Cool Water ICC076A. . Contin s Close Component Cool Water ICC076B Conti ous Close- Component Cool Water-ICC127 Cont uous close sponent Cool. Water ICC128 ICY 016 C tinuous Close Cyc d Condensate. ntinuous Close Cyc1 Condensate ICYO17 ICYO20 Continuous Close Cycle Condensate Continuous Close- Cycled ndensate ICYO21 IC41-F001A Continuous Open Standby L1 uid Control IC41-F001B Continuous Open Standby.!.fq d Control i e C NTON - UNIT 1 3/4 8-46 .
, rx , ,
%hN h b 6 8 4a LS-91-004 Page 113 of 127 TABLE 3.8.4.2-1 (Continued) fj,0TOROPERATEDVALVESTHERMALOVERLOADPROTECTION BYPASS DIRECTION SYSTEM (S) AFFECTED VALVE ,
1E12-F003 Continuous- Open Residual Heat Remo 1 Residual Heat Re val. 1E12-F003B Continuous Open IE12-F004A Continuous Open/Close Residual Heat R oval IE12-F0048 Continuous Open/Close Residual Heat emoval ontinuous Open/Close Residual Hea Removal IE12-F006A Removal IE12-F0068 ntinuous Open/Close Residual He 1E12-F008 Co "inuous Open/Close Residual I at Removal 1E12-F009 Con'.' uous Close Residual eat Removal Conti ous Open/Close Residu Heat Removal IE12-F011A 1E12-F0118 Contin us Close Resid 1 Heat Removal' IE12-F014A Continuo O'en/Close p Resi al Heat Removal IE12-F0148 Continuou Open/Close Re dual Heat Removal 1E12-F021 Continuous Close idual Heat Removal. IE12-F023 - Continuous _Open/Close esidual Hea't Removal 1E12-F024A . Continuous Open/Close Residual Heat Removal 1E12-F024B' ' Continuous Open/Close Residual Heat Removal 1E12-F026A - Continuous lose Residual Heat Removal 1E12-F026B . Continuous se Residual Heat Removal 1E12-F027A 4.- Continuous Op /Close - Residual Heat Removal
~
1E12-F027B Continuous . Ope :los Residual Heat Removal IE12-F028A Continuous. Open $ e Residual Heat Removal.
,e Open/C' e Residual Heat Removal IE12-F028B Continuous
- 1E12-F037A Continuous Open/ o . Residual He'at Removal O 1E12-F037B Co'ntinuous Ope Clos Residual Heat Removal IE12-F040 Continuous C se Residual Heat Removal 1E12-F042A' Continuous i en/Close Residual Heat Removal 1E12-F042B Continuous pen /Close Residual Heat Removal.
1E12-F042C Continuous Open/Close ' Residual Heat Removal-IE12-F047A :r Continuous -Open esidual Heat Removal ! 1E12-F047B *
- Continuous Open idual Heat Removal IE12-F048A Continuous Open/Close Re
- dual Heat Removal
.1E12-F0488 - Continuou Open/Close Res al Heat Removal IE12-F049 -
Continuo Close 'Resid 1 Heat.Renoval 1E12-F052A Contin us Close Residu Heat Removal IE12-F0528 Conti ous Close Residual eat Removal 1E12-F053A Con nuous Open/Close Residual t t Removal. l L 1E12-5053B Co inuous Open/Close Residual He Removal , tinuous Open/Close Residual Hea emoval l L 1E12-F064A ! 1E12-F064C ontinuous Open/Close Residual Heat moval l 1E12-F064B Continuous Open/Close Residual Heat R oval l l 1E12-F068A Continuous Open Residual Heat Rem al i Open Residual Heat Remo 1 l 1E12-F068B Continuous 1E12-F073 Continuous Open/Close Residual Heat Remova l
- 1E12-F07 Continuous Open/Close Residual Heat Removal 4
CLINTON - UNIT 1 3/4 8-47
, . - - . - . - - - ., , ,w - . . - --, .- . . - - - , - . ,
.m - -
9emove EnBre % ce MnML'. LS-91-004
\
W ^ - Page 114 of 127 TABLE 3.8.4.2-1 (Continued) NOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION VALVE NO. BYPASS DIRECTION SYSTEM (S1 AFFECTED 1E12-F074A Continuous Open/Close Residual Heat Remov-IE12-F074B Continuous Open/Close Residual Heat Remo 41 Residual Heat Re, val
~
1E12-F087A Continuous Close 1E12-F087B ntinuous Close Residual Heat R . oval IE12-F094 C tinuous Open/Close Residual Heat emoval 1E12-F096 Con inuous Open/Close Residual Hea" Removal 1E12-F105 Cont uous Open/Close Residual He :. Removal Continu s Open/Close Low Pres te Core Spray IE21-F001 Low Pr sure Core Spray 1E21-F005 Continuo Open/Close Continuous Open/Close Low P ssure Core Spray 1E21-F011 Low ressure Core Spray 1E21-F012 Continuous Close
