ML19312A212
| ML19312A212 | |
| Person / Time | |
|---|---|
| Site: | 05000495 |
| Issue date: | 11/29/1978 |
| From: | NEW YORK STATE ELECTRIC & GAS CORP., STONE & WEBSTER, INC. |
| To: | |
| References | |
| NUDOCS 7909050306 | |
| Download: ML19312A212 (604) | |
Text
{{#Wiki_filter:SNESSAR-P1 CHAI*IER 9 AUX 1LIARY SYSTEMS LIST OF EFFECTIVE PAGES Page, Table (T) , Amendment Page, Table (T) , Amenument or Fiqure (F) No. or Fiqure (F) No. 9-a thru d 39 9.2-13/14 19 9-1 12 9.2-15 thru 20 19 9-11 19 9.2-21 thru 24 9 9-iia /B 32 9.2-25/26 32 9-lii 9 9.2-27 thru 29 (BSW) 32 9-1v,v 30 T9.2.1-1 33 9-vi 25 T9.2.1-263 ('W) 19 9-vii thru viiiB 33 T9.2.1-263 (W-3S) 19 9-ix 19 T9.2.1-263 (BSW) 30 9-x 30 T9.2.1-263 (C-E) 19 9-xA/xB 33 T9 . 2 .1- 4 19 9-x1 19 T9.2.2 35 9-xli thru xiv 30 T9.2.2-263 (W) 19 9.1-1 17 T9.2.2-263 (W-3S) 19 9.1-2 20 T9.2.2-263 (uSW) 30 9.1-3/4 17 T9.2.2-263 (C-b) 19 9.1-5 thru 6A 20 T9.2.2-4 19 9.1-7 12 T9.2.2-5 04) (2 Sheets) 21
,j-9.1-8/8A 33 T9.2.2-5 (W-3S) (2 Sheets) 28 9.1-9/10 20 T9.2.2-5 (BSW) 33 9.1-11 thru 14 24 T9.2.2-5 (C-E) 23
- .e 9.1-14A 33 T9.2.2-6 ( i) 23 9.1-15 thru 17 pi) 12 T9.2.2-6 (W-3S) (2 Sheets) 23 T9.1.1-1 15 T9.2.2-6 (uSW) (2 Sheets) 23 T9.1.2-1 15 T9.2.2-6 (C-E) 23 T9.1.3-1 (2 sheets) 30 T9.2.3-1 9 T9.1.3-2 (W) 17 T9.2.3-2 pi) 21 T9.1.3-2 (W-3S) 17 T9.2.3-2 (W-3S) 18 T9.1.3-2 (B&W) 30 T9.2.3-2 (BSW) 30 T9.1.3-2 (C-E) 17 d'T9.2.7-1 30 T9.1.3-3 17 T9.2.7-2 (W) 21 T9.1.4-1 pi) 10 T9.2.7-2 (W-3S) 21 T9.1.5-1 04) 21 T9.2.7-2 (BSW) 30 T9.1.5-1 (W-3S) 28 T9.2.7-2 (C-E) 21 T9.1.5-1 (bSW) (2 sheets) 33 T9 . 2 .10 - 1 (BSW) 32 T9.1.5-1 (C-E) (2 sheets) 21 F9.2.1-1 (W) 19 F9.1.3-162 12 F9.2.1-2 04) 14 9.2-1 14 F9.2.1-1 (W-3S) 19 9.2-2 25 F9.2.1-2 (W-3S) 18 9.2-3 33 F9.2.1-1 (BSW) 33 9.2-4 thru 9 25 F9.2.1-1 (C-E) 19 9.2-10/10A 21 F9.2.1-2 (C-E) 14 9.2-10B 25 F9.2.2-1 04) 21 9.2-11 19 F9.2.2-1A pi) 19 9.2-12 & 12A 30 F9.2.2-1B (W) 21
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9-a Amendment 39 7/14/78
SWESSAR-P1 LIST OF EFFECTIVE PAGES ( CO!n') Paga, Taule (T) , Amendment Page, Table (T), Amendment or Fiqure (F) No. or Figure (F) No. , F9.2.2-1C DO el T9.3.4-1 (W-3S) 28 F9.2.2-1 (W-36) 41 T9.3.4-1 (bSW) (sheets 162) 33 F9.2.2-1A (W-3S) 21 T9.3.4-1 (BSW) (sheet 3) 34 F9.2.z-18 (W-3S) 19 T9.3.4-1 (C-E) (2 sheets) 26 F9.2.2-1C (W-3S) 21 T9.3.6-1 17 F9.2.2-1 (BSW) 19 T9.3.6-2 (sheet 1) 12 F9.2.2-1A thru lD (B&W) 19 T9.3.b-2 (sheet 2) 17 F9.2.2-1 (C-E) 22 T9.3.b-2 (sheets 364) 12 F9.2.2-1 A thru 1D (C-E) 22 T9.3.6-3 17 F9.2.2-1F (sheets 162) 19 T9.3.6-4 2 F9.2.2-1F (sheet 3) 21 T9.3.b-5 (W) (2 sheets) 18 F9.2.2-1F (sheet 4) 22 T9.3.6-5 (W-3S) (2 sheets) 18 F9.2.2-1F (sheet 5) 19 T9.3.6-5 (BSW) 29 F9.2.3-1A g T9.3.6-5 (C-h) 18 F9.2.3-1B 30 T9.3.6-6 thru 8 18 F9.2.7-1A 12 F9.3.1-1 12 F9.2.7-1B 30 F9.3.1-2 Orig F9.2.6-1ASd 13 F9.3.2-1A pi) 13 F9.2.8-2A, 2B 13 F9.3.2-1A (W-3S) 17 F 9 . 2 .10 - 1 (B&W) 32 F9.3.2-1A (BSW) 28 9.3-1 tnru 3 12 F9.3.2-1A (C-b) 18 9.3-4 30 F9.3.2-1B 13 9.3-5 9 F9.3.2-1C (3 sheets) 29 9.3-b 29 F9.3.2-2 (2 sheets) 12 9.3-bn 12 F9.3.3-1 32 9.3-bu 9 F9.3.3-2A ('W) 12 9.3-7 4 F9.3.3-2A (W-3 S) 17 9.3-8 29 F9.3.3-2A (B&W) 29 9.3-8A 9 F9.3.3-2A (C-E) 12 9.3-9 9 F9.3.3-28 (5 sheets) 29 9.3-10 29 F9.3.4-1 pi) (4 sheets) 8 9.3-10A/B pi) 9 F9.3.5-1 pi) 8 9.3-10A/d (W-33) 17 F9.3.4-1 (W-3S) (4 sheets) 17 9.3-10A (B&W) 29 F9.3.5-1 (W-3S) 17 9.3-10B (B&W) 32 F9.3.4-1 (BSW) (sheet 1) 19 9.3-10A (C-E) 23 F9.3.4-1 (B&W) (sheet 2) 29 9.3-10B (C-E) 26 F9.3.4-1 (B&W) (sheets 364) 19 9.3-10C/D (C-E) 23 F9.3.4-1 (C-E) (sheets 162) 9 9.3- 10 E /10 F 18 F9.3.4-1 (C-E) (sheet 3) 23 9.3-11 12 F9.3.4-1 (C-E) (sheet 4) 9 9.3-12, 13 7 F9.3.4-1 (C-E) (sheet 4n) 10 9.3-14, 15 12 F9.3.4-1 (C-d) (sheets 566) 23 9.3-1o 18 .F9.3.6-1A 12 T9.3.1-1 12 F9.3.6-1B 29 T9.3.1-2 7 9.4-1 17 T3.3.1-3 29 9.4-2 30 T9.3.2-1 7 9.4-3 thru 12B 30 T9.3.3-1 9 9.4-13 14 T9.3.3-2 (2 sheets) 17 9.4-14 thru 14B 9 T9.3.4-1 (W) 21 9.4-14C 25 9-b Amendment 39 7/14/78 i
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SWESSAR-P1 LIST OF EFFECTIVE PAGES (CONT) Page, Table (T) , Amendment Page, Table (T) , Amendment or Floure (F) No. or Fiqure (F) No. 9.4-14D 17 O 4*I-O
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9.4-15 12 17 F9.4.2-1 (W-3S)
*"* ~ Idb I 9.4-17/18 14 F9.4.2-1 (C-E) 14 g,q_)g g F9.4.3-1 14 9.4-20 14 12 F9.4.4-1 9.4-20A 9 F9.4.5.1-1 (W) 12 9,q_jg 34 F9.4.5.1-1 (W-33) 17 9,4_g g H F9.4.5.1-1 (B&W) 9.4-23 9 F9.4.5.1-1 (C-E) 17 9.4-24624A 35 * * *
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9.4-24B 22 ' ~1 9.4-25 25 '. ' '. 6 - 1 M 9.4-26,26A 9
.4. -162 1 9.4-27 thru 28A 18
- 9.4-29 33 9.4-30 18
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* '9 9.4-31/32 9.5-13 h 16 9 9.4-33 20 26 9.4-34 30 .5-17/18 9.4-34A T9.5.1-1 (sheet 1) . 33 18
,= 9,g_33 T9.5.1-1 (sheet 2) 30 37 T9.4-1 (sheet 1) '30 T9.5.1-2 (W-3S) (5 shets) 38
,T9 . 4 - 1 (sheen 2) 17 T9.5.1-3 (W-33) (3 sheets) 38 T9.5.1-2 (B&W) 33 T9.4-2(B&W) 30 T9.4.1-1 30 (sheets 1 thru 4)
T9.5.1-2 (8SW) (sheet 5) 38 T9 . 4 .1 -2 (2 sheets) 8 T9.5.1-3 (BSW) (sheets 162) 33 T9.4.1-3 (3 sheets) 30 T9.5.1-3 (8SW) (sneet 3) 38 T9.4.1-4 30 38 T9.4.1-5 12 T9.5.1-2 (C-E) (4 sheets) T9.5.1-3 (C-E) (3 sheets) 38 T9.4.z-1 Orig 33
. .1 65 T9.4.3-1 12 17 T9.5.4-1 T9.4.4-1 (2 sheets) 9 5
T9.5.5-1 T9.4.5.1-1 17 5 T9.5.6-1 T9.4.b.1-2 (2 sheets) 17 5 T9.5.7-1 T9.4.5.1-3 (W) (2 sheets) 9 T9 8-1 ig T9.4.5.1-3 (W-33) 27
' I F9.5.1-2 30 T9.4.5.2-1 4 F9.5.1-3 (W-3S) (5 sheets) 38 T9.4.5.3-1 Orig 8
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T9.4.6-1 Orig 30
,r9.4.8-1 21 F9.5.1-3 (BSW) (5 sheets) 79,q_) F9.5.1-4 (B&W) (3 sheets) 30 34 F9.4.1-1 30 F9.5.1-3 (C-S) (5 sheets) 38 F9.4.1-2 33 F9.5.1-4 (C-E) (3 sheets) 38 F9.5.1-5 38 F9.4.1-364 30 F9.4.1-SS6 30 F9.5.1-6 (W-3S) (4 sheets) 38 79,q,3_7 g F9.5.1-6 (B&W) 30 (sheets 1 thru 3) , , , ,
b60 1 1J 9-c Amendment 39 7/14/78
SWESSAR-P1 LIST OF EFFECTIVE PAGES (CONT) Page, Tanle (T) , Amendment Page, Table (T) , Amendment or Piqure (F) No. or Figure (F) No. F9.5.1-6 (BSW) (sheet 4) 38 F9 . S .1-6 (C-E) (4 sheets) 38 F9.S.4-1 12 F9.5.5-1 3 F9.S.6-1 3 F9.S.7-1 3 F9.S.8-1A 26 F9.S.8-1B 29 0 h i :; G 9-d Amendment 39 7/14/78
SWESSAR-P1 CHAPTER 9 AUX LIARY SYSTEMS TABLE OF COtlTEf!.S Section Pace 9.1 FUEL STORAGE AND HANDLING 9.1-1 4.1.1 New Fuel Storage 9.1-1 9.1.1.1 Design Euses 9.1-1 9 .1.1. 2 Facilities Description 9.1-1 9.1.1.3 Safety Evaluation 9.1-2 9.1.2 Spent Fuel Storage 9.1-2 9.1.2.1 Desian Ba ses 9.1-3 9.1.2.2 Facilities Description 9.1-3 9.1.2.3 Safety Evaluation 9.1-5 9.1.3 Fuel Pool Cooling and Purification Systems 9.1-6 9.1.3.1 Design Bases 9.1-6 9.1.3.2 System Description 9.1-7 9.1.3.3 Safety Evaluation 9.1-8 9.1.3.4 Testing and Inspection Recuirements 9.1-10 9.1.3.5 Instrumentation Applications 9.1-10 9.1.4 Fuel Handling System 9.1-11 9.1.4.1 System Description 9.1-11 9.1.4.2 Design Evaluation 9.1-12 9.1.5 Interface Requirements 9.1-14 9.1.6 In-Containment Fuel Storage 9.1-15 9.1.6.1 Design Bases 9.1-15 12 9.1.6.2 Facilities Description 9.1-15 9-i Amendment 12 6/16/75 (. ,,. in;
SWESSAR-P1 TABLE OF CONTENTS (CONT) Section Pace 9.1.6.3 Safety Evaluation 9.1-16 9.2 WATER SYSTEMS 9.2-1 9.2.1 Reactor Plant Service Water System 9.2-1 9.2.1.1 Design Bases 9.2-1 9.2.1.2 System Description 9.2-2 1 9.2.1.3 Safety Evaluation 9.2-3 9 . 2 .1. 4 Testing and Inspection Requirements 9.2-4 9.2.1.5 Instrumentation Applications 9.2-4 9.2.1.6 Interface Requirements 9.2-4 9.2.2 Reactor Plant Component Cooling Water System 9.2-5 9.2.2.1 Design Bases 9.2-5 9.2.2.2 System Description 9.2-6 9.2.2.3 Safety Evaluation 9.2-7
" 9.2.2.4 Testing and Inspection Requirements 9.2-8 9.2.2.5 Instrumentation Applications 9.2-8 9.2.2.6 Interface Requirements 9.2-10 9.2.3 Demineralized Water Makeup System 9.2-10 9.2.3.1 Design Bases 9.2-10 9.2.3.2 System Description 9.2-11 9.2.3.3 Safety Evaluation 9.2-11 9.2.3.4 Testing and Inspection Requirements 9.2-12 9.2.3.5 Instrumentation Applications 9.2-12 9.2.3.6 Interface Requirements 9.2-12 9.2.4 Potable and Sanitary Water Systems 9.2-12 i ,.
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' k) 9-ii Amendnent 19 12/12/75
SWESSAR-P1 TABLE OF CONTT:NTS (CONT) Section Page 9.2.5 Ultimate Heat Sink 9.2-12 9.2.6 Condensate Storage Facilities 9.2-12A 9.2.7 Primary Grade Water System 9.2-13 9.2.7.1 Design Bases 9.2-13 9.2.7.2 System Description 9.2-13 9.2.7.3 Safety Evaluation 9.2-15 9.2.7.4 Testing and Inspection Requirements 9.2-15 9.2.7.5 Instrumentation Applications 9.2-15 9.2.7.6 Laterface Requirements 9.2-15 9.2.8 Cnilled Water Systems 9.2-15 9.2.8.1 Chilled Water System 9.2-15 9.2.3.1.1 Design Bases 9.2-16 9.2.8.1.2 System Description 9 . 2 -1 f-9.2.8.1.3 Deqign Evaluation 9.2-21 9.2.8.1.4 Testing and Inspection Requirements 9.2-22 9.2.8.1.5 Instrumentation Applications 9.2-23 9.2.8.2 Air Cbnditioning Chilled Water 9.2-23 9.2.8.2.1 Design Bases 9.2-23 9.2.8.2.2 System Description 9.2-23 9.2.8.2.3 Design Evaluation 9.2-24 9.2.8.2.4 Testing and Inspection Requirements 9.2-25 9.2.8.2.5 Instrwentation Applications 9.2-25 9.2.9 Water Treatment System 9.2-25 9.2.10 Control Rod Drive Mechanism Motor Cooling System 9.2-27 32 9-iia - 3 r1 Amendment 32 (>,U i Jl S/11/77
SWESSAR-P1 TABI2 OF C01TfENTS (CONT) Section Page 9.2.10.1 Design Bases 9.2-27 9.2.10.2 System Description 9.2-27 32
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9.2.10.4 Testing and Inspection Requir ments 9.2-28 9.2.10.5 Instrumntation Applications 9.2-29 9.2.10.6 Interface Requirements 9.2-29 9.3 PROCESS AUYTLTARIES 9.3-1 9.3.1 Compressed Air Systems 9.3-1 9.3.1.1 Design Bases 9.3-1 9.3.1.2 System Design 9.3-1 9.3.1.3 Design Evaluatior. 9.3-3
- 9. 3 .1. 4 Testing and Inspection Requirements 9.3-4 9.3.1.5 Instrnwntation Applications 9.3-4 t
9 9-lib Amendment 32 5/11/77
SWESSAR-P1 TABLE OF CONTENTS (CONT) 9.3.1.6 Interf at.e Requirements 9.3-4 9.3.2 Sampling Systents 9.3-5 9.3.2.1 Design Bases 9.3-5 9.3.2.2 System Eesign 9.3-5 9.3.2.3 Safety Evaluation 9.3-6A 9.3.2.4 Testing and Inspection Requirements 9.3-6A 9-iii Amendment 9
, , ,,__, 4/30/75
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SWESSAR-P1 TABLE OF CONTENTS (CONT) Section ? age 9.3.2.5 Instrumentation Applications 9.3-6A 9.3.2.6 Interf ace Requirements 9.3-6B 9.3.3 Vent and Drains Systems 9.3-6D 9.3.3.1 Design Bases 9.3-6B 9.3.3.2 System Description 9.3-7 9.3.3.3 Safety Evaluation 9.3-9 9.3.3.4 Testing and Inspection Requirements 9.3-9 9.3.3.5 Instrumentation Applications 9.3-10 9.3.4 Chemical, Volume Control, and Liquid Poison 9.3-10A System 9.3.5 Failed Fuel Detection System 9.3-10B 9.3.6 Boron Recovery System 9.3-10E 9.3.6.1 Design Bases 9.3-10E 9.3.6.2 System Design 9.3-11 9.3.6.3 Design Evaluation 9.3-14 9.3.6.4 Testing and Inspection Requirements 9.3-15 9.3.6.5 Instrumentation Applications 9.3-15 9.3.6.6 Interface Requirements 9.3-16 References for Section 9.3.6 9.3-16 9.4 AIR CONUITIONING, HEATING, COOLING, AND 9.4-1 VENTILATION SYSTEMS I 9.4.1 Control Building Ventilation Systems 9.4-2 9 . 4 .1.1 Design Bases 9.4-2 30 9 . 4 .1. 2 System Design 9.4-4 9.4.1.3 Design Evaluation 9.4-8 9.4.1.4 Testing and Inspection 9.4-10 9-iv Amendment 30 bob ] ~ 1/28/77
SWESSAR-P1 TABLE OF CONTENTS (CONT) Section Page 9.4.1.5 Instrumentation Applications 9.4-12 9.4.1.6 Interface Requirements 9.4-12A 9.4.2 Annulus Building Ventilation System 9.4-12A 30 9.4.2.1 Design Buses 9.4-12A 9.4.2.2 System Design 9.4-13 9.4.2.3 Safety Evaluation 9.4-14D 9.4.2.4 Testing and Inspection Requirements 9.4-14D 9.4.2.5 Instrumentation Applications 9.4-15 9.4.3 Solid Waste and Decontamination Building 9.4-16 Ventilation System 9.4.3.1 Design Bases 9.4-16 9.4.3.2 System Description 9.4-16 9.4.3.3 Saf ety Evaluation 9.4-17 9.4.3.4 Testing and Inspection Requirements 9.4-17 9.4.3.5 Instrumentation Applications 9.u-18 9.4.4 Turbine Building Ventilation System 9.4-18 9.4.4.1 Design Bases 9.4-19 9.4.4.2 System Description 9.4-19 9.4.4.3 Safety Evaluation 9.4-19 9.4.4.4 Testing and Inspection Requirements 9.4-20 9.4.4.5 Instrumentation Applications 9.4-20 9.4.5 Containment Structure Ventilation Systems 9.4-20 9.4.5.1 Containment Atmosphere Recirculation System 9.4-20 9.4.5.1.1 Design Bases 9.4-20 9.4.5.1.2 System Design 9.4-21 9-v Amendment 30 y Vu- 1/28/77
SWESSAR-P1 TABLE OF COhENTS (CONT) Section Page 9.4.5.1.3 Safety Evaluation 9.4-21 9.4.5.1.4 Testing and Inspection Requirements 9.4-22 9.4.5.1.5 Instrumentation Applications 9.4-23 9.4.5.1.6 Interface Requirements 9.4-23 9.4.5.2 Containment Purge Air System 9.4-23 9.4.5.2.1 Design Bases 9.4-23 9.4.5.2.2 System Description 9.4-24 9.4.5.2.3 Safety Evaluation 9.4-24A 9.4.5.2.4 Testing and Inspection Requirements 9.4-24B 9.4.5.2.5 Instrumentation Applications 9.4-25 1 9.4.5.2.6 Interface Requirements 9.4-25 25l 9.4.5.3 Containment Atmosphere Filtration System 9.4-25 9.4.5.3.1 Design Bases 9.4-25 9.4.5.3.2 System Design 9.4-26 9.4.5.3.3 Safety Evaluation 9.4-26 9.4.5.3.4 Testing and Inspection Requirements 9.4-26A 9.4.5.3.5 Instrumentation Applications 9.4-27 9.4.6 Fuel Building Ventilation System 9.4-27 9.4.6.1 Design Bases 9.4-28 9.4.6.2 System Design 9.4-28 9.4.6.3 Design Evaluation 9.4-28A 9.4.6.4 Testing and Inspection 9.4-29 9.4.6.5 Instrumentation Applications 9.4-29 9.4.7 Plant Heating System 9.4-29 9.4.7.1 Design Bases 9.4-30 9-vi Amendment 25 4/30/76
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SWESSAR-P1 TA RLE OF CONTENTS (CONT) Section Page 9.4.7.2 System Design 9.4-30 9.4.7.3 Safety Evaluation 9.4-32 9.4.7.4 Testing and Inspection Requirements 9.4-32 9.4.7.5 Instrumentation Applications 9.4-32 9.4.8 Control Rod Drive Mechanism (CRDM) 9.4-33 Cooling System 9.4.8.1 Design dases 9.4-33 9.4.8.2 System Design 9.4-34 9.4.8.3 Safety Evaluation 9.4-34 9.4.8.4 Testing and Inspection Requirements 9.4-34 9.4.8.5 Instrumentation Applications 9.4-34 9.4.9 Enclosure Building Air Mixing System 9.4-34 References for Section 9.4 9.4-34A 9.5 OI11ER AUXIIUaY SYSTEMS 9.5-1 9.5.1 Fire Protection 9.5-1 9.5.1.1 Overall Requirements of the Fire Protection 9.5-1 Program 9.5.1.2 Administrative Procedure, Controls, and 9.5-4 Fire Brigade 9.5.1.3 Quality Assurance Program 9.5-6 33 9.5.1.4 General Plant Guidelines 9.5-6 9.5.1.4.1 Building Design 9.5-6 9.5.1.4.2 Control of Combustibles 9.5-8 9.5.1.4.3 Electrical Cable Construction, Cable Trays, 9.5-8 and Cable Penetrations 9.5.1.4.4 Ventilation 9.5-8C 9.5.1.4.5 Lighting and Communication 9.5-8 D 3r, 9-vii U t.. O i>' Amendment 33 6/30/77
SWESSAR-P1 TABLE OF CONTEtTPS (CONT) Section Page 9.5.1.5 Fire Detection and Suppression 9.5-8D 9.5.1.5.1 Fire Detection 9.5-8D 9.5.1.5.2 Fire Protection Water Supply Systems 9.5-8E 9.5.1.5.3 Water Sprinkler and Hose Standpipe Systems 9.5-8F 9.5.1.5.4 Carbon Dioxide Suppression Systems 9.5-81 9.5.1.5.5 Portable Extinguishers 9.5-8J 9.5.1.6 Specific Plant Areas 9.5-8K 9.5.1.6.1 Containment Structure 9.5-8K 9.5.1.6.2 Annulus Building 9.5-8K 9.5.1.6.3 Control Room 9.5-8L 33 9.5.1.6.4 Cable Spreading Room 9.5-8M 9.5.1.6.5 Plant Computer Room 9.5-8N 9.5.1.6.6 Switchgear Rooms 9.5-8N 9.5.1.6.7 Remote Safety Related Panels 9.5-80 9.5.1.6.8 Safety Related Battery Rooms 9.5-80
- 9. 5.1. 6 . 9 Turbine Building 9.5-8P 9.5.1.6.10 Diesel Generator Building 9.5-8P 9.5.1.6.11 Diesel Generator Fuel Oil Storage Areas 9.5-8P 9.5.1.6.12 Saf ety Related PuIrps 9.5-8P 9.5.1.6.13 Fuel Building 9.5-80 9.5.1.6.14 Solid Waste and Decontamination Building 9.5-8Q 9.5.1.6.15 Safety Related Water Tanks 9.5-8Q 9.5.1.6.16 Cooling Towers 9.5-8Q 9.5.1.6.17 Miscellaneous Areas 9.5-8Q
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<so 9-viii Amendment 33 6/30/77
SWESSAR-P1 TAIEE OF CONTE!TPS (CONT) Section Page 9.5.1.7 Interf ace Requirements 9.5-8R I References for Section 9.5.1 9.5-8R 9.5.2 Communications Systems 9.5-8R 33 9.5.2.1 Design Bases 9.5-8R 9.5.2.2 System Description 9.5-8R 9.5.2.3 Design Evaluation 9.5-10 9.5.2.4 Testing and Inspection Requirements 9.5-10 9.5.3 Unit Lighting System 9.5-10 9.5.3.1 Design Bases 9.5-10 9.5.3.2 System Description 9.5-11 9.5.3.3 Safety Evaluation 9.5-12 9.5.3.4 Testing and Inspection Requirements 9.5-12 9.5.3.5 Failure Analysis 9.5-12 9.5.3.6 Instrumentation Applications 9.5-13 9.5.4 Diesel Generator Fuel Oil Storage and 9.5-13 Transfer System 9.5.4.1 Design Bases 9.5-13 9.5.4.2 System Description 9.5-13 9.5.4.3 Safety Evaluation 9.5-14 9.5.4.4 Testing and Inspection Requirements 9.5-15 9.5.4.5 Instrumentation Applications 9.5-15 9.5.5 Diesel Engine Cooling Water System 9.5-15 9.5.5.1 Interface Design Information 9.5-15 9.5.6 Diesel Engine Air Starting System 9.5-15 9 5.6.1 Interf ace Design Information 9.5-15 9-viiiA / e . ,, Amendment 33 (!i O s/ 6/30/77
SWESSAR-P1 TART E OF CONTENTS (CONT) Section Page 9.5.7 Diesel Engine Lubrication System 9.5-16 9.5.7.1 Interface Design Information 9.5-16 9.5.8 Reactor Plant Gas Supply System 9.5-16 9.5.8.1 Design Bases 9.5-16 9.5.8.2 System Description 9.5-16 9.5.8.3 Safety Evaluation 9.5-17 9.5.8.4 Testing and Inspection Requirements 9.5-18 9.5.8.5 Instrumentation Applications 9.5-18 9.5.8.6 Interface Requirements 9.5-18 O q O i i. . . .U 9-viiiB Amendment 33 6/30/77
SWESSAR-P1 LIST OF TABLES Table 9.1.1-1 Deleted 9.1.2-1 Deleted 9.1.3-1 Fuel Pool Cooling and Purification System Principal Component Design Characteristics 9.1.3-2 Performance Characteristics of the Fuel Pool Cooling System 9.1.3-3 Deleted 9.1.4-1 Deleted 9.1.5-1 Fuel Handling and Storage Systems Interf ace 9.2.1-1 Reactor Plant Service Water System Principal Component Design Characteristics 9.2.1-2 Reactor Plant Service Water System Flow Requirements 9.2.1-3 Reactor Plant Service Water System Heat Load 9 . 2 .1 -4 Performance of the Reactor Plant Service Water System 9.2.2-1 Reactor Plant Component Cooling Water System Principal Component Design and Performance Characteristics 9.2.2-2 Reactor Plant Component Cooling Water System Flow Requirements 9.2.2-3 Reactor Plant Component Cooling Water System Flow Requirements 9.2.2-4 Performance of the Reactor Plant Component Cooling Water System 9.2.2-5 Reactor Plant Component Cooling Water Sy stem Interf ace Requirements 9 . 2 . 2 -6 Equipment Supplied by Reactor Plant 19 Component Cooling Water 9.2.3-1 Denineralized Water Makeup System Water Chemistry Limits 9-ix Amendment 19 7 , , , 12/12/75 0vO ioI
SWESSAR-P1 LIST OF TABLES (CONT) 9.2.3-2 Demineralized Water Makeup System Interface Requirements 9.2.7-1 Primary Grade Water System Chemistry Limits 9.2.7-2 Primary Grade Water System Interface Requirements 9.3.1-1 Deleted 9.3.1-2 Compressed Air Systems, Consequences of Component Failures 9.3.1-3 Compressed Air System Interface Information 9.3.2-1 Reactor Plant Sample System Design Interface Characteristics 9.3.3-1 Aerated Vents and Drains 9.3.3-2 Gaseous Vents and Drains 9.3.4-1 Chemical and Volume Control System Interface Information 9.3.6-1 NSSS Design and Operating Interface Parameters 9.3.6-2 Boron Recovery System Principal Component Design and Performance Characteristics 9.3.6-3 Assumptions Us ed in Activity Discharge Calculations 9.3.6-4 Boron Recovery System Failure Analysis 9.3.6-5 Boron Recovery System Interf ace Requirements 9.4-1 Plant Ventilation Systems and Modes of Operation 30 9.4.1-1 Control Room Air Conditioning System Outside Air Rates in Terms of Air Changes Per Hour 9.4.1-2 Control Room Air Conditioning System, Description of Operation 9.4.1-3 Control Building Ventilation Systems Consequences of Component Failures 30 9.4.1-4 Control Building Safety Related Air Conditioning i and Ventilating Systems Principal Component Design and Performance Characteristics
, Jsmendment 30 9-x (;. ;
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SWdSSAR-P1 IJST OF TABLES (COYP) Table 9.4.1-5 Control Room Area Volumes 9.4.2-1 Annulus Building Ventilation System Principal Component Design and Performance Characteristics 9.4.3-1 Solid Waste and Decontamination Building Ventila-tion System Principal Component Design and Performance Characteristics 9.4.4-1 Turbine duilding Ventilation Systems Principal Component Design and Performance Characteristics 9.4.5.1-1 Containment Atmosphere Recirculation Systen Principal Component Design and Performance Characteristics 9.4.5.1-2 Containment Atmosphere Recirculation System Operation Modes and Design Conditions of Air Handling Units 9.4.5.1-3 Containment Ventilation Systems Interf ace Require-ments 9.4.5.2-1 Containment Purge Air System Principal Component Design and Performance Characteristics 9.4.5.3-1 Containment Atmosphere Filtration System Principal Component Design and Performance Characteristics 9.4.6-1 Fuel Building Ventilation System Principal Component Design and Performance Characteristics 9.4.8-1 Control Rod Drive Mechanism Cooling System Charac-teristics Principal Component Design and Performance 9.5.1-1 Codes and Standards 9.5.1-2 Fire Protection System, Fire Hazard Analysis Data 9.5.1-3 Fire Protection System, Protection Features 9.5.1-4 Typical Values Used for Electrical Cable Construction g 9.5.1-5 Fire Stop Provisions 9.5.4-1 Diesel Generator Fuel Oil System Principal Com-ponent Design and Performance Characteristics 9-xA Amendment 33
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SWESSAR-P1 LIST OF TABLES (CONT) Ta ble 9.5.5-1 Diesel Engine Cooling Water System 9.5.6-1 Diesel Engine Air Starting System 9.5.7-1 Diesel Engine Lubrication System 9.5.8-1 Storage of Reactor Plant Gases Under Pressure O e.c O 9-xB Amendment 33 6/30/77
SWESSAR-P1 LIST OF FIGURES Fiqure 9.1.3-1 Fuel Pool Cooling System 9.1.3-2 Fuel Pool Purification System 9.2.1-1 Typical Reactor Plant Service Water Subsystem Train 9.2.1-2 Reactor Plant Service Water Load System Post-DBA Heat Load (Minimum Safeguards) 9.2.2-1 Reactor Plant Component Cooling Water System 9.2.2-1A Reactor Plant Component Cooling Water System 9.2.2-1B Reactor Plant Component Cooling Water System 9.2.2-1C Reactor Plant Component Cooling Water System 9.2.2-1D Deleted 19 9.2.2-1E Deleted 9.2.2-1F Reactor Plant Component Cooling Water System, 5 Sheets 9.2.3-1A Demineralized Water Makeup System 9.2.3-1B Demineralized Water Makeup System 9.2.7-1A Primary Grade Water System 9.2.7-1B Primary Grade Wdter System 9.2.8-1A Chilled Water System 9.2.8-1B Chilled Water System 9.2.8-2A Air Conditioning Chilled Water System 9.2.8-2B Air Conditioning Chilled Water System 9.3.1-1 Instrument and Service Air System 9.3.1-2 Containment Instrument Air System 9.3.2-1A Reactor Plant Sampling System 9.3.2-1B Reactor Plaist Sampling System 9-xi / - - Amendment 19 l ' '( 'c> : uJ 12/12/75
SWESSAR-P1 LIST OF FIGURES (CONT) Figure 9.3.2-1C Reactor Plant Sampling System, 3 Sheets 9.3.2-2 Turbine Plant Sampling System, Sheet 1 9.3.2-2 Turbine Plant Sampling Systam, Sheet 2 9.3.3-1 Aerated Vent and Drain System 9.3.3-2A Gaseous Vent and Drain System 9.3.3-2B Gaseous Vent and Drain System, 5 Sheets 9.3.4-1 Chemical and Volume Control Syster. Modification, Sheet 1 9.3.4-1 Chemical and Volume Control System Modification, Sheet 2 9.3.4-1 Chemical and Volume Control System Modification, Sheet 3 9.3.4-1 Chemical and Volume Control System Modification, Sheet 4 9.3.4-1 Chemical and Volume Control System Modification, Sheet 4A 9.3.4-1 Chemical and Volume Control System Modification, Sheet 5 9.3.4-1 Chemical and Volume Control System Modification, Sheet 6 9.3.5-1 Gross Failed Fuel Detector Modification 9.3.6-1A Boron Recovery System 9.3.6-1B Boron Recovery System 9.4-1 Reactor Plant Ventilation 9.4.1-1 Control Room Air Conditioning 9.4.1-2 Control Room Refrigeration Equipment Room 30 Ventilation 9.4.1-3 Control Room Air Conditioning, Chilled Water System 9-xii Amendment 30 1/28/77
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, LIST OF FIGURES (CONT)
Fiqure i 9.4.1-4 Emergency Switchgear and Safety Related Cable Spreading Area Air Conditioning. 30 9.4.1-5 Neutral Cable Spreading Room Ventilation 9.4.1-6 Electrical Tunnel Ventilation 9.4.1-7 Typical Diesel Generator Room Ventilation 9.4.1-8 Intake on Exhaust Hood, Control Building 9.4.2-1 An'.ulus Building (HVAC) 9.4.3-1 Solid Waste and Decontamination Building HVAC 9.4.4-1 Turbine Building (HVAC) 9.4.5.1-1 Containment Atmosphere Recirculation System 9.4.5.2-1 Containment Purge Air System 9.4.5.3-1 Containment Atmosphere Filtration System 9.4.6-1 Fuel Building (HVAC) 9.4.7-1 Medium Temperature Water Btdiding Heating System 9.4.7-2 Glycol Building Heating System 9.4.8-1 Control Rod Drive Mechanism Cooling 7; stem 9.5.1-1 Water Fire Protection System 9.5.1-1A Water Fire Protection System 9.5.1-2 CO2 Fire Protection System 9.5.1-3 Annulus Building Fire Areas, Sheet 1 9.5.1-3 Annulus Building Fire Areas, Sheet 2 30 9.5.1-3 A.mulus Building Fire Areas, Sheet 3 9.5.1-3 Annulus Building Fire Areas, Sheet 4 9.5.1-3 Annulus Building Fire Areas, Sheet 5 9-xiikb[, )(( Amendment 30 1/28/77
SWESSAR-P1 LIST OF FIG'JRES (CONT) Figure r 9.5.1-4 Control Building Fire Areas, Sheet 1 9.5.1-4 Control Coilding Fire Areas, Sheet 2 9.S.1-4 Control building Fire Areas, Sheet 3 30 9.S.1-5 Diesel Generator Building Fire Areas 9.5.1-6 Contair,;.ent Structure Fire Areas, Sheet 1 9.5.1-6 Containment Structure Fire Areas, Sheet 2 9.5.1-6 Containment Structure Fire Areas, Sheet 3 9.5.1-6 Containment Structure Fire Areas, Sheet 4 9.5.4-1 Typical E lesel Generator Fuel Oil System 9.5.8-1A Reactor Plant Gas Supply System 9.Su8-1B Reactor Plant Gas Supply System 9-xiv Amendment 30 1/28/77 1
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SWESSAR-P1 CHAPTER 9 AUXILIARY SYSTEMS 9.1 FUEL STORAGE AND HANDLING 9.1.1 New Fuel Storage The new fuel storage area is located in the fuel area shown in Fig. 1.2-8, and is designed to provide a safe, effective means for dry storage of the new fuel assemblies. 9.1.1.1 Design Bases The new fuel storage facility meets the following criteria:
- 1. The new fuel shall be maintained at a safe level of subcriticality even if accidentally flooded with unborated water. -
- 2. The new fuel storage facility shall be able to withstand normal operating loads as well as the safe shutdown earthquake (SSE} .
- 3. The new fuel storage area shall have storage capacity for at least 1/3 of the total fuel assemblies.
- 4. The new fuel storage area shall provide support and protection for the new fuel storage racks. j7 9.1.1.2 Facilities Description The new fuel storage area is shown in Fig. 1.2-8. The new fuel is transferred fram the new fuel storage area to the new fuel elevator, located in the spent fuel cask loading pit, using the 10 ton auxiliary hook of the 130 ton fuel building crane as described in Section 9.1.4. During initial core loading opere tions, the new fuel assemblies which cannot be stored in the new fuel storage area are stored in the spent fuel storage racks in the fuel pool. At this time the fuel pool ,is dry and the spent fuel bridge crane is used to transfer new fuel.
The fuel storage area is provided with embedments for the support of the new fuel storage racks. Spacings and elevations of embedments allow installation of the new fuel racks to their specific tolerances. The embedments are designed to withstand 17 the design loads transmitted by the racks. SWESSAR's design for Westinghouse RESAR-41 provides for temporary storage of new fuel inside containment during refueling operations as described in Section 9.1.6.
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SWESSAR-P1 The new fuel storage racks supplied by Westinghouse are described in RESAR-41 and RESAR-3S. The storage capacity of these racks is at least 1/3 core. Higher density fuel racks with smaller center-to-center fuel spacing may alternately be supplied. The design and technical justification for these will be described in the Utility-Applicant's SAR if they are utilized. The higher 20 density racks will also accommodate at least 1/3 core. CESSAR and B-SAR 205 do not include a fuel rack design. Thus the design and technical justification for the racks will be described in the Utility-Applicant's SAR if the CESSAR or B-SAR 205 NSSS is utilized. The design will accommodate at least 1/3 core. 9.1.1.3 Safety Evaluation The new fuel storage area is located in the Seismic Category I fuel area. Refer to Section 3.7 for details of the seismic design. Handling operations are minimal in transferring the new fuel assembly from the inspection area to the new fuel storage area, and finally to the new fuel elevator. New fuel assemblies are stored dry in a vertical position with a minimum center-to-center spacing to ensure a safe degree of subcriticality even if inadvertently flooded with unborated water. This analysis as well as the rack design is within the NSSS Vendor's scope. Effects of dropped objects are designed for in the new fuel area by preventing the main hook of the 130 ton fuel building crane from operating over the new fuel storage area. Power to the crane hook is cut off once it reaches the area between the spent fuel cask loading pit and the new fuel storage area. The auxiliary hook operates over the storage area for movement of the fuel assembly. The hoist loads of the auxiliary hook are limited to the design impact loads of the racks. The heaviest load to be transported over the new fuel area is a fuel element. The new fuel area supporting concrete and embedments can withstand the loads which result from the design impact load on the racks. Height of the drop is limited by physical arrangement and the use of limit switches on the hook. Uplift forces from the auxiliary hook, resulting from the crane exerting lif t on a stuck fuel assembly will not exceed NSSS Vendors' limits. All hoists operating in the fuel building have overload indicators and load-limiting devices. 9.1.2 Spent Puel Storage The fuel pool is located in the fuel area, shown in Fig. 1.2-8, and provides a safe, effective means for storing the spent fuel assemblies. The design ensures the capability for confinement and filtration of the atmosphere, including all contaminants, h within the facility. f, f f: _J ., , 9.1-2 Amendment 20 1/23/76
SWESSAR-P1 9.1.2.1 Design Bases The spent fuel storage f acility design is based on the following criteria:.
- 1. The spent fuel shall be maintained in a suberitical geometric array even if unborated water is accidentally used to fill the fuel pool.
- 2. The fuel pool shall have storage capacity for a minimum of 1-1/3 cores.
- 3. Water shielding shall be provided in the fuel pool to protect operating personnel from exposures in excess of the values in Chapter 12. These values allow limited access to the fuel pool area.
- 4. Uncontrolled radioactivity releases to the environment shall be prevented through the use of the supplementary leak collection and release system and the seismic design of the building.
- 5. The spent tuel storage facility shall be designed to withstand normal operating loads as well as Seismic Category I loads in accordance with the criteria established in Section 3.8.3.
- 6. The fuel building shall provide protection against tornado and external missiles.
- 7. By design the 130 ton fuel building crane shall be unable to travel over the fuel pool.
- 8. All penetrations into the fuel pool shall be at least 11 ft above the top of the fuel assemblies and siphon breakers shall be provided on all lines extending below this.
- 9. Failure or misoperation of permanently connected systens to the fuel pool shall not caose the uncovering of the stored fuel.
10.. The spent tuel storage area shall provide support and protection for the spent fuel storage racks. g
- 11. The fuel pool design shall conform to Regulatory Guide 1.13 (Section 3A.1-1.13) .
9.1.2.2 Facilities Description The fuel pool holds spent fuel assemblies in underwater storage for a suitable decay period af ter their removal f rom the reactor. Borated water is used to provide shielding for operating 9.1-3 ("' <
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SWESSAR-P1 personnel as well as the removal of decay heat generated in the spent fuel assemblies. During initial core loading, the fuel pool is kept dry for storage of new fuel assemblies. Normally, the primary grade water system (Section 9. ' 7) supplies makeup water to the fuel pool. Borated makeup water mdy be supplied trom the refueling water storage tank through the fuel pool purification system (Section 9.1.3) . In addition, two reactor plant service water trains each supply a makeup line to the fuel pool. The fuel pool cooling and purification system (Section 9.1.3) maintains the fuel pool water temperature at a safe level by providing adequate decay heat removal. The spent tuel shipping cask storage area is designed to accommodate one s pent fuel shipping cask. This area is separated from the fuel pool by a 6 ft thick concrete divider wall and the fuel transfer canal, providing separation from the spent fuel during the handling of the shipping cask. Makeup to the cask storage ureu is f rom the primary grade water system. The divider wall between the spent fuel pool and the fuel transfer canal is solid except for the cate. A dropped spent fuel cask cannot strike the divider wall because the f uel building crane , which moves the cask, does not pass over the spent fuel pool or the divider wall. Motion of the crane is parallel to the f uel transfer canal and the spent fuel pool, so the cask will not impact the divider wall directly even if the cask hits the shelf und tips backward (see Fig. 1.2-B). A crack in the cask storage pool as a result of a cask drop will cause a loss of water in the fuel transfer canal and the cask pool. However, the gate in the divider wall is watertight and the level in the spent fuel pool will remain constant. If the loss of water in the cask storage pool and the fuel transfer canal occurs coincident with tie removal of the gate, the water level in the spent fuel pool will not drop below the top of the stored fuel. Spent fuel storage rocks provide for vertical, underwater storage 01 irradiated f uel assemblies in a subcritical geometric array. The water in the fuel pool provides an effective and transparent shielding and coolant medium to allow for efficient fuel handling operations. The spent fuel storage area is provided with embedments for the support of the spent tuel storage racks. Spacing and elevations u of the embedments allow installation of the racks to the specific tolerances. The embedments are desianed to withstand the design louds transmitted by the rucks. As part of the annulus buildina, the fuel pool and the shipping cask storage area are designed as Seismic Category I structures ds Well aS being satety related (pA category I) . The concrete walls or the annulus buildino protect both areas from tornudo winds and missiles (Section 3.8.4). 9.1-4 Amendment 17 9/30/75
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SWESSAR-P1 The fuel pool and spent fuel shipping cask storage area are provided with a welded stainless steel liner to maintain the watertightness of these areas. Every liner seam weld has a channel welded to the back of the liner. Both liners are divided into several zones and all channels within a zone are interconnected to a pipe, which terminates at the fuel building sump. After completion of the construction of the pool, each zone will be leak tested by pressurizing through this pipe and sniffing for leakage using a halogen leak detector along every seam weld. During plant operation, any leakage that may occur in a seam will be collected in the backing channel. Leakage can be detected at the fuel building sump which has a high level alarm. The location of any leak can be detected by pressurizing the zone with the expected leak and observing bubbles in the pool. The spent fuel storage racks supplied by Westinghouse are described in RESAR-41 and RESAR-3S. The storage capacity of these racks is at least 1 1/3 cores. Higher density fuel racks with smaller center-to-center fuel spacing may aternately be supplied. The design and technical justification for these will be described in the Utility-Applicant's SAR if they are utilized. 20 The higher density racks will also accommodate at least 1 1/3 cores. ,CESSAR and B-SAR 205 do not include a fuel rack design. Thus the design and technical justification for the racks will be described in the Utility-Applicant's SAR if the CESSAR or B ,SAR 205 NSSS is utilized. The design will accommodate 1 1/3 cores. SWESSAR's design for Westinghouse RESAR-41 provides for temporary storage of spent fuel inside containment during refueling operations as described in Section 9.1.6. 9.1.2.3 Safety Evaluation In accordance with Regulatory Guide 1.13, the storage and handling of fuel in the fuel building are designed to protect the fuel, limit potential offsite exposures, and prevent loss of water from the fuel pool which may uncover the fuel. The fuel pool water is normally borated; however, even if the fuel pool is filled with unborated water, the geometric configuration ensures a safe degree of subcriticality. The spent fuel in the fuel pool is protected from tornado missiles by the concrete construction of the annulus building and fuel building. The fuel pool bridge crane is used to move the spent fuel from the spent fuel racks through the transfer canal to the shipping cask which is stored in the shipping cask storage area. Transferring the shipping cask from its storage area through the 9.1-5 /- ( i~j Amendment 20 dU 1/23/76
SWESSAR-21 decontamination area for washdown to the shipping aisle for loading is done by the fuel building crane. Since the 130 ton fuel building crane cannot pass over the fuel pool and the shipping cask storage area is separated from the fuel pool by the transfer canal and a concrete wall, there is no possibility of damage to the spent fuel or fuel pool if a shipping cask drop accident occurs. If the water . level drops approximately 6 in., an alarm sounds both locally and in the control room. Due to the elevation of all penetrations into the fuel pool and the use of siphon breakers on all lines extending below this, the minimum water level required for cooling and shielding cannot be violated by a pipe rupture. The concrete supporting the fuel pool area is an integral part of the annulus building and is seismically designed. See Section 3.7 for details of the seismic design. The fuel pool supporting concrete and embedments are designed to withstand the loads which result from the design impact load on the racks. The maximum load to be transported over the fuel pool is a fuel element in a fuel container. Equipment and instrumentation used for radiation monitoring in ti e fuel area are described in Sections 11.4 and 12.1.4. Section 9.4 describes the ventilation in the fuel area and fuel building. 9,1.3 Fuel Pool Cooling and Purification Systems ne fuel pool cooling and purification systems, shown in Fig. 9.1.3-1 and 9.1.3-2, remove decay heat from spent fuel stored in the fuel pool and provide adequate clarification and purification of water in the fuel pool, refueling cavity, and refueling water storage tank. Table 9.1.3-1 lists the principal component design characteristics for the systems. Table 9.1.3-2 gives the fuel pool cooling system performance characteristics. 9.1.3.1 Design Bases We design bases for the fuel pool cooling and purification systems are:
- 1. The temperature of the fuel pool water shall be below 120 F when 1/3 of a core is placed in the pool.
- 2. Purity and clarity of the refueling cavity and fuel pool water shall be maintained to permit observation of fuel assembly handling during refueling operations.
- 3. Filtration and ion exchange capability shall be provided to remove suspended and dissolved radionuclides to allow access to required areas. ~~
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- 4. Redundant Seismic Category I sources of makeup water shall be provided to maintain cooling in accordance with Regulatory Guide 1.13 (Section 3A.1-1.13) .
- 5. The cooling system and the reactor plant service water makeup lines are safety related (QA Category I) , Seismic Category I, and are designated SC-3 and designed to the requirements of ASME III, Class 3.
- 6. The purification portion is not safety related and is designated nonnuclear safety (NNS).
9.1-6A uoD ' Amendment 20 1/23/76
SWESSAR-P1 9.1.3.2 System Description The fuel pool water flows from the fuel pool through either of the two fuel pool cooling pumps and their associated fuel pool cooler, and then returns to the fuel pool. Since these components must maintain a safe temperature in the fuel pool, they are safety related (QA Category I) . The performance characteristics of the fuel pool coolers are listed in Table 9.1.3-2. Cooling for the fuel pool coolers is provided by the reactor plant component cooling water system (Section 9.2. 2) . The purification system provides means for filterino and demineralizing (1) the fuel pool water to improve optical clarity tor ease of underwater fuel handling, and to reduce radioactive contamination in the water, (2) the reactor cavity water during a ref ueling operation to improve optical clarity for ease of underwater fuel handling, and to reduce radioactive contamination in the water, and (3) the water stored in the refueling water storage tank (RWST) to reduce radioactive contamination in the water. This equipment is not safety related. This reouires two puritication pumps, two purification prefilters, one purification demineralizer, and one post filter. Either pump can be utilized with the prefilter to filter the water in the RWST, in the refueling cavity, or in the fuel pool. The flow rate for filtration is suf ficient to process the entire fuel pool water inventory in 24 hr. This water can also be purified by dive rting the flow through the purif ication demineralizer and post filter, which removes resin fines. In addition, by operating both pumps, the system can be used to purity the Iuel pool and simultaneously filter either the RWST or the refueling cavity. The fuel pool filters and demineralizer attain high radiation levels as radioactive materials accumulate. For this reason, the filters and the demineralizer are in shielded cubicles. Permanently installed skimmers remove particles on the surface of the fuel pool water, minimizing surface refraction. Some sources of impurities are corrosion products, hydroxides, and crud deposited in the reactor vessel. Fuel detects, Inconel 718, und other nickel bearing alloys are sources of soluble rad ionuclid es . These impurities and radionuclides enter the tuel pool through the fuel transfer tube in the f orm of a hydrated tilm adhered to the spent fuel assemblies. Boruted water is not necessary for reactivity control in the fuel pool. However, it is used to prevent diffusion of Doric acid during refueling. At this time the refueling cavity and fuel pool are interconnected. The fuel pool can be initially tilled @ with primary grade water (Section 9.2.7) and initially boratec by 9.1-7 Amendment 12
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SWESSAR-P1 manually emptying bags of boric acid crystals into the water. The fuel pool cooling system is used to recirculate and mix the boric acid solution in the fuel pool. A supply of borated water makeup to the fuel pool is provided by the connection from the RWST to the fuel pool purification system which can also be used for initial fill of the fuel pool. In addition to these two sources of makeup water, makeup from two separate reactor plant service water trains is provided. Drain lines to the purification pumps are provided at low points in the refueling cavity to remove the water remaining below the reactor vessel flange following refueling. The purification pumps are used to transfer the water from the refueling cavity to the RWST. These pumps can also drain and refill the upender area inside containment, utilizing the RWST for water storage and supply. The spent fuel cask pool is provided with a drain line to the purification pumps and a makeup line from primary grade water in order to drain and refill the upender area outside containment. Water drained from this area can be pumped either to the fuel pool or the boron recovery system for storage. The gate between the fuel pool and the fuel transfer canal shall remain closed to maintain water level in the fuel pool. However, the design of the gate is such that even with the gate open, the fuel pool cannot be drained below the top of the f uel racks. For BSW, the decay heat removal pumps fill and drain the refueling cavity using separate suction and discharge lines 33 (Section 5.5.7) . Each purification pump and decay heat removal pump drain line from the refueling cavity and upender area has a tee with one open branch, which is capable of blank flange closure. This branch is open during normal operation to prevent an accumulation of water in the refueling cavity or upender area. For refueling operations, a blank flange must be in place. All piping in the fuel pool has a vent hole drilled in each pipe to act as an anti-siphoning device . This vent is located above the spent fuel to prevent uncovering of the spent fuel. Piping, valves, and components of this system making contact with the fuel pool water are austenitic stainless steel which is corrosion resistant to the boric acid solution. Local samples are provided throughout the system to periodically check the gross activity, particulate matter, boric acid concentration, and component performance. The fuel pool cooling system for Westinghouse RESAR-41 services the in-containment storage area as described in Section 9.1.6. i O t, b ; 9.1-8 Amendment 33 6/30/77
SWESSAR-P1 9.1.3.3 Safety Evaluation The fuel pool cooling system consists of two separate, redundant trains of cooling, each with one pump and one heat exchanger. The system is Seismic Category I and Safety Class 3. The pumps are on two different emergency buses. A second pump is automatically started in case of a failure of the first pump. 9.1-8A Amendment 33 6/30/77
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SWESSAR-P1 The pumps are sized to handle flow to one heat exchanger only. The performance characteristics of the fuel pool cooling and purification systen are stated in Table 9.1.3-2 for the 1/3 and 1-1/3 core conditions with one and two coolers operating. The heat for Westinghouse are given in RESAR-41 and RESAR-3S. No heat load is given in CESSAR. American Nuclear Society Standard ANS 5.1 draft dated October 1971 is used to calculate the heat 20 load. B-SAR 205 does not give heat loads. However, decay heat curves supplied by B&W were used to calculate 1/3 and 1 1/3 core heat loads. At the design heat load of 1/3 core in the pool, both heat exchangers and pumps are required to maintain a fuel pool temperature of 120 F. Loss of one cooling train does not allow pool traperatures to reach unacceptable limits (see Table 9.1. 3-2) . With 1-1/3 core ir the pool, both heat exchangers and pumps are required to maintain a fuel pool temperature below 150 F. The temperature in the pool with loss of one cooling train at this time is also acceptable (see Table 9.1.3-2) . Two Seismic Category I sources of makeup water are provided. An alarm sounds both locally and in the control room if the liquid level in the fuel pool drops approximately 6 in. Piping penetrations are at least 11 ft above the top of the spent fuel so that accidental piping leaks, system misalignment, or a siphon path cannot reduce the water below this level. This minimum water level ensures adequate shielding and cooling of the stored fuel. The Seismic Category I service water system provides makeup to the fuel pool in accordance with Regulatory Guide 1.13 (Section 3A.1-1.13) . The two 3 in. pipes supply sufficient makeup to prevent the uncovering of the fuel pool due to boiling upon loss of both independent trains of cooling. Only one makeup line is required to provide 150 gpm at the design condition of boiling with 1-1/3 core in the fuel pool. To prevent contamnation of the pool from service water, a spool piece is included at the fuel pool end of the piping, with a blind flange normally in place. The spool piece is 3 in. diameter and approximately 1 ft long, and is stored alongside the pipe at the point of insertion. Upon loss or all pool cooling, the pool temperature rises to boiling in 1.25 hours. This time period is the shortest for the three NSSS Vendors and is conservative because of the following assumptions:
- 1) 1-1/3 core placed in the fuel pool, generating the maximum heat load.
