ML19312A214

Chapter 11 of S&W SWESSAR-P1, Radwaste Mgt.

ML19312A214
Person / Time
Site:	05000495
Issue date:	11/29/1978
From:	NEW YORK STATE ELECTRIC & GAS CORP., STONE & WEBSTER, INC.
To:
References
NUDOCS 7909050539
Download: ML19312A214 (376)

Text

SWESSAR-P1 CHAPTER 11 RADIOACTIVE WASTE MANAGEME17f LIST OF EFFECTIVE PAGES Page, Table (T) , Amendment Page, Table (T) , Amendment or Figure (F) No. or Figure (F) No.

11-a/b 39 T11.2-12 (2 sheets) 19 11-i/ii 9 T11.2-13 (2 sheets) 19 11-iia 7 T11.2-14 (2 sheets) 19 11-iii/iv 8 T11.2-15 (2 sheets) 19 11-v/vi 9 T11.2-16 (2 sheets) 19 11-vii/viii 8 T11.2-17 (2 sheets) 19 ll-ix-x 29 T11.2-18 (2 sheets) 19 11-xi 10 T11.2-19 10 11.1-1 7 T11.2-20 (2 sheets) 19 11.1-2 19 T11.2-21 (2 sheets) 19 11.1-3 17 T11.2-22 (2 sheets) 19 11.1-4 7 T11.2-23 19 11.1-5/6 19 T11.2-24 (2 sheets) 19 T11.1.1-1 19 T11.2-25 (2 sheets) 19 T11.1.1-2 (W) 18 T11.2-26 (2 sheets) 19 T11.1.1-2 (B&W) 18 T11.2-27 (2 sheets) 19 T11.1.1-2 (C-E) 18 T11.2-28 (2 sheets) 19 T11.1.2-1 (sheet 1) 19 T11.2-29 (2 sheets) 19 T11.1.2-1 (sheet 2) 22 T11.2-30 (2 sheets) 19 T11.1.2-1 (sheet 3) 19 T11.2-31 (2 sheets) 19 T11.1.2.2 (2 sheets) 19 T11.2-32 (2 sheets) 19 T11.1.2-3 7 T11.2-6 thru 17 (W-3S) 17 T11.1.3-1 (2 sheets) 19 T11.2-18 (W-3S) 19 T11.1.3-2 (2 sheets) 19 T11.2-20 thru 31 (W-3S) 17 11.2-1 9 T11.2-32 (W-3S) 19 11.2-2 7 T11.2-33 Orig 11.2-2A 7 T11.2-34 ('W) 11 11.2-3 thru 5 9 T11.2-34 (C-E) 11 11.2-6 7 T11.2-35 11 11.2-7/8 9 T11.2-36 (W) 11 11.2-9/10 7 T11.2-37 (sheet 1) 9 11.2-11 19 T11.2-37 (sheet 2) 7 11.2-12, 13 25 T11.2-38 (4 sheets) 7 T11.2-1 (2 sheets) 9 F11.2-1 12 T11.2-2 2 F11.2-1A 12 T11.2-3 (3 sheets) 10 Fll.2-1B 12 T11.2-4 (2 sheets) 9 F11.2-1C 12 T11.2-5 9 F11.2-1D 12 T11.2-6 (2 sheets) 19 F11.2-1E 12 T11.2-7 (2 sheets) 19 F11.2-1F 12 T11.2-8 (2 sheets) 19 F11.2-1I 29 T11.2-9 19 F11.2-2 pi) 10 T11.2-10 (2 sheets) 19 F11.2-2 (W-3S) 17 T11.2-11 (2 sheets) 19 F11.2-2 (Le,n ) 19 11-a Amendment 39

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SWESSAR-P1 LIST OF EFFECTIVE PAGES (CONT)

Amendment Page , Table (T) , Amendment O

Page, Table (T) ,

or Figure (F) No. or Figure (F) ho.

F11.2-2 (C-E) 10 T11.5-2 (sheet 2) 12 F11.2-3 (W) 10 T11.5-3 (sheet 1) 8 F11.2-3 (W-3S) 17 T11.5-3 (sheet 2) 2 F11.2-3 (B&W) 19 T11.5-4 5 F11.2-3 (C-E) 10 T11.5-5 (W) g 11.3-1 thru 6 19 T11.5-5 (W-3 S) 17 11.3-7/8 25 T11.5-5 (B&W) 30 T11.3-1 19 T11.5-5 (C-E) 26 T11.3-2 (W) 10 F11.5-1 12 T11. 3-3 (W) 10 F11.5-1A 12 T 11. 3-2 6 3 (W-3S) 17 F11.5-1B 12 T11.3-2 (DSW) 19 F11.5-1C 12 T11.3-3 (BSW; 19 F11.5-1D 12 T11.3-2 (C-E) 10 F11.5-1E 12 T11.3-3 (C-E) 10 F11.5-1F (sheet 1) 19 T11.3-4 (5 sheets) 17 F11.5-1F (sheet 2) 23 T11.3-5 thru 7 11 /11.5-1F (sheets 3 turu 5) 19 T11.3-8 17 F11.5-2 19 F11.3-1 12 11.6-1 thru 3 Orig F11.3-1A 12 11.6-4 10 F11.3-1B 12 11.6-5 thru 6A 17 F11.3-1C 12 11.6-7 thru 14 10 F11.3-1D 12 T11.6.1-1 thru 3 Orig F11.3-1E 12 T11.6.2-1 Orig F11.3-1F 12 T11.6.3-1 Orig F11.3-1G 29 T11.6.4-1 Orig 11.4-1/2 8 F11.6.4-2 orig 11.4 -3 thru 4A 19 F11.6.1-1 thru 3 Orig 11.4-5 thru 6A 17 F11.6.2-1 thru 25 (W) 11 11.4-7/8 8 F11.6.2-1 thru 25 (C-E) 11 T11.4-1 17 T 1 1. 4 -2 21 T11.4-3 3 T11.4-4 (W) 17 T11.4-4 (W-3S) 17 T11.4-4 (BSW) 19 T11.4-4 (C-E) 17 F1'.4-1 6 F11.4-2 17 11.5-1 8 11.5-2, 2A 19 11.5-3/4 12 11.5-5/6 8 11.5-7 32 11.5-8 7 11.5-9 8 Tll.5-1 19 ,, n-h O, c, Tll . 5-2 (shee t 1) 10 V i ~

11-b Amendment 39 7/14/78

Sh?SSAR-P1 CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT TABLE OF CONTENTS Section Page 11.1 SOURCE TERMS 11.1-1 11.1.1 Radioactivity in Core and Fuel Rod Gap Radio- 11.1-1 activity in the Core 11.1.2 Primary Coolant Equilibrium Activity Fission 11.1-2 Product Activities 11.1.3 Radioactivity in Secondary Side 11.1-4 References for Section 11.1 11.1-5 11.2 RADIOACTIVE LIQUID WASTE SYSTEM 11.2-1 11.2.1 DesigT Objectives 11.2-1 11.2.2 System Description 11.2-2 11.2.2.1 Izundry Waste Provision 11.2-5 11.2.2.2 Input Waste Streams 11.2-6 11.2.2.3 Components 11.2-9 11.2.3 System Evaluation 11.2-9 11.2.4 Operating Procedures 11.2-10 11.2.5 Perfornance Tests 11.2-10 11.2.6 Est3ated Releases 11.2-11 11.2.7 Release Points 11.2-11 11.2.8 Dilution Factors 11.2-11 11.2.9 Estimated Doses 11.2-12 11.2.10 Overflow of Canks 11.2-12 11.2.11 Interface Requirements 11.2-12 9

References for Section 11.2 11.2-13 11.3 RADIOACTIVE GASEOUS WASTE SYSTEM 11.3-1 11.3.1 Design Objectives 11.3-1 11-i Amendment 9

_. , 4/30/75

([0 u'J

TABLE OF CONTENTS (CONT)

Section Page 11.3.2 System Descript'on 11.3-2 11.3.3 System Design 11.3-2 11.3.3.1 Process Gas Portion of Radioactive Gaseous Waste System 11,3-2 11.3.3.2 Process Vent Portion of Radioactive Gaseous Waste System 11.3-3 11.3.3.3 Ventilation and Relief Valve Releases 11.3-3 11.3.3.4 Oomponents 11.3-4 11.3.3.5 lonitors 11.3-4 11.3.4 Operating Procedures 11.3-4 11.3.4.1 Process Gas Portion of Radioactive Gaseous Waste System 11.3-4 11.3.4.2 Process Vent Portion of the Radioactive Gaseous Waste System 11.3-5 11.3.4.3 Ventilation Streams 11.3-5 11.3.5 Performance Tests 11.3-5 11.3.6 Estimated Releases 11.3-5 11.3.7 Release Points 11.3-6 11.3.8 Dilution Factors 11.3-6 Reference for Section 11.3.8 11.3-6 11.3.9 Estimated Doses 11.3-7 9 11.3.10 Interf ace Requirements 11.3-7 11.4 PROCESS AND EFFLUENT RADIATION MONITORING SYSTEM 11.4-1 11.4.1 Design Objectives 11.4-1 11.4.2 Process and Effluent Radiation Monitoring 11.4-1 11.4.2.1 Iocations to be Monitored 11.4-2 11.4.2.2 Anticipated Concentrations, Sensitivities, and Fanges 11.4 -3 11-ii Amendment 9 4/30/75 i.

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SWESSAR-P1 TABLE OF CONTENTS (CONT) 11.4.2.3 Description of Radiation Monitors 11.4-4 11.4.2.3.1 Airborne Process and Effluent Monitors 11.4-4 11.4.2.3.2 Liquid Process and Effluent Monitors 11.4-6 11.4.3 Sampling 11.4-9 11.4.4 Inservice Inspection, Calibration, and Maintenance 11.4-10 f Amendment 7 11-11A hvnv L

2/28/75

SWESSAR-P1 TABLE OF CONTENTS (CONT)

Section Page 11.4.2.3 Description of Radiation Monitors 11.4-4 11.4.2.3.1 Idrborne Process and Effluent Monitors 11.4-4 11.4.2.3.2 Liquid Process and Ef fluent Monitors 11.4-5 8 11.4.3 Sampling 11.4-7 11.4.4 Inservice Inspection, Calibration, and Maintenance 11.4-8 11.5 RADIOACTIVE SOLID WASTE SYSTEM 11.5-1 11.5.1 Desiga Objectives 11.5-1 11.5.2 System Inputs 11.5-1 11.5.2.1 Spent Resins 11.5-2 11.5.2.2 Waste Evaporator Bottoms 11.5-2A 11.5.2.3 Regenerant Chemical Evaporator Lottoms 11.5-2A 11.5.2.4 Laundry Waste Evaporator Bottoms 11. 5- 2A 8

11.5.2.5 Boron Evaporator Bottoms 11.5-3 11.5.2.6 Miscellaneous Radioactive Solid Wastes 11.5-3 11.5.3 Equipment Description 11.5-3 11.5.3.1 boron, Waste Evaporator, and Regenerant g Chemical Evaporator Ecttoms Handlina 11.5.4 11.5.3.2 Spen t Resin Handling 11.5-5 11.5.3.3 Filter Hundling 11.5-5 11.5.3.4 Incompressible Waste Handling 11.5-6 11.5.3.5 Waste Ealing Operation 11.5-6 11.5.3.6 Components 11.5-6 11.5.4 Expected Volumes 11.5-6 11.5.5 Packugin g 11.5-7 11.5.6 Storage Facilities 11.5-7

@ 11.5.7 Shipment 11.5-8 11-iii Amendment 8

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SWESSAR-P1 TABLE OF CONTENTS (CONT)

Section Page 8

11.S.8 Interface Requirements 11.5-9 11.6 OFFSITE RADIOLOGICAL MONITORING PROGRAM 11.6-1 11.6.1 Expected Background 11.6-1 11.6.1.1 External Background Exposure Rates 11.6-2 11.b.1.2 Internal Background Exposure Rates 11.6-3 11.6.2 Critical Pathways 11.6-4 11.6.2.1 Liquid Releases 11.6-5 11.6.2.2 Airborne Radioactivity Releases 11.6-7 11.6.2.3 Assumptions for Dose Calculations 11.6-9 11.6.3 Sampling Media, Locations and Frequency 11.6 - 11 11.6.4 Analytical Sensitivity 11.6-11 11.6.5 Data Analysis and Presentation 11.6-12 11.6.6 Program Statistical Sensitivity 11.6-12 References for Section 11.6 11.6- 13

/. O ua O 11-iv .'anen dment 8 3/28/75

SWESSAR-P1 LIST OF TABLES Table 11.1.1-1 Iodine and. Noble Gas Inventory in Reactor Core and Fuel Rod Gaps 11.1.2-1 Parameters Used in the Calculation of Reactor Coolant, Secondary Side Liquid, and Secondary Side Steam Fission and Activation Product Activity 11.1.2-2 Reactor Coolant Equilibrium Concentration 11.1.3-1 Secondary Liquid Equilibrium Concentrations 11.1.3-2 Secondary Steam Equilibrium Concentrations 11.2-1 Characteristics of Pumps in Radioactive Liquid Waste System 11.2-2 Characteristics of Demineralizers and Filters in Radioactive Liquid Waste System 11.2-3 Characteristics of Tanks in Radioactive Liquid Waste System 11.2-4 Characteristics of Heat Exchangers in Radioactive Liquid Waste System 11.2-5 Deleted 11.2-6 Netivity from Decontamination Drain,s (Desi,gn Case) 11.2-7 Activity from Reactor Plant Sampling Sinks (Design Case) 11.2-R Activity from Boron Recovery Letdown (Design Case) 11.2-9 Activity from Spent Resin Flush (Design Case) 11.2-10 Activity from Laboratory Wastes (Design Case) 11.2-11 Activity from Processed Primary Coolant System Leakage (Design Case) 11.2-12 Activity from Unprocessed Primary Coolant System Leakage (Design Case) 11.2-13 Activity from Turbine Plant Sampling Sinks (Design Case) 11- V Amendment 9

[ 4/30/75

^

4/o

SWESSAR-P1 LIST OF TABLES (CONT)

Table 11.2-14 Activity from Turbine Building Sumps (Desian Case) 11.2-15 Activity from Chemical Regenerative Waste (Desion Case) 11.2-16 Activity from Laundry Drains (Design Case) 11.2-17 Total Activity from Radioactive Liquid War ' System with Steam Generator Leakage (Design Case) 11.2-18 Activity at Discharge Point (Design Case) 11.2-19 Deleted 11.2-20 Activity from Decontamination Drains (Expected Case) 11.2-21 Activity from Reactor Plant Sampling Sinks (Expected Case) 11.2-22 Activity from Boron Recovery Letdown (Expected Case) -

11.2-23 Activity from Spent Resin Flush (Expected Case) 11.2-24 Activity from Laboratory Wastes (Expected Case) g 11.2-25 Activity frm Processed Primary Coolant System Leakage (Expected Case) 11.2-26 Activity from Unprocessed Primary Coolant System Leakage (Expected Case) 11.2-27 Activit.,f frm Turbine Plant Sampling Sinks (Expected Case) 11.2-28 Activity from Turbine Building Sumps (Expected Case) 11.2-29 Activity from Chemical Regenerative Waste (Expected Case) 11.2-30 Activity from Laundry Drains (Expected Case) 11.2-31 'Ibtal Activity Released from Radioactive Liquid Waste Systs with Steam Generator Leakage (Expected Case) 11.2-32 Activity at Discharge Point (Expected Case)f/ O 1 Ls L Oud 11-vi Amendment 9 4/30/75

SWESSAR-P1 LIST OF TABLES (CONT)

Table 11.2-33 Bioaccumulation Factors for Aquatic Organisms 11.2-34 Dose to Individuals from Radionuclides in the Liquid Effluent Bused on Nominal Dilution Estimates of Table 11.6.2-1 11.2-35 Comparison of Liquid Releases and Calculated Annual Doses from Liquid Pathways 11.2-36 Populat i an Dose Equivalent Rates for Liquid Effluent Pathways 11.2-37 Liquid Waste Daily Input Flows 11.2-38 Tank Overflow Protection 11.3-1 Values Used in Calculating Padioactive Gaseous Release 1 1 . '.- 2 Estimated Gaseous Ef fluent Sources (Design Case) 11.3-3 Estimated Gaseous Ef fluent Sources (Expected Case) 8 11.3-4 Radioactive Gaseous Waste System Component Data 11.3-5 Dose to the Population dt a River Site from Submersion in the Gaseous Effluent (Whole Body Gamma) 11.3-6 Dose to the Population at a Lakeshore Site from Submersion in the Gaseous Effluent (Whole Body Gamma) 11.3-7 Dose to the Population at a Seashore Site from Submersion in the Gaseous Effluent (Whole Body Gamna) 11.3-8 KSSS Design and Operating Purification Flow Rates 11.4-1 Airborne Process and Efiluent Monitors 11.4-2 Liquid Process and Effluent Monitors 11.4-3 hadiological Samples Taken at heactor Plant Sample Sink 11.4-4 Expected Concentrations in Various Airborne Process 8

and Effluent Monitors 11.5-1 Volume of Spent Resin Generated Annually

,  ?

