ML20086N221
| ML20086N221 | |
| Person / Time | |
|---|---|
| Site: | 05000605 |
| Issue date: | 12/13/1991 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20086N219 | List: |
| References | |
| NUDOCS 9112190171 | |
| Download: ML20086N221 (47) | |
Text
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Amendment 19 Page change instruction The following pages have been changed, please make the specified changes in your SSAR. Pages are listed as page pairs (front & back). Hold page nurnbers represent a page that has been changed by Amendment 19.
REMOVE ADD REMOVE ADD PAGE No. PAGE No. PAGE No. PAGE No.
CIIAPTER 1 CllAITER 18 1.2-i:.,iii 1.2 11,111 18A.41 15 1BA.41 15 1.2iv,v 1.2-Iv,v 18A.5-1 18A.5-1 23 1.2-vila,viii 1.2 vila, vill 18A.6-1 18A.61 12 1.2-ix 1.2-It 18A.71 18A.7-1 1.2 46,47 1.2-46,47 18A 81 18A.81 5 1.2-48,49 1.2-48,49 18A.9-1 3 18A.9-1 3 1.2-50,51 1.2-50,51 18A.11 1 18A.11 1 8 1.2-52,53 1.2 52,53 18A.121 7 18A.12-1 7 18A.13-1 18A.13-1 3 1.8-53,54 1.8-53,54 1SB 23 18B.2 - 24 Add 1.8 54.1 CilAITER 19 IO CllAITER 5 19N COVER 19N COVER 5.2-33,34 5.2 33,34 19N.5 5 19N.5-1 5 CilAITER 6 CilAITER 20 6.14,5 6.14,5 20.3-351.29 20.3-354.28 6.1-6,7 6.1 6,7 CilAITER 9 9A.41 - 271 9A.4-1 271 CilAITE.R 11 11.5-iv 11.5-Iv 1
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i c- ABWR awmac Standanti Plant nt>v. c SECTION 1.2 o
U CONTENTS Section Title Page 1.2.1 l'rincloal Desien Criterla 1.2-1 1.2.1.1 General Design Criteria 1.2-1 1.2.1.1.1 Power Generation Design Criteria 1.2-1 1.2.1.1.2 Safety Design Cri:eria 1.21 1.2.1.2 System Criteri- 1.2-3 1.2.1.2.1 Nuclear System Criteria 1.2-3 1.2.1.2.2 Electrical Power Systems Criteria 1.2 4 1.2.1.23 Auxiliary Systems Criteria 1.2-4 1.2.1.2.4 Shielding and Access Control Criteria 1.2-4 1.2.1.2.5 Process Control Systems Criteria 1.2-4 (3I
.w 1.2.1.2.5.1 Nuclear System Process Control Criteria 1.2-4 1.2.1.2.5.2 Electrical Power System Process Control Criteria 1.2 4 1.2.1.2.53 Power Conversion Systems Process Control Criteria 1.2-5 1.2.1.2.6 Power Conversion Systems Criteria 1.25 1.2.2 Plant Description 1.2-5 1.2.2.1 Site Characteristics 1.25 1.2.2.1.1 Site L.ocation 1.2 5 1.2.2.1.2 Description of Plant Emirons 1.2-5 1.2.2.1.2.1 Meteorology 1.2-5 1.2.2.1.2.2 Hydrology 1.2-5 1.2.2.1.23 Geology and Seismology 1.2-5 1.2.2.2 General Arrangement of Structures and Equipment 1.2-5 1.2-il Amendment 7
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ABWR ==c Standard Plant re c SECTION 1.2 $
CONTENTS (Continued)
St.etion Title Enge 1.2.23 Nuclear Systems 1.2-5a 1.2.23.1 Reactor Core and Control Rods 1.2 5a 1.2.23.2 Reactor Vessel and Internals 1.2 6 1.2.233 Reactor Internal Recirculation Pumps 1.2-6 L2.23.4 Residual Heat Removal System 1.2-6 1.2.23.5 Reactor Water Cleanup System 2.2-6 1.2.23.6 Leak Detection and isolation System 1.26 1.2.2.4 Nuclear Safety Systems 1.2 7
? 2.2.4.1 Reactor Protection System 1.2-7 1.2.2.4.2 Neutron Montoring System 1.2-7 g
1.2.2.43 Control Rod Drive System 1.2-7 1.2.2.4.4 Control Rod Drive Housing Supports 1.27 1.2.2.4.5 Control Rod Braking Mechanism 1.27 1.2.2.4.6 Nuclear System Pressure Relief System 1.2-7 1.2.2.4.7 Reactor Core Isolation Cooling Syste.n 1.2-7 1.2.2.4.8 Emergency Core Cooling Systems 1.2-8 1.2.2.4.8.1 High Pressure 1.2-8 1.2.2.4.8.1.1 High-Pressure Core Flooder System 1.28 1.2.2.4.8.1.2 Reactor Core Isolation Cooling System 1.28 1.2.2.4.8.2 Autorna;ic Depressurization System 1.2-8 O