- IE22-F001 Continuous Oper/Close f gh Press Care Spray 1E22-F004 Continuous Open/Close igh Press Core Spray 1E22-F010 Continuous lose High Press Core Spray 1E22-F011 Continuous se High Press Core Spray 1E22-F012 continuous Op /Close High Press Core Spray 1E22-F015 Continuous Ope lose High Press Core Spray 1E22-F023 Continuous close . High Press Core Spray 1E32-F001A Continuous Close HSIV-Leakage Control System 1E32-F001E Con'tinuous Close HSIV-Leakage Control System IE32-F001J Continuous Clos . HSIV-Leakage Control System 1E32 F001N Continuous Cloj HSIV-Leakage Control System
.1E32 F002A Continuous C16se HSIV-Leakage Control System 1E32-F002E continuous ese . MSIV-Leakage Control System 1E32-F002J Continuous Close 4SIV-Leakage Control System 1E32-F002N Continuous Close IV-Leakage Control System 1E32-F003A Continuous' Close H V-Leakage control System 1E32-F003E Continuous close MS Leakage Control System 1E32-F003J Continuous Close HSIV eakage Control System 1E32-F003H Continuou Close HSIV-L kage Control System 1E32-F006 Continuo Close HSIV-Le age Control System 1E32-F007 Contini us Close HSIV-Leak e Control System Conti ous close HSIV-Leaka Control System 1E32-F008 1E32-F009 Con nuous Close HSIV-Leakage ontrol System 1E51-C002E ntinuous Open/Close Reac Core Isol ool 1E51-F010 ontinuous Open/Close Reac Core Isol 1 1E51-F013 Continuous Open/Close Reac Core Isol Co IE51-F019 Continuous Open/Close Reac Core Isol Cool 1E51-F022 Continuous Open/Close Reae Core Isol Cool l IE51-F031 Continuous Open/Close Reac Core Isol Cool 1E51-F0 Continuous Ooen/Close' Rene Core Isol Cool -
l 1E51-F Continuous Open/Close Reac Core Isol Cool CLINTON - UNIT 1 3/4 8-48
h W v v7 Attachment 3 d to 6 84 a 6[M d l Page 115 of 127 TABLE 3.b.4.2-1 (Continued) MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION VALVE _102 BYPASS DIRECT 15N SYSTEM ($) AFFE ED 1E51-F05. Continuous Open/Close Reac Core Is Cool IE51-F063 Continuous Open/Close Reac Core ' ol Cool IE51-F064 Continuous Open/Close Reac Core msol Cool 1E51-F068 Continuous Open/Close Reac Cor Isol Cool IE51-F076 Continuous Open/Close Reac C e Isol Cool IE51-F077 ontinuous Open/Close Reac re Isol Cool 1E51-F078 tinuous Open/Close_ Reae ore Isol Cool 1E51-F095 Co inuous Open/Close - Re Core 1501-Cool 1E51-C002E Cont uous Open/Close R c. core Isol Cool 1FC007 Continu s close uel Pool ' Cool & Clean IFC008 Continuo Close Fuel Pool Cool & Clean IFC011A Continuous Open/Close Fuel Pool Cool & Clean 1FC011B Continuous .Open/Close Fuel Pool Cool & Clean 1FC015A Continuous Open/Close Fuel Pool Cool & Clean
, IFC0158 , Continuous Open/Close - Fuel Pool Cool & Clean 1FC016A Continuous Close Fuel Pool Cool & Clean IFC016B Continuous 'l o s e... Fuel Pool Cool & Clean 1FC024A Continuous se Fuel Pool Cool & Clean 1FC024B Continuous C1 e Fuel Pool Cool & Clean
.(d
.1FCO26A Continuous Continuous Ope Ope / ose lose Fuel Pool Cool ~& Clean fuel Pool Cool & Clean 1FC026B IFC036 Continuous C1 se Fuel Pool Cool & Clean 1FC037 Continuous - ose- Fuel Pool Cool & Clean 1FP050 Continuous close- Fire Protection-IFP051 Continuous Close Fire Protection-IFP052 Continuous Close- Fire Pratection -
IFP053 Continuous close Fire Protection 1FP054 Continuous Close- tre Protection 1FP078 Continuou! Close e Protection ' 1FP079 Continuo a Close Fi Protection 1FP092 Contin us Close- Fir rotection 1G33-F001 Cont- uous Close React Cleanup IG33-F004 Con ,nuous .Close React Wt Cleanup 1G33-F028 C tinuous Close- React Wtr leanup 1G33-F034 ntinuous Close React Wtr C anup IG33-F039 ' ontinuous Close React Wtr C1 up 1G33-F040 Continuous Close React Wtr Clea p IG33-F053 Continuous Close React Wtr Clean 1G33-F054 Continuous Close- React Wtr Cleanup 1HG001 Continuous Open H2 Recombining-1HG004 Continuous Open/Close H2 Recombining 1HG005 ' Continuous Open/Close H2' Recombining 1HG00 Continuous Open/Close H2 Recombining 3 '