11-vii l- Amendment 8

[s 5S 3/28/75

SWESSAR-P1 LIST OF TABLES (CONT)

Table 11.5-2 Radioactive Solid Waste System Component Data 11.5-3 Radioactive Solid Waste System Pump Data 11.5-4 Principal Nuclides Present in Solid Waste g 11.5.5 Fadioactive Solid Waste System Interf ace Information 11.6.1-1 Estimated Average Annual Internal Whole-Body Dose Fates from Natural Radioactivity in the United States 11.6.1-2 Estimated Per Capita Whole Body Dose Equivalent Pates from Inhalation of Radioactive Fallout in the United States 11.6.1-3 Estimated Whole Body Dose Equivalent Rates from Ingestion of Radioactive Fallout in the United States 11.6.2-1 Effluent Dilution Factors for Single Reactor Sites 11.6.3-1 Preopera tional Environmental Radiological Monitoring Program - Samples, Locations, and Frequency 11.6.4-1 Typical Sample Sizes and Sensitivities for Gross Activity Analysis 11.6.4-2 7ypical Minimum Detectable Concentrations of Isotopes in Environmental Samples m**

(> v/a0 L ,

11-viii Amen dment 8 3/28/75

SWESSAR-l'1 LIST OF FIGURES Figure 11.2-1 Radioactive Liquid Waste (with Laundry) System 11.2-1A Radioactive Liquid Waste (with Laundry) System 11.2-1B Radioactive Liquid Waste (with Laundry) System 11.2-1C Radioactive Liquid Waste (with Laundry) Syatem 11.2-1D Radioactive Liquid Waste (with Laundry) System 11.2-1E Radioactive Liquid Waste (with Laundry) System 11.2-1F Radioactive Liquid Waste (with Laundry) System 29 11.2-2 Estimated Source Quantities to Radioactive Liquid Waste System (Expected Case) 11.2-3 Estimated Source Quantities to Radioactive Liquif Waste System (Design Case) 11.3-1 Radioactive Gaseous Waste System 11.3-1A Radioactive Gaseous Waste System 11.3-1B Radioactive Gaseous Waste System 11.3-1C Radioactive Gaseous Waste System 11.3-1D Rddioactive Gaseous Kaste System 11.3-1E Radioactive Gaseous Waste System 11.3-1F Radioactive Gaseous Waste System 11.3-1G Radioactive Gaseous Waste System 11.4-1 Airborne Radiation Monitor (Two Detectors) 11.4-2 Release Paths for Potentially Radioactive Gases 11.5-1 Radioactive Solid Waste System 11.5-1A Radioactive Solid Waste System 11.5-1B Radioactive Solid Waste System 11.5-1C Radioactive Solid Waste System 11-ix Amendment 29 10/29/76 6 ', hj c.J

SWESSAR-P1 LIST OF FIGURES (CONT)

Fiqure 11.5-1D Radioactive Solid Waste System 11.5-1E Radioactive Solid Waste System 11.5-1F Radioactive Solid Waste System (5 Sheets) 11.5-2 Radioactive Solid Waste System, Estimated Quantities 11.6.1-1 Map Showing Calculated Terrestrial Dose Rates (in mrem per year) for Areas in the United States (Adapted from Oakley, Reference 2) 11.6.1-2 Map Showing Calculated Cosmic Ray Dose Rate Ranges (in Mrem per year) tor Areas in the United States (Adapted from Oakley, Reference 2) 11.6.1-3 Map Showing Calculated Total Dose Rate Ranges (in mrem per year) for Areas in the United States (Adapted from Oakley, Reference 2) 11.6.2-1 External Exposure 11.6.2-2 External Exposure, Shoreline Activities 11.6.2-3 Drinking Water, Lake and River 11.6.2-4 Eating Freshwater Fish 11.6.2-5 Eating Marine Fish 11.6.2-6 Eating Marine Mollusks 11.6.2-7 Eating Marine Crustacea 11.6.2-8 Eating Freshwater Plants 11.6.2-9 Eating Marine Plants 11.6.2-10 Eating Irrigated Vegetables 11.6.2-11 Gamma Whole Body Submersion - Lakeshore, from Airborne Radioactive Releases 11.6.2-12 Gamma Whole Body Submersion -

Rivershore

,n 0va 7^6 11- x Amendment 29 10/29/76

SWESSAR-P1 LIST OF FIGURES (CONT)

Figure 11.6.2-13 Gamma Whole Body Submersion - Seashore 11.6.2-14 Beta Skin Submersion - Lakeshore 11.6.2-15 Beta Skin Submersion - Rivershore 11.6.2-16 Beta Skin Submersion - Seashore 11.6.2-17 Inhalation Thyroid - Inf ant - Rivershore 11.6.2-18 Inhalation Thyroid - Infant - Lakeshore 11.6.2-19 Inhalation Thyroid - Infant - Seashore 11.6.2-20 Milk Chain - Infant Thyroid - Rivershore 11.6.2-21 Milk Chain - Infant Thyroid - Lakeshore 11.6.2-22 Milk Chain - Infant Thyroid - Seashore 11.6.2-23 Iodine Deposition on Vegetables - Adult Thyroid -

Rivershore 11.6.2-24 Iodine Deposition on Vegetables - Adult Thyroid -

Lakeshore 11.6.2-25 Iodine Deposition on Vegetables - Adult Thyroid -

Seashrte n

/ 's c,J 11-xi Amendment 10 5/15/75

1

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f 11.1

(

.Y I

,w f

e-

SWESSAR-P1 CHAPTER 11 RADIOACTIVE WASTE MANAGEMEtTP 11.1 SOURCE TERMS During normal operation of the plant, radioactive material is produced by fission in the core and induced activation in the coolant and metals by neutron capture.

11.1.1 Radioactivity in Core and Fuel Rod Gap Radioactivity in the Core The fission product activity in the core is calculated using the Stone & Webster cmputer program ACTIVITY. The following differential equations are solved by ACTIVITY:

a. First order isotope:

dN ci dt

-F . - (A.1 + h7.1 +S)i N 1 i (t)

b. Second order isotopes:

dN C.

3

= Fa. +A + g)j Nc (t) dt 3 f..

i 13 Nc1(t) - (A.3 + h7 3 3

c. Third order isotope:

I dN e

k =

Fa k+A j fjk N c.

(t) - (A k + h7p' +S k "c k dt J where, N c' = Concentration of isotope i per fuel region i (atoms / region) t =

Time (sec)

F = Fission rate (fissions /sec in fuel region)

" = Fission yield for isotope i (atoms / fission)

A

= Decay constant for isotope i (sec-3)

T = Escape rate coefficient (sec-1) i S,

= a g 4g =Burnup rate (se c-1 )

f. = Branching - fraction from i to j ii

@ h = Fraction of failed fuel.

11.1-1 Amen 6nent 7 r c.g 9? 2/28/75 u

{ v. O ,

SWESSAR-P1 The program has a basic library of 167 nuclides that includes decay schemo information, production information, purification factors for typical demineralizers, and fuel escape rate coefficients. The library also contains decay gamma spectra in seven energy groups. The user may add isotopes up to a total of 200 or change data, such as purification factor and/or escape rate coefficients. Input data include time intervals, initial source inventory in the fuel, neutron flux, power level, fraction of fuel defects, and density of reactor coolant. The chemical and volume control system, Section 9.3.4, may also be des cribed including flow rates, densities, and operating intervals. The program output describes the system analyzed, as well as the operating history, the activities, and associated gamma spectral information as a function of time.

The calculation of the core iodine fission product inventory is consistent with the inventories given in TID-14844 (Ref 1) . The fission product inventories for other isotopes which are important from a health ha..ards point of view are cc.lculated using the data from NEDO-12154-1 (Ref 2) . The core iocine and noble gas fission product inventories are presented in Table 11.1.1-1 based on continuous operation of the unit at 19 4100 MWt (C-E , W-41) 3,876 MWt (B&W) , or 3,636 MWt (W-3S). These fission produ ct inventories are used in the evaluation of the accidents in Chapter 15.

Radioactivity in the Puel Rod Gap The core gap activity is that fraction of the gaseous activity in the core that dif fuses to the ruel gaps. In accordance with the guidance provided in Regulatory Guides 1.25 and 1.77, the noble gas and iodine inventory in the fuel gap region is assumed to be 10 percent (30 percent for Kr 85) of the core inventory for accident analysis. The core gap activities are presented in Table 11.1.1-1.

Each of the NSSS Vendors has provided a basis for the core gap activity in Chapter 15 of the NSSS Vendor's SAR. As can be seen from the gap activity reported for Westinghouse and Babcock and Wilcox, the calculated values are generally much less than 10 percent of the core inventory.

11.1.2 Primary Coolant Equilibrium Activity Fission Product Activities The design fission product activities in the reactor coolant are also calculated with the ACTIVITY program. The following differential equations are used:

a. First order isotopes:

40 l b( e V LV 11.1-2 Amendment 19 12/12/75

SNESSAR-P1

b. Second order isotopes:

"j "

i N c (t) + A.1 f..N (t) - A.+

+ 0.

3 T1 j g3 V 2) N"j (t) dt V 13 wi

c. Third order isotopes:

dN PF yg Q w i T k hny( N k +d 1 dt

=

V w

c k

(t) + A.] f jk N w.(t)

J

- A k+ V kT 2 N

W,K (t) w where, N g; = Concentration of isotope i in the main coolant (atoms /cc) n = Total number of fuel regions V, n

=

Volume of main coolant (cm3)

PF = Equivalent purification f actor (fraction) for i EQ.

T; =

Coolant residence time in core (sec)

Ty =

Coolant circulation time (sec)

Q.

= Equivalent flow into purification stream Q 4 (cm3/sec)

P# w Op = Actual flow entering purification stream 8 coolant loop density p p

(cma /sec)

P.w

= Density of the main coolart (9/cc)

P p

= Density of the purification flow (g/cc)

The reactor coolant system design basis equilibrium ,

radioactivities f or continuous operation of the core at 1.02 j7 times the proposed licensed power level with fuel clad defects in i fuel producing 1.0 percent of power are presented in Table 11.1.2-2 based on parameters in Table 11.1.2-1.

In these calculations the defective fuel rods are assumed to be present in the initial core and uniformly distributed throughout the core. The fission product escape rate coef ficients are based upon the average fuel temperature. Calculations are performed using the average temperature of the reactor coolant. The reactor coolant density correction of 1.4 is made in order to obtain the correct radioacti.'ities downstream of the letdown heat exchanger.

Also included in Table 11.1.2-2 are the expected equilibrium concentrations for the reactor coolant system. These results are based on measured and calculated concentrations reported in 11.1-3 Amendment 17 efn n- 9/30/75 C00 cs i

SWESSAR-P1 proposed ANS Standard N237 (Ref 3) and the parameters listed in Table 11.1.2-1.

Activation Products The activity in the coolant also includes activation products.

These include both corrosion product activity and N-16. The intensity of activation products in the primary coolant is based on information in Ref 3 and in the NSSS Vendor's SAR.

Tritium The source of tritium and the tritium production rates are given in the NSSS Vendor's SAR. The expected tritium concentration in the primary coolant is based on the value provided in Ref 3. For the purpose of radioactive liquid waste analysis, it is assumed that all the activity produced and entering into the coolant in one year is relei. sed in the radioactive liquid waste effluent.

The design tritium concentration in the primary coolant is selected to allow limited access to the containment during normal operation when tritium is the significant isotope.

11.1.3 Radioactivity in Secondary Side 7

The concentrations of principal radioisotopes in the secondary side of the steam generators are listed for both the design and expected cases in Tables 11.1.3-1 for liquid and 11.1.3-2 for steam. The design results for fission and activation products based on parameters in Table 11.1.2-1, were calculated with the Stone & Webster computer program IONEXCHANGER, which solves the following differential equations for secondary liquid activities for W and C-E and for secondary steam for BSW.

a. First order isotopes:

dN.

i~ ^i + O dt Ng(t)

b. Second order isotopes:

dN. Og dt 3

=R.

J

+ A.

1 f..

1J N.

1 (t) - (A.3 + y) N .3 (t)

c. Third order isotopes:

dN dt k +Aj f jk Nj (t) - A k+ Nk N I

,,n n- a O

D eo c_

11.1-4 Amendment 7 2/28/75

SNESSAR-P1 where,

= Concentration of isotope i (atoms /cc)

N;

= Feed rate if isotope i (atoms /sec)

R; A = Radioactive decay constant for isotope i (sec-1)

1. . = Branching fraction f rom i to j 11 y = Volume of receiving body (cc) g = Steam generator radioactivity resaoval rate H

(cc/sec) t -

Time in sec The steam activities for W and C-E are obtained using the following relationship:

A si

• Ei uli where A;3

= Steam equilibrium activity for isotope i (uCi/gm)

Ag = Liquid equilibrium activity for isotope i (uCi/gm)

P

= Partition f actor (liquid to steam) fcr isotope i The expected secondary liquid and steam activities are based on the concentrations reported in proposed ANS Standard N237 (Ref 3) and the parameters in Table 11.1.2-1.