1.2 iii Amendment 19
ABWR mame Standard Pinnt arv. c SECTION 1.2 (1
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CONTENTS (Continued)
Sectlon Title Luc 1.2.2.4.83 Low Pressure Flooder Loop 1.2-9 1.2.2.4.9 Containment 1.2-9 1.2.2.4.9.1 Functional Design 1.2-9 ,
1.2.2.4.9.2 IIeat Removal 1.79 1.2.2.4.93 Erwironmental Systems 1.29 1.2.2.4.9.4 WeIwell/Drywell Spray 1.29 1.2.2.4.9.5 Flammability Control 1.2-9 1.2.2.4.10 Containment and Reactor Veuelisolation Control System 1.2-9 1.2.2.4.11 Main Steamline Isolation Valves 1.2-9 1.1.2.4.12 Main Steamline Flow Restrictors 1.2-10 r]
v 1.2.2.4.13 Radiation Munitoring and Control 1.2 10 1.2.2.4.14 Residual Heal Removal System (Containment Cooling) 1.2 10 1.2.2.4.15 Process Radiation Monitoring System 1.2 10 1.2.2.4.16 Standby Gas Treatment System 1.2 10 1.2.2.4.17 Reactor Building isolation Control System 1.2-10 1.2.2.4.18 Standby AC Power Supply 1.2-10 1.2.2.4.19 DC Power Supply 1.2-11 1.2.2.4.20 Standby Liquid Control System 1.2-11 1.2.2.4.21 Remote Shutdown System 1.2-11 1.2.2.4.22 Condensate Storage Facilities and Distribution System 1.2-11 1.2.2.5 Electrical Systems and Instrumentation and Control 1.2-11
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1.2-is Amendment 19 l
ABWR u..a m e Standard Plant EV A SECTION 1.2 g CONTENTS (Continued)
Secilon 3 1(12 }'i@
1.2.2.5.1 Electrical Power Systems 1.2-11 1.2.2.5.1.1 Unit Auxiliary AC Power System 1.2-11 1.2.25.1.2 Unit Class 1E AC Power System 1.2 11 1.2.2.5.13 Safety Systes Protection System Power System 1,2 11 1.2.2.5.1.4 Instrument Power System 1.2-11 1.2.2.5.1.5 Uninterruptible Power System 1.2-12 1.2.2.5.1.6 Unit Auxiliary DC Power System 1.2-12 1.2.2.5.1.7 Unit Class 1E DC Power System 1.2 12 1.2.2.5.2 Nuclear System Process Control and Instrumentation 1.2-12 1.2.2.5.2.1 Rod Control and Information System 1.2-12 1.2.2.5.2.2 Recirculation Flow Control System 1.?-12 0
1.2.2.5.23 Neutron Monitoring Syrtem 1.2 12 3.2.2.5.2.4 RefuelingInterlocks 1.2 12 1.2.2.5.2.5 Reactor VesselInstrumentation 1.2-12 1.2.2.5.2.0 Process Computer System 1.2-13 1.2.2.6 Feedwater Control System 1.2-13 1.2.2.7 Fuel Handling and Storage Systems 1.2-13 1.2.2.7.1 New and Spent Fuel Storage 1.2-13 1.2.2.7.2 Fuelllandling System 1.2 13 1.2.2.8 Cooling Water and Auxiliary System 1.2-13 t.2.2.8.1 Reactor Building Cooling Water System 1.2-13 9
1.2-v Amendment 1
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l 1.213d Drywell Steel, Arrangem nt Pla1 at El 18100 rnm 1.2-29c l 1.2-13e Lower Drywell, Arrangement Plan at Elevation
(-) 6600 to (-) 1850mm 1.2-29d 1.2-13f lower Drywtl., Arrangement Plan t t Ekvation
(-) 1850 to 1750mm 1.2-29e 1.2-13g Lower Drywell, Arrangement Plan at Elevation 1750 to 4800mm 1.2 29f 1.2-13h - Lower Drywell, Arrangement Plan at Elevation 4800 to 6700mm 1.2-29g 1.2 131 Wetwell, Arrangement Plan at Elevation
(- ) 8200mm 1.2-29h 1.2-13j Wetwell, Arrangement Plan at Elevation
(- ) 1700mm 1.2 29i
/~'s V 1.2-13k Wetwell, Arrangement Plan at Elevation 4800rm 1.2 29j l
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ABWR mauc Standard Plant . . _ _ .