\
\ '
CLINTON - UNIT 1 3/4 8-49
. ~ ,
2%%;;";s'e Bemove En+WeTa9e ' LS-91-004 Page 116 of.127 TABLE 3.8.4.2-1 (Continued) MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION VALV NO.. . BYPASS DIRECTION SYSTEM (S) AFFt'CTED Continuous Open/Close H2 Recombining 1HG009A 1HG009B Continuous Open/Close H2 Recombinin 11A012A Continuous Open/Close Instrument r
.11A012B Continuous Open/Close Instrumen Air 11A013A Continuous Opeh/Close Instrume Air 11A013B ntinuous Open/Close Instru t Air 0MC009 Con ' nuous Close Make p Condensate Storage OMC010 . Cont' uous Close Ma Up Condensate Storage 1SF001 ' Continu s close ppression Pool & Cleanup 1SF002 Continuou Close uppression Pool & Cleanup ISF004 - Continuous close Suppression Pool & Cleanup ISM 001A Continuous Open -
Suppression Pool Makeup ISM 001B Continuous - Open- Suppression Pool. Makeup 1SM002A Continuous Open Suppression Pool Makeup ISM 002B Continuous en - Suppression Pool Makeup
-ISX003A Continuous Op Shutdown Service Water ISX003B Continuous Open Shutdown Service Wate'r 1SX003C Continuous Op Shutdown Service Water-
~
T ISX004A Continuous O n Shutdown Service Water ISX004B Continuous ) en Shutdown Service Water ISX004C Continuous ) pen Shutdown Service Water ISX006C- - Continuous Open . Shutdown' Service Water ISX00BA Continuous Open/Close -Shutdown Service Water 1SX008B Continuous Open/Close- Shutdown Service Water ISX008C Continuous ' Open/Close Shutdown' Service Water ISX011A Continuou Open/Close hutdown Service Water ISX011B Continuo Open/Close tdown Service Water ISX012A Contir s Open/Close Sh down Service Water 1SX012B Conti oos Open/Close Shut wn Service Water l Open/Close Shutd n Service Water l -- ISX0130 Cont uous-1SX013E Co nuous Open/Close . Shutdo Service Water l ISX013F C tinuous Open/Close Shutdown ervice Water l Shutdown tvice Water ! 1SX014A ntinuous Close 1SX014B ontinuous Close Shutdown Se ice Water ISX014C Continuous Close Shutdown Ser 'ce Water Continuous Open/Close- Shutdown Servi Water ISX016A ISX016B Continuous Open/Close Shutdown Servic Water 1SX017A Continuous' Open/Close Shutdown Servh:e ter ISX017B Continuous Open/Close Shutdown Service W er CLINTON - UNIT'l 3/4 8-50 4
,_.,-,s...., -...-m.-..mr,-ye--,. ,4. m,-,-m_.,-e ,- r w~ y , m ,~.n-y <'e.g.-,.g, ,. % ,,,. , .,--# w
<- ~ v Bemove EnWeTage- ngm,';
LS-91-004 Page 117 of 127 TABLE 3.8.4.2-1 (Continued) MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION DIRECTION SYSTEM (S) AFFECT VALVE NO. BYPA5s close Shutdown Serv Water ISX020A Conti uous ice Water Continuens Close Shutdown Ser ISX020B Shutdown Se vice Water ISXO62A ntinuous Ooen/Close C tinuous Open/Close Shutdown rvice Water 1SXO62B ervice Water Con inuous Open Shutdow ISXO63A Service Water Cont uous Open Shutdo ISXO63B n Service Water Contin us Open/Close Shut
.1SXO71A 1SX0718 Continu s Open/Close Shu own Service Water 1SXO73A Continuot, Open/CJose Sh down Service Water e utdown Service Water ISX0738 Continuous Open/Close Continuous Open/Close hutdown Service Water ISX074A Continuous Open/Close Shutdown Service Water ISXO748 Continuous Open/Close Shutdown Service Water ISXO76A 1SX076B Continuous Open/Close Shutdown Service Water ISX082A Continuous lose Shutdown Service Water 1SX0828 Continuocs se Shutdown Service Water
-ISX088A Continuous Op /Clo '
Shutdown Service Water ISXO888- Continuous Ope C1 e Shutdown Service Water ISX089A Continuous Open ose Shutdown Service Water Continuous Ope , se Shutdown Service Water w ISX089B
. Shutdown Service Water ISXO95A Continuous Op ISX095B Continuous 0 n Shutdown Service. Water
- ISX096A Continuous pen /Close Shutdown Service Water Continuous Open/Close Shutdown Service Water
, ISXO968 1SXO97A Continuous Open/Close Shutdown Service Water Continuous Open/Close Shutdown Service Water ISX097B continuous Open/Close Shutdown Service Water .