The results given in Table 11.1.2-2 and 11.1.3-2 for BSW are generally taken frew 'revious analyses which were based on values of parameters s__ghtly different thsn those given in Table 11.1.2-1. Since the results are consistent with those g already presented for the W and C-E NSSS, revisions in the calculations are unnecessary for this application for Preliminary Design Approval.

References for Section 11.1 (1) DiNunno, J .J . , et al. , " Calculation of Distance Factors for Power and Test Reactor Sites," TID 14844, March 1962.

(2) Meek, M.E. and Rider , E.F. , " Compilation of Pission Product Yields," NEDO-12154-1, General Electric Corporation, January 26, 1974.

11.1-5 Amendment 19

, ., g nr, 12/12/75 0vu LsJ

SWESSAR-P1 (3) Proposed American Nuclear Society N237, " Source Term Specificaticn," submitted for review and ballot Novanber 1974.

O 0ev t_ _

e

11. -6 Amendment 19 12/12/75

SWESSAR-P1 TABLE 11.1.1-1 IODINE AND NOBLE GAS ITNENTOFY IN PEACTOR CORE AND FUEL ROD GAPS Fraction Core of Core Fuel Rod Gap Activity Isotope [Ci) in Gap (Cil H f. W W-41, CFJ_ W-3S B6W W -41, C-E W-3E I-131 9.7E 07* 1.0E 08** 9.1E 07*** .1 9.7E 06* 1.0E 07** 9.1E 06***

I-132 1.4E 08 1.5E 08 1.3E 38 .1 1.4E 07 1.5E 07 1.3E 07 I-133 2.2E 08 2.3E 08 2.0E 38 .1 2.2E 07 2.3E 07 2.0E 07 I-134 2.5E 08 2.7E 08 2.4E 08 .1 2.5E 07 2.7E 07 2.4E 07 I-135 2.0E 08 2.1E 08 1.9E 08 .1 2.0E 07 2.1E 07 1.9E 07 Kr-83m 1.7E 07 1.8E 07 1.6E 07 .1 1.7E 06 1.8E 06 1.6E 06 Kr-85m 4.2E 07 4.5E 07 4.0L 07 .1 4.2E 06 4.5E 06 4.0E 06 Kr-65 1.1E 06 9.5E 0 5 8.4E 05 .3 3.2E 05 2.9E 05 2.5E 05 "

Kr-87 8.2E 07 8.7E 07 7.7E 07 .1 8.2E 06 8.7E 06 7.7E 00 Kr-88 1.2E 08 1.2E 0 8 1.1E 08 .1 1.2E 07 1.2E 07 1.1E 07 Kr-8* 1.5E 08 1.6E 08 1.4E 08 .1 1.5E 07 1.6E 07 1.4E 07 Xt. - r31m 8.5E 04 9.0E 04 8.0E 04 .1 8.5E 03 9.0E 03 8.0E 03 Xe-133m 5.2E 06 5.5E 06 4.9E 06 .1 5.2E 05 5.5E 05 4.E 05 Xe-133 2.2E 08 2.3E 08 2.0E 08 .1 2.2E 07 2.3E 07 2.0E 07 Xe-135m 5.9E 07 6.2E 07 5.5E 07 .1 5.9E 06 6.2E 06 5.5E 06 Xe-135 2.3E 07 2.9E 07 4.1E 07 .1 2.3E 06 2.9E 06 4.1E 06 Xe-137 1.9E 08 2.1E 08 1.8E 08 .1 1.9E 07 2.1E 07 1.8E 07 Xe-138 1.9E 08 2.0L 08 1.8E 08 .1 1.9E 07 2.0E 07 1.8E 07 m

r C7 PJ

( l L.,

• Based on 17,520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> of operatiori at 3,876 MWt, for use in Chapter 15.

• Based on 14,740 hours0.00856 days <br />0.206 hours <br />0.00122 weeks <br />2.8157e-4 months <br /> or operation at 4,100 MWt, for use in Chapter 15. "

• • • Based on 14,740 inours of operation at 3,636 MWt.

1 of 1 Anendnent 19 12/12/75

SWESSAR-P1 Tables 11 1*1-2 (W), (B6WI' and (C-E) are deleted.

gg 1 of 1 Amendment 18 10/30/75 nr-

) E-

SWESSAR-P1 TABLE 11.1.2-1 pas <AMETEPS USED IN ThL CAlfULATION OF REAC'IUR COOLANT, SECONDAhY SIDE LIQUID, AND SECONDARY SIDL STEAM FISSION Ah'D AC'lIVATION PEODUCT ACTIVITY 1st,W C-U W-41 W-3S Core therml lower, hht 3,8 7 t> 3,876 3,876 3,636 Clad def ects, as a percent of rated core ther7nal Exnser being generated by ruls with clad detects, design 1.0 1.0 1.0 1.0 Fission product escap(? rate coefficients:

a. Noble gas isotopes, see-t 6.5 x 10-a 6.5 x 10-8 6.5 x 10-8 6.5 x 10-8

b. Er, Rb, I, and Cs iso-topes, sec-a 1,3 x 10-m 1.3 x 10-8 1.3 x 10-8 1.3 x 10-*

c. Te isotopes, sec-a 1.0 x 10-* 1.0 x 10-* 1.0 x 10-* 1.0 x 10-*

d. ho isotopes, sec-8 2.0 x 10-* 2.0 x 10-* 2.0 x 10 ' 2.0 x 10-*

e. Sr and La isotopes, see-a 1.0 x 10-88 1.0 x 10-18 1.0 x 10-18 1.0 x 10-81

1. Y , l.a , Ce, Pr isot o;+s, sec-bt 1.6 x 10-82 1.6 x 10-s2 1.6 x 10-82 1.6 x 10-sa keactor coolont liquid volum, ft3 12,500 13,130 12,750 12,100 n Reactor coolant full power average temperature, F 602 589 592 590 Purification ilow rate (normal)

CN gpm 50 84 100 75 CN

,;.-g Mixed bed domineralizer decun-taminution iactors:

a. Noble Gases, N-16 1.0 1.0 1.0 1.0 F3 b. Cs, Rb

( '1 Design 1.0(81 1.0 1.0 1.0ta> g

~.; Expected 2.0 2.0 2.0 2.0

c. All other isotopes includ-ing activation products 10.0 10.0 10.0 10.0(8) 1 of 3 Amendment 19 12/12/75

SWESSAR-P1 TABLE 11.1.2-1 (Coffr)

B&W C-E W-41 W-3S Cation bed demineralizer decon-tamination factors

a. Noble Gases, N-16, Italogens 1.0 1.0 1.0 1.0

b. Cs, Rb 10.0(8) 10.0 10.0 10.0(1)

c. All other isotopes includ-ing activation products Design 1.0 1.0 1.0 1.0ta>

Expected 10.0 10.0 10.0 10.0 Ratio of cation bed demineral-izer flow to purification bed d uineralizer flow 0.1 0.1 0.1 0.1 Reactor coolant letdown dis-charged via boron recovery system, Ib/hr Nominal 5.0 x 102 5.0 x 10e 5.0 x 102 5.0 x lor 22 Steam flow rate, Ib/hr 1.67 x 107 1.72 x 107 1.70 x 107 1.58 x 10?

Water mass per steam generator, Ib NA 168,800 110,000 87,700 h tal war'r mass of secondary systesa, It- 3.5 x 106 3.8 x 106 4.0 x 106 3.5 x 106 Blowdown rate per steam generator, Ib/hr NA 37,000 7,400 7,400 Primary to secondary leak rate, lb/ day O'- Design 1,370 1,370 1,370 1,370 cs Expected 110 110 110 110 CO Steam generator partition factor

4. Noble Gases, N-16 1.0 1.0 1.0 1.0 D3 b. Italogens 1.0 0.01 0.01 0.01

( c. Others 1.0 .0025 .0025 .0025 C L' 2 of 3 Amendment 22 3/17/76

G WESSAR-P 1 TABLE 11.1.2-1 (Corn) 14W C-E W - 841 W-3S Condensate polishing desnineral-izer oecontalaination tactors

a. lialogens 10 10 10 10 l,9

b. Cs , u , Mo (Design) 2.0 2.0 2.0 2.0 1 Cc , k b (Expected) 2.0 2.0 2.0 2.0

c. Other particulates 10 10 10 10 Condensate poli:daing 110w r at e, Ib/hr 1. o re x 107 1.05 x 10s 1.02 x 107 9.76 x 106 It c >Ef f ective design decontantination tactor f or Cs, Mo, and Y lur the design case f or the carabined mixed bec. demineralizer - cation lxd demineralizer = 1.1.

CN c,s CO p) t1

~~

3 of 3 Arrendment 19 12/12/75

U 95 17

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G SWESSAR-P1 TABLE 11.1.2-2 (CONT)

B&W C-E W-41 W-3S Isot or Design Expected Design Expect ed Design Expected Design Expect ed SR 89 6.67E-03 5. 75E -0 4 4 .12E-0 3 3.55E-04 3.44E-03 2.99E-04 4 . 3 3 E-0 3 3.74E-04 SR 90 2.96E-04 1. 6 5E -0 5 1.82E-04 1.01E-05 1.51E-04 8.53E-06 1. 9 2E-0 4 1.07 E-0 5 SR 91 2. 3 4 E -0 3 8.41E-04 1.91E-03 6.87E-04 1.74E-03 6.32E-04 1.96E-03 7.0 6 E-0 4 Y 90 3. 4 2E-0 4 2.61E-05 5.0 6E-0 5 1.74E-05 3.95E-05 1.50E-05 2.32E-04 1. 8 3 E-0 5 Y 91 M 1. 4 0 E-0 3 4. 2 5E -0 4 1.07E -0 3 4 .15E -0 4 9.65E-04 4.11E-04 1.18 E-0 3 4.18E-04 Y 93 6. 0 8 E -0 4 1.69E-04 3.30E-04 1.37E-04 3.00E-04 1.26E-04 5.95E-04 1.41E-04 ZR 95 3. 8 0 E-0 2 9.8 8E-0 5 6.78E-04 6.09E-05 5.65E-04 5.12 E-0 5 7.14E-04 6.42E-05 NB 95 1.15E-0 3 8. 20E -0 5 7.04E-04 5.08E-05 5.87E-04 4.2BE-05 7. 4 3E-0 4 5. 35 E-0 5 MO 99 3.84E 00 6. 9 2E -01 7. 31E -01 4.62E-01 6.23E-01 3. 97 E-01 3.35E 00 4. 8 3 E-01 TC 99 M 2.51E 00 4 .7 0E -01 4.10 E-01 4.06E-01 3.26E-01 3.81E-01 1.91E 00 4.14 E-01 RU 103 5.28E-04 7.39E-05 3. 2 6E -04 4.57E-05 2.72E-04 3. 8 5 E-0 5 3.44E-04 4. 81E-0 5 RU 106 5.35E-05 1. 6 5E-0 5 3.28E-05 1.01E-05 2.74E-05 8.53E-06 3.46E-05 1.07E-05 RH 103M 5. 29E-0 4 5. 0 5E-0 5 3.2 7E-0 4 4 . 91E-0 5 2.73E-04 4.86E-05 3.44E-04 4. 9 4 E-0 5 RH 106 5. 35E-0 5 1.0 9 E-0 5 3.28E-05 1.10E-05 2.74E-05 1.10 E-0 5 3. 4 6E-0 5 1.10E-05 11 TE 125M 1.37E-04 4 . 77E -0 5 8.43E-05 2.94E-05 6.89E-05 2.48E-05 8.9 2E-0 5 3.10 E -05 TE 127M 3. 27E-0 3 4. 6 2E -0 4 2.01E-0 3 2.84E-04 1.68E-03 2.39E-04 2.12E-0 3 2.99E-04 TE 127 1. 3 6E-0 3 1.10E-03 1.02E-03 9.00E-04 1.03E-03 8.28E-03 1. 0 5 E-0 3 9.24E-04 TE 129M 6.01E-02 2. 3 0E -03 3.7 2E -0 2 1.42E-03 3.10E-02 1.20E-03 3.92E-02 1.50E-03 TE 129 3.05E-02 1. 8 0 E-0 3 2.09E-02 1.74E-03 1.83E-02 1.72E-03 2.18 E-0 2 1.76E-03 TE 131M 3.13 E-0 2 1. 59E -0 3 2.2 4 E -02 2.59E-03 1.95E-02 2.27E-03 2.33E-02 2.70E-03 TE 131 1.24E-02 1.22E-03 1 07E-02 1.20E-03 1.01E-02 1.20E-03 1.09 E-0 2 1.21E-03 TE 132 3.91E-01 4 .19E -02 2.58E-01 2.77E-02 2.19E-01 2.37E-02 2.70E-01 2.90 E-0 2 BA 137M 2.56E 00 1.75E-02 1.58E 00 1.76E-02 1.32E 00 1. 76E-0 2 1.66E 00 1.76E-02 BA 140 6. 69E-0 3 3.57E-04 4.19E-03 2.24E-04 3.51E-03 1.89E-04 4. 41 E-0 3 2.36E-04 LA 140 2. 81E-0 3 2. 23E-0 4 1.43E-Os 1.55E-04 1.11E-03 1.35E-04 1. 5 3E-0 3 1.61E-04 CE 141 1.07E-03 1.15E -0 4 6 . 6 2E -0 4 7.11E-05 5.53E-04 5. 99E-05 7.00E-04 7.4 ? f-0 5 CE 143 7.01E-04 5. 8 4 E -0 5 4 . 96E -0 4 4.14E-05 4.31E-04 3.62E-05 5.17E-04 4.31E-05 CE 144 8.02E-04 5. 4 5E -0 5 4.93E-04 3.35E-05 4.10E-04 2.82E-05 5.20E-04 3.53 E-0 5 PR 143 1. 03E-0 3 8.12E -0 5 6.41E-04 5.08E-05 5.35E-04 4.30E-05 6.7 8 E-0 4 5. 35E-05 PR 144 8.022-04 3.63E-05 4.93E-04 3.61E-05 4.118-04 3.62E-05 5.2 0 E-0 4 3. 63E-0 5 NP 239 5. 4 8 E-0 3 1. 8 3E -0 3 3.70E-03 1.23E-03 3.19E-03 1.06E-03 3. 8 7E-0 3 1. 29 E-0 3

'N rh

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)

N 2 of 2 Amendment 19 12/12/75

SWFSSAR-P1 7

Table 11.1.2-3 1s deleted.

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9 15 7

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EWESSAR-P1 11.2 RADIOhCTIVE LIQUID WASTE SYSTEM The function of the radioactive liquid waste system is to reduce the concentration of radioactive nuclides in liquid effluents to the lowest lev ? s practicable.

The r;dioactive liquid waste system flow diagram is shown in Fig. 11.2-1. This figure indicates the piping within the system and shows the instrumentation and a provision for processing laundry waste. 9 11.2.1 Design Obiectives The design objectives for the radioactive liquid waste system meet the criteria suggested in 10CFR20 and 10CFR50. The following specific requirements apply to the system design.