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ILLUSTRATIONS Eigur.c Tilk Eags 1.2 14 Control and Senice Building, Arrangement Elevation, Section 0/1800 1.2-30 1.2 15 Control and Service Building, Arrangement Elevation, Section 270/900 1.2-31 1.2-16 Control and Senice Building, Arrangement 4,
Plan at Elevation ThtSL (-) S200 mm 1.2-32 1.2-17 " itrol and Senice Building, Arrangement Plan at Elevation ThiSL (-) 2150 mrn 1.2 33 i
1.2 18 Control and Senice Building, Arrangement Plan at Elevation ThtSL 3500 mm 1.2-34 1.2 19 Control and Senice Building, Arrangement Plan at Elevation ThtSL 7900 mm 1.2-35 1.2 20 Control and Senice Building. Arrangement Plan at Elevation ThtSL 12300 mm 1.2-36 1.2-21 Control and Senice Build m , '" nent Plan at Elevation ThtSL 'i: . 1.2-37 1.2-22 Control and Senice Buildin - u: Zement Room at Elevation Th!SL 22tJ0 :.4m 1.2-38
.i 1.2-23a Radwaste Building at Floor Elevation (-)6500mm 1.2 39 1.2 23b Redwaste Building at Floor Elevation (-)200mm 1.2-40 3
1.2 23c Radwaste Building at Floor Elevation 7300mm 1.2-41 1.2 23d Radwaste Building at Floor Elevation 1600mm 1.2-42 1.2 23e Radwaste Building.Section A-A 1.2-43 i2-23f Radwaste Building, Equipment List (Sheet 1) 1.2-4/
1,2 23g Radwaste Building, Equipment List (Sheet 2) 1.2-45 1.2 24 Turbine Building, General Arrangement at Elevation 5.3M 1.2-46 l
1.2-vm. . .
Amendment 19
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Iv ') SECTION 1.2 ILLUSTRATIONS (Continued)
Eig1Lrg Title Page 1.2 25 Turbine Building, General Arrangement at Elevation 12.3M 1.2-47 l 1.2-26 Turbine Building, General Arrangement at Elevation 20.3M 1.2-48 1.2 27 Turbine Building, General Arrangement at .