ISX105A ISX105B Continuous Open/Close lutdown Service Water Continuo Open/Close' S tdown Service Water ISX107A ISX107B Continu s Open/Close Shu own Service Water ISX173A Conti ous Open/Close Sht wn Service Water-Cont" uous Open/Close Shu,tdo Service Water ISX173B Co ,nuous Open/Close Shutdow Service Water 2SX076A C tinuous Open/Close Shutdown ervice. Water 2SX076B 2SX107A ntinuous Open/Close Shutdown-S vice Water 2SX107B Continuous Open/Close- Shutdown Se ice Water IVP004A Continuous Close Drywell Coolin - Plant Chilled Water IVP004B Continuous Close Drywell Cooling - lent Chilled Water , 9 CLINTON - UNIT 1 3/4 8-51
\ ' e L,, -. . . . . , , , , . . . . . , . -
- y. -, . .
Bemova En+1Yt Tye- 2";'.7 nL
'
- LS-9l-004 A
- _ E-Page 118 of 127 1ABLE 3.8.4.2 1 (Continued)
HOTOR__0PERATED VALVES THERMAL OVERLOAD PROTECTION DIRECTION SYSTEM ($) AFFE D VALVE l DYPASS IVP005A Continuous Close Drywell cool g - Plant Chilled Wat IVP005B Continuous Close Drywell C ing - Plant Chilled ter IVP014A .ontinuous Close Drywel cooling Plant Chill Water IVP014B C tinuous Close D 11 Cooling - Plant Ch led Water ( IVP015A Cont uous Close ell-Cooling --Plant
- hilled Water IVP015B Continu s , close Drywell tooling - Plant Chilled Water IVQ006A Continuous Close Drywell Purge - Contain HVAC Continuous Close Drywell Purge - Contain HVAC 1YQ006B IVR002A Continuous Close Drywell Purge - Contain HVAC IVR0028 Continuous lose Drywen Purge - Contain HVAC IW0001A - Continuous C '!
. DryweV Cooling - Plant 1 "
1 Chilled Water IW0001B Continuous os - ,Drywell Cooling - Plant '
. Chilled Water 1W0002A Continuous close Drywell cooling - Plant .
Chilled Water IV0002B Continuous Close Dry' ell Cooling - Plant Chilled Water 1WO551A Continuo Close Drywell Cooling - Plant Chilled Water
- 1WO551B Conti us Close rywell Cooling - Plant illed Water 1WO552A C tinuous Close Dry 11 Cooling - Plant Chil d Water 1WO552B ontinuous close Drywe cooling - Plant Chille ater s
f C 8 1 CLINTON - UNIT 1 3/4 8-52 4 4 g- ,
Attachment 3 t o U+601884 a LS-91-004 Page 119 of 127 ELECTRICAL POWER SYSTEMS REACTOR PROTECTION SYSTEM ELECTRIC POWER HONITORING L1HITING CON 0lT10N FOR OPERATION
. 3.8.4.3 One RPS electric power monitoring channel for each inservice RPS special solenoid power supply or alternate power supply shall b'g OPERABLE.
APPLICABILITY: At all times. . ACTION: With the RPS special solenoid electric power monitoring channel for an inser-
+ vice RPS special solenoid power supply or alternate power supply inoperable, restore the power monitoring channel to OPERABLE status within 30 minutes or remove the associtred R?S specta) solenoid power supply or alternate power supply f rom service.
SURVEILLANCE REQUIREMENTS 4.8.4.3 The above specified RPS special solenoid electric power monitoring channels sha11 be determined OPERABLE: ,
- a. At least*once per six months by performance of a CHANNEL FUNCTIONAL TEST, and
- b. At least once per 18 months by demonstrating the OPERABILITY of over-voltage, undervoltage and underfrequency protective instrumentation by performance of a CHANNEL CALIBRATION including simulated automatic actua- ;
i tion of the protective relays, tripping logic and output circuit breakers and verifying the following setpoints. , EPA-INVERTER A EPA-!NVERTER B
- 1. Overvoltage < 134.2 + 0,-3 VAC < 133.6 + 0, - 3 VAC Undervoltage I 114.2-0, + 3 VAC I 113.2 - 0, + 3 VAC
- 2. .