1. Fig. 11.2-2 id 11.2-3 identif y the various sources of radioactive liqui,d and their annual flows for the ernected and design basis cases respectively. The 1;.

ires also show the expected and design basis releases 9 from the plant to the environment from each source in curies per year.

2. Table 11.2-37 gives the daily input, average and maximum flows to the liquid waste system. The average daily flows presented in Table 11.2-37 are the basis for both the design and expected sources in Tables 11.2-5 through lg 11.2-32. The maximum daily flows in Table 11.2-37 are not conce rent, nor are they coincident with the design basis activity levels in the liquid waste syctem. A detailed isotopic listing of sources entering and leaving the radioactive liquid waste system is given in Tables 11.2-5 through 11.2-32.

3. Radiation protection criteria for the radioactive liquid vaste system are given in Section 12.1.

4. The radioa ctive liquid waste system is designated non-nuclear safety (NNS).

5. 'Ite system is located on the Seismic Category I founda-tion to collect and contain any leakage which may occur dcring a seismic event.

6. Pr ?ssure retaining components of the system utilize we lded construction to the maximum practicable extent.

Fianged joints or suitable quick disconnect fittings are used only where maintenance or operational requirements clearly indicate that such construction is pref erable.

Screwed connections in which threads provide the only seals are not used except for instrumentation connections where welded connections are not suitable.

11.2-1 knendment 9 4/30/75

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SWESSAR-P1 Process lines will not be less than 3/4 in. Screwed connections backed up by seal welding, socket welding ,

or mechanical joints are used on lines gi .ter than 3/4 in. but less than 2 1/2 in. nominal size. For lines of 2 1/2 in. and above, piping is butt-welded. Backing rings are not used in lines carrying resins or other particulate material. All welding constituting the pressure bound'ary of pressure retaining components will 7 be performed in accordance with ASME IX.

7. The process piping systems are hydrostatically tested.

Testing of piping systems is performed in accordance with ANSI B31.1 or ASME III as applicable, but in no case at less than 75 psig. The test pressure is held for at least 10 minutes and for such additional time as may be necessary to conduct the examination for leakage.

8. The following areas are included in the Quality Assurance program for the liquid waste system:

a. De' sign and Procurement Document Control

b. Control of Purchased Material, Equipnent, nd Services

c. Inspection of Activities and Methods

d. Handling, Storage, and Shipping of Equipment

e. Inspection , Test, and Operating Status

f. Corrective Actions

9. Materials for pressure retaining components of process systems are selected from those covered by the material specifications listed in Section II, Parts A, B, and C of the ASME Boiler and Pressure Vessel Code and applicable approved ASME Code Cases (see Section 3A.1-1.85) except that malleable, wrought, or cast iron materials shall not be used. The components meet the requirements of the material specifications with regard to manuf a cture , examination, repair, testing, identification, and certification. For atmospheric tanks, the use of fiberglass is a sutisfactory alternative material.

10. Plastic pipes shall not be used for radioactive service.

11.2.2 System Description Included in Fig. 11.2-2 and 11.2-3 are leukages from occurrences which could happen durinc; the normal course of plant operations, such as blown or ruptured valve and pump seals.

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SWESSAR-P" Not included in Fig. 11.2-2 and 11.2-3 are the volumes of dilution liquids, such as floor washings, which are more a tunction of operational philosophy than design or anticipated occurrences. However, note that the activity that coulc be present in this liquid is included in the source data.

In determining the activity of various radioactive liquid waste inputs, the leakages in Regulatory Guide 1.42 togetter with liquids of nonrudioactively contaminated origin are collected from the different buildings in the vent and drains system (Section 9.3.3) and are sent to the radioactive liquid waste system for processing. Table 11.2-37 provides the average daily flow and the maximum daily flow from each raurce of raf.ioactively contaminated liquid (the average daily an/. maximum flow of 7/; m-.;

U ,_. o L v 11.2-2A Amendment 7 2/28/75

SWESSAR-P1 dilution liquid is also included) . The volumes for these collected leakages is greater than that used by the NRC in WASH 1258. Liquids whose sources are not derived from leakages are based on a combination of operating experience and engineering judgment. Pretreatment systems such as the collection and recycling of liquid leakage in the feedwater train of the turbine plant reduce the volume of waste liquid released and its impact on the radioactive liquid waste system. Minimum residence time of liquid in the radioactive liquid waste system is assumed. Additionally, all the tritium produced is assumed released each year by a controiled discharge of distillate from the boron recovery system.

Filter efficiencies for corrosion products are based upon operating experience. Although some reduction for fission products was also observed, no credit is taken for fission product removal. Decontamination f actors in excess of 105 are used in the design of the waste and regenerant chemical evaporators and is accomplished by features such as low vapor velocity, tray section, and vapor-liquid separators. However, a conservative decontamination factor of 10* is used for performance evaluation of the waste-evaporator-demineralizer combination. The laundry evaporator is a single stage thin film evaporator and is used to process detergent solutions. i

[9 Liquid wastes enter the system via the high and low level waste drain tanks. Af ter sampling, the high level waste is sent to the evaporator and low level waste is filtered, monitored, and discharged.

The waste evaporator is designed to produce a distillate suitable for discharge. The waste evaporator is designed with an external reboiler, a large liquid disengaging space, a tray section, and a vapor-liquid separator. These features combine to form a system with extremely high separation factors for nonvolatile nuclides.

A decontamination factor of greater than 10* for nonvolatile nuclides is expected. Although not a system function, the waste evaporator can act as a backup for the boron evaporator.

The distillate f rom the waste evaporator is collected in waste t es t tanks , sampled for radioactivity, and if within allowable limits, it is discharged. Part of the distillate may be pumped to the prima ./ grade water storage tank for reuse, depending on the water balance within the plant. If the distillate samples indicate an activity greater than allowable for discharge, the dis tillate is either passed through the waste demineralizer and resampled or sent back to the high level waste drain tanks for reprocessing .

A second evaporator , the regenerant chemical evaporator, is pr:cid ed to reduce radioactivity and chemicals from the concenu te plishing system regenerative chemical waste. This eva porato.: is identical to the waste evaporator. The dis tillate 11.2-3 Amendment 9 6h] { } 4/30/75

SWESSAR-P1 returns to the condensate polishing system. The contents of the 9l high level waste drain tanks can be transferred to the regenerant chemical evaporator and the distillate from this evaporator may be sent to the waste test tanks.

Assurance that no high level waste is inadvertently discharged to the environment is provided through sampling of the effluent prior to discharge, radiation monitoring of the effluent stream, and sa 'ety features incorporated in the design of the equipment.

A radiaactive liquid waste system decontamination factor of greater than 105 has been calculated for all nuclides. Howeve r, a conservative value of 104 is assumed for the waste evaporator-waste demineralizer ccanbination, and a minimum residence time of 20 hr is assumed in the calculations . The evaporator design provides a decontamination factor of greater than 10+ for nonvolatile nuclides. Aerated waste demineralizer experience at Connecticut Yankee has shown overall decontamination factors of over 100 attainable for all nuclides and substantially higher than 100 for iodine. Problems experienced at Connecticut Yankee with cobalt leakage through the demineralizer are expected to be minimized by placement of the demineralizer after the evaporator.

This complex-forming species reduces the stability of any cobalt ccanplexes which may be formed in the waste liquid. The use of decontamination solutions is restricted for this reason.

The liquid from the waste test tanks is recycled as much as is consistent with good practice. However, for the purposes of evaluating the radiological impact on the environment, all processed waste is assumed to be discharged.

h%ste evaporator bottoms are allowed to concentrate to whichever of the following occurs first: approximately 15 percent solids by weight or to an activity determined by the shielding characteristics of the container used to ship the evaporator bottoms offsite. The regenerant chemical evaporator bottums are concentrated to 24 percent solids by weight. Evapora tor bottoms are pumped to the radioactive solid waste system (Section 11.5) for solidification and eventual shipment offsite.

Low level wastes ara those wastes which can be rendered suitable for discharge from the site by dilution alone. Filtration is provided for low level wastes as an added precaution against discharge of particulates. Suitability for discharge is determined not only by cc carison of the activity levels of low level waste drain tank samp. ts with applicable limits but also by the capabilities to reduce further activity by means of the radioactive liquid waste system equipment. Provisions are made for conveying the contents of the low level waste drain tanks to the high level drain tanks if the activity level of any of the liquids in the low level waste drain tanks is found to have an activity greater than about 5x 10-5' uCi per cc for sites with cooling tower blowdown dilution. Low level liquid wastes whose 11.2--4 Amendment 9 4/30/75 ,a

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SWESSAR-P1 activity is below this level are sampled and, after analysis, are pumped through the waste effluent filters to the discharge line, For sites that include a once through cooling system, the radioactive liquid wastes with concentration greater than 5x10-* uCi/cc would be processed by the waste evaporation prior to release to the environment.

The low level waste effluent filters provide a decontamination factor of 5 for corrosion products. A filter element is changed when the radioactivity level at the filter surface or the pressure drop exceeds a predetermined lovel.

The demineralizers use mixed beds wit h resins in the H and OH form. Resin is replaced when analys is of the influent and effluent indicates that the decontamination factor falls below the design value of 10 11.2.2.1 Laundry Waste Provision Toe provision for orocessing laundry wastes is optional, and whether the option is utilized is identified in the Utility - Applicant's SAR. It is described as an integral part of the plant. Lt.undry is processed primarily for environmental reasons, not radioactive decontamination. Therefore, solely for the purpose of estimating the liquid discharges, no credit is taken for the decontamination factors associated with the laundry waste processing equipment and the liquid waste is assumed to be discharged through only the low level waste effluent filters.

These liquid radioactive wastes are a small portion of the total liquid radioactive wastes generated by the plant, and are included in the totals reported for the plant. The refore ,

irrespective of whether the laundry is processed onsite or shipped offsite, there will be a minor reduction in the total liquid radioactive wastes reported for the plant.

Liquid from the laundry waste drain tanks is processed by the laundry waste evaporator. The laundry waste evaporator is designed to ,roduce a distillate suitable for discharge.

The laundry waste evaporator is a thin film evaporator which is expected to give a decontamination f actor of greater than 103 for g non-volatile nuclides in the soapy feed. The distillate from the laundry waste evaporator is condensed in a water cooled shell and tube laundry evaporator condenser, sent to the laundry waste distillate test tank, sampled for radioactivity and soap content, and, if within allowable limits , discharged.

11.?-5 Amendment 9

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SWESSAR-P1 If the distillate sample indicates an activity or soap content that is greater than allowable for discharge, the distillate is sent back to the laundry waste drain tank for reprocessing by the laundry waste evaporator or the low level waste drain tanks.

Laundry waste evaporator bottoriis are allowed to concentrate to approximately 25 percent solids by weight. The laundry waste evaporator bottoms are sent to the laundry waste bottoms tank which is emptied periodically by pumping to the radioactive 7l solid waste system (Section 11.5) for packaging and eventual shipment offsitc.

11.2.2.2 Input waste Streams 1

Inputs to the liquid waste system identified in Fig. 11.2-2 and 11.2-3 are described in more detail below.

IAundry Waste Drains The onsite laundry facilities produce low level laundry waste effluent which is collected in the laundry waste drain tank. The liquid from the laundry waste drain tank is treated in the laundry waste evaporator. The activity values are determined from estimates of the activity on the contaminated cloths, the amount of liquid used as wash and rinse liquids, and the average time before this activity enters the laundry waste drain tank.

Reacto; Plant and Turbine Plant Samples Operating procedures determine the exact frequency of samples and the amount of liquid required for sample line purging for each sample taken. However, based on the operating experiences and procedures followed at Connecticut Yankee, an estimate of the liquid that is generated was made, taking into account the additional unount of liquid that would be generated by the taking of more frequent samples to check the effectiveness of various pieces of equipment.

The level of sample activity was set at two values:

1. The reactor coolant activity (for reactor plant samples) ;

2 The main steam and feedwater system activity (for turbine plant samples).

Most samples taken have an activity below the values shown in Fig. 11.2-2 and 11.2-3 because they are taken from tanks where decay hes occurred, after equipment where purification has occurred, and from components where dilution has occurred.

9 11.2-6 Amendment 7

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SWESSAR-P1 Boron Recovery System Distillate The expected volumes of liquid discharged from the boron recovery system (Section 9. 3. 6) to the radioactive liquid waste system are based on the amount of reactor coolant that must be released from the reactor coolant system in order to maintain a water balance within the unit and to control the tritium concentration in the 9 reactor coolant. The activity in the boron recovery distillate is a function of the activity of the reactor coolant letdown fluid and the processing performed in the boron recovery system.

Spent Resin Flush The resin flushing and transfer operations described in Section 11.5 break loose corrosion products which collect on the surface of the resin beds. After the resin transfer is complete, a residual activity due to corrosion activation products remains in the transfer liquid. The excess water from the resin flushing and transfer operation, together with its accompanying activity, are discharged to the radioactive liquid waste system for processing. Activity levels shown are based on calculations of the activity that are built up on the resin after 90 days of operation, the decay of that activity during the buildup and in the transfer operation, the efficiency of the filter in removing corrosion products, and the amount of liquid used in the resin flushing and transfer operation.

Laboratory Wastes The volumes of liquid waste generated during the radiochemical analysis of samples, and subsequent cleanup operations, are estimated based on experience in radiochemical laboratories.

Diluted in this estimated volume of liquid are the samples themselves, which account for the activity present.

Mrated Vent f, Drain Systems Leakage to Sumps The uncollected leakage of reactor plant liquid which flashes or evaporates leaves behind a residue which is washed into various 9 sumps during cleanup operations or after maintenance. Estimates of the leak rates that could occur were made, and the total volume of liquid thus released was determined. Estimates were based on operating experience at Connecticut Y'a nkee. The activities shown in Fig. 11.2-2 and 11.2-3 are based on the time period that passes before the residue is washed into the sump.

The activities shown are representative of those that would be present assuming 30 days between floor washings.

Unlike reactor plant leakage, most of which is contained and collected, there are no collected valve stem leakoffs in the liquid side of the turbine plant system. Expected points of

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11.2-7 ' Amendment 9 LvU J 4/30/75

SWESSAR-P1 leakage, such as pump seals, have drains connected to local sumps. A small fraction of the total leakage is not collected by drains and arrives at the turbine building sump during floor washings or cleanup following maintenance. The activity levels shown in Fig. 11.2--2 and 11.2-3 are representative of this type of collection procedure.

Liquids resulting f rcun operation or maintenance are collected by the vent and drain system (Section 9.3.3) and are sent to the radioactive liquid waste system. Vent and drain waste liquids are segregated by piping arrangement and equipment layout in accordance with po tential activity level and/or ionic content.

Those liquids with an activity of greater than that specified previously are sent to the high level waste drain tanks for further processing by the waste evaporator in the radioactive liquid waste system.

91 Decontamination Drains These drains are from washdown of solid waste containers, spent fuel shipping ca sks , safety showers, and equipnent decontamination. This liquid is transferred from the vent drain system to the low level waste drain tank for sampling. If, unacceptable for discharge, it is pumped to the high level waste drain tank for processing in the liquid waste evaporator.