- 2) Pool temperature prior to loss of all cooling is a maximum with one cooler operating (Table 9.1.3-2) 9.1-9 ea Amendment 20 6L uJ 1/23/76
SWESSAR-P1
- 3) No heat transfer from the pool to the supporting concrete structure or by evaporation.
- 4) No addition of cold makeup water to account for evaporative losses.
After 1.25 hours boiling is initiated with 24 ft of water depth (Fig. 1.2-8, C-E) over the stored fuel and assuming the design boil--of f rate of 150 gpm and no makeup, the fuel will not be uncovered before 18 hours. Each spool piece weighs approximately 25 lb, and at least one can be installed in less than the 1.25 hours required with the subsequent 18 hours providing additional margin. 9.1.3.4 Testing and Inspection Requirements The fuel pool level and temperature instrumentation is tested and calibrated on a periodic basis. Operating and standby ccxnponents are alternated periodically to verify operability of all equipment. Visual inspection of system components and instrumentation is conducted periodically. Safety Class pumps and valves require inservice testing as specified in Section 16.4.2. In addition, containment isolation valves require testing as specified in Section 16.4.4. The pool may have to be emptied for ine . ion or repair of the stainless steel liner. This process s infrequent and is performed using special portable piping and fitting when no fuel assem31ies are in the pool. 9.1.3.5 Instrumentation Applications The fuel pool has redundant level indicators and high and low level alarms on the main control board. Redundant temperature indicators are provided both locally and on the main control board with high and high-high alarms in the control room. The temperature alarms are set at 120 and 140 F associated with the maximum temperatures expected due to the heat output of 1/3 and 1-1/3 cores of spent fuel, respectively. A local temperature indicator is provided on each fuel pool cooler inlet and outlet. Fuel pool cooler outlet temperature is alarmed at the control room. Fuel pool cooler outlet flow is indicated locally. O a s .) s 9.1-10 Amendment 20 1/23/76
SWESSAR-P1 High and low fuel pool levels, high fuel pool temperature, and high fuel pool cooler outlet temperature activate a common alarm locally for each train. The fuel pool cooling pumps have indicating lights on the main control board. The discharges of all pumps have local pressure indicators. Upon a high temperature at the pool, the standby fuel pool cooling pump is started automatically. The cooling pumps can be operated manually either from the control room or the local panel. The purification pumps are operated from the local panel. A level indicator and a low level alarm are provided locally inside containment with sensors in the refueling cavity. For Westinghouse RESAR-41, this instrumentation is replaced by a level indicator and low level alarm in the control room and a local low level alarm inside containment. Level sensors are located in the in-containment storage area rather than in the refueling cavity. A local temperature indicator and alarm are also provided in the in-containment storage area. Flow through the fuel pool demineralizer is regulated manually and indicated locally. Local differential pressure indicators are used across the filters and demineralizers to indicate clogging. Radiation monitors installed in the fuel pool area alarm both locally and in the control room. Maximum purification flow can be established in the event of an alarm. 9.1.4 Fuel Handlina System The fuel handling system provides a safe, effective means for handling the .uel f rom the time of receipt at the plant until it leaves the plant. The refueling equipment and procedure are described in the NSSS Vendor's SAR. In addition to that equipment, SSW provides equipment for handling the transfer of the new fuel to the new fuel storage area, nnd the spent fuel 24 shipping cask to offsite transportation. Although not strictly part of the fuel handling system, the containment polar crane is also included in this section. This additional equipment is described herein. 9.1.4.1 System Description This additional equipment . includes : 24
- 1. 130 ton crane with 10 ton auxiliary hook
- 2. Snent fuel cask decontamination area
- 3. Spent fuel cask lifting beam 9.1- 11 r, on Amendment 24
- LU '! u L 4/23/76
SWESSAR-P1 24 4. Containment polar crane The new fuel can be received by truck or railroad car in the fuel building, where it is unloaded using the 10 ton auxiliary hook of the 130 ton fuel building crane. The new fuel containers are placed in storage at the 158-6" elevatica for fuel removal. At this fuel inspection area, stabilizing legs are positioned, the cover is removed, and the strong back is upended by the auxiliary hook. Once the new fuel handling tcol on the auxiliary hook is latched onto the uprighted fuel assembly, the fuel is unstrapped from the shipping container. The auxiliary hook and the new fuel handling tool support the fuel assembly during inspection. After in spection , the fuel is placed in the new fuel storage racks. The container cover is then replaced, and the process is repeated for the next assembly. The 10 ton auxiliary hook moves equipment in the fuel building and also transfers new fuel from the new fuel storage area to the new fuel elevator where the refueling equipment transfers the fuel to the reactor. Tne spent fuel is transferred from the fuel pool storage racks to the spent fuel cask in the spent fuel loading pool using the spent fuel bridge and the spent fuel handling tools. Once the cask is filled, the 130 ton crane lifts the spent fuel cask onto the shelf where the head is tightened and the long rigging is replaced with short rigging. The spent fuel cask is then washed down as it is raised out of the pool and transported to the h decontamination area where the cask radioactivity level is reduced below the limit specified in 10CFR71. Once the cask is cleaned, the crane then moves the cask to the shipping aisle where the spent fuel cask lifting beam is used to lower the cask to the rail car or truck f or shipment offsite. The containment polar crane is used to remove and install the reactor vessel closure head. The polar crane is a top-running, bridge-type, double girder, electric, overhead traveling crane running on a circular runway rail. The main hoist is used to transfer the closure head to and from the reactor vessel and storage stand. The crane's auxiliary hoist is used to handle 24 refueling and servicing equipment. Objects are not handled over an open reactor vessel other than those required for refueling. The polar crane normally operates only during routine refueling shutdown periods. The crane is restrained horizontally and vertically from seismic dislodg ement. The restraints and the crane's structural steel support are described in Section 3.8.3.1 and Table 3.2.5-1. bI ,bj 9.1-12 Amendment 24 4/23/76
SWESSAR-P1 9.1.4.2 Design Evaluation Fabrication of Stone & Webster supplied equipment is governed by 24 the codes and standards tabulated below (included in procurement specifications) :
- 1. Code of Federal Regulations, Title 29 Part 1910, 24
" Occupational Safety and Health Standards, Section 1910.179, Overhead and Gantry Cranes."
- 2. ANSI Standard B30.2.0, " Standard Safety Code for Overhead and Gantry Cranes."
- 3. C.M.A.A. Specification No. 70, " Electric Overhead Traveling Cranes."
- 4. AWS Code D1.1, " Structural Welding Code."
- 5. National Electric Code, Article 610, " Cranes and Hoists."
- 6. NEMA Standards MG1-Section I & II Standards Publication for Motors and Generators Some of the design f eatures of these codes are:
- 1. Hoist load liniting devices
- 2. A five-to-one rope safety factor based on ultimate breaking strength
- 3. End stops for bridge and trolley
- 4. A power supply disconnect
- 5. Earthquake restraints to prevent the bridge and trolley from disengaging their rails
- 6. Two redundant load holding brakes
- 7. Sheave design, incorporating guards, to prevent ropes from coming out of sheave grooves
- 8. Two redundant upper limit switches, each of different design
- 9. Safety lugs to prevent trolley drop in the event of a wheel or axle failure.
In the event of a crane malfunction which necessitates a lowering of the spent fuel cask, redundant holding brakes are .eleased and the emergency lowering function of the crane's controls lowers 24 the load at a safe rate without a-c power. The holding brakes 9.1-13 Amendment 24 4/23/76
SWESSAR-P1 may also be reapplied at any time to stop the load. If 24 necessaiy, a separate hoist or winch can be used to move the - trolley or bridge. If the cask does not need to be lowered for repairs to be effected, cooling of the raised cask is provided by water from the demineralized water makeup system through hose connections in the building, with reactor plant service water as a seismic backup system. The NSSS Vendor provides an upender in the fuel transfer canal at both ends of the transf er tube. In the event of an upender malf unction , both these areas can be isolated and drained of water to permit maintenance. Inside containment, a gate can be lowered between the refueling cavity and the upender area. Outside containment, the fuel transfer canal and cask pool can be isolated from the fuel pool by a gate. These areas can then be drained and refilled as described in Section 9.1.3. 24l All Stone S Webster supplied equipment is given both a no-load operational test and " rated load" test in the field prior to initial use. These tests meet all the requirements of ANSI B30.2.0 and 29CFR1910 Section 1910.179. Fuel storage equipment supplied by Stone S Webster is given shop and field leak tests and nondestructive examinations as applicable, and the equipment complies with 10CFR17 and 10CFR50, Appendix B. Fuel Building 9 The fuel building is designed such that the 130 ton crane does not pass over the fuel pool coolers, fuel pool pumpt or the new fuel area when loaded with spent fuel casks. This is accomplished by inteclocking a load cell with the track limit switches. When loaded beyond a predetermined amount set by the spent fuel shipping cask, the path of the 130 ton crane will be restricted. When the main hook and auxiliary hook load cells are both less than a preset amount representative of a single fuel assembly, the trolley is percitted to pass over the new fuel area. Thus, potential damage resulting from a shipping cask drop is prevented. The spent f uel cask cannot drop, unrestricted, a greater distance than specified in 10CFR71. 9.1.5 Interface Requirements Interface requirements for fuel storage and handling systems are given in the NSSS Vendors e SAR. Westinghouse Interface requirements are given in RESAR-41 and RESAR-3S. Table 9.1.5-1 lists the applicable requirements with the specific references and the Stone & Webster response to each. ,, 9.1-14 Amendment 24 4,23/76
SWESSAR-P1 Babcock & Wilcox Interface requirements are given in B-SAR 205. Table 9.1.5-1 lists the applicable requirements with the specific references and the Stone & Webster response to each. The following modifications are made to BSW equipment listed in 13-SAR-2 05 Table 9.1-6.
- 1. The length of the transfer tube is increased to 40 f t. 33
- 2. The span of the spent fuel handling bridge is increased to 32 ft.
Combustion Engineering Interface requirements are given in CESSAR. All applicable requirements and the specific references are listed in Table 9.1.5-1 dlong with the Stone & Webster response to each. The following requirements are not addressed since these are not necessary for the fuel handling and storage systems to perform their functions or overlap the Stone & Webster scope of design responsibility. Section 9.1.3.1.2 (2-26) Section 9.1.4.6 (2, 4, 8, 11, 14, 17, 19, 21, 22, 23, 26) Section 9.1.2.4 (3, 8) Section 9.2.7.1.3 (F) Secolon 6.3.2.21 (7th par) The fuel pool does not provide an alternative source of borated water to the CVCS as required in CESSAR Section 9.3.4.3.18. Utility-Applicant The size of fuel racks described in the Utility - Applicant's SAR shall allow storage of 1/3 core of new fuel and 1-1/3 core of spent fuel.
- 3 l \)
9.1-14A Amendment 33 6/30/77
SWESSAR-P1 9.1.6 In-Containment Puel Storage The SWESSAR design for Westinghouse RESAR-41 provides an in-containment storace area for storing new and/or spent fuel in order to facilitate faster refueling operations. 9.1.6.1 Desian Bases
- 1. The in-containment storace area shall be caoable of storing one-third core of fuel assemblies.
- 2. Capability shall be provided to isolate the storace area from the refueling cavity to pennit independent draining of the refueling cavity.
- 3. Water shielding shall be provided in the storace area when spent fuel is present to protect operating personnel from exposures in excess of the values in Chapter 12.
- 4. The in-containment storage area shull be desianed to withstand normal operating loads as well as Seismic Category I loads in accordance with the criteria established in Section 3.8.3.
- 5. Failure or misoperation of permanently connected systems shall not cause the uncovering of stored spent fuel.
- 6. The in-containment storage area shall provide support and protection for the NSSS Vendor's fuel storage racks.
- 7. All penetrations shall be at least 11 ft above the top of stored fuel assemblies, and siphon breakers shall be provided on all lines extending below this.
9.1.6.2 Facilities Description The in-containment storage area is Seismic Category I and QA Category I. Underwater storage is provided for one-third core of fuel assemblies. A welded stainless steel liner is provided in the area to maintain watertightness as described in Section 9.1.2.2. The spent fuel storage area is provided with embedments for the support of tne NSSS Vendors' fuel storage racks. Spacing and elevations of the embedments allow installation of the racks to the NSSS Vendors
- tolerances. The embedments are designed to withstand the design loads transmitted by the racks.
W 9.1 - 15' l , [j lC/ Amendment 12 6/16/75
SWESSAR-P1 The manipulator crane is used to service the in-containment ' storage area. New fuel can be transferred to this area and stored d uring operations prior to fuel loading into the reactor core. Spent fuel can be placed in this area during refuelina in order to speed completion of the fuel transfer operations around the core. A gate isolates the in-containment storace area trom the refueling cavity to permit draining of the cavity. Cooling for the stored fuel is provided by the residual heat removal system prior to dewatering the refueling cavity. After the storage area is isolated, one train of the fuel pool coolina system provides cooling (see Fig . 9.1. 3-1) . The cooling system is of sufficient capacity to remove the heat from this area as well as any fuel which is stored in the fuel pool (See Section 9.1.3.3). The in-containment storage area and the upender area inside containment are hydraulically connected and both are served by the fuel pool purification system independent of the refueling cavity. Capability for purification, filtration, drainac e, and makeup is provided by the fuel pool purification system by a drain line and supply line at the upender area. A portable cump 12 must be used to drain the in-containment storage area below the level of the partition between the upender and the stored fuel. 9.1.6.3 Safety Evaluation ! The in-containment storage area is designed to provide tenporary storage of fuel, to protect the fuel, to support the USSS Vendors' racks, and to prevent loss of water which may uncover the fuel. The fuel storage area water is normally borated; however, even if the area is fille d with unborated water, the ceometric configuration ensures a safe degree of suberiticality. The fuel stored in the in-containment storage area is protected from tornado missiles by the containment building. If water level in the area drops 6 in., an alarm sounds both locally and in the control room. Due to the elevation of all penetrations into the storace area and the use of siphon breakers on all lines extending below this, the minimum water level required for shielding cannot be violated by a pipe rupture. The gate separating the refueling cavity from the in-containment storago area shall remain closed when dewatering the refueling cavity to maintain water level in this storage area. However, the design of the gate is such that even with the gate open the stored fuel is not uncovered. W_ 9.1- 16 Amendment 12 6/16/75
SWESSAR-P1 A failure of the drain line on the upender area and subsequent loss of water will not uncover stored fuel since the top of the partition between these two areas is above the fuel racks and water cannot be drained from the fuel storage side of the partition. - Cooling for stored fuel is provided by one train of the fuel pool y2 cooling system. If this train is inoperable, the fuel pool purification system can be used to circulate water to and from the fuel pool where it can be cooled by the remaining cooling train. The containment structure serves as a controlled boundary to prevent possible offsite doses as a result of an accidental release of radioactivity from the fuel. 3I"o c; E 9.1-17 bbb Amendment 12 6/16/75
SWESSAR-P1 Table 9.1.1-1 has been deleted. 15 1 Of l Amendment 15
, n 8/8/75
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SWESSAR-P1 TABLE 9.1.2-1 has been deleted " 9 1 of 1 Amendment 15 c ', ' . u v v. . , i 8/8/75
SWESSAR-P1 TABLE 9.1.3-1 FUEL POOL COOLING AND PURIFICATION SYSTEM PRINCIPAL COMPONENT DESIGN CHARACTERISTICS Fuel Pool Cooling Pumps guantity 2 Capacity, gum 4,000 Head, ft later Design pressure, psig 150 Design temperature, F 220 Fuel Pool Heat Exchangers Westinghouse Quantity BSW C-E RES AR-41 RESAR-3 (1) Design heat load, Btu /hr/ heat exchanger 7.05x10s 7x106 9.1x106 7x106 30 Reactor plant component cool-ing water flow, gpm 2,500 2,500 2,500 2,500 Reactor plant component cooling water inlet temperature, F 105 105 105 105 Reactor plant component cooling water outlet temperature, F 111 111 112 111 l30 Fuel pool cooling flow, gpm 4,000 4,000 4,000 4,000 Fuel pool inlet temperature,F 120 120 120 120 Fuel pool outlet temperature, F 116 117 116 117 Design pressure, psig 150 150 150 150 Design temperature, F 220 220 220 220 Fuel Pool Purification Pumps Quantity 2 Capacity, gpm 400 Head, ft later Design pressure, psig 150 Desir,n temperature, F 220 Fuel Pool Purification Prefilter Quantity 2 Capacity, gpm 400 Design pressure, psig 225 Design temperature, F 250 Fuel Pool Demineralizer Quantity 1 Capacity, gpm 400 Design pressure, psig 225 Design temperature, F 250 1 of 2 ,,, ,c., Amendment 30 b L. O i ,c 1/28/77
SWESSAR-P1 TLBLE 9.1.3-1 (CONT) Fuel Pool Post Filter Quantity 1 Capacity, gpm 400 Design pressure, psig 225 Design temperature, F 250 ( ) Design heat loads for Westinghouse RESAR-41 and RESAR-3S were taken from Table 9.1-1 of their respective SAR. C-E heat loads are not given in CESSAR; thus American Nuclear Society draft Standard ANS-5.1 dated October 1971 is used to calculate the 1/3 and 1-1/3 core heat loads. BSW heat loads for 1/3 and 1-1/3 cores were taken from Section 9.1.5 of B-SAR-205. Ebr all NSSS l30 Vendors the design condition is 1/3 core in the pool with two fuel pool coolers operating to maintain a pool temperature of 120 F. 2 of 2 , in' Amendment 30 leu ! 'J 1/28/77
SWESSAR-P1 TABLE 9.1.3-2 PERFORMANCE CHARACTERISTICS OF T1!E FUEL POOL COOLING SYSTEM 2 Fuel Pool Ooolers Operatirus 1 Fuel Pool Cooler Operating Spent Fuel in Fuel Pool 1/3 Core 1 1/3 Core 1/3 Core 1 1/3 Care t a > Heat Imad in Fuel Pool, Btu /hr 18.2x108 5.2x10* 18.2x10* 52x10* Required Duty of One Fuel Pool Cooler, Btu /hr 9.1x106 26x10* 18.2x106 52x10* , 11 Maximum Fuel Pool Temperature, F 120 14 6 133 186 Flow Rates of One Fuel Pool Cooler, gpm Tube Side - Fuel Pool Water 4,000 4,000 4,000 4,000 Shell Side - Reactor Plant Component cooling Water 2,500 2,500 2,500 2,500 Reactor Plant Component Cooling Water Temperature, F 105 105 105 105 ( s 3 Heat loads in fuel pool wre taken f rom RESAR-41 Table 9.1-1. 'I Cw G 7
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SWESSAR-P1 TABLE 9.1.3-2 PERFORMAf4T CHARACTERISTICS OF Ti!E MJEL T*OOL COOLING SYSTEM 2 Fuel Pool Coolers Operatina 1 Fuel Pool Cooler Operating Spent Mael in Fuel Pool 1/3 Core 1 1/3 Core 1/3 Core 1 1/3 P re (83 Heat Innd in Puel Fool, Btu /hr 14.1x10* 48.7x106 14.1x106 48.7x106 kequired Duty of One Fuel Pool 33 Cooler, atu/hr 7.05x10* 24.35x10* 14.1x106 48.7x106. Maximum Fuel Pool Tenperature, F 120 150 131 195 Plow Rates of One Fuel Pool Cboler, gpn Tube Side - Fuel Pool Water 4,000 4,000 4,000 4,000 Shell Sice - Reactor Plant comp >nent Cooling Water 2,500 2,500 2,500 2,500 Reactor Plant Component Cooling Water Temperature, F 105 105 105 105 N ( m 3 Heat loads in f uel pool were taken f rcun Section 9.1.5 of B-SAR-205. C B6W 1 of 1 Amendment 30 1/28/17
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SNESSAR-P1 TABIE 9.1.5-1 (OONT) B-SAR 205 He<1uirement Reference _SWESSAR Re1erence support ring and the fuel transfer tube h dif f erential axial expansion will be aupport stand shall not exceed 1 inch less tthan 1 inch. unter all derlecti- a, including seanic displacement. Stared tools and equipment shall ne Sections 9.1. 5. 2.5 Storage of tools and equipment will be sucn arranged so that systems and comeponents and 9.1.5.15.2 that safety systems and components can not important to saf ety will not. oe <ta=. aged be damaged charing a seismic event. during a seismaic event. Omre reactivity monitoring instrumer.tation Section 9.1.5.10.3 Instrumentation shall be provided as re-including audible alarms shall be provided quired. A dilution accident analysis sna11 during ref ueling. A dilution accident ana- be described in the Utility-Applicant's SAR. lysis as described in B-SAR-205 shall oe performed. The suberiticality of the fuel str. rage Section 9.1.5.18.4 'ntis requirement shall be addressed in the array shall be denonstrated if tuel is Utility-Applicant's SAR. stored with a more limiting reactivity than described in B-SAR-205. Iow level alarms and radiation monitors sect r is 9.1.5.10.1 Level instrumentation is provided as de-shall be provided for the fuel pool and and 0.1.5.10.2 scribed in Sections 9.1.2 armi 9.1.3. Ra-refueling cavity. diation monitors are provided as described in Sectiu. 12.1.4. Support structures that mate with the Section 5.7.15.7c Suwort of the reactor vessel acen-ndates integral reactor vessel nozzle supports the forces and reactions of a postniated shall accomanodate the forces and reactions load drop acx:ident. of a postulated load drop accident. 13 Component dimensions and weights are given Section 9.1.5.15.5 Sections 9.1.1, 9.1.2, and 9.1.4 descrive in B-SAR-205 for B&W requireraents as inter- Table 9.1-6 the arrangement and operation of fuel land-f ace information for the aOP design. ling equipment. Section 9.1.5 describes the modif1 cations to B&W tuel handling equipment. Note 1: h ae requirements are safety related. 'the INESSAR-P1 design accnemodates and is compatible with all applicable f uel handling and storage interf ace rexIuirements O in 3-SAR 205. CX CN D) c3 va B&W 2 of 2 Amendment 33 6/30/77
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S%ESSAR-P1 TABLE 9.1.5-1 (CONT) CESSAR Requirement CESSAR Location SWESSAR Design tube as described in CESS.- A. meet all requirements. The fuel pool shall provide an alternate source Section 9.3.4.3 (0-4,R-4) The f uel geol will not provide this 21 of borated water to the CVCS. requirenent. C'N r_ .~ . C" [ .) C .? Li C-E 2 of 2 Ar.endment 21 2/20/76
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- 3. COOLING FOR IN-CONTAINMENT FWEL STORAGE IS APPLICABLE ONLY FOR WESTINGHOUSE PESAR-41. NO CONNECTIONS ARE PROVIDED AT THESE FDINTS FOR B&W OR C-E.
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- 1. THIS SYSTEM 15 NON-Nt'CLE Ak S AFETY (NNS) EICEPT WHERE 0THERilSE NOTED.
- 2. SC-2 AND SC-3 PORTIONS OF SYSTEM ARE SEISMIC CATEGORY 1.
- 3. REMOTE OlSPL AY INSTRUMENTATION IS SAFETY CL ASS 3. SEISMIC CATEGORY 1.
- 4. LEVEL INDICATOR AND LOW LEVEL ALARM IN THE CONTPOL ROOM ARE APPLICABLE ONLY FOR SESilNGHOUSE RESAR-41. B&W AND C-E WILL H AVE ONLY LOCAL LEVEL INDICATOR AND LOW LEVEL ALARM IN THE REFUELING CAVITY.
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SWESSAR-P1 9.2 WATER SYSTEMS The following reactor plant water systems are discussed herein: Reactor plant service water (Section 9.2.1) Reactor plant component cooling water system (Section 9.2. 2) Demineralized water makeup system (Section 9.2.3) Primary grade water system (Section 9.2.7) Chilled water system (Section 9.2.8) The potable and sanitary water system and the ultimate heat sink will be described in the Utility -Applicant's SAR. The reactor plant service water system and the reactor plant component cooling water system are the only Safety Class 3, Seinmic Category I water systems. These systems are necessary for the safe shutdown of the plant in transferring heat to the Safety Class 3, Seismic Category I, ultimate heat sink. ileat is transferred from the residual heat removal system and auxiliary systems during normal shutdown ard from the emergency core cooling system (ECCS) and the containment atmosphere recirculation coolers f allowing a design basis accident (DBA) . 9.2.1 Reactor Plant Service Water System The reactor plant service water system provides cooling water to remove the heat from the reactor plant auxiliary systems during all modes of o pera'_ ion . A typical subsystem for each reactor plant service water crain is shown in Fig. 9.2.1-1; Table 9.2.1-1 lists the principal c % nent design and performance characteristics. T @les 9.2.1-2 and 9.2.1-3 list the flow and heat load requirements for this system. Fig. 9.2.1-2 gives the reactor plant service water heat load vs time profile after a 14 DBA. 9.2.1.1 Design Bases 'Ite design bases for the reactor plant service water system are:
- 1. The system shall transfer the heat load from the reactor plar'c auxiliary syccens to the ultimate heat sink.
- 2. The system is denignated Safety Class 3, Seismic Ca* egory I, and the mechanical components shall be designed to ASME III, Class 3 requirements.
9.2-1 Amendment 1 f4 7/18/75 t t. ( UUU _
SWESSAR-P1
- 3. The system shall provide water during normal operation, accident, and shutdown conditions at the flow rates and tomperatures required to remove the component heat loads ar.d maintain the reactor plant component cooling water below the NSSS Vendor's limits during all conditions.
- 4. The system shall provide separation between trains during a DBA and loss-of power accidents.
t g 5. The maximum allowable service water temperature is 100 F. 9.2.1.2 System Description Tne NSSS Vendor requirements on the reactor plant component cooling water, which is cooled by the service water system, are identified on Table 9.2.2-5. They are 105 F during normal operation and 120 F during shutdown and DBA conditions. Based on 25 these requirements, the service water system is sized for a nominal 95 F during normal opera tions . The equipment design envelope which allows a 100 F_ service water temperature, is adequate to meet the 120 F shutdown and DBA component cooling water temperature limit. The reactor plant service water system consists of separate safety trains. The number of safety trains listed in Table 9.2.1-1 is based on the number of engineered safety features provided by the NSSS Vendor. Power (Section 8.3.1.1.2) for each safety train is provided by a separate emergency bus. The reactor plant service water pumps are located at the ultimate heat sirGc (Section 9.2.5) . Each train contains two pumps, two strainers, and associated piping and instrumentation. Each pump is sized for the maximum flow requirement and only one pump in each train is required to operate at any time. The remaining pump in each train is on standby and is started manually on a low flow or pressure alarm. The reactor plant service water system supplies cooling water to the reactor plant component cooling water heat exchangers (Section 9.2.2) , the diesel generator coolers (Section 9.5.5) , the control building water chillers (Section 9.4.1) , and the safety related unit coolers discussed in Section 9.4.2. Emergency makeup water is supplied to the fuel pool and the auxiliary feedwater system. During all modes of operation, each safety train provides cooling water to its associated reactor plant component cooling water heat exchanger which in turn can provide cooling for one residual heat removal (RHR) heat exchanger, one engineered safety features train, and o'ter auxiliary systems equipment. UvU i ' '- 9.2-2 Amendment 25 4/30/76
SWESSAR-P1 There are no cross connections between trains for Westinghouse RESAR-41, Combustion Engineering, and BSW. For Westinghouse j) RESAR-3S, cross-connect piping is used to supply the three charging pump cubicle unit coolers f rom two trains. The chemical control of the water in the system is maintained by the water treatment systems associated with the ultimate heat sink and is discussed in Section 9.2.5. 9.2.1.3 Sarety Evaluation The reactor plant service water system is separated into saf ety trains associated with their corresponding safety trains in the reactor plant component cooling water system, control ou11 ding water chillers, unit coolers, emergency fuel pool makeup, duX111ary feedWater makeup, and diesel generator coolers. This separation enables the system to withstand a single failure with no effect upon the shutdown capability of the safety related systems. The system designs for Combustion Engineering, Westinghouse RESAR-41, and B6W consist of completely independent trains. For Westinghouse RESAR-3S, cross-connect piping for the charging pump 33 cubicle unit coolers includes two sets of locked closed manual valves providing a double barrier between trains. Under no circumstances are more than two valves open. A break in the service water piping is considered unlikely for the rollowing reasons:
- 1. Piping is Sarety Class 3 and is buried or ocated within tornado protected and seismically designed buildings.
- 2. Piping is designed to meet Seismic Category I require-ments.
The service water pumps are located at the ultimate heat sink. The ultimate heat sink provides a reliable source of water and shall meet the provisions or long term cooling identified Dy bvU LiJ 9.2-3 Amendment 33 b/30/77
SWESSAR-P1 Regulatory Guide 1.27 (Section 3A .1 - 1. 2 7) or other comparable guidelines. Euch service water pump is sized to handle the DBA requirements with margin. If one pump requires maintenance, the remainino pump in the safety train can take its load. This procedure does not require a technical specification limit (Section 16.3. 3.4) . Table 9.2.1-4 gives the minimum performance requirements 01 the reactor plant service water system. 9 . 2 .1. 4 Testing and Inspection Requirements The system is inspected during installation to ensure proper installation. Pumps and valves in the reactor plant service water system require inservice testing as specified in Section 16.4.2. Inservice inspection of piping is also specified in Section 16.4.2. Isolation valves are provided at both ends of the buried portions of piping to permit hydrostatic testing as required. Flow and temperature data are taken periodically, during normal unit operation, to verify the heat transfer capabilities of the heat exchangers. 9.2.1.5 Instrumentation Applications The pumps and remotely operated valves have provision for manual operation from the control room. The indicating lights for monitoring of operating status of equipment are located adjacent to the manual controls. During normal operation, the pressure and flow in the service water supply headers are monitored by indicators and alarms in the control room. Low flow and pressure alarms on each train alert the operator to start the standby pump. The reactor plant service water temperature is monitored at the discharge header of the service water pumps by a local temperature indicator and an indicator and recorder on the main control board. Radiation is monitored downstream of the reactor plant component cooling water heat exchangers to detect any radioa ctive nuclide transfer across the tube bundles. Return header flow is indicated in the control room. Flow mismatch between pump discharge and return header flows is alarmed in the control room. 9.2-4 Amendment 25 4/30/76
SWESSAR-P1 9.2.1.6 Interface Requirements The Utility-Applicant's design of the ultimate heat sink shall 25 meet the requirements imposed on it by the service water system, as specified in Section 9.2.5. Interface information provided in Westinghouse RESAR-41 and RESAR-3S Section 9.2.1 is not applicable since Stone & Webster supplies the rear: tor plant component cooling water system from which the reactor plant service water system removes heat. BSW and C-E impose no interface requirements in Section 9.2.1. Interface points between the Utility-Applicant's system and the reactor plant service water system are listed on Fig. 9.2.1-1. 9.2.2 Reactor Plant Component Cooling Water System The reactor plant component cooling water system provides an intermediate cooling loop for removing heat from reactor plant auxiliary systems and transferring it to the reactor plant service water system ( iection 9.2.1) . Figure 9.2.2-1 shows the system piping and Table 9.2.2-1 lists the principal data for the system components. Tables 9.2.2-2 and 9.2.2-3 J ist the component cooling water heat loads, and tiows for the olant system described in SWESSAR and also those auxiliary systems described in the NSSS Vendor's SAR which Stone & Webster does not supply. \25 Table 9.2.2-4 gives the minimum performance requirements of the reactor plant component cooling water system. 9.2.2.1 Design Bases The design bases for the reactor plant component cooling water are:
- 1. The system is designated Safety Class 3 (SC-3) and ASME III Code Class 3 for those portions which are required for safe shutdown and to maintain cooling for the spent fuel.
- 2. The SC-3 portions of the system shall be Seismic Category I and tornado protected.
- 3. The system shall supply sufficient cooling water at or below the NSSS Vendor's temperature limits (see Table 9.2.2-5) during all conditions.
- 4. The subsystems are physically separated and can be isolated from each other.
A reactor plant component cooling water temperature of 105 F for normally operating equipment was used for equipment sizing. This 9 temperature meets NSSS Vendor's requirement described in Table 9.2.2-5. For the accident and shutdown conditions, the
,v
._ i J 9.2-5 Amendment 25 4/30/76
SWESSAR-P1 NSSS Vendor's temperature limit described in Table 9.2.2-5 is also met. 9.2.2.2 System Description The system is subdivided into separate safety trains, each of which consists of two pumps, two heat exchangers (aae heat exchanger per train for Westinghouse RESAR-41 only) , and associated cooling train. Power for each train is provided by separate evergency buses (Section 8.3.1) . The number of safety trains listei in Table 9.2.2-1 is based on the number of engineered safety features systems provided by the NSSS Vendor. The ccanponents supplied by the reactor plant cmponent cooling water system are listed on Table 9.2.2-6. Physically separated component cooling water trains supply safety related equipnent. Based on equipment locations and comparable flow, each train supplies a portion of the non safety related equipment through air operated isolation valves. Crossties with normally closed manual valves connect safety trains outside of the isolation valves. These crossties are necessary only upon loss of one train 's cooling car,>acity in order to supply the minimum flow to the af fected train for norm =il plant operation. During a DBA or loss of power condition, one set of air operated isolation valves per train must close in order to isolate the train from its NNS equipment and the other trains. Each train has two component cooling water pumps, an A pump sized for normal operation, and a B pump sized for maximum flow conditions. The A pump is the preferred pump during normal operation and the B pump is required to operate when the residual heat removal heat exchangers require corponent cooling water. During normal operation, the B pump in each train is started manually on a low flow or pressure alarm. Only one pump in each train is required to operate at any time. The reactor plant component cooling water system for BSW and Westinghouse RESAR-3S supplies three centrifugal charging pumps. Two pumps are independently supplied from different trains and the third the third pump can receive component cooling water from either train. If either of the independently supplied pumps is down for maintenance, the third can be supplied from the affected pump's train. Two sets of locked closed manual valves separate the third pump from each train. At all times, this flow path between component cooling water trains is separated by at least two closed valves. 25 The reactor plant component cooling water systems for BSW and C-E include a motor operated valve on each supply and return line for the reactor coolant pumps. These valves close upon receipt of a CIB signal following a DBA. This feature prevents the loss of a reactor plant component cooling water train due to a component
!!( a'
'i a u Lnu 9.2-6 Amendment 25 4/30/76
SWESSAR-P1 cooling water pipe break inside the reactor ce >lant pump cubicle where a reactor coolant system rupture has occurred. The reactor plant component cooling water systems for Westinghouse RESAR-41 and RESAR-3S supply four reactor coolant pumps from two trains. Each reactor coolant pump requires cooling water for two motor air coolers, an oil cooler, and a thermal barrier heat exchanger, which is integral with the pump. Each reactor coolant pump has one supply line and one return line for the oil cooler and motor air coolers. A motor operated valve on each line closes on a CIB signal as described above. Ea7h reactor coolant pump thermal barrier heat exchanger has a separate set of supply and return lines. 'Ivo flow elements are included on each return line to sense high flow resulting from a rupture of the thermal barrier heat exchanger and the subsequent release of reactor coolant into the component cooling water system. One motor operated valve and a check valve are located upstream of the thermal barrier heat exchanger and two motor operated valves downstream. The motor operated valves are closed when high flow is sensed by the flow elements. The component cooling water piping and in-line instrumentation, up to and including the three motor operated valves, are designed for reactor coolant pressure and temperature. The motor operated valve on the supply line and the motor operated valve f arthest downstream are closed upon a CIB signal as described above. The reactor plant component cooling water system is designed as a closed system. Variations in volume, due co temperature changes, are acconmodated by the surge tanks in each train. The surge tank is the highest point of each train. Makeup to the system is provided by the demineralized water makeup system (Section 9.2.3) through supply piping to the surge tanks. A chemical addition tank is connected to the pump discharge piping. To add chemicals to the subsystem, the tank is isolated, drained, and filled with the desired chemicals. The tank isolation valves are then opened and the discharge pressure of 'he operating pump forces water through the tank, thus injecting the mixture into the system. The desired water chemistry is obtained by the addition of appropriate chemicals for corrosion inhibition and pH control. The nominal ccxnponent cooling water temperature is 105 F. The component cooling water heat exchanger is sized for a ncrainal service water temperature of 95 F. The component cooling water 3 limit during shutdown and DBA conditions of 120 F can be met with the limitation of 100 F on the service water temperature. 9.2.2.3 Safety Evaluation The system is separated by design into separate safety trains which have closed cross-connections between trains. These cross-9.2-7 I>v - c / Amendment 25 4/?0/76
SWESSAR-P1 connections join the NNS portions of each safety train outside of the air operated isolation valves. These valves either fail closed or close on a CIA signal to isolate each train from its NtiS equipment and the other trains. The B pump in each train is required to operate following a DEA. If this pump is down f or maintenance, a technical specif ication limit, as stated in Section 16.3.3.3, is in effect. The system design for BSW and Westinghous? RESAR-3S allows either train to supply the third centrifugal charging pump. Piping from each train has two sets of locked closed manual valves. Under all circumstances, at least two sets of valves are always closed. Automatic isolation following a DBA of all component cooling water lines to and f rom the reactor coolant pumps is provided by motor operated valves that close upon receipt of a CIB signal (except for C-E, where the oil coolers and motor air coolers are automatically isolated upon receipt of a CIA signal along with the remainder of the nonnuclear safety equipment) . This isolation prevents the loss of a component cooling water train due to the eff ects of a reactor coolant system rupture adjacent to the component cooling water piping inside the reactor coolant pump cubicle. Protection against the release of rea ctor coolant into the component cooling water systems of Westinghouse RESAR-41 and RESAR-3S following the rupture of a thermal ba rrie r heat exchanger is provided by douole isolation valves upstream and downs tream of the heat exchanger. Redundant flow elements are provided downstream of each thernal barrier heat exchanger to O (; , O 9.2-8 Amendment 25 4/30/76
SWESSAR-P1 close the isolation valves. 'Ivo motor operated valves and one flow element are powered from the same emergency bus as their associated component cooling water train. These two valve receive CIB signals as described above. The remaining motor operated valve and flow element are powered from a different emergency bus. The piping and in-line instr mentation, up to and including the three motor operated valves, are designed for reactor coolant pressure and temperature. This design accommodates a single failure without the loss of automatic isolation capabilities The reactor plant component cooling water system for Westinghouse RESAR-41 and RES.*R-3S supplies two reactor coolant pumps from each of two trains. Loss of cooling water to two pumps simultaneously due to the failure or misoperation of either the containment penetration valves or the motor operated valves on the supply and return lines from the component cooling water header is prevented by the following design features: 1 ., Each reactor coolant pump has a separate set of supply and return lines from its respective trains' component cooling water headers inside the containment. Each of these lines has a motor operated valve that closes upon receipt of a CIB signal for automatic isolation following a DBA as described in Section 9.2.2.2. The use of separate lines, each with isolation valves, prevents a failure or misoperation from affecting two reactor coolant pumps simultaneously.
- 2. Electrical power is removed at all times from the motor operated valves outside containment. These valves do not receive an automatic signal and manual operation from the control room requires prior manual restoration of power (ref erence Fig. 7.8.2-30A) . 3 Leakage into the reactor plant component cooling water system through its components may result in slight contamination.
Provisions to preclude the possible spread of radioactive contamination include the capability of isolating each heat exchanger by manually closing the inlet and outlet component cooling water valves. Welded construction is used extensively throughout the system to minimize the possibility of leakage from pipes, valves, and fittings. Potentially radioactive fluids cooled by the system are isolated from the environment by two barriers. The first barrier is the tube walls of the heat exchanger where the potentially radioactive fluid is cooled by the component cooling water. The second barrier is the tube walls of the component cooling water heat exchanger where component cooling water is cooled by the reactor plant service water.
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9.2-9 Amendment 25 4/30/76
SWESSAR-P1 Thus two barriers in series, with a radioactivity alarm in the intermediate reactor plant component cooling water system, ensure that no radioactivity is released to the environment through this system. Inleakage to the component cooling water system is indicated by an increasing level in the surge tank which alarms on high level. The surge tank also alarms on low and low-low levels. The low-low level allows sufficient volume to operate the train for 30 days following a DBA assuming an NNS pipe break and subsequent automatic closure of the NNS equipment supply and return piping plus the maximum expected leakage from system components. The NNS equipment isolation valves automatically close upon low-low level in the surge tank to prevent draining of the surge tank in the event of an NNS pipe break. 9.2.2.4 Testing and Inspection Requirements The component cooling water pumps require inservice testing as specified in Section 16.4.2. Safety class valves require testing as specified in Section 16.4.2 (for all safety class valves) and Section 16.4.4 (for containment isolation valves). Components are accessible for periodic visual inspections. 9.2.2.5 Instrumentation Applications Temperature Instrumentation Local temperature indicators are located on the discharge side of all heat exchangers and pumps supplied with reactor plant component cooling water. The component cooling water heat exchanger is equipped with a temperature transmitter on the downstream side with a signal to an indicator and high and low temperature alarms on the main control board. A bypass line is provided around the component cooling water heat exchanger. In event of low service water temperature, a temperature control valve on this line regulates bypass flow to maintain component cooling water temperature above the limits set by the NSSS Vendors. Temperature is controlled in each of the following pieces of equipment by temperature control valves located on the downstream side of each:
- 1. Gaseous waste system trim cooler
- 2. Letdown heat exchanger (RESAR-41, RESAR-3S, and C-E
- only) , ,
t', b d 9.2-10 Amendment 21 2/20/76
SWESSAR-P1
- 3. Reactor coolant pump oil coolers (C-E only)
Flow Devices Flow in the system is measured at the outlet side of the com-ponent cooling water heat exchanger, is indicated, and low flow alanned on the main control board. Flow is indicated locully at the outlet of each RHR heat exchanger. High flow alarms on the main control board are provided for Westinghouse RESAR-41 and RESAR-3S from each of the two flow elements located downstream of the reactor coolant pump thermal 21 barrier heat exchangers. Motor operated isolation valves upstream and downstream of the thermal barrier heat exchanger are closed automatically upon high flow sensed by the flow elements. Pressure Instrumentation On the discharge header of the component cooling water heat pumps, a pressure tranmaitter is provided with indication and alarms on the main control board. A bypass line with a pressure control valve is provided between the outlet of the component cooling water heat exchanger and the suction of the component cooling water pumps. The pressure control valve regulates bypass flow to maintain a cons' cunt differential pressure between these two points. A pressure control valve is provided on the downstream side of the rollowing components to vary cooling water flow to maintain a constant outlet temperature of the cooled fluid:
- 1. Boron evaporator condenser
- 2. Liquid waste evaporator condenser
- 3. Laundry waste evaporator condenser
- 4. Regenerant waste evaporator condenser
- 5. Degasifier condenser Level Instrumentation Level in the reactor plant component cooling water surge tanks is alarmed for high, low, and low-low levels on the main control board. Upon a low-low level, the NNS equipment isolation valves are automatically closed.
ff ' ' ' U v v( cc i 9.2-10A Amendment 21 2/20/76
SKESSAR-P1 Radiation Instrumentation Radiation levels in the a ctor plant component cooling water systems are monitored in the . uS portion of each train and high radiation levels are alarmed on the main control board. 9.2.2.6 Interface Requirements Tae reactor plant component cooling water system meets the applicable interface requirements given in the USSS Vendors' SAR. Fig. 9.2.2-1D lists the interface points between the USSS Vendors' systems and the reactor plant component cooling water system. Ta ble 9 . 2. 2-5 lists the applicable interface requirements and the specific references on the NSSS Vendors' Sia and SWESSAR where these interfaces are addressed. The Utility-Applicant shall supply reactor coolant pumps that shall be demonstrated to be capable of operating for more than 20 minutes without component cooling water flow and consequent loss of pumping capability. If the Utility-Applicant cannot supply such pumps, a) The safety grade flow instrumentation (reference g Section 7.3.3.7) shall be modified to initiate automatic protection of the plant, or b) The component cooling water supply to the pump shall be capable of withstanding a single active failure or a moderate energy line leakage crack (as defined in Branch Technical Position APCSB3-1, Protection Against Postulated Piping Failures in Fluid Systems Outside Containment, dated November 24, 1975, as appended to NRC Standard Review Plan 3.6.1) . 9.2.3 Demineralized Water Makeun System The demineralized water makeup system supplies water to the reactor plant and turbine plant systems listed below for makeup to ta nk s , sample sink flushing, and other miscellaneous requirements. Demineralized water is also supplied to the NSSS Vendors' systems and equipment as required. Hose connections are provided throughout the plant for general use of clean water. The demineralized water makeup system is shown in Fig. 9.2.3-1 and the water chemistry limits are shown in Table 9.2.3-1. 9.2.3.1 Design Bases The demineralized water makeup system design bases are:
- 1. The system shall supply demineralized water for makeup to other systems, as required.
- 2. The system is not saf ety related and is designated non- .
nuclear safety. . 9.2-10B Amendment 25 4/30/76
SWESSAR-P1
- 3. Water s upplied to the primary grade water system shall be deaerated to meet primary grade water chemistry requirements.
9.2.3.2 System Descr j,pti on The demi'oralized water storage tark (DNST) receives water from the water tleatment facility (Section 9.2.9) and stores it prior to distribution. Demineralized water is supplied to:
- 1. Reactor plant component cooling water surge tanks (Section 9.2.2)
- 2. Primary grade water storage tank (Section 9.2.7) -
- 3. Chilled water surge tank (Section 9.2.8) 4 Reactor plant sampling sink (Section 9.3.2)
- 5. Turbine plant sampling sink (Section 9.3.2)
- 6. Condensate storage tank (Section 10.4.7)
- 7. Turbine plant component cooling surge tank (Section 10.4.9) f 8. Auxiliary boiler condensate tank (Section 10.4.12)
- 9. NSSS Vendor equipment requirements Fig. 9.2.3-1
- 10. Radioactive solid waste system catalyst tdnk and uroa formaldehyde processing equipment (Section 11.5) --
19
- 11. Reactor vessel support surge tank
- 12. Condensate polishing system The size of the DWST is determined by the duration of the maximum demand on the system.
A deaerator is provided in the supply line to the primary grade water tanks. This allows water supplied to the reactor coolant system from the primary grade water system to meet the USSS Vendor's chanistry requirements. 9.2.3.3 Safety Evaluation The demineralized water makeup system is not safety related.
/ , ,, ,
Uv U cm s 9.2-11 Amendment 19 12/12/75
SWESSAR-P1 9.2.3.4 Testing and Inspecticn Requirements
'Ihe DWST is hydrostatically tested after construction. Samples are taken periodi.eally from the demineralized water makeup system to determine oxygen content, pH value, and possible contamination or deterioration.
9.2.3.5 Instrumentation Applications The level of the DWST is monitored in the control room, and alarms are provided for both high and low levels. A pressure switch on the discharge header of the demineralized water transfer pumps provides the control in maintaining a constant header pressure. The preferred pump is started automatically on low header pressure. The failure of this pump to start requires the manual operation of the second pump. 9.2.3.0 Interiace Requirements Interface requirements with Westinghouse are described in Table 9.2.3-2. Interface requirements with the Combustion Engineering c? cmical and volume control system as modified and described in Section 9.3.4 are addressed by the primary grade water system (Section 9.2.7.6) . BSW demineralized water 30 interface requirements are addressed in Tables 9.2.3-2 and 9.2.7-2. The Utility-Applicant's water treatment system shall supply makeup water to the demineralized water storage tank. This water shall meet the chemistry requirements of SWESSAR Table 9,2.3-1. Fig. 9.2.3 -1 lists the interface points of the demineralized water makeup system. 9.2.4 Potable and Sanitary Water Systems The potable and sanitary water systems are di .ussed in the Utility-Applicant's SAR. 9.2.5 Ultimate Heat Sink The ultimate heat sink is discussed in each Utility-Applicant's SAR; however, the design of the ultimate heat sink shall meet the following interface requirements.
- 1. The reactor plant service water pumps shall be flood protected and missile protected.
- 2. The reactor p service water trains shall be physically separate...
< , e ueo m 9.2-12 Amendment 30 1/28/77
SNESSAR-P1
- 3. Pump net positive suction head shall be sufficient to meet the design characteristics of the service water pumps.
- 4. The reactor plant service water system shall not exceed the temperature required to maintain reactor plant component cooling water below the NSSS Vendor's limits as stated in Section 9.2.1.2.
- 5. The ultimate heat sink shall be capable of removing the heat loads in Table 9.2.1-3 and Fig. 9.2.1-2.
- 6. The component cooling water heat exchanger and the service water pump capacity (including number of pumps) will be optimized within the design bases of Sections 9.2.1.1 and 9.2.2.1 in conjunction with the ultimate heat sink design 9.2.6 Condensate Storage Facilities The condensate storage tank is discussed in Section 10.4.7.
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L v v,, m uj 9.2-12A Amendment 30 1/28/77
SWESSAR-P1 9.2.7 Primary Grade Water System h The primary grade water system is a storage and distribution system that supplies reactor plant auxiliary systems exclusively. The system is shown in Fig. 9.2.7-1 and the water chemistry lianits are shown in Table 9.2.7-1. 9.2.7.1 Design Boses The design bases for the primary grade water system are:
- 1. The sys tem ahall be capable of supplying sutticient makeup water to reactor plant auxiliary systen.s.
- 2. The primary grade water storage tanks shall be capa'le of storing water produced by the radioactive liquid vaste s yst em (Section 11.2) and the boron recovery systen (Section 9.3.6) .
- 3. No part of the system is safety related except tor the containm eT. t isolatien valves and interconnecting piping.
These v alves and piping shall be Safety Class 2 and shall meet the requirements of ASME Section III, Class 2.
- 4. The prinary grade water storage tanks shall be capable of providing sufficient water for the chemical and volume control system (NSSS Vendor's scope) and shall meet the chemistry requirements of Table 9.2.7-1.
9.2.7.2 System Description The primary grade water system is used exclusively for reactor plant systems; the system consists of two primary grade water storage tanks, two primary grade water transfer pumps, and associated piping bastrumentation and controls. Primary grade vater consists principally of reactor coolant letdown that har. been stripped of dissolved gases and distilled to eliminate boric acid, cesium, and other radioactive material in the boron recovery system (Section 9.3. 6) . Carryover from the boron recover y system causes the primary grade water system to have a boron concentration of less than 5 ppm and a slight amount of radioactivity (5 x 10-* uCi/cc maximum). The initia? fill and makeup supply for the primary graf ? water system is f rom the demineralized water system (Section 9.2.3) . Primary grade water is used for the following purposes:
- 1. To provide makeup water to the reactor coolunt system via the chemical and volume control system of the USSS Vendor (see Section 9.2.7.6).
9.2-13 , ,,, Amendment 19 bc a cco 12/12/75
SWESSAR-P1
- 2. To provide water for the seals on the following pumps:
- a. Boron evaporator reboiler pump
- b. Waste evaporator reboiler pump
- c. Waste evaporator feed pumps
- d. Boron evaporator feed pumps
- e. Regenerant waste evaporator reboiler pump
- 3. To supply water to the following:
- a. Puel pool
- b. Spent resin surge tank
- c. Liquid waste system
- d. Regenerant waste system
- e. Boron recovery system
- f. Spent fuel cask pool
- g. Gaseous vent and drain system
- h. NSSS Vendor equipment requirements (Fig. 9 . 2 . 7-1 )
- i. Lithium hydroxide tank (BSW only)
Boron test tanks are provided in the boron recovery system to prevent inadvertent boron contamination of the primary grade water storage tar.ks. If the decision to further reduce the boron concentration in the distillate is made after the distillate has been tested at the test tanks, the tank contents can then be pumped through the applicable demineralizers and filters to the primary grade water storage tanks. Water can be sent from the storage tanks back to the boron cleanup demineralizer and filter if required. Two half-size tanks are provided to permit f eeding from one tank and receiving in the second tank sbnultaneously. The primary grade water storage tanks are located in the enclosed tank area next to the solid wasto and decontamination building. Water supplied to the primary grade water system from the boron recovery system, liquid waste system, and demineralized water system meets the NSSS Vendors' chemistry requirements for makeup to the reactor coolant system. Each of the two full capacity primary water pumps is designed to furnish the flow required for maximum makeup to the reactor coolant system plus additional capacity to satisfy other uses. 9.2-14 Amendment 19 12/12/75
SWESSAR-P1 9 The primary grade water system lines that penetrate the con-tainmert are isolated upon a containment isolation phase A (CIA) signal. 9.2.7.3 Safety Evaluation Ex cept for the containment penetrations, the primary grade water system is not safety related. The primary grade water storage tanks store an adequate supply of primary grade water, and the two full capacity primary grade water pumps ensure the ability to 19 transfer primary grade water as required. 9.2.7.4 Testinq und Inspection Requirements The primary grade water system is continuously in use and requires no periodic test beyond nonnal observation and inspection involved in a mainten ance program except for the containment isolation valves which require testing as specitied in Sections 16.4.2 and 16.4.4. 9.2.7.5 Instrumentation Applications A level indicator and high and low level alarms are provided in the control room for each primary grade water storage tanks. Bo th pumps can be operated manually. One punp is running continuously and the second pump starts automatically on low pressure in the discharge header. This low pressure alarm sounds in the control roan. 9.2.7.6 Interface Requirements Interface requirements with the NSSS Vendors are described in Table 9.2.7-2. Fig. 9.2.7-1 lists the interface points of the primary grade water system. 9.2.8 Chilled Water Systems Two separate chilled water systems are provided in the SWESSAR-P1 design. The first, the chilled water system (Section 9. 2. 8.1) , provides chilled water to equipment located in the containment structure. The second, the air conditioning chilled water system (Section 9.2.8.2), supplies chilled water to equipment in areas outside the containment structure. 9.2.8.1 Chilled hater System A chilled water system is provided for the following:
- a. Containmen t utmosphere recirculation coolers (Section 9.4.5.1)
- b. Reactor vessel support shield tank
,on
{I U/ U (, LLd 9.2-15 Amendment 19 12/12/75
SWESSAR-P1
- c. Containment instrument air compressors and aftercoolers (Section 9.3.1)
- d. Reactor coolant drain tank (Section 9.3.3)
The containment structure chilled water system is shown in Fig. 9.2.8-1. 9.2.8.1.1 Design Basis The design bases of the chilled water system are:
- 1. The chilled water system shall be designed tor f ull load operation with chilled water supplied to various equipment served at a maximum temperature of 44 F at the chillers.
- 2. The heat removed by the chilled water system shall be transferred to the turbine plant service water which is at a maximum supply temperature of 95 F.
- 3. The por tion of the chilled water system which includes the containment isolation valves and the containment penetrations shall be designated Safety Class 2 (SC-2) and designed in accordance with ASME III, Code Class 2.