- 3. Underfrequency E 57 - 0 + 1.2 Hz i 57 - 0 + 1.2 Hz t
t t e em _m CLINTON - UNIT 1- 3/4 8 27 . _ . = s
Attachment 3 to U 601884 a LS-91-004 Page 120 of 127 INSTRUMENTATION BASES 3/4.3.7.11 MAIN CONDENSER OFFGAS TREATMENT $YSTEM EXPLOS!VE gas HONITORING INSTRUMLNTATION The main condenser offgas treatment system explosive gas monitoring instrumen-tation is provided to monitor and control the concentrations of potentially explosive gas mixtures in.the main condenser offgas treatment system. ;
~
The intent 'of the
- note attached to the CHANNEL CAllBRATION requirement is to !
specify that the CHANNEL CALIBRATION is to be performed using at least two separate gas samples of different, specific hydrogen concentrations
' appropriate for the sensor range. The balance of the sample cas mixture (normally nitrogen) is not necessarily restricted purely to nitrogen but must be in accordance with the requirements or recommendations provided by the manufacturer of the explosive gas monitoring instrumentation.
3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM T9.: Th eta;pnifh;thr. h ernid;d t: =nr;'th:t th; t;;t5.; [.;;;had p..t ;7.. p
- y:t r ' :trr ::t:th: ::d th: tud!:: :;nd :ntc;; .;i. ; ac, ^,":,t";.: ..,J !
ill pretut th. t;; tin fre;,;n;nin :nr; pud. .aretathr 77;.. t.ctir., ' f a n n k; n;.;; n d h n;;in d ; k n u n ;;h; e. r;p;;d ef tl,, t .;,;,,, s. J u
> an;nu p;tathitj I:n -
(nhud::;n:c.t.;;; ipa;h;:h:th;d.Sh;widSpnt...d4...;,,ef,;,- c.; ;r ;trat;ca. _ 3/4.3.9 PLANTSYSTEMSACTUATIONINSTRUMENTATION The plant systems actuation instrumenttition is provided to initiate action to mitigate the consequences of accidents that are beyond the ability of the opera-tor to control. The LPCI mode of the RHR system 1F automatically initiated on a high drywell pressure signal and/or a low reactor water level.-level 1, signal. The containment spray system will then actuate automatically following high drywell and high containment pressure signals. Negative bar: metric pressure i 8 3/4 3 8 . /cendment No.40 CLINTON - UNIT 1 e
Attachment 3 to U 601884 a d LS-91 004 i Page 121 of 127 l REACTOR COOLANT SYSTEM BASES
- 3/4.4.6 PRES $URE/ TEMPERATURE LIMITS (Continued)
The reactor vessel materials have been tested to determine their initial RT NDT' The results of these tests are shown in Table B 3/4.4.6-1. Reactor operation and resultant fast neutron (E greater than 1 HeV) Irradiation will cause an increase in the RT HDT of the core beltline region. Therefore,anadjusted reference temperature based upon the fluence, nickel content and copper coa-tent of the material In question, can be predicted using Regulatory Guide 4.W.
" Radiation Embrittlement of Reactor Vessel Materials," Revision 2. Hay 1988.
The pressure /nmperature limit curve, Figure 3.4.6.1-1, curves A, B - and C, includes an as amed shif t in RT NDT for the conditions at 12 Effective Full ] Power Years. The actual shift in RTNDT of the vessel material will be estab- ] lished periodically during operation by-removing and evaluating,' in eccordance i with specimensASTH installed E185 and oear 10the CFR 50,inside wall of the reactor vessel in the coreAppendix iH area. The irradiated specimens can be used to predict reactor vessel material transition temperature shift. Flux wires which were removed after the first fuel cycle and will be removed at later intervals with the survelliance speci-mens are analyzed and provide an improved neutron fluence estimate for the reactor vessel. This data is then used to modify Bases Figure B 3/4.4.6-1 and predictions of reactor vessel material transition temperature shift per Regu- , latory Guide 1.99, Revision 2. The operating limit curves of Figure 3.4.6.1-1 > have been and will be~ adjusted, as required, on the basis of the specimen data and the recommendations of Regulatry Guide 1.99, Revision 2. , The pressure-temperature limit. lines shown in Figures 3.4.6.1-1, curves C and A for reactor criticality and for inservice leak and hydrostatic testing-have . been provided to assure compliance with the minimum temperature requirements of i Appendix G to 10 CFR Part 50-for reactor criticality and for inservice' leak and > hydrostatic testing, j i Th; - M ;r Of r:n ter = n:1 ' r d!at'^r tem!'hre =p=h: =d th: f r:;;=-
- ;h: f;r r==bg =d tuth; th: :;n' = '-th= n;;;h: Ar; pr=id;d '-
3 Q ','.C.1-1 t: n;;r: ;m' br.;; . tth th; 7;;;f r=xt; ef "+p=di, : te . l
-mn - - = _
3/4.4.7 HAIN STEAM LINE ISOLATION VALVES Double isolation valves are provided on each of the main steam lines to minimite the potentialilcakage paths from the containment in case of a line break. Only. one valve in each line is required to maintain the integrity of the containment;_ ' however, single failure considerations require that two _ valves be OPERABLE.