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INDUSTRIAL CODES AND STANDARDS APPLICABLE TO ABWR 1 Code or ' , Standard i Number Year Title .l l
-ANS
' 2.3 . 1983 Standard for Estimating Tornado and Other Extreme Wind Characteristics at Nuclear Power Sites
, 2.8 1981 Determining Design Basis Flooding at Power Reactor Sites
- . 5.1 1979- Decay Heat Power in LWRs n . . 18.1 (N237) 1984 Radioactive Source Term for Normal Operation of LWRs 52.1 ; _1983 . Nuclear Safety Design Criteria for the Design of Stationary Boiling Water Reactor Plants 55.4 :1979 - Gaseous Radioactive Waste Processing Systems for Light - Water Reactors
- O 57.1- 1980 Design Requirements for LWR Fuel Handling Systems 57.2(N270) '1976 Design Requirements for LWR . Spent Fuel Storage Facilities at NPP 58.2 .1988 Design Basis for Protection of Light Water NPP Against Effects of Postulated Pipe Rupture 59.51'(N195) - 1976 Fuel Oil Sys: ems for Standby Diesel-Generators D
. Amendment 12 1.8-53 l 4
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iABWRe mauc - r4' l Standard Plant' __ nrw. c TABLE 1.8 21 (Continued) - INDUSTRIAL CODES AND STANDARDS , , APPLICABLE TO ABWR - Code or Standard Number- Year Title ANSI q A581 1982 Design Loads for Buildings and other Structures, Minimum B'.' s 1960 American Standard Tolerance for Ball and Roller Bearings 3
- B30.2 1983- . Overhead and Gantry Cranes (Top Running Bridge, Sity,le or !L Multiple Grider, Top Running Trolley Holst) 97 q p _ B30.11 1980_ Monorail and Underhung C. anes '
l B3L1 -1986 Power Piping ; C1 :- 1985 SpeZeations of General Requirements for a Ouality
' Program D975 - =1981! ' Diesel Fuct Oils, Spec for lHEI 1970. Standards for Sicam Surface Condenscr,6th E., Heat
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, -10,000 Pounds (4500 Kg) or More for Nuclear Materials
- N45.2.1' 1973 Cleanhig of Fluid Systems and Associated Components (RG 137) During Construction Phase of Nuclear Power Plants N45.2.2' 1972 Packaging, Shipping, Receiving, Storagennd Handling of
' (RG 138) . Items for Nuclear Power Plants Daing the Construction Stage N45.23 -1973 Housekeeping During the Constructian Phase of Nuclear Power Plants N45.2.4 1972 Quality Assurance Program Requirements for Nuclear Power Plants O
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;AB'WR" usiac LSandard Plant - any c-haj. - TABLE 1.8 21 (Continued)
INDUSTRIAL CODES AND STANDARDS y APPLICABLE TO ABWR Code or Standard - Number -Year ' Title
?
- N45.2.5 - 19741 Supplementary Quality Assurance Requirements for.
Installation. Insprction, and Testing of Structural-p '
. Concrete and Structural Steel During the Construction -
Phase of Nuclear Power Plants N45.2.6* ~ 1978.' Oualifications of Inspection, Examination, and Testing
;(RG 158) - . for Nuclear Power Plants -
e : N509. _ ' 1980- . Nuc' ear Power Plant Air Cleaning Units and Components irP N5107 :1980 Testing of Nuclear Air Cleaning Systems
.Prote:tive Coatings (Paints) for Light Water Nuclear
^
1972
- N101.? ~
4 Containment Facilities N101.'4 : 1972 OA for Protective Coatings Applied to Nuclear Facilities l N195 l.
. (See ANS 59.51)
.. N237-(See ANS 18.1 s
' As
' . ' modified by NRC accepted alternate positions to the related Regulato. (Mde ar.d identified in Table 2-1 of Reference'l to Chapter 17.
h
+ -
L l- " Amendment 19' l.8-54.1 1- --w_n, ------+y v-m i-r v_ w -v w ..,-r- = . - - y 9- -- r- r+:= ej
ABWR mama Standard Plant nrv. c n Table 5.2-4 J REACTOR COOLANT PRES 3URE BOUNDARY MATERIALS (Continued) Component Ferru hlaltrhil SnecificationI6STM/ASME) Recirculation Pumn Motor Cover Bottom flange (cover) Forging Carbon steel ASME SA 533 Gr. B Class I or SA 508 CL Ill Stud Bolting Alloy steel ASME SA 540 CL3 Gr..B24 or SA 193, B7 -
^
Nut Bolting Alloy steel ASME SA 194 Gr 7 Middle flange Forfng Stainless steel SA 182, F30tL or 316L Spoo! piece Forging Stainless steel SA 182, F304L or 316L Mounting bolts Bar Alicy steel SA 194, B7 Seal housing Forging Stair.less steel SA 182, F304L or 316L Seal housing nut Bar Stainless steel SA 564,17-4PH (H1100) Reactor Pressure vessel Plate Mn-1/2 Mo-1/2 Ni SA-533, Type B Class 1 Ferging 3/4 Ni-1/2 Mo- SA-508, Class 3 Cr-V Low Alloy Forging C-Si SA-508 Class 1 Carbon steel Forging Ni-Cr-Fe SB 166 NO 66N High nickel alloy Forging 16 Cr-12 Ni-2 Mo SA-132 F316L High alloy Type 316 Stainless steel O timendment 19 5.2-33
y -. . . ,
^
M 2%6100AD Standard Plant - nriv. .c Table 5.2 5 g-BWR WNTER CHEMISTRY l j
- Electro. -
Chemical Corrosion Concentrations
- C99dnetivity Egign11al Parts Per Billion (ppb) -
pS/cm pH at iron Copoer Chloride Sulfate Oxwen" at 250C 250C V at 250C Condensate < 20 <2 <4 <4 <10 - 0.075 - - - - - l
- Condensate
. Treatment Effluent -
and Feedwater ,<2.2 <0.1 <032 <032 20-50 <0.059 ---- l Reactor Water ; (a); Normal
' Operatica . < 20 <1 < 20 <20 ". <03 ~7- <-0.23 - 4 04
, : (b)_ Shutdown < 20 <1 < 20 < 20 -
< 1.2 ~7- ---
n . (c) Hot Standby - <20 <1 <20 -<20 < 200 <03 ~7 ----
' (d) Depressurized < 20 '<1 <20 <20 high (may <1.2 - 5.6-8.6 ---
be 1000 to 8000) e Control Rc:d Drive - Cooline Water - < 2.2 < 0.1 <032 <032 20-50 5 0.059 ---- i r-
- c. .These limits should be met at least 90% of the time.