- 4. The portion of the chilled water system associated with the containment atmosphere recirculation coolers shall be designated Safaty Class 3 (SC-3) and designed in accordance with ASME III, Code Class 3.
- 5. The rest of the chilled water system is not safety-related and shall be designated Nonnuclear Safety Class (NNS).
Section 9.2.8.1.2 System Description The principal e quipment served by this chilled water system are as shown in Section 9.2.8.1. The reactor vessel support shield (~; c/ /d
^
^)
L-l 9.2-16 thru 9.2-20 Amendment 19 12/12/75
SWESSAR-P1 tank provides support and shielding for the reactor vessel and cooling for the surrounding concrete. Two thermosiphon heat 9 exchangers utilize chilled water for cooling the shield tank. This chilled water system is served by three 50 percent capacity mechanical refrigeration units, three 50 percent capacity chilled water circulating pumps, and two 100 percent capacity service water recirculation pumps (Section 10.4.11). The chilled water system is a closed system where the variation in water volume due to temperature changes is accommodated by an expansion tank located at a point higher than any other equipment or chilled water piping of the system and connected to the chilled water piping at a point close to the chilled water 9 suction. The expansion tank provides the net positive suction head for the chilled wter circulating pumps. Chilled water system makeup is provided from the demineralized water system (Section 9. 2. 3) through an automatic control valve which maintains the water level in the expansion tank. A chemical addition tank is connected to the pump discharge piping to add chemicals to the system. The tank is isolated, d ra ined , and filled with the desired chemicals. The tank isolation valves are then opened and the discharge press ure of the operating pumps forces water through the tank, injecting the mixture into the system upstream of the pumps. The desired water chemistry is obtained by the addition of the appr opria te chemicals for corrosion inhibition and pH control. Proper cold weather operation of the mechanical refrigeration units is ensured by a recirculation loop in the tur bine plant service water system supplying the units. See Section 10.4.11 for details. 9.2.8.1.3 Design Evaluation g The chilled water system uses equipment and components of proven conventional design. Low pressure, hiah temperature, low temperature, or mechanical refrigeration unit trouble alarms signal the operators' attention to malfunctions. If the malfunction is not corrected , components and systems served by the chilled water system may be inadequately cooled . However, this would present no safety p roblem . During normal op er a tion , two mechanical ref rigeration units and two pumps can acconmodate the heat removal load. The third mechanical refrigeration unit and pump provide 50 percent spare capacity. Maintenance of system components can be accomplished without loss of chilled water. n -a ( ! i sd U v d( " 9.2-21 Amandment 9 4/30/75
SWESSAR-P1 The portion of the chilled water system associated with the containment atmosphere recirculation coolers and reactor plant component cooling water is safety Class 3. Air operated valves are provided in each cross connecting pipe. These valves fail closed and close on a CIB signal in order to maintain the independence and sqparation of each train. No additional valves are required for redundancy since the trains themselves are redundant. 9 9.2.8.1.4 Testing and Inspection Requirements The chilled water system is in continuous opera tion and performance tests are not required, except as discussed below. Standby mechanice.1 refrigeration equipment and pumps are rotated in service on a sched';1ed basis. Components are accessible for visual inspections which will be conducted periodically, and following installation of repair parts or modifications, to confirm normal operation of this system. Routine prestar tup inspections will be performed in addition to periodic observation and monitoring of system parameters during operation. Safety class valves in the system require testing as specified in Section 16.4.2 (for safety class valves) and Section 16.4.4 (for containment isolation volves). O
/// ^~i
;i U t. o m 9.2- 22 Amen dment 9 4/30/75
SWESSAP-P1 9.2.8.1.5 Instrumentation Applications Chilled water system low pressure, mechanical refrigeration unit outlet line high and low temperature, and malfunction of the mechanical refrigeration units are alarmed in the control room. 9.2.8.2 Air Conditioning Chi' led Water An air conditioning chilled water system is provided for the following:
- a. Annulus building air cooling system (Section 9.4. 2)
- b. Fuel building air cooling system (Section 9.4.6)
- c. Solid waste and decontamination building air cooling sys-tem (Section 9.4.3)
- d. Health physics aren
- e. Administration building
- f. Generator leads coolers (Section 10.2)
- g. Service building The air . conditioning chilled water system is shown in 9 Fig. 9.2.8-2.
9.2.8.2.1 Design Bases The design bases of this chil!ed water system are:
- 1. The chilled water system shall be designed for full load operation with chilled water supplied to the various equipment served at a temperature of 42 F.
- 2. The heat removed by the chilled water system shall be transferred to the turbine plant service water system which is at a maximum supply temperature of 95 F.
- 3. The chilled water system is not safety-related and shall be designated Nonnuclear Safety Class (ISS) .
- 9. 2. 8. 2. 2 System Description The principal equipment or areas served by this chilled water system are shown in Section 9.2.8.2. This system is served by t hree 50 percent capacity mechanical refrigeration units, three 50 percent capacity chilled water circulating pumps, and two 100 percent capacity service water recirculation pumps (Section 10 .4.11) .
fe n'9 () & l) LJL 9.2-23 Amendment 9 4/30/75
SWESSAR-P1 The chilled water is a closed system where the variation in water volume due to temperature changes is accommodated by an expansion > tunk located at a point higher than any other equipment or chilled water piping of the system and connected to the chilled water piping at a point close to the chilled water pump suction. The expansion tank provides the net positive suction head for the chilled water circulating pumps . Chilled water system makeup is provided trom the demineralized water makeup system (Section 9.2.3) through an automatic control valve which maintains the water level in the expansion tank. 9 A chemical addition tank is connected to the pump discharge piping to add chemicals to the system. The tank is isolated, drained, and filled with the desired chemicals. The tank isolation valves are then opened and the discharge pressure of the operating pumps forces water through the tank, injecting the mixture into the system upstream of the pumps. The desired water chemistry is obtained by the addition of the appropriate chemicals for corrosion inhibition and pH control. Proper cold weathe r operation of the mechanical refrigeration units is ensured by a recirculation loop in the turbine plant service water system supplying the units. See Section 10.4.11 for details. 9.2.8.2.3 Design Evaluation The chilled water system uses equipment and components of proven O conventional design. Low pres sure, high temperature, low temperature, or mechanical ref rigeration unit trouble alarms signal the operators' attention to malfunctions. If the malfunction is not corrected, components and systems served by the chilled water system may be incdequately cooled . However, this would present no safety problem. During normal operation , two mechanical refrigeration units and two pumps can accocmodate the heat removal 3aad. The third mechanica l ref ricer ation unit and pump provide 50 percent spare Cdpacity. Maintenance of system conponents can be accomplished without loss of chilled water. The tortion of the chilled water system associated with the containment atmosphere recirculation coolers and reactor plant component cooling water is Saf ety Class 3. Air operated valves are provided in each cross connecting pipe. These valve s fail closed and close on a CIE signal in order to maintain the independence and separation of each train. No additional valves are required for redundancy since the trains themselves are redundant.
~~
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'c c G -)
9 2.-24 Amendment 9 4/30/75
SWESSAR-P1 9.2.8.2.4 Testing and Inspection Requirements The chilled wate r system is in continuous opera tion and performance tests are not required, except as discussed below. Standby mechanical refrigeration equipment and pumps are rotated in service on a scheduled basis. Components are accessible fcr visual inspections which will be conducted periodically, and following installation of repair parts or modi fica tions , to confirm normal operation of this system. Routine prestartup inspections will be performed in addition to periodic observation and monitoring of system parameters during operation. Safety class valves in the system require testing as specified in Section 16.4.2 (for safety class valves) and Section 16.4.4 (tor containment 1 solation valves) . 9.2.8.2.5 Instrumentation Applications Chilled water system low pressure, mechanical retrigeration unit outlet line high and low temperature, and malfunction of the mechanical refrigeration units are alarmed in the control room. 9.2.9 Water Trea trent System The water trea tment system is discussed in the Utility-Applicant's SAR; Ifowever, the system must meet the applicable requirements of Section 9.2.3.6
? ( (. n
000 L .J 't 9.2-25/26 Amendment 32 32 5/11/77
SWESSAR-P1 A surge tank is provided at the suction of the CRDM cooling pumps to accept system volume changes. This tank is the highest point ' in the system and is provided with level alarms in the control room. Makeup to the system is from the demineralized water makeup system (Section 9.2.3) through supply piping to the surge tank. Manual valves on the supply piping require operation at the tank location for makeup. Water chemistry of the cooling water is maintained by the addi-tion of chemicals through a chemical addition tank connected between the suction of the cooling pumps and outlet of the coolers.
'Ihe temperature of the cooling water supplied to the CRDM motors will be between 70 and 120 F utilizing reactor plant component cooling water at a maximum temperature of 105 T during normal operation.
The pressure of the CRDM motor cooling water n the tubes of the cooler is higher than the pressure of the reacxor plant component 32 cooling water in the shell. Inledage and subsequent contamination of the CRDM motors is prevented by maintaining this pressure differential. The system is located in the annulus building and supplies CRDM motors inside containment. The containment isolation valves are automatically closed upon receipt of a CIA signal. Minimum flow recirculation lines are provided on the CRDM pumps to circulate water to the surge tank in the event the containment isolation valves are closed. A spool piece is provided ca the supply and return lines to the CRDM service structure inside containment. Both spool pieces are removed during refueling to allow detachment and remote placement of the reactor vessel head. 9.2.10.3 Safety Evaluation The CRDM motor cooling system is designated nonnuclear safety with the exception of the valves, piping, and instrumentation required for containment isolation. These components are Safety Class 2 and Seismic Category I. Failure of the CRDM motor cooling system does not affect the safety function of the CRDMs; however, redundant ptunps and coolers are provided to prevent an interruption of power generation. 9.2.10.4 Testing and Inspection Requirements Containment isolation valves require testing as described in . Sections 16.4.2 and 16.4.4. BSW 9.2-28 g.'g c)J Amendment 32 5/11/77
SWESSAR-P1 9.2.10 Control Rod Drive Mechanism Motor Cooling System 'Ihe control rod drive mechanism (CRDM) motor cooling system is shown on Fig. 9.2.10-1. Table 9.2.10-1 lists the principal component design and performance characteristics. This system operates in conjunction with the CRDM cooling system discussed in Section 9.4.8. . 9.2.10.1 Design Bases The design bases for the CRDM motor cooling system are:
- 1. The system shall transfer the heat load from the CRDM motors to the reactor plant component cooling water system.
- 2. Cooling water temperature shall be maintained between 70 and 120 F.
- 3. '20oling water pressure shall be less than 300 psig at the inlets of the CRDM motors.
32
- 4. The materials of constructico shall be chosen to minimize the collection of magnetic particles in the magnetic field of the CRDM motors.
- 5. The CRDM motor cooling system is designated nonnuclear safety (NNS).
9.2.10.2 System Description The CRDM motor cooling system consists of two full capacity pumps that circulate cooling water in a closed circuit through the control rod drive coolers to the CRDM motors. Each CRDM cooling pump has a capacity of 300 gpm, based on the flow required for all CRDM motors. One pump is required for system operation. The redundant pump is started manually from the control room upon low system flow or high CRDM motor temperature. Two CRDM coolers are included at the discharge of the cooling pumps. These coolers utilize nonnuclear safety reactor plant component cooling water (Section 9.2.2) as a cooling medium. Each cooler is sized to remove the maximum heat load from all CRDM motors and one cooler is required for system operation at I any time. CRDM motor cooling system components are fabricated of austenitic stainless steel to avoid the collection of iron particles in the magnetic field of the CRDMs. 0 0, 0 csJ BSW 9.2-27 Amendment 32 5/11/77
SWESSAR-P1 Operating and standby components are alternated periodically to verify operability of all equipnent. Components are accessible for periodic visual inspections. 9.2.10.5 Instrumentation Applications Flow is measured at the outlet of the CRDM coolers with low flow alarms provided in the control room. Temperature is sensed at the outlet of the CRDM coolers with a high alarm in the control room. High and low level alarms are provided in the control room for the surge tank. Local pressure indicators are provided on the suction and dis- 32 charge of each cooling pump. Local temperature indicators are provided on the inlet and outlet of each cooler. 9.2.10.6 Interface Requirements The CRDM uctor cooling system meets the BSW interface require-ments in the B-SAR 205 sections listed below with the following exception:
- 1) Temperature requirements of Section 9.2.2 (4) - Cooling water will be maintained between 70 and 120 F during normal operation utilizing reactor plant component cooling water at a maximum temperature of 105 F.
B-SAR 205 interface requirements: Section 5.7.8 Section 9.2.2 Table 9.2-1 Table 9.2-2 Interface points between BSW systems and SWESSAR systems are indicated on Fig. 9.2.10-1. t,0 ; cs/ BSW 9.2-29 Amendment 32 5/11/77
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SWESSAR-P1 TABLE 9.2.1-3 RfACTOR PIAlfr SERVICE WA1TR SYSTEM HEAT LOAD Heat load (106 Bt tt/hr) DBA** (Minimian Norm l Shutdown Safeguards) loss of Power Iten Operation a4 Hr Recirculation Phase cooldown i 4 Hr
*Nactor plant component <x>oling 89.58 306.52 197.37 Later heat exchanger ODntrol building water chillers 4.7 4.7 4.7 4.7 9.2 18.4 d Diesel generator coolers - -
Annulus building unit coolers - safety related areas 1.4 1.4 .7 1.4 TurAL *E.od 312.62 211.97 Later
- Based on Table 9.2.2-3
** m la assume single f ailure of me train, which results in the swximum heat load per train.
Os C r' ) P .J W-35 1 of 1 Amendment 19 12/12/75
SWESSAR-P1 TABLE 9.2.1-2 REAC'fDR PLANT SERVICE MATER SYSTD1 FTEW REQUIREMENTS Flow Requirernents (q1m) Normal Shutdown **DBA-Recirculation Loss of Power ITEM Operation 3 6 hr Mininnm Safeguards) Cooldown 3 6 hr 38
- Reactor Plant Component Cboling Water Heat Exchanger 14,716 29,716 15,067 30,134 ,
Control Building Water chillers 950 950 950 950 Diesel Generator Coolers 1,450 1,450 725 1,450 Annulus Building Unit Coolers - safety related areas 300 300 150 300 TOTAL 17,416 3 2,41 b 16,892 32,834 l38
- Based on Table 9.2.2-2 and assuming reactor plant component cooling water and service water flows are identical through the reactor plant ccuponent cooling water heat exchanger.
** Totals assume single failure of either train. 38 c'
cm CN r) L. B&W 1 of 1 Amendment 30 1/28/77
SWESSAR-P1 TABLE 9.2.1-3 REACTVR PIAfff SERVICE WATER SYSTD1 HEAT IDAD Heat Load (10* Btu hr)
*
- DM-Recirculation Normal Shutdown (Ministna loss of Power ITD4 Operation _A 6 hr Sa feguards) Cboldown a 6 hr
- Reactor Plant Component Cooling Water IIeat Exchanger 141.5 286.1 203.7 207.9 38 Control Building Water Chillers 4.7 4.7 4.7 4.i Diesel Generator Coolers - -
10.8 21.6 Annulur, Building Unit Coolers - safety related areas 1.4 1.4 0.7 1.4 TorAL 147.6 292.2 219 9 235.6 ,
- Based on Table 9.2.2-3 and assuming reactor plant component cooling water and service water flows are identical through the reactor plant cornponent cooling water heat exchanger.
** htals assume single failure of either train, which results in maximum heat load per train.
O C D PJ _; a BCW 1 of 1 Amendment 30 1/28/77
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- LF 7 1 2 UR S p 0 6 1
P OE S m 0 r 0
- 2 C I' N u e 5, t 0 0 3 1 R P - x f A 9 TD 0 a52C 0 0 r o S I N n 12L12S b. 0 0 3 e 3 S E EA 7 9,5 2 4 9,4 2 90 00 - t00 - 1 E L N E 2 52C a52C W B ON - 22 2 41 891 81 1 12S 2l 12S S A PG C or T MI r 0 r OS i 0 e 3 CE P 5,ta52C0 0 -
D T A 1 RL1 2S NT AN LE PN O p 0
- RP m 0 r 0 OM u 5, et 00 3 1 TO P - x CC 7 t 52C 9 0 0 r A B 1 1 Is 1 2S 5 5 3 e 3 EL RA 0 1
5,5 2 2 5,7 42 0 00 - 52C t00 - a52C P 2l1 2S I C M 22 2 n n 0r 41 791 71 1 1 2S N e t 0 e 3 I R P 5, a52C t00 - I A 1 8L1 2S g g q n n g n i i n i l l i l o o l o o o o o ns C r o C i r C_ re C ss e t t ht F F t nrq n n /a F t F n it n e gF e uW , n , gF e gF a a n i n r t , e e ,e i n i rrh o s , o o Be er n er s , o s , tec p pe p g c ru o p ru pe p pe px m r m n ,i ut ut r m r y e o n ,u o a ndv ta m t a ,u o k ,u t s C i et C h i ar ar o ar et C n et ept a ran c aae re C re ep uro ran a ran f ma aue t n rm uro t p sei t x n E t S ep pm - pm sei t n T l uro asei s ph a u s pt a t - pet mme mme s pt a e gspt l p r ema l t ra e pet ema rec l g ,ema rec G fff n P m e , rec P a e e e gt d gt P r oooi u p yt pti e phd t i t pti u yypti a r P tf f r if i,te S ,t e f r S tt f rrrr o ri ec,nni ggs o rnSwel eg we' nni ggs o r i i nni tcggs eeet t r t r olt lrolt t m bbb c e t adiis c e biel nu lel nu iis c e n aii s t e nmmr r t uue a t e a mpassa uaeeel a t e a usbFIO r eu t etFIO ha ssa eel a t e a apssa uaeel I NNNp RW NCiDDC f RW NDT SW DJC RW QCDDC N g _^C C %
G LYSTEM INTER FACE POINTS - DEMINERALIZED WATFR SYSTUt (MWS) ID NO. RESAR - 1S RESAR-41 fi-SAR 205 CESSAR MWS-1 Supplied to chiller Supplied to chiller surge NA surge tank to valve tank to valve 1-7034 30 1-7034 (Fig. 9.3-1 (Fig. 9.3-1 Sh f)4 Sh 3) MWS-2 NA NA Supplied to boric acid MA mix tank through valve MV200 (Fig. 9.3-3 Sh 3) MWS-3 NA Supplied to fuel trant.fer NA NA system inside containment (Section 9A.5) MWS-44 NA Supplled to f uel transf er NA IM system outside mntainment (Section 9A.5) CN Os CN I ) FIG. 92.3 -IB 2 DEMINER AllZED WATER SYSTEM PWR REFERENCE PLANT S AFETY AN ALYSIS REPORT SWESS A R - PI
~
AMENDMENT 30 1/28/77
SWESSAR-P1 TABLE 9.2.2-2 REACIOR PLANT COMPQfENT CDOLING WAT1.R SYSTUS FLOW RIQUIREMEICS Flow kequiresnents (qpra) Normal Shutdown **DaA piinimum Saf eguards) Loss of Power Itse (Note 11 Operation B 4 br Recirculation Phase Cooldown 4 4 hr
- Reactor Coolant Pumps Seals & Dearings 864 864 - -
- Reactor Coolant Pumps Motor ,
Air Coolers 1,600 1,600 - -
- Letdown Heat Exchangers 1,400 2,083 2,083 2,083
- Excess Letdown Heat Exchanger 372 3 ?2 372 372
- Seal Water Beat Erchanger 370 370 -
370
- Safety Injection Pumps 120 120 80 120
*RBR Pumps 60 60 40 60
*RHR Beat Exchanger -
14,700 9,800 14,700
- Charging Pumps 80 80 80 80
- Chiller Unit - Boron Thermal -
Regeneration Subsystem 1,000 - -
*Doron Injection Pumps 40 40 20 40 Containment Atmosphere Recirculation Coolers - - 4,000 6,000 Fuel Pool Coolers 5,000 5,000 5,000 5,000 il Containment Spray Pumps Seal coolers 60 60 40 60 Con' ainment Penetrations 100 100 Sample Cooiers 100 100 - -
Padioactive Liquid Kaste System 1,370 1,370 - - Moren Recovery System 1,300 1,300 - - Radioactive Gaseous Waste Systes: 3,200 3,200 - - Aegenerant Waste System 1,300 1,300 - - TOTAL 18,336 32,719 21,515 28,885 rp C- *1111s emipment is provided by Westinghouse and these requirements are based on RESAL-41, CN ** Totals assume single tailure of train C, which results in the maximum heat load per train. Note 1. Hydrogen recombiner coolers are required days af ter a DBA. Flow required is 12 gpn per recombiner cooler. ( ~1 C -) W 1 of 1 Amendment 19 12/12/75
SWESSAR-P1 TABLE 9.2.2-3 REACIOR PLAttf COMPONE*fff COOLING WATT.R SYSTEM HEAT IDAD fieat Ioad f10* Dtu/hr) Nonaal Shutdown DBA** Ioss of Power (Minimum Safeguards) Itm fNote 1) Operation 3 4 hr Recirculation Phay Cooldown D 4 hr
- Reactor Coolant Pumps Seals and Bearings 5.2 1.3 - -
- Reactor Coolant Pumps Motor Air Coolers 4.0 1.0 - -
- Letdown Heat Exchanger 20 11.6 -
11.6
*Excesrs Ietdown lleat Exchanger - - - -
- Seal Water Beat Exchanger 2.4 2.4 -
2.4
- Safety Injecticn Pumps - -
.4 -
*RER Pumps -
.21 -
.21
*RHR Heat Exchanger -
296.7 178 (1) 296.'7
*Ciarging Pumrps .16 .08 -
.08
*0iiller Unit - Boron thermal Regeneration Subsystem 3.42 - - -
- Boron Injection Ptmps - - - -
Containment Atmosphere Recirculation Coolera - - 113 (1) 2.5 : Fuel Pool Ccolers 10.0 10.0 10.0 10.0 ['l Omtaianwmt. Spray Pumps semi Coolers - -
.2 Containment Penetrations .5 .5 - -
9==ple Coolers .5 .5 - - Radioactive Liquid Maste System 16.6 16.6 - - Boron Recovery System 15.4 15.4 - - Radioactive Gaseous Weste System 20.9 20.9 - - Regenerant Waste System 15.4 15.4 - - TOTAL 114.48 392.59 301.6 323.49 18
*This equipment is provided by hestinghouse and these requirements are based on Table 9.2-1 in RESAR-41.
**Tutals assume eingle f ailure of train C , which results in the maximum heat load per train.
Note 1. Hydrogen recombiner coolers are required days af ter a DBA. Heat load to be removed 11 is 67,000 Btu /hr per cooler. (1) Determined by IDCTIC Code T rp CN r) L W 1 of 1 Amendment 19 12/12/75
SWESSAR-P1 TABLE 9.2.2-2 RFACTOR PIAlfr COMPWENT CDOLIPC WATP.R SYSTEM FLOW REQUIRD4EffrS Plow Requiresnents (qtim t tu>rmal Shutdown **DRA(Minimtzn Saf eguards) loss of Power Operation 4 4 ??r_ Recirculation Pliase giolekun a 4 hr Item (Not e 11
- Reactor Coolant Pumps -
Seals & bearings 864 864 - II
- Reactor Coolant Pmps Motor -
Air Cbolers 1,600 400 - 700 1,000 1,000 1,000
- Letdown lleat Exchangers 262
- Excess Letdown Heat Exchanger 262 262 -
372 372 372 372
- seal Water 11 eat Exchanger to 10 5 10
- Safety Injection Pumps 40
*RER Pumps 40 40 20 15,200 7,600 15,200
*RHR Heat Exchanger -
100 100 100 50
- marging Pumps
- miller Unit - Boron Thermal -
Regeneration Subsystem 414 - Containment Atmosphere 8,000 gy,
- - 4,000 Recirculation Coolers 5,000 t 5,000 5,000 2,500 Fuel Pool Coolers 20 40 Ct>ntainment Spray Pumps 40 40 Sample molers 100 100 -
Containment Penetrations Ccx)lers 100 100 - Radioactive Liquid Waste Systesn 1,370 1,370 - 1,300 1,300 - ps Regenerant Water System - Radioactive Gaseous Waste Systeso 1,100 1,100 - Doron Recovery System 1,300 1,300 - 14,672 29,758 15,567 30,024 19 TurAL
*These requirements are based on RLSAR-35.
** Totals assume single f ailurs of either train, which results in the greatest heat load per train. fit Flow required is Note 1. Hydrogen recombiner coolers are not required until days after a DBA.
CT 12 gym per re<xunbiner cooler. CN rs J L1 T' s 1 of 1 Amemiment 19 W-3S 12/12/75
SWESSAR-P1 TARI.E 9.2.2-3 REAC'IT)k PIMrr COMPONENT COOLItG WATER SYSTEM !! EAT IDAD Heat Inad (10* Ptu/hr) Normal Shutdown DBA** Loss of Power Item (Note 11 (Minimtn Safeguards) Operati on 4 4 hr Pecirculition Phase cooldown 4 4 hr
- Reactor Coolant Pumps Seals and Bearings 4.8 1.2 -
- Reactor Coolant Pumps Motor Air Coolers 4.0 1.0 -
- Letdown IIeat Exchanger 10.5 4.8 -
4.8
- Excess Ietdown Heat Exchanger - - - -
- Seal Water lleat Exchanger 1.R8 1.88 -
*Saf ety Injection Pumps - -
0.1 -
*RIIR Pumps -
0.14 0.07
*RIIR Heat Exchanger 0.14 237 74.0 (Not e 2) 232
*0iarging Pumps .2 .2 0.1 .2
- Chiller Unit - Boron 'Ihennal Regeneration Subsystem 2.5 - - -
Cantainment Atmosphere Recirculation Coolers - - 113.0 (Note 2) Iater Fuel Pool Coolers 10.0 10.0 10.0 Oontainment Spray Pumps - 10.0 l19 0.1 - Sanple (bolers 0.5 0.5 - (bntainanent Penetrations coolers 0.5 0.5 - Radioactive Liquid Waste System 16.6 16.6 - Regenerant Maste System 15.4 15.'4 - Radioactive Gareous Maste System 7.3 7.3 - pg Doron Recxwery System 15.4 15.2 - 1UTAL 89.58 306.92 197.37 Iater l11
*7hese rquirements are based on RESAR-33.
**'tbtals assume single failure of either train, whicia results in t11e greatest heat load per +aain.
Hotes {il
- 1. IFydrogen rectubiner coolers are not required until days af ter a DBA. Heat load to le removed is 67,000 Btu /hr per cooler.
<y gig qX 2. Determined by IDCTIC Cale p r; t7 W-3S 1 of 1 Amendment 19 12/12/75
SWESSAR-P1 TABLE 9.2.2-2 REACTOR PLANT COMPOMP COOLING WATER FIDW RFQUIREMEN'IS Flow Requirements (giun) ITDt raormal Shutdown *
- DBA-R ec irculation Ioss of Power Operatini 4 6 hr (Minirmur. Safequardn) Cooldown 3 6 hr
- Heactor Coolant Pump Coolers 612 612 - -
hg
- ictor Coolant Pump Motor Coolers 1,200 1,200 - -
e
- L t(kwn Coolers 1,220 1,220 610 1,220
- Decay Heat Removal coolers -
15,000 7,500 15,000
- Low Pressure Injection /DI[R Pumps Seal Coolers 50 50 25 50
- High Pressure Injection / Makeup Pumps Seal Coolers 70 70 35 70 Control Rod Drive Coolers 534 534 267 534
- Seal Return Coolers 220 220 110 220 Puel Pool coolers 5,000 5,000 2,500 5,000 Oontainment Spray Pumps Seal cooler 40 40 20 40 Contal.nment Atmosphere Recirculation Coolers - -
4,000 8,000 Boron Recovery System 1,300 1,300 - - Liquid Waste System 1,370 1,370 - - Regenerant Waste System 1,300 1,300 - - Gaseous Waste System 1,600 1,600 - - Penetration Coolers 100 100 - - Sample Coolers 100 100 - M AL 14,716 29,716 15,067 30,134
- Flow requirements for Bf.W supplied coriponents are given in B-SAR-205
** mtals assume single failure of either train.
c~ c: C' r) L ~7 Bsw I of 1 Amendrnent 30 1/28/77
8 3 1 8 3 3 3 3 07 37
/
t9 r n2 r e e/ rh p m1 e d w6 r n o 68 4 h e P# 28 3 4 8 / m 8 10 4 8 u A fn - - 40. -- - t o 94 10 2 7 D 8 1 0 s&w s1 1 2 0 0 oo Ib
. 0, C 7 6
s i n o ) d e i s t d *
- v r *38
- o lama *68 3 0* 1 m h
r umu Acig - - 000
- 4 0 1 50.- - -
8 6 e r
/ Brne 7 10 u Diif 6 1 2 3 e t
- cMa 1 0 b B
- e(S 2 .
R n o 6 i t 0 a D 1 r d A ( t a D o I d r l a e T p t A I o a E d e H t a H a n o R E e wr 68 5 l H oh 6 28 3 . T d 8 464555 0 t A A t6 1 0. 4 0.- a B W u 8784 10 5650 6 e D ha 4 99 1 1111 8 h G S 8, 1 2 a 3 N m
- I 3 u r 1 2 L m e P O .ix t 1
- 2 O f R C 5a a A 9 0 m f S T n 2 s o S E N o 5
-n y a 1 E L E li Ri W B N at 6 33 6 A d S A O T P ua rr 8
-3 4 0. - -
464555 4 Sg
- s. l M ce E p 878 4
110 1 5650 1111 1 4 Bi t a r D 1 4 C O 8, 1 n' e in v f r 3 s e u ne s J er I P i v, d e s gn r R r i i U e ea u T C l rr q e o at A b r E C sr R te e s n nh r p o et a s m i ni r u t oe s e sp a p r l p l mf e o mp u oo l o uu c c o C Pe r e o k i dr c r sRa c eu e rHMs e ile r t eD/r r R lid e o l/ne es m wfC ao ni M onol ape e pp Cito ooio nrra atae t snsr u oeC b mm tcCshPht myer t u lce rc pseSte PP aejeexysyt sl W gT 5nC e lI ttsonIio vjnvlEaoSseyo rm ytSo bid sI r s nnr aI r o t pt yS s Cs r oey n aaee eDCaSA ae r e. lllRer aoo rudnHtt e deWtse vt snl f mb u t gr ae oootusor nn ustaoo ssd rl CCCassRu1=ese t nWanMio a tC dsm aae doyo o - i Hc M rrnHerl oow ttoyP r rPoRMi e nR rsa i deure
> a ni n o tl L l .mr E ccda*htllttoueeep A P tatt'a e :
T aatc gnaennrqgsnn u 1 I e e s e oi o e u o o RRIDIHCSFCCBLRGPS oi e a e a UT ebe H1D e
- t W
*
- o &
******** *** N B l '
nC
-s I( L r C
SNESSAR-P1 TABLE 9.2.2-2 REACIOR PLANT COhPONENT COOLING WATT.R SYSTm FI4M RM)UIREMEfCS Flow Requirement s (qin]
**DbA loss of Power Normal Shutdown (Minimum Saf eguards) 11TM (Note 1) Operation 3 3.5 hr Decirculation Cooldown a 4 hr
- Reactor Coolant Pumps - High Pressure Coolers 300 300 -
300
* - Seal coolers 70 70 -
70
* - Oil Coolers $16 516 - -
* - Pbtor Air Coolern 700 700 - -
- Ietdown Heat Exchanger 1,500 35 - -
- Shutdown Cooling Heat Exchanger -
22,000 11,000 22,000
- Shutdown Cooling Pumps Cooler 30 30 15 30
- High Pressure Safety Injection Pumps Seal Cooler 20 20 10 20
- Low Pressure Saf ety Injection Tunq>s Seal Oooler 15 15 7.5 15 Containment Atmosphere Recirculation Coolers - -
4,000 8,000 Fuel Pool Coolers 5,000 5,000 2,500 5,000 Oontainment Spray Pun:p Seal Coolers 40 40 20 40 Containment Penetrations Coolers .00 100 - - ig Sample Coolers 100 100 - - Radioactive Liquid Waste System 1,370 1,370 - - Radioactive Caseous Wast e System 1,100 1,100 - - Horon Recovery Systen 1,300 1,300 - - Regenerant Waste System 1,300 1,300 - - TOTAL 13,461 33,996 17,552.5 35,475
- Titis equit snent is supplied by C-E and these requiranents are based on CESSAR.
** Totals assume single f ailure, one of either train which results in the maximum heat load per train.
Note 1 Hydrogen recombiner coolers are required days af ter a DHA. Flow required is 12 gym per cooler. y r; C. ' L7 C' C-E 1 of 1 Amendment 19 12/12/75
SWESSAR-P1 TABLE 9.2.2-3 REACTOR PLAtrP QNPotTErrF ODOLING WATER SYSTD4 HEAT IDAD 11 eat load (106 Dtu/hr) Normal Shutdown DBA* * (Minimum Sa f eguards) Ioss of Power ITD1 (Note 1) Operation a 3.5 hr Recirculation Coold w & 4 hr
- Reactor Coolant Pumps fligh Pressure Coolers .748 .748 -
.748
- Reactor Coolant Pumps Seal Coolers .127 .127 -
.127
- Reactor Coolant Pumps Oil Coolers 2.55 1.27 - -
- Reactor Coolant Pumps Motor Air Coolers 5.46 2.73 - -
- letdown Heat Exchanger 21.6 .51 - -
- Shutdown Cooling fleat Exctianger -
270.0 120 (1) 270.0
- Shutdown Cooling Pmps Cooler -
.2 -
.2
- liigh Pressure Safety Injection Punps Seal Cooler - - .1 -
- Low Pressure Saf ety Injection Putps Seal Cooler -
.2 .1 .2 Oontainment Atmosphere R mirculation Coolers - -
125 i 1) 2.5 ,, niel Pool Coolers 10.0 10.0 10.6 10.0 (bntainment Spray Pumps Seal Coolers - - .1 - Containment Penetrations Coolers .5 .5 - Sample (bolers .5 .5 - Radioactive Liquid Waste Syst m 16.6 16.6 - Radioactive Gaseous Waste System 7.3 7.3 - - Boron Recovery System 15.4 15.4 - - Regenerant Waste System 15.4 15.4 - - M AL 96.2 341.5 255.2 283.8
- Based on CESSAR Table 9.2.2-1
** Totals assu:ne single f ailure of either train, which results in the maximum heat load per train. [11 Note 1 Ilydrogen recombiner molers are required days af ter a DBA.
Ifeat load to be removed is 67,000 Btu /hr per cooler. l13 (1) Determined by IIX'FIC code 7 c. L' [- ) t7
-)
C-E 1 of 1 Amendment 19 12/12/75
SWE "> sal < - P 1 TABLE 9.2.2-4 PERFOhMANCE OF THE REA("N)R PLAFTP CtWPONENT G)OLING WATER SYSTtJ1 i W-3S ( 1) W-41 ( 1) BCW (1) [E ( 1) lIl No. Trains No. Trains No. Tr a in s No. Trains Operating Mode Rp E irmt Av.silable Requir.d Av.tilable I<twpaired Av.sil.ible Required Available 2 2 3 1 2 1 2 Normal operation 1 (minimum) 2 2 3 3 2 2 2 2 Normal shutdown Shutdown considering single f ailure 1 2 2 1 1 1 criteria 1 1 DnA- Recirculation 2 2 2 2 3 3 2 2 phase DBA- Recirculation phase considering single failure 1 1 criteria 1 1 2 2 1 1 Loss of power ccx)l- 2 2 2 2 3 3 2 2 down loss of power could(wn considering single 1 1 failure criteria 1 1 2 2 1 1 O c ,s C' t' ) tm (_J The- B puznp ( 1) There are two puripgine r tr. sin. Thea A pump is re< paired t o ogw rat e only during ruirla.nl orw rat ion. ,, is required to o;w r at e during all other crinditions lit;ted. Only one pianp ola r at e:. at .sny t ime. 1 of g Ann ruinu*nt 19 12/12/75
1 2 !
- r f o nitle 16 dt -
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n 2 2 7 wat r. gia'tb e a re e wcae s oe,ue. r e ge mV ldr prd m 9 2 , g end F pt lee tmt oe A 5 n d pi n l oo nbeS iig siorf r etnoei
, 9 1 ieorol0 n i hS lltS wlpan r (b p S 2 2 li uci6m N r ph df x T - 2 , 2 olld w el ol N 2 4 2 o pa n etl oih euc eeI pne E
2 2 cpmFwevsi cwte. tsx. bi mw 2 8 9 ur oroyw tywtt i h a wy ael f li . pd a uos D e 9 9 tso0 dubs R c 9 s s n n2tta F . nr n ltn lce h I Rn n n n n ee 1 ua s etene gl a g ieltt U Ae s o o o o nbg hrd 0r nslim naei p ichs w pb n u d si a h o e i o nwsees2u Q E R Sr Se Ef l b i i i t c c c t t t pli o c mlrldri ma h pne1 o wib midi ueteu otRA li w oeso sl si r We a e e e e oiueneait S CwdbaTtta4 Ccpue CmRC ohasq oaHI lhooee Ftpcbp E SR T S S S C A F R E T N 2 I 3 1 1 M E 8 7 A T , , 9 S 5 Y ) ) d
- S ) I I ) n 1 2 I
( ( ( I ( a P R 2 2
- 2 E 2 2 A 1 R T 2 2 1. 5 2 A 9 A 1 2 2 7 A A S M - 9 9 7. s 6 S f S E e 2 9 9 1 e 1 o E L G 1 c s s x x x W B N 4 n 9 n n n o o o n ni o od n
o i d i d 1 S A I e T L Rr e i i i i in i n n O Ae l t t t t te t e e O Sf b c c c c cp c p p p p C Ee a e e e e ep e Rh T S S S S SA S A A r f f t E n N l e C a d s P u i pr M - decrn me O rt ibneo ug C es s ivi pn f e s t eloot o P sW y l aS rlcha a tl n N n o eS cl A af t r hS ehdtu ar L rose t n r N r hseic t hwr l o of P t ef o oy s sra e rssi o R O t d s onus tit c fb t a i t oei c cd t gl ee e T n a aar d sd w s m nbhr rt oa C e o mree. n de a gt i waat oht o A E m e l t etfht tn r ri al ni l l csot tn. ci R i r t a seyoe e n dp yet n w o np im li y r fxet e ams n ere u e sredp o i au ol t r yro ret q h hf ni p t ts o s elloi tu e ntaau q l t a s s ce r i m t alit avarc hei e n h d i s n am te a n dr tu e wocpe tbm a roen trsed i m ag c e ne nt ea h c ni s getrn ot0 j s fume r u nr nr nraoi to1 w i o pt t r sao oe r i m n c t ehd oattu oya w n o tthia pp e ltohn l lagul e s dcn mm t F uenqe Mhier E l I n oxe ue CeV Ct a W oeuir lah Chawf Fmt W~ ( m I C<c
a 1 16
- 2. r 27
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- 2. of t0 n2 9
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art pa l
- 2. e o 2.hti s e 9 c ee Rn nbt Ae oia Sr iru Se tcu Ef cse We eed SR Sda
)
r r r o 2 C ( A f 1 5 P 5 e o
- - 1 c x R 2 4 n i 2 A - < d S 2 ' . n S e e E 9 ,. t p W e p S E LP A L
B m - A e tr T n t ne i s et se pi nn a p y. t m n u t g i i ae p nra aek ueqr mrupnloae tdlta ea osuauowl f e tsrl oc - e ow gn osu erao rni so dp choi th t a f ctlt ng n mtoricon en e n ohaoa mi n r eattwecl et e blnc r o rs r oear to ie i toveeenC uW q u scerihe t t u rtnr ey e mrnet oo upt rb R oih nt tt mc ed ocy iarnlrce boa he. ti s e ai a u r ld ird mst ype v nersnh l pc oeureeat nua rhouhrli Osf Ptbttppw
- W~
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.(
SWESSAR-P1 TABLE 9.2.2-6 EQUIPMENT SUPPLIED BY REACTOR PLANT COMPONENT COOLING WATER Supplied From: FJTuipment Train A Train B Train C l
*High head safety injection p _(2) . . . X. . . .X. . . .X
- Low head safety injection pt. ,; (2) . . . X. . . .X. . . .X
- Containment spray pumps (2) . . . . . . . X. . . .X. . . .X
- Residual heat removal pumps . . . . . . . X. . . .X. . . .X 23
- Residual heat removal heat exchangers (2) X. . . .X. . . .X
- Containment atmosphere recirculation. . . X. . . .X. . . .X coolers (2)
- Letdown heat exchanger. . . . . . . . . . . . . . .X
- Excess letdown heat exchanger . . . . . . X
- Seal water heat exchanger . . . . . . . . . . . . . . . . .X
- Reactor coolant pumps (1) (2) . . . . . . . . . . .X. . . .X l23
- Charging pumps. . . . . . . . . . . . . . X. . . .X
- Fuel pool coolers . . . . . . . . . . . . X. . . .X
- Boron injection pumps . (2) . . . . . . . X. . . . . . . . .X {23 Boron thermal regeneration system . . . . . . . ,, .X chiller Radioactive liquid waste system cooling . X Radioactive gaseous waste system cooling. . . . . . . . . .X Regenerant waste subsystem cooling. . . . X Boron recovery system cooling . . . . . . . . . . . . . . .X
- Hydrogen recombiner cooling (2) . . . . . X. . . .X l23 Sample coolers. . . . . . . . . . . . . . X. . . .X Penetrations coolers. . . . . . . . . . . X. . . . X. . . .X
- Safety related cooling water supply Note 1: Two of four components are supplied from each train.
Note 2: Cooling water supply to these components is governed by a technical specification in 23 Section 16.3.3.3.
- - 3
_V ._s_ i W 1 of 1 Amendment 23 3/31/76
l l I I
. 1 s
r
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lr hos 86 dt tu - ne. le tl p 2. r 27 nn ao o ahe h te tv it-wan s fm u 2. fo t6
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- e0ocnaai pnv ee iit .n m 2 8 t1i com a tai td tae eoue, bt p t
atS l S rnn go cia ii d n 2 2 7 wta teare soel w S sal Fs. e a r gi b ec ldr hN eto i n m 9 2 , g end Fpx leeht gt dno dvo A S 5 n d pi n l oe ii g c u nie. i c noi C
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SWESSAR-P1 TAN E 9.2.2-5 (COMr1 RESAR-3S SWESSAR R muirement Re f erence Reference Arrangement M the refueling Appendix SA Suf ficient space is provided cavity shall allow adequate space for refueling operations, as described in Section 9.1 and Fig. 1.2-3. insta11ation of retueling e< palp-ment, storage of reactor compo-nents, and access f or inspection of reactor coolant system ccaponents. Water introduced into the Appendix SA The contents of RNST qiven on refueling cavity at any time Table 6.2.2-1 can fill the shall not touch the reactor containment (Fig. 1.2-3) tr 18 vessel while the vessel is a maximum elevation of -3 6*. hot and pressurized. The elevation of the bottom of the reactor vessel is
-31' 6" which provides suffi-cient clearance to meet this requirenent.
A minimura of 10 feet of Section S.7.1 '1he SWESSAR design provides water shall be provided over the core during post- at least 10 feet of water above the core during all accident f uel handling fuel handling operations. operations to minimize personnel exposures.
*Only the requirements of equipment supplied by Westinghouse are interfaced.
O Gs Cs bJ ( n .y W-3S 2 of 2 Amendment 28 8/6/76
SWESSAR-P1 TABLE 9.2.2-6 EQUIPMENT SUPPLIED BY REACTOR PLAh"T COMPONENT COOLING WATER Supplied From Equipment Train A Train B
- Safety injection pumps (3) . . . . . . . X . . . . X
- Centrifugal charging pumps (1) (3) . . . X . . . . X
- Containment spray pumps (3). . . . . . . X . . . . X
- Residual heat removal pumps (3). . . . . X . . . . X 23
- Residual heat removal heat exchangers (3) X . . . . X
- Containment atmosphere recirculation coolers (2) (3) . . . . . . . . . . . . X . . . . X
- Reactor coolant pumps (2) (3). . . . . . X . . . . X
- Letdown heat exchanger . . . . . . . . . . . . . X
- Excess letdown heat exchanger. . . . . . X
- Seal water heat exchanger. . . . . . . . . . . . X
- Fuel pool coolers. . . . . . . . . . . . X . . . . X
- Hydrogen recombiner cooling (3). . . . . X . . . . X 23 Boron thermal regeneration system chiller . . . . . . . . . . . . . . . . X Boron recovery system cooling. . . . . . . . . . X Radioactive liquid waste system cooling. X Radioactive gaseous waste system cooling . . . . X Regenerant waste subsystem cooling . . . X Sample coolers. . . . . . . . . . . . . . X . . . . X Pe2.c M .tions coolers. . . . . . . . . . . X . . . . X a
- Safety related cooling water supply h( ,c, y L. ., -
h-3S 1 of 2 Amendment 23 3/31/76
SW"M 37.R-P1 TABLE 9.2.2-6 (CONT) Equipment Supplied From Train A Train B Notes:
- 1. Each train independently supplies one pump and the third charging pump may be supplied from either train.
- 2. Two of four components are supplied from each train.
- 3. Cooling water supply to these components is governed by a technical specification in Section 16.3.3.3. 23
( f. t' ov0 ?'5 W-3S 2 of 2 Amendment 23 3/31/76
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SWESSAR-P1 TARTR 9.2.2-6 EQUIPMENT SUPPLIED BY REACTOR PLANT COMPONENT COOLING WATER Supp.ied From Equipment Train A Train B
- High head safety injection / charging pumps (1) (3) . . . . . . . . . . . . . X . . . . X
- Low head safety injection / decay heat removal pumps (3) . . . . . . . . . . . X . . . . X
- Containment spray pumps (3). . . . . . . X . . . . X 23
- Decay heat removal heat exchangers (3) . X . . . . X
- Containment atmosphere recirculation coolers (2) (3) . . . . . . . . . . . . X . . . . X
- Reactor coolant pumps (2)(3). . . . . . . X . . . . X
- Letdown heat exchangers . . . . . . . . X . . . . X
- Control rod drive coolers. . . . . . . . X . . . . X
- Seal water heat exchangers . . . . . . . X . . . . X
- Fuel pool coolers. . . . . . . . . . . . X . . . . X
- Hydrogen recombiner cooling (3). . . . . X . . . . X 23 Boron recovery system cooling. . . . . . . . . . X Radioactive liquid waste system cooling. X Radioactive gaseous waste system cooling . . . . X Regenerant waste subsystem cooling . . . X Penetrations coolers . . . . . . . . . . X . . . . X Sample coolers . . . . . . . . . . . . . X . . . . X
- Safety related cooling water supply
, , o i V#
b'uO BSW 1 of 2 Amendment 23 3/31/76
SWESSAR-P1 Notes:
- 1. Each train independently supplies one pump and the third pump may be supplied from either train.
- 2. Two of four ccruponents are supplied frcan each train.
- 3. Cooling water supply tc, these ecxnponents is governed by a technical specification in Section 16.3.3.3. 23
,,, n ' :n 000 LVJ B&W 2 of 2 Amendment 23 3/31/76
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SWESSAR-P1 TABLE 9.2.2-6 EQUIPMENT SUPPLIED BY REACTOR PLANT COMPONENT COOLING WATER Supplied From Equipment Train A Train B r
- Eigh head safety injection pumps (2) . . . X . . . . X
- Low head safety injection pumps (2) . . . X . . . . X 23
- Containment spray pumps (2) . . . . . ., . X . . . . X
- Shutdown cooling pumps . . . . . . . . . X . . . . X
- Shutdown cooling heat exchangers (2) . . X . . . . X
- Containment atmosphere recirculation 23 coolers (1) (2) . . . . . . . . . . . . . X . . . . X
- Reactor coolant pumps (1) (2) . . . . . . X . . . . X
- Letdown heat exchanger . . . . . . . . . X
- Fuel pool coolers. . . . - . . . . . . . X . . . . X
- Hydrogen recombiner cocling (2). . . . . X . . . . X l23 Boron recovery system cc.71ing. . . . . . . . . . X Radioactive liquid waste t ystem cooling. X Radioactive gaseous waste system cooling . . . . X Regenerant waste subsystem cooling. . . . X Sample coolers. . . . . . . . . . . . . . X Penetrations coolers. . . . . . . . . . . X . . . . X
- Safety related cooling water supply Notes: 1. Two of four ccrnponents are supplied from each train.
- 2. Cooling water supply to these components is governed 23 by a technical specification in Section 16.3.3.3.
n~ ()b U i'] C-E 1 of 1 Amendment 23 3/31/76
SWESSAR-P1 TABLE 9.2.3-1 DEMINERALIZED WATER PAKEUP SYSTEM WATER CHEMISTRY LIMITS Fluoride Less than 0.1 ppm Oxygen Less than 0.1 ppm From demineralized water dearator only Chloride Less than 0.1 ppm 9 Sodium Less than 0.005 ppm Carbon Dioxide From demineralized water Less than 0.01 ppm deaerator Silica (as SiO2n Less than 0.02 ppm Iron, Total (as Fe) Less than 0.01 ppm pH 6.5-7.5 Total Dissolved Solids Less than 0.03 ppm Hardness (as CACO ) O Electrical Conductivity Less than 0.2 uMho/cn at 77 F
- , -. 3
(, /. f, o t, -
- c. , i 1 of 1 Amendment 9 4/30/75
SWESSAR-P1 TABIE 9.2.3-2 DEMINERALIZED WATER MAKEUP SYSTEM IITTERFACE REQUIREMENTS RESAR-41 SWESSAR Requirement . Reference Reference Demineralized water Section 9.2.3.1
- Table 9.2.3-1 21 chemistry Equipment supplied- Section 9A.5 Fig. 9.2.3-1 required flow rates Section 9.2.3.2 and pressure Table 9.2-2 21 Water Section 9.2.3.2 Section 9.2.3.2 requirements
*The oxygen and carbon dioxide requirements are not only at the 21 outlet of the demineralizer water deaerator.
. -. o
(, ( l L. i L-W 1 of 1 Amendment 21 2/20/76
SWESSAR-P1 TABLE 9.2.3-2 DEMINERALIZED WATER MAKEUP SYSTEM INTERFACE PEQUIREMENTS RESAR-3S SWESSAR Requirement Reference Reference Demineralized water Section 9.2.3.1 Table 9.2.3.1 chemistry
- Equipment supplied Table 9.2-2 Fig. 9.2.3-1 M Section 9.2.3.2
- Initial water Secticn 9.2.3.2 Section 9.2.3.2 requirements
- Only the seguirements of equipment supplied by Westinghous* are interfaced.
/ f m ~' m
' . u ..J W-3S 1 of 1 Amendment 18 10/30/75
SWESSAR-P1 TABLE 9.2.3-2 DEMINERALIZED WATER MAKEUP SYSTEM I17TERFACE REQUIREhENTS B-SAR-205 SWESSAR
- Requirement Reference Reference Domineralized water chemistry Section 9.2.3.1 Table 9.2.3-1 0
Water requirements Section 9.2.3.2 Section 9.2.3.2
- B*W's make cp and purification system is modified as described in SWESSAR Section 9.3.4.
, , n --
ivu c,r B8W 1 of 1 Amendment 30 1/28/77
SWESSAR-P1 TABLE 9.2.7-1 PRIMARY GRADE WATER SYSTEM WATER CHEMISTRY LIMITS Reference in NSSS SAR NSSS Vendor SAR Section 9.2.3.1 RESAR-41 Section 9.2.3.1 RESAR-3S Section 9.2.3.1 30 B-SAR-205 Section 9.2.3 CESSAR
, i 3 "' ?
( _) 1 of 1 Amendment 30 1/28/77
SWESSAR-P1 TABLE 9.2.7-2 PRIMARY GRADE WATER SYSTEM INTERFACE REQUIREMENTS RESAR-41 SNESSAR Requirement
- Reference Reference Equipment supplied- Section 9.2.3.3 Fig. 9.2.7-1 required flow rates and Appendix 5A Section 9.2.7.2 21 pressures Table 9.2-3 Water chemistry Section 9.2.3.1 Table 9.2.7-1
*Only the requirements of equipment supplied by Westinghouse are g interf aced.
f .f 7 ~ .' [i e L c. J W 1 of 1 Amendment 21 2/20/76
SWESSAR-P1 TABLE 9.2.7-2 PRIMARY GRADE WATER SYSTEM INTERFACE REQUIREMENTS RESAR-3S SWESSAR Requirement
- Reference Reference Makeup water flow rates Section 9.2.3.3 Section 9.2.7.2 Table 9.2-3 Section SA l21 Section 9.2.3.3 Fig. 9.2.7-1 Equiptuent supplied Table 9.2-3 Table 1.7-2 l2i Water chemistry Section 9.2.3.1 Table 9.2.7-1
*Only the requirements of equipment supplied by Westinghouse are interfaced.
y W-3S 1 of 1 Amendment 21 2/20/76
SWESSAR-P1 TABLE 9.2.7-2 PRIMARY GRADE WATER SYSTEM INTERFACE REQU E MEITfS B-SAR-205 SWESSAR
- Requirement ,
Reference Reference Water chemistry Section 9.2.3.1 Table 9.2.7-1 Water requirements Section 9.2.3.2 Section 9.2.7.2 30
- B8Wes makeup and purification system is modified as described in SWESSAR Section 9.3.4.
u
/_ v B8W 1 of 1 Amendment 30 1/28/77
SWESSAR-P1 TABLE 9.2.7-2 PRIMARY GRADE WATER SYSTEM INTFRFACE REQUIREMENTS CESSAR ShESSAR Requirement Reference Reference Equipment supplied Table 1.2-2 Fig. 9.2.7-1 Fig. 9.3.4-1,2, Section 9.2.7-2 3,4
*SWESSAR Section 9.3.4 21 Water chemistry Table 9.2.3 -1 Table 9.2.7-1 Section 9.3.4.3 (M-1)
- C-E's chemical and volume control system is modified as described in SriESSAR Section 9.3.4. Interfaces between SSW systems and the modified CVCS are stated in Section 9.3.4 of SWESSAR.,
- ~ c; C-E 1 of 1 Amendment 21 2/20/76
SWESSAR-P1 TABLE 9.2.10-1 CON'. R0L ROD DRIVE MECHANISM MC7POR COOLING SYSTEM PRINCIPAL COMPONENT DESIGN AND PERFORMANCE CHARACTERISTICS (bncrol Rod Drive Cooling Pumps
'hrnber 2 Capacity, gpn 300 Head, it (Later)
Design pressure, psig 150 Design temperature, F 220 Classification NNS Control Rod Drive Coolers Number 2 Design heat load, Btu /hr 32 1.335x106 Tube side - CRDM cooling water Flow, gpm 300 Inlet temperature, F 129 Outlet temperature, F 120 Shell side - reactor plant component cooling water Flow, gpm 300 Inlet temperature, F 105 Outlet temperature, F 114 Design pressure 150 Design temperature 220 Classification Ims Control Rod Drive Cooling Surge Tank Quantity 1 Capacity, gal (Later) Design pressure, psig Atmospheric Design temperature, F 220 Classification NNS
.)
, a i_ v d B&W 1 of 1 Amendment 32 5/11/77
l DIESEL N L
->& GENERATOR YARD 9 BUILDING 4-- BURIED PIPE
{ __________+__a , I o l - I a b l l S'.'P PL E' TENT A R Y l l LEAK COLLECTlap Tl S RELEASE SYS. I
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- 7. TYPICAL OF THREE TRAINS ( A.B,C).