' The surveillance requirements are based on the' operating history of this type valve. The maximum closure time:has been selected to contain fission products ;
and to ensure the core is not uncovered.following line breaks. The minimum-closure time is consistent with the assumptions in the safety analyses to prevent' pressure surges. CLINTON - UNIT 1 B_3/4 4-6 Amendment No. 51
- - - ~
t 'FY-tM 7 e1 'TWTT? y W e M=n y M"1Wtie==-< rv sgle :#V Tur=T*-' EuMr*-$ M es y Jt'w"*'ryg--R-T'eg-g --* Ff'*Fuhre-* $ -p- Fyrt*P'm+-Sl2'* ? 'e T - T t9 4$s V--r?Y*g-f6 >Tg%,% 9 g w ig.y y-' P-M TB4 Wy y'T "T"'T ' M'T '4**-vT"T'M-*'T
Attechment 3 to U 601884 a LS 91-004 Page 122 of 127 CONTAINMENT SYSTEMS BASES 3/4.6.1.4 MSIV LEAKAGE CONTROL SYSTEM Calculated doses resulting from the maximum leakage allowance 'for the main stream line isolation valves in the postulated LOCA situations would be a small fraction of the 10 CFR 100 guidelines, provided the main steam line system from the isolation valves up to and including the M$1V LCS motor operated boundary valve remains intact, Operating experience has indicated that degradation has occasionally occurred in the leaktightness of the MSIV's such that the specified leakage requirements have not always been maintained continuously. .The require-ment for the leakage control system will reduce the untreated leakage from the HSIV's when isolation of the primary system and containment is required. 3/4.6.1.5 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the unit. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 15 psig in the event of a steam line break accident. A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability. , 3/4.6.1.6 CONTAINMENT INTERNAL PRESSURE . The-limitations on' containment to secondary containment differential pressure , ensure that the containment peak calculated pressure of 9.0 psig does not exceed the design pressure of 15.0 psig during design basis steam line break conditions or that the external pressure differential does not exceed the design maximum external pressure differential of 3.0 psid. The limit of -0.25 to +0.25 psid for initial containment to secondary containment pressure will limit.the containment pressure to 9.0 psid which is less than the-design pressure and is consistent with the safety analysis for containment design pressure. 3/4.6.1.7 PRIMARY CONTAINMENT AVERAGE AIR TEMPERATURE The limitation on containment average air temperature ensures that the contain-ment peak air temperature does not exceed the design temperature of 18
- uring st*am 11- 3 b.rea_k eonditions and_14 eoneintanL whh 1he sa_fety an_alysis_. "Ihe containm:nt average'evJ +cmeernium h 'deiermined b3whe. arWmcEcd cCvera$c cf 4he readin$$ fr m eight ecenment o'.c 4emeendose insrements.,ba \n each
, quadrant c4 4be conkinment.'the (Wefage should conste of ni le<5+ ene readin3 km .'
eo,ch quadrant. Houaever, nu AvAMAbit in$tt9,6mts Shouid be, used 'in deierm'ining 4ke ce.ntainment avern3e cc.c +empergio<v. _
+
[ CLINTON # UNIT 1 - B 3/4 6-2
l Attachment 3 to U-601884 a LS-91-004 CONTAINMENT SYSTEMS "*" " 3 # # BASES 3/4.6.2.4 DRYWELL STRUCTURAL INTEGRITY This limitation ensures that V $ . 'uctuaal integrity of the drywell will be maintained comparable to the -igiN n'gn anecification for the life of the unit. A visual inspection in n % r w A ' ype A leakage tests is suffi-cient to demonstrate this capa N y 3/4.6.2.5 ORWELL INTERNAL PRESSURE The limitations on drywell-to-containmeat differential pressure ensure that the drywell peak calculated pressure of 19.'/ psig d6es not exceed the design pressure of 30.0 psig and that the containment pea ( pressure of 9.0 psig does not exceed the design pressure of 15.0 psig during steam line break conditions.- The maxi-mum external drywell pressure differential is limited to 0.2 psid, well below the pressure at which su)pression pool water will be forced over the wier wall and into the drywell. Tie limit of 1.0 psid for initial positive drywell to' containment pressure will limit the drywell-pressure to 19.7 psid which is less
- than the design pressure and is consistent with the safety analysis to limit drywell internal pressure.