The activity values are determined form estimates of the amount of material washed from the containers, equipment, and personnel, as well as the wash and rinse volumes used.

Regenerative Chemical Waste The volume of chemical waste produced by the regeneration of the full-flow condensate polishing system is based upon estimates of long term main condenser inleakage. The waste is a dilute sodium sulfate solution with a basic pH and is concentrated to approximately 24 wt percent in the regenerant chemical evaporator. The activity is based upon estimates of the carryover fractions of radionuclides from the leaking steam generators and the expected frequency of regeneration. The time for a cycle of regeneration of all the demineralizers is assumed to be 30 days.

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SWESSAP-P1 11.2.2.3 Couponents Tables 11.2-1, 11.2-2, 11.2-3, and 11.2-4 summarize the desion and operating conditions of the radioactive liquid waste system cooponents.

The following inf ormation is included to supplement the tables:

Effluent Filters Low level waste effluent filters are either cartridge type pressure filters or stainless steel etched disc type. The stainless steel etched disc type filter elements are backwashable. ' 'e cartridge type filter elements ere designed for removal as a single basket assembly. In either case, the vessels are fabricated from stainless steel. Both methods are presently being considered.

Pumps Centrifugal frame mounted pumps with single or double mechanical seals are provided. Materials in contact with process fluids are l7 austenitic stainle ss steel. One pump is provided for each tank with cross ties where appropriate, such as on waste evaporator feed pumps. External cooling and seal water are supplied to 1 radioactive pump seals as required.

11.2.3 System Evaluation The radioactive liquid waste system has been classified as NNS (Quality Group D) in accordance with Regulatory Guide 1.26. An analysis of this system indicates that a failure of any component does not result in potential exposures in excess of 0.5 Rem whole body (o r its equivalent to parts of the body) at the nearest site boundary or beyond. The calculated potential exposure from various components is based on the following assumptions:

1. Fuel clad defects in fuel producing 1 percent of maximum design core power.

2. Accident met 90rology CHI /Q, as given in Section 2.3.

3. All the liquid in each component is released into t.to building.

4. 0.1 percent of iodine in the liquid in tanks becomes airborne.

5 0.75 percent af iodine .in both the waste evaporator and the recenerant chemical evaporator becomes airborne. I

6. No credit is taken for decay.

11.2-9 Amendment 7

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SWESSAR-P1

7. No credit is taken for mixing inside the building.

8. 1:o credit in taken for plateout inside the building.

In accordance with Regulatory Guide 1.29, the radioactive liquid waste system is classified as nonseismic. A postulated failure of the radioactive liquid waste system does not re sult in conservatively calculated potential offsite doses (using meteorology as given in Section 2.3) which are more than 0.5 Pem to the w' ole body or its equivalent to any part of the body. The system is located in the Seismic Category I annulus building to ensure that no radioactive liouids are released to the ground as a result of a seismic event.

11.2.4 Operating Procedures The vent and drain system sends liquid to the high and low level waste drain tanks . Before release of waste liquid from either the high or low level waste drain tanks, samples are taken to verify the radioactivity classification of the liquid in the tank. Provisions are made in the radioaccive liquid waste system to allow a transfer of the liauid between the high and low level waste drain tanks. This is done manually and only und er administrative control.

On determination that a liquid is classified as high level, it is processed by evapotation and sampled to determine suitability for discharge. It unsuitable for discharge, it is passed through a mixed bed demineralizer, waste demineralizer filter, samoled, and sent to either the environment or the primary grade water storage tanks.

Waste liquids classified as low level are sampled and, if suitable, discharged through the radioactive liquid waste system effluent filters to the environment. If the liquid is unsuitable for diccharoe, it is directed to the high level waste drain tanks.

g A radiation monitor measures the total discharge activity from

.. the radioactive liquid waste system to the environment. A high radiation alarm actuates (closes) a valve downstream of the

'] This prevents any inadvertent high level discharge to mon itor .

the environment. This valve fails closed upon a loss of actuating signal or air.

11.2.5 Performance Tests E H n s .'." ' nalyr-3 of Jignido beino processed for discharge, coupled with samples taken betore any processing occurs, yield information on the specific perfornance of each portion of the radioactive liquid waste system. On this basis, no periodic testing of the radioa ctive liquid waste system is required to 11.2-10 Amendment 7 2/28/75

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SWESSAR-P1 verify its performance, except for the radiation monitors which are tested periodically.

11.2.6 Estircated Releases The radioactive liquid releases from the various effluent streams and from the plant can vary from zero activity to the design basis case activities. The values for the design basis case activities and for the expected case are presented here. The radioactive liquid activity releases from each of the potential liquid effluent streams, in curies per year per nuclide, are given in Tables 11.2-5 through 11.2-16. These activity releases are design basis cases with clad defects in fuel producing 1 percent of maximum rated core power coincident with 1370 lb/ day primary-to-secondary leakage.

Table 11.2-17 sumarizes Tables 11.2-5 through 11.2-16 in curies per year m nuclide. Table 11.2-18 provides the annual average concentra.. ton in the discharge line for each nuclide for the design basis case.

Tables 11.2- 9 through 11.2-32 provide the corresponding information for operation with sources consistent with the source terms specified in the proposed American Nuclear Society Standard N-237.

The results given in Tables 11.2-5 through 11.2-32 and Fig. 11.2-2 and 11.2-3 for B&W are generally taken from previous analyses which were bacM on values of parameters slightly different than those given b Tables 11.1.2-1 and 11.2-5 thru 11.2-32. Since the n results are consistent with those already presented for the ]i and C-E NSSS, revisions in the calculations are nnnecessary for this application for Preliminary Design Approval.

11.2.7 Release Points All liquid effluent releases from the radioactive liquid waste system are discharged in the plant discharge line. The discharge location is discussed in the Utility-Applicant's SAR.

11.2.8 Dilution Factors The near field :lilution of radionuclides released to a river, lake, or ocean in the discharge water from the cooling system will be dependent upon the ocnfiguration of the discharge structure. When the receiving body is relatively nonturbulent, as may be the case with lakes and oceans, dilution in the far field will vary inversely with distance. Dilution in rivers is not as simply described, since it is dependeat on flow rate, geometry, bottom roughness, and density gradients (1). Moreover, in river systems, there is a maximum dilutioa which occurs when the effluent is fully mixed with the river flow. Since no single relationship is applicable to dilution in tae near and far fields 11.2-11 Amendment 19 g ,~q 12/12/75

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SWES S. '.2 -P 1 for any of the receiving bodies considered, a range of dilutions is employed r. the computations of dose. This provides a met hod by which doses can be determined based on the distance dilution relationship observed at a specific site. Nominal dilution factors for thi - three types of sites are listed in Table 11.6.2-1.

The process b', which aquatic organisms accumulate radionuclides from water is termed bioaccumulation. The ratio of the concentration of an element in a f resh- or salt-water organism to the concentration of the element in water is termed the ca ncentrz tion or bioaccumulation f a ctor. The concentration factors for stable elements listed in Table 11.2-33 for fresh-c2) and salt-waterca) organisms are used for the computation of dose.

Critical pathways are discussed in detail in Section 11.6.2.

11.2.9 Estimated Doses The various potential exposure pathways for man are discussed in Section 11.6.2. Upper limit dose estimates are presented for external and internal exposures to liquid ef fluents in tresh- and salt-water systems based on dilution ' factors obtained from a review of a number of existing sites.

Estimates of exposure based on the dilution f actors presented it.

Table 11.6.2-1 have been calculated and are presented in Table 11.2-34.

Table 11.2-35 presents a ccxnparison of calculated annual doses from liquid pathways resulting from discharges from the PWR Reference Plant with the minimal dilution conditions of a cooling tower blowdown dilution to those for a range of other plants and sites. (A total of 53 sites were reviewed camprising a total of 81 nuclear units.) Data for these plants were taken from the Final Environmental Impact Statements in each case. The maxirum, minimum, and average liquid discharges are presented in Table 11.2-35 along with the conservatively calculated liquid pathway doses. The comparable data for this plant as obtained from Table 11.2-34 are also reported in Table 11.2-35.

The population dose equivalent rates in terms of person Rem are tabulated in Table 11.2-36. The population density distributions in these analyses were d)tained from WASH-1258 as summarized in Chapter 2.

As can be seen f rom the data presented in Section 11.2-1, a BSW or W-3S NSSS has releases of the same order of magnitude as a W-41 or C-E NSSS. Consequently, Tables 11.2-34, 11.2-35, and 11.2-36 are not duplicated for W-3S and B&W.

25 The data reported herein represent conservative analytical approaches.

/ ' ,

b 'r n cuj 11.2-12 Amendment 25 4/30/76

SWESSAR-P1 11.2.10 Overflow of Tanks Table 11.2-38 provides a list of tanks outside the reactor containment which contain potentially radioactive materials.

Provisions for monitoring tank levels, annunciating potential overflow conditions, and collecting and processing liquid in the event of an overflow are listed.

11.2.11 _ Interface Requirements Radioactive nuclides inventories, liquid volumes, and shielding requirements utilized for the SWESSAR-P1 design are calculated by Stcne & Webster. NSSS Vendor interface information on the applicable systems and camponents is compared to Stone & Webster calculations. The applicable NSSS Vendor information is used to complement the Stone & Webster calculation if the comparison indicates that it is more conservative.

Doses will be estimated on a case-by-case basis in the U-A SAR to account for site-dependent variables such as dilution factors and pathways and to indicate conformance with the 10CFR50, Appendix 1, "ALARA" criterion. Realiscic dose models will be 25 used in those analyses.

References for 11.2

1. U.S.A.E.C. " Final Environmental Statement Concerning Proposed Rulemaking Action: Numerical Guides for Design Objectives and LCOs to Meet the Criterion "ALAP" for Radioactive Materials in Light Water Cooled Nuclear Power Reactor Effluents," WASH 1258, July 1973.

2. Thompson, S.E., Burton, C. A., Quinn, D. J., and Ng, Y. C.,

1972. " Concentration Factors of Chemical Effluents in Edible Aquatic Organisms," USAEC Report UCRL-50564, Rev. 1, University of California, Lawrence Radiation Laboratory.

3. Freke, A. M., "A Model for the Approximate Calculation of Safe Rates of Discharge of Radioactive Wastes into Marine Environments," Health Physics 13. 743-758. (1967).

9 11.2-13 Amendment 25

( (,8 [ 4/30/76

SWESSAR-P1 TABLE 11.2-1 CHARACTERISTICS OF PUMPS IN RADIOACTIVE LIQUID WASTE SYSTEM Waste Evaporator Feed Pumps Number 2 Capacity, gpm 50 Design pressure, psig 75 Design tmperature, F 180 Material of construction 304 SS Waste Evaporator Reboiler Pump Number 1 Capacity, gpm 2,750 Design pressure, psig 75 Design temperature, F 250 Material of construction 304 SS Waste Evaporator Bottoms Pump Number 1 Capacity, gpm 25 Design pressure, psig 20 Design temperature, F 250 Material of construction 304 SS 9

Waste Distillate Pump Number 1 Capacity, gpm 35 l9 Design pressure, peig 75 Design tmperature, F i 250 Material of construction 304 SS Waste Test Tank Pumps Number 2 Capacity, gpm 150 Design pressure, psig 125 Design tmperature, F 130 Material of construction 304 SS Low Level Waste Drain Pumps Number 2 Capacity, gpm 50 Design pressure, psig 50 Design temperature, F 130 Material of construction 304 SS Laundry Waste Drain Pump Number 1 Capacity, gpm 25 Design pressure, psig 150 Design temperature, F 200 Material of construction 304 SS 1 of 2 { ,{ Og 2[] Amendment 9 4/30/75

SWESSAR-P1 TABLE 11.2-1 (CONT)

Laundry Waste Distillate Test Tank Pump Number 1 Capacity, gpm 20 Design pressure, psig 150 Design tmperature, F 200 Material of construction 304 SS Laundry Waste Bottms Tank Pump Number 1 Capacity, gpm 15 Design pressure, psig 150 Design tmperature, F 300 Material of construction 304 SS Regenerant Chemical Evaporator Retoiler Pump h% ber 1 Capacity, gpm 2,750 Design pressure, psig 40 Design tmperature, F 250 Material of construction 304SS Regenerant Chemical Distillatt Pump Number 1 Capacity, gpm 35 l9 Design pressure, psig 75 Design tmperature, F 250 Material of construction 304SS Regenerant Chemical Evaporator Bottoms Pump

. Number 1 Capacity, gpm 25 Design pressure, psig 20 Design tmperature, F 250 Material of construction 304SS 9

9 2 of 2 (0 '[ g ; Amendment 9 bud 4/30/75

SWESSAR-P1 TABLE 11.2-2 CHARACTERISTICS OF DEMINERALIZERS AND FILTFRS IN RADIOACTIVE LIQUID WASTE SYSTEM Waste Demineralizer(2) (2)

Number 1 Size, ft3 35 Through put, gpm, each 150 Type Mixed bed Material of container structure 304 SS Design pressure, psig 225 2 Design temperature, F 250 Effluent filters (1)

Ntrnber 2 Through put, gpm, each 50 Type Wound fiber or SS disc Material of container structure 304 SS Design pressure, psig 225 2 Design temperature, F 250 Waste Demineralizer Filterta)

Number 1 Through put, gpm, each 150 Type Wound fiber or SS disc Material of container structure 304 SS Design pressurc, psig 225 l2 Design temperature 250 (8) Designed in accordance with ASME VIII, Division I.

(2) Design temperature is for vessel only, not internals.