- 3. TYPICAL OF TRAINS A L B ONLY.
4 INTERF ACE P0lNTS,5fM-9, APPLY TO APPLICANT'S ULTIM ATE HE AT SINK. DOTTED INTERF ACE P0lNTS,5fP4-6 AND SWP7-9, CORRESPONO TO TRAINS B & C RESPECTIVELY.
- 5. TYPICAL OF TRAINS A L C ONLY.
- 6. CH(MICAL FEED sitt BE SITE CEPENDENT,1NTERFACf POINTS SWP10-12 APPLY TO THE UTILITY APPLICANT'S CHEulCAL FEED SYSTEM. , , .[,'
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- UN E CA T I O
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l i j (SEE NOTE 3) l~X X~ _. - l f,- -( ' f ; g f 5- TI , I REACTDR PL4T l FE' "'
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h3--- l CB i l j [ ,q V L/ MCB i________ Q t L- - - - SC fI.C} _CI4_; t WCB y' . .O l REACTOR
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ATER PUMPS - FT ___ FI I di PURP *A' ( ' PURP"B'(q ') ib l_i
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Bl l m rr' O TU AUIILI ARY FE SYSTDI (EEREh FIG.10.4.ID-1 SEE SEE l % 0. TO FUE NOTE d NOTEa f BURIED L ANNULUS r NAKEUF YAR0 2 a 2 PIPE 'I BLOG. FIG 9-1 y L_______ _ ___ - t NOTES:
- 1. THl$ SYSTEM IS SAFETY CLASS 3 (SC-3) AND SEISulC CATEGORY 1 EICEPT WHERE OTHERtlSE NOTED.
I
- 2. INTERFACE POINTS, SIPI-E, APPLY TO UTILITY APPLICANT'S ULTIMATE HE AT SINK.
- 3. CHEulCAL FEE 0 flLL BE SITE DEPENDENT. INTERF ACE POINTS T-B APPLY TO THE UTILITY APPLICANT'S CHEMICAL FEE
-rper.er39 -o ._ o 9 mA8O bi 'hr - ^Nd i II','.i,~a.\ hg ' , g id O Q u V " M
A.A C CONTROL BLOG. GNfRATOR g g BLOG. I
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] r TIATER j k /
I ( ) CHILLER I I /' \ /'
/
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- RECIRQJL ATI(h ;,
,L%ir CICLER i 6 FIG.9.4.2-1 ][c s , l 8 1/' J' E l FIG.9.4.2-1 J g PUNP
'as
_ _ _ . _ _ _ _ _ ~ _ _ _ _ _ l i l
@ )N6 TARD M
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w I cg; p g _ ._. _ _J O, lt.g in I 4 BulilED PIPE Tl I L.D. j r 62 , s'
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. RECIRCULAil0N PLtfP
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+ LEAK "1LECTION (ggy LNii --
1 1 L.O. QRERS l r- - 1
& Rill SE SYS. > QXLER j lW QJBICLE LNIT FIG.9.4.2-1 FIG 9.4.2-1 g I 9 1
(Il0LER '
' I d il il
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DEATER ' ' FIG.9.4.2-1 I l " i I WILLER I OlESEL
' i l (DOENSER I GENERATGR RECIRQJLATION l i l ' I PCOL R RGDICT) -. _ __ _. - - .- -l L. ] E
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----____j _
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BURIED PIPE -- REACTOR PLANT SERVICE RATER T ~ r-L.O. g I PIR REFERENCE PLANT SAFETT ANALYSIS REPORT I l SIESSAR-PI
,$y377,- l g Oi M ,.s TARO O!C CONTROL BLOG. , f i
I 1 ANENDIENT Ig I2/12/75
250 200 - N 3 .50 - o
=
Q START OF f g 100 RECIRCULATI 6 1 50 - o ' ' ' 10' lo' 10 3 lo* 10 5 e[ TIME AFTER ACCIDENT (SECONDS)
~
FIG 9. 2.1 - 2 REACTOR PLANT SERVICE WATER SYSTEM POST-DBA "' : udvE IS BASED ON FIG 6.22-3,6.2.2-5 D WWW W8WM h'- AND TABLE 9. 2. l -3 PWR REFERENCE PLANT SAFETY ANALYSIS REPORT SWE SS AR - Pl W-3S AMFNOMFNT la in/in/75
1
~
ANNULUS BLOG. - u CONTROL BLOG. rl: OlESEL 0 HYOROGEN RECOMBINER I A HL CUBICLE UNIT COOLER l FIG.9.4.2-1 l l l I l N I N_l@ N@ b@ N@ 6ll , ( ) l$00f;oa l A L l L.O.n PU BP l l l i 2 .. --____, SUPPLEEENTARY CHARGING LESF AREA ag i i i
'g i
l vg LEAK COLLECTION . PUMP 7 UNIT COOLER g l ' ' A & RELEASE SYS. sCUBICLE FIG.9.4.2-1 y l l ER UNIT COOLER UNIT 000LER (TYP.) l CON $ R 'i I FIG.9.4.2-1 l i FIG. 9.4. 2 -1 g , I PU R P ', I
' ' d i d i i i i i.
' A1 L.O.E g
- TO FUEL POOL r---,--g '
l l i , MAKEUP (EMERGENCY) I Y ARD -> J . L _ _ _ _ ____ j _ _ _ _ _ F_L .9_.l_3-2 _ _ _ _ _ _ _ j G 4 81RIED PIPE F L.O. ( i L.O. F---~--
- - - - - - - - - - - d M IESEL 1 GENERATOR BLOG.
I HYOROSEN RECCMBINERlI + I SUPPLEMENTARY CHARGINGPUMPCUBICL/CUBICLE 1 NIT COOLER I CONTROL BUILDING 5flE 9 4 2-1 WATER CHILLER I LEAK COLLECTION & UNIT COOLERS
- l l RELEASE SYS. FIG.9.4.2-1 \
CLBICLE UNIT CLR. l 1 l@ I DIES (.L GENER AT". FIG.9 4.2-1 I Il l 1 t.0.
/
---- - i t
[ , i r -- , kg I l - - - - - - ,\ ! l i ,h I I M
>\N l l CH LLER CONDENSERI i
I T _ T i i i ,r i ESF AREAf l - RECIRCUL ATION PURPl ! i i UNIT COOLERS i FIG.9.4.2-1 g
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l (TYP.) g TS d ' 2 6 o I d i d
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.3-2 i , FIG. 9.2.1-1 j
X+ c BURIED PIPE N L.O. REACTOR PLANT SERVICE WATER i
, L.C. IPER REFERENCE PLANT I
ISAFETY ANALYSIS REPORT s. I
!q A1 ->re- CONTROL BLOG. - W Sl[SSAR-P1 EED SYSTER. h b b h h,mt. g '
i
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HEAT EXCHANGERS
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E ! ---1~~~ I NCB MCB h - V
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CB
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i NOTE 3) SC-3 , il UQ l [
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, YARD - - ANNULUS BLCG.
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- L.0~ / h ICB [_CIAl O FUEL PCOL SEE NOTE 2 FE d i i U $ REACTL' PLANT COOLING PUu!
BURIED I s ___!--- i [CII-- F. C COMPONE'T COOLING WATER HEAT EXCHANGERS CUBICLE UN11 PIPE I l COOLER S 3)\ / M B NNS , Y / y u_______--_, SC N /TA\__ M ! e g
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' TO AUllLIARY SATER PUMPS ""
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e ' O ,, j
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TATER SYSTEu FIG.10.4.10-1 J ,
/{SEENOTE2,\ / -
y TRAIN "B" '? T C g g g i
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u_________.___.-___________ NOTES:
- 1. THIS SviTEM 15 SAFETY CLASS 3 (SC-3) AND SEISMIC CATEGORY 1 EXCEPT WHERE OTHERWISE h0TED.
- 2. INTERFt E POINTS StPI-6. APPLY TO UTILITY APPLICANT'S ULTluATE HEAT SINX.
3 CHEulCAL FEED alLL BE SITE-CEPENDENT. INTERF ACE P01 HTS 7 - B APPLY TO THE UTIL;TY APPLICANT'S CHEMICAL [ ,h
~ g l OlESEL ANNULUS CONTROL BLOG. C aC GENERATOR Bull 0ING :I= i ) BLOG. l l n n a n - I; Xo Xo >D Eo,
-.- I b d D '
D / Oj, C hhS' CHILLER i S
/
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i l l DIESEL l
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/ /\ '
/ /
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I _ _ _ _ _ ' i I COOLER
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SijPPLEMENTAFY mARGING ESF AREA i I, I I leu 0)LLECT10h PUWS LNii l ' l
,* y & RELEASE XJ 0)BICLES pp XcC00LERS XO I j CHILLER j i
SYS. 0)Bi1E thli C00LERs Fig.g.4.2-1 l i I (DCENSER i ER i i l j ,UI.,! C)DLEP i i F I G. 9. 4. 2-1 i i i i
'_ REClR0'LAil0N ,
i g g g,4.;.r ; ' E l i \ P(Np 2 6 _.____.____________J i l ID EU F i YARD M a l 1 -
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l l v - _.____.___________J .fs\ Q M
< CHILLER CGCENSER I *
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,LE M QLLECTION CHARGING PUW CL'9!a E g lhli ESF APEA
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---1 2 ~& RELEASE SYS. < UNIT COOLER CDOLERS FIG.9.4.2 1 l
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-- _ _ J .0. a l
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,
- SURIEC PIPE .- p i
X ~ r REACTOR PLANT SERVICE WATER L.O. I PER REFERENCE PLANT I SAFETY ANALYSIS REPORT .- SIESSAR-P1 ,,v l l , T ARD 4- CCNTROL BLDS. N gp-I AM."CMENT 19 12/12 75
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T FT T BURIED (pit 3 PIPE MB QCB h '- [ - t i N -s , 4 f p; O _ _ _ __ __ PT MCB IV ' V NCB I r MCB cg Q MCB t- RE CHEMICAL c l [ V ' t FEED be.7 M e'F. C. fiE Y.' ITI '_ _ _ _ - } LINE i V\ .
~
(SEE NOTE 3) i ; , j l SC-' 7 [FS I d, REACTOR PLANT
, _ J v@ l /$ C3PONENT COOLIN l WATER HEAT EXDi E TRAIN A [] (. ;
b,QL MCB i 10 AUXILIARY FEECs { #'
' M SYSTEM (DERGENCY, PUMP 'A' PUMP 'B' s
D ._ FIG.10 4.10-1
' \ l I 'y'0.
L. TO BURIED I
' P00 SEE
/\ /\ SEE at PIPE Y ARD -* 4 ANNULUS gy i
BLOG. NOTE NOTE I FIG f f y
._ 2 " 2 FT e q I
L.0. [J I ANNULUS BLCG-
&C l-YARD
( SIP-C h X , c ;/; : SEE NOTE 2 <FE, : (V J3gp t R I'y;g__ SURIED PIPE I,
]
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R 7 g~y L CHEMICAL A( l g FEED LINE MCBIRAHH N ('.EE NOTE 3)l d i _ g g'g ' 1f_g i l l O NNS - -j - l 7 Iv i..__ _ _ _ ll _ ' i I SC-3 - V. C: ' C5 l ~~~ > r g ,MCB i f TT + @ 9 AL: V i ,f l REACTOR Pl 4T
/k REACTOR -
MCB i ENT i EDCLING WATEF [}S, PLANT yc FS i 'l HEAT EXDi E E
- SERVICE S-TRAIN 8 ~ WATER PUMPS q FET _ F ' FT r-
' 4 F1 T I I L sa TO AUXILLARY PuuP "A" (' PUMP'B'( ') J L I
~ 1.?(' '
'F CB I FIG.10.4.ID-1
, , X SEE .n SEE l* i
% L.0. TO F NOTE 2
j I" [f NOTEIf " BURIEC YARD ' 'a ANNytus : MAKE FIG-2 PIPE flL OG . 9 l i ______ ___ NOTES: I. THIS SYSTEM IS S AFETY CL ASS 3 (SC-3) AND SEISMit CATECCRY 1 EXCEPT WHERE OTHER8tSE NOTEC.
- 2. IN'ERF ACE POINTS, StPI-C, APPLY TO UTILITY APPLIC ANT'S ULTIM ATE HE AT SINM.
3 CHEMICAL FEED WILL BE SITE DEPENDENT. INTERFACE POINTS 7-8 APPLY TO THE UTILITY APPLICA W S CbEMICAL F (i e u ._. , U 4 w A'
5 7
/
si
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m _ G TO REACTOR 8"9 1 X" PLANT REGEN. EV AP. CONDENSER S AXPL ING SYS. ' FIG.9.3.2-1 ll EGEN.0lSTILLATE
]J i r SAPPLE C00LER(TYP)
FROM PENETRATICN COOLER (TYP) COOLER + REACT 0FL PLANT y p, SAMPLING SYSTEF1 ' r , , FIC.9.3.2-1 a POOL g r y 'A i r , , / 7 R TC FROM CONTAINMENT = j CH ARGING ATMO SPrt E R E - l' W ] PUWP C00LER R ULATION p p TDC rN i COOLER FIG.9 2 8-1 r HX
} {@
CTICN. h y 1 { PLNP (LOLER ___
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pgg, b* b .?" N L CONTAINWEN s - @.-- m, b d PWR -
))C LRTP REC RCILA 10N CCOLER / Dil -- -
Olt COOLER + $], 3 3 i ' p FIG.C.2.8-1 COOLER
) .{ g .} g"0CL E R Ny) -
THEWAL BARRIER ~ dY~h (' THERMAL BARRIER HYOR0 GEN j '
, pg y g g '
i REACTOR COOL @T PPS -_f"17 I Q C00LER / ,
,s' ~ Futt POLLI -
r FlG 0_2_2 IC g C00LER ( , L TO RE ACTOR PL ANT BORON _ -- - ----~ t"f I S AMPo LNG SYSTEM _J RECOVERY FIG.9 3.2-!
- SY STEM 3 ,
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~
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+
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4,., EVAPURATO:
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$2 ' '
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COOLERS h h (TYP.) D 4 r", FIG.9.2.2-1 G(4hJ I # Oil COOLER l--- l g r lb RHR REACTOR PLANT COMP 0t.ENT COOLING WATER hh ,l M 'd' ( , PUMP , PRR REFERENCE PLANT i, '" COOLER
" , ,, , SAFETY ANALYSIS REPORT
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.-)
REACTOR COOL ANT PUMPS / U ,; Q c,c AAEN0 MENT 21 2/20'76
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('\ FROM _ MMINERAtlIED 9 - REACTOR PLANT I4 2 TATER VAKLUP SYSTEM N' \ OMPONENT C0vllNG RATER SURGE TANK WASTE
-4 ~
pic g 2 3 1 EVAPORATOR CONDENSER 1 r 1s LIQUID i r i t 3 ( - WASTE
' ~ SYSTEM RFACTOR PL ANik ' ,
) COMPONENT _
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*Q
=
.r-1N f C00llWG WATER WASTF SAVPLE -
PUMPS CGCLER f FUEL, FUWF C60LER5 , CCCLI FIG.9 2 2-la 3 ADDITION TANK (1 CONT H65i LHS i
/ 7' 7 ;pgv REACTOR PLANT l '3r SFRAYs il
[C04PONENTCCOLING d
's t
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REACTOR PLANT I - - - - CCMPCNENT ' F1;.5 2 3-1 C00 LING WATER l J {"" i i PUUPt '" '
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'I w r V! ] "*'"" , ,
+ :
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,p . _
'sl ' '
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_ m i REACTOR PLANT ' '
' PCMP COOLERS -
3 j'g/ k - @ w, COMPONENT i FRAY HHS LHSI
, CONT.INWENT \
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- ATMOSPWERE HE AT EXCHANGER RECIRCLLATION v git <
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; r i ,
i i t imus I I J CHEMICAL A00lil0N U TANK - THERNAL BARRIER
- 8 3 ,
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L10VLD WASTE SYSTEM Pi TO REACTOR
'C Q PLANT SAMPLING X- - /=
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- (TYP) 3 -s sASTE DISilLLATE
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'f 7 PUMP COOLERS HH I N W I CCP-3)
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p F (. - mn-(.N/ 3 Fl3 9 2 2-1A C REACTOR PLANT CONPCNENT 8 C00LINC WATER (O. PWR REFERENCE PLANT S AFETY AN ALYSIS REPOP.T
$1FSSAR-Pl W allen 0 MENT 19 I2/12'75
3 i REALTOR PLANT CCvPONENT COOLING WATEN SURGE TANK r
,MCB , MCB u,
[ f's U ^ ' - (p's i LC FROM l RE ACT' it PL?NT ' TA AL i DEMINERAlflE L;CMPONENT
/ I RATER MAKEUP ' - - CI A , CB_ _ , M CB COOLING NiR ..
FIG S 2 3-1 NOTE 5 . HEAT EAL .NGER { <g g j d ' u _C_B CB H- k' c->.x " 6s 17 W, _ i -e. rTi f
,,( MX f 4 .) Hg5 E @ 1 r
'KB REACTOR PLANT g3 SE9VICE WATEd w r ':
' ' I 2 I~I i ,
'f REAvr0H PLANT CCMP0NENT 5
,g C00 LING WATER DUMPS , ,
'3 I i
i r
.s CH ~" C A L P DC' A00lil0N
'V TANK TRAIN A NOTE 4 ok' CIAj_ _
I L _ (,
- 0 X F .C.
SC} % I NNS 1 J b h N 2 k r ' 26 L d L I r NOTES- ' '
- 1. THIS SYSTEM 15 SAFETY CLASS 3 (SC3) EXCEPT WPERE OTHERTISE NOTED
- 2. ALL SC2 AND SC3 PORil0NS OF THIS SYSTEM ARE SEISMIC CATEGORY 1.
- 3. EtulPMENT SUPPLIED BY NSSS VENDOR
- 4. EMERGENCY POTER FROM THE ORANGE EN'RGENCY BUS SUPPLIES THIS TRAIN TO IRCM
- 5. CONNECil0N IILL BE MADE ABOVE NORMAL IATER LEVEL IN TANK.
flG 9 2 f / i" , , I I.. tl '
. 1
I
- TO REACTOR PLANT BORON RECOVERY SYSTEM '
_ S AWPLING SYSTEM FIG 9.3.2-1 M- (DNDENSER (CCP-84 : DCP-83) c x PENETRATION JE[VAP s , '\ '\. COOLERS ~~~ (TYP) (- BP.RON THERMAL i ~ REGENERATION <tCP9
~ FRON REACTOR Pt*T ,
CHILLER SAMPLING SYSTEM NOTE 3 - FIG.9.3.2 t c) agg ; _t _N Px l OI NOTE 3L 12
' INSIDE MOTOR AIR C)0LERS ANNULUS CCP-G CCP-fl BulLDING [ 4 CONT AINVEST STRUCTURE
< ~^
CCP 44 NOTE
" 3(')
p, CCP.i3' & &k- __ PTP h RE - - '
#CB I - yMwo
- ClB COOLER 4tp.12Ggs o CIB ! s_-
Q' L
}.Fl, CCP-45 CCF-46 @ __,
- C@-59>I~ l g WCB
[ p,g, ott , SC3 V NN; \ . @- g@1 cts o C00Le , ye-o, '! , sets
~
, rQ)NT HHil LH;l g 77l j
- M F/ . (IP G6
- SPRAY NOTE 3 NOTE 3 c-~,, ' hy- SC2 -*
- i k' THEINL ' REACTOR QRWT
, r 3 ,
i r SC3
! ggapig pgg 4.1 g 3 @ 43
~ 2 FUD.
3MN$ POOL )b ' f W ) p % ICT@ AlH
" QREE E' 3 y y y, LETD0m _gl0LER HYCfrJGEN Tu TR(y [ ;Cfj7 g b , HI NOTE 3' r REQ 1431NER Q)NTAlWENT
' % , j>p% g V D' OtAA.,1NL F.C.
W LER I RECIRQ1Atl0F j C[Bj g.g@__ 2_ , _62, p.g 7-COOLER ptpg g U E TV Ott
; / g _
I Cf B_' b) fjI5[p 90 [h) c [ b b
- in ,_= % tes _ s u, Co-20 H i GA a Mwu, o
( mb .m;6. y o u _1_ 07 -78 3 ($ m 6 Y
^
h
- THM" REACT @ QDLMT lC@-16) C@-19 h-38 j i
baler / SC3 y 502
- SC3 PDF W.2 E 3 ~
PUNP COOLERS FIG.9.2.2-1B REALTOR PLANT COMPONENT COOLING nATER l-l C PRR REFERFNCE PLANT SAFETT ANALYSIS REPORT SIESSAR-PI g )(YS nop".(dJn#' yum ,
,o AVENOMENT 21 2/20 '76
~
REACTOR PLANT Cr,MPCNENT COOLING WATER SURGE TANK r A MCB x FRnN MCB ' ,MCB Y_ _ __ _ __ __ _ __ _ _ _ __ _ __ TD.FRCu FIG.9.2.2-1 CEhiNERAll2E0 h j -- - ~ ~ " LG i WATER MAKEUP '
!' 'k SYSTEM NOTE $
~
@ ' r REACTOR CS MCB M COM NENT TT r-J -
4%' ( Mb {T . + C00 LING WATER HEAT E XCH ANGER MCB , _I CIA--- T p.C
-{'/d l'H o +
r MX- * ' a ' ' FE SC3l SC3 NN S' g' r Sf3 J L ,' d
, REACTDR PLAN' SERVICE WATER T -
h REACTOR PL JT COMPONENT COOLING #IUI 2 I-I,G F.C NNS WATER _PUNPS gg3 ,- - j! ) . Ce Lj
\
CIA I C'A I CHEMICAL v ADDITICN TANK g
TPAIN B (NOTE 4) 9 Pir
.J 6s s i' r
'a 6 NOTES:
- 1. THIS SYSTEM 15 SAFETY CLASS 3 (SC3) EICEPT WHERE OTHEPR'SE NOTED TO 'FRrW
- 2. ALL SC2 AND SC3 PORTIONS OF THIS SYSTEM ARE SEISMIC CATECORf 1~ FIG.9 2
- 3. EQUIPMENT SUPPLIED BY NSSS VENCCP
- 4. EMEPGENCY POWER FROM THE PURPLE ENERGENCY BUS SUPPLIES THIS TRAIN ~
- 5. CONNECTION IILL BE.MADLABOVE NORNAL IATER LEVEL IN T ANK.
- 6. PIPING.VALVESANDINSTRUMENTATIONAREDESIGNEDFORREdORi .-
COOLANT PRESSURE AND TEMPERATURE. I (; .u
A TO REACTOR PLANT SAM / LING SYSTEM FIG.9.3.2-1 BORON RECOVERY GASEOUS WASTE SYSTEM SYSTEM s f PE NE T R AT I ON EdPORATOR , Py
.) e CONDENSER \ I c COOLERS O o YQ T DEGASIFIER TRIM N N (iYP)
M, M } 000ENSER (DOLER Jf% H' p) g y g V gc g ' l OlSTILLATE COOLER + _ -)GM f-i>SP y s v-(g SAMPLE COOLER k(3 3 g] Oh C0WPRESSOR v AFTERCOOLERS
'P V C '
,,,4 _,, (
h y 4, ." FRCW REACTOR n fr "/ "_" [ _ . _ _ . _ - - -
't
- - - - - - - - - - - - - - - SYSTEM
- PL4T SAWLING FIG S 3 2-1 0RYERS
- c' A g pp
; "h. CCP-51'QCCP-52 O / *~
_q TO BLC'i o CCP-53 ACCP-S4 .C-s, C1B , 1, I , M'*C ,ICiB j
-. 1 G CCP43 ~-- A ' CCP-,4 ICTOR AIR C00LERS NOTE 3 f's AUCRY TASTE [fEArIO .'i i _
VAPORATOR CONDENSER v y , Olt i ty g ,y% ylN 5 Xc Vh- 4)b ____ COOLER, ; l, _. _ _ _ ;ss, _ _
._( <
g v
/ _(g C0Cm mTE 3
.\ J F S ,.-.- % W^^T; I
\\
( SC3 hwS CIB , i V OE X;0 B_ h' ._ _f Q_L_ l [
- ^
CCP-79i THERMAL CCP-0 k/ ,
*N *-
,,,' 1 i
T[;; H CCF-3C; tg ' BARRI ER. ~ ,7
- - - ~
,F.C.' 41CTE 6 ( FE T TE 6 + '
! ! REACTOR COOLANT -- . .g *z, RHR n i i PLMP NC.3 "N,0 CCP)5 '/~?CCP-56 l .C, hCif 3 1 , KTE 3 O / ~" ,_
x =' lCCP-18j ' y I g) CCPi? f CCP-xi - CIB
" ~~
T-MOTT AIR l LCLA J~ -- HHS: LHSI @ "A2 h -
,"d CCP-45? s CCPk ryci ros arTr 1 j '
y 503 SC3 3 h0TE 3.k - ER ,j ,'MCB h MCB N"- y l s p -- e - . - - - - - - - -- __;
' ; [ifP-71 ' TO TTLW .
CN AIMNT l I t FS t FS ,
./
,N [ , RECIRCULATION
' ' I Q[
('f ( \~ e( E EELER
; C_1B_ _-
g PORDN INJECT.ON FIG.9.2.B-1
" p' ~9 s PU"P C0CLER Q,M
's ' ' lCCPAl /~
-y > f_ _ e 7 ,,
NOTE' 3
""" s"Q e C7-8 IMFtHIER L ' THERMAL 3 , L"*
)IMCCT-Z2S '* 2 TE S REACTOR CDOLANT ( II *
' 6
'WP COOLERS ,k PLNP 2. 4 NOTE] 6 s. 1 SC3 4' SC W SC3 ' Cfk i ANNULUS _._ g lNS10E iIG 9.2.2-1C ""h ' ellL0 LNG CONTAINMENT 7C STRUCTURE REACTOR PLANT COMPONENT y
~~~
COOLING WATER CM PIR REFERENCE PLANT (Q SAFETY ANALYSIS RtPORT SNESSAR-PI Q F f
, v.n CC3
,, , .i em u s
TO FRCW REACTOR PLANT COMPONENT FIG.9.2.2-1B COOLING WATER SURGE TANK r ' ' hj f ilH , (iAl /tEli ' i LG h I-- CD MCB
-J l
h' REACT @ PL#iT C ,MCB MC8 MCG
"- " l ^\--f' i
FRON WCB NCB CQAPOENT C00Lt AU > L--4 CEY:NEPatlZE0 f- a 51 MCB 2 CE5 ; , C05'FR E S S O
- 2*J ,
- SOLIC n!
m)>X
- d
_ , '- s a> , P DECfNT4 i k
, e FE.') '
V A y/ j'- 9
, i REACT I PLANT
-- r- )
j
-r
' (g/ SC3 , r, SERVICE saTER s
SCC t n- FIG.9 21-1 N_,uSC3 _ I-[ , CIA I F.C. 3 REACTOR PLANT NS 'TY s COvP0f NT COOLING i WATER PUMPS g l , j _A _ q'" { +2 T M, r
- _y i
,j i
, , rcP-29
* ) sg g t l 3 fC- #
3 {C '
'P
{CHTMICAL j _ , _ ADDITICN v u I TPAIN C (NOTE 4) CCNT. spray
; 2 g r
, s 4
\f
/,
/Tl v
% KP T-1 P NOTES'
- l. THIS SYSTEM IS SAFETT CLASS 3 (SC3) EXCEPT WHEHt OTHERelSE NOTED.
- 2. ALL SC2 AND SC3 PORil0NS OF THIS SYSTEN ARE SEISMIC CATEGORY 1, 3 EQulPMENT SUPPLIE0 BY NSSS VENDOR.
- 4. ENERGENCY POWER FRC4 THE GREEN EWERGENCY BUS SUPPL r.S THIS TRAIN.
5 CONNECTICN WILL BE ABOVE MORAML WATER LEVEL- IN TANK. . ,.
- 6. PIPING, VALVES AND INSTRUMENTATION ARE DESIGNE0 TO REACTOR COOL ANT .
PRESSURE AND TEMPERATURE.
% e y_l j
.1 ANNULUS !- INSIDE MOTOR AIR BullulNG I CONTAlhMENT MOTOR AIR COOLERS l STRUCTURE i OCOOLERS m 4 FUEL
= h! .l 1 r i r m
$O Oll Oil O
EXCESS' POOL b COOLER r R C00LER ENTRIFUGAL LE 00tN
- ARGING COOLER l lC0 A NMENT *b E lATMDSPHFRE d ' !
RECIRCULATit'N m l ' HYOR0 GEN THERMAL t , 'y y RECOMBINER l COOLE RS BARRIER (p COOLER l FIG 92.8-1 q , 3,
"'______--L--
- - - t- -
REACTOR COOLANT PUMPS FIC.9 2.21 A t w ay ,ASTE L_ _ _ - - - l < i EVAPCRATOR I BORON RECOVERY ["' (I)NCENSER SY STEM l h ': . l HEP #AL 'J': ATION l CHILLER DI STILL AT E mg s q d' d' l COOLER
)b )b I
'l l I CENTRIFUGAL
{ EVAPORATOR l bd CONDENSER g :E b i N :t :S I FIG.9.2.2-1B T------ [ A COOLER E i
,F_l G. 9. 2. 2- f C j
a I l , 1 MOTOR AIR W MOTOR AIR CMPRESSORS l' l h COOLERS COOLERS l 1 i
-X ( xe
=
9 p& a , n >
= , - -
SEAL RATER HX FUEL POOL COOLER 1 rg l l 1 ' 1 ' Oll BARRIER OIL BARRIER
~ "
j X lTO,TROM C0hTAINMENT _ b-,. l ATMOSPHEht 3 i
' y N
lRECIPCulAil0N COOLERS THERM AL ah RE ACTOR COOL ANT THERMAL BARRIER
@1 ,
BARRIER RE INER FIE.9.2.6-1 @ PUMPS l
...... - TG331 "
REACTOR PLANT CmPONENT COOLING WATER l I PIR REFERENCE PLANT I SAFETT ANALYSIS REPORT SIESSAR-PI l
'" (,((, NU AMENDMENT 21 2/20 /78
O REACTOR PL ANT C0uPONENT COOLING WATER g SURGE TANK FROM DEulNER-ALilED r
' ' +
WATER MAKEUP ( , RHR 1' SYSTEM - z~ "* gqg FIG 9.2.3-1 [ REACTOR PLANT g-
- % [gi -
\) \ ~ /{
~
COMPONENT U ,' k
/ COOLING BATER ]
d 6 PLlWP S > TRAIN A A I b -l,. h)[ I' PUMP COOLERS l CHE4ICAL ADDITION REACTOR PLANT COMPCNENT V TANK COOLING WATER HE AT EXCHG5
; LIQUID WASTE SYSTEu REGENERANT gASTE
. 6 1 1r . -
EVAPORATOR . EVAPORATOR I 3 I g ll ki ' -' TO F D REACTOR PLMT i,
- CONDENSER k*j
- C[hDENSER FIG.9.2.2-1 A 7gAyjg SAIFLING SYSTEN l 0 i LL LLATE BORON h
y IIE I'3* 2~I FIG.9 2.2-18 _ ][ ' (IDLER
' (TF s dl - COOLER 1'
CDOLER REGEN
'1' RE GENE R ANT
; WASTE SMPLE S,WLE SAMPLE
-(HIER TF; ' f **b C00LER COOLER
/ T PENETRATION C00LERtIYrs gg* ~ 'I '
_ GASECUS sASTE StSILM _ REACTOR DEGASIFIER TRIM' REFRIGERANT ar ORYERS PLANT d e CORNSER COOLER - 3 i SA1 FLING ' FIG.3. 3. 2h t , [ FIG.9.2.2-19 FIG.9.2.2-IC ~l b b.) + i , , ,,
- COWPRESSOR , ,
1 AFTERCOOLERS - FR0u REACTOR PLANT CCEPONENT d' DENINER-ALIZED COOLING WATER SURGE , r h I I l ' , 1 r TANK uk EUP l __ _ _ _ _ i _ _ ___ ___ I RHR CENTRIFUG,R LET00 ilG.9.2.3-1 1 r t H1 WARGING HI [ T 1 r A CONT. SPRAY Sl RHR
\ .
(}M ' REACTOR PLANT
- i
\
- COMPONENT COOLING k -
' y, TRAIN B RE ACiun l" ANT F! COMPONENT C00Lin; @ @]"'
f CHEMICAL IATER HE AT EICH ANGERS PUuP g COOLERS
- ADDITION TANK
, ,- ~n1 l . -; b vl 1
P%E NGbii UnidN#L- -
i AletULUS _ fjg :NSIDE BUILDING ; 'ONTAINEENT l STRUCTURE l ! I I
@-43 CEP-4:
o o TO FIG.9.2.2-1C ' d' O , D
' ' !@7) (1y4 SC3 MlC2 ESC 3 '
Lcli * *[4 A 4*4 iCte O
- l Q.. QP-39 > ~
3 Al MERS j ', 'M pu;c Of ER g C00LEh1 (CCP-25j N ' i_.1.~ b i i Ei-
~
i be M
, CEP-7$
L[ h 3 me\
$ y* w
.HE%AL BARRIER IM (C&-3 sF FUEL POOL A g7E SM WTE 6 4 COOLER q
lCC95 UEF RiR 2PJ r if RuCrm f'E ' d f TO ru CWTAl'eENT SS COOLAhI R.NP NO. I NOTE 3 s / hTDRDGEN ATICSR.ERE L g 57% (ECP-58--' _
^
g]p RECr3EINER REClRLATim h0 3 ' CIO l l C&-4] CDOLER COOLERS CCP-7T, @dgj Fir 9 2.8-1 ,p N I g h-- U 45 _ 4PQ-6 6_l NOTOR AIR EDOLER NOTE 3 y;
, ' ~ #
- l f %2S)'^ DIL I
(Il0LER g , NRif y^ F j DIARGING ' ' -~ -- r PtFD NOTE 3 l
' (CFTJ! ' l]
i l C1B j
' 'E I
LCIE8D
~
I u e. i 9s' , s' ~* BARRIER M h4 ' NOTE T "3 ESC 2++ SC3 TE 6 FE FE 6 FROI l REACTOR (I)0LANT PLhE' FC. 4 fCTE 3 FIG.9.2.2-1C l g N ' i r
}kffag drauto' n ma FIG 9.2.2-1A FIG.9.2.2-18 REACTOR ftANT CONPONENT COOLING 1/ATER PER REFERENCE PLANT ' ' s' SAFETT ANALYSIS REPORT SIESSAR-Pt 3 3s AXENDEENT 21 2/20/76
REACTOR PLANT COMPONENT COOLING EATER SURGE TANK CBI r \ e2280-I I l CIA Bl i CB
^
l I r, yy i L- [A[} l
)CLG
- L--- J
; l j CB CB k
r--- J -
< g FRft i A@ [.C.
DEMINERAlllED IATER MAKEUP
' i G
'gts "
gCg FIG 9 2 3 1 NOTE 5 PT
$Y & -
M~ "
, y* G )
tt , l I MM @ E l F sCCP-il l SC3 g {0 SC3 y f N N
. REACTOR PLANT COMPONENT ] h_1L REACTOR PLANT SPRAY i 4 COOLING WATER PUNPS SERylCE WATER -
l NN$ NNS FIG.9.2.1-1 T' M ' REACTOR PLANT COMPONENT Tl M I COOLING WATER HEAT EXCHANGERS PDC [ / i W l 6 ('
\ j l
l RHR s I CHEulCAL A00lil0N I HX i TANK Qe l I WTE 3 l F.C.3- -
;CCP-2) l4 6 I V " gJ r' i TRAIN A (NOTE 4)
CI A l I I I. C . E3 CI A l- TMF.C. r - - R I I
'M
_ ._)I AA I ",, RE L _ _ _ _ _. E I 3C_3 NOTES:
- 1. THIS PORTION OF THE SYSTEM IS SAFETY CLASS 3 (SC3) EICEPT THERE OTHERtlSE NOTED.
- 2. ALL SC2 AND SC3 PORil0NS OF THl5 SYSTEM ARE SEISult CATEG09Y 1.
3- EQUIPMENT SUPPLIE0 BT NSS$ VENDOR.
- 4. EMERGENCY POWER TO THIS TRAIN IS SUPPLIED FROM THE ORANGE EMERGENCY BUS.
- 5. CCNNECTION IILL BE ABOYE NORIAL BATER LEVEL IN TANK. ,
6. PIPING. INSTRUMENTATION ANO VALVES ARE DESIGNE0 TO REACTOR COOLANT PRESSURE (; ,~,1'i . ; .s ) AND TEMPERATURE.
WASTE EVAPORATOR i- ~- '- I CONDENSER
.i N I l l 1
- @ I y# - i
, , CCP-83) -3 l
- 4K . .
, , , (CCP-84 l LALNORY l
)
TASTE i , g l EVAP, l 1 { } l CONCENSERj BORON THERWAL { l 4 '94 WASTE DISTILLATE COOLER REGENERATION SYSTEM CHILLER l g i ,
+9 h WASTE SAMPLE C00tFR R Nn2 i
r l 1
~
\
I L__ __ _. _.1 SOLID fASTE & ECONTI#1 Nail 0N X BUILDING 4 RY SYSTEM COOLER 0
, N*
b
=
1 X*
$~
E my p7 } R \ { u,
'IG 9.2.2-1B REACTCR PLANT CCHFCNENT C0 CLING HATER PER REFERENCE PLANT SAFETY ANALYSl1 REPORT SWESSAR-PI ., ,, ,, ,
5-3S . t. u j u AMENOMENT 19 12 12 75
i 1 iC FRCW Ll0U10 EASTE SYSTEW FIG 9 2 2-lA t, . RECENERANT 4 EVAPORATOR N, CONDEN!ER i r
'jo c;o S[s Y
'"PENETRAT10N'^ ' '
'" CCOLERS (TYP)
TO FRDW > REACTOR PLANT j
->=9' X~
SAWPLING SYSTEW EGENERANT DISTILLATE DLER FIG 9 3 2-1
~ 4 p 9
,, G
.[9 /9 RECENERANT SAMPLE COnLER I
, y 10 REACIDR Q '
8b PLANT SAMPLING FIG 9 3 2-1 ,_
- BORON RECC GASEQUS WASTE SYSTEN i r l OfSTILLA 4 6 ~
Y '- EV i
- OEGASIFIER d C
/g I
ir C00ENSER f, b{b [f. > N C ER EVAPORA CONDENS
.. "[
h[ ,'- , ,
' . l k '
N/(
~ *- CCMPRESSOR (
8 " AFTERCCOLERS'
'l PENETRA CN COOLERS (!YF
.y ,
$ $- El
% : REFRIGERANT '
N I SauPLE FROM ORYERS 84 _ COOLER REACTOR A ~ ' ' ' r' 6(TYP) PLANT ' ' J SAMPoiNG b ' TO FRCW FIG 3 2 2-IC COMPRESSORS b *l o, T A _ r' r' g notes 1 THIS PORTION OF THE SYSTEM 15 NON-NUCLE AR SAFETY EXCEPT ,
, r-2 EQUIPMENT SUPPLIED BY NSSS VENDOR. [i[ ij _; b 3
MCB CB 10 /FROM FIG.9. 2. 2-1 A INSIDE 1 ' i b ANNULUS : e CONTAINMENT BUILDING STRJCTURE s
- a q d
y d' CENTRIFUGAL g CH AFGING
) [* b 3 I m r.
e ,,
$ sr-se ,
h ! fj > SC3ySC2*n3 - sb s 5 o-iO dh n" U i C18 ;(p. 4 k rn Og aficb CIS 1 r / ,
; Z ( n (CCP-6$ NOTE 3 h'
,i)- -'~ x-PuuP COOLERS 7
"TCP-29
][_3 DIL (DOLER yyqj fg.
T,ggg- - ' FUEL PCOL - - - - - l *- COOLER
- CP-27 l i i
- A B B p i <SA ( "),'
I CCP-11 CCP-37' f ' E ' RHR CENTRI FUGAL { h' '
<f N 3
NOTE 3 W ARGl% $ $ 3r 3 r- =X=> =i THEPJdAL , ! -Nd:. h y 8 6 d NOTF 3 SEAL RATiR
,*- WTE 6 h
v
/ 5';
v F NOTE + 0 r (GM $MM REACTOR QX1 ANT M , gg PLNP N0 3 [ C-
\ N01E 3 z ATMOSPHERE ) .-.J'" D -4T2 \(/ D C7-48.X' -
( h RECIRWLATION NOTE 3 _ IJ CCF-lh @P-38 C00L'ERS g4 g iI #" z b M1)
'4 O _fJ1 4
Tl h _V NOTE 3 gl d L 4 L o
@P-62 MOTDR AIR 7
b Tl g
~
Oil L I TOLERS ETE 3 {% TV f WOLER ' M3 MCB F.O. W'~ I , k][-o ' ' rll i ' l FC ! I I i % (,CCf,7[> ICP78! ': Ft
& 'i',. : n t l[9,kh Yy-
- LALCw J THERNAL ll 1
@'I e
SC2 *l %3
;*-- WTE S i BERIER gb p KTE *'
SC3 Y l REACTDR (DOLANT b, 6 Ptw NO. 2 N TE 3 - FIG.9. L 2-lC REALTOR DLANT C0t4PONENT COOLING HATER PER REFERENCE PLANT SAFETY ANALYSIS REPORT 'j SWESSAR-P Mi.
@ ' ,f i < ,<.; ,
-; .g r . T u. . e -
" 3S 'G*
AMENDMENT 2. 2/20'76 u svJ
~
10/FROM FIG 9.2.2-1B [
- f REACTOR PLANT COMPONENT COOLING IATER SURGE TANK e -e i r
_ __..NNS _ _ NNS LD
~ ~ - - -
_,__{ _ _[ 3 iMCB',MEB C0 l
; hh -)C '
F C.
\ I
'h]
IV tg ($ , . [
.- g YCB)
}
M NERAllZE0 hv Pl C. ( O
,_%, J fATER MAKEUP MCB 1 F I G. 9. 2. 3-1 MCB ;-- i NOTE 5 b Y
/
7 N i ' W' Tl (CCP-9
@ ~
K PDC /O SC3 yf g SPRA) NC j[c, REACTOR PLfNT ,
][o ~*- SERV CE AATER ,'
RE ACTOP PLANT COMPONENT IIO'N 2 I-I COOLING WATER PUWPS NS , r I , NN
' RkR -
REACTOR PLANT COMPONENT I gy (V TE I NOTE 3 COOLING W ATER HE AT E XCH ANGERS l CP-10
/H $
i CHrMICAL A00liiON j ( TANK l CIA } A F . C. M - - M[ ICIA I
'a TRAIN B (NOTE 4)
I NOTEP
- 1. THIS PORTION OF THE SYSTEM IS SAFETY CLASS 3 (SC3) EXCE
- 2. ALL SC2 AND SC3 PORTIONS OF THIS SYSTEM ARE SEISMIC CATEGORY 1 3.
- 4. 100lPMENT SUPPLIED BY NSSS VENDOR. EMERGENCY PDR _ ,_
5 CONNECTION IILL BE ABOVE NORM AL # ATER LEVEL IN T ANK. 6. PIPING, INSTRUMENTATION ANO V ALVES ARE DESIGNED TO PE ACTOR C00'.'NJ PRESSURE AND TEMPER ATURE.
=a k m. e O
i g--, CRC + - IRC g _ ~- .
- s hj ,_
r7
~
HIGH Z '
~ ~
PRESSURE
F COOLER FUEL M H AT ~
P00L CCOLER TOTR3d CIET Altt'E NT EX2 ANGER u gr HIGH i 3 , K1 r 3 4- CONTROL PRESSURE 1 ' l (( ___ f.I jj ATM1 SPHERE ROD COOLER p 3 i DRIVE 9 F SEAL RETURN COOLER LJ Li l FIG.9.2.S-1 CCCLER - REACTOR C CLANT REACTOR (DOL ANT E SEAL 40 Olt PLNPS SEAL AND Cll
,, 37
," , UI- . 00nLERS N RS Xl,7 3, e u C y : _
l DECASIFIER TRIM GASEQUS , BORON RECOVERY 3 CENSER (DCLER WASTE SYSTEM SYSTEM p,- g [f -}
; R I' b __
u o ./q
=Z- d
! BnRON 01STILLATE COOLER LAUNDRY 8AS1E CTPRESSOR 6
, lAFTERCOOLERS Ek APORATDR Dy
% CENSER l;
J q c" $ 3ERANT v S l
; BORON EVARRATOR C0t0 ESSER V{
- ou --
b -h (D'PPESSORS = h
, r BORON ,\' ,.
L.J g'rJ1 r i 1 SWPLE i r 3 r
, CDOLER --
'8 PENE TR ATI O.
C00 LENS (TYP> ; ;
'r A Jkt ~ \/ [ bI- ~ s vI s-s TC FR0" n [.
N l
' kl RE ACTOR PLANT j
A t A" FLING SYSTE" l r1 HICH oI FIG.9 3 2-1 - r 7 ,H. [l + PRESSLFE ]a k jl LETDOWS COOLER -- COOLER l ll 1r I _ ,/ ; _JJ HIGH i u v ! I u > i y CmTRCL
1' R00 PkESSURE FUEL POCL (c" i CTaLER 1 1, ORIVE H p (DOLER
.-; H o LJ
] -f]
COOLER i {--- __ f REACTOR C00LANT PtyPS REACT"R COOLANT PUMPS in FROu SEAL AND Olt COOLERS SEAL AND Oil COOLERS SEAL RETURN AT.. AERE COLER . nECIRCUL ATION f I CDOLERS
~IG 9 2 B-1 F'G.9.2.2-1 37 u n3 - , REACTOR PLANT CCNPONENT C00 LING WATER c,3 v ~,. nv
[ 3 PER REFERENCE PLANT X S AFETY AN.iLYSl$ REPORT SWESSAR-P1 ORC - > aG -- IRC
' B&h A4ENDMENT 19 12 12 15 1
1
') JGd
4 3 l C O FROM W N DEWINERAttIED , WATER \ 1 i NAKEUP REACTOR PLANT COM%ENT COOL WATER PWPS e ; FIG.9 2 3-1 3 , s g.g RhR _ r- - HI C[hT. MHSI Lu TRAIN A
] SPRAY p J#Gl% B
[ ->--
~
G/, v hi -) - haw a rj O . W,,
, REACTOR PLANT CCWPONENT ,s, COOLING TATER HEAT CHEFICAL I '
l EXCHANGERS A00lil0N TANK G ] , COOLERS I 1 FTGrfWj __ _ _ _ _ _ _ ._ _c _ _ - J, '
~
' + - d 'f~./ -~
FIG.9 2 M B. . LIQUID -
"" _ _ _ d,*" "
TASTE
~
- +-
REGENERUT SYSTEM #ASTL EVAPORATOR EVAPDFATa' C90EZER PESETRATICN S $P' ,- CONCENSER C0CLER (TYP.) 2LER;TYP. ) . 1
/[\ fi, /N i RECENtR4ii d L}}
Nfl
* { -- { *- DISTILLATE COOLER RAVE Of STILLATE C)0LER
~
, r f REGENERANT 3 '
S&PLE (DOLED sASTE w' I SWLE 6 y,, r, V C00lER k A - ri_ FIG.9 2 1-lC
~
REACTOR PLANT COMPONENT COOLING TATER 62 SURGE TANK , , , ' ' FRCM M g glqq pyyp CEWINERALIZED G COOLER 9'r WATER 62 sw F' L' MAKEUP p 7 FIG 9 2 3-1 C00tlNG TATER PWPS 3 , A.1 I W) . TI TRAIN B ( f l' RG ],
>*f>
=HX =
C[hT . HHS! l l SFRAY
>$GN l GM h (^h b:. 'H REACTOR PLANT CCr*0NENT COOLING TATER HEAT
( l n,r PUYP EXCHANGERS d' v C00LERS ' CHEWICAL A00lil0N TANK p~ -~.,, k 5
..a, ~ ., c ,
4 REACTOR COOLANT PUWPS Al & A2 _g NOTE 3 l HIGH PRESSURE (DCLER CCP-67) I 2-1B ANNULUS _ _ INSIDE , M AL M BulLDING CCNTAINWENT STRUCTURE
%58) CIL CDCLERS , ,
i i (P-44I
~-
--I F. C. ' l f( p.43}
p Wj J - , CCP-45) 4" jq [C)) 2 SC3 SC? SC3 HYOROGEN CCP-83) CCP84] RECCWBINER k CIB h' g* COOLER . gp,g (CP-92 OEU
- LETDLE O.
f i r
! Tl- .
COOLER g[vY A __ 03
.0, j , ,
4- A
' ' / ' NOT E 1 ' -
p.5 > ' '1 ' 1 < " kP 75) gj l l q s bA M ', - I L .c.
<CC781 4)HMSI!RKd tgsy 1
m 9 i i , A
' LI
/ RHR i CCP 2) I rE s Ch HIGH PRESS'fE 70/FRCW s
C(hTAlWENT k C0CLER ATMCSPHERE
$l .CCP 63 ,
RECI RCUL Ail 0h . t
' Olt COOLERS I
' ' '6 1 r '
gTRot !CCP4}h, 0 ,p, (CCP4B b, -
"""*A I I NC DFIVE CCP-49 (CCP 50j l /o,
~-
! CDCLER -
NOTE 3 [CCP c. " A (CCP-86l o > x -x (CCPy 1 dyl p FUEL y [CCP-93) c P 29 b b , p l ' '
' 1 i r ,_
~} g [CCP-61j , (CCP 62 l
N A2 7,- ICCP77) (CCP7 ff* yl-one SC2 m y U T h SEAL RETURN T i f"_ ^ l,, I
~
COOLER NDTE 3 ClE 10/FiCM FIG 9 2 2 tA FIG.9.2.1.lC l REACTOR OLANT C04PONENT CCOLING HATER PER REffRENCE PLANT SAFETY ANALYSIS REPORT SNESSAR PI BLE 6 - ART AMENDMENT 19 12/12/75
I REACTOR PLANT CLMPONENT COOLING WATER SURGE ALL _ , _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _
!ANK MC8 l , TO FF I
I FIG.t
, i h hi D v(
g \ 1 r ka WCB T _ _ W3 g- N m3 MCa l es I-1 F.C. fl
;F.C.
FRrW LG LS -- I 3 M, CEulNERALIZED REACTOR PLANT O~ O' ~ e ATER W APEUP j CCMPCNENT 3 i CIA fic.9 2 3 1 pgt pi COOLING WATER _ HEAT EXCHANGEPS uCs i 3 i . u__ f YM *b vy 6 u) YN~ ,
,+ @
v _, , w . = q~ g. h i '
, I l .
. - ,l
[di[' REACTCR PLANT CCWPONENT l SC 3 COOLING WATER PUMPS g;.3 9 ' I M:8, WC8
' -h
~
l REACTOR TAL } ,G I g3 NNS PLANT utg SERVICE WATER [ f FIG.9.2.1-1 i
- e. ,
o I ( CHEWICAL 8 pg AC0 TICN
, F.C. n W HE AT EXCH AM N3TE 3
,O 4
i j r TRAIN A
@r 3
lCCP-2) NOTES-
- 1. THIS SYSTEM 15 SAFETY CLASS 3 (SC3) EXCEPT WHERE OTHERWISL NOTED.
- 2. ALL SC2 AND SC3 PORil0NS OF THIS SYSTEM ARE SEISulC CATEGORY 1.
- 3. EQUIPMENT SUPPLIED BY NSSS VENDOR.
- 4. CONNECTION WILL BE AB0VE NORM AL BATER LEVEL IN TANK. ,
I . .O _/ i i
r--- GASECUS WASTE SYSTEM BORON RECOVERY SYSTEW CEGASIFIER BORON OlSTILLATE CONDENSER COOLER
)
O x9 O enl x x TRIM COOLER ' BORON EVAPORATOR i
. 6 jyx CONDENSER a 6 i
, , -C#- b 3
@: SF CCMPRESSOR "
il B000N SAMPLE AFTERCOLLERS ' ' COOLER S,a fa d i r r, LAUNDRY REFRIGERANT v f A CRATOR "I A V CONDENSER
$& & $ (W) v O 2*h J2 A ri ri COMPRESSORS , ,
k i r i r 1 s. F' s
, , 70/FROM REACTOR PLANT gne pe f es,y n g 'f 1 SAMPLING SYSTEM FIG 9.3.2-1 3, T'
r-
,[,,,u ',,t,
- 2. ),,,
LERS
, r FIG 9.2.2-1B REACTOR PLANT COMPONENT COOLING nATER PER REFERENCE PLANT ;
~-
SAFETT ANALYSl5 REPORT c SIESSAR-PI PSV ABENOMENT 13 12/12n 5
1 RADIDACTIVE LICul0 WASTE SYSTEM REGENERANT WASTE No EVAPORATOR EVAPORATOR CONDENSER CONDENSER TO REACTOR PLANT SAMPLING SYSTEM FI'. 9.3.2-1
,a n
SAMPLE f^ h REGENERANT 70 BASTE I
' ' DISTILLATE COOLERS (TYP) OlSitLLATE COOLER COOLER u _
F ew v9 % 7' k V RE GENER 8,NT WASTE SAMPLE COOLER SAMPLE COOLER FPCM REAL, TOR PLANT
,, h b SAMPLING SYSTEM F J_9 3 7-1 ]
$ h,o ,,
'+4 PENETRATION
~
TP M CB D 'o I : L_ B I _._E 1 NCB -_ ~ C8
'o I RE --
PENETRATION C n~ (TYP) Yl$ o f , T0/FR0s FIG 9 2.2-1 A T0/FRCH FIG 9.2.2-1C NOTES: s
- 1. THl3 PORTION OF THE SYSTEM 15 NON NUCLEAR SAFETY (NNS). "
4
\ J J e .
i
'b) RE ACTOR COOL ANT 2.2-IA 3 b (
N A Nk .NT 5
' ' j g dSi/ g ' r B D NG STRUCTURE H
' SE AL & OIL C00LERS CH ARGING CCP-72j (CCP-35 CCP-51) (CCP-52j l CCP-36 )
(CCP-54 [ [oC00ERo% k,hCP-53) L ET COIN CCOLEd n" V
,h_CP-87) (CCF-86 g
' r e g' 'r
+
SC1 M+SC2 O SC3 , $ %-95) (CCP-96 9 ]X-g(NOTE 3 CCP-31 A
'Qu A l
'l'~~ , ,
ILERS p p{ - i r l CCP-63) L _ (ccp.64
^
C00LER --. -{ }- B1 p" SE AL 'q- ' RETURN (CCP-8C X< M'" , n , , CC'-32 / " -d' r CCP-79) l ___] $ (CCP-33 [CCP-4 ll 9 [70 HIGh PRESSURE COOLER 3: , "
%R l TO'FRCM WROL kP-73) l '
} CONTAlhMEN7 RCC
*ll ( CCP-74 TE 3
] { ATW0 SPHERE RECIRCUL ATION ME [*
COOL ERS CDOLER SE AL & Olt C00LERS ,
' [o il ' '
'*I' FIG.9.2.8-1 NOTE 3 l l 1I O[CCP-55) l (CCP-55 l' HYCROGEN ' I ' l Oil RECC4B! NER 9CCP-57) (CCP-58 COOL ER ho h C CP -42 ' g g ' CCP-69 f (CCP-90 6 . [CCP-34) CCP-g7) (CCP-b8
- xe ,
x 4: r " CC,. ,) ii m 1l $CF-ss , Is .,- 4 , ' c- M B2 b ' f CtB - (CCP-22 , S C 3 -*+ S C 2 +*- S c 3 M : ! $0 l CCP-81 ) FIG.9.2.2-lC REACTCR PLANT COMPCNENT C0 CLING nATER PRR REFERENCE PL ANT
, /
SAFETV AN ALYSIS REPORT '
' i 't SWESSAR - PI h
Asi A AMENOMENT 19 12/12/75
l' REACTOR PLANT COMPONENT COOLING TD>FRCW RATER SURGE T ANK FIG 9.L N B CB 3 , j g 7 _ _ _ _ __ _ _ _ ._ __ _ _ _ _ __ _ _._ _ _ _ hNS i i
& i TV r-iCIA F. C. i LAi
'b b 9 { EO " J
-)(- ; ~ ~ -
~ OLM
,MCB >M i ' SC j] j f C.