3/4.6.2.6 ORYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that peak drywell temperature does not exceed the design temperature of 330'F during LOCA condi-tions and is consistent with the safety analysis., 3/4.6.2.7 DRYWELL VENT AND PURGE The drywell purge system must be normally maintained closed to eliminate a potential challenge to containment structural integrity due to a steam bypass of the suppression pool. Intermittent venting of the drywell is allowed for pressure control during OPERATIONAL CONDITIONS 1, 2, and 3, but the cumulative time of venting is limited to 5 hours per 365 days. Venting of the drywell is prohibited when the 12-inch continuous containment purge system or the 36-inch containment building ventilation system supply or exhaust valves are ogen. 1his eliminates any resultant direct leakage path from the drywell to t e environment. . 4 In-0PERATIONAL CONDITIONS 1 2 and 3 the drywell isolation valves (IVQ002, IVQ003)'have permanently ins,talled blocking devices so as not to open more than 50 .- This assures-that the valve would be able to close against drywell pressure buildup resulting from a LOCA. Operation of the drywell vent and purge 24-inch supply and exhaust valves during-plant operational conditions 4 and 5 is unrestricted, and the cumulative time for ve}nt and purge operat_ ion _is_ unlimited. _ _ The dryen ave < age nic +<msecatvre. is deteerninedyb *we arawmia;w average. et 4we. feaa:" weil etmu We av$5 erageC<ern sbound N drawen contar aic et n+ icast 4empeenhvre. ene read \n adwe. tneroments wooid be. used in dewemijn3 4we. oc3 wen Instrornents, No cd each gn deNrn each c
,yenaoec, LINTON - NIT 1 B 3/4 6-5 Amendment No.18 4
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Attachment 'l to U 601884a LS-91-004 Page 124 of 127 CONTAINMENT $YSTTMS BASES 3/4.6.3 DEPRESSURIZATION SYSTEMS (Continued) The suppression pool cooling function is a mode of the RHR system and functions as part of the containment heat removal system. The purpose of the system is to ensure containment integrity following a LOCA by preventing excessive con-tainment pressures and temperatures. The suppression pool cooling mode is designed to limit the long term bulk temperature of the pool to 185'F consider-ing all of the post-LOCA energy additions. The suppression pool cooling trains, being an integral part of the RHR system, are redundant, safety-related component systems that are initiated follow!ng the recovery of the reactor vessel water level by ECCS flows from the RHR system. Heat rejection to the standby service water is accomplished in the RHR heat exchangers. The suppression pool make-up system provides water from the upper containment pool to the suppression pool by gravity flow through two 100% capacity dump lines following a LOCA. The quantity of water provided is sufficient to account for all conceivable post-accident entrapment volumes, ensuripg the long term energy sink capabilities of the suppression pool and maintaining the~ water cover-age over the uppermost drywell vents. The minimuin freeboard distance above the suppression pool high water level to the top of the weir vall is adequate to During preclude flooding of the drywell in the event of an inadvertent dump. refueling, neither automatic nor manual action can open the make-up dump valves. 3/4.6.4 CONTAINMENT !$0LATION VALVES The OPERABILITY of the containment isolation valves ensures that the contain-ment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressuriza-tion of the containment and is consistent with the requirements of GDC 54 through 57 of Appendix A to 10 CFR 50 "and the requirements of NUREG-0660 as clarifiedbyNUREG0737asdescribedintheFSQ, Appendix 0,itemII.E.4.2 (Containment Isolation Dependability)."(IW5a)T M'easurement o'f the closure time of automatic containment isolation valves is
~
performed for the purpose of demonstrating PRIMARY CONTAINMENT INTEGRITY and system OPERABILITY (Specification 3/4.6.1). The Maximum Isolation Times (MIT) for primary containment automatic isolation valves listed in this specification are either the analytical times used in the accident analysis; described in the FSAR; or times derived by applying margins to the test data obtained by performing testing in accordance with Forthe Inservice Testing program (IST) outlined in Section XI of the ASME Code. non-analytical automatic primary containment isolation valves, the* HIT is de-rived as follows:
- 1) Valves with full stroke times less than or equal to 10 seconds, MIT = Initial Base Line Time X 2
- 2) Valves with full stroke time greater than 10 seconds, MIT = Initial Base Line Time X 1.5.
CLINTON - UNIT 1 B 3/4 6-7 L
l
- Attachment 3 '
to U.601884a 13 91 004 Page 125 of 127 Insert for var.c B 3/4 6 1 OPERABILITT of the automatic containment isolation valves which isolato the j reactor water cleanup systein auction containment penetration is also ' required in OPERATIONAL CONDITION $ with any control rod withdrawn to I ensure that, in the event initiation of the standby liquid control systeta - becomes necessary, the sodium pentaborate solution is not removed from the reactor coolant systern. The requirements for OPERABIL11T of these valves agree with those conditions for which the standby liquid control system is required to be OPERABLE per Specification 3/4.1.5. The opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations (1) stationing an operator, who is in constant communication with the control room, at the valve controls. (2) instructing this operator to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.
.-,A
Attachment 3 y to U-601884a 1.S-91-004 No C6n3es.%.s p%e poy n6 of m
*per.cl ec9 io r Cc40,no i % .