Some revision of oxygen values may be established after hydmgen water chemistry has been established.
- Amendment 15 $.2-38
,-- a
- - - - , . . . . . . -. -e.v - . , _ , ,, m ,_ .- ,w 1- v n - , _ , , , ,, e -
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i
. LABWR us6iooxo
- Slac@rd Plant - nev. A
~ h:2 Table 6.1 1 ENGINEERED SAFETY FEATURES COMPONENT MATERIALS Specification
'.Copponend! E9tm Matrrial (ASTM /ASMEl RHR Heat Exchanger
. Shell, Head and Channel Plate > Carbon Steel SA516 Gr 70 -
Tube Sheet = Plate Carbon Steel SA516 Gr 70 I l Nozzles and Flanges Forging Carbon Steel SA350 Gr LF2 -
. Tubes n Tube Stainlest Steel SA249 Type 304L -
l
- Nuts and Bolts . ' Bar Low Allow Steel ' SA194 Gr 7,
, SA193 Gr B7 ECC$ Pumps -
- Bowl Assembly Casting Carbon Steel SA352 Gr LCB e Discharge Head Shell/ Cover Plate /Fotging Carbon Steel SA516 Gr 70/
i' v : SA350 Gr LF2 Suction Barrel Shell & Disked Plate Carbon Steel SA516 Gr 70
. Head :
Flanges Forging Carbon Steel SA350 Gr LF2
, . Pipe. Pipe Carbon Steel - SA333 Gr 6 Shaft i Br.t Stainless Steel SA276 Type 410(Q&T or N&T)
'Impellcrs - Casting ' Stainless Steel SA351 Gr CA6h%i I Studs & Nuts Bar Low Allow Steel SA193 Gr B7/SA194 Gr 7 :
' RFIR -
- A--Hich and Low Pressure I'-imary Pipine (Class 1 or 2) y 4.'-
l ' Piping Seamless Pipe Carbon Steel SA333 Gr 6
/ Welded Pipe Carbon Steel SA672 Gr C70 L
L Fittings Forging Carbon Steel SA350 Gr LF2 or l' SA420 Gr WP14
- Amendment 19 6.14 j[ >
.-. , . . - . . , . . . , . . . , , . ~ . . . , . . , - - . , , , . , , ,-
k 21A6100AD - SIBudard Plant REY.A Table 6.1-1 $ ENGINEERED SAFETY FEATURES COMPONENT MATERIALS (Ccntinued) Specification Component Ects hl41ttial _{ ASTM /ASMD Flanges Forging Carbon Steel SA350 Gr LF2 Valves (Gate, Globe, Check) Forging Carbon Steel SA350 Gr LF2 Casting Carbon Steel SA352 Gr LCB Bolting Bar low Alloy Steel SA193 Gr B7 Nuts Bar Low Alloy Steel SA194 Gr 7 B--Low Pressure Snrav Eauipment_ Tr side Wetwell (Ciass 31 Piping Pipe Carbon Steel SA106 Gr B SA 672 Gr C Fittings Forging Carbon Steel SA105 SA234 Gr WPB Flanges Forging Carbon Steel SA105 Valves (Gate, Globe, Check) Forging Carbon Steel SA105 SA216 Gr WCE Bolting (same as A above) Nurs (same as A above) C--Interface to Fuel Pool Pinine (Class 3) Piping Pipe Stainless Steel SA3% Type 316L SA312 Type 316L SA3'8 Type 316L Valves (Gatc; siobe, Check) Forging Stainless Steel SA182 Gr F316L SA351 Gr CF3 Fittings Forging Sta:aless Steel SA182 Gr F316L or SA403 Gr WP3161/N l Flanges Forging Stainless Steel SA182 Gr F316L SA351 Gr CF3 Bolting (same as A above) Nuts (same as A above) G I Amendment 19 6.1-5
, . ~. . . . . . . ..