FRCu ULWl*'_ l / (g
' g _ J _ _. $ _CB
\
RE AFTOR FL ANT CB
' - ~ ~ " M CB A6 P1 ESTER N - _ _ -
COWi ONtNT COOLING FT NMEUP CB .E RATER 1E AT FIG 9 2 3-1 i GCH ANGE PS t_ Mfr- & -tk; .. f* [ r l
'r y FE RHR HEAT E X CH ANGE R y PuuF C P 9l b b
[ , A d3 i ' ' 4x Qth * - , l I Q)hT. CCP-15) s [ e RE ACTOR PL ANT TRAY COMPONENT COOLING SC-3 1 4 _,
+33 I SC ;, r RATER PUWPS r
? ' Oi so
"#" "Cu'
}s W n {,s ,
'c: 6 @DiARG
.S i
~NS
""'F"@
SERVICE MCB NOTE 3 t E 9.2.1-1 c- CCP-16) h ADDITION CIA CCP-10) TANK d i TRAIN 9 eg & h E CIA NOTES 1 THIS SYSTEN !! SAFETY CL ASS 3 (SC3) EXCEPT WHERE OTHERil!E NOTED.
- 7. ALL SC2 AND SC3 PORTIONS OF THIS SYSTEM APE SEISult CATERGORY I.
- 3. EQUIPMENT SUPPLIED BY NSSS VENDOR.
- 4. CCNNECTION WILL BE ABOVE NORM AL IATER LEVEL IN T ANK.
I
_} SWESSAR-Pi Fig. 9.2.2-1D is deleted. 19 i ,j B&W 1 of 1 Amendment 19 12/12/75
1 ANNULUS -
' ' _ INSIDE BUILDING CONTAINEENT '
l STRUCTURE u REACTOR COOLANT PusPS - m x 8 I l LETDOWN HEAT l ' i t
}
p (EICHANGER,
/0 ) H.P.
LHSI l [ ' C00LER 3 r O
\ d l NA 3ENi ER (p
OS M RE FUEL POOL 1 r COOL:R lRECIRCULAT10k @; l COOLERS / EJ h l' ' ' P SE Al COOLERS
-- '_.___.'________ h FIG.9.2.2-1A
- L t-;r---_. - - - -
. . _ . . ' FEACTOR ~ ~ COOLANT FUMPS
+ BORCN RECOVERY SYSTEM N_L :
x i r d ' i n o o n CISTILL ATE I 7 COOLER I M - l
)
7f
*~
EVAPORATOR
~
l/ l CC% CENSER I
'__ l g\ i LJ LJ U U u o0RCN MOTOR AIR AND MOTOR AIR AND 50 TOR AIR AND NOTOR AIR AND l
'T- ' AMPLE Dil COOLERS DIL COOLERS Oll COOLERS DIL COOLERS i i .;00L E R l
i l L_'l CORESSORS '
' O
= F f G'9~2 2't8
----------T I I REACTOR CCOL ANT PUNPS
_U___ h 1r 4 r-- ,
.f . '
i , i 3 ,
,. o l
'g
'l T0eTR04 H.P.
1r
/k g00LER PCCL l CONT A INW'r:i ER 1 -v ATuGSPHEHL RHR l RECIRCULATION HX q HYCROCEN COOLERS SEAL 1 SEAL ,'
RECTMSINER l F IG .9.2.8.g H COOLERS 3 C06LERS
,CDDLER ; 3, , , Pt2P l '~~flG.S.2.2-1 l } ,, , REACTOR PLANT C04PONENT COOLING HATER PIR REFERENCE PLANT l
Mfs SAfiTY ANALYSIS REPORT ; l SIE SS M-PI C*-
, n00.9
(,ty 1 E\....,.v AMENOMENT 22 3/17<76 [I f, ,I)
" ' }']l
l d O REACTOR PLANT COMPON EN T FROM
) SURGECOOLING tau WATER ,
DEulNER-AllZED WATER
+ 2 S S Eu fp FIG.9.2.3-1 HH:
[' REACTOR PL ANT 4q- r COMPONENT -Y l ' COOLING WATER J b PUYPS + TRAIN A O We ., CHEulCil A00lil0N RE ACTOR PL ANT COMPONENT PUNP COOLERS f v TANK COOLING WATER HJ AT EXCHGS _
-----__----_--_g---' ~
i LIO410 EASTE SYSTEW
; IASTE i t i 1r REGENERANT EVAPORATOR 1 '
8 i l EVAPCRATOR l
; R E PLANT T A TE
,ilG.9.2.21 A: NTIM SMPLING SYSTEM
'j DISTlLLATE DISTILLATE FIG 9 2.2 TB. 2 pER FIG.9.3.2-1 y : COOLER y COOL E R h ANT 1
'fASTE 3N E
-Un ER TYP p ' r d C00LER f0 R
/ r PEnfiRailCN CODLER(IIF)
+ -
'l 1j "LAUNDRV EASIE EvAF. CONDENSER GASEOUS EASIE SY51tM TD /TH c REACTDR ar DEGASIFIER TRlu REFRI ERANT se - 1' ' ' CC0LER PLANT C00ENSER ,__ DRYERS 2h 9 ,
E + s l l F5.9.2.2 B - FIG.9 2 2-lC l b) h) -+, ] '
, -fg r g
FRCu k I L -
+
7 CCuPRE SSOR AFTERCOOLERS q
/
I REACTOR PLANT COMPONENT OEMINER-AllifU 3, COOLING WATER SURGE TANK r $ d ' I I l i r W A TETt i
~
is ; FIG.9.2.3-1 l CONT. 3, SPRAf 1' 1 i HHSl LHSI
,s %')\ _
y? J * ' LREACTOR PLANT I CCMPONENT COOLING RATER PutPS TRAIN B R O R P'W 3 COMPCNENT COOLING
' CHEulCAL WATER HEAT EXCHANGEAS PUWP l ' '
O 8001 TION TANK COOLERS
,,, ~*3 gbb I )4d
E ANNULUS _g INSIDE Bif l LD I NG _ CCNTAINWENT STRUCTURE I
,/- -
g RE ACTOR COOL ANT PUNPS 1 A & 28 \ CIB han 3 l l hg CCP-73,) ', SC3 pC2 b4SC3 l.
, 4 l N k
- \
' ' CCP-3 ) NOTE 3 SEAL
\
85 C00LERS' i r RHR % P - (CCP-27j COOLER
' I CCP-4 ) H>
l FUEL POOL 7"g ecp_; COOLER COOLER 1 r i r p
" : CCP7D ugt EC381st ATESPHERE RECIRCJLATim Q AO j i #" I y COOLERS CrP-2)
FIG 9 2.5-1 LETDOWN g] ' y L 3i NOTE 3 '
- 1 i r , , RCP-28) f , 7 i r I i '
f 23
)b @ .C. COOLER i
SEAL COOLERS CCP-8D Sc3$ SCb + SC3 l u Cd (N 1 p'pn ftq 6
; v v. . L . 6 w.
"'in r"'
FIG g.2.2-!A REACTOR Pt. ANT C0F0ENT C0Q.ING DATER PWR RIFEREEI' PLAlti ,. . , ,
'3 SUETT FJBALT!!! REPCRT [, (, O ; ;/
SVESSAR-P1 g AEElWBENT 22 3fg7fyg
A REACTOR PLANT CCMPONENT CCOLING WATER SURGE TANK pgn 8 liCB Mc.l: 1 l i
' h Qtgl . CB
] I
~
i r1 TV T '-~ AD IIID l ! TT 20 - FRfW
/ r---
J pi' /Th l k . FT
' [. C .
DEWINERALIZED IATER NA5EUP _ _ _ _ _ _ _ _ "Q N. .-
'uCB NCB IIG I 2 3'I ,
L PT [ gp y'K TTE 5 A 1 MN- [' gp FE M PUNP CCO [Il' N)N B 4'! i I d I i SC3 ir _ {o REACTOR PLANT COMPONENT SC3
] [o_1' hf REACTOR PLANT PDC Vo
^
33 i 2 6 COOLING W ATER PUMPS SERVICE WATER [ NN; NNS t F I G 9. 2.1-1 i r
' l CCP .
REACTOR PLANT COMP 0NINT l - I i COOLING IATER HEAT EXCHANGERS I& CONT. g 3 ; l 3pp3y I CHEMICAL ADDITION 'W-f TA."K F 3 L 6
. v i
TRAIN A (NOTE 4) 1 I l l.O,- - wh sg gg3 CIA
+ 1- +
NPS 8 WS L _ _ _. t _ _ _ _________________________2__ ___ __) T0/FR05 FIG 9.2.2-lfi NOTES: 1. THIS PORTl0N OF THE SYSTER IS SAFETT CLASS 3 (5C3) EICEPT IHERE OTHEREISC NOTEC
- 2. ALL SC2 AND SC3 PORTICNS OF THl3 SYSTEM ARE SEISMIC CATEG0DY 1.
- 3. EQUIPRENT SUPPLIE0 BT NSSS VENDOR.
- 4. EutRSENCY POIER TO THl3 TRAIN IS SUPPLIED FR95 THE ORAh;E ZEERGENCY BUS.
- 5. C(hMECTION flLL BE ABOVE NORIAL BATER LEVEL in TANK.
/ ,
() t / (8 ) L
ANNULUS INSICE Bu l L 0 l N G -->t-- CONTAINEENT STRUCTURE WASTE EVAPORATOR CONDENSER ,'y pyt l
#EACTOR-COOLANT PusPS NOTE 3
) - X (CCP-41
- (CCP-43l l m + -
i r i 4'9- " RASTE ' CISTILLATE COOLER " ' I , o, Q g I t IB - Q , ,. CCP-4:
shii"" u -
40-(CCP-44 NOTOR AIR i i i r AND Dil COOLERS N BOTOR AIR
, IA l AND Cll C00LERS SYSTIE E
NNS -Dy4- 2 l LS r i ~~ t g CCP-SI) TOR m ER I cp_$ $j _ C ~ (($* - 2A lCCP-52 I l > N I
- 2B EDTOR AIR AND Dil LE FR Db C00 lek 3 V [CI A LIA I
'f h 1-BOTOR AIR AND Olt C00LEWS T \ A NNS : SC2 ; ; NNS i r l %I
$20
- m. . >
ris s.2.2-is
*^'
-O REALTOR PLANT COMPONENT
$' f4 COGLING nATER ffi r:R RErERENCE PtANT h SAFETT ANALYSIS REPORT SIESSAR-PI CI' CE 7 -e:
C e.d 7
.. i f[- ABENOMENT 22 3/17/76
T0/FR05 FIG 9.2.2-1A LIQ'JIO B ASTE SYSTEu REGENERANT EVAPORATOR
\ ORA NCB Vo
CONDENSER RE RS \
' ' (
CB l 1 ve 3 -.m 2 PENETRAT!DN
~
' l -
CCOLERS (IfP) TO FROM REACTOP PLANT [ l
/ f' l SAMPLING SYSTEN FIG 9 3 21 +]hEGENERANTD ^
OLER r - w s l ? b N' REGENERANT SAMPLE CDOLER m r TO REACTOR 8 ' PLANT SAMPLING h FIG.9.3 2-1 GASEOUS WASTE SYSTEM 9 d f l BORON RECOVERt I"* r g '- - 9 3 O AM AT , 2 { h, t{lDING s/s, , /s ;
" - 4 frhg C00 ER '
V EVAPORJ
, g CCNDEN:
f
$ [ ;
x 5 i h, i k 1 y I
$ COMPRESSCR V
,yP, , , y"
' AFTERCOOLERS y,_O PENETRAil0N 9h I i
,( ; I '
, [
COOLERS (TYP) V / \ g
'Q ! s REFRIGERANT f j e-h SA COI SAMPLE FROM ' .
> ORTERS C00LER REACTOR ---- I ,o, u
r ,a d L(TYP) PLANT SAEPLING FIG.9 3.2 1
- CLC 70/TROM FIG 9.2.2-lC i I
% 1 r COMPRESSORS b M
NOTES: 1.
'@'Q ,c, THIS PORil0N 0" THE SYSTEE IS NON-NUCLEAR SAFETT EXCEPT WHERE OTHERilSE NOTf D.
- 2. ALL SC2 PORT:0NS OF THIS STS1En ARE SElSulC CATEGORY I.
- 3. EQUIPhiNT IS SUPPLIED BT NSSS VENDOR.
/
- n, g
]
ANNULUS - _ INSIDE BUILDING CCNTAihuENT STRUCTURE I l REACICfl COOL ANT PURPS IB & 2A CIB h h0TE 3 CCP-7 0 SC3 ** SCT
- SC3 I
i ' ' l CCP-19 NOTE 3 . E )b i ' RHR PUuP 18 I COOLER 3FAL COOLERS @ FUEL PC0L M ICE-II $ pp (co-ia @hij '
= y o o l ' C00Lill i T0/FRCu
] S CCNTAlhMENT ATMOSPHERE
$@ C l Co-10) : bltcp_;g)
(CCP-14 -
. _g ,
o & o
$EAL 2A N)h C00ifR$
r l l HP COOLER
*-5C3
~
SC3 Ol SC2
- i '
% ,9 wJ
, L!B _
1
) OO *!'.
Q "* P ,n n E
>: j F I G . I . 2. 2-11,l VS1 lLA.!kiu;.s,t.
REACTUt PLANT CCHPOENT CIX1.ING BATER PTR REFERERCE PLANT
$1FITT AXALT313 REPORT ITES!AR.-P AMEWDif 31 3/UA8 '
}
REACTOR PLANT CC4PONENT COOLING WATER SURGE TANK CONT ON FROW FIG.9.2 2 1B d6
~
MM /k r---------------
--' CS 33
\ C CB p , CIA (G LS ' ' -- J
] CIA MCB WCB FT C N NERALIZEC PA 'h-p, e ,"
WATER MAKEUP V D ' F 'G.9 7 3 -1 MCE l l MCB NOTE 5 5
'. *X"l Y II PUNP C00 1 r yp Tl X tM- -M-S3 S f A g g
_u]h REACTOR PLANT COMPONENT ] p_q3 y- REACTOR PLANT n C00 LING W ATER PUMPS & KP-1 SER) W IAU R NN NNS FIG.9.2.1-1 ' ' D REACIOR PLANT COMPCNENT CONT. E3 NCT 3 COOLING WATER HEAT SPRAY EXCHANGERS CHEMICAL A00lil0N g , , k TANK ; g n F.C. a aa v TRAIN B (NOTE 4) NOTES:
- 1. THIS PORTION OF TK SYSTER IS SAFETT CLASS 3 (SC3) EXCEPT IHERE OTHERIISE NOTED.
- 2. ALL SC2 AND SC3 PORTIONS OF THl3 SYSTEM ARE SEISMIC CATEGORY 1.
- 3. EQUIPMENT SUPPLIED BY NSSS VENDOR.
- 4. ENERGENCY POWER TO THIS TRAIN iS SUPPLIED FROM THE PURPLE ENERGENCY BUS.
- 5. CONNECTION ElLL BE ABOVE NORMAL IATER LEVEL IN TANK.
, - n r
) L.
oo
l SYSTF.N INTERFACE POINTS - PEAC'IOR PL EA nWPOmrF COOI.IMi WATD SYSTm (CCP)
.ID NO. RESAR -3S RFSAR 41 H-SAR 205 CESSAR CCP-1 & 2 Inlet and outlet of RHR Inlet and outlet ot RHR Inlet and outlet of decay Inlet and outlet of heat exct' anger No. I at heat exchanger A at first heat r euuwal (DHR) (moler shutdown cooling heat first flanges (Fig. 5.5-4) flanges (Fig . 6. 3-1 Sh 1) No. 1 at first flanges exchanger th. 1 at first (Fig. 6. 3- 1) Flanges (Fig. 6.3-1A)
CCP-3 & 4 Inlet and outlet of RHR Inlet and out1st of RHR NA Inlet and outlet of ptunp No. I at iirst pump A coolers at 1irst shutdown cooling pump flanges (Fig. 5.5-4) flanges (Fig. n.3-1 Sh 1) No. 1 at first flanges (Fig. 6.3-1A) CCP-S & 6 Inlet and outlet of Inlet and outlet of low Inlet and outlet of low Inlet and outlet of low saf ety injec-tion pump head saf ety injection pressure injection /DHR head saf ety injection No. I at first flanges pump A coolers at first puup A coolers at first pump No. 1 at first (Fig. 6.3 -1 Sh 3) fl angPs (Fig. 6.3-1 Sh 1) flanges (Fig. 6.3-1) flanges (Fig. 6.3-1A) CCP-7 & 8 NA Inlet and outlet of high Inlet and outlet of high Inlet and outlet of high head safety injection pressure injection /inakeup head saf ety injection pump A axilers at first pump A coolers at first punrp No. I at 1irst flanges (Fig . 6.3-1 Sh 1) flanges (Fig. 6.3-1) flanges (Fig. 6.3-1A) il CCP-9 & 10 Inlet and outlet of RHR Inlet and outlet of RIIR Inlet and outlet of DHR Inlet and outlet of heat exchanger No. 2 at heat exchanger B at first cooler No. 2 at first shut down cooling heat first flanges (Fig. 5.5-4) flanges (Fig. 6.3-1 Sh 2) flanges (Fig. 6.3-1) exchanger No. 2 at first flanges (Fig. 6.3-1A) CCP-11 & 12 Inlet and outlet of RHR Inlet and outlet of FifR NA Inlet and outlet of pump No. 2 at first pump B coolers at first shutdown cooling puup flanges (Fig. 5.5-4) flanges (Fig . 6.3-1 Sh 2) tb . 2 at first flanges (Fig. 6. 3- 1 A) CCP-13 & 14 Inlet and outlet of Inlet and outlet of low Inlet and outlet of low Inlet and outlet of low saf ety injection pump head safet y injection pressure injection /DHR head safety injection No. 2 at first flanges pump B coolers at first pump B coolers at first pump No. 2 coolers at (Fig . 6.3-1 Sh 3) flanges (Fi g. 6.3-1 Sh 2) flanges (Fig. 6. 3 -1) f i rs t flanges (Fig. 6.3-1A) CCP-15 & 16 NA Inlet and outlet of high Inlet and outlet of high Inlet and outlet of high a head safety injection pressure in jection/nukeup head safety injection pum No. 2 coolers at o puw B coolers at first pump B coolers at first flanges (Fig. 6.3-1 Sh 2) flanges (Fig. 6.3-1) first flanges (fig. 6. 3- 1 A) CCP-17 5 18 NA Inlet and outlet of kHR NA NA FIG 9 2.2-lF(SH 1) beat exchanger C at first flanges (Fig. 6.3-1 Sh 3) REACTOR PLANT COM PONENT
, COOLING WATER SYSTEM f '
CCP-19 & 20 NA Inlet and outlet of RHR NA NA PWR REFERENCE PL ANT gj ptanp C cnolers at first SAFETY ANALYSIS REFuRT flanges (Fi g . 6.3-1 Sh 3) S*E SSAR - P1 AMENDMENT 69 12 /12 / F 5
SYSTIN INWRFACE POIh"PS - REACTOR PLAFP QMPONFNT COOLita; %=ATER SYSTEM (CCP) ID NO. RESAR-3S PESAR 41 B-SAR 205 CFSSAR CCP-21 & 22 NA Inlet and outlet of low NA NA head safety injection pusp C molers at iirst ilanges (Fig . 6.3-1 Sh 3) CCP-23 $ 24 NA Inlet and outlet of high NA NA head safety injection punp C coolers at iirst flanges (Fig . 6.3-1 Sh 3) CCP-25 5 26 Inlet and outlet of Inlet and outlet of NA NA excess letdown heat excess letdown heat exchanger at first exchanger at iirst flanges (Fig. 9.3-1 Sh 1) flanges (Fig. 9.3-1 Sh 1) CCP-27 & 28 Inlet and outlet of Inlet and outlet of Inlet and outlet of Inlet and outlet of letdown heat exclunger letdown heat exchanger letdown cooler No. 1 letdown heat exchanger at first flanges at first flanges at first flanges at first flanges (Fig. 9.3-1 Sh 2) (Fig. 9.3-1 Sh 2) (Fig. 5.1-2) (Fig. 9. 3.4 - 1) CCP-29 & 30 Inlet and outlet of seal Inlet and outlet seal Inlet and outlet of seal NA water heat exrhanger water heat exchanger return cooler No. 1 at first ilanges at first flanges at first ilanges (Fig. 9.3-1 Sh 2) (Fig . 9.3-1 Sh 1) (Fig. 5.1-2) CCP-31 & 32 NA NA Inlet and outlet of NA letdown cooler No. 2 at fiTst flanges (Fig. 5.1-2) CCP-33 & 34 NA NA Inlet and outlet of NA seal return moler No. 2 at first flanges (Fig. 5.1-2) CCP-35 & 36 Inlet and outlet of Inlet and outlet of Inlet and outlet of high NA centrifugal charging wntrifugal charging pressure injection /DIUt pump A at first flanges pune A coolers pump C cooler at first (Fig. 9.3-1 fh 2) at first flanges flanges (Fig. 6.3-1) (Fig. 9.3-1 Sh 3) CCP-37 5 38 Inlet and outlet of Inlet and outlet of NA
, centrifugal charging centrifugal charging ' FIG. 9 2 2 -lF (SH.2) - N punp B at first flanges pump B coolers REACTOR PL ANT COMPONENT Cs (Fig. 9. 3- 1 Sh 2) at first flanges COOLING WATER SYSTEM is (Fig . 9.3-1 Sh 3) PWR REFERENCE PL ANT SAFETY A N ALYSIS REPORT S*E SS AR - P1 A ME NChE N T 19 Q/12/ TS L
ESTEMJ NTEFf AW pol tfrS - FEAL*FOR PLAR OM*} NT Ct m iLI NG WATEF SYSTEF (CCF) ID No. FESAP-1S RESAR 41 B-SAR 20 '> CFSSAP CCP-39 & 40 NA NA Inlet and outlet of NA cuntrol roi drive cooler A at first flanges (F ig . 9.2-2) CUP-41 & 12 Inlet and outlet of NA Inlet and outlet of NA centrifugal charging conirol rod drive pury C at first flanges cooler B at first ilanges (Fig. 9.2-2) CCP-43 & 44, h and f rom reactor To and f rurn re.4ctor % and from reactor h and trm reactor 45 & 46 molant purp 1 motor cuolant pump 1 notor coulant pump Al motor pump 1% motor air cooler s and air coolers at first air coolers at tarst air molers at first oil cuolers at f ir st flanges flanges flanges flanges (4 3 & 44 only) CCP-47 6 48, To and t rm reactor W and f rom reactor To and trm reactor To and f rom Jeactor 49 & 50 cuolant ptunp 2 w> tor coolant vnp 2 motor coolant paa) A2 mtor coolant psup 18 mot or air air coolers at ' r at air coolers at first air n>olers at first c.>olers and oil coolers at flanges flanges f lang e= s first f las.ge s (47 & 48 only) (Fig. 5.1-4) CO-51 & 52 % and a rm reactor To and t aum r eactor To and fr m reactor To and f rom reactor coolant 51 & 54 molant pump 3 motor coolant pump 3 untnr coolant pump B1 motor pump 2A air roolers and air coolers at first air coolers at first air coolers at first oil coolers at first flanger flanges flanges flanges (51 & 52 only) (Fig. 5.1-4) CCP-55 & 56 h and t rm reactor To and f rm reactor To and f rm reactor To and frm reactor 57 5 58 molant purnp 4 motor coolant pump 4 sotor coolant pinp B2 motr'r cuolant pune 2B motor mir Il air Coolers at first air coolers at first air coolers at tirl' Cuolers and oil molers at flanges flanges flanges first flanges (55 & $6 only) (Fig. 5.1-4) CCP-59 6 60 To and from reactor To and from reactor % and t rarn reactor NA cuolant pump 1 oil cuolant pnp 1 011 coolant ptmp A l cuolers at first molers at first oil coolers flanges flanges at first flanges CCP-61 5 62 % and from reactor To and f rom reactor To and t rtan reactor NA coolant ptmp 2 oil molant pump 2 oil ctnlant pimp A2 coolers at first molers at first oil cuolers flanges flanges at first flanges CCP-6 3 & 64 To and f rom reactor % and f rom reactor m and t r m react or NA coolant ptmp 3 oil (mlant pinp 3 oil coolant pump B1 .m coolers at tirst coo? 'r s at first oil coolers 7 flanges flar es at first f l anges CN FIG 9 2 2-IF(SH 3) & RE ACTOR PL ANT COMPONENT COOf ING WATER SYSTEM P'4 R RE FEREN CE PL ANT t J SAFETY AN ALYSIS REPORT pj S A E S SAR-Pl
-d Aut hDwE N T 21 J / 20/ 4
yY STPJ4 I N'W9 FAtX POlfCS - PF AC"POR _PIM COMPONt"?fr CW LING hATFS SYSTh# (CCP) ID NO. EESAF-35 FESAR 41 B-SAR 205 CESSAP CCP-t:5& 66 To and fr m reactor 1b and from reactor To and f rcan reactor NA coolant purp 4 oil coolant pump 4 oil coolant pump B2 cnolers at f irst coolers at first oil coolers flanges flanges at first flanges CCP-67 & 68 NA NA To and from reactor ta coolant pump A1 high pressure coolers at first flanges CCP-6 9 & 70 NA NA W and f rcan reactor ta tuolant pump A2 high pressure coolers at first flanges CCP-71 & 72 NA NA 'Ib and f rom reactor NA coolant pump B1 high pressure coolers at first flanges NA W and frtsu reactor NA ?! CCP-73 5 74 NA coolant purcp B2 high pressure coolers at first flanges CCP-75 6 7b To and from re.ctor 'Ib and from reactor To and f rom reactor 1b and f rcun reactor coulant coolant punp I thermal coolant pump I thermal coolant pump A1 seal pump 1A high presture Mrrier at f ir st barrier at first area cooler at first cooler and seal coolers flanges flanges flanges at first flanges (Fig . 5.1-4) CCP-77 6 78 'Ib and f rom reactor % and from reactor To and trcza reactor To and f rom reactor coolant coolant pump 2 thermal coolant pump 2 thermal coolant ptunp A2 seal pump 1B high pressure barrier at f ir st barrier at first area cooler at first cuoler and seal coolers flanges flanges flanges at first flanges (Fig . 5.1-4) CCP-79 & 60 To and from re.ctor % and from reactor To nd fr m re.ctor To and f rom reactor coolant coolant pump 3 therinal coolant tg 3 thermal coolant pump B1 seal pump 2A high pressure M rrier at f irs t M rrier at first area cooler at first cooler and seal ociolers flanges flances flanges at first flanges (Fig . 5.1-4) CCP-81 & 82 To and from reactor ib and f rum reactor To and frrun reactor To and f rcrm redor coolant coolant pump 4 thermal coolant pturp 4 thermal coolant pump B2 seal punp 23 high preasure Mrrier at f irst Mrrier at first area cooler at first cooler and seal cx>olers flanges flanges flanges at first flanges (Fig. 5.1 -4 ) (N O ', FIG 9 2 2-IF(SH 4) REACTOR PL ANT COk8PONENT COOL!NG W AT E R SYSTEM PWR REFERENCE PL ANT l S AFETY AN A LY SIS REPOR T f T S*ESSAR-PI L-AMENDMENT 22 3/17/76
S_TSTFN INMPACE POINTS - RFAChR PLANT ODMPON'g? COOLING WATER SYSTD4 (CCP) ID NO. RESAR-3S RESAR 41 B-SAR 205 CE S"AR CCP-83 & 84 h and f rm loron m and f rtun boron m and fr m reactor NA thermal regeneration thernal regeneration coolant pump A1 motor system ctiiller system chiller upper bearing oil cooler at first flanges at first flanges at first flanges (Fig. 9.3-1 f21 3) (Fig. 9,3-1 Sh 4) CCP-85 & 8 6 NA h and from boron h and fr m reactor NA injection ptump No. I coolant pump A2 motor at first flanges upper bearing oil cooler (Fig . 6.5-1) at first flanges CCP-87 G 88 NA h and from boron h and fr m reactor NA injection pump No. 2 coolant pump B1 motor at first flangea upper bearing oil cooler (Fig . 6.5-1) at first flanges 19 CCP-89 & 90 NA NA h and f rm reactor NA coolant pump B2 motor upper bearing oil cooler at first flanges CCP-91 & 92 NA NA h and f rcun reactor NA coolant pump Al motor lower bearing oil cx>oler at first flanges CCP-93 6 94 NA NA h and f rom reactor NA coolant pump A2 motor lower bearing oil cooler at first flanges CCP-95 & 96 NA NA To and f rm reactor NA coolant pump B1 motor lower bearing oil cooler at first flanges CCP-97 & 98 NA NA h and f rm reactor NA ecolant pump B2 motor lower bearing oil cooler C~x at first flangen FIG.9.2. 2 -IF(SH 5)
' ' RE ACTOR PL A NT COMPONENT C' COO LIN G WATE R SYSTEM PWR REFERENCE PL ANT SAF E TY AN A LYSIS RE PO RT L SWESSAR-Fi I
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- FIG.11.5-lE I lCOOLINGWATER l SOLIO stSTE l G 10 4 9-1 B NG '
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TO AUIILIARY STEAM AND CONDENSATE DERINERAll2E0 IATER HEATER p CONTROL VALVE FIG.10.4.12-1 c' I
, bib I IU DEMINERAlllE0 AUX WATER STORAGE I. ANO TANK
, ( G
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- 1. THIS SYSTEu IS NON-NUCLEAR SAFETY CLASS (NNS),
EXCEPT IHERE NOTE 0. fff ~' 1 OUV sJl
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\
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;TO REACTOR PUMP FIG 11.2-IF Pl. ANT !A."PLE SYSTEF FIG 9.3.2-1 TO HIGH AND LOW LEVEL WASTE DRAIN ,
TANKS FIG 11.2-1 PRIMARY GRADE WATER SYSTE4 PWg REFERENCE PL ANT SAFETY ANALYSIS REPORT SWFSSAR-P1 , , ,, JuJ Jaw AMENDMENT 12 6/16'75
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- I CECONTAMINAT!CN i FIG 9.3.6-1 8 BUILCING 8 l
TO BORON DEMINERAllZERS _ 1 F I G 9.3.6-1 > 1 , y y J 6 PS Y; lg )., ~f t g, ,7,
,P Ah FROM IASTE ,, ,, p Ce TEST TANK
,)p,,'MCB PtlMP , , /\ /g/ _ $ j FIG II.2-IC
_. _32 _ __ _ __C 82 r, FR0W c 4' cy DEulNERALIZER, : ,9 - y l WATER MAKEUP SYSTEM
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I FIG 9.2.3-1 l ; .# - i F9tWARf GRACE EATER i t TRANSFER PUvPS b '/ M s BCRON EVAPORATOR FEE 0 PL'MPS FIG 9 3.6-1 TO RA010 ACTIVE SOLID WASTE SYSTEM FIG ll.5-lE TO WASTE SLUDGE : TANK FIG 11.5-1C in SPENT RESIN ' SURGE TANK l FIG 11.5-1C l' TO SPENT RESIN , HOLD TANK FI3 11.5-1C l NOTES:
- 1. THIS SYSTEM IN NON-NUCLEAR SAFETY CLASS (NNS) EXCCPT WHEr1E L'HERWISE NOTED. l l
,o u,; b JaJ
SYSTFM INTEP FACE - PRIMARY GRAPE O TER SYSTE*4 (PG3) ID NO. FESTP-lS FRSAP 41 B-SAP 241 CFESAP PGS-1 To chemical mixing tank and To chemical mixing tank and Supplied upstream of To voltrne control tank charging pump suction to boric acid blend control purification ominer- to valve CH195 valve 1-8455 (Fig. 9.3-1 valve to valve 1-9338 alizers to valve MV118 (Fig. 9.3.4-2) Sh 3) (Fig. 9. 3-1 Sh 3) (Fig. 9. 3-1) PGS-2 To loric unid batching To toric acid batchiry tank t ank t o va lve 8494 To Loric acid addition To boric acid batch-to valve 8430 (Fig. 9.3-1 tank to valve Pf/233 ing tank ta valve (F ig . 9.3-1 Sh 5) Ph 5) (Fig. 9.3-4) C11119 PGS-3 To boron in jection makeup 7b suction of boron injec-pump discharges to valve To concentrated boric NA tion makeup ptrnp to valve acid storage tanks to 8255 (Fig. 9.3-1 Eh 5) M 39 (Fig. 9. 3-1 Sh 5) valve t'/20 9 (Fig. 9.3-4) PGS-4 To pressurizer reliet tank N To tiressurizer relief tank To boric acid feed NA an1 reactor coolant pump and reactor coolant pnp line upstrean of seal standpipes to seal standpipes to PCS- valve V20 (Fig. 9.3- 1) j RCS-MOD-1 (o M AR-P1 MOD-1 (EVESSAR-P1 Fig. 5.1-1 Sh 1) Fig. 5.1-1 Sh 1) 3 N O Fl3 9 2. 7 - 1B PRIMARY GRADE WATER SYSTEM k P AR REFERENCE PL ANT i SAFETY ANALYSIS REFORT S A E S S AR-PI awe NDME NT 30 s/28/7
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- 2. TYPICAL OF 4 COOLFRS FOR ELI AND CE. GED ITPICAL OF 3 COOLL G FOR WESTINGHOUSE.
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- 1. TH S SfSTEM 15 NON-NUCLEAR SAFETY CL ASS (NNS).
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- 1. THIS SYSTEM IS NON-NUCLE AR SAFETY EXCEPT WHERE INDICATED.
- 2. INTERF ACE PalNTS. ROS-1 AND R05-2. INTERF ACE WITH BLW'S CONTROL RCD ORIVE MECHANISM SERVICE STRUCTL'RE.
- 3. PIPING ENTERS SURGE TANK ABOVE NORMAL IATER LEVEL.
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SWESSAR-P1 9.3 PROCESS AUXILIARIES 9.3.1 Compressed Air Systems The compressed air systems include the instrument and service air system, shown in Fig. 9.3.1-1, and the containment instrument air system, shown in Fig. 9.3.1-2. The instrument and service air system, located in the turbine building, supplies compressed air to the plant; the containment instrument air system, located in the containment, supplies only instruments inside the containment. 12 9.3.1.1 Design Bases The compressed air systems are designed to meet the following requirements:
- 1. The compressed air systems shall meet normal instrumentation and service air requirements.
- 2. The ccmpressed air systems s'lall be nonnuclear safety (Ims) , except f or the containment isolation valves and the connecting piping which shall be Safety Class 2 (SC-
- 2) .
- 3. Upon loss of instrument air, all air operated valves y shall fail in the safe mode.
- 4. Redundant instrument air compressors shall be provided.
- 5. The containment instrument air system shall be located entirely within the containment structure to preclude any pressurization of the containment structure.
- 6. The compressed air systems shall supply clean dry air for plant instrumentation and controls which r2ets or exceeds the requirements specified by the NSSS Vendor .
9.3.1.2 System Design Instrument and Service Air System The instrument and service air system consists of three 50 percent capacity nonlubricated instrument air compressors. Each compressor is f u rnished with an intake filter, silencer, water cooled af tercooler, and an air receiver. These compressors discharge into a comnon discharge header. The service air header and instrument air header branch off this discharge header. The instrument air header has one 100 percent capacity dual tower desiccant air dryer and two 100 percent capacity pre- and post-air filters. 9.3-1 Nien dment 12 6/16/75
/t/ u, Ueo ; .
SWESSAR-P1 Normally, two air compressors provide instrument and service air, operating on a load / unload mode, and one on automatic standby. The standby air compressor starts on low discharge header pressure. Also, the pressure control valve in the service air discharge header isolates service air on low pressure to allow more air for plant operation and an alarm sounds in the control room. To maintain uniform " ear and verify proper component operability, the operating modt of the three air compressors are alternated through administrative control. The largest demand for service air is anticipated to be during planned refueling shutdowns. Since the instrurent and service air system is located in the turbine building, which contains no safety related equipment , this location precludes the possibility that missile generation f rom a rupture type f ailure of any of these components will cause damage to any safety related equipment. Relief valves are provided on the instrument and service air receivers and on lines downstream from the instrument and service air aftercoolers :a prevent overpressurization of the air receivers and aftercooAers. The instrument air line penetrating the containment contains one air operated isolation valve oucside the containment structure and a check valve inside. This instrument air line serves as a u backup to the containment instrument air system and supplies air to the containment for the containment leakage monitoringsystem (Section 6.2.6) . The service air line penetrating the containment contains one locked closed isolation valve outside the containment and one check valve inside. This line provides service air for use inside the containment structure when the plant is shut down. Containment Instrument Air System The containment in strument air system is a separate air system provided for instrumentation , controls , and valves inside the containment. This system takes air from and discharges air to the containment, thus creating no pressure increase inside the containment. Two 100 percent capacity nonlubricated air compressors, water cooled air coolers, air receivers, air filters, and one 100 percent capacity dual tower desiccant dryer are provided to ensure a reliable system. The containment instrument air system is also backed up by the instrument and service air system. Normally, one compressor operates on a load / unload mode and one on automatic standby. The instrument air compressor on the automatic mode starts if the instrument air pressure falls below
,, > i 9.3-2 Amendment 12 6/16/75
SWESSAR-P1 a preset value. The instrument air compressor operating modes are reversed periodically to maintain uniform wear and verity proper component operability. The containment air system equipment is located in an area or the containment isolated from any safety related equipment as shown in Fig. 1.2-3 Sh 2. This location precludes the possibility that missile generation f rom a rupture type f ailure of this equipme nt would cause damage to any safety related components. 9.3.1.3 Design Evaluation The following provisions maintain an adequate instrument air supply and enhance system reliability:
- 1. Three 50 percent capacity air compressors are supplied for the instrument and service air system.
- 2. If the dis charge header pressure in the instrument and service air system falls below a preset value, a pressure control valve isolates the service air header from the discharge header.
- 3. Two 100 percent capacity air compressors are supplied for the containment instrument air system.
- 4. In the event of loss of the containment instrument air system, in strument air can be supplied from the instrument air system through an administratively controlled valve.
- 5. Air compressor intake filters remove all particles 3 microns or larger and 98 percent (by weight) of all particles 1.5 microns or larger. To ensure cleanliness, the air is filtered again before and af ter leaving the desiccant dryers. The use of nonlubricated compressars prevents introduction of oil to the air.
With the exception of the air control J ines for the condensa te otorage tank and demineralized water storage tank, all air lines are located in heated buildings which precludes freezing. If no instrument air is available, all air-operated valves fail in the safe position . There are no safety related components or equipment necessary for safe shutdown that utilize compressed air. Loss of ins trument air is discussed in Section 15.1.34.
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t ,( ,' 1 O loj s .J 9.3-3 Amendment 12 6/16/75
SWESSAR-P1 9.3.1.4 Testing and Inspection Requirements During operation, periodic simulated low air pressule tests are performed on the instrument and servi ce air system to ensure proper starting of the standby compressor when required. Testing of the instrument and service air system is not required because it is normally in operation except for the containment isolation val.ves which require testing as specified in Sections 16.4.2 ar.d 16.4.4. 9.3.1.5 Instrumentation Application Each instrument and service air compressor is equipped with pressure switches, unloaders , and a start-stop auto selector switch . Two compressors are manually started and run continuously, loading and unloading as required. The third compressor is on standby in the automatic position and starts automatically on low discharge header pres sure . Low discharge header pressure is alarmed in the control room and the service air header is automatically isolated. Containment instrument air system low pressure is alarmed in the control roCxn . High dirrerential pressure across the air filters is also alarmed in the control room. One air rlow totalizer is supplied in the instrument air line to the containment structure for local monitoring of the air for the containment leakage monitoring system. 9.3.1.6 Interf ace Requirements The instrument and service air and containment instrument air systems supply air as requ2 red to all NSSS Vendor supplied pneumatically operated instruments, controls , and operators throughout the plant. The air supply design criteria are 90 1 10 psig, oil tree, no particles greater than 3 microns, and d dew point ot -40 F. Thes.+ design criteria meet all applicable air system interrace requirements given in SWESSAR-P1 Tables 6.3-3, 9.3.1-3, and 9.3.4-1. NSSS Vender requirements for d sdiety reldted air system are not applicable
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7,( UUU . 9.3-4 Amendmt .t 30 1/28/77
SWESSAR-P1 9.3.2 Sampling Systems The sampling systems consist of the reactor plant s ampling system, shown in Fig. 9.3.2-1, and the turbine plant sump?ing system, shown in Fig. 9.3.2-2. Both sampling systems collect samples at tne sample sinks for chemical and radiochemical a na lysis . Other san pling is done by local sampling in the individual systems and the radioactivity monitoring system discussed in Section 12.2. Table 9.3. 2-1 lists the interface design characteristics of the sampling systems. 9.3.2.1 Design Ba s es The design bases for the sampling system are:
- 1. Sampling flows shall be collected to preclude any radioactivity release
- 2. The sampling lines from the reactor coolant pressure boundary, f rom the accumulators, from the low head safety injection system, and all penetrations through the containment including the innermost and outermost isolation valves shall be designed in accordance with ASME III, Class 2.
- 3. The sampling lines outside the containment shall be designed to ANSI B31.1 and classifi-d nonnuclear safety GRIS) with the exception of lines connected to Safety Class 2 or 3 systems as indiceced in Fig. 9.3.2-1.
- 4. Samples from systems with operating temperatures greater than 150 F shall have sample coolers which shall reduce sample temperatures to 150 F or less for safe handlino.
- 5. All sample coolers shall be designed in accordance with ASME VIII.
9.3.2.2 System Design Shi Gding is provided around the reactor plant sampling sink to protect laboratory personnel from radioactivity emitted tron the sample piping and sample coolers. The exhaust hool over the reactor plant sampling sink exhausts to the annulus building ventila tion system (Section 9.4.2) . Potentially radioactive samples f rom components in the reactor plant tank area and solid waste und decontamination building are collected at one local sink. The sample piping, sample sinks, and hooded enclosure are of stainless steel construction. i? 7 -"3 uea Jav 9.3-5 Amendment 9 4/30/75
SWESSAR-P1 A delay coil is used in the reactor coolant sampling lines to provide suf ficient holdup time to pennit the decay of short-lived isotope N16 to a safe level in the samples taken. Prior to collecting a sample, sampling lines are purged for a suf ficient period of time to ensure that a truly representative sample is obtained. Sample collection vessels are designed for the type of sample to be collected; sampling techniques are designed to ensure sate handling. Samples having a temperature greater than 150 F are reduced to 125 F or less by sample g coolers which utilize component cooling water or containment structure chilled water (Sections 9.2.2, 9.2.8, and 10.4.11) as the cooling medium. This cooling reduces sample temperatures to allow for sate handling. Local instrumentation at the sample sinks permits manual control of sampling operations and ensures that the samples are at suitable temperatures, pressures, and flow rates before diverting flow to the sample sinks. Atter sufficient purging, a sample is obtained by means of isolating the sample in the collection vessel. Demineralized water is available for rinsing the sample sink. Typical of the analyses performed on samples are boron concentra tion , fission product radioactivity level, hydrogen and oxygen gas content, pH, corrosion product concentration, and conductivity. Analytical results are used in regulating boron concentration, evaluating fuel eJement integrity, minimizing oxygen get content, and regulating additions of corrosion controllin 3 chemicals to the fluid systems. The sampling systems are designed to be operated manually, on an intermittent or continuous basis, during conditions ranging trom tull power operation to cold shutdown. The steam generator blowdown (W_ and C-E only) is continuously monitored for Na, pH, cation conductivity, and radiation; condensate and feedwater systems are continuously monitored for oxygen, pu, Na, cation and conduct ivity . Process radiation monitors (Section 11.4) continuously monitor the letdown sample. A neutron gross f ailed fuel detector (Westinghouse NSSS scope of design responsibility) continuously monitors the RCS loop sample (Section 9.3.5) . The flow paths which are sampled continuously v also be manually sampled . A constant temperature ba th is provided for semples being measured for conductivity in crder to minimize errors in conductivity measurement due to temperature dif terences. The ba th temperature is maintained by a closed loop subsystem containing a pump and a mechanical refrigeration unit. All sampling lines penetrating the containment structure have containment isolation valves in accordance with General Design Criteria 55 (Section 3.1.55) and 57 (Section 3.1.57) . These containment isolation valves are closed automatically on a containment isolation phase A (CIA) signal. In addition, each 9.3-6 ~ Amendment 29
.,su j 10/29/76
SWESSAR-P1 sampling line containment isolation valve io designed to be opened and closed by its own individual remote switch. A CIA signal overrides a manual signal to the containment isolation valve from the remote switch. All remotely operated valves in the reactor plant sampling system {12 can be operated frcxn a sample control panel in the samole room in the annulus building. 9.3.2.3 Safety Evaluation Except for the sampling line containment isolation valves, which close on a CIA signal as part of the containment isolation system, the sampling system is not required to f unction during an accident condition or to prevent an accident condition. All remotely operated valves fail in the safe position. 12 9.3. 2. 4 Testing and Inspection Requirements The sampling systems are used regularly during power operation, cooldown, and shutdown, thus ensuring the availability and performance of the sampling systems. Safety class valves in the system require testing as specified in Section 16.4.2 (for safety class valves) and Section 16.4.4 (for containment isolation valves) . 9.3.2.5 Instrumentation Applications Sampling instrumentation is located adjacent to the sample sinks. Local temperature indicators, at the outlet of the hiah temperature sample coolers , measure sample temperature prior to sample collection. Local pressure indicators, downstream from the hign pressure throttling valves, permit the adjustment of these valves. A radiation detector is provided on the steam c .3rator blowdown sample line pi and C-E only) for indicatio;. of primary-to-secondary leakage in the steam generator. Two radiation detectors are provided on the letdown s ar.p.'. e line for process radi, tion monitoring. l12 Relief valves are furnished, with discharge to the gaseous drain header or aerated drain header, to protect equipment from overpressure. Sampling line containment isolation valves are individually operable remote-manually from switches on the sample control panel. A CIA signal overrides a remote manual signal and closes the containment isolation valves.
,, -"a JUb JJ' 9.3-6A Amendmant 12 6/16/75
SWESSAR-P1 9.3.2.6 Interf ace Requirements The reactor plant sampling system is designed to sample all NSSS Vendor supplied systems at the frequency and flow rates required. The sample lines are 3/8 inch stainless steel and are designed f or the pressures and temperatures given in Table 9.3.2-2. The g Westinghouse gross failed fuel detector is interf aced to the sampling system in modif! cation Fig. 9.3.5-1. Fig. 9.3.2-1 gives the safety class at each interface. This design meets or exceeds all applicable interfaces as given in the following SWESSAR-P1 tables: Tables 5.1-1 5.5.7-1 9 6.3-3 9.3.4-1 9.3.3 Vent and Drain Systems The vent and drain systems consist of the aerated vent and drain system, s hown in Fig . 9.3.3-1, and the gaseous vent and drain system, shown in Fig. 9.3.3-2. The gaseous vents and drains core from components in radioactive systems which contain hydrogen. The aerated vent and drain system including building drains comes from systems which contain air and are potentially radioactive. All radioactively contaminated vants and drains are delivered to the radi_ active liquid and gaseous waste systems (Sections 11.2 and 11.3) before release. Other equipment and piping which are not radioactive are vented directly to the atmosphere and drained to the floor drainage system. 9.3.3.1 Desian Basis The design bases of the aerated vent and drain system are:
- 1. All vents and drains which are potentially radioactive and contain air shall be collected.
- 2. The system shall transfer all vents and drains to the radwaste s ystems for monitoring and treatment as recuired prior to release.
- 3. The system shall not be safety related and shall be designated nonnuclear safety RmS) except for the containment penetrations which a_e Safety Class 2.
The design bases of the gaseous vent and drain system are:
- 1. All vents and drains from radioactive systems that may contain hydrogen shall be coller:ted.
(!!v , os - 9.3-6B Amendment 9 4/30/75
SWESSAR-P1
- 3. The system shall not be safety related and shall be designated nonnuclear safety (NNS) except for the containment penet'ations which are Safety Class 2.
9.3.3.2 Lystem Description Aerated Vent and Drain System The aerated vent and drain system, shown in Fig. 9.3.3-1, is from equipment and building sumps, which are potentially radioa ctive and contain air as the predominant gas. This equipment, listed in Table 9.3.3-1, drains to the building sumps and vents to the aerated vents header. All aerated vents are vented to the aerated vent header . This vent header has a vent pot inside the annulus building for separating any entrained liquid. Liquid leaving the vent pots is directed to the building sumps; air leaving the vent pot is discharged to the ventilation vent via the radioactive gaseous waste system. The process vent blowers maintain a constant flow through the vent header. For example, the boron recovery tanks draw from the atmosphere for supply air and discharge to the aerated vents header for removal of released gases. Sumps are provided in the containment structure, in-core instrumentation tunnel, ann ulus building, engineered safety features area, solid waste and decontamination building, fuel building, and turbine building. Liquids from all these sumps (except for the turbine building) are transferred to the low or high level waste drain tanks in the radioactive liquid waste system. These liquids are treated for further decontamination prior to disposal as descrit 3 in Section 11.2. Liquid from the turbine building sump is normally discharged with no treatment to the radioactive liquid waste system discharge line. Turbine building sump untreated releases meet the sana req 0irements as in Section 11.2.2-1. Dilution factors are discussed in Section 11.2.9. Turbine building sump activities for the design case are 4 given in Table 11.2-14, for the maximum expected case in Table 11.2-28, and are discussed in Section 11.2.6. This discharge is automatically transferred to the radioactive liquid waste system upon a high radiation alarm (Section 11.4) . Two parallel sump pumps are provided for each sump. Each pump is of full capacity and independently controlled. One pump is in automatic service and the other in standby during normal operation . When the water level in the sump reaches a specified height, the first pump starts automatically. If the first pump is unable to empty the sump and the level rises to activate a high level alarm, the standby pump starts automatically. For the containment sump, an alarm is sounded in the control room when bJU s- ' 9.3-7 Amendment 4 11/1/74
SWESSAR-P1 the first pump is started, and a high-high level starts the standby pump and initiates a second alarm. In addition to the high level alarm, the ESF area sump level is monitored and indicated on the main control board. This monitors leakage from the ESF systems, the reactor plant component cooling water system, and the reactor plant service water system in this area. Since the ESF systems circulate reactor coolant af ter a DBA, the ESF area sump design meets the same criteria as that tor RCPU leakage detection whose criterion is to detect a 1 gpm leak in 1 hour. This leak detection capability provides the operator with information needed for isolation of these systems as required. Containment isolation valves provided in the discharge piping of the containment sump are interlocked with the pump controllers. The isolation valves open and close on pump start and stop signals. When initiated, the containment isolation signal overrides the pump signal to keep the isolation valves closed. Gaseous Vent and Drain System The gaseous vent and drain system, shown in Fig. 9.3.3-2, is from equipment which normally contains reactor coolant and thus hydrogen gas. These are listed by system in Tables 9.3.3-2 and 9.3.3-3. Inside the containment, gaseous drains are collected in tb reactor coolant drain tank (RCDT) . (The RCDT and associatt, instrumentation are within the NSSS Vendor's scope for Combustion 2 Engineering.) The reactor coolant system (RCS) , except the reactor vessel, can be drained to the RCDT. The RCDT accepts drains trom the accumulators, valve stem leakoffs, RCS loops, and the chemical and volume control system inside the containment. Makeup water for the RCDT is supplied from the primary grade water system (Section 9. 2.7) . Cooling of the water in the RCDT is accomplished by the RCDT coolers which transfer the heat to the reactor plant component cooling water system (Section 9.2.2) . Once these drains are cooled, the RCDT pumps transf er them to the radioactive gaseous waste system (Section 11.3) for degasification. Outside the containment , gaseous drains are collected in the primary drains transf er tank (PDTT). The PDTT accepts drains from the radioactive gaseous waste system, emergency core cooling system, reactor plant s ampling system, and the chemical and volume control system. The PDTT pumps transter these drains to the radioactive gaseous waste system. Gaseous vents inside the containment are vented to the gaseous vent header for treatment in the radioactive gaseous waste systen (Section 11.3). A vent pot in the header separates any entrained liquid which drains by gravity to the RCDT. When the pressure in ~ f i. (>: o a J 9.3-8 Amendment 29 10/29/76
SWESSAR-P1 above 2 psig, the operating
,the gaseous vent header rises gaseous vents are processed pressure of the degasifier , the through the radioactive gaseous waste system (Section 11.3).
The PDTT (W, C-E, BSW), RCDT (Westinghouse only) , and gaseous vent header are maintained above atmospheric pressure by a process gas supply through an interconnection with the radioactive gaseous waste system. 9 The RCDT (C-E 6 ESW) and the PRT Q[) , which are normally isolated f rom the gaseous vent header, are maintained above atmospheric pressure by a regulated nitrogen supply from the reactor plant gas supply system (Section 9.5.8) . Nitrogen is supplied to the gaseous vent header. ) 8
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(; v/. J' ; ;s 9.3-8A Amendment 9 4/30/75
SWESSAR-P1 9 An air operated motor valve, provided in the discharge piping f rom the ECDT pumps, is i::terlocked with the pump con trollers . The isolation valves open as the pump starts to transfer tre 9 drains to the radioactive gaseous waste system. 9.3.3.3 Safety Evaluation The vent and drain systems are sized to handle the maximum amounts of liquids and gases expected during operation. Vent headers allow simultaneous venting of multiple items of equipment assuming 1-1/2 times the venting rate from the largest itera of equipment. Drain headers are sized to allow simultaneous draining of multiple items of equipment, assuming 1-1/2 times the draining rate from the largest item of equipment. All liauids and radioactive ga ses are transferred through austenitic stainless steel piping ; nonradioa ctive gases use carbon steel piping. Sumps are sized to accept the simultaneous drainage of multiple items of equipment, and sump pumps are sized to preclude overflowing the sumps during the draining operations. In the case of equipmen t malfunction, the respective system instrumentation alerts the operator as to the source of the d rainage . All sumps have sump pumps arranged in pairs. Level switches O. operate the pumps on and off, and alternators cycle the pumps to obtain equal wear. Additional level switches sound an alarm on hiuh sump level and start the standby pump. Liquids from sumps in safety related areas discharge to the radioactive liquid waste system where they are held up for treatment prior to release or disposel. For this reason, site-related events, including the probable maximum hurricane and the probable maximum flood, are unable to adversely affect the safety related areas served by the vent and drain system. The PCDT and PDTT pump.s are arranged in pairs. 9.3.3.4 Testing and In_spoction Pequirements Periodic testing of the vent and drain systems is unnecessary because they are used in normal operation with the exception of the high-high level alarm which is tested to ensure operability. Inspection is performed in accordance with normal maintenance procedures. Safety class valves in the system require testing as specified in Section 16.4.2 (for safety class valves) and Section 16.4.4 (for containment isolation volves) .