ELECTRICAL POWER $YSTEMS I ests 3/4.8.1 3/4.8.2, and 3/4.8.3 'AC $0VRCES. DC $00RCES, AND ON$llE POWER DT5TRid> TION SYSTEMS (Continued) The survei,11ance requirements for demonstrating,the OPERABIL11Y'of the Unit i batteries are in accordance with the recommendations of Regulatory Guide 1.1$9
" Maintenance Testing 'and Replacement of Large Lead Storage Batteries for Nuclear Power Plants," February 1978. Regulatory Guide 1.32 "Criterla for Safety-Related Electric Power Systems for Nuclear. Power P.lants," February 1977, IEEE Std 450-1975, "IEEE Recommended Practice for Haintenance Testing, and Replace-ment of Large Lead Storage Batteries for Generating Stations and Substations."
and IEEE Std 308-1974 "lEEE standard Criteria for Class 1E Power systems for Nuclear Power Generating stations" with exceptions noted in tk CPS-FSAR. Verifying average elect'rolyte temperature above the minimum for which the battery was sized, total battery terminal voltage on float charge, connection resistance values and the performance of battery service and discharge .ttsts ensures the fectiveness of the charging system, the cbtlity to handle high discharge rates ef,d an compares the battery capacity at that time with the rated capacity. Table 4.8.2.1 1 specifies the normal limits for e'ach designated pilot cell and each connected cell for electrolyte level, float voltage and specific gravity. The limits for the designated pilot cells float voltage and specific gravityIc greater than 2.13 volts and .015 below the manufacturer's full charge specif gravity or a battery charger current that had stabilized at. a low value, is characteristic of a charged cell with adequate capacity. The normal limits for each connect 6d cell for float voltage and, specific gravity greater than 2.13 volts and not more than $020 below the manufacturer's full charge specific gravity with an average specific gravity of all the connected cells not more than .010 below the manufacturer's full charge' specific gravity, ensures the OPERA 0ll!1Y and capability of the battery. Operation with a battery cell's parameter outside.the normal limit but within the allowaDie value specifito in TaDie 4.0.2.1-1 is permitted for up to 7 cays. During this 7 day period: (1) the allowable values for electrolyte level ensures no physical damage to the plates with an adequate electron transfer capability; (2)theallowablevaluefortheaveragespecificgravityofallthecells,not more than .020 below the manufacturer s recommended full charge specific gravity ensures that the decrease in rating will be less than the safety margin provided in sizing; (3) the allowable value for an individual cell's specific gravity ensures that an individual cell's specific gravity will not be more than .040 below the manufacturer's full charge specific gravity and that the overall capability of the battery will be maintained withien an acceptable limit; ano (4) the allowable value for an individual cell's float voltage, greater tha.. 2,07 volts, ensures the battery's capability to perform its desigrr function. 3/a.8.a Et!CTRICAL EOUIPMENT PROTECTIVE DEVICES Containment electrical penetrations and penetration conductors Fe protected by demonstrating the CPERABILITY of primary and backup overcurrent protection CLINTON
- UHli 1 B 3/4 8 2 l
l (
Attachment 3 to t!-601884n
- LS-91-004 Page 127 of 127 (LECTRICAL TMR $YSTEMS pASES
'3/4.8.4 fl[CTRICAL[QUltM(NTPROTICTIVEDEVICES(ConUnved)
The surveillance requirements circuit applicablebreakers by periodic to lower voltage surveillance.f(s circuit breake provides assurance.of breaker reliability by testing at least.one representative sample of each manufacturer's brand of circuit breaker. Each manufacturer's molded case and metal case circuit breakers are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers are tested. If a wide variety exists within any manufacturer's brand of circuit breakers, it is necessary to di' vide that manufacturer's breakers into groups and treat each group as a separate type of breaker for survelliance purposes. The bypassing of the motor-operated valv'es thermal overload protection contin-vously ensures ihnt the thermal overload protection will not prevent safety-related valves fre f.erforming their function. The Surveillance Requirernents for demonstrating the bypassing of the thermal overload protection continuously c are in accordance with Regulatory Guide 1.106 " Thermal Overload Protection for Electric Motors on Motor-Operated Valves,", Revision ~ l', March 19,77. The reactor protection system (RPS) electric power monitoring assemblies provide protection to the RPS and other systems which receive power from the RPS buses by acting to disconnect the RPS from the power source in the presence of an electrical fault in the power supply. 0 fr ^ &- r v n - , --
%C Io@ *Efetlutrq rnoier ynendor set clcctriced -powef Spphg io ibe. (entior rec'irtutAHon pornp6 In pro &ied talh one, overcorrent proteLuon c1fcWit bro *ec since 3%e. needeth rnulmurn ootput urwter Edit CordM006 M ICSS 9han 4 C y&DthtdOM b6 0 fM.$*
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