1 of 1 Amendment 2 8/30/74

SWESSAR-P1 TABLE 11.2-3 CHARACTERISTICS OF TANKS IN RADIOACTIVE LIQUID WASTE SYSTEM 0

High Level Waste Drain Tanks Number 2 Capacity, gal 25,000 Operating pressure, psig Atmo spheric Design pressure, psig Atmospheric l10 Design temperature, F 200 Material of construction 316 SS or fiberglass ,10 Low Level Waste Drain Tanks l10 Number 2 Capacity, gal 4,000 Operating pressure Atmospheric Design pressure, psi? Atmospheric l10 Design temperature 200 Material of construction 316 SS or i 10 fiberglass i Waste Distillate Tank l10 Number 1 Capacity, gal 550

@ Operating pressure, psig 15 Design pressure, psig 100/fu11 vacuum Design temperature, F 350 Material of construction 304 SS Waste Test Tanks \10 Number 2 Capacity, gal 18,000 Operating pressure Atmospheric Design pressure, psig Atmospheric l 10 Design temperature, F 250 Material of construction 304 SS or 10 fiberglass Waste Evaporator Body

• Number 1 Capacity, gpm 25 Opc ating pressure, psig 15 Design pressure, psig 100/ full vacuum Design temperature, F 350 Material of construction Incoloy and 316 SS b0 L

• Designed in accordance with ASME VIII, Division I 1 of 3 Amendment 10 5/15/75

SWESSAR-P1 TABLE 11.2-3 (CONT)

Laundry Waste Drain Tank l10 Number 1 Capacity, gal 4,000 Operating pressure Atmospheric Design pressure, psig Atmospheric \10 Design iemperature, F 200 Material of construction 316 SS or fiberglass 10 Laundry Waste Evaporator Body

• Number 1 Capacity, gpm 2 Operating pressure Atmospheric Design pressure, psig 100/ full vacuum Design temperature, F 350 Material of construction 316 SS Laundry Waste _Bottczns Tank l:0 Number 1 Capacity, gal 200 Operating pressure Atmospheric Design pressure, paig Atmospheric Design temperature, F 300 l10 Material of construction 304 SS or fiberglass 10 Laundry Waste Distillate Test Tank

• Number 1 Capacity, gal 2,000 Operating pressure Atmospheric Design pressure, psig 25 Design temperature, F 350 Material of construction 304 SS Regenerant Chemical Evaporator Body

• thmtber 1 Capacity, gpm 25 Operating pressure, psig 15 Design pressure, psig 100/ full vacuum Design temperature, F 350 Material of construction Incoloy and 316SS

@ f:n Uvv or[

c. V J

• Designed in accordance with ASME VIII, Division I 2 of 3 Amendment 10 5/15/75

SWESSAR-P1 TABLE 11.2-3 (CONT)

Regenerant Chemical Distillate Tank

• Number 1 Capacity, gal 550 Operating pressure, psig 15 Design pressure, psig 100/ full vacuum Design temperature, F 350 Material of construction 304SS

'O (i c a s

7b

• Designed in accordance with ASME VIII, Division I 3 of 3 Amendment 10 5/15/75

SWESSAR-P1 TABLE 11.2-4 CPARACTERISTICS OF HEAT EXCHANGERS IN RADIOACTIVE LIQUID WASTE SYSTEM Waste Evaporator Rebeiler Quantity 1 Duty, Btu /hr 15,400, .0 lg Saturated Steam (shell)

Operating pressure, psig 100 Design pressure, psig 200/ full vacuum Design temperature, F 400 Operating temperature, in/out, F 338/338 Liquid Waste (tube)

Operating pressure, psig lg 35 Design pressure, psig 100/ full vacuum Design temperature, F 400 Operating temperature, in/out, F 253/264 Waste Distillate Cooler {g Quantity 1 Duty, Btu /hr 1,630,000 \g Distillate (tube)

Operating pressure, psig 35 Design pressure, psig 100/ full vacutrt Design totaperature, F 350 Operating temperature, in/out, F 250/120 Cornponent Cooling Water (shell)

Operating pressure, psig 125 Design pressure, psig 175/ full vacuum Design temperature, F 175 Operating temperature, in/out, F 105/120 Waste Evaporator Cmdenser Quantity 1 Duty, Btu /hr 13,000,000 Saturated Steam (shell)

Operating pressure, psig 15 l9 Design pressure, psig 175/ full vacuum Design temperature, F 350 Operating temperature, in/out, F 250/250 Component Cooling Water (tube)

Operating pressure, psig 125 Design pressure, psig 175/ full vacuum Design temperature, F 350 Operating temperature, in/out, F 105/135 Regenerant Chemical Evaporator Reboiler Quantity 1 Duty, Btu /hr 15,400,000 lg 1 of 2 Amendment 9

- }j 4/30/75 6/n 0o

SWESSAR-P1 TABLE 11.2-4 (CONT)

Saturated Steam (shell)

Operating pressure, psig 100 Design pressure, psig 200/fu11 vacuum Design temperature, F 400 Operating temperature, in/out, F 338/338 Sodium Sulphate Solution (tube) k9 Operating pressure, psig 35 Design pressure, psig 100/ full vacuum Design temperature, F 400 Operating temperature, in/out, F 253/264 Regenerant Distillate Cooler 9 Quantity 1 Duty, Btu /hr 1,630,000 gg Distillate (tube)

Operating pressure, psig 35 Design pressure / psig 100/ full vacuum Design temperature, F 350 Operating temperature, in/out, F 250/120 Component Cooling Water (shell)

Operating pressure, psig 125 Design pressure, psig 175/ full vacuum Design temperature, F 175 Operating temperature, in/out, F 105/120 Regenerant Chemical Evaporator Condenser Quantity 1 Duty, Btu /hr 13,000,000 {g Saturated Steam (shell)

. Operating pressure, psig 15 Design pressure, psig 175/ full vacuum Design temperature, F 350 Operating temperature, in/out, F 250/250 Component Cooling Water (tube)

Operating pressure, psig 125 Design pressure, psig 175/ full vacuum Design temperature, F 350 Operating temperature, in/but, F 105/135 Laundry Waste Evaporator Condenser Quantity 1 Duty, Btu /hr 1,250,000 Distillate (shell)

Operating pressure, psig 15 Design pressure, psig 30 Design temperature, F 350 Operating temperature, in/out, F 212/120 Ccxnponent Cooling Water (tube)

Operating pressure, psig 125 Design pressure, psig 150

@, Design temperature. . 350 Operating temperatuw, in/out, F 105/135 2 of 2 'Cl Amendment 9 bboO 4/30/75

SNESSAR-P1 9

Table 11.2-5 is deleted.

1 f I Amendment 9 14/30/75

/ (, 0 nL'c- ].

O U ')

G SWESSAR-P1 TABLE 11.2-6 ACTIVITY FROM DECONTAMIKATION DRAINS (DESIGN CASE)

Decontamination factor of waste dinposal system for this source = 1.00E 04 l11 Decay time in waste disposal systesa (hours) = 2.00E 01 (Max.)

Flow rate (gal /yr) = 1.64E 04 h&W C-E W Discharge Discharge Discharge Activity Rate From Activity Rate Fram Activity Rate Frma Initial After Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treatment posal Sys- Activity Treatment posal Sys- Activity Treatment posal Sys-Nuclide (uCi/cc) (uCi/cc) tem (Ci/yr) (uCi/cc) (uCi/cc) tem (Ci/yr) (uCi/ 'c) (uCl/cc) t an (Ci/yr)

ER83 6.3E-06 1.9E-12 1.2E-10 1.04E-06 3.22E-13 1.98E-11 7.50E-07 7.13E-11 4.4 2E-09 nh84 5.9E-07 2.6E-22 1.6E-20 1.04E-07 4.54E-23 2.78E-21 7. 22 E-08 4.70E-12 2.91E-10 nub 5 7.7E-09 2.9E-56 1.8E-54 1. 3 5 E-0 9 5.02E-57 3.08E-55 4 .14 E-0 9 6.08E-14 3.77E-12 1131 2.5E-02 2.3E-06 1.4E-04 6.57E-03 56.12E-07 3.75E -O S 3 . 06 E-03 3.06E -07 1.90E-0 6 1132 9.9E-04 7. 7E -0 8 4.9E-06 1.91E-04 1.54E-08 9.46E-07 1.33E-04 1.33E-08 8.23E-07 1133 3.2E-03 1.6E-07 1. 0 E-0 5 4.89E-04 2.51E-08 1.54E-06 8.02E-04 8.02E-08 4 .97E -0 6 1134 1.4 E-0 5 1.8E-16 1.1E-14 2. 4 2E-0 6 3.00E-17 1.84E-15 1.44E-06 1.10E-10 6.79E-09 1135 5.0E-04 5. 9E-09 3.7E-07 7.51E-05 9.43E-10 5.7 8E -0 8 1.45E-04 1.44E-08 6 . 9 4 E-07 RB88 3.0E-05 1.2E-29 7.2E-28 4 . 8 4 E-0 6 1.90E-30 1,16E-28 3.41E-04 3.39E-08 2.10E-06 SR89 2.5E-04 2.4E-04 1.5E-06 1.05E-04 1.04E-08 6.36E-07 4.03E-05 4.03E-09 2.50E-07 SR90 2.4E-05 2.4E-09 1.5E-0 7 1.10E-0 5 1.10E-0 9 6.74E-08 4 .13 E-0 6 4.13E-10 2 .5 6 E-0 8 SR91 5.3E-07 1.5E-11 9.6E-10 1.00E-07 2.38E-12 1.46E-10 2.06E-07 2.06E-11 1.28E-09 Y90 2.4E-05 2.4 E-0 9 1.5E-07 1.10 E-0 5 1.10E-09 6.74E-08 4.08E-06 4.08E-10 2.53E-08 Y91 4.0 E-0 4 3.9E- 08 2.4 E-0 6 1.59E-07 1.59E-11 9.82E-10 Y91M 2.9E-07 9.9E-12 6.2E-10 4 . 50 E-0 8 1.54E-12 9.45E-11 1.25E-07 1.24E-11 7.71E-10 Y93 1.8E-07 4.5E-12 2.8E-10 1.83E-08 4.70E-13 2.88E-11 3.76E-08 3.76E-12 2.33E-10 g ZR95 5.0E-05 5. 0E-0 9 2.9E-07 2. 06 E-05 2.04E-09 1.2SE-07 7.87E-06 7.87E-10 4.88E-08 NB95M - - -

1.59E-07 1.59E-11 9.82E-10 NB95 6.8 E-05 6.3E-09 4.1E-07 2. 7 4 E-0 5 2.70E-09 1.65E-07 1.15E-0 5 1.15E-09 7.11E-08 MO99 7.7E-03 6.3E-07 3.8E-05 4 . 06 E-0 4 3.30E-08 2.02E-06 3.12E-04 3.12E-08 1.94E-06 TC99M 7.2E-03 5.9E-07 3.7E-05 3.79 E-04 3.18E-08 1.95E-06 2.83E-04 2. 8 3E -0 8 1.76E-06 RU143 1.7E-05 1. 6E-09 1.0E-07 6.79E-06 6.69E-01 4.10E-08 2.61E-06 2.61E-10 1.62E-08 hul06 3. 8 E-0 6 3.8E-10 2.4E-08 1. 75E-0 6 1.75E-10 1.07E-08 6.57E-07 6.57E-11 4.07E-09 RH103M 1.7E-05 1. 6E-0 9 1.0E-07 6 .8 0E-0 6 6.56E-10 4.02E-08 2. 62 E-0 6 2.62E-10 1.62E-08 RH106 3.8E-06 3.8E-10 2.4E-08 1.75E-06 1.75E-10 1.07E-08 6.57E-07 6. 57E-11 4.07E-09 TE125M 5.4E-05 5.4E-10 3.4E-08 2. 36 E-0 6 2.34E-10 1.43-C8 CTN TE127M 1. 8 E-0 4 1.8E-10 1.1E-0 6 7. 9 2E-0 5 7.88E-09 4.83-07 3. 01E-0 5 3.01E-09 1.86E-07 rycs TE127 1.8 E-0 4 1.8E-10 1.1E-0 6 7.9 4 E-0 5 7.86E-09 4.81E-07 3.01E-05 3.01E-09 1.87E-07 TE129M 1.7E-03 1.6E-07 1.8 E-0 5 6.6 9 E-04 6.58E-08 4.03E-06 2.57E-04 2.57E-08 1. 59 E -0 6

(;3 2.58E-06 2.54E-04 2.54E-08 1.5EE-06 TE129 1. 7E-0 3 1. 0 E -07 6.5E-06 6.70E-04 4.22E-08 TF131M 2.7E-05 1.7E-09 1.1E-07 4 . 3 4 E-0 6 2.73E-10 1.68E-08 5.710.-06 5.71E-10 3.54E-08 TE131 5.4E-06 3.1E-10 1.9E-08 8 .9 3 E-07 4.99E-11 3.06E-09 1.09 E-0 6 1.08E-10 6.69E-09 P3 TE132 9.0E-04 7 .7E-0 8 4 .7E-06 1.79E-04 1.50E-08 9.18E-07 1.24E-04 1.24E-08 7.70E-07

- ') CS134 4 .1 E-0 2 4.1E-06 2.be-04 2.42E-02 2. 4 2 E -06 1.48E-04 7.15E-03 7.15E-07 4.43E-05

_m CS136 2.4 E -0 3 2.3E-07 1.5E-05 2.65E-03 2.54E-07 1.56E-05 4.92E-04 4.92E-08 3 .0 $E-0 6 CS137 2.2E-01 2.2E-05 1.4E-03 1.02E-01 1.02E-0 5 6.25E-04 3.86E-02 3.86E-06 2.39E-04 1 oi 2 Luendment 19 12/12/75

SWESSAR-P1 TABLE 11.2-6 (Coffr)

Bcw C-E w Discharge Discharge Discharge Activity Rate From Activity Rate Fram Activity Rate Prom Initial After Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treatment posal Sys- Activity Treatment posal Sys- Activity Treatment posal Sys-tiuclide (uCi/cc) (uci/cc) tem (Ci/yr) (uci/cc) (uci/cc) tem (Ci /yr) (uCi/cc) uC1/cc) tem (Ci/yr)

CS138 - - -

1. 66 E-0 9 1.66E-13 1.03E-11 BA137M 2. 0 E-01 2.1E-05 1.3r-03 9. 4 3E-0 2 9. 5 4 E-0 6 5.94E-04 3.55E-02 3.55E-06 2. 2 0 E-04 BA140 7.2 E-0 5 6.8E-09 4.2E-07 2. 2 6 E-0 5 2.16E-0 9 1.32E-07 3 . 51E-0 6 9.51E-10 5.90E-08 LA140 7.7E-05 7. 2E-09 4.5E-07 2.51E-05 2.42E-09 1.48E-07 9. 91E-0 6 9.91E-10 6 .14 E-0 8 CE141 2.8E-05 2.8E-09 1.7E-07 1.14 E-0 5 1.12E -0 9 6.86E-08 4.42E-06 4.42E-10 2.74E-08 CE143 6.8E-07 4.4E-11 2.7E-09 1. 0 8 E-0 7 7.10E-12 4.35E-10 1.34E-07 1.34E-11 8.30E-10 CE144 5.4E-05 5. 4 E-09 3.4E-07 2 .5 2 E-0 5 2.51E-09 1.54E-07 9. 4 9E -0 6 9.49E-10 5.88E-08 PR143 1.2E-05 1.2E-09 7. 2E -0 8 3.87E-06 3.71E-10 2.27E-08 1.69E-06 1.69E-10 1.05E-08 PR144 5.4E-05 5 . 4 E-0 9 3. 4 E-0 7 2.52E-05 2 . 51 E -O '. 1.54E-07 9.49E-06 9.49E-10 5.8 8 E-08 18 NP239 9.0 E-0 6 7.2E-10 4.4E-08 1.6 3 E -0 6 1.27E-10 7.81E-09 2.19E-04 219.E-08 1.36E-06 CR51 9.0E-04 9.0E-08 5.5E-06 1.61E-0 3 1. 58 E-07 9. 6 6E -0 6 7.90E-04 7.9 0 E-08 4.90E-06 MN54 8.1E-04 8.1E-08 5.1 E-0 6 1.6 3 E-0 3 1.63E-07 9 . 9 7E-0 6 7.40E-04 7.40E-08 4.59E-06 MN56 1.2E-06 5.4E-13 3.4E-11 3. 8 9 E-0 4 3.89E-08 2 . 41E-0 6 FESS 5.0 E-0 3 5.0E-07 3 .1E-0 5 9.8 0 E-0 3 9.79E-07 6.00 E-0 5 4 . 4 2 E-0 3 4.42E-07 2.74E-05 PE59 3.0E-04 8.6E-08 5.4E-06 1.64E-03 1. 62 E-07 9. 9 2E-0 6 7.73E-04 7.73E-08 4 .79 E-0 6 C058 2.2E-02 2.2E-06 1.3E-04 4.17E-02 4.14E-06 2.54E-04 1.94E-02 1.94E-06 1.20E-04 CO60 6.3E-03 6.3E-07 4.0E-05 1. 27E-0 2 1. 2 7E-0 6 '.78E-05 5.79E-03 5.79E-07 3.59E-05 TOTAL 5.4E-01 5.4E-05 3.4E-03 3. 0 2 E -01 3. 02 E-0 5 1.85E-03 1. 20 E-01 1.20E-05 7.45E-04 Ch CA CO PJ

.)