- - ~"7 (n a aai 9.3-9 Amendment 9 4/30/75
SWESSAR-P1 9.3.3.5 Instrumentation Apolications g The RCDT is provided for the Westinghouse and BSW NSSS applications with the following instrumentation:
- a. A level transmitter
- b. A temperature indicator
- c. A high-low level alarm
- d. A level indicator
- e. A high pressure alarm
- 1. A pressure transmitter
- g. A pressure indicator
- h. A temperature transmitter
- i. A ternperature alarm (high)
The PDTT is provided with the following instrumentation:
- a. A level transmitter
- b. A level annunciator (higbflow level alarm) O
- c. A level indicator All the sumps, except the in-core instrumentation tunnel sump and the co"tainment sump, are provided with two level switches: one for aatomatic starting of a sump pump and the other ror high level alarm.
The in-core instrumentation tunnel sump and the containment sump are provided with high level and high-high level switches and alarms. On high level, one pump is started; on high-high level the second pump is actuated. Both alarms are sounded in the control room. Level switches cycle the sump pumps on and off, and alternators cycle the pumps to obtain equal wear.
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9.3-10 Amendment 29 10/29/76
i i SWESSAR-P1 9.3.4 Chemical, Volume Control, and Liquid Poison Systems A. System Interface Modifications The chemical and volume control system (CVCS) is described in RESAR-41. The . fluid system interfaces as set forth in Table 1.7-2 of RESAR-41 are satisfied by the SWESSAR-P1 design as indicated in Table 1.8-3. The following modifications to the CVCS interface are required:
- 1) 'Ih e Stone & Webster radioactive gaseous waste system design requires the addition of one three-way valve at CVCS--MOD 1 and one tee connection at CVCS-MOD 2 (Fig . 9.3.4-1 Sheet 1) to provide for continuous degasification of the letdown steam.
- 2) A sparger system is added to the volume control tank to adequately dissolve hydrogen in 'he reactor coolant.
Fig . 9. 3.4-1, Sheet 2, indicates the required changes to the systen to adequately dissolve hydrogen in the reactor coolant.
- 3) The Stone & Webster radioactive solid waste system design requires the addition of tee connections at CVCS-MODS 3 thru 10 (Fig. 9.3.4-1 Sheet 3) and CVCS-MODS 11 thru 20 (Fig. 9.3.4-1 Sheet 4) . This change makes the piping of the RESAR-41 demineralizers g identical with the piping of the demineralizers in SWESSAR-P1 (Section 11.5) and standardizes the filling, draining, and flushing operations.
B. System Description The SWESSAR-P1 design affects the RESAR-41 description by providing continuous degasification of the reactor coolant in the radioactive gaseous waste system for removal of fission product gases. The letdown coolant flows through one of the two reactor coolant filters and into the radioactive gaseous waste system (Fig. 11.3-1) for degasification to maintain low gaseous activity levels in the coolant. The letdown is then returned to the volume control tank to be re-hydrogenated. This is accomplished by meanc of the spray nozzle at the try of the volume control tank ( P nozzle = 15 psi) and a gas sparger below the liquid level. A portion of the letdown (approximately 10 gpm) is introduced tangentially, below the liquid level, causing a slow rotation of the liquid, to ensure that the gas bubbles are dispersed throughout the liquid. This sparger system provides adequate contact between the hydrogen and liquid to ensure that equilibrium is approached. Before initiating a cold shutdown, the reactor coolant system hydrogen concentration is lowered by reducing the volume control tank overpressure, by replacing the volume control tank hydrogen
- r .-
W 9.3-10A bI Amendment 9 4/30/75
SWESSAR-P1 atmosphere with nitrogen through a separate inlet in the gas ' space of the volune control tank. Hydrogen depletion of the gas space is accomplished by either absorption by the degassed letdown or purging with nitrogen to the radioactive gaseous waste system. C. Interface Requirements 9 Table 9.3.4-1 lists the system interface requirements. 9.3.5 Failed Fuel Detection System The gross failed f uel detector (GFFD) is described in RESAR-41. The system is interfaced to the SWESSAR-P1 sampling system (Fig. 9.3.2-1) as shown in GFFD modification Fig. 9.3.5-1.
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_, _j E 9.3 10E Amendment 9 4/30/75
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SWESSAR-P1 9.3.4 chemical, volume control, and Liquid Poison Systems A. System Interfact Modifications The chemical and volume control system (CVCS) is described in RESAR-3S. The fluid system interfaces as set forth in Table 1.7-2 of RESAR-3S are satisfied by the SWESSAR-P1 design as modifications to the indicated in Table 1.8-3. The following CVCS interface are required: The Stone & Webster radioactive gaseous waste system
- 1) valve at design requires the addition of one three-way at CVCS-MOD 2 CVCS-MOD 1 and one tee connection (Fig . 9. 3. 4-1 Sheet 1) to provide for continuous degasification of the letdown steam.
- 2) A sparger system is added to the volume contrcl tank to adequately dissolve hydrogen in the reactor coolant.
Fig. 9.3.4-1, Sheet 2, indicates the required changes in the to the system to adequately dissolve hydrogen reactor coolant.
- 3) The Stone & Webster radioactive solid waste system design requires the addition of tee connections at CVCS-MODS 3 thru 8 (Fig. 9.3.4-1 Sheet 3) and CVCS-MODS 9 thru 18 (Fig. 9.3.4-1 Sheet 4) . This change makes the piping ot the RESAR-3S demineralizers identical with the 17 piping of the demineralizers in SWESSAR-P1 and standardizes the filling, dr aining, (Section 11.5) and flushing operations.
(4) The positive displacement charging pump is replacedother with a centrifugal charging pump identical to the centrifugal charging pumps. This change gives increased cooling system reliability when used for emergency core pump is by maintaining redundancy waile.one char.ging down for maintenance. B. System Description design affects the RE M -3S description by The SWESSAR-P1 providing continucus degasification M the reactor coolant in the radioactive gaseous waste system for removal of fission product gases. The letdown coolant flows through the reactor coolant filter and into the radioactive gaseous waste system (Fig. 11.3-1) for dega::ification to maintain low gaseous activity levels in the coolant. The letdown is then returned to the volume control tank to be re-hydrogenated. This is accomplished by means of the spray nozzle at the top of the volume: control liquid tank ( P nozzle = 15 psi) and a gas sparger below the 10 gpm) is level. A portion of the letdown (approximately slow introduced tangentially, below the liquid level, causing a of the liquid, to ensure that the gas bubbles are rotation N-3S 9.3-10A Amendment 17 [j ([ h))
SUESSAR-P1 dispersed throughout the liquid. This sparger system provides adequate contact between the hydrogen and liquid to ensure that equilibrium is approached. Before initiating a cold shutdown, the reactor coolant system hydrogen concentra' ion is lowered by reducing the volume control tank overpressure,- cy replacing the volume control tank hydrogen otmosphere with nitrogen through a separate inlet in the gas space of the volume control tank. Hydrogen depletion of the gas g space is accomplished by either absorption by the degassed letdown or purging with nitrogen to the radioactive gaseous waste system. C. Interface Requirements Table 9.3.4-1 lists the system interface requirements. 9.3.5 Failed Fuel Detection System
'It e gross failed fuel detector (GFFD) is described in RESAR-3S.
The system is interfaced to the SWESSAR-P1 sampling system (Fig. 9.3.2-1) as shown in GFFD modification Fig. 9.3.5-1. 4
) u I >
W-3S 9.3-10B Amendment 17 9/30/75
SWESSAR-P1 9.3.4 Chemical,_yolume Control, and Liquid Poison Systems A. System Interface Modifications The makeup and purification system (MUSPS) is described in B-SAR 205. The fluid system interfaces as set forth in Fig. 9.3-1 of B-SAR 205 are satisfied by the SWESSAR-P1 desi.gn as l29 indicated in Table 1.8-3. The following modifications to the MDSPS interface are required:
- 1) The SSW radioactive gaseous waste system includes a three-way valve at the system outlet that is redundant to BSW valve;s V55 and V16 (Fig. 9. 3-1) . Fig. 9.3.4-1 Sh 1, CVCS-MOUS-1S2 eliminate this redundancy by moving the interface point of the SSW radioactive gaseous waste systela to the B&W MUSPS to locations on the letdown line side or these valves.
29
- 2) B-SAR 205 Fig. 9.3-2 components shown in SSW Fig.
9.3.4-1 (Sh 4) and all components of B-SAR 205 Fig. 9.3-4 are included as part of the complete MUSPS. The remainder of the B-SAR 205 chemical addition and boron recovery system is redundant to SSW supplied ccuponents and is t'aerefore not included as part of the SWESSAR-P1 design. CVCS-MOD 18 (Fig. 9.3.4-1 Sh 4) eliminates the deborating demineralizer inlet connection to the reactor coolant bleed holdup tank.
- 3) The Stone & Webster radioactive solid waste system l29 design requires the addition of tee connections at CVCS-MODS 5 thru 7 (Fig. 9.3.4-1 Sheet 3) and CVCS-MODS 9 thru 11 (Fig. 9.3.4-1 Sheet 4) . CVCS-MOD 8 (Fig.
9.3.4-1 Sh 3) and CVCS-MODS 12 thru 14 (Fig. 9.3.4-1 Sh 4) eliminate the flush connections to the demineralizers from primary grade water that would be redundant to the primary grade water connection to the SSW radioactive solid waste system (Fig. 11. 5-1B) . CVCS-MODS 15 thru 17 (Fig . 9.3.4-1 Sh 4) eliminate the regeneration line from the deborating demineralizers making the demineralizers nonregenerative. Resin discharge, flush, and strainer flushes are manifolded into one connection (Fig. 9.3.4-1 Sh 364) . These changes make the piping of the B-,SAR 205 demineralizers identical with the piping of the demineralizers in SWESSAR-P1 (Section 11.5) and Ftandardizes the filling, draining, and flushing operations. 1
- 4) The concentrated boric acid storage tanks (B-SAR 205 1 29 Fig. 9.3-4) are modified to be vertical cylindrical tanks rather than horizontal. This design is more adaptable for preventing oxygen absorption into the boric acid solution without venting the tank a gaseous BSW 9.3-10A k, yg} Amendment 29 10/29/76
SWESSAR-P1 vents. This eliminates the need for nitrogen to the tanks. .
- 5) The MUSPS connection (Fig. 9. 3 -1 ) to the spent fuel storage pool (valves MV33 6 MV37) are not applicable in the SWESSAR-P1 design.
- 6) Only one emergancy power supply will be available to ea h makeup pump with pumps P1B and Plc powered from the 32 same emergency bus. This eliminates the requirement for pump P1B to have the capability of being colmected to either emergency power supply.
B. System Description The SWESSAR-P1 design affects the B-SAR 205 description by providing continuous degasification of the reactor coolant in the radioactive gaseous waste system for removal of fission product gases. The letdown coolant flows through the purification demineralizers and into the radioactive gaseous waste system 32 (Fig. 11.3-1) for degasification to maintain low gaseo s activity levels in the coolant. N letdown is then returned to the volume control tank. Maker famps P1B and P1C will be used for normal plant operation, and are powered from the same emergency bus. Pump P1A is powered from the other emergency bus and is used only for emergency or accident situations. i C. Interface Requirements Table 9.3.4-1 lists the system interface requirements. 9.3.5 Failed Fuel Detection System
'Ihe SSW reactor coolant letdown gross activity monitor (Section 11.4.2.3.2) tisfies the failed fuel detection requirements.
ffy io-ove uu., BSW 9.3-10B Amendment 32 5/11/77
SWESSAR-P1 9.3.4 Chemical, Volume control, and Liquid Poison Systems A. System Definition The Combustion Engineering chemical and volume control system (CVCS) is described in Section 9.3.4 of CESSAR. The C-E CVCS includes many functions and components that are provided in other Stone & Webster system designs, Stone & Webster herein defines the applicable Combustion Engineering CVCS to provide a simple understandable interface to the CVCS as shown in CESSAR Fig. 9.3.4-1, 2, 3, and 4. The following defines the boundaries of the CVCS and its relationship with the SWESSAR-P1 design:
- 1) Fig. 9.3.4-1 (CESSAR)
All the components depicted on this figure are applicable. Piping moditications are made as shown on SWESSAR-P1 modification Fig. 9.3.4-1 (Sheet 3) for ion exchanger resin replacement and Fig. 9.3.4-1 (Sheet 6) to move the seaJ injection filters outside the containment s ncture. In 23 addition, the letdown heat exchanger and le. contro; valves are inside the containment structure.
- 2) Fic. 9.3.4-2 (CESSAR)
All the components depicted on this figure are applicable with the exception of the refueling water storage tank, including return and supply lines, as indicated on SWESSAR-P1 modirication Fig. 9.3.4-1 (Sheet 4) . The volume control tank is modified as shown on SWESSAR-P1 modification Fig. 9.3.4-1 (Sheet 2) . A piping modification is nade to the letdown line as shown on SWESSAR-P1 modification Fig. 9.3.4-1 (Sheet 1) . Fic. 9.3.4-3 (CESSAR) All components inside the containment s tructure are applicable except a piping modification is made to the 1 refueling pool drain (SWESSAR-P 1 nodif icat'.on Fig . 9.3.4-1 23 (Sheet 5)) . All components outside the cont 6inment structure l are within Stone S Webster's design responsioility.
- 4) Fig. 9.3.4-4 (CESSAR) hone or this figure is applicable, since all components are within Stone S Webster's design responsibility.
Piping which previously conne cted the CESSAR figures and components and which now connects a CESSAR component to a SWESSAR-P1 component due to the defined boundaries described above are not interfaced as modifications. These unnumbered in ter r ace points are treated as interface points and are indicated in Table 1.8-3. C-E ' 9.3-10A Amendment 23 3/31/76
SWESSAR-P1 B. Systme Interf ace twdifications The fluid system interfaces as set forth in CESSAR Fig. 9.3.4-1, 2, 3, ana 4, and redefined above are satisfied by the SWESSAR-P1 design. This is indicated in Table 1.8-3. The follciinq modifications inside.the CVCS boundary are required as follows:
- 1) !!odification Fic. 9.3.4-1 (Sheet 1) (SWESSAR-P 1)
The Stone 6 Webster radioactive gaseous waste system design requires the addition of one 3-way valve and one tee connection between CVCS-MOD-1 and CVCS-MOD-2, for continuous degasification of the letdown stream. This change deletes the gas stripper return line at CVCS-MOD-19.
- 2) Modification Fig. 9.3.4-1 (Sheet 2) (SWESSAR-P1)
A sparger system is added to dissolve hydrogen in the liquid space of the volume control tank. CVCS-MOD-3 and 4 revise the hydrogen and nitrogen supply to the volume control tank as described in Section 9.3.4-C.
- 3) Modification Fig. 9.3.4-1 (Sheet 3) (SWESSAR-P 1)
The Stone & Webster radioactive solid waste system desian requires the addition of flush and bypass lines with isolation valves from CVCS-MOD-5, 6, and 9. This makes the piping of the CESSAR demineralizers identical with the demineralizer piping in SWESSAR-P1 (Section 11.5) and standardizes the filling, draining, and flushing operations.
- 4) Modification Fig. 9.3.4-1 (Sheet 4) (SWESSAR-P 1)
The refueling water storage tank is a component of the SWESSAR-P1 containment spray system. The CESSAR scope or design responsibility components are interfaced to the SWESSAR-P1 refueling water storage tank at CVCS-MOD-11, 12,
, and 14 The SWESSAR-P1 desi7n provides boric acid 26 tankage for the boric acid makeup pump, soction instead of the refueling water storage tank in order to provide separation between normal and emergency component f unctions .
CVCS-MOD-15 and 16 move the boric acid makeup purr recirculation and suction lines f rom the refueling water storage tank to the boric acid tank. CVCS-MOD-17 and 18 delete the connections between the fuel pool purification systen and boric acid makeup purp line. The SWESSAR- - fuel pool purification system connects directly to the reluelinc water storage tank. k C-E 9.3-10B Amendment 26 6/2/76
/
t, y
SWESSAR-P1
- 5) Modification Fig. 9.3.4-1 (Sheet 5) (SWESSAR-P 1)
The SWESSAR-P1 design provides the gaseous vent header, reactor coolant drain tank pumps, and reactor coolant drain tank cooling inside the containment structure. CVCS-MOD-20, 21, and 22 interface the reactor coolant drain tank to the gaseous vent- and drain system vent header, reactor coolant drain tank pumps, and reactor coolant drain tank cooling water supply. CVCS-MOL -23 deletes the line and valve from l23 the fuel pool purification system. The SWESSAR-P1 design does not require this connection.
- 6) Podification Fig. 9.3.4-1 (Sheet 6) (SWESSAR-P1)
For ease of filter replacement, the seal injection filters have been relocated outside the containment structure. The CESSAR design locates these filters inside the containment structure. CVCS-MOD-7 makes valve CH-230Q a containment 23 isolation valve and the line upstream a containment penetration. CVCS-MOD-8 makes the line downstream of the seal injection filters a containment penetration and adds a containment isolation valve. CVCS-MOD-10 moves the inlet to the seal injection filters to upstream of valve CH-524. C. System Description 'Ihe CVCS interf ace modifications above affect the CESSAR chemical and volume control system description as follows:
- 1. The SWESSAR-P1 design provides continuous degasification of the reactor coolant in the radioactive gaseous waste system for removal of fission product gases. The letdown coolant flows through the letdown strainer and into the radioactive gaseous waste system (Fig . 11.3-1) for degasification to maintain low gaseous activity leve)s in the coolant. The letdown is then returned to the volune control tank to be re-hydrogenated. This is acccxnplished by use of the spray nozzle at the top of the volume control tank ( P nozzle =
15 psi) and a gas sparger below the liquid level. A portion of the letdown (approximately 'O gpm) is introduced tangentially, below the liquid level, causing a slow rotation of the liquid so that the gas bubbles are dispersed throughout the liquid. This sparger system provides adequate contact between the hydrogen and the liquid to ensure that equilibrium is approached. Before initiating cold shutdown, the reactor coolant hydrogen concentration is lowered by reducing the volume control tank overpressure, and replacing the volume control tank hydrogen atmosphere with nitrogen through a separate inlet in the gas space of the volume control tank. Hydrogen depler. ion of the gas space is accomplished by absorption in the degassed letdown or by purging with nitrogen to the radioactive gaseous waste system.
, , r7 %
C-E 9.3-10C hL' Amendment 23 3/31/76
SWESSAR-P1
- 2. The Stone & Webster boron recovery system deborates the letdown flow, recovers boron, and provides the surge capacity -
for water rejected from the CVCS.
- 3. The Stone S Webster primary grade water system supplies makeup water to the CVCS.
- 4. The Stone & Webster boric acid tank provides boric acid makeup to the CVCS. No makeup to CVCS is provided from either the fuel pool or the refueling water storage tark.
The refueling water storage tank is supplied by Stone & Webster.
- 5. The Stone & Webster vent and drain system provides drainage taps for the NSSS Vendor components (except for the vent and drain inside the containment structure which flows to the reactor coolant drain tank) . Stone & Webster supplies reactor coolant drain tank pumps to transfer reactor coolant drain tank water, and two means of cooling the water in the reactor coolant drain tank (primary grade water and the reactor coolant drain tank cooler).
- 6. The Stone S Webster radioactive solid waste system flushes and recovers spent resin in the CVCS.
D. Interface Requirements Table 9.3.4-1 lists the system interface requirements. 9.3.5 Failed Fuel Detection System The failed fuel detector is described in CESSAR Section 9.3-4.8.6.1 This .iystem does not directly interface with any Stone & Webster systems. Its function will be l'.ited to the detection of a failed fuel element in the reactor ccre.
~
' t ;a C-E 9.3-10D Amendment 23 3/31/76
SWESSAR-P1
- 9. 3. > Boron Recovery System Ston a & Webs ter 's boron recovery system replaces the following systems or portions of systems included in the base design:
Westinghouse (RESAR-41 and RESAR-3S) Section 9.3.6, boron recycle system 18 C-E, Section 9.3.4*, chemical and volume control system Detailed interface requirements for the replaced system or portion of system are given in Section 9.3.6.6 of SWESSAR. The boron recovery system processes reactor coolant to recover primary grade water and boric acid for reuse or disposal. The liquid entering the boron recovery system is produced by the feed and bleed operations necessary to maintain the boron concen-tration in the reactor coolant at the desired level. This liquid is reactor coolant letdown from the chemical and volume control system (CVCS, NS SS Vendor 's scope) and has been passed through a mixed bed demineralizer and degasifier. 9.3.6.1 Design Bases The design bases for the boron recovery system are:
- 1. The system shall process the letdown liquid generated by normal unit operationn, under either b. 3e loaded or load following conditions.
- 2. The system shall handle, by means of sufficient tankage, one cold shutdown-startup sequerce at any time prior to the fuel cycle being approximately 95 percent complete with no boron evaporator availability.
- 3. The system shall handle a back-to-back cold shutd: -
startup sequence at any time prior to the fuel cycles being approximate ly 85 percent complete with the boron evaporator available. The back-to-back cold shutdown-startup sequence is defined by going from operating to hot standby, boration to a 700 ppm B over equilibrium boron concentration, cooling at a maximum rate to 120 F, shutdown for one shift, heating at maximum rate to operating temperature, and dilution. This sequence then repeats itself. The total time for this event is no less than 60 hours. With limited evaporator availability, the maximum liquid accumulated in tankage after the occurrence is apprcximately 260,000 gal.
- Portions only, see equivalent section in SWESSAR tor modification to NSSS system. 18 9.3-10E . Amendment 18 I, lv .) 10/30/75
SWESSAR-P1
- 4. The system shall acccrnmodate a programmed weekly unit load schedule consisting of 52 hr at a weekend power level of 30 percent power, followed by an increase to 9
,7; t.) :_, i e'n ot d O
9.3-10F Amendment 18 10/30/75
SWESSAP-P1 full power in 4 br, and then 4 days of power cperation - each day consisting of 12 hr at full power, a decrease to 50 percent power in 3 hr, remaining there for 6 hr, and then returning to f ull power in 3 hr. 6 4 days are followed by 1') hr of full power operation, followed by a return in 4 hr to the weekend power level of 30 percent power.
- 5. Dur ing normal operation, the system shall have an evaporator availability of 90 percent for any 30-day period.
- 6. The systm shall produce distillate from the boron evaporator with less than 5 ppm boron and to include provision by means of the boron demineralizers (mixed bed ion exchange units) to reduce the boron concentration even further below 5 ppm if desired.
- 7. The systs shall produce an effluent frcm the boron recovery system to the radioactive liquid waste system discharce with on activity, excluding tritius, of less than the values given in the radioactive liquid waste system (Section 11.?) . This liquid is discharged as required to maintain a water balance within the unit and to control the tritium concentration in the reactor coolant. Tables 11.2-8 and 11.2-22 list the radionuclide concentrations in the effluent from the boron recovery system for the design case and for the expected ca se .
- 8. The systen shall produce, from the boron evaporator bottoms, boric acid solutions at concentrations for reuse in the reactor plant (Table 9. 3.6- 1) , or 12 weight percent boric acid for processina in the radioactive solid waste system. Fig. 11.5-2 lists the radionuclide concentration in the boron evaporator bottoms for the nuximum expected case.
- 9. This system is not safety related and is designated nonpuclear sufety (NNS) .
9.3.6.2 Svstem Desian The boron recovery system is shown in Fio. 9.3.6-1. Characteristics of the t mponents of the boron recovery system are shown in Table 9.3.6-2. y The plant ooerates primarily as a base loaded unit: however, it oossesses sutticient operatina flexibility to follow the weekly load schedule of a loud followina unit. This flexibility is
,, ,; e' i Lee U' Amendnont 12 9.3-11 b/16/75
SWESSAR-P1 obtained through the combined use of the CVCS and the boron recovery system. Passage through the cesium removal ion exchangers, storage, evaporation, and demineralization constitutes the processing that the reactor coolant letdown ic able to receive in the boron recovery system before discharge to either the primary grade water sy" (Section 9.2.7) or the radioactive liquid waste system (Sectan 11.2) . The bottoms from the boron evaporator are filtered c ,4 sent either to the CVCS for reuse or to the radioactive solid waste system (Section 11.5) for solidification and offsite shipment. Reactor coolant, which previously passed through the mixed bed demineralizer in the CVCS and was stripped of gases in the radioactive gaseous wa r,'ce system (Section 11.3) , is pumped through a cesium removal ion exchanger and a boron recovery filter. The cesium removal ion exchangers are mixed beds in the hydrogen-borated form of resins and provide a minimum decontamination factor of 10 for cations in the liquid stream in addition to removing anions for which no credit is taken. The two cesium removal ion exchangers are able to be operated in series to ensure this minimum decontamination factor. From the cesium removal ion exchanger (a) , the coolant is filtered by one of two boron reccvery filters before passage to the boron recovery tanks. The letdown is then stored in one of the two boron recovery tanks where it awaits further processing by the boron evaporator. The boron recovery tanks (150,000 gal c.ach) are sized so that, in conjunction with the boron evaporator (25 gpm) , the boron recovery system provides the capability for meeting a wide range of unit operating conditions. The boron recovery tanks are located in a diked area inside a heated enclosure which protects them from freezing. The liquid in the boron recovery tanks is pumped to the boron evaporator by one of two boron evaporator feed pumps. Either pump is able to supply the boron evaporator with feed in addition to supplying liquid, if necessary, to the radioactive liquid waste system for processing and disposal. The boron evaporator is constructed with an external reboiler, a vapor -liquid separator, and a tra3 section to reduce any liquid carryover to insignificant amounts and to maintain the boron content in che distillate at less than 5 ppn. For the specific design of the boron evt ator to be used in this unit, a decontamination factor for volatiles of greater than 104 is calculated at a bottm.s-to- ed concentration ratio greater than 1,000 (i.e. , the worst conditAon for removal of radionuclides). Operation of the boron evaporator is automatic on selector control from the boron recovery panel in the annulus building . Manual bypass piping and controls are provided. Rapid drainage 9.3-12 Amendment 7 2/28/75 [U
/ 'l fv -
SWESSAR-P1 of the boron evaporator is provided by transferring the evaporator bottoms to the boron recovery tanks. Pump or reboiler maintenance may require emptying of the boron evaporator. The boron evaporator distillate is collected in the boron distillate tank from which it is continuously removed on level control by the boran distillate pump, cooled in the Mron distillate cooler, and discharged to one of the two boron test tanks. A anall side stream from th. boron distillate pump is utilized for reflux in the fractionating column of the boron evaporator. Noncondensable gase; (primarily resulting from absorption of nitrogen and oxygen and from decay of iodine) which are removed from the liquid phase in the boron evaporator are discharged from the boron evaporator condenser and the boron distillate tank to the reactor plant aerated vents system (Section 9.3.3). The vent system combines these gases with the discharge from other vents and directs them to the radioactive gaseous waste system. The liquid discharged from the boron distillate tank fills one of the two boron test tanks (12,000 gal each) in approximately 8 hours. After one of the test tanks is filled, flow is transferred to the other tank. The contents of the filled tank are mixed (by circulating the contents with a boron test tank pump) , sampled, and if the boron content is suitable, pumped to a primary grade water storage tank (Section 9.2.7) . Should the baron test tank contents require further reduction of the boren con centration, the contents are processed through the toron demineralizers, either one demineralizer or both in series, and filtered by the boron demineralizer filter prior to storage in the primary grade water storage tanks. If a decision to further reduce the boron concentration in the di stillate is made af ter the distillate is transf erred to the primary grade storage tanks, the tanks' contents are then circulated through the boron demineralizers and boron demineralizer filter. Part of the boron test tank liquid can also be discharged to one of the low leveI" waste drain tanks for resampling and discharge (Section 11.2) to the environment via the discharge line. 'Ite se discharges occur only when necessary to maintain a water balance within the unit or to control the tritium concentration within the reactor coolant system. However, under no circumstances is the discharge activity, excluding tritium, from the boron recovery system to the discharge line greater than the values given in the radioactive liquid waste system (Section 11.2). ] Decontamination factors and retention times assumed for the analysis of the radionuclides in the boron distillate effluents are given in Table 9.3.6-3. When the concentration of the boric acid in the boron evaporator bottoms is at the desired NSSS Vendor value, the reclaimed boric 9.3-13 _. Amendment 7 (J ' I [;J 2/28/75
I SWESSAR-P1 Acid is pumped batch-wise through the boron evaporator bottoms filters to tanks in the CVCS. When packaging of the boron evaporator bottoms is desired for offsite shipment, the boric acid concentration in the bottoms is increased to about 12 percent by weight. The bottoms are then pumped to the radioactive solid waste system for immobilization in a shippin container . The activities given in Fig. li.5-2 are based on the relevant assumptions given in Table 9.3.6-3 and an average residence time of 1 week for the evaporator bottoms in the boron evaporator. All piping in the boron recovery system containing liquids with greater than 4 percent by weight of boric acid is electrically heat traced with redundant circuits to prevent precipitation of boric acid. The control of each process in the boron recovery system is automatic once the system setpoints have been established by preoperational tests prior to startup. Operation of the boron evaporator is initiated from the boron recovery panel in the annulus building. Batch processing and proper sampling of liquids ensure control of boron recovery system effluent streams. 9.3.6.3 Design Evaluation Monitoring devices are provided to measure conditions of pressure, temperature, flow, and liquid level in the boron recovery system. These monitorino devices ensure that the boron recovery system is operated safely within design limits. The design criteria listed in Section 9.3.6.2 are met through the choice of boron recovery tankage and boron evaporator capacity. Because there is an interdependence between the sizing of tle boron recovery tankage and the sizing of the boron evaporator, it is possible, within certain limits, to trade evaporator capacity for tankage. However, the criteria place a boundary on the minimum size of tankage required, and this, in turn, determines the maximum evaporator capacity needed . Because tanks are more reliable than evaporators, more emphasis is placed on the use of tankage; thus, 300,000 gal of tankage is supplied with a 25 gpm boron evaporator. Removal of radioactive ions from the decassed letdown liquid is accomplished through the use of ion exchange, storage, and evaporation. Conservatism in design is evident in a comparison of the decontamination factors assumed in Table 9.3.6-3 with those obtained through actual plant operations and equignent design ( 1 ) ( 2 ) . For example, iodine is removed from borated solutions with decontamination factors which are often more than an order of magnitude greater than those assumed in the calculations. If required, the use of the boron demineralizers O 9.3-14 Amendment 12 6/16/75 n' 6 b< V is7 bii
SWESSAR-P1 in series operation ef fects a higher decontamination f actor f or all radioa ctive ions. Higher decontamination f actors are accomplished through the measurement and control of the interstage activity between the boron demineralizers. The boron evaporator is desianed with an external reboiler, a large liquid disengaging space above the bottone, a rapor-liquid separator, and a tray section to reduce carryover tc a minimum. In addition, the boron evaporator is designed with a low vapor velocity throughout to further reduce any entrainment of liquid. Use of the boron evaporator yields a minimum decont am ma t ion f actor of greater than 10* for nonvolatiles. 12 The performance of the boron recovery system is ensured through the overall design of the system. The use of equipment havinc high decontamination factors and of long retention times causes the system effluent activity to be considerably less than that required for dis charge , even for the design basis case. J2 Tables 11.2-6 and 11.2-22 give desion case and maximum e xpect ed case activities, respectively, for the system discharge to the radioactive liquid waste system. A malfunction anc7' sis of the boron recovery system is presenter in Table 9.3.6-4. 9.3.6.4 Testing and Inspection Requirements A program of tests and inspections ensures that the design basis capability of the bcron recovery system is maintained through the lifetime of the unit. Prior to unit startup, each piece of equip nent or subsystem that may be independently operated is made to perform at desian flow rates, tempera .ures , and pressures so as to establish control setpoints. These control setpoints are used to verify the subsequent proper coera tion of the subsystems and to ensure that the overall system capability is not reduced by any cormonent of the system. The boron recovery system is operated frequently during normal unit operation. This treguency of operation plus adminis trative control ensure the proper performance of boron recovery system components. Standby pumps are used on a periodic basis, and continuously operating equipment is visually examined at uppropriate opportunities, to ensure their availability. Routine maintenance checks are performed to ensure that alternate subystems or equignent perform upon lailure of ar operating subsystem or equipment. 9.3.6.5 Jnstrumentation Applications 9.3-15 ()] Amendment 12 6/16/75
SWESSAR-P1 Instrumentation in the boron recovery system is designed to f ail sate and prevent inadvertent release of radiaactivity from the system. Level indicators on tanks read both locally and on the boron recovery panel, with alarms at tank liquid levels above control setpoints. Level controls on the boron evaporator are independent and control separate functions . The failure of one level controller in any position does not cause a runaway change of conditions in the boron evaporator subsystem; the oth er level controller, through its con trol functions, maintains the level within the boron evaporator or shuts down the boron evaporator. boron recovery system. Manual override controls are provided to allow continued operation of the boron recovery system, if re quired , under operator supervision. 9.3.6.6. Interf ace Requirements Table 9.3.6-5 identifies the boron recovery function interf ace requirements for the NSSS system or portion of system deleted g trom the base NSSS. These interface requirements are derived from the design bases for the boron recovery function in the NSSS SAR. The capability of the SWESSAR boron recovery system to meet these requirements is also identified in Table 9.3.6-5. References ror Section 9.3
- 1. Conne cticut Yankee Operating Reports, January 1970 - March 1972.
- 2. Cohen, P., Water Coolant Technology of Power Reactors, Chapter 7, Gordon & Breach, New York, 1969.
/
t ,E ') 9.3-16 Amendment 18 10/30/75
SWESSAR-P1 TABLE 9.3.1-1 is deleted. l12 Amendment 12 6/16/75 n-('1. ' / Uij
SWESSAR P-1 TABLE 9.3.1-2 COMPREE ED AIR SYSTEMS CONSEQUENCES L? COMPONENT FAILURES Comment and Component Failure Mode Consecuen es Instrument and service Compressor casting Redundant compressor air and containment ruptures. can be used to instrument air achieve full system compressors capability. Instrument and service Aftercooler tube Redundant air com-air and containment ruptures. pressor and after-instrument air cooler can be used aftercoolers to achieve full system capability. Instrument and service Air receiver Redundant air com-air and containment ruptures. pressor and receiv-instrument air er can be used to receivers achieve full system capability. Instrument and service Prefilter and/or Redundant prefilter h air and containment postfilter clogs. and postfilter can instrument air dryer be used to achieve prefilters and post- full system capa-filters bility. Instrument and service Air dryer ruptures . All instrument air air or containment users will fail in instrument air dryer , safe mode. Also, in-strument and service I air can supply con-tainment instrument air as required. Electrically powered Electrical failure Sufficient electri-instrument and service of one electrical cal system redund-air and containment bus. ancy is provided to instrument air ensure full system compressors capability (Section 8.3) . Service air section Rupture of service Service air section of instrument and air section is automatically service air system isolated on low discharge header pressure. ff, ri7 Ov, Uid 1 of 1 Amendment 7 2/28/75
SWESSAR-P1 TABLE 9.3.1-3 COMPRESSED AIR SYSTEM INTERFACE INFORMATION B&W* C-E* W-41 and W-3S* Pressure 100 psig 90+10 psig _ 90-125 psig Cleanliness Oil less than Oil free Oil free, no l 2 mg per 1,000 particles scf, no par- greater than 10 ticles greater microns 29 than 40 microns Maximui dewpoint 15F -40 F 0F Consumption Not stated 200 scfm 350 scfm (typi-continuous cal) * * (instrument air)
- Requirements as stated in NSSS 'J 1.. lor's SAR.
- Not stated in RESAR-41; however, stated in RESAR-3S U i. r /
p .j
- t. i, 1 of 1 Amendment 29 10/29/76
SWESSAR P-1 TABLE 9.3.2-1 REACTOR PLANT SA**PLE SYSTEM DESIGN INTERFACE CHARACTERISTICS Sample Pressure (psig) Temperature (F) 7 Reac or Coolant System Loop 2,500 670 Reactor Coolant System Pressurizer 2,500 700 Safety Injection System (C-E) 1,950 'J ' ^ Accumulators (W , ESW) 700 650 Residual Heat Removal 1,950 '600 Chemical and Volume Control System 370 650 Steam Generator (:B&W) 1,235 630 l 1 of 1 Amendment 7 c- ,
'^
umo
- 2/28/75 Ou
SWESSAR-P1 TABLE 9.3.3-1 AERATED VENTS AND DRAINS Eoron Recovery System (Section 9.3.6) Cesium removal ion exchangers lg Boron recovery filters Boron recovery tanks Boron evaporator reboiler pump seal Boron evaporator bottoms filters Boron demineralizer filter Boron evaporator condenser and distillate tank Boron test tanks g Boron demineralizers Radioactive Liquid Waste System (Section 11.2) High level waste drain tanks Low level waste drain tanks Waste evaporator condenser and distillate tank [g Waste demineralizer filter Low level waste effluent filters Waste test tanks Waste demineralizer Regenerant chemical evaporator condenser and distillate tank Laundry waste drain tank Laundry waste evaporator condenser 9 Laundry waste distillate test t: ak Laundry waste bottoms tank Waste evaporator reboiler pump seal Regenerant chemical evaporator reboiler prmp seal Radioactive Gaseous Waste System (Section 11.3) Process vent filter assembly lg Degasifier recovery exchanger Degasifier recirculation pumps Trim cooler jg Radioactive Solid Waste System (Section 11.5) Spent resin surge tank Spent resin transfer pump filter Catalyst tank g Evapcrator bottoms tank Skid mounted solidification unit Waste sludge tank Waste decontamination tank Oci Lu ! 1 of 1 Amendment 9 4/30/75
SWESSAR P-1 TABLE 9.3.3-2 GASEOUS VENTS AND DRAINS NSSS Vendor Westinghouse BSW C-E RESAR-41 and 3S Chemical and Volume Control System Relief Valves x x Reactor Coolant Filters x Seal Water Injection Filters x x Seal Water Return Filters Volume Control Tank x x x Boric Acid Filter x x Boric Acid Tanks x x Seal Water Heat Exchancer x Boric Acid Blender x Boric Acid Transfer Pumps x Purification Demineralizers x x Boron Thermal Regeneration Demineralizers x x Charging Pumps x x defueling Shutdown Tanks x Auxiliary Spray Line x Excess Letdown heat Exchanger x g Safety Iniection System High Head Saf ety Injection Pumps x Low Head Safety Injection Pumps x Accumulators x x x Reliet Valves x x Reactor Coolart System Reactor Coolant Pump Seals x x Pressurizer x RCS Loop x x x Control Rod Drive Mechanism x x Refueling Failed Puel Detector x Reactor Vessel Flange Leakoff x Relief Valves x x Residual Heat Renoval Systen Injection Headers x Coolerd x Reliet Valves x x
/<' r^q UC, buc 1 of 2 Amendment 17 9/30/75
SWESSAR P-1 TABLE 9.3.3-2 (Cottr) NSSS Vendor Westinghouse BSW C-E RESAR-41 and 3S Reactor Plant Sampling System (Section 9.3.2) Purge Header x x x Radioactive Gaseous Waste System (Section 11.3) g Degasifier recovery exchanger x x x Process gas ccrnpressor af ter- x x x cooler _M_iscellaneous Equipment Drains Valve Stem Leakoffs x x x 0 2 of 2 / ~.7 "; o - Amendment 17 b' U i LcJ 9/30/75
SNESSAR-P1 TABLE 9.3.4-1 CHEMICAL A7.7 VOLUME CONTROL SYSTEM INTERFACE INFORMATION RESAR-41 ' Interface Item (Note 1) RESAR-u1 Reference SWESSAR Reference
- 1. Component Note 3 Refer to SWESSAR-P1 cooling Section 9.2.2.6.
water (Note 2)
- 2. Electrical Note 3 Refer to SWESSAR-P1 Power Section 8.4.
- 3. System layout 9A.1 Annulus building for operation arrangements are shown and inspection in Fig. 1.2-4.
- 4. Instrument air 9.3.1, 9A.1 Section 9.3.1.6
- 5. Protection from 3.3, 3.4, 2.5.2 Sections 3.3, 3.4, and natural phenomena 3.7 21
- 6. Protection from 3.5 Sections 3.5 and 3.6 rupture and missiles
- 7. Nitrogen to VCT 1.7.1 Sections 9.5.8.6 and
9.3.4 Notes
- 1. These requirements are safety related. The SWESSAR-P1 design accommodates and is compatible with all chemical and volume control interface requirements in RESAR-41.
- 2. This interface requirement is cross referenced in RESAR-41 Appendix 9A.
- 3. The RESAR-41 cross ref erence fo:, these interface requirements is given in the cited SWESSAR-P1 section.
W 1 of 1 Amendment 21 g na 2/20/76 7ai U <_
SWESSAR-P1 TABLE 9.3.4-1 CHEMICAL AND VOUJdE CONTROL SYSTEM INTERFACE RIQUIREMENTS( * > Interface from RESAR-3S RESAR-3S Reference SWESSAR Reference Electric Note 2 Section 8.4 Power (Note 3) Component Note 2 Section 9.2.7,6 cooling water Protection 3.3,3-4, 2.5 Sections 3.3.3, 3.4.3, from natural 3.7.6, 3.8.6 phenomena Protection 3.5, 3.6 Sections 3.5.6, 3.6.6, from pipe rupture and 3.8.6 28 missiles Ir.strument air 9A.1 Section 9.3.1.6 System layout 9A.1 Section 1.2 for operation Note 1: These resuirements are safety related. The SWESSAR-P1 design accommodates and is compatible with all chemic 1 and volume control interface requirements in RESAR-3S. Note 2: The RESAR-3S cross reference for these interface requirements is given in the referenced SWESSAR-P1 section. Note 3: Includes heat tracing. t . J W-3S 1 of 1 Amendment 28 8/6/76
SWESSAR-P1 TABLE 9.3.4-1 CHEMICAL AND VOLUME CONTROL SYSTFl4 INTERFACE INFORMATION (Notes 1 & 2) Requirement B-SAR-205 Reference SWESSAR Reference
- 1. Electric power Notes 3, 4 Section 8.4 to operate the equipuent
- 2. Controls to Note 3 Section 7.8 operate the system
- 3. Process chemistry require m ts
- a. Sampling 9.3.4.1.4.13.2 Section 9.3.2.6 9.3.2.1 l33 1
9.3.2.2 9.3.2.5 9.3.2.6
- b. Makeup water 9.3.4.1.4.13.1 Sectiens 9.2.7.6 and 9.3.4 l33
- c. Boric acid Sections 9.3.6.6 makeup and boron and 9.3.4 recovery
- d. Hydrogen 9.3.4.1.4.13.4 Sections 9.5.8.6 and 9.3.4
- 4. System layout 9.3.4.1.n.15.6 Arrangement drawings for operation 9.3.4.2.6.15 are shown in Fig.
ard inspection 1.2-3 and 1.2-4 33
- 5. Ccxnponent cool- Note 3 Section 9.2.2.6 ing water flow to the pumps and heat exchangers
- 6. Protection 9.3.4.1.4.2.1 Sections 3.3, 3.4, from natural 9.3.4.1.4.2.2 3.5, and 3.7 phencxnena 9.3.4.2.6.2 B&W 1 of 3 Amendment 33 6/30/'?
nn, bcisr /7 Lmu
SWESSAR-P1 TABLE 9.3.4-1 (CONT) Requirement B-SAR-205 Reference SWESSAR Reference
- 7. Separation 9.3.4.1.4.3 Sections 3.5 and and protection 9.3.4.1.4.4 3.6 from pipe 9.3.4.1.4.5 rupture, 9.3.4.1.4.6 internal mis- 9.3.4.1.4.7 33 siles, and pipe whip
- 8. Environment 9.3.4.1.4.19.1 Sections 6.2.2, ,
9.3.4.1.4.19.3 9.4.2, 3.11, and [33 9.4.5
- 9. Instrument 9.3.4.1.4.18 .1 Section 9.3.1.6.
air The instrument air l33 systems supply no safety related functions.
- 10. Equi xnent 1 9.3.4.1.4.15.7 Section 5.5.1.4 Supports and 9.3.4.1.4.18 .3 loadings l33
- 11. Leakage 9.3.4.1.4.40 Section 12.2.4 Monitoring 9.3.4.2.6.10
- 12. Radiological Waste
- a. Solid waste 9 .3 . 4 .1. 4 .16 .1a ,b , c 11.5.8 9.3.4.2.6.16.1a,d,e
- b. Liquid waste 9.3.4.1.4.16.2a,b,c 11.2.11 9.3.4.2.6.16.2a,b,c 9.3.2.3
- c. Gaseous waste 9. 3. 4 .1. 4 .16 . 3a ,b ,c 11.3.10 9.3.4.2.6.16.3a Hote 1. Requirements related to ECCS operation are addressed in Section 6.3.6.
- 2. These requirements are safety related. The SWESSAR-P1 design acc e ndates and is compatible with all applic-able chemical and volume control system interface re-quirements in B-SAR-205 except as noted below:
rm, Y 'tJ a l k ,_, B&W 2 of 3 Amendment 33 6/30/77
SWESSAR-P1 TAnLR 9.3.4-1 (CONT) Requirement B-SAR-205 Reference SWESSAR Reference
- 1. Items 9.3.4.1.4.15.1a, 1b, 2a, 2d, 2e, 2f. Rese require detailed design not yet performed. These interfaces will be addressed in the application for Fi:aal Design Approval.
- 2. Items 9.3.4.1.4 (1.3) , (8.3) , 19.3. These are re-quirements based on makeup pump PIB having power avai1ah1e from either emergency power supply. Jys-tem interface modification 6 has changed thin power supply arrangemet so that pump P1B is supplied f;om only one emergency power supply.
- 3. Item 9.3.6.6.18.3a.2. W e HPI pumps suction is switched over to LPI pump discharge autrvnatically at an RWST level higher than that required for minimun HPI pump 34 NPSH. This switchover is also discussed in Section 6.3.6.
- 3. The B-SAR-205 cross reference for these interface re-qumments is given in the referenced SNESSAR-P1 Section.
- 4. Includes heat tracing.
ff - p, n . , Uvi cmc B&W 3 of 3 Amarwiment 34 7/22/77 I
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SWESSAR-P1 TABLE 9.3.6-1 hSSS DESIGN AND OPERATING INTERFACE PARAMETERS Babcock & Combustion Parameter, Wilcox Engineerina Westinghouse-41 Westinghouse-3S bori e acid concentra-tions pro-duced and reclaimed n in boron evaporator 5% 4% 4% 4k Letdown flow rate 5 0 gpm 84 gpm 100 gpm 75 gpm
, , c1
(, , i _. _ - t 1 of 1 Amendment 17 9/30/75
SWESSAR-P1 TABLE 9.3.6-2 BORON RECOVERY SYSTEM PRINCIPAL COMPONENT DESIGN AND PERFORMANCE CHARACTERISTICS Boron Evaporator Number 1 Capacity, gpm 25 Design pressure, psig 100/ full vacuum Design temperature, F 350 l'aterial of construction SS Boron Recovery Tanks Number 2 Capacity, gal 150,000 Design pressure Atmospheric Design temperature, F 212 Material of construction SS or fiberglass Boron Test Tanks Number 2 Capacity, gal 12,000 Design pressure Atmospheric Design temperature, F 212 O Material of construction SS or fiberalass { Boron Distillate Tank Number 1 Capacity, gal 550 Design pressure, psig 100/ full vacuum Design temperature, F 350 Material of construction SS Cesium Removal Ion Exchangers Number 2 Capacity, ft3 35 Design pressure, psig 225 Design temperature, F 250 Material of construction SS Boron Demineralizers Number 2 Capacity, ft3 35 Design pressure, psig 225 Design temperature, F 250 Material of construction SS Boron REcoverv Filters Number 2 1 of 4 ,. n' ' Amendment 12 b 'O / v-6/16/75
SWESSAR-P1 TABLE 9.3.6-2 (CONT) Capacity, gpm B6W 250 C-E 150 W41 450 g W3S 150 Design pressure, psig 225 Design temperature F 250 Material of ccnstruction SS Boron Evaporator Bottoms Filters Number 2 c.pacity, gpm 50 Design pressure, psig 225 Design temperature, F 250 Material of construction SS Boron Demineralizer Filter Number 1 Capacity, gpm 200 Design pressure, psig 225 Design temperature, F 250 Material of cons' ruction SS Boron Distillate Cooler Number 1 Duty, Btu /hr 1,630,000 Distillate (tube) Capacity, lb/hr 12,500 Design pressure, psig 35 Design pressure, psig 100/ full vacuum Design tmperature, F 350 Operating temperature c in/out 250/120 Reactor Plant Component Cooling Water (shell) Capacity, lb/hr 81.625 Operating pressure, psig 75 Design pressure, psig 150/ full vacuu Design ternperdture, F 220 Operating temperature, in/out 105/120 Boron Evaporator Reboiler N'Inber 1 Duty, Btu /hr 15,400,000 Saturated steam (shell) Capacity, lb/hr 17,500 Operating pressure, psig 100 Design pressure, psig 200/ full vacuum Design temperature, F 400 Operating temperature, in/out 338/338 Borated Water (tube) Capacity, lb/hr 1,375,000 Operating pressure, psig 35 Design pressure, psig 100/fu11 vacuum 2 of 't , p ._ , . , , Amendment 17 OL, ysj 9/30/75
SWESSAR-P1 TABLE 9.3.6-2 (COIrr) Design temperature, F 350 l12 Operating temperature, in/out 235/264 Horon Evaporintor Condenser Number 1 Duty, Btu /hr 13,000,000 12 Saturated steam (tube) 13,750 Capacity, lb/hr Operating pressure, psig 15 Design pr essure, psig 175/ full vacuun Design temperature, F 350 Operating temperature, in/out 250/250 Reactor Plant Component Cooling Water (shell) Capacity, lb/hr 650,512 Operating pressure, psig 75 12 Design pressure, psig 150/ full vacuum Design temperature, F 220 Operating temperature, in/out 105/135 Boron Evaporator Feed Pumps Number 2 Capacity, gpm 50 Head, ft Late r Design pressure, psig 100 9~ Design temperature, F Material of construction 180 304 SS 12 Boron Distillate Pump Number 1 Capacity, gpm 35 Head, ft Later 12 Design pressure, psig 165 Design tmperature, F 350 Material of construction 304 SS Boron Evaporz' ar Bottorns Pump Number 1 Capacity, gpm 25 Head, it Later Design pressure, psig 200 l12 Design temperature, F 250 Material of construction 304 SS Boron Test Tank Puno Number 2 Capacity, gpm 150 Head, it Later Design pressure, psig 150 Design tmperature, F 212 12 Material of construction 304 SS 12 3 of 4 Amendment 12 6/16/75 (47 p}'
SWESSAR-P1 TABLE 9.3.6-2 (CONT) Boron Evarorator Reboiler Pump Number 1 Capacity, gpm 2,750 Head, ft Later Design pri.ssure, psig 150/ full vacuun l12 Design tenperature, F 350 Material of construction 316 SS
,, t _. J 4 of 4 Amendment 12 6/16/75
SWESSAR-P1 TABLE 9.3.6-3 ASSUMPTIONS USED IN ACTIVITY DISCHARGE CALCULATIONS Decontumination Factors Cesium renoval ion exchanJers 10 for (mixed Ded) (H-bO rorm) Cs, Rb Boron evaporator and boron 10* for all ions deminerali::ers (conbined) (mixed bed, H-OH f orm) R, ntion Times Boron recovery system minirnim 24 hr Letdown flow rate BSh' NSSS SO gpm C-E NSSS 84 cmm W-41 USSS 100 gpm n W-3S NSSS 75 gpm ( ; e,I J *: J - 1 of 1 Amendment 17 9/30/75
SWESSAR-P1 2 TABLE 9.3.6-4 BORON RECOVERY SYSTEM FAILURE ANALYSIS Component Malf un ction Comments and Consequences Pressure vessels and Outleakage Pressure vessels and other cou-other components con- ponents are protected f rom over-taining letdown pressure by automatic controls liquids with dis- and relief valves; thoretore, solved gases only minor leaks are cor.sidered possible. Boron recovery Outleakage Only degasse3 liquids are nor-tanks mally stored in these tanks which are protected by a diked area capable of retaining the entire contents of the tanks. The dikes are Class I s tru c-tures. One boron recovery Failure to Sufficient capability to makt evaporator or aux- function boric acid solution for station iliaries requirements exist in the horic acid batt - tanks, and the pri-mary water tanks can supoly adequate quantities of water.
/
k)v/ '- ' 1 of 1 Amendmont 2 8/30/74
SWESSAR-P1 TABLE 9.3.6-5 DORON RECOVERY SYSTEM INTERFACE REQUIRD(ENTS Requirement RESAR-41 Reference SWESSAR Reference The boron recycle systes is designed to Section 9.3.6.1.1 The capacity of the boron collect, via the letdoun line in the recovery system exceeds that chemical ard vr kne contzul system, the given by RESAR-41. See design excess reactor coolant that results bases, Section 9.3.6.1. from the following plant operations during one core cycle:
- 1. Dilution for core burnup from approximately 550 psum h eron at the beginning of a semi-annual cure cycle to apgroximately 10 ppm near the end of the core cycle or frcza apprminately 1,200 ppm boron at the beginning of an annual core cycle to approximately 10 ppe near the end of the core cycle.
- 2. Hot shutdowns and startups. Two hot 4 shutdowns are asstamed to tale place during a semi-annual core cycle. Nur hot shut-downs are assumed to take place during an annual core cycle.
- 3. Cold shutdowns and startups. One cx)1d shutdown is assumed to take place during a semi-annual core cycle. 17 tree cold shutdowns are assumed to take place during an annual core cycle.
- 4. Refueling shutdown and Ltartup.
The boron recycle syntan also collects water frun the following sources:
- 1. Reactor coolant drain tank (liquid waste Section 9.3.6.1.1 Collected in gaseous vent and processing system) - collects leakof f drain system, Section 9.3.3.
type drains from equipna:t inside the contairament.
- 2. Volume control tank pressure relief Section 9.3.6.i.1 Collected in gaseous vent and (chemical and voltane control system) drain system, Section 9.3.3.
' > and high htad safety injection pumps pressure reliefs (safety injection system). c1 g , 3. Boric acid blender (chemical and volume Section 9.3.6.1.1 Stored in the boron recovery
; .* control system) - provides storage of tanks, Section 9.3.6.
'J boric acid if a boric acid tank muxt be emptied for maintenance. The botic acid solution is W 1 of 2 Amendment 18 10/30/75
SWESSAR-P1 TABLE 9.3.6-5 (CONT) Requirement RESAR-41 Rulerence SWESSAR Reference stored in a recycle holdup tank af ter first being diluted with reactor makeup water by the blender to ensure against precipitation of the boric acid in the unheated recycle holdup tank.
- 4. Accumulators (safety injection systen) - Section 9.3.6.1.1 Cbilected in the gaseous collects effluent resulting frorn lear vent and drain system, testing of accumulator dieck valves.
- Section 9.3.3.
18
- 5. Liquid waste processing system - Section 9.3.6.1.1 nis is provided, Section 11.2.
provides capability for using the recycle evaporator as a waste evaporator and vice versa.