LABTVRL 22^61*^n e Standard Plant REV.A h Table 6.1 1 ENGINEERED SAFETY FEATURES COMPONENT MATERIALS (Continued) , Speelfication ,. ComponJ.nl fann h171ttial OLSTM/ASMD HPCF Same as RHR A above.
' RCIC
' Sane as RHR A above.
- Standby Liquid Control Pump
~ (No wnlding) _ l
' Fluid Cylinder _
Forging Stainless Steel SA182 F3M ' Cylinder Head, Valve Plate Stairiless Steel SA240 Type 2M ' Cover, and stuffmg Box Flange Plate Cylinder Head Extension, Bar Stamless Steel SA479_ Type 304
' Valve Stop, and Stuffing l- Bex p . Stuffing Box Gland Forging Stainless Steel SA564 Type 630 (H 1100) l '
- G and Plungers :
' Studs - Bar Alloy Steel SA193 Grade 87 Nuts Ft *ging Alloy Steel SA194 Grade 7 Standby Liquid Storage Tank Tr.nk Plate- Stainless Steel SA240 Type 3M
- Fittings _ -
Forgings Stainless Steel SAIS3 Gr F3M l' - Pipe; Pipe ' Stainless Steel SA312 Type 304 : l '- --Welds Electrodes Stainless Steel FA 5.4 & J,9, t- Types 308,308L, l 316L l - Containment Vessel Plate Carbon Steel SA516 Gr 70 Plate Stainless Steel SA240 Type 3ML i-Peceirations Forging - Carbon Steel SA350 Gr LF 1 or 2
- Forging Stainless Steel SA182/FNML t . Structural Steel Shapes Carben Steel A-36 l-
'! Amendment 19 6.1-6 l
' lb: .
ABWR _ ux62 man Standard Plant REV.C Table 6.1 3 ENGINEERED SAFETY FEATURES COMPONENT MATERIALS (Continued) Specification Comnonent EgrHI Materia (ASTM /ASMD HVAC Emergency Cooling Water System Heat Exchanger Plate Carbon Steel SA283 Gr A Tube Copper Alloy SB'i5-C12200 Pump Casting Carbon Steel SA216 Gr WCB Casting Stainless Steel ' SA351 Gr CF8
-Valves Casting Carbon Steel SA216 Gr WCB Forging Carbon Steel SA105 Piping Seamless Pipe Carbon Steel SA106 Gr A Welded Pipe arbon Steel SA672 Gr B60
' Reactor Building Cooling Water System Heat Exchanger Plate Carbon Steel SA283 Gr B Tubes Copper Alloy Note 1 l Pump Casting Carbon Steel SA216 Gr WCC Casting Stainless Steel SA351 Gr CF8 _
Valves - Casting Carbon Steel SA216 Gr WCB Forging Carbon Steel SA105 Piping _ Seamless Pipe Carbon Steel SA106 Gr A Welded Pipe Carbon Steel SA672 Gr B60 Reactor' Service _ Water System Pump Casting - Stainless Steel SA351< CF8M '
- Valves Casting Carbou Steel & SA216 Gr WCB Rubber lining Casting S'ainless Steel SA351 CF3M Casting Bronze SB584-C90500 Forging Stainless Steel SA182 Type 316L Piping Seamless Pipe Carbon Steel & SA106 Gr A '
Welded Pipe Polyethylene- SA672 Gr B60 i'_ lining Note 1: Materials are site dependent
- e l Amendment 16 6.17
~w e, .