I' J 2 of 2 Amendment 19 12/12/75

g 95 17

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EEEEEEEEEE E A EEE h el( EE EEEEEEEEEEEEEEEEEEE 0767718520 1 000 ceta 96 2653576151496677013 000 stssm iaaoe 24022028287760435760170 9 6 4 1 3 3 0 1.R. 6 0 8 123 D R W pt 22022282331437866533310 123312231103 t 7862615554 7 y n) 87 4742547880508856894 0001020000 0 t ec 01 0001020000100000001 i mc - -

EEEEEEEEEE E W vrt/ E8 EEEEEEEEEEEEEEEEEEE 7559033801 6 iea1 17 5905180188080783842 630720876403 tteC 01099825845112467026750 cf ru 123212121103 AAT( 22011172231436755532210 y) 22301010034354444114545 332222111003

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e y t s s l y nct) a w a t ec 8704542547b8888774489898776667555447 s i m/ 0150001020O0000000000000000000000000 f o vrti o p ieaC EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE 980747114606366111923134389806341764 s W tteu r i & cf r(

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oc l irna i v/

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ncu 9453155236323161 13255551316331352226 nse IAf i me msit aita e th r d M MM M M M nty M36365779911246770 i

o aw l 345123458901 d 5599000022222333333341111 11111 crco c 888333338899013999911111111 eoel N

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3) aj N :s3 j P-(

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G t SWESSAR-P1 TABLE 11.2-7 (CONT)

B&W C-E W Discharge Discharge Discharge Activity Rate From Activity Rate Fram Activity Rate Prom Initial After Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treatment posal Sys- Activity Treatment posal Sys- Activity Treatment posal Sys-Nuclide fuci/cc) p C1/cc) tem (Ci/yr) (uci/cc) (uci/cc) tem (Ci/vr) (uci/cc) uCi/cc) tem (Ci/yr)

LA140 2.8E-03 3.9E-07 4.4E-06 1.43E-03 2.21E-0 7 2.47E-06 1.11E-03 7.86E-08 8.93E-07 CE141 1.1E-03 1.1E-07 1.2E-06 6. 62 E-04 6.5 0 E-0 8 7.29E-07 5.53E-04 5.43E-08 6.17E-07 CE143 7.0E-04 4 .6 E -0 8 5. 2E-0 7 4 . 96 E-0 4 3.26E-08 3.f5E-07 4.31E-04 2.83E-08 3.22E-07 CE144 8. 0 E-0 4 8.0E-08 9.1E-07 4.93E-04 4 .92E-0 8 5.52E-07 4.10E-04 4.09E-08 4.65E-07 l 1.0 E -0 3 1.1E-06 6.41E-04 6 .14 E-0 8 6.89E-07 5 . 35 E-0 4 5.13E-08  %.034-07 PR143 9.9E-08 PR144 8.0E-04 8.0E-03 9,.1E-07 4 .9 3 E-0 4 4 .9 2 E-0 8 5.52E-07 4.11E-0 4 4.61F-23 5.23E-28 4 .3E -0 7 4.9E-06 3.70 E-0 3 2.89E-07 3.25E-06 3.19E-03 2.50E-07 2.84E-06 NP239 5.5E-03 9.3E-03 9.1E-07 1.0E-05 5.79E-03 5.6 7E -0 7 6.36E-06 4.88E-03 4.78E-07 5.43E-06 g CRS1 1.5E-07 1.7E-0 6 9.4 3E-0 4 9.41E-08 1.06E-06 7. 93 E-0 4 7.91E-08 8.99E-07 MN54 1.5E-03 1. 57E-07 MN56 1. 6 E-02 7.5E-09 8.5E-08 2. 97E-0 2 1.38E-08 7.9E-07 9.0 E-0 6 4 . 8 7E -0 3 4 . 8 7E-07 5.46E-06 4.09E-03 4.09E-07 4.64E-06 FE55 7.9E-03 FES9 4.9E-03 4.9E-07 5.5E-06 3.05E-03 3. 01E -0 7 3.38E-06 2.56E-03 2. 5 3E-07 2.87E-06 7.8 E-0 6 8 .9E-0 5 4. 8 7E-0 2 4 . 8 3E-0 6 5.42E-05 4 .10 E-0 2 4.07E-06 4.62E-05 CO58 7.9 E -0 2 CO60 9.9E-03 9. 9E-07 1.1E-05 6.09E-03 6.09E-07 6.83E-06 5.12E-03 5.12E-07 5 . 81E -06 TOTAL 3,0E 01 ' .0E-0 4 3 2. 2 E-02 192E+01 1. 05E-0 3 1.18E-02 1.68E 01 6.70E-04 7.61E-03 G

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~

2 of 2 Amendment 19 12/12/75

9 SWESSAR-P1 TABLE 11.2-8 ACTIVITY FROM BORON RECOVERY LE'IDOWN (DESIGN CASE)

Decontamination tactor of waste disposal system for this source = 1.00E 00 Decay time in waste disposal system (hours) = 0.0 Flow rate (gal /yr) = 1.2SE 05 B&W C-E W Discharge Discharge Discharge Activity kate From Activity Rate From Activity Rate From Initial Alter Waste Dis- Initial After Waste Dis- Initial After huste Dis-Activity Treatme nt posal Sys- Activity Treatment posal Sys- Activity Treatment posal Sys-Nuclide (uci/cc) (uci/cc) tem (Ci/yr) (uci/cc) (uci/cc) tem (Ci/yr) (uci/cc) (uCi/cc) tem (Ci/yr)

BR83 1.4 E -0 8 1. 4 E-08 6.4E-06 3.54E-08 3.54E-08 1.66E-05 3.44E-08 3.44E-08 1.63E-05 BR84 1.3E-0 9 1.3E-09 6. 2E-0 7 3. 61 E-09 3.61E-OS 1.69E-06 3.60E-09 3.60E-09 1.70E-06 BR85 1.7E-11 1.7E-11 7.9E-09 4.69E-11 4.69E-11 2.19E-08 4.72E-11 4.72E-11 2.23E-08 1131 2 .7 E-0 5 2.7E-05 1.3E-02 2.16E-05 2.16E-OS 1.01E-02 1. 82 E-05 1. 8 2E-0 5 8.61E-03 I132 1.8E-06 1. 8 E-0 6 8.4E-04 2.11E-06 2.11E-06 9.88E-04 1.83E-06 1.83E-06 8.66E-04 1133 6.8E-06 6.8E-06 3.2E-0 3 1.33E-05 1. 3 3E-0 5 6.21E-03 1.18E-05 1.18E-05 5.58E-03 1134 3.1E -0 8 3.1E-0 8 1.5E-05 8.36E-08 8.36E-08 3.91E-05 8.28E-08 8.28E-08 3.92E-05 1135 1.0E-06 1.0E-06 4.9E-04 2. 4 5E-0 6 2. 4 5E-0 6 1.15E-03 2. 29 E-0 6 2. 29E-06 1.0 8 E-0 3 Rb88 6. 5 E-0 8 6 . 5E -0 8 3.1E-05 1.68E-07 1.68E-07 7.86E-05 1.66E-06 1.66E-06 7.85E-04 SR89 6.2E-08 6.2E-08 2.9 E-0 5 4. 0 2E-0 8 4 . 02E-0 8 1.8dE-05 3. 36 E-0 8 3.36E-08 1. 59 E-05 SR90 3.0 E-0 9 3.0E-0 9 1.4E-06 1.8 2 E-09 1.82E-09 8.51E-07 1.51E-09 1.51E-09 7.14E-07 SR91 1.4E-09 1.4E-09 6.6E-07 3.16E-09 3.16E-09 1.4 8 E-06 2. 91E-0 9 2.91E-09 1.38E-06 Y90 3.1E-09 3.1E-09 1.5E-06 9.57E-10 9.57E-10 4.48E-07 7.75E-10 7.75E-10 3.67E-07 Y91M 9.0E-10 9.0E-10 4.2E-07 2.02E-09 2.02E-09 9.44E-07 1.30E-09 1.30E-09 6.15E-07 Y91 9.2E-08 9.2E-08 4.3E-C5 1.02E-10 1.02E-10 4.83E-08 Y93 3.8E-10 3.8E-10 1.8E-07 5.75E-10 5.75E-10 2.69E-07 5.27E-10 5.27E-10 2. 4 9 E-07 ZR95 1.0E-08 1. 0E -0 8 4.9E-06 6. 6 6 E-09 6. 6 6 E-0 9 3.11E-06 5.55E-09 5.55E-09 2.63E-06 NB95M - - -

3.00E-11 3.00E-11 1. 4 2E-08 Nb95 1.0E-08 1. 0E-0 8 4.9E-06 6. 8 0 E-0 9 6. 80 E-0 9 3.18E-Of 5.86E-09 5.86E-09 2.7 7E-06 MO99 1.4E-05 1.4E-05 6.8E-03 4 . 8 7E-0 6 4 . 8 7E-0 6 2.28E-03 4.17E-06 4.17E-06 1.97E-03 TC99M 1.3E-Oi 1.3E-05 6.4E-03 4 . 41 E-0 6 4 .41E-0 6 2. 0 6E-0 3 3.70E-06 3,70E-06 1.75F-03 RU103 4.9E-09 4 .9 E-0 9 2 . 3E-0 6 3.15E-09 3.16E-09 1.48E-06 2 . 64 E-0 9 _ 4E-09 1.2 5 E-06 kul06 5.3E-10 5.3E-10 2.5E-0 7 3.27E-10 3.27E-10 1. 5 3E -07 2.73E-10 2.7iE-10 1.29E-07 R11103M 4 .8 E -0 9 4 .8 E-0 9 2.2E-0 6 3.10 E-09 3.10E-09 1.45E-06 2.64E-09 2.64E-09 1.25E-06 RH 106 5.3E-10 5.3E-10 2.5E-07 3.27E-10 3.27E-10 1. 5 3E-0 7 2.73E-10 2.73E-10 1.29E-07 TE125M 1.3E-09 1. 3E -0 9 6.1E-07 8.26E-10 8.26E-10 3. 8 6E-0 7 TE127M 3.2E-08 3.2E-08 1.5E-05 1.99E-08 1. 99E-0 8 9.30E-06 1.66E-08 1.66E-08 7. 8 5 E-06 C?N TE127 3. 0 E-0 8 3 .0E-0 8 1.4 E-0 5 1.8 2 E-08 1. 8 2E-08 8.52E-0 6 1.56E-08 1.56E-08 7.38E-06 r; TE129M 5.5E-07 5.5E-07 2.6E-04 3.59E-07 3.59E-07 1.68E-04 2.99E-07 2.99E-07 1.41E-04 in TE129 3.5E-07 3.5E-07 1.6E-04 2. 3 0 E-07 2. 3 0E-07 1.07E-04 2.97E-07 2.97E-07 1.41E-04 TE131M 5.8E-08 5.8E-08 2.7E-05 9. 8 8 E-0 0 9 . 8 8 E-0 9 4.62E-05 8.65E-08 8.65E-08 4.09E-05 TE131 1.1E-08 1.1E-08 5. 0E-0 6 1. 8 5 E-0 8 1.85E-08 8. 6 5E-0 6 1.80E-08 1. 8 0E -0 8 8 .52E-0 6 TE132 1.6E-06 1. 6E-0 6 7.7E-04 1.81E-U6 1.81E-06 8.49E-04 1.54E-06 1.54E-06 7.29E-04 F ) CS134 5.4E-06 5.4E-06 2.6E-03 4.24E-06 4.24E-06 1.98E-03 2.78E-06 2.78E-06 1.32E-03 s CS136 1.7E-0 6 1.7E-06 8.2E-04 4.09E-06 4 . 0 9 E-0 6 1.91E-03 1. 5 3 E-0 6 1.53E-06 7.24E-04

(' CS137 2.7E-05 2.7E-05 1.3E-02 1.6,3-05 1. 69 E-0 5 7. 9 0E-0 3 1.41E-05 1.41E-05 6 . 6 7E-03 CS138 - - -

2.35E-08 2.35E-08 1.11E-05 1 or 2 Amendment 19 12/12/75

SWESSAR-P1 TABLE 11.2-8 (Coffr)

B&W C-E W Discharge Discharge Discharge Activity hate Prom Activity Rate Prom Activity Rate Fruc Initial After Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treatment }csal Sys- Activity Treatment posal Sys- Activity Treatment posal Sys-Nuclide fuci/ccl (uci/cc) tem (C1/yr) (uci/ce) (uci/cc) ten (Ci/yrl (uCi/cc) uCi/cc) tem (Ci/yr)

BA137M 2.6E-05 2.6E-05 1.2E-02 1.5 8 E-0 5 1.5 8 E-0 5 7.39E-03 1.30E-05 1.30E-05 6.15E-03 BA140 5.2E-08 5.2E-08 2.5E-05 3.82E-08 3 . 8 2E-0 8 1.78E-05 3.20E-08 3.20E-08 1.51E-05 LA140 4.8E-08 4 . 8 E-0 8 2.3E-05 2.60E-08 2.60E-08 1.22E-05 2.13E-OS 2.13E-08 1.01E-05 CE141 9 .7E -0 9 9.7E-09 4.6E-06 6 . 38 E-0 9 6.38E-09 2.98E-06 5.33E-09 5.33E-09 2.52E-06 CE143 1. 4 E -0 9 1.4 E -0 9 6 . 7E -0 7 2.33E-09 2 33E-09 1.09E-06 2.04E-09 2.04E-09 9.65E-07 CE144 7.9E-09 7.9E-09 3.7E-06 4.41E-09 4.91E-09 2.30E-06 a.08E-09 4. 0 8 E -09 1.93E-06 PR143 8.1E-09 8 .1E-0 9 3. 8 E -06 5.87E-09 5.87E-09 2.74E-06 5.12E-09 5.12E-09 2. 4 2E-06 PR144 7.9E-09 7. 9 E-0 9 3. 7E-0 6 4.91E-09 4.91E-09 2.30E-06 4 . 0 8 E-0 9 4 . .' 8 E-0 9 1.93E-06 14P239 1. 8 E-0 8 1.8 E-0 8 6.5E-06 2. 31E-0 8 2. 31E -0 8 1.08E-05 CR51 8.3E-08 8.3E-08 3.9E-05 5. 5 4 E-0 8 5.54E-08 2.59E-05 4.67E-08 4.67E-08 2.21E-05 MN54 1.5E-08 1.5F-08 7. 2E-0 6 9. 39 E-09 9 . 3 3 E-09 4.39E-06 7. 9 0 E-0 9 7.90E-09 3.74E-06 MN56 2.5E-09 2.5E-09 1.2E-06 1.33E-08 1.33E-08 6.29E-06 FESS 7.9E-08 7. 9E -0 8 3.7E-05 4.86E-08 4 . 8 6E -0 8 2.27E-05 4 . 0 8 E-0 8 4 . 0 8 E -0 8 1.9 3 E-05 FES9 4.6E-08 4 . 6 E -0 8 2.2E-05 2.97E-08 2.97E-08 1.39E-05 2.49E-08 2.49E-09 1.18E-05 C058 7.5 E-0 7 7.5E-07 3. 6 E-0 4 4.79E-07 4.79E-17 2.24E-04 4.03E-07 4.03E-07 1.91E-04 CO60 9 .9 E-0 8 9.9E-08 4 .7 E-0 5 6.09E-08 6.0 9E-6 ? 2.85E-05 5.12E-08 5.12E-08 2.42E-05 TOTAL 1.3E-04 1.3E-04 6.1E-02 9. 35 E-0 5 9.35E-05 4.37E-02 7.82E-05 7.82E-05 3.70E-02 C?N r :r C. D FJ