- 6. Spent fuel pool pumps (gent fuel pool section 9.3.6.1.1 cooling and cleanup system) Stored in the boron remvery provides tankes, Section 9.3.6.
means of storing the fuel transfer canal water in case maintenance is required on the transfer equipment.
- 7. valve leakof fs and equipnent drains. Section 9.3.6.1.1 collected in the gaseous vent and drain systesu, Section 9.3.3.
-1 1
1
)
W 2 of 2 Mendment 18 10/30/75
SWESSAR-P1 TABLE 9.3.6-5 BORON RECOVERY SYSTDi INTET FACE REQUIRDiENTS Requiremment RESAR-3S Reference SWESSAR Referenm The boron recxrvery systese (BRS) is designed to collect, via Section 9.3.6.1.1 The capacity of the BRS exceeds the letdown line in the chemical and volomme cmtrol system that given by RESAR-35. See (CVCS) . the ercess reactor oaolant that resulta fram the design bases, Sectina 9.c.6.1 following plant operations during one core cycle:
- 1. Dilution for core burnup frtum approximmately 1,200 prum boron at the beginning of an annual core cycle to '
approximately 10 p5mm near the end of the core cycle.
- 2. Hot shutdowns and starrtps. Four hot shutdooms are asstamed to take place during an annual core cycle.
- 3. Cold shutdowns and startups. Three cold shuttorns are assummed to take place during an annual core cycle. 18 4 Refueling shutdoorn and startup.
The BRS also collects water frcum the following sources:
- 1. Reactor molant drain tmk (liquid waste processing Section 9.3.6.1.1 Q)11ected in gaseous vent and drain system) - cx211ects leakof f type drains f rtum equip- system, Section 9.3.3.
ment inside the containment.
- 2. Volumme control tank and charging piamp suction Section 9.3.6.1.1 Collect ed in gaseous vent and drain pressure reliefs (CVCS) and safety injection pumps systemi, Section 9. 3. 3.
pressure reliefs (esiergency core cooling systesa) .
- 3. Boric acid blender (CVCS) provides storage of Section 9.3.6.1.1 Stored in the baron recovery tanks, boric acid if a boric acid tank must be captied Section 9.3.6.
for maintenance. The boric acid solution is stored in a recycle holdup tank af ter first being diluted with reactor makeup water by the blender to ensure against precipitation of the boric acid in the un-heated recycle holdup tank. O 4. Accruml a tors (safety inje<-tion systese) - collects Section 9.3.6.1.1 Collected in the gaseous vent and cm effluent resulting from leak testing of accturulator drain system, Section 9.3.3. ma check valves.
- 5. Liquid waste processing systeam - provides capability Section 9.3.6.1.1 This is provided, Section 11.2.
for using the recycle evaporator as a waste evaporator CD and vice versa. CD W-3S 1 of 2 Amendment 18 10/30/75
SWESSAR-P1 TABLE 9.3.6.5 (CONT) Requireurnt RESAR-3S Reference WESSAR Reference
- 6. Spent fuel pool ptumps (spent f uel pool cooling and Section 9.3.6.1.1 Stored in t re toron recovery tanks, cleanup systesa) - provides a ameans of storing the Section 9.3.6.
fuel transfer canal water in case usintenance is required on the transfer equipment.
- 7. Valve leakoffs and equignment drains. Section 9.3.6.1.1 Collected in the gaseous vent and drain system, Section 9.3.3.
cs C. ~,3 CJ __m W-3S 2 of 2 18 Amendmen.t--
SWESSAR-P1 TALLE 9.3.6-5 DORON RECOVERY SYSTEM INTERFACE RE(NJIRD4ENTS Requiresaent B-SAR-205 Reference SWESSAR Reference
- 1. Stores reactor coolant bleed and Section 9.3.4.2.1 Section 9.3.6, boron reactor cxnlant evaporator distillate. recover systen
- 2. Degasifies reactor coolant l etdown Section 9.3.4.2.1 Section 11.3, gaseous and/or bleed. waste systm-0%
c.N
.j C~.) .*m BW 1 of 1 Amndment 29 10/29/76
TWZSSAR-P1 TABLE 9.3.6-5 BORON RECOVERY SYSTEM Ih1TRFACE REQUIREMENTS Requirement cgsgAp Reference EESSAR Reference
- c. Receive, store and separate borated waste for Section 9.3.4.1 Section 9.3.6, teron reuse and/or discharge to the liquid waste recovery system management system (IMMS) ; 'I
- 1. Provide a means f or continuous removal of noble Section 9.3.4.1 Section 11.3, radioactive gases frota the reactor coolant system. qaseous waste system
- h. the CVCs has the capacity to acconsmodate all Section 9.3.4.2 Section 9.3.6.1, design bases, liquid wastes generated due to the operations boron recovery system identified in Table 9.3.4-3.
cm t .h CO gj C-E 1 of 1 Amendrrent 18 10/10/75
SWESSAR-P1 Tables 9. 3. 6 -6, -7, and -8 have been deleted. 18 1 of 1 Amendment 18
-- c '
10/30/75 i i ., i G -
e CONTAINMENT INSTRUMENT AIR POST FILTERS ECB A V A A
- r ::
,.. i U NCB fd!NSTRUMENT i M 7 1 7 AIR DISTRIBUTION thSIDE CONAT!hMENTi STRUCTURE l T d 6 w i i CONTAINMENT FROM INSTRUMENT AIR INSTRUMENT (FIG.g.3.1 1) AIR CRYERS () Y =X - h >> c P h ] , PD . V MCB ENT NSTRudENT AIR PREFILTERS FIGURE 9.3.1-2 CONTAIN? TENT INSTRLUENT AIR SYSTE!! PrR STANDARD PL ANT , , , , _ SAFETY ANALYSIS REFORT SIESSAR P1 U J
3 a I i <a 3 [ CONT AINNENT g INSTRUMENT AIR TO CONTAINMENT = FILTER S!LENCER ATM0 SPHERE (TTP) _________________y n TO CONTAINMENT ATMOSPHERE I I (TYP) l l A n h b
- > X -
X-
+ +
9 v CONTAINMENT CONTAINMENT INSTRUMENT INSTRUMENT AIR AFTIRC00LER AIR CCMPRESSO4 V CONTAINMENT INSTRUMENT AIR RECIEVER CONT A! NM ENT INSTRUMENT AIR FILTER SILENCER r----------------7 A I I TO CCNTAINMENT I REACTOR PLANT COMPONENT l COOLING MATER d l i rig.9.2.2.lE(TYP) y V CCEPONENT
+ + 4' COOLING MATER V FIG.9.2.2-lE CONTAINMENT CONTAINMENT INSTRUPENT (TYP) AIR AFTERC00LER INSTRUMENT AIR COMPRESSOR V
CONTAINMENT p INSTRUMENT AIR RECF!VER U 3 NOTE: THIS SYSTEM IS NON-NUCLE AR SAFETY CL ASS (NNS)' LOCATED IN THE CONTAINMENT.
! i p r l
i I FRf1d TRiu NN S ->i.+ SC2 FR08 L0e STE LEVEL sASTE C00LER FRDW LE1008N HEAT ANKS ORAIN TA*S EFFLUENT s
+ 2 x55R-Il EXCH ANGER DUTLET E, .IA FIG.11 2-lE FIG.11.3 1A l[y NnTE 1 ~* -%
J -{ FRCW REACTOR C00LANT WTE -- j* k
'g ,FX
- sSSR-13 ! FILTER INLET .
FR0v 10 NnTE 1 I ? '
$5 w.SC3 NOTE STEAW GENERATOR I
4 ;5, BL0t0CaN SYSTEW
- g. MU4W WTE "7P "" SSR '14 GN 0 LET 4
NOTE 1 NOTE 4 g v p pwp
- - - g -m: c ces_, e e e ._ __.i__
RMP _J NM yp s TEMP p gyp _ __ . . _ rG _ _ . RT - Rt (TYP OF 2) t -' RNP i(X)- - { N%S NOTE 4 SC2 9 ir3 ,
)3r
-u-JLJ b J .
U (/ _ , TO LIQUID T' -[ y. g - WASTE SYSTEN F I G .11 2 -1
/fis ' a TO GASEOUS VENT V ' > AND ORAIN SYSTEM 10 VOLUME h
,m, SSR-11) CONTPDL TANK NmE i
!E ild E N Er . 6Nf SC2 ro oy p 3 3 y , ,
/
NK FIG.9 3 2-1A REACTOR PLANT SAMPLING SYSTEM PIE REFERENCE PLANT SAFETY ANAlfSIS REPORT SIESSAR-P1 h ,
, n . ~
u I ()Ui - AMENOMEmi 13 6/30'75
INSIDE INSIDE CONTAINMENT
-*"* ANNULUS BUIL0 LNG FROM CESIUM FR STRUCTURE R90iAL % LE ClA F , .c8_1Al EX} ANGERS CG FROM FIG.9 3 6-1 A FI s'i'"0" NOTE 1 Ssa ' W IN~
x : X-iCIA = {-{ l
=
SAE S3"~ 0 ) SC2 h NNS Cl A F, . {CTr] REACTOR PLANT l COMPONENT DELAY COOLING #ATER Y FR0c RCS C0ll TYP)@ h -- @ FIG 9 2 2 1(TYP) 3 L0nP #1 SSR.9 ,
==4X X ; N NOTE I NnTE 4 NOTE 4 7 DTE 4; 11 00 Q SC2 M NNS i ,
h SSR 10 % -
- NOTE 1 2TE 4 V FRDM SSR-A & '
ACCUMULATORS @ , NOTE 1 $3p.5 $pf. I dCIAl Q ~ G SSR 6 j-f X == ] 4 ; g SC2 h *S FROM SSR 1 M y M ; l 1 ' RHR i N TE SSR 2 K )(M ) r & iCIA i i b b I [EE3 'rc<c-c< : X -M cpl +
, , Bi TO NFO r i r SC2
' 1r,
. g3 ' i ilG.9 3 51
' ' d ' d 6(p NOTE 1 q7 7 il hM FRru OEMINrRAllZED a T i WATER SYSTEM < - - & -
FIG 9 2.3-1 > ' ' ' 10.FROM REACTOR > - r, T T T T C PLANT COMPONENT gr ,h i L or ,L '
,r,,
d ' d 6 d ' sh d 6 d 6d COOLING 6 sATER 3 Fli. 9.2.2-1
I UI
) 7 (TYP.0F 3) _
F SAMPLE TO HIGH LEVEL WASTE NnTE3: d M ORAIN TANK FIG.11.2 1A
- 1. EQUIPMENT SUPillE0 BY NSSS VENDOR.
- 2. THIS SYSTEM IS NON-NUCLEAR SAFETY CLASS (NNS)
EICEPT EHERE OTHERTISE NOTED.
- 3. 50LEN010 OPERATED VALVES ARE SH0fN IN SAMPLING POSITION.
- 4. THESE VALVES ARE OPEN DURING NORMAL PLANT OPERAil0R ALL OTHER SOLEN 010 0*ERATED VALVES ARE CLOSED DURING NORMAL OPERATION.
- 5. GENERAL REvlSIONS HAVE BEEN MADE TO INCLUDE SEPARATE SAMFilNG LINES.
A00lil0NAL SAMPLING POINTS, INSTRUMENTATION A00lil0NS, AND OTHER MINOR N00lFICATl0NS.
/ 7 ,n / .1 (J U i G .' O
pg Ltg Firu Trig NNS - >4- SC2 I LIVEL TASTE C00LER m WWTE 4 FROM LETOOWN HEAT OPA!N TMRS EFFLUD(T
> _ (SSRl EXCHANGER DUTLET c
;j A FIG li.2 lE FIG.ll.3 1A MnTE 1 M\,
@TE FR0u REACTOR COOLANT X{ . _ f
' M33 FILTER INLET / FRCu'TO PNS wSQ MnTE 1 WTE " '/ SYFtw rINianton 4 C. , BL0tD05% SYSilu
",* Y^, 2 SSR-14 p g pg g g( y
# O NDTE 1
'y: :
NOTE 4 w
" " ~
e -~ m e e - % e@ 6) @
- . RuP - , _ _ _ _ _ - _J 7
NIM y M TDF. gp __.. .. . l ry, P'c . _ $m'4" v L.g. 4
>< I SC2
~ ~
g ri , 3 r d kJ b J > TO Ll0010 g .-
- ; IA%TE SfSTEN C F!G 11 2I
/ii\' s in GASEOUS VENT U ' '
> A40 DRAIN SYSTEM FIG.9.3 3 2 l
X in 60LusE
@' M cf--isrii) CnNTa0t NOTE I im d 6
, Lu 4 s wa 6 a 6 4
d 6 s 6 db s 6 e 6 SC2 1 'l' I P P j f 1 I
) J J
/
A FIG.9 3.2 1A REACTOR PLANT SAMPLING SYSTEM PIR REFERENCE PLANT SAFETY ANALYSIS REPORT SIESSAR PI I35 , i: i U ' AufteDEEni 1793075
INSIDE INSIDE A ENT
++ ANNULUS Bull 0 LNG FR3B QSIL31 FRQ1 )
C ( RDEN AL l(N LEVEL fR08 U] EIDW41RS FIG 9 3 61A FIG.11 ORAIN A OR S AC WOTE 1 Mq rdCI A
' ' 4 Sp g SSR-8 ]
SC2 se NNS C I A }-, ,-{ REACTOR PLANT
. , COMPONENT U l 'Y l l COOLING WATERY [ " 3 g
FIG 9 2 2-1(TYP)Q NDTE 4 NOTE 4 7 0TE 4l Tl NnTE I SC 2 -*** kNS M L 3 [$$R 10, h0TE 1 W)TE 4 % SSR 3 :
's FROM ,
ACCUNULATORS ' ' NOTE I [$3p.4 % , tQ im -s M :: k SC2 >g 25
@)-
k6 1 1 '
,, = l ><4o-d! = a 1
.n 9 RHR E
{SSR 2 r 935-1 g NOTE I FRnu DEMINERAllZED o o I WATER SYSTEg ,_ ,, p Pi 9 FIG.9 1.3-1 10/FEON RE ACTOR) ' r' b mr w h 9 b Nr wh w pq r a PLANT CnEPONENT d ' ' ' d ' d ' d ' d 'd '
- COOLING
, , , i , ,
IATER , , 3 q q q ,q F I G. 9. 2. 2 -1 {r >' (TTP.0F 2) O SAIPLE $ TD HIGH LEVEL IASTE d ORAIN TANK pnTES: FIG Il 2-1 A
- 1. EQulPEENT SUPPLIED ST NSSS VENDOR.
- 2. TNIS SYSTEE 15 NON NUCLEAR SAFETT CLASS (NNS)
EICEPT IFERE OTHERWISE NOTED.
- 3. 50'.EN010 OPER ATED VALVES ARE SHOIN IN SARPLING P0$lTIDN.
- 4. THESE VALVES ARE OPEN DURING NORMAL PLANT OPERATION. ALL OTHER
- n c SOLEN 010 OPERATED VALVES ARE CLOSED DURING NORMAL OFERATION.
- 5. GENERAL REVISIONS HAVE BEEN HADE TO INCLUDE SEPARATE SAIPLING LINES, Lv d ADDITl0NAL SAMPLING POINTS, INSTRUEENTATION A00lil0NS, AND OTHER EINOR EC0lFICATIONS.
PLRIFICATICN FROM OUTLET OF WAREUF TANK INERALIZER OFB0 RATING CAS SPACE OUTLET DEMINERAllIERS NOTE I NOTE 1 NOTE I FRCY CESIUp FRCM HIGH FRCM LOW g j
"i REMOVAL ION EXCHANGERS
{ m LEVEL #ASTE CRAIN TANKS LEVEL WASTE DRAIN TANKS
!g
\w/
- SC2 FIG. 9.3.6-1 A \"/ FIG. 11.2-1A F I G . 11. 2-1 E hNS
{' SC2 FRCM LET00sN _y_ M LINE NOTE I a liAK ('R AH ) ([ArH M RI (k, , , / g"j YRWF#RWPjuF - viiM P s/ ^ g - - - " SAMPLE SC2 3 A-fil d
.T T < __ t, _ t _ .._ Y , ,
e TRlu C00LER
. PI EFFLUENT FIG. 11.3-1A p
A (TYP.0F 2) x - -
-x- o l ,, "
C b SC2 NNS 1 r GASEQUS WASTE I FIG. 11.3-1 N N E'S y TO R CIDACTI'iE _ _ _ g ri X '
, y LIQUIC WASTE 0 I*2'I y p; . TI ,
-{ j- J 'pi yl(y TO GASECUS VENT
- ANC DRAIN SYSTEM
'- NNS FIG. 9.3.3-2A
.Pl il , r{-
y l SC2 FI ' XM )( SSR19) TO DECAY HE AT 1PI l g .c PUWP SUCTION V7_ (PI) % 55R20 ) NOTE 1 3r ; TO PURIFICATION l pl' )(=)', SSR11) FILTER wr sw dr sw wr sw sw w- wr s u sr sw s
,r w
Yr s w
,r n
OV a 7 NOTE I ir r , r I r 1r 1 r 1 3 r 3r 1 1r 1 i t SAMPLE SINK TO PRl!I ARY ORAINS TRANSFER TANK TO HIGH LEVEL IIO' 0'3'3-2A NM WASTE DRAIN TANA FI G.11.2-1 A FIG. 0.3.2-1A REACTOR PLANT S W LING SYSTEP PWR REFERENCE PLANT SAFETT AN4 LYSIS REPORT . SIESSAR-Pl ' v ' Vs i BM AMENOMENT 28 8/6/75
i
! ppy r>=4 NNS FRC4 MAKEUP TANK CE CI A ;-- ; ,-" CIA- sATER SPACE NOTE 1 FRCM PRESSURIZER 6 ra
- 'i '
, STEAM SPACE Ssg7 " ' ' T 'y # lA NOTE I i f Mi a d- i b[,y ,) t m
s, q FRCM PRESSURIZER L10Ul0 SPACE NOTE 1 SSRB ,N - O
'y*, C h ~ [Q'l 4 CIA CIA ,r , 'T Q^/ '
CEBCR AT I NC-I r'-d CIA g DEWINERAllZERI k FRCM LETOCIN LINE
\
o b' ' _' w NEAR RC CCNNECTION SSR9 f [*] [ N -~ ,FRr# DECAY HEAT ' El 'E" NOTE 1 lRENCWALCOOLERSNOTEI 'd \ \ g][_i]O s 33 o SR-2 ( 4
-.'T
+.
u. SSR14M3HM ,L.
~
"5 FROM SriAM GENERATOR NNS 5 4 SC2 I
DRAIN LINE ,4 --i C l 2 ! FRCW CORE SC2 NOTE 1 o l d FLOD0 LNG bSSR.2)x f
~
- s44 -lP 6 T ANKS NOTE 1 y) in3 W- s NNS REACTOR PLANT ls $ '
5 N
~
C LN WATER SYSTEM (TYP.) INSIDE INSIDE CONT AI NWENT - A% ULUS IIG 9 2 2" ] d STRUCTURE l BullulNG m. . m P I ') vPl ; N/, PI ~ , PI ) .i PI ) PI i O v v v J - ir~ FRCM DEMINERAllZED { ( WATER SYSTEM I4 C FIG. 9.2.3-1
/
in<FROM REACTOR PLANT CCMPCNENT COOLING WATER 74 ff P. U 2 T w T m C n
=r wr ir ir O Wr dr sw dr sw sw su sw sw s & s w if if I I if i f 1 P if 1f M
NOTES:
- 1. ECUIPMENT SUPPLIED BY NSSS VENDOR.
V
- 2. THIS SYSTEM 15 NON-NUCLEAR SAFETY CLASS (NNS)
EXCEPT IHERE OTHERWISE NOTED.
- 3. AIR OPERATED VALVES ARE SHOIN IN SAllPLING l POSITION. ALL AIR OPERATEn VALVES ARE CLOSED DURING NORMAL OPERATION.
w . Gv l-
,mo ,RO, 01 a ,il .ASn GAS SeiDE c00tER
,RO. 1RI.
crez x x
. ,SSR-i2 i,Iln,
,. ,cR,,.DuuE1 DRAIN TANKS NOTE 1 EFFLUENT l NOTE I FIG.11.3-1A F I G .11. 2-1 E k ^
. FD Rm 1 7 I ^ OSa-i) rituR iNui
^y d ' t I
eni h
.s x , SSR-u i FRCM PURif. 10N
-< TO FRT
- Sn,,
1 tomR I OURET NOTE I h 2 ENERATOR
/- BLOWDCA CONSTANT #h
/ N l) 'M
- FIG.10 4 3-1 TEMPERATURE (if V 'k i
BATH
/ ' *y.Yy{
hs N M4Lb/ 3 @M,e _x ee W ____4-___ s m c-RS P
@P@@868 Ru RMP RWP RWP RWP RWP RWP RMP R R Rjt?
M mSQ("fW@Q6Q@s$99 u_,__ __a J r A A s R$. RS) (RT) RS RS) RT j V v' Y L _. __ ___ J r- - --J--' CELAV E j
+ -x-eg
+s 60 ai isn -.
r TEN O- ST F I G.11. 2 ' 3 es g . TO GASEOUS
' VENT & DRAIN V
SY STEM F I G. 9. 3 3-2 h SSR-11) TO dr dr dr dr 3r sr 1r 3r ~~ SU) VOLUWE sk s k s k s k J L sk dk s k CONTROL r i r i r i r i r 't ? 1 r j O F I G. 9. 3. 2-1 A I y - h g!cp REALTOR PLANT SAMPLING SYSTEM LEHL PWR REFERENCE PLANT WASTE SAFETY ANALYSIS REPORT ORAIN SWESSAR-PI TANK FIG.11.2-1A CE - ,-, o', _ uaJ AMEN 0 MENT 18 10/30/75
k lNSIDE CONT AINulNT*lNSIDE ANNULUS FRCW CESIUM FRCS HIGH I STRUCTURE l BUIL3ING REWQVAL ICN LEVEL WASTE FRCM PRESSURIZER 1 k - -[QA_j EACHANCERS ORAIN TAMS $ W @[Cl A_fN- M f N G.9. 6-{ Flyyl.2-}A
- g VAPOR SU'i W [_ v Q'N lI I _'I g
[C10 , SC2
, @^ i >, s Xf y
FRCM yugo issm--xC h
.s 1 ]
s x CIAf , rl-i CI AkA FRCu RCS
}
LOOP 81 NOTI 1 gjysg, .] T, TO REACTOR v 6', PLANT CCuPONENT
\' - '
COOLING IATER SYSTEN FIG.9.2.2-1 (TYP) a
' 1 Sg gggy lSSR-1 / XS ['*W h SC2 h NNS LINE NOTE 1
$ $R-2 ,' XN /M S E
- ' 4 GUARD Pur '
MINIFLDI 'd} LINE NOTE 1 lSSR-4e X$ /M - E Ek 4 y ye ye au y y
& 6 --O O '
FRCs DEMINERAllZED C 4 l i BATER hj SYSTEM FIG.9.2.3-1 I )( T0/FRCN I II - 4 COMPCNENT C COOLING C II Nr d ' kr d ' dr A Mr
^
kr d ' Er J' 1r wr d ' ' ' IATER F I G.9. 2. 2-18 1 r ' t y s r 1 r 1r i r < r (TYP OF 2) \ SAMPLE SINK NOTES:
- 1. EQUIPMENT SUPPilED BY NSSS VENDOR.
- 2. THis SYSTER 13 NON-NUCLEAR SAFETY CL ASS (NNS) EXCEPT THERE OTHERtlSE NOTED.
, -o r-t
._.l
J FRCW RADIDACTIVE LICulD FROM WASTE WASTE PLANT F ACM PRIM ARY DISCHARGE GRADE WATER TEST TANKS FIG.11.2-1E F I G.9. 2-7 -1 A
.F I G.11 2-1s, C
.s _
X X X X
,, ,r b
JA dk d b i If 1P 1t f SINK FI G.9. 3 2-1B REACTOR PLANT SAMPLING SYSTEM PWR REFEREhCE PLANT SAFETY ANALYSIS REPORT SWE SS A R -PI , I. I
, 1 ANENCMENT 13 63015
FROM BORON FRCW BORON FRCW BORCN RECOVERY TANRS TEST (ANRS CEWiNERAtlZ FIG. 9. 3.6-1 A F ~I G.9. 3. 6-1 A FIC.9. 3 6-1 v, , ,, s s X X X X : wr gr s r w r 9 7 db Jk A b d b d b if i r if 1r 1 r
\
SANI O v ,, TO SL SASTE AND DECONTAMINATION BUIING SuuP NOTES: , f
- 1. THis SYSTEM 11 NON-NUCLE AR SAFETY CL ASS (NNS). ~ ' ' , (.J
- 2. GENERAL REVISIONS HAVE BEEN MADE TO INCLUDE SEPARATE SAMPLING LINES.
A00lil0N AL SAMPLING POINTS INSTRUNENTATION A00lil0NS. AND OTHER ulNOR N00lFICAil0NS.
SYPTrM I!4Tr kFAL'M M)T fits - P E AC'IX)F PLAfiT SAAPLING SYSTFli (SSR) ID NO. RESAP-41 I< tS AP -3 S B-SAR 205 CESSAR SSR-1 Sample trom outlet to Sanple f rm RifR heat Sample irm outlet of D!l Sample from shutdown cooling I<!IR heut exchanqer no.1 exchanger no.1 outlet removal cooler HX1A trm loop 1 suction line from valve trom valve 1-9066A (Fig. 5.5-4) valve MVSA (Fig. 9.3-5) SI429 (Fig. 6.3-1A) g (Fig. 6.3-1 Sh 1) SSh-2 Sample from inlet to Sunple f rma FifR heat Sample from outlet of DH Sample from shutdown cooling RIIR heat exchanger no.2 exdianger no.2 outlet removal cooler !!X1B from loop suction line frm valve from valve 1-906bB (Fig. 5.5-4) valve MVLB (Fig. 9.3-5) SI445 (Fig. 6. 3-1 A) (Fig. 6.3-1 Sh 2) SSR-3 Sample t rm inlet to Saq)1e f rom accumulator NA Sample from safeguard pump 1 Elih heat exchanger no.3 tank no.1 from valve miniflow line tram valve trom valve 1-9066C 1-8933A (Fig. 6.3-1 Sh 2) SI465 (Fig. 6.3-1A) (Fig. 6.3-1 Sh 3) {' } SSR-b ) Sample from occumulator Sample from accumulator Sample from core flooding Sample from safeguard pump 2 yj tank A trom valve 1-8933A (Fig. 6.3-1 Sh 4) tank no.2 trom valve tanks through valve 1-8933B (Fig. 6.3-1 Sh 2) MV6 (Fig. 6. 3- 1) miniflow line from ralve SSh- L ) Sample irca accumulator Sample from accumulator NA NA pd tank B from valve tank no.3 from valve
. - >== 1-8933B (Fig. 6.3-1 hh 4) 1-8933C (Fig. 6.3-1 Sh 2)
C& SSR-bG m Sample f rm accumulator Sample f rosn accumulator NA NA
** 7 tank C from valve tank no.4 from valve
( 1-8933C (Fig . 6.3-1 Sh 4 ) 1-8933D (Fig. 6.3-1 Sh 2) p.w SSR-7 P""'" Sample of pressurizer Saq)1e of pressurizer Sample of pressurizer Sample of pressurizer steam from volve 1-8078 trm valve 1-8078 steam (Fig. 5.1-2) steam from valve RC238 (Fig. 5.1-1 Sh 2) (Fig. 5.1-1 Sh 2) (Fig . 5.1-3) SSR-8 Sample of pressurizer Sample of pressurizar Sample of pressurizer Sample of pressurizer liquid from valve liquid from valve liquid (Fig. 5.1- 2 ) liquid from valve RC210 1-8030 (Fig. 5.1-1 Sh 2) 1-8080 (Fig. 5.1-1 Sh 2) (Fig. 5.1-3) sSh-9 5 iple at reactor coolant Sample of reactor cool- From letdowr. line nea r RC Sample f rom RCS loop 1 sp no.1 trm valve ant loop no.1 from valve connection (loop A) from valve RC213
-8056 (Fig. 5.1-1 Sh 1) 1-8056 (Fig. 5.1-1 Sh 1) (Fig. 5.1-2) (Fig. 5 .1-3 )
SSh-10 Saqile of reactor coolant Sample of reactor cool- hA volume control tank gas loop no . 3 f r om va lve ant loop no.3 from valve sample from valve Cl! 104 O 1-8077 (Fig. 5.1-1 Sh 1) 1-8077 (Fig. 5.1-1 Sh 1) (Fig. 9.3.4-2) (~. ~ j SSR-11 heturn to volume cont r ol Return to volume control Peturn from sample system Peturn to volume control tank to valve 1-8306 tank to valve 1-8414 upstream of purification tank to valve CII 197 (Fig. 9.3-1 Sh 3) (Fig. 9.3-1 Sh 3) tilter valves V23A and (Fi g . 9. 3. 4-2) V23B (Fig. 9. 3-1) ( . FIG. 9.3. 2 - IC ( S H. l) ( ~1 REACTOR PLANT SAMPLING SYSTEM
% s PWR REFERENCE PLANT SAFETY ANALYSIS REPORT SWESSAR - Pl A M E NDMENT 29 10/29 re
FY L'T EM INTERFACE POINTS - P E ACTOR PLANT SAMPLING SYSTEM (SSR) ID NO. RESAR-41 FESAR-J B-SAR 205 CPSSAP SSR-12 Sample trcun letdown heat Saraple f rom letck)wn heat Sample from letdown line exchanger outlet trom Sample f rom purification exchanger outlet from of demineralizer prefilter filter outlet from valve valve 1-8217 valve 1-8372A from valve MVII (Fig. 9.3-1 Sh 2) OI353 (Fig. 4.3.4-1) (Fig . 9.3-1 Sh 2) (Fig. 9.3-1) Il SSR-13 Sanple of reactor coolant Sample of reactor cool- Sample ot purification Sample f rom purification tilter inlet /demineralizar ant filter inle=t/ outlet iron valve 1-8243 demineralizer outlet from filter inlet f rom valve demineralizer outlet valve MV30 (Fig. 9.3-1) QM 26 (Fig. 9. 3. 4 - 1) (Fig. 9.3-1 Sh 2) from valve 1-83721; (Fig. 9.3-1 Sh 2) SSR-14 Sanple of outlet of Sariple of outlet of Sample of outlet of Sample f rom purification boron themal boron thermal deborating deineralizers ion exchanger from valve regeneration regeneration from valve MV44 CH420 (Fig. 9. 3. 4 - 1) demineralizers from demineralizers from (Fig. 9.3-1) valve 1-7018 valve 1-7018 (Fig. 9.3-1 Sh 4) (Fig. 9.3-1 Sh 4) SSR-15 Gross failed fuel Gross failed fuel Sample of first two NA detector inlet (modi- detector inlet purification demineralizers fication Fig 9.3.5-1) (SWESSAR-P1 Fig. 9.3.5-1) at outlet from valve MV122 (Fig. 9.3-1) SSR-16 NA NA Sample of makeup tank gas NA space from valve MV60 (Fig. 9.3-1) SSR-17 NA NA Sample of makeup tank NA water space from valve MV63 (Fig. 9.3-1) SSR-18 NA NA Sample downstream of NA demineralizer prefilter from valve MV16 (Fig. 9.3-1) SSR-19 L 20 NA NA 1b DII/LP1 pumps suction NA through valves MV31A and i:V31B (Fig. 9.3-5) SSR21,22,23 NA NA Sample of outlet of NA deborating desnineralizers trom valves MV15A, MV15P, f, C'. - MV15C (Fig. 9.3-2) SSR24 hA NA Steam generator A sa:r'ple NA trom valves MV17Al und
, MV17A2 (Fig. 10.1-1) FIG. 9 3.2 - IC ( FH. 2) f %
REACTOR PLANT SAMPLING SYSTEM f PWR REF ERENCE PLANT SAFETY ANALYSIS REPORT ZW ESS A R - Pl AMENDMENT 29 10/29/76
SYSTI M INTERFACE IOI?CS - RE AL'POR PIRE SAMPLING SYSTEF! (SSb) ID NO. R E SAR -141 RESAR-3S Is-S AR 205 CESSAP LSR25 ta NA Steam generator B saltple NA valves MV17a1 and MV1782 lU (Fig. 10.1-1) l D C- -a FIG. 9.3.2 -IC ( SH. 3) REACTOR PL ANT SAMPLING SYSTEM PWR REFERENCE PLANT C '? S AFETY ANALYSIS REPORT t S AESSAR - Pi
.g AMENDMENT 29 10/ 2 9'76
}
=
; FROM CONDENSER FRCM CONDENSER HOTsELL FIG 80.4.1-1 TUBE SHEET FIG 10.4.1-1 r (TYP 0F 5) (TVP OF 12) b h i ?- >
r e, ( ,) M c h i
+ f' d
( CONOUCTIVITY SAMPLE PUMP s
>~
TO CONDENSER i'Ch CV' PCV
- HOTWELL FIG.10.4.1-1 U
/
s7 s N y + _ _ - f
.L 1 L J, L .L ,l. 3 A c. AAA i A A MECHANICAL REFRIGERATICN s s s ' s'
- s, O ' UNIT I
k
] -
/ g \_/
' s o -
m:.mj CATICN TO'FRGW TURBINE E X CH A NGE R PLANT CCMPONENT _ CE . 'Cl j-I q. AP) 7 l [AE 's (TYP) COOLING WATER
/,'AEN -
D F I G.10. . 9-1 I '- CE i [ 02 N yH ,
-, 1PH
-,I . p
- a. .
p n .,= .=ai a ' ' 1 r i r i r 1 r 1 r , ' ' ' ' ' - TO TURBINE BUILDING
' ' SUMP F IG. 9.3.3-1
-] ", g r, _]r, 3r FIG 9.3.2-2 SHEET I 0F 2 (PLE SINK TURBINE PLANT SA9PLING SYSTEM PWR STANDARD PLANT r,
SAFETY ANALYSIS REPORT f .ff } SWESSAR-PI (j y , Uv .) AMEN 0 MENT 12 6'16 75
FRCW CONDENSATE HEADER. BEFORE AND AFTER C0h0ENSATE POLISHING SYSTEN FEEDIATER HEATER NO. 1C F I G.10. 4. T-1 ( T Y P 0F 2.1 FEEORATER HEATER NO. 18 FRCW IST P0thT FEECsATER HEATERS DISCHARGE ! FEEDIATER HEATER NO. IA FIG.it.4.7-2 {' NAIN STEAM HEADER NO. 4 MAIN STEAM HEADER h0. 3 FRCW WA!h STEAW FIG.10.3.1-1ALB , NAIN STEAM HEADER h0. 2 TO FRCW 7 TURBlhE PLAhi MAIN STEAM HEADER h0. 1 CCMPCNENT r C00LlhG RATER l (TYP)
- flG 10 4 9-1 FRCW AullLI A'tY STE AM FIG.10.4.12-! }g FROM INDIVIDUAL [
) i's CONDENSATE DEMINERAll2ER
(# 4 EFFLUENT O { P3 F I G .10. 4. 6--I (TYP 0F 9) , O @ 'PR 4CV Q p' s X~C,Xfh E~,MC-a ~ Q ->- ==> -> -> -p T: ci l l l F
. A 5 ,
E R E E g g , g ., , , , . , , , s , A
' CCNSTANT TEMPERATURE BATH L '
s
, C'E 'CE] [ N CE C ~J CE s
, L ). )
.L -
.I M b, h TO TURBINE , , , , ,
~
EUILDING s SdWR -) [> -)[> -][> -][> yr
-] [> -) [> , ,
FIG,9.3.3-1 q , , r 3p i ,
\ / \ _s TURSINEPLANTSb i
I s N07r. Q TO TUR5lhE BullulNG SUNP l -
)
- TO TURBINE BulLCING SUWP , -
i THIS SYSTEW IS NON-hUCLEAR SAFETY CLASS FIG.g,3,3_1 Fig,g,3,3_, ;.,, _,t
- l. . ; ,.
(NNS). LOCAIED IN TURBINE Bull 0 LNG.
FRCW WAREUP AND DRAWOFF FIG.10 4 7-1 + b Ib
=
TO'FRCM TURBINE
# PLANT CCNPCNENT '[ [ [ COOLING IATER (TYP)
FIG.10.4.9-1 3 b 3'? h FIG.9.3.2 2 SHEET 2 0F 2 [ TURBINE PLANT SAMPLING SYSTEM PWR STANDARD PLANT SAFETT ANALYSIS REPORT SIESSAR-P1
, ,, ,, /O
() v I YU AMENDEENT ART 12 6/i6'75
FEEDsATER HEATER NO.1C FEE 0 TATER HEATER NC.18 FROM IST POINT FEEDIATER HEATER ORAINS FEE 0 TATER HEATER NO.lA ( - . ~ _ _ , FEE 08ATER HEATFR ' .1C FROM 2ND POINT FEEDRATER HEATER NO.28 FEECWATEP 4 H E AT E'1 t. I NS FEECWATER HEATER NO.2A FEE 05ATER HEATER NO.3C F FR M 3 0 POINT FEEDIATER HEATER NO.38 FEEDWATER HEATER NO.34 FEEDIATER HEATER NC.4C 1 RH ER 0 PS FEEDIATER HEATER NO.4A 0S S FEEDIATER HEATER NO.5C FROM 5TH POINT FEE 0sATER HEATER NC.5B FEE 0 TATER HEATERS ORAINS FEE 0 TATER HEAltR NO.5A FEECIATER HEATER NO.6C as ][ )[ FROM 6TH POINT FEEDIATER HEATER NO.68 FEEDWATER - HEATERS DRAINS FEEDIATER HEATER NO.6A AUXILIARY BOILER, AUXILIARY BOILER A BLO100fN - r 1r wr F I G.10. 4.12 - 1 AulillARY BOILER B f AUXILIARY BOILER
~
g FEEDIATER _
~
F I G.10. 4.12 -1 g #, AUllllART BOILER [ CONDENSATE 2'hh;' j( ?
~
,r R PLANT CCMPONENT s 7 COOLING TATER FIG.10.4.9-1 -)e -] h 3 h -) [* 3 h FEE 0 TATER HEATER
-' DRath SAMPLE PUMP FROM DEMINERAll2E0 'f 1 i 1 i '
i , IATER r FIG.9.2.3-1 ) NOTE:
- 1. THIS SYSTEM 15 NON NUCLEAR SAFETY CLASS (NNS). ,
LOCATED IN TURBINE BUILDING. J (; v i uv
1 VENT HEACER A - ____ _ s TO PROCESS
- VEP.T ELC*ERS di d i d '
FIG 11.3-1F PCn]N RACIDACTIVE SPENT hi: "ERY LIQUID RESIN SYSTt. #ASTE SURGE VENTS SYSTEy TAhn FIG 9.3.6-1 VENTS FIG 11.5-1 (TYP) FIG 11.2-1 (TYPy ( N ~,. TO HIGH LEVEL 1 4,3 ,, ,, , a,l, ' ' y LIQUIC *ASTE A h un TANAS FIG 11.2-1 M W m r m r q' , 3 ' n r d' d'- - d ' TO LCe LEVE, (U y' % LlGUIC *ASTE TANYS FIG.11.2-1 l L AM{ LS
- E" 4 LS 1AD-,LS SC 10 #AS. AC ~"
c ] v;g Y:B ; CECMTA W T m l l SUILDIN: i eq , g- c- 7
/ ';
tS - - - . t3 .. LS ,
- u. , I
~ ~ '
_.'-__ t l , e- ----,
.1 l ' i 1
I { , s. l l I I q-i q i q _., s ANNULUS SUILDING SUuPiTYP OF 2) FUEL AREA SUvP SOLID #ASTE AND DECONTAMINATION SUli9
. - . _ _ _ _ _ - . . _ _ . __ _ __ _ l___ _ _ ___
t f I i h , ' nATER CIRCULATld j DISCHARGE
-Si - 'Tr l
. . i
~
AS - A5 l
-..-_.RSH, C/
RI 8 F I C. 9. 3. 3 -1
<E -->
[ UUNI g AERATED VENT AND ORAIN SYSTEM l FWR REFERENCE PLANT SAFET7 At;ALYSIS REPORT SWESSAR-PI AWENCHENT 32 5 11 77 ' i, 7 */ ^)
!) f U V '"
INSICE ! INSICE CD$.TAIN"ENT - - > < A W LUS STRUCTCPE i SJILCINC LE~ fY
' m ,
m 2 Y% - V WS -H S Cc.' >4 ','. 5 a , t L (S I hL! $b
\_ ,' i _
WCB l M;B l l .. ., i l
's 1
LS'- 1.. l L S . _.
^ A s . .
\ i lh th ,
6
- P < ,- r- -
i 3 JLS } r _ _ _ 8 l
. - - 'si , .__
y
' I YC8 1 ; N , ,. , -
t l l i { - ( MCB ! r 3 _ _ H ! ( l SAFETY FEATURES AREA INCORE INSTRUPENTATION CONTAINWENT SUWP(TYP OF 2) SUPP (TYP) TUNNEL SUYP I .l. M( LS g '[' NCB g -
- l. I -
NOTES: - - 1 THIS SYSTEM 15 NON-NUCLEAR SAFETY (NNS) EXCEPT i L 1 WHERE OTHERilSE NOTED
- 2. BulLDING SUMPS TO RECEIVE JERATED EQUIPMENT -- -
AND FLOOR ORAINS. TURBINE SulLDING SUYP PUMPS (TYP 0F 2) , (; u j LU
CIA CIAh NyS VENT HEACER I TO RADIDACTIVE
- s g_ .j s GASECUS WASTE I sc2 7
F I G. 11. 3-1 NNS C2 SC2 Nyg , f, FROM RE ACTOR FLANT NITROGEN O
' ' 0~I , M REACTOR AND LM NTROL PLANT NITROGEN FRCM PRIMARY GRADE I (NSSS SCOPE)
WATER FIG.9.2.7-1
' ' , MI AL AND
_OGS _- 4_ jYOLUME CONTROL DGS -3 5, (kSSS SCOPE) FRCr R ACTOR COOL ANTI 0'
' VALVE STEM LEAK 0FFS
' ' DGS-54 I SY5 TEM (NSSS SCOPE) 0 ,
vn REACTOR PLANT U i r FROM RA010ACT!vE U O *
' , OUS RASTE Q CONFONENT i
hy t QGS-2l COOLING WATER F I G.9.2. 2 -1 y SUMP FIG 11.3-l! & 10 TO REACTOR COOLANT
.SUvP L .- ,
@ SYSTEM (NSSS SCOPE.I'p V REACTOR COOLANT I h FROM REACTOR PL ANT g 'M3 DRAIN TANK QA SAMPLING SYSTEM COOLER NT LX ( F I G. 9 .3. 2 -1 )
' ' PRIMARY ORAINS TRANSFER TANK i
v A b, r g o X F.C. X 1 r i PI Y. X- u 7 ); I CRAIN PRIMARY ORAINS TRANSFER PUMPS 1 r [ CIA j m . 3 TO RADIDACTIVE 7' -- F' " s GASEQUS WASTE FIG. 11.3-1 NNS -5l4- SC2 SC2 ->4-- NNS I INSIDE INSIDE CONTAINMENT ->+- ANNULUS STRUCTURE Bull 0 LNG FIG. 9.3.3- 2 A GASEOUS VENT AND CRAIN SYSTEM PIR REFERENCE PLANT SAFETY ANALYSIS REPORT SNESSAR-P1 I _. m f < iy; i v aa AMENDMENT 12 6/1675
i n b, r z_ CHEMICAL AND
/\ VOLUNE CONTROL l0GS-3.5 6y >
N SYSTEM ~/
~~
(r4SSS SCOPE)
N/ VALVE STEW _
REACTOR COOL ANT LEAK 0FFS SYSTEM (NSSS SCCPE) MCB &>E y;g 37 1, e w Uv F> " REACTOR C00Lt CRAIN TANK ta REACTOR COOL ANT ' DGS-1 SYSTEtt f X'G M (NSSS SCOPE) l 0 GS -51. 52.53,55) : C DGS-56 ) :
; X ACCUMULATORS #
(NSSS SCOPE) DGS-57 / REACTOR C00LAN DGS-5B)
%.n.
~ : en .n .r .
5 'a d h ; ,rQ,
- 1. THIS SYSTEM lS NON-NUCLEA) SAFETY (NNS) EXCEPT WHERE DlHER11SE NOTED.
i ,, p 3 UGt VuI
CIA CI A h 6 VENT HEADER NYS I I TO RADIDACTIVE X s
,_ ; y-s GASECUS 8ASTE FRCW RE ACTOR f,4: ' PLANT NITROGEN FR0u CHEulCAL S
- b FIG. C.5.8-1 AND VOLtuE CONTROL 'N r, u OR FROM PRIMARY GRADE I TROGD (NSSS SCOPE) 5ATER FIG.G.2.7-1
[ 0GS -4546M : EQUIPMENT ORAINS f FROM CHEMICAL an0 N UE3-4 VOLUME CONTROL (NS$S SCOPE)
, FROY R{ ACTOR C00L ANil 10GS-37 THRU 43 %
' 0GS~3 : VALVE STEM LEAK 0FFS x
$YSTEN (N355 SCOPE) 4 ;
sm FRON RA010 ACTIVE s e~ lREACTORPLANT 1 ' r #, g7 43 d d CCuPCNENT s 4 i r
' ' GASECUS BASTE SYSTEW
\ DGS-2} COOLING IATER LS 9 '[\ F I G.11. 3_1 A & 10 t TO REACTOR COOLANT flG 9 2 2-1 SCEP SUNP
@ SYSTEu (NSSS SCCPE y L--
/
Vh3REACTOR CRAIN TANK COOLANT h I V(L T] y, r llV
/
FROM REACTOR PL ANT
% SAMPLING SYSTEM g COOLER u21-X (' ,, PRlW ARY CP AINS (IlG.9 3.2 O TRANSFER TANK O
fA % Y M ) h F.C. ~X~f 1r l Pi "% M l' CM X I .NT CRAIN PRIEARY ORAINS iPS TRANSFER PURPS 1 r i CIA 1,
. m s TO RA010 ACTIVE m - . ry -
- s GA$EOUS BASTE FIG. 11.3 1 NNS SC2 SC2 -De- NN1 ,
IN!!n! IN110E *e i' o s /I T CONTAINEENT ->4- ANNULUS -t. tj STRUCTURE Bull 0 LNG FIG 3.3.3- 2A GASEOUS VENT AND DRAIN SYSTEM PER REFERENCE PLANT SAFETY ANALT311 REPORT Sff$$AR-P1 g3S (k I ' -' } ANENOMENT 17 9 '30'75
4 I 3 4 5 I a . - FROM REACTOR ' PLANT NITROGEN FIG 9.5.8-1 CHEulCAL AND , .
/\ YOLUME CONTROL DGS E Tucu 9e -
SYSTEM y (NSSS SCOPE) E
\/ VALVE STEM ;
REACTOR COOLANT LEAK 0FFS SYSTER (N!!$ SCOPE) RCB h , ugg y Mrv,!F*< REACTOR CC CRAIN TAW
=
REACTOR COOL ANT OGS-1 ) K SYSTEM (NS$$ 3 COPE) DES-51 THRU 54 f h 7 DGS-55 THRU 58) r ACCU 5ULATORS (NS$$ SCOPE) REACTOR COO TANK P
- l. THl3 $YSTER 13 50N-400 CLEAR $4FETT (NNS) EICEPT WHERE 01HERIl5E NOTED. ,
Ubi bV
VENT HEADER g TO RADIDACTIVE GASEQUE L j IASTE FIG.11.3-1 d 6 NMS $RS-1 ! GASEOUS VENTS X " (NSSS SCOPE) [fEKOF$ FROM REACTOR g PLANT N1TROGEN XMj, (FIG.9.5.8-1) ( O GS-12-21. 2 7 GASEOUS ORAINS GASEOUS RELIEFS d i (NSSS SCOPE) (NSSS SCOPE)
;f FROM RADIDACTivE MCB h DGS-33-55 )
y , , .] 1 gg,p GASEQUS WASTE SYSTEM (FIG.11.3-1 AL10) OLS FROM REACTOR PLANT kk V A- LT ;
+< sagPLING SYSTEk (FIG.9.3.2-1)
MCB PRIMARY ORAINS TRANSFER TANK PI
>X-X
(-
._Q
>w x( ' , ,
PRIMARY ORAINS TRANSFER PUMPS r TO II:10 ACTIVE GASEQUS -, p'y gl Q{ j
' I '
/ IASTE FIG. 11.3-1
} /"h M t NNS fUUa L'*
OE g FIG. 9.3.3-2A GASEOUS VENT AND DRAIN SYSTEM PER REFERENCE PLANT SAFETY ANALYSl5 REPORT (SSAR P-1 ,
), , G' W //
r I 6 CIAIUlil < a r, _ r FR05 REACTOR PLANT NNS-DySC2 SC2
) NITROGEN FIG. 9.5.8-1
/ PRESSURIZER RELIEFS VRS-2,3,4 4 C xVRS-7'8 ANO VENTS (NSSS SCOPE) 1 DHR RELIE7S GASEQUS VENTS (NSSS SCCPE)
(NSSS SCOPE) \ (DGS-28.29.56.57 'f E ACTOR COOL ANT Q uCB M(0 GS-1,2, 26. 30. 3 I SYSTEM . 37 (NSSS SCOPE) g y EC8'
' 1
' s -Q l 0 h MCB y ,s = Q BCg s
FROM PRIMARY
.AmR
' O, 0 GRADE WATER
$ X ,- y FIG.9.2.7-1
~
' REACTOR COOLANT TS h uCB- l/
ig
- g ,
ORAIN TANK V L--> RE ACTOR COOL ANT DRAIN TANK / p
, C00LER ,
REACTOR COOLANT dN , wx / W l STSTEM OGS-3-9 f ; (NSSS SCOPE) 1 r CORE FLOODING (N $$ SCOPE) N
\
Mb REACTOR COOLANT ORAIN h1 r, 7 TANK PUIPS NHS SC2 SC2 I INSIDE -p+l CONTAINMENT A STRUCTURE B NOTES:
- 1. THis SYSTER IS NON-NUCLEAR SAFETT (NNS)
EICEPT IHERE OTHER11SE MOTED..
, , -- p3 Uu i Ue I
VENT HEADER TO RADIDACTIVE CASE 0VS aASTE FIG. 11.3-1 y a FRCW REACTOR x VRS-1-6 N 74 PLANT NITROGEN (FIG.9.5.8-1) GASECUS VENTS
- VALVE STEM LEAK 0FFS (NSSS SC0PE)
GASECUS REllFFS GASE0VS ORAINS S18-29 ' (NSSS SCOPE) 16 's (NS35 SCOPE) OGS30 45 : FRCM RAO'0 ACTIVE
/M 3 r T , ,
2 y V MCB Supp FIG. 11.3-IA L 10 I , l -M L S ('LT r f'
] ,;g FRCM REACTCR PLANT PRIMARY ORAINS ; SAMPLlhG SYSTEM TRANSFER TA (FIG.9.3.2 1)
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I
- CI A . i l CI A ,
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REFUEllNG (FIG.9.5.B-1) FAILED FUEL VRS24 DETECTOR YENT ( Om
.,, _ FRCM PRIMARY 1 6 9 r, - GRADE WATER FIG.9.2.7-1 1r FROM REACTOR l '
DRAIN TANK __ (NSSS M PE) \ i i 0 J, l! 't . REACTOR PLANT
-I $ f COMPONENT COOLING RAT
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^! {} , b
EYE).M I tq} P_ FEE POIN*S - G AS LOUS VE NT (VPS) AND DFAIN SYSTEM l Q H IIJ No. PETAF 41 PFSAP-3S n-SAR 205 Ct. :S AR 16S1 Fr om pr es s ur e nellet tank firtan pressure rellet tank inop lb Th drain trom P ea ct or coolant dr a in t ank to reactor coolant drain to reactor cu)lant drain valve MV -2 5 (Fig. 5.1-2) pump suction f rom reactor tann purap trom valve tank pump f rtan valve cuolant drain tank upatream ;g 1-8031 (Fig. 5.1-1 Sh 2) 1-8031 (Piq. 5.1-1 sh 2) of valve CH560 (Fig. 9. 3. 4 -3) DGS2 From react or coolant drain Frore reactor molant dr ain Reactor vessel head from reactor coolant drain tank heat (*xchanger t o tank heat exchanger t o gasket drain trm valve tank heat exchanger to re-pressurizer relief tank pressurizer relief tank MV-22 (Fig. 5.1-2) actor t oolant drain tank spray downst ream of check spray downstream of check spray (Fig. 9. 3.4-3) valve 1-804b (Sht.i' dAP - P 1 valve 1-8046 (1,N ESSAR-P 1 na>dif ication Fig. 5.1-1 mdificat ion Fig . 5.2-1 Sh 1) Shl) DGS3 From reactor coolant pump heact or vessel tlange Pressurizer sur ge line NA Seals from valve 1-8159A leakott from valve 1-8032 drain from valve MV20 (Fig. 9.3-1 Shl) (Fig 5.1-1 Sh 1) (Fig. 5.1-2) ILS4 from outlet ut e x ce'ss From outlet of excess let- Steam generator SG1A t ube tus letdmm heat exchanger down heat exchanger tr(su side drain f rcan valve MVSA f rm valve I-8190 valve 1-8143 (Fig. 9.3-1 (Fig. 5.1-2) (Fig. 9. 3-1 Sh 1) Sh 1) DC5 h om reactor coolant pump NA St eam generator SG1B tube NA 2 seal trarn valve 1-81598 side drain tre valve MVSB (Fig. 9.3-1 Sh 1) (Fig. 5.1-2) EUS t> & 7 From reactor molant pumps From reactor coolant pumps Feactor coolant loops NA 3& 4 seals from valves 1& 2 seal ledkott t rarn 1Ai & 1A2 TC drains from 1-8159C & D (Fig. 9.3-1 valves 1-8518A & B538B valves MV3A1 & MV3A2 Sri 1) (Fig. 9.3-1 Sh 1) (Fig. 5.1-2) LAS8 & 9 tus Frcan reactor coolant pumps Reactor coolant loops NA 3&4 seal leakott trom 1B1 & 1B2 TC drains from valves 1-8538C & 1-8538D valves MV3b1 & MV3B2 (Fig. 5.1-2) se DGS10 & 11 i . tm NA wre f looding tanks T1.1 & NA 79 T1B from valves MV6A & [M] LJD MV8B (Fig. 6. 3 - 1) DGS12 ts NA NA Batch controller flush Chemical addition tank sh f rom valve MV36 outlet strainer drain trom (Fig. 9. 3- 1) valve CH309 (Fig. 9. 3.4 -2) m DGS13 & 14 t .' NA NA NA NA
- r. m.
O DG 15 b-A a. NA NA NA NA 19 D w te. ML , , Boron analyzer flush NA
'i == # w ar m".A F IG 9 3 3 - 2 8(SH 1) 6" GASEOUS VENT AND DRAIN SYSTEM D P A R RE FERE NCE PLANT CJ gwzamu SAFE T Y ANALYSIS REPORT
.l $4 E SSAR - P t
_ ;.x AMENDMENT 29 10/29/76
'. v idi INTERFACE POTNTS - GMaudS VENT (VPS) AND DRAYN SYSTtN (NS)
ID No. FESAR 41 RFSAR-3S D-SAR 205 CESSAR trom valve MV117 (Fig. 9. 3- 1) DGS17 NA NA NA NA DGS18 NA NA NA Volume control tank dlain from valve 01117 (Fig. 9.3.4-2) DGS19 NA NA NA NA DGS20 NA NA Core flooding tank bleed Purification and deborating from valve MV5 (Fig. 6. 3-1) ion exchanger drains trun valves CI!379, C11390, and 01399 (Fig. 9. 3. 4 - 1) DGS21 NA NA Auxiliary addition line NA from boric acid pumps flush from valve MV65 (Fig . 9.3-1) DCS-22 NA NA NA Accumulator test line drain from valve S1461 (Fig. 6 . 3 - 1 A) DGS23 NA
] NA NA NA DGS24 (.. . ,M NA NA NA hA 21 t.