\ 23A610(Mii Standard Plant nu n m; 9AA ANALYSIS GE PROPRIETARY - provided i:nder separate cover Pgg Amendment Eggg Amendment 9A.&1 - 41 16 9A.4-157 18 9A.4 46 6 9A.4-158 - 160 16 9A.4 48 18 9A.4-161 6 9A.4 56 6 9A.4-162 16 9A.4-57 18 9A.4163 - IM 18 9A.4-58 16 9A 4165 - 170 16 9A.4 59 - 61 6 9A.4171 172 18 9A.4-62 18 9A.4-172.1 16 9A.4 68 6 9A.4-173 174 16 9A.4-69 18 9A.4-175 18 9A.4 108 16 9A.4176 - 200 16 (m 9A.4-103.1 16 9A.4-201 6 b 9A.4-109 - 115 9A.4-115.1 16 16 9A.4-202 9A.4-201 - 211 18 16 9A 4-116 - 120 16 9A.4 212 - 213 18 9A.4-120.1 16 9A.4-214 - 224 16 9A.4-121 16 9A.4-224.1 - 224.60 16 9A.4 121.1 16 9A.4-225 - 249 14 9A.4122 - 131 16 9A.4-250 - 255 19 9A.4-132 18 9A.4-255.1 - 255.2 19 9A.4-133 6 9A.4 256 14 9A.4-134 - 150 16 9/ 4-257,258 18 9A.4-151 6 9A.4-259 - 271 14 9A.4-152 - 156 16 l f3 l 'w]
l Aaaendment 19 9A.4 1 - 271
ABWR uuima Standard Plant RIN D
'~'
v) SECTION 11.5 CONTENTS (Continued) Section Iith P_gg; 11.5.5.4 Audits and Verifications 11.5-12 TABLES Iahls ' Title Page 11.5-1 Process and Eilluent Radiation Monitoring Systems 11.5-13 11.5-2 Process Radiation Monitoring System (Gaseous and Airborne Monitors) 11.5-16 11.5-3 Process Radiation Monitoring System (Liquid Monitors) 11.5-18 11.5-4 Radiological Analysis Summary of Liquid Pracess Samples lif 19 11.5-5 Radiological Analysis Summary of Gaseous p) ( _. Process Samplcs 11.5-20 11.5-6 Radiological Analysis Summary of Liquid Ekluent Samples 11.5-21 11.5-7 Radiological Analysis Summary of Gaseous Eftluent Samples 11.5-22 l
, ('] 11.5-iv L.)
Amendment 19
iABWR naaman Standard Plant nev ^ SECTION 18A.4 GE PROPRIETARY - provided under separate cover
]).ggy Amendment 18A.41 14 18A.4 2 19 18A.4-3 19 18A.4-4 19 18A.4-5 14 18A.4-6 19 l
18A.4 7 14 18A.4-8 14 18A.4-9 14 18A 410 19 l 18A.411 14 18A 4-12 19 18A.413 19 18A 4-14 19 18A.415 19 O Amendment 19 18A 4 15
ABWR 234can StamlanLElant neu SECTION 18A.5 O GE PROPRIETARY - provided under separate cover hgx Amendmynt hgg Amendment 18A.5-1 14 18A.5-12 19 l 18A.5-2 19 18A.5-13 19 18A.5-3 14 18A.5-14 19 l 18A.5-4 19 18A.5-15 19 18A.5-5 14 18A.5-16 19 18A.5-6 19 18A.5-17 19 18A 5-7 18A.5-18 19 19 18A.5-8 14 18A.5-19 19 18A.5-9 19 sA 5-20 19 18A.5-9.1 19 3A.5-21 14 18A.5-10 19 18A.5-22 14 18A.5-11 19 18A.5-23 14 O Amendment 19 IBA.$ 23 l
ABWR DAMMAR Standard Plant Rev A
~ SECTION 18A.6 'n. )
GE PROPRIETARY provided under separate cover h Amendment 18A.61 14 18A.6-2 14 18A.6-3 19 18A.6-4 19 18Ali-5 19'
,3 18A.6-6 14 ' ,j IFA6-7 14 18 4.6-8 14 18A.6-9 14 18A.6-10 14 18A.6-11 14 18A.6-12 14
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Amendnwn 19 18A (el - 12
ABWR ux6iwan Standard Plant nev ^ SECTION 18A.7 GE PROPRIETARY - provided under separate cover O fagg Amendment 18A.7-1 19
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Amendment 19 ' M .7 1
ABWR unaun Staadard Plant n~2 g SECTION 18A.8 GE PROPRIET/ ru' . provided under separate cover Eact Anirnsmini AbA.8-1 14
' 18A.8-2 19 1&A.8-3 19 ISA.8-4 14 18A.8 3 14 t
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O Amendment 19 18A 8-1 5 f
1 ABWR- 23A6100AR Stan.dard Plant x,, A
-s SECTION 18A.9
(~_,r GE PROPRIETARY - provided under separate cover , f~s, Egg Amendment Q) 18A.91 19 l 18A.9-2 14 18A.9 3 17 I-l
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Amendment 19 18A.9 3
i
'ABWR uAaun Standard Plant _g e SECTION 18A.11-
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- (..J GE PROPRIETARY- provided unde ,tparate cover fags Amelldmrpt 18A.11 1 14 18A.1 i. - 19 l
-18A.11-3 14
- 18A.114 - -14 18A.11-5 19
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, 18A.11-6 19
('"' ). 18A.11-7 19 18A.11-8 -14 Amendmert 19 18A.11 8 l
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- ., Engg Amendmen,1
- .4=-
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18A.12-1 - 19 -
+ 18A.12-2 . 17 >
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-ABWR nyima .
Sjalulard Plant a,.. a l SECTION 18A.13 I 1 v - GE PROPRIETARY - provided under separate cover h Amendment ( . 'v ISA.13-1 19 18A.13-2 19 18A.13-3 19 O 18A 111 3 Amendment 19 l
ABWR uuima Stendard Plant Rev.A
. SECTION 1811 i) v GE PROPRIETARY - provided under separate cover Jiagg Amendment Eggs Amendgigni 18B-2 13 ISB 14 19 18B-2.1 19 18B 15 19 18B-3 19 18B-16 13 18B-4 19 18B-16.1 19 m 188-5 19 18B-16.2 19 i )
s ISB-6 19 18B 17 19 ISB/r 19 15B-18 19 ISB-8 19 18B 18.1 19 ,- 18B-9 13 18B-19 19 ISB-10 19 ISB-19,1 19 18B 10.1 19 18B-20 19 ISB-11 19 18B 21 19 18B-11.1 19 18B 22 19 18B-12 19 188-22.1 19 18B-12.1 19 18B-23 19 18B 13 19 18B 24 19 O Amendment 19 18102 24 l
LO b' APPENDIX 19N ANALYSIS OF COMMON-CAUSE FAILURE OF , MULITIPLIER EQUIPMENT l-- 1 l O-
ABWR UMlWAS Standard Plant act A r,3 SECTION 19N.5 GE PROPRIETARY. provided under separate cover h A_m_tndment 19N.5-1 18 19N.5-2 18 19N.5-3 18 19N.5-4 18 19N.5-5 18 19N.5-6 18
,/ -
L) O Amendment 19 19N51 - 5 I 1
,, 3\
pd U- V-y Le> PLANT DESIGN DEFINITION i
?, $:Y a2 i
D 1 y es U U U' V ~ SYSTEM DESIGN DEFINITION INTEGRATED EMERGENCY INCLUDES REQUIREMENTS OPERATING PROCEDURE FOR SYSTEM EOUIPMENT & GUIDELINES PROCEDURES MA.N MACHINE INTERFACES
/s Plant andSystem Design Definition me a em em um en am si se = em em ar -===m - se en = se - em - = = iem============
Applicant Scope EQUIPMENT PROCUREMENT y y y 4 U V _ V U U EQUlPMENT FINAL VERSION EMERGENCY OPERATING OPERATOR MAINTENANCE INSTALLATION, OF SYSTEM PROCEDURES AND FINAL TRAINING TRAINING INSPECTION, OPERATING VERSION OF INTEGRATED MATERIALS - MATERIALS AND TESTING PROCEDURES OPERATING PROCEDURES m t
? Figure 20.3-54 Relationship of System Training Material Preparation to gE
- !! Other Plant Design and Procurement Activities ;E 1 (Response to Question 620.8) 3
_ __ _ _ _ .}}