DGS25 V NA NA NA Charging pump 1 drains and leakage trom valves Ch317 (c _7
~ and 01329 (Fig. 9. 3.4 -2) g, cc1 DGS26 ,,. - M NA NA Reactor coolant pump Charging puap 2 drains and r"' "J] P1A1 seal leakage leakage f rom valves 01320 r n-2 r> (Fig. 5.5-8) and 01332 (Fig. 9.3.4-2)
DGS27 f M NA NA Boron analyzer reliet Charging pump 3 drains and b[# reliet valve RV6 leakage from valves 01323 DGS28 & 29 r-"" NA NA (Fig. 9. 3-1) DlfR trains A & 11 suction
& Of336 (Fig. 9. 3. 4 -2)
NA ^ rellets f run reliet valves a RVSA & RV5B (Fig. 9.3-5) 21 DGS30,31 & 32 NA NA Peactor cx>olant punps Chargi.aq pump reliet tram PIA 2, P181, & P1B2 seal relief valves 01315, 01318,
--) J enkage (Fig. 5.5-8) & GI321 (Fig. 9. 3.4 -2) 29 J
DGS33 NA NA Reactor coolant pump seal Irtdown reller t rom r elief FIG 9 3 3 - 2B(SH 2) GASEOUS VENT AND DRAIN SYSTEM PWR REFERENCE PL ANT SAFETY ANALYSIS REPORT S W E SSAR-P l AMENDM(NT 29 IQr29ns
SYSTF#. INTEFFACE POISTS - GASFOUS VENT (VRS) AND DRAIN SYSTIN (ICS1 ID No. RESAR 41 PESAR-3S H-SAR 205 CESSAk return line reliet from val: CH345 (Fig. 9.3.4-1) reliet valve RV4 (Fig. 9. 3-1) DGS34 PA NA letdown line relief from letdown reliet trum relier relief valve RV1 valve Cf!354 (Fig . 9. 3- 1) (Fig. 9.3.4-1) DGS35 & 36 ECCS suction reliefs IIom NA Seal return cooler reliefs LPSI reliets from reliet reliet valves 1-90511. & from reliet valves RV8A & valves S1439 & SI449 1-9051b (Fig. 6.3-1 Sb 1&2) RV8B (Fig. 9. 3-1) (Fig. 6.3-1) DGS37 ECCS suction relief trora EX'CS suction reliefs trom Boric acid pump P4A IIPSI reliet frta reliet reliet valve 1-9051C relief valves 1-8858A & discharge reliets frm valve SI409 (Fig . 6.3.1 A) (Fig . 6.3-1 Sh 3) 1-88585 (Fig. 6.3-1 Sh3) reliet valve kV-26A (Fig. 9.3-4) 21 DGS38 NA RIIR-SIS relief s irm Boric acid pump P4B IIPSI reliet from reliet relief valves discharge reliefs trom valve SI417 (Fig . 6.3.1 A)
**f'] 1-8842, 1-8856A, & 1-8856B relief valve RV26 bsus n (Fig. 6.3-1 Sh 3) (Fig. 9. 3-4)
-m DGS39 db j ta SIS-RifR reliefs from Demineralizer pretilter IIPSI relief trm reliet Fu relief valves 1-8851, reliet from relief valve valve SI472 (Fig. 6. 3.1 A) 1-8853A, & 1-88538 EV5 (Fig. 9.3-1)
(Fig. 6.3-1 Sh 3) {rg DGS40 6 41 7 d hA 4 na NA DIl <x>oler reliet s from reliet valves RV4A & RV4B Shutdown cooling drain line reliefs from rellet valves Q)
.mus (Fig. 9.3-5) SI166 & SI179 (Fig. 6.3.18)
V LC*
" NA Dl! pump sur*. ion reliefs Shutdown cooling drain line
[M Ot;S4 2 & 43 NA from reliet valves RV7A reliefs from relief valves
& RV7B (Fig. 9.3-5) SI189 & SI468 (Fig. 6.3.1B)
DGS44 LA NA DH pumps to auxiliary Reid;ing water storage spray line rellet trom tank return line relief from relief valve EV2 reliet valve S1407 CN (Fig. 9.3-5) (Fig . 6.3.1A) CN Volum control tank reliet m keup tank liquid level Volume control tank 1ellet x 'y DGS45 Volume control tank relief from relict valve from relief valve 1-8120 reliet from reliet valve from relief valve CH115 1-8332 (Fig. 9.3-1 Sh 3) (Fig. 9.3-1 Sh 3) RV3 (Fig. 9. 3 - 1) (Fig. 9.3.4-2) DGS46 NA G arging pump suction line Nkeup & purification to NA c% Dl! pump suction r elief from J[ relief from reliet valve 1-8124 (Fig. 9.3-1 Sh 3) relief valve RV6 (Fiq . 9. 3-5) FIG 9 3 3- 29(SH 3) O - GASEOUS VENT AND DRAIN SYSTEM PWR REFERENCE PL ANT SAFETY ANALYSIS REPORT SWESSAR-PI AMENDMENT 29 f o/2 9/76
6 SYSTFM INTERFACE POINTS - GASEDUS VFNT IVRS) AND DRAIN SYSTE}l (DGS) TD No. FESAR 41 PESAR-35 B-SAR 205 ff.SLAR DGS47 M MA Auxiliary spray line relief NA from reliet valve RV3 (Fig. 9.3-6) A;S 48,49 6 50 NA NA Deborating demineralizer M reliefs trosa reliet valves RVIA, RV1B, & RVIC (Fig. 9.3-2) DGS$1,52 6 53 heactor coolant lwgis 1,2, Reactor coolant loops 1,2, Purification demineralizer NA
& 3 loop drains from 63 loop drains f rom valves relief s trc.za reliet valves 1-8058A, 1-80588, & 1-8058A, 1-8058B, & RV2A, RV2B, & RV2C 1-8058C (Fig. 5.1-1 Sh *) . 1-8058C (Fig . 5.1-1 Sh 1) (Fig. 9.3- 1)
DGS54 Reactor vessel flange Reactor coolant loop Purification filter F2A hA leakoff from valve 1-8032 drain from valve 1-8058D relief from relief valve (Fig. 5.1-1 Sh 1) (Fig. 5.1-1 Sh 1) RV7A (Fig. 9. 3- 1) DGS55 Reactor coolant loop Accumulator tank I drain Purification tilter F2B NA 4 loop drain f rcza valve from valve 1-8955A relief f rom relief valve 1-8058D (Fig. 5.1-1 Sh 1) (Fig. 6.3-1 Sh 2) RV7B (Fig. 9.3-1) DGS$6,57,& 58 Accumulator tanks A,b, Accumulatur tanks 2,3,6 4 DHR drop line reliefs from NA
& C drains from valves drains frua valves 1-C9558, reliefs trun reliet 21 1-8955A, 1-8955B, & 1-8955C, & 1-8955D valves RVBA & RV8B (Fig. 9. 3-5) 1-8935C (Fig. 6.3-1 Sh 4) (Fig. 6.3-1 Sh'2) (DGS-56 6 57 only)
VKS1 Volune control tank vent Volume control tonk vent MJ eup tank vent from Volume contzol tank vent from valve 1-PCV-115 tram valve 1-PCV-115 valve MV59 (Fig . 9.3-1) valve CH100 (Fig . 9.3.4-2) (Fig. 9.3-1 Sh 3) (Fig. 9.3-1 Sh 3) VkS2 & 3 NA NA Steam generators SGIA & NA SG1B tube side vent from valves MV10A & MV10B (Fig. 5.1-2) VRS4 88aM NA NA CRDM vents trara valve NA MV24 (Fig. 5.1-2) D VRSS & 6 -
') NA NA NA NA ) VRS7 'hh- NA NA Pressurizer reliet and NA safety valve discharges frora valves RVIA, RV1B,
(., q--
- RV2, & MVIS (Fig. 5.1-2) ,
C-~ VRS8 NA NA Pressurizer vent t rcan hA ' ' "1~ 'Q valve MV16 (Fig. 5.1-2) s ba -% FIG 9 3 3 - 2B(SH 4) b M> GASEOUS VENT AND DRAIN SYSTEM 6 PWR REFERENCE PLANT
)M SAFE TY ANALYSIS REPORT SWESSAR-Pl A u t N Dut NT n 10 /2 9/76
SYSTtJ1 INTEkFACE POI?rrS - GASEOllS VENT (VRS) AND DRAIN SYSTEN (DGS) ID No. RFSAR 41 RESAh-3S li-SAR 205 CESSAF VRS9 thru 23 NA NA NA NA VES2 I4 NA NA NA Prom refueling failed Iuel detector vent VkS25 Pressurizer relief tank Pressurizer relief tank NA Peactor coolant drain tank vent at nozzle to/irom vent at nozzle to/from vent at nozzle before ECS-MOD 2 (SW 2;SAR-P 1 RCS-MOD 2 (SWESSAR-P1 valve CI!540 (Fig . 9.3.4-3) Fig. 5.1-1 Sh 2) vig. 5.1-1 Sh 2) 79 i Os c:,
]
FIG 9.3.3 - 28(SH 5) [' GASEOUS VENT AND DRNN SYSTEM PWR REFERENCE PL ANT SAFE TY ANALYSIS REPORT SWESSAR-PI AMENOMENT 29 10/29/76
FROM RE ACT,0R COOL SYSTEM ANT - - - - ]
~L
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< - ? 4 0k
= a-0 lA 5 a V V
-h TO RADIOACTIVE GASEOUS WASTE SYSTtiM I, = (FIG. l l . 3-1) w c 5 -
r FROM RADIDACTIVE GASEOUS WASTE SYSTEM (FIG.l l . 3-l ) n 8 t 7'l-Lcv-il2A TO BORON RECOVE RY SYS T EM
= t -----
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=
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- o. l RESAR DESIGN -41 SWESS AR-PI DE SIG N
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- o I
b h5 VOLUME 3 CONTROL l l TANK g L___J FI G. 9.3.4 -1 (SH.1) CHEMICAL AND VOLUME CONTROL SYSTEM MODIFICATION PWR REFERENCE PL A NT S AFETY ANALYSIS REPORT e-e' A , SWESSAR-P1 af s
- 6; , C 2)
AMEND MENT 8 3/28/75
RES AR- 41 DESIGN -; ; SWESSAR-Pl DESIGN lcvcs-m tvns ,;) VENT TO RADIOACTIVE GASEOUS l- PCV-Il5 WASTE SYSTEM (FIG.ll.3-1) c r RE VISED RES AR-41 DESIGN DESIGN l _ REVISED FROM CVCS l LE T DOWN (FIG.9.3-1 RESAR- . 41 DESIGN SH. 3 )
/
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+
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)
.' r X cvcs- *(csN-tmM) X h CONTROL TANK FROM l- 8319 REACTOR PLANT G AS SUPPLY SYSTEM NNS- : SCE
( N2 ) ( FIG. 9. 5. 8 -1) , I , v ~s FROM
- X l-8316 X b( SP N-'
ER/ RADIOACTIVE GASEOUS WASTE SC5 : SC2 SYST EM (FIG.ll.3-1) FIG. 9.3.4 - 1 (S H. 2 ) cs " CHEMICAL AND !- VOLUME CONTROL -: TO SYSTEM M O DIFIC ATION p.U M P PW9 REFERENCE PLANT _., SUCTION S AFETY AN ALYSIS REPORT '{ } SWESSAR-Pl CSWESSAR-P 1 REVISED RES AR -41 W DESIGN D E SIG N ( FIG. 9.3-1 SH. 3 ) AMENDMENT 8 3 /28/75
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*t " #3
, e SAMPLE MANUAL g [ COOLER FLOW SHUT-OFF N/ METER VALVE TO CHEMICAL AND Y ys n h VOLUME CONTROL SYSTEM g L._I (FIG. 9.3 - 1, SH EET 2)
ISOLATION ' DETECTOR FLOW VALVES 3/8 TUBING ^
) It COf L DELAY TIME TO GRAB 60 SECONDS TO SC2 ][ SAMPLE I
DETECTOR NNS l CONNECTION l (FIG.91?-l) REAC'C3 Ft. ANT COM PONE NT COOLING WATER telG. 9. 2.2- 1 ) FIG. 9.3.5 -I cs GROSS FAILED FUEL c, DETECTOR MODIFICATION
'1-PWR REFERENCE PLANT SAFETY ANALYSIS REPORT c, SWESSAR -Pl c,
L; - W AMENDMENT 8 3/28/75
FROM REACTOR CCOLAn. - g ~~ SYSTEM
~]
l IP l-8421 I CVCS FI LT E RRC S l A i i = _ l a ~I )7 W l o " Y l-8422 m - E e.1 l
- m o
= = _____J m $2 O Eh $ l V
E = TO R ADIOACTIVE GASEOU3 WASTE SYSTEM
' ( F I G . 11. 3 - l )
z k3 wo i FROM R ADIOACTIVE GASEOUS WASTE SYSTEM [f J (F IG 11. 3 - 1 ) h t7 LC V -Il2 TO BORON RECOVERY SYSTEM
~
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o _ m h l REEAR DESIGN3S -~ SWESS AR-PI DESIGN 4 ) ( F IG. 9.3- 1 g e I SH.2 ) as w u l e _ l 1 r-L , j VOLUME
! CONTROL TANK ll L _ _ _ _J F IG. 9.3.4 - 1 (S H. I )
CHEMIC'4L AND VOLUME CONTr50L SYSTEM MODIFICATION PWR REFERENCE PLANT SAFETY ANALYSIS REPORT SWESSAR-Pl W-3S , 0"< u v 'r AMENDMENT 17 9/30/75
S W E S S t. R -Pt REVtSED RESAR-3S
.r RESAR-3S e.-> R E S A R-3 S e4 DE SI G N DESIGN DESIGN DE SIGN VENT TO GASEOUS (cyggtw3-i!] g Fhaf t CVCS VENT E DRAIN L E T DOW N(FIG.9 3-1 SY S T E M (FI G 9. 3.3 - 2) l- P CV-ILS SH 3) g 9
l l b cycs-*tssse-nos)
' VOLUME l
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FROM PURIFICATION DEMINERALIZERS MV30 I SR U l RADIOACTIVE SYSTEM (FIG.11. 3 - 1) GASEOUS I WAS l CVCS-GNS-3)) V54 ; l i l l I I 25 l V56] h l l l l(CVCS-MOD I l J j l l D h l l 1 L________ _ _ _ t _ _ ql l l l CVCS-MOD 2 / g l Vl8 l
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!----------------j DEMINERALIZERS MV33 TO PURIFICATION FILTERS B-SAR 205 r SWE S S AR-PI DESIGN DESIGN FsO. 9 . 3. 4 -l (SH.1)
CHEMICAL AND VOLUME CONTROL SYSTEM MODIFICATION PWR REFERENCE PLANT SAFETY AN ALYSIS REPORT SWESSAR-Pl B E. W bU/ Lv/ AMENDYENT 19 !2 /12 / 7 5
SWESSAR-P1 Fig. 9.3.4-1 (sheet 2) is deleted. 29
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1 o o E E W O FIG. 9.3.4 - l (S H. I ) CHEMICAL AND VOLUME CONTROL SYSTEM MODIFICATION PWR REFERENCE PL ANT SAFETY ANALYSIS REPORT SWESSAR-PI C-E h[, O ,' } AMENDMENT 9 4/30/75
SW ESSAR - PI _~ _ CE SSAR DESIGN ~ DESIGN VENT TO GASEOUS (CVCS-GWMS-6 VENT E. DRAIN = N pq SYSTEM (FIG 9. 3. 3 -2) CHIOO TO REACTOR F L AN T (CVCS-GWMS -71 Q-- SAMPLING SYSTEM 4 X REVIS E D (FIG 9. 3. 2 -1) CHIO4 CFSSAR CESSAR DESIGrf _ _ DESIGN CESSAR DESIGN FROM CVCS
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GASEOUS WASTE SYSTEM SC3= rSC2 (FIG. 11. 3 - l) m SWESSAR- P ~ = REVISED CESSAR DESIGN CA DESIGN (FIG. 9.3 4-2) TO CHARGING
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CVCS FIG 622-1 CHl26 i, BORIC ACID BATCHING CESSAR EDUCTOR SWESSAR-P1 DESIGN = = DESIGN ir ., - TO REFUELING (FIG 9 34-2) d6 j,, CHI 73 SHUTOO*N TANKS q (CVCS -MOD-13
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TO/FROM F U E L POOL PURIFIC ATION SYSTE M SYSTEM MODIFICATION TO CHARGING PWR REFERENCE PL ANT ' PUMP COMMON S AFETY AN ALYSIS REPORT ' SUCTION SWESSAR-Pl C C-E AMENOMENT 9 4/30/75
SYSTEM INTERFACE POINTS TO CHEMICAL & VOLUME COffrROL SYSTU4 (CVCS) ID Mo. CESSAR CVCS-1 Boric acid makeup pump recirculations to boric acid tank from valve CH647 (Fig. 9. 3.4-2) CVCS'2 Boric acid makeup pumps suction from boric acid tank to valve CH532 (Fig. 9.3.4-2) FIG. 9.3.4 -1 ( SH. 4 A ) CHEMICAL C VOLUME CONTROL SYSTEM MODIFICATION PWR REFERENCE PLANT SAFETY ANALYSIS REPORT SWESS AR - Pl C-E 66, G ;) AMENDMENT 10 5 /15 / 7 5
SEAL INJECTION F ILT ERS-- - * ]I 3_ % D-22] RWT RECIRCUL ATION - FIG 9 3 3-2 LINE---*,, RELIEF HP COOLER DR AIN b* F ILT E R CVC S- MOD- 20) VENT SIS---~~*N (CVC S- MOD-2 3 f - ~ ~ ~ ~ ~ ~ - - ~ - ~ ~ F I G. 9. 3 3 - 2 REACTOR b *M-- CH456
-----l L OO P - - - - + - l CESSAR SWESSAR-PI DR AINS l l DESIGN = = DESIGN FIG 9 3 4-3 F IG. 93.3-2 REFUELING l
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RELIEF VALVE L _ _._ __ _ '.J . l I 1 I R _ _ _ ,_ _ _ _ _ _ _ w _,4 p CH560 a I A I I I l 0> I cx 0'I FIG. 9.3.4-1 (SH. 5) FIG. 9.3.3-2 - . CHEMICAL AND VOLUME CONTROL SYSTEM MODIFICATION PWR REFERENCE PL ANT SAFETY ANALYSIS REPORT SWESSAR-Pl C-E AMENDMENT 23 3/ 31/ 7 6
FROM CH@ CHARGING PUMPS M :: : CH-524 REGENE R ATIVE HEAT EXCHANGER TO LETDOWN - O _- CONTROL VALVES L OWN CH-523 CH-516 CH-515 8 CH-230P
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$YSTEM INTERFACE POINTS - m)FON FECOVEFY SYSTEM (bF S)
ID No. RESAh-3S PESAF-41 B-fM 205 CESSAR LRS-1 To boron recovery To boron recovery From volume control From chemical and volume mntrol from SIS occumulator from SIS accumulator system downstream system valve C1500 (Fig. 9.3.4-2) test, valve 1-8963A test valve 1-8963A of valve V18 (Fig. 6.3-1 Sh 2) (Fig.5.3-1 Sh 4) (Fag . 9.3- 1) 29 BRS-2 From chemical und From chemical and N/A Prom chemical and volume mntzul volume control system volume control system system valve CH330 (Fig. 9.3.4-2) RC letdown to boron RC letdown to boron recovery irm valve recovery from valve 1-8420 (Fig. 9.3-1 Sh 2) 1-8323 (Fig. 9.3-1 Sh 3) BKS-3 N/A Thermal regeneration N/A N/A demineralizer to boron recovery syst m from valve 1-7051 (Fig. 9.3-1 Sh 4) BRS-4 From chemical and Prom chemical and N/A N/A volume control system volume control systema RC letdown f rom down- RC letdown f rom down-stream of valve 1-8433 stream of valve 1-8347 (Fig. 9.3-1 Sh 3) (Fig . 9.3-1 Sh 3) bks-5 From boron remvery From boron recovery From boron recovery 'Ib chemical and volume control syst m to boric acid system to boric acid systm to concentrated system valve 01127 (Fig. 9. 3. 4-2 ) tanks from upstream tanks frcun upstream boric acid storage or valve 1-8456 of valve 1-8410 tanks upstream of (Fig. 9.3-1 Sh 5) (Fig. 9.3-1 Sh 5) valves MV231A & B (Fig. 9. 3-4) l29 o C .x
' d FIG 9 3 6-19 BORON RECOVERY SYSTEM FWR REFERENCE PLANT SAFETY ANALYSIS REPORT C; SAESSAR - P1
(' J AMENOMENT 29 10/29/76
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SWESSAR-P1 9.4 AIR CONDITIONING, HEATING, COOLING, AND VENTIIATIOh SYSTEMS Heating, ventila ting , and air-conditioning systems are providec in the control building (Section 9.4.1) , annulus buildina (Section 9.4.2) , solid waste and decontamination building (Section 9.4.3) , turbine building (Section 9.4.4) , containment structure (Section 9.4. 5) , and fuel building (Section 9.4.6) to maintain the temperature and humidity within the required limits. The s-pplementary leak collection and release system (SLCR S , Section 6.2.3.1) is used tor filtration of exhaust air in all contiguous areas of the containment during a DBA and for filtration of the exhaust air of the fuel building during tuel handling activities it required or a fuel handling accident. The only safety related ventilation systems are f or the control bu ilding , the containment structure, and the SLCRS. Control building HVAC systems are safety related to maintain control room habitability (Section 6.4) during all conditions. The containment structure cooling system is saf ety related because it is part of the containment heat removal system (Sect ion 6.2.2) . The SLCRS is safety related because it is used to mitigate the consequences of accidental releases of radioactivity. The remainder of the ventilation systems are not safety related and are used only to maintain temperature and occasional ly humidity conditions in various buildings, to control the radioactivity level in the containment, to transport air from g uncontaminated areas to potentially contaminated areas and then to the ventilation exhaust, to minimize buildup of airborne radioactivity in the buildings, and to reduce radioactivity released to the atmosphere. The ventilation systems meet the criteria of Regulatory Guide 8.8, C.3.1 and C.3.j, as discussed in Section 12.1. Airflow within the annulus, solid waste and decontamination, ruel, and turbine buildings shall generally be from areas less likely to have airborne contamination to areas more likely to have contamination. Airborne contamination in all plant areas shall be as low as practicable and ventilation systems shall be designed with a minimum of approximat ely one air changeper hour. g Some. local recirculation of air is planned due to the nature of the design, which incorporates unit air coolers in conjunction with once-through airflow. In general, several adjacent cubicles are serviced by a single unit cooler with air being exhausted from each such group of cubicles. Specific design bases for airborne radioactivity are described in Se ction 12.2.
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\) V t i O 'i 9.4-1 Amendment 17 9/30/75
SWESSAR-P1 Fig. 9.4-1 is a composite drawing of the reactor plant ventilation systems. Table 9.4-1 lists all plant ventilation systems and their modes of operation. Interface Requirements 30 3.-SAR-205 ventilation syst, 7 interface requirements are addressed in Table 9.4-2. 9.4.1 Control Building Ventilation Systems The function of the control building ventilation aystems is to remove equipment heat, ventilate, and maintain personnel comfort in the control building and the electrical tunnels. Emergency outdoor air filter units maintain positive room air pressure in the control room area during the design basis accident (DBA) . The systems are shown in the following figures: Control Rcom Air Conditioning 9.4.1-1 Control Building Refrigeration Equipment 30l Room Ventilation 9.4.1-2 Control Building Air Conditioning - Chilled Water 9.4.1-3 Emergency Switchgear and Safety Related 30 Cable Spreading Area Air Conditioning 9.4.1-4 Neutral Cable Spreading Room Ventilation 9.4.1-5 Electrical Tunnel Ventilation 9.4.1-6 Diesel Generator Room Ventilation 9.4.1-7 9.4.1.1 Design Bases All subsystems except the electrical tunnel ventilation subsystem, the control room toilet and kitchen exhaust subsystems, the neutral cable spreading room ventilation subsystem, and the diesel generator normal ventilation subsystem 30 shall be Safety Class 3, Seismic Category I and shall be protected against tornadoes . The electrical tunnel ventilation, control room toilet and kitchen exhaust, and the neutral cable spreading room ventilation subsystems are NNS. The diesel generator normal ventilation subsystem shall be NNS but seismically supported and anchored so as to maintain structural integrity during seismic events. The duct systems shal) be designed to withstand abrupt pressure change due to the tornado characteristics described in Section 3.3. Fig. 9.4.1-8 shows a detail of a missile protected duct hood. The individual system design bases are: bt lv j 9.4- 2 Amendment 30 1/28/77
SWESSAR-P1 Control Room Air Conditioning
- 1. The control room air conditioning system shall maintain ambient temperature of 75 F and relative humidity below 60 percent in all rooms served by the system.
- 2. The capability shall be provided to isolate the entire control room floor area from outside contaminated atmosphere in the event of any one of the containment isolation phase A (CIA), smoke, or chlorine signals. During control room isolation, the control room pressure shall be maintained at 0.25 inch W.G. above atmospheric pressure by means of clean outdoor air supplied by an emergency outdoor air filter unit to prevent the infiltration of potentially contaminated outdoor air.
Control Building Refrigeration Equipment Room Ventilation The control building refrigeration equipment room ventilation subsystem shall maintain a maximum room temperature of 110 F 30 including accident conditions. Control Buildino Air Conditioning - Chilled Water,
- 1. The control building air conditioning - chilled water system shall supply chilled water (40 F supply and 50 F return) to the cooling coils of the air handling units.
- 2. The system shall operate during all modes of plant operation.
Emergency Switchgear and Safety Related Cable Screading Area Air Conditioning
- 1. The emergency switchgear and safety related cable spreading area air conditioning subsystem shall maintain the ambient temperature of approximately 80 F in the emergency switchgear cable spreading areas during normal plant operaticn and not more than 104 F during emergency modes of plant operation.
- 2. An independent purge exhaust and supply subsystem shall remove smoke and CO2 from the areas. 30 Neutral Cable Spreading Room Ventilation
- 1. The neutral cable spreading room ventilation subsystem shall maintain the ambient room temperature above 50 F in winter and below 110 F in summer.
- 2. Outdoor air shall be used to ventilate, to cool the room, and to remove smoke and CO2.
.o?
) ;t b U0 9.4-3 Amendment 30 1/28/77
SWESSAR-P1 Electrical Tunnel Ventilation
- 1. The electrical tunnel ventilation sdbsystems shall ventilate the tunnels and remove smoke and CO2 from the + unnel (s) .
- 2. Outdoor air, neither heated nor cooled, shall be supplied to maintai n the exhaust air temperature below 110 F.
Diesel Generator Room Ventilation 30 1. The diesel generator room ventilation subsystem shall ventilate the room and remove smoke from the room. 30l 2. The ventilation subsystem shall maintain the room temperature at 50 F in winter and below 120 F in summer when the diesel generator is in operation. During the normal standby condition, the room temperature shall be maintained at 50 F in winter and below 104 F in s u. une r . 9.4.1.2 System Design 30l Table 9.4.1-1 lists each control room area and gives the maximum and minimum air changes per hour for each area. Control Room Air Conditioning (Fig. 9. 4 .1 - 1 ) The control room air conditioning system serves the control room, instrument rack room, computer room, office, kitchen, and the fan rooms. Table 9.4.1-2 provides a description of operation of the control room air conditioning system. The system comprises air 30 conditioning units, and charcoal filter banks with related booster fans, ducts, dampers and controls. Normally, one air conditioning unit recirculates the mixture of the control room return and outdoor air through 80 percent efficiency filters based on the National Bureau of Standards (NBS) Dust Spot Method on Atmospheric Dust, cooling coils, and electric heating coils to maintain design ambient conditions in the rooms. The fans maintain the control room at a slight positive pressure during normal operation. During a DBA, outdoor smoke, chlorine, or other toxic gas conditions, the outdoor air and the exhaust air isolation butterfly valves are closed and the control room floor area is 30 pressurized to a minimum of 0.25 in. W.G. relative to outside by one of two 100 percent control room pressurization systems to prevent infiltration of radioactive and hazardous chemical contaminants. The air for the control room pressurization system is taken from one of two air intakes located approximately 180 degrees apart. (/- ~n: s iv/ 9.4-4 Amendment 30 1/28/77
SWESSAR-P1 Each of the remote air intake flow paths has two valves in series in the control building that are normally open. If subsequent to a DBA, chlorine, or other toxic gas conditions, one of these remote intakes is not available (valves closed due to airborne cc atamination) and one valve from the other intake fails to open, the valve will be mai.ually opened with a handwheel. The estimated time to implement this manual action is less than 5 ndnutes . To implement this requirement for manual action, the design specifications and installation of the valves conform to the following criteria:
- 1. Since the remote air intake valves are normally onon, manual operation to open a valve is not required more than once following a DBA or similar events.
- 2. Adjustment or realignment of other parts of the system is possible from the control room with the tailed valve in a tixed position.
- 3. Control room instrumentation is provided for clear indication and annunciation of valve malf unction.
4 The purchase specification for valves will require the identification of valve components as to which are considered internal (nonrepairable) and which are external (repairable) . These will be designed as follows:
- a. Internal valve components (that are dif ficult to repair manually without opening ductwork) will have the lowest practicable probability of failure.
- b. External valve components (including motors and power supplies that are assumed to be repairable or removable) will be designed to ensure that the failed valve component can be bypassed easily and safely and that the valve can be manipulated into an acceptable position. The components will be isolated from other equipment to assure that the repair operations do not result in further equipment failure.
- 5. The location and positioning of the valve permit easy access from the control room for convenient repair, especially under DBA conditions.
- 6. Plant operations are the responsibility of the Utility-Applicant. However, Stone & Webster will recommend periodic manipulation of the valve by control room operators f or training purposes and to verity manual operability of the valve. c
<, , iuU 9.4-5 Amendment 30 1/2b/77
SWESSAR-P1 The location of the air intakes is site-related; however, the following factors shall be considered when selecting the location of the intakes: fh
- a. Location of toxic gases and any flammable liquids and gases stored on the site and chemicals shipped on routes near the nuclear plant snall be considered. The distance to any potential source shall be as far as practical.
- b. The intakes shall be located 90 degrees away frcm the direction of the prevailing wind.
- c. The air intakes shall be located sufficiently far from the station structures to avoid buildiag wakes and to prevent potential recirculation due to buildin, walls.
- d. The remote air intake structure and the air duct (approximately 15 in. diameter) connecting this structure with the control room shall be protected against tornado and seismic forces. In addition, the air duct which runs below ground shall be an airtight structure, protected against corrosion and external forces caused by equipment moving above. The location and description of the remote air intake and connecting ducting are site-related and are discussed in the Utility-Applicant's SAR.
Each control room pressuriza tion system consists of a 2,000 cfm (approx) centrif ugal f an, a demister, an electric coil, a roughing filter, a carbon adsorber and two high efficiency particulate air (IEPA) filters, one upstream and one downstream of the carbon adsorber. Each roughing filter is rated for 80 percent efficiency, as determined by the NBS dust spot test. The roughing filter is of water and fire resistant design UL (Underwriters ' Laboratories) Class 1. The carbon adsorbers are of the gasket-less nontray type to reduce problens encountered during adsorbent replacement. The carbon adsorber is designed for a flow velocity of 40 fpm to give sufficient residence time (0.25 sec/2 in. bed depth). Two inches of charcoal bed is sufficient for iodine removal as discussed in Section 9.4.2.2; an additional 2 in. is provided for additional capability, which may be required for weathering and aging. The impregnated carbon is of a typo which has been demonstrated to be capable of removing in excess of 99.5 percent of methyl iodide (CH3I) and 99.9 percent of elemental iodine under entering conditions of 70 percent relative humidity. Anticipated operational pressure surges do not affect the carbon adsorbers. Each " PA filter is capable of removing at least 99.97 percent of the o micron or larger particles which impinge on the filter. r au , C , is , 9.4-6 Amendment 30 1/28/77
SWESSAR-P1 The HEPA filters are of water and fire resistant design (UL Class 1) . Control Building Refrigeration Equipment Poom Ventilation (Fig . 9.4.1-2) Each control building refrigeration equipment room is served by a 30 separate ventilation saLsystem. Ea ch ventilation subsystem consists of a fan and filter with 25 percent efficiency as determined by the NBS dust spot test and an air exhaust fan with modulating air dampers and controls. Control Building Air Conditioning Chillod Water (Fig. 9 . 4 .1 -3 ) Two 100 percent control building air conditioning chilled water systems supply chilled water to the related cooling coils. 30 Each system consists of one 100 percent capacity water chiller of the centrifugal compressar type, one 100 percent capacity chilled water pump, one 100 percent capacity condenser water pump, an open expansion tank, piping, and controls. The condenser water pump is used to eliminate a difficult start-up situation during the winter operating conditions. Emeroencv Switchgear and Safety Related Cable Spreading Area Air Conditioning (Fig. 9.4.1-4) The emergency switchgear and safety related cable spreading area air conditioning system serves emergency switchgear rooms, safety battery rooms, safety related cable spreading rooms, and 30 emergency switchgear air conditionina equipment rooms. The system consists of air conditioning units, the battery room air exhaust fans, air dampers, ducts, electric coils, and controls. The mixture of the emergency switchgear and safety related cable spreading urea return air and the outdoor air is recirculated by an air-conditioning unit through a 25 percent efficiency filter, as determined by the NBS dust spot method, a cooling coi.1, and the electric heating coils to maintain design conditions in all rooms served by the system. Each battery room exhaust fan is of the sparkproof design with a i capacity based on not less than five battery room air changes every hour. Neutral Cable Spreading Room Ventilation (Fig. 9 . 4 .1 -5) 30 The neutral cable spreading room ventilation system consists of an air handling supply unit, return fan air ducts, and controls.
/ , ', a 9.4-7 Amendment 30 1/28/77
SWESSAR-P1 The air handling supply unit consists of a supply fan, a 25 percent efficiency air filter, as determined by the NBS dust 30 spot test, heating coil, and two position and modulating air dampers. Electric Tunnel Ventilation (Fig. 9 . 4.1 -6) Each electric tunnel in the control building is served by an independent air supply and exhaust system. A portion of the supply air for the neutral tunnels is provided by an additional 30 air supply system located in the normal switchgear build ing . Outdoor air is delivered by a supply f an a t one end of each tunnel and discharged at the other end by an exhaust fan. Diesel Generator Room Ventilation (Fig. 9. 4 .1 -7 ) Each diesel generator room has a separate ventilation system consisting of the primary, supplementary, and normal ventilation subsystems. The primary and supplementary ventilation subsystem for each room consists of a primary supply fan, a supplementary supply fan, outdoor air, return air and exhaust air modulating primary dampers, two position supplementary dampers, ducts, and controls; and operates when a diesel generator is running. The normal ventilation subsystem consists of an exhaust fan and related ducts and operates during normal diesel generator standby condition. An independent air handling unit is provided for each room 30 housing electrical equipment associated with each diesel generator.
- 9. 4 .1. 3 Desion Evaluation 30 Air-conditioning and ventilation systems provide a controlled environment in the control building. Ambient design temperatures for various control building areas ensure operator safety and comfort, and acceptable performance of con trol equipment under both normal and emergency conditions.
In the event of a fire in the control building (a ref rigeration equipmen t room, an emergency switchgear room, an emergency switchgear a;r-conditioning room, a cable spreading room, an 30\ electrical tunnel) the applicable air-conditioning or ventilation system will be isolated or shut down. The related fire dampers or the outdoor dampers will close, so that no pathway will exist for the entry of smoke or toxic gases into the control room. Redundant radiacion monitors, chlorine and smoke detectors in all outdoor air ducts of the control room air-conditioning system, and smoke detectors in the return ducts of all control building 9.4-8 Amendment 30
.1 1/29/77 l , iii
SWESSAR-P1 uir-ccnditioning and ventilation systems detect and alarm the pre",once of radioa ct ivity , chlorine, or smoke. Administrative procedures will be used to advise control room personnel of a toxic gas condition. Under these conditions, control room wolation procedures are initiated manually upon smoke alarm or automatically by radiation monitors and chlorine detectors, and th e pressurination systems are activated manually or automatically, thus maintaining a positive pressure within the control room. Automatic startup of the pressurization system
\30 reduces the time duration, for which the control room is without pressurination, to the instrument response time only.
Automatic chlorine detectors are quick acting. The combined toiponse time or the detectors and isolation valves is less than 10 secor.ds. Due to the wide separation of the redundant emergency outside air intakes, radioactivity, chlorine, noxious gases, or other contaminants present in the site vicinity are prevented from entering the control roon by automatic isolation of the air intake that is contamin a ted. 'I h e air conditioning units and their associated controls at the control room and the emergency switchgear ar.a safety related 30 ca bl e spreading area are tully r ulundant and are powered from two independent emergency electrical buses as protection against a single tailure. The only portions of these systems which are not redundant are some ducts shared by two 100 percent capacity tans and individual room air reheat coils with their related instrumentation. 30 The air reheat coils with their related instrumentation are not essential during DBA conditions because they are provided only for personnel comfort. This equipment maintains constant room temperature regardless of variations in heat load resulting from ditterent moden of plant opera t ion . Reheat coil controls are selected tail sute. Should nonredundant equipment fail, the space temperature of the affected room may drop below 75 F, but not below 65 F. The control room pressurization system which takes noncontam inoted outdoor uir trom one of two independent remote air intakes and nasses it through one of two redundant charcoal filter trains to ensure clean air to the control room and a provision for an emergency control room breathing air system (Section 6.4.1.2) provide full satety to personnel during air particulate or hazardous chemical releases. When required under accident conditions, a portion at the room air is recirculated to decrease airborne radioactive contaminant concentration in the control rcom. 90arate ventilation ..ystems are provided for each control i iu11 ding refriceration equipment room an6 each diesel generator room. The selection of separate ventilation systems satisties 30 the single railure criterion since each ventilation system is 9.4-9 7
, ,.. Amendment 30
(., , , ,c 1/28/77
SWESSAR-P1 powered from the same emergency generator serving the equipment 30 in the room. Through 100 percent system redundancy, loss of any one system caused by loss of its associated ventilation system f does not prevent the total system from performing ita intended safety function. Redundant components in the air conditioning, ventilation, and chilled water systems are installed in separate rooms to prevent d single internal event from rendering more than one redundant system inoperable. l Independent subsyc cm purge capability is provided for all l control building areas. The electrical tunnel ventilation systems are required only during normal plant operation (see Section 8.3.1. 4.4) and are thus HNS. 30l The control room area volumes are shown in Table 9.4.1-5. The consequences of component failure are listed in Table 9.4.1-3.
- 9. 4 .1. 4 Testing and Inspection All control building air conditioning, ventilation, and chilled water systems will be tested and inspected for air balance, water balance, and completeness of installation.
Control foom Pressurization Systen Initial performance verification and periodic surveillance tests will be conducted to ensure operability and performance of all control room pressurization systems to the stated ef ficiencies. HEPA filters will be tested in accordance with proposed ANSI Standard N101.1 " Efficiency Testing of Air Cleaning Systems Containing Devices for Removal of Particulates." Charcoal adsorber banks will be leak tested using a halogenated hydrocarbon in accordance with test procedures described in "USAEC Report ORNL-NSIC-65, 1970" by C. A. Burchsted and A. B. Fuller, " Design, Const ru ction , and Testing of High Efficiency Filtration Systems for Nuclear Applications." Charcoal filter banks will also be tested in accordance with
" Standardized Non-Destructive Test of Carbon Beds for Reactor Containment Applications" by D. R. Muhlbaier, DP-1082, July 1967.
The charcoal adsorbers contain test cells that are removed annually in accordance with Regulatory Guide 1.52 (Section 3A.1-1.52). Water Chillers The water chiller rotors are subjected to an overspeed spin test and static and dynamic balancing. The water sides of the heat h 9.4-10 Amendment 30 3
. . . 1/28/77 7 i' ,
(,; I iJ
SWESSAR-P1 exchangers are pressure tested in accordance with ASML III, Class 3. Material certification for all parts subjected to pressure is required. The chiller package is capacity tested prior to acceptance. Operating chillers are observed daily for color, level, pressure, and temperature of the oil, condenser water inlet and outlet temperature, chilled water inlet and outlet temperature, and refrigerant vapor temperature in the condenser. Machine operating hours will be metered. Performance data will be recorded in a log book. This record reflects machine performance and also permits the operator to determine: (1) the progressive fouling of heat transfer surfaces (2) the progressive increase or decrease of inert gases present in the condenser The water chiller units will be rotated every three months. Prior to rotating the units to active s ta tus , the following routine is followed:
- 1. Check filters and driers.
- 2. Check Freon level.
- 3. Clean contacts on inactive unit starters.
- 4. Remove dust and dirt from control panel enclosures and any open motors.
- 5. Check all safety and operating controls for the proper settings.
Calibration data and records will be maintained. A Freon sample from each machine will be analyzed annually for moisture content. Fans The fan impellers are subjected to an overspeed spin test and static and dynamic balancing. Every f an is given a shop running test at free delivery. A performance test or manufacturers' certified ratings in accordance with Air Moving and Conditioning Association (N+CA) standards are required. Material certification for f an shaf t and impeller is required. Operating fans will be checked periodically for unusual vibration and high bearing and motor temperature. Instrumentation indicates functional operation of the system. The fan units will be rotated every three months. Prior to rotating the units to active status, all bearings are lubricated as required. V-belt 9.4-11 Amendment 30 1/28/77
/ r. 3 1 e
(I b / 1 l '"
SWESSAR-P1 drives, when used, are checked for alignment and worn belts are replaced. Drives, pulleys, belts, couplings, hubs, and blades will be checked for alignment and tightness. Air Handling Units The air handling unit impellers will be subjected to an overspeed spin test und static and dynamic balancing. Every air handling unit will be given a shop running test. The cooling coils will be hydrostatically air pressure and leak tested. A performance test or manuf acturer's certified ratings in accordance with AMCA or Air Conditioning and Refrigeration Institute stand ards are required. Material certification for fan shaft, blade, and cooling coil is required. Operating air handling will be checked periodically for unusual vibration and high bearing and motor temperature. Lastrumentation indicates f unctional operation of the system. Prior to rotating the units to active status, all bearings will be lubricated, V-belt drives will be checked for alignnent, and worn belts will be replaced. Chilled water coils will be checked for leaks. Drives, pulleys, belts, couplings , hubs, and blades will be checked for ulignment and tightness. Pumps The control room chilled water pumps require inservice testing as specified in Section 16.4.2. Operating and standby components are alternated periodically to verify operability of all equipment. Valves All valves in the control room chilled water system require testing as specified in Section 16.4.2. 9.4.1.5 Instrumentation Applications Instrumentation in the control room monitors control room radiation levels, and chlorine, smoke, and radiation levels of all fresh air supplies to the control room. It initiates automatic isolation of the control room if allowable limits are exceeded. Air flow failure for all fans, high room temperatures, high pressure differential across filters, chilled water system malfunction, and control building fire detection systems are alarmed in the control room. High differential pressure alarms re Provided across air filters. The control room operator has 30 the capability of selecting the least contaminated supply air 9.4-12 Amendment 30 4 - 1/28/77 i ,J
SWESSAR-P1 intake, bypassing supply air to either of the redundant standby air filters, manual operation of the air handling and chilled water systems, and operation of the fire protection systems. The duct thermostats of the control room and emergency switchgear und saf ety related cable spreading area control the cooling coil control valves. The room thermostats of the control building refrigeration equipment room ventilatior. systems modulate outdoor air, return air, and exhaust air dampers to maintain temperatures within thermostat demands. The tunnel thermostats operate the related supply and exhaust 3 fans as required to maintain tunnel temperature limits. Euch water chiller is started manually or automatically by a standby room thermostat, either in the switchgear room or the control room. Each chiller with its associated thermostat is powered by a a separate emergency bus. The chilled water thermostat installed in the chilled water supply line to the system modulates compressor inlet vanes to maintain the chilled water temperature within thermostat demands. Each standby room thermostat is wired to its associated chiller and is also connected to an air handling unit piped to the chilled water system. The diesel generator room thermostats modulate outdoor air, return air, and exhaust air dampers; sta rt summer fans when diesels are operating; and open summer exhaust air dampers when the cutdoor temperature is above freezing to maintain room temperature within the thermostat's demands. 9.4.1.6 Interf ace Requirements Design of the remote air intakes provided by the Utility-Applicant shall be in accordance with Section 9.4.1.2. 9.4.2 Annulus Building Ventilation System The function of the annulus building ventilation system is to provide a suitable environment for personnel and equipment, and to prevent the spread or release to atmosphere of airborne radioactive material. The ventilation system is shown in Fig. 9.4.2-1 and the principal component design and performance characteristics are given in Table 9.4.2-1. 9.4.2.1 Design Buses The design bases of the annulus building ventilation system are: in, / 4 i J 9.4 -12 A Amendment 30 1/28/77
SWESSAR-P1
- 1. The supply air shall be heated in winter and cooled in summer to maintain indoor temperature at approximately 80 F in open areas and below 104 F in the cubicles.
- 2. The engineered safety feature areas are safety related and shall maintain room temperature normally below 104 F and not more than 120 F during a DBA.
- 3. The electric tunnels shall be cooled with outside air to maintain tunnel temperature below 110 F during normal plant operation.
- 4. Air flow within the annulus building shall be from noncontaminated areas to potentially contaminated areas to maintain the airborne radioactive concentrations as low as practicable
- 5. The exhaust air from the building shall be bypassed or filtered in the event of high radiation prior to ventilation vent discharge.
- 6. The supply and exhaust subsystems capacities are sized so that the exhaust flow rate shall be greater than the supply flow rate, thus maintaining a slightly subatmospheric pressure within the annulus building.
- 7. During a DBA, the supply and exhaust ventilation subsystems shall be stopped on receipt of a CIA signal.
At the same time the exhaust fan of the supplementary leak collection and release system (SLcus) shall be started to maintain a partial vacuum in the annulus building. The SLCRS is described in Section 6.2.3.
- 8. Local connections shall be provided to exhaust ducts for connection of portable ventilation equipment to be supplied by the Utility-Applicant for additional decontamination capability and for periods when normal air flow patterns may be disrupted.
(. ., i/ 9.4-12B Amendment 30 1/28/77
SWESSAR-P1 8 The annulus building ventilation system shall be classified as nonnuclear safety (tmS) , with the exception of the building isolation air dampers which shall be Safety Class 3 (SC 3) . The local unit coolers in the engineered saf ety f eature and charging pump areas shall be Safety Class 3 (SC 3) . 9.4.2.2 System Design The annulus exhaust may be discharged to 'he aunosphere tiltered or unfiltered (Fig . 9.4. 2-1) . The annulus exhaust system includes a two-speed filter bypass fan and three parallel 50 percent capacity fan-filter trains. One of these three trains, which can serve the solid waste and decontamination building , the fuel building, the containment building, or annulus building when required has a two speed motor to handle the 14 different air flows required by the individual buildings. Each filter bank includes an electric heating coil, prefilter, a carbon adsorber and two high ef ficiency pa rticulate air (HEPA) filters (one upstream and one downstream of the carbon adsorber) . The prefilters have a minimum filter efficiency of 80 percent as determined by the National Bureau of Standards (NbS) dust spot method. The carbon adsorbers are of the gasket-less nontray type to reduce problers encountered durina replacement. The carbon adsorber is designed for a flow velocity ot 40 rpm to give sufficient residence time (0.25 sec/2 in. bed depth) . Two inches or charcoal bed is sufficient for iodine removal and an additional 2 in. is provided for additional capability which may be required for weathering and aging. The impregnuted carbon is of a type which has been demonstrated to be capable of removing in excess of 99.5 percent of methyl iodide (CH31) and 99.9 percent of elemental iodine under entering conditions of 70 percent relative humidity. Anticipated operational pressure surges will not af f ect the carbon adsorbers. The HEPA filters have a ninimum 111ter efficiency of 99.97 percent when filtering particulates that are 0.3 micron or larger. The choice of a 2 in. charcoal adsorber bed is based on results from experiment s done at reported ambient background concentrations of stable methyl iodide and stable elemental iodine, which are about 1 ugm/m3 and 10-* ugm/m3, respectively( x ) ( 2 )( a ) . These concentrations are 10* to 1010 times greater than the ventilation flow concentrations equivalent to the 15 mRer'T thyroid dose to a child discossed in Regulatory l14 Guide 1.42 etion 3A.1-1.4 2) . Since the concentration of unstable icJine is much less than that of stable iodine and because charcoal cannot distinguish between the stable and unstable io dine , the relevant inlet iodine concentration is the background concentration. The background concentration for methyl iodide is 106 tir.es greater than the 10-6 ugm/m3 value where Pence (1) reported a sudden decrease in the methyl iodide filter ef ficiency for 9.4-13 i 4 a O', i i o Amendment 14 7/18/75
SWESSAR-P1 velocity, or filter bed residence time. C 5 ) The magnitude of the
- gradient, dE = f (W) ,
dc where E = filter removal ef ficiency c = inlet concentration W = face velocity, decreases with decreasing face velocity. Present charcoal filter design has a f ace velocity of 40 fpm. For 50 fpm, Pence reported a decrease in the filter efficiency with decreasing inlet concentration of a f ew percent filter ef ficiency over 9 decades of low inlet concentration (<1 ugm/M3) . In addition, within the range of inlet methyl iodide concentra-tions, 1 MPC to 1010 MPC 10CFR20, which includes both the background concentration and Pence's concentration effect; FortadoC*) reported that his experimental and theoretical work showed no concentration effect; Ritzman(5) reported there is no experimental or theoretical knowledge to support such an effect; and Bellamy(6) reported that the methyl iodide filter efficiency increases with decreasing inlet concentration. Within the above range of inlet concentrations for elemental iodine, RitzmanC S) again reported that there is nothing to support a concentration effect and Bellamy's(6) experiments showed no effect. Iodine is removed from the gas phase by physical or chemical adsorption on the surface of the charcoal. Elemental iodine is removed predominately by physical adsorption and methyl iodide by chemical adsorption (the methyl iodide reacts with the impregnant on the surface of the charcoal) . The relationship between the amount of iodine adsorbed on the charcoal and the partial pressure of iodine in the gas phase at equilibrium conditions and at constant temperature is the adsorption isotherm. The isotherms for chemisorption and physical adsorption of iodine on charcoal are characterized by the gradient of the isotherm, dV = Kp' dp where V = amount adsor bed P = equilibrium partial pressure K = constant 7 = constant being inversely proportional to the partial pressure (n <1) at low partial pressures.(b 5) For this type isetherm, the number of new sites available per molecule added to the gas phase, dV/dp, becomes smaller the larger the partial pressure, and the removal 9.4-14 Amendment 9 t, , 4/,30/75
SNESSAR-P 1 ef ficiency should decrease with increasing inlet concentration or conversely whould increase with decreasing inlet concentration. This relationship can also be shown in the equation derived by Hougan(20 5) for the tbne-position-temperature dependent concentration of the adsorbate during the adsorption of a dilute gas from a fluid flowing through a stationary granular bed . The equation was developed for isothermal conditions assuming a linear adsorption isotherm, V = Kp, to simplify the mathematics . The derived removal ef ficiency, exit gas phase concentration over inlet concentration, is: uL E=e e"~ I g (2V 6 tex) d (ax) O where 8 = constant K and K is the gradient of the adsorption isotherm since any small change about a partial pressure for a nonlinear isotherm can be described by the linear isotherm: Y V = dp- p + C = Kp The value of the removal efriciency, E, is directly proportional to the value of K. If the gradient, dV/dp, increases with decreasing partial pressure, the removal ef ficiency will increase with the decreasing partial pressure, or inlet concentration. Therefore, theory predicts an increase in the iodine charcoal removal ef ficiency with decreasing inlet iodine concentration since the charcoal-iodine adsorption isotherm shows an increased gradient with decreasing iodine concentrations for low iodine concentrations. Although theory predicts an increase in removal filter ef ficiency with a decrease in inlet iodine concentration, Fu rtado( * ) reports no significant concentration effect on the removal filter efficiency of methyl iodide and Bellamy(6) reports an initial incrense of removal filter efficiency with decreasing inlet iodine concentration , which is predicted by theory, but which changes at some low inlet concentration to no significant change in removal efficiency with a further decrease in the inlet iodine concentra tion . Furtado C * ) explains his results in terms of the limiting reaction for the K127 I, CH 131 I interchange being proportional to the partial pressure of methyl iodide in the gas phase. Bellamy(6) explains his results in terms of a surface site reactivation 9 . 4 - 14 A Amendnent 9
/ /" i^ ,
4,'30/75 t\ , i l <..w
SWLSSAR-P1 effect whereby, as the gas phase concentration of methyl iodide f alls below a characteristic concentration for the charcoal, the rate of reactivation of previously used sites becomes unimportant and the removal ef ficiency becomes independent of the inlet gas phase concentration. Each author has overlooked the fact that the background methyl iodide concentration in the carrier gas was not removed before adding the me thyl iodide used to determine the inlet concentration for their experiments. Therefore, if the amount of methyl iodide added to the carrier gas is small compared to that alreaay present in the carrier gas, the measured removal efficiency should be for the background concentration, not the added concentration, and the removal efficiency should be independent of the added concentration of methyl iodide. Bellamy 's C 6 )chara cte ris tic concentration, Co, is sbmply the background concentration in the carrier gas. The value of Co estimated was 8.51 x 10-5 uCi/cc. Converting to ugm/M3 for 1131, Co is about 10-3 ugm/M3 which agrees with the estimated background concentration of methyl iod"ide in air given in References 1 and 2. This estimate of the background concentration is greater than the 1-200 MPC range of methyl iodide concentra tions in Furtado's(*) experiments. Therefore, his conclusion that there was no significant conctntration effect on the removal efficiency of methyl iodide may bo the result of masking his inlet concentrations by the background concentration within the carrier gas. Therefore, theory predicts an increasing ef ficiency f or removing elemental iodine and methyl iodide by charcoal with dec reasino inlet iodine concentrations in the carrier gas for low iodine concentrations, and experiments have shown that the removal efficiency remains constant once the inlet concentracion becomes smaller than the background iodine concentration in the carrier gas. The iodine removal for a 2 inch deep bed should be at least 90 percent since:
- 1. Be llamy 's ( 6 ) experimental results at background inlet concentrations, where the measured activity (coun ts per minute) was at least 100 times background activity, for 2 inch beds had removal efficiencies in excess of 99 percent,
- 2. Hesbol reports methyl iodide filter efficiencies in excess of 99 percent for greater than 90 percent humidity, 0.27 second dwell time, 2 inches of ch arcoal, and an inlet concentration of approximately 10-10 ugm/M 3 ,
- 3. At inlet iodine concentrations in the range 103 greater ta 103 smaller than background, 40 fpm superficial 9.4-14B Amendment 9 4/30/75
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