- 3 Cx 2 of 2 Amendment 19 12/12/75

SWESSAR-P1 TABLE 11.2-9 ACTIVITY FROM SPENT RESIN FLUSII (DES IGN CASE)

Decontamination f actor of waste disposal system for this soaree= 1.00E 04 Decay time in waste disposal systen (hour s) = 2.00E 01 Flow rate (gal /yr) = 2.30E 04 B&W C-E W Discharge Discharge Discharge Activity Rat e From Activity Rate From Activity Rate From Initial After Waste Dis- Initial After Waste Dis- Initial After War.te Dis-Activity Treatment posal Sys- Activity Treatment posal Sys- Activity Treatment posal Sys-Nuclide JuCi/cc) JuCi/cc) M (Ci/yr) JuCi/cc) (uCi/cc) tem (Ci/y r) JuCi/cc) uCi/cc) tem (Ci/yr)

CR51 7.1E-02 7.0E-06 6.1E-04 7.15E-02 7.00E-06 6.04E-04 2.84E-02 2.78E-06 2. 4 2E -04 MN54 2.7E-02 2 . 7E-0 6 2. 3E -0 4 2.68E-02 2.68E-06 2.31E-04 5 . 4 3 E-02 5.42E-06 4.72E-04 MN56 1.8 E-04 8.5E-11 7.4E-09 1.34E-03 6.23E-10 5.42E-08 FESS 1.5E-01 1.5E-05 1.3E-03 1. 4 8 E -01 1. 4 8 E -0 5 1.28E-03 - - -

FE59 5.1E-02 5.1E-06 4.4E-04 5.14 E-0 2 5.07E-06 4 . 3 7E-0 4 4.49E-02 4.43E-06 3.86E-04 19 C058 1.0E 00 1.0E-04 8.8E-03 1.01E+00 1. 01E-0 4 8.68E-03 1.31E 00 1.30E-04 1.13E-02 CO60 1. 9 E -01 1.9E-05 1. 6E -0 3 1. 8 8 E -01 1.88E-05 1.62E-03 5.78E-02 5.78E-06 5.03E-04 TOTAL 1.5E 00 1.5E-0 4 1.3E-02 1.50E+00 1.49E-04 1.28E-02 1.50E 00 1.48E-04 1.29E-02 G%

(~%

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- 3

-a 1 of 1 Amendment 19 12/12/75

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- 2 A t R L y n) 00456647878080 08 866898997766886554 A 1 O t ec 12500010200101 10 000000000000000000

- - - - - - - - - - - - - - - - - 2 S 1 O E i nc - - - - - - - - - - - - - - - -

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P y) 45712142334545 64 422454553322342110 ltc 00000000000000 00 000000000000000000

- - - - - - - - - - - - - - - - +

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P y1 4571 2142334545 64 422454553322342110 D ltc 00000000000000 00 000000000000000000 E aic - - - - - - - - - - - - - - - - - - -

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I e y T t s C s t A a l y n) w as t i mc ec 51002172334545364 01500000100000000 411454543322342110 000000000000000000 f o p vrt/ - - - - - - - - - - - - - - - - - - -

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t c e=

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G SWESEAR-P1 TABLE 11.2-12 (CONT)

B&W C-E W Discharge Discharge Discharge Activity Rate Prom Activity Rate Prom Activity Rate Prom Initial After Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treatme nt posal Sys- Activity Treatment posal Sys- Activity Treatment posal Sys-Nuclide fuci/ce) (uci/cc) tem (Ci/yr) (uci/cc) (uci/cc) tem (Ci/vr) (uci/cc) uCi/cc) tem (Ci/yr) liA137M 2.6E 00 2.6E 00 1.7E-01 1.58E 00 1.53E 00 1.04E-01 1.27E 00 5.60E-71 3.73E-72 BA140 3.3E-03 3.2E-03 2.2E-04 2.07E-03 2.0 3E -0 3 1.33E-04 1.70E-03 1. 67E -0 3 1.11E-04 LA140 3.4E-03 3.4E-03 2.3E-04 2.11 E-0 3 2.10E-03 1.38E-04 1.73E-03 1.46E-03 9.70E-05 CE141 7.9 E-0 4 7.8E-04 5.2E-05 4.89E-04 4 . 8 5 E-O c 3.19E-05 4.02E-04 3.98E-04 2.65E-05 CE143 4.6E-05 3. 8 E -0 5 2.5E-06 3.28E-05 2 . 6 6E-0 5 1.75E-06 2.79E-05 2. 2 7E-05 1.51E-06 CE144 7.7E-04 7.7E-04 5.2E-05 4.75E-04 4. 7 5E -04 3.13E-05 3.88E-04 3. 8 7E-0 4 2.58E-05 PR143 5.3E-04 5.2 E -0 4 3.4E-05 3.28E-04 3.21E-04 2.11E-05 2.90E-04 2.84E-04 1.89E-05 PR144 7.7E-04 7.7E-04 5.2E-05 4 . 75 E-0 4 4.75E-04 3.13E-05 3.88E-04 1.30E-14 8.65E-16 g NP239 6. 2 E-0 4 5.5E-0 4 3.7E-05 4 .18 E-0 4 3.70E-04 2.43E-05 CR$1 6.6E-03 6.5E-03 4.3E-04 4.08E-03 4.04E-03 2.66E-04 3. 37 E -03 3.34E-03 2 . 22 E-04 MN54 1.5E-03 1. 5E -03 9.9E-05 9 .12 E-04 9 .12 E-0 4 6.00E-05 7. 54 E-0 4 7.53E-04 5.02E-05 MN56 8.3E-05 5.6E-06 3.8E-07 1.51E-04 1.03E-05 6. 8 5E-0 7 FESS 7.8E-03 7.8E-03 5.2E-04 4 .8 2E-0 3 4 . 8 2 E-0 3 3.17E-04 3.97E-03 3. 9 7E-03 2. 64 E-04 ,

FES9 3.9E-03 3.9E-03 2.6E-04 2.44E-03 2. 4 3E -03 1.60E-04 2.02E-03 2.01E-03 1.34E-04 C058 6.9E-02 6.8E-02 4.6E-03 4. 2 3E -02 4 . 21E-0 2 2. 77E-0 3 3.50E-02 3.48E-02 2.32E-03 CO60 9.9E-03 9.9E-03 6.6 E-0 4 6 . 06 E-0 3 6 .0 6E-0 3 3.99E-04 4.99E-03 4.99E-03 3.33E-04 TOTAL 8.9E 00 8.6E 00 5.8E-01 5.34E 00 '.21E 00

, 3.43E-01 4.22E 00 2.72E 00 1.81E-01 O

c.w CO L I C3

( 'i 2 of 2 Amendment 19 12/12/75

SWESSAR-P1 TABLE 11.2-13 ACT1VITY FROM 'IURBINE PLANT SAMPLING SINKS (DESIGN CASE)

Decontamination f actor of waste disposal system for this aource= 1.00E 04 Decay time in waste disposal system (hours) = 2.00E 01 Flow rate (gal /yr) = 3.00E 04 B&M C-E W Discharge Discharge discharge Activity Rate Prom Activity Rate Prom Activity Rate Fram Initial After Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treatment posal Syn- Activity Treatment po3al Sys- Activity Treatment posal Sys-Nuclide (uCi/cc) (uCi/cc) tem (Ci/yr) fuCi/cc) fuCi/cc) tem (Ci/Vr) (uCi/cc) (uCi/cc) tem (C1/yr)

BR83 5.7E-07 1.8E-13 2.0E-11 1.91E-0 7 5.92E-14 6.64E-12 1.91E-07 4.64E-1a 5.27E-12 BR84 2.5E-07 1.1E-22 1.2E-20 3. 8 0E-0 8 1.66E-23 1.86E-21 3.21E-08 1.78E-23 2.02E-21 BR85 2.9E-08 1.1E-55 1.2E-53 6.52E-10 d.43E-57 2.72E-55 4.99E-10 0.0 0.0 I131 2. 4 E-0 5 2.3E-09 2.6E-07 8. 8 P E-0 6 U .19E-10 9.19E-08 9. 90 E-0 6 9.21E-10 1.05E-07 I132 6.6E-06 2.1E-10 2.4E-08 2.54 E-0 6 3.45E-11 3. 8 7E-0 9 3.0 8 E-0 6 7.44E-13 8.44E-11 1133 3.3E-05 1.7E-0 9 1.9E-07 1. 31E-05 6.73E-10 7. 54 E-0 8 1.48E-05 7.65E-10 8.68E-08 1134 3.5E-06 4.4E-17 5.0E-15 7.4 8 E-07 9.26E-18 1.04E-15 6. 6 6E-07 8.80E-18 9.99E-16 1135 1.6 E-0 5 1.9E-10 2.2E-08 6.25 E-0 6 7.85E-11 8.80E-09 6.84E-06 8.66E-11 9.84E-09 RBS8 2.2E-05 8.5E-30 9.6E-28 5.67E-07 2.22E-31 2.49E-29 4 . 25E-07 3.84E-31 a.37E-29 SR89 4.1E-08 4.1E-12 4.6E-10 6. 50 E-09 6.43E-13 7.21E-11 9.75E-09 9.64E-13 1.09E-10 SR90 1. 8 E-0 9 1.8E-13 2.1E-11 2.87E-10 2.87E-14 3.22E-12 4.30E-10 4.30E-14 4.88E-12 SR91 1.4 E-0 8 3.5E-13 3.9E-11 2.3 9 E-0 9 5.70E-14 6.39E-12 3. 05E-0 9 7.33E-14 8.33E-12 Y90 3.8E-09 3.4E-13 3.9E-11 8.80E-11 1.27E-14 1.42E-12 2.36E-10 1.90E-14 2.16E-12 Y91M 1.5E-08 2.2E-13 2.5E-11 1.14 E-0 9 3.68E-14 4.13E-12 1.48E-09 9.51E-21 1.08E-18 Y93 6.8 E-0 9 1.7E-13 2.0E-11 4.17E-10 1.07E-14 1.20E-12 7.40E-10 1.84E-11 2.09E-12 ZR95 6. 8 E-0 9 6.8E-13 7.7E-11 1.07E-09 1.06E-13 1.19E-11 1.60E-09 1.59E-13 1.80E-11 1.22E-11 1. 67 E-0 9 1.64E-13 1.87E-11 0 NB95 7.1E-09 7.0E-13 8.0E-11 1.11E-09 1.09E-13 MO99 4.3E-05 3.5E-09 4.0E-07 1.11E-0 6 9.01E-11 1.01E-08 2.75E-06 2.24E-10 2.55E-09 TC99M 1.6E-05 3.1E-09 3.5E-07 7.45E-07 8.39E-11 9 . 41E-0 9 2.14E-06 2.12E-11 2.41E-09 RU103 3.3E-09 3. 2E-13 3.7E-11 5.15E-10 5.08E-14 5.69E-12 7.70E-10 7.59E-14 8.62E-12 RU106 3.3E-10 3.3E-14 3.8E-12 5.20E-11 5.19E-15 5.82E-13 7.80E-11 7.79E-15 8.84E-13 RH103M 3.3E-09 3.2E-13 3.6E-11 5.15E-10 4.98E-14 5.58E-12 7.72E-10 4.30E-20 4.89E-18 RH106 3.3E-10 3.3E-14 3.8E-12 5.20E-11 5.19E-15 5.82E-13 7.80E-11 0.0 0.0 TE125M 8.5E-10 8.4E-14 9.6E-12 1.33E-10 1.32E-14 1.48E-12 1.96E-10 1.94E-14 2.20E-12 TE127M 2.0E-08 2.0E-12 2.3E-10 3.18E-09 3.16E-13 3.55E-11 4.77E-09 4.74E-13 5.39E-11 TE127 8 . 5E-0 9 1.7E-12 2.0E-10 1. 95 E-0 9 2.88E-13 3.22E-11 3.67E-09 8.392-14 9.53E-12

- TE129M 3.7E-07 3.7E -11 4.2E-09 5.8 8 E-0 8 5.78E-12 6.48E-10 B .77E-0 8 8.62E-12 9.79E-10 TE129 1.9E-5r 2.4E-11 2.7E-09 5.07E-08 3.71E-12 4.15E-10 8.22E-08 1.26E-17 1.43E-15

TE131M 1.*L-07 1.2E-11 1.4E-09 3.27E-08 2.06E-12 2.31E-10 4 . 6 2E-0 8 2.85E-12 3.24E-10 3 TE131 s.6E-08 2.2E-12 2.5E-10 7.9 7E-09 3.76E-13 4.22E-11 1.05E-00 2.11E-27 2.40E-25 TE132 2.4E-06 2.0E-10 2.3E-08 3 .9 5 E-0 7 3.30E-11 3.71E-09 5.80E-07 4.86E-11 5.51E-09 CS134 6.1E-06 6.1E-10 6.9E-08 1.21E-06 1.21E-10 1.36E-08 1. 4 3 E-06 1.41E-10 1. 62 E-08

, . , CS136 2.4E-06 2.3E-10 2.7E-08 1.25 E-0 6 1.20E-10 1.34 E-0 8 8.35E-07 8.01E-11 9.09E-09 CS137 3.1 E-0 5 3.1E-09 3.5E-07 4. 8 2 E-0 6 4 . 8 2E -10 5.40E-08 7. 37 E-0 6 7.37E-10 8.37E-08 C3 hh137M 1.8E-05 2.9E-09 3.3E-07 4 .4 0 E-0 6 4.15E-10 5.05E-06 3.70E-06 0.0 0.0

- BA140 4.2E-08 4.0E-12 4.5E-10 6.58E-09 6.29E-13 7.05E-11 9. 8 2 E-0 9 9.39E-13 1. 0 7E-10 LA140 1.7E-08 2.4 E-12 2.7E-10 2.5 3E-0 9 3.67E-13 4.11E-11 4.05' 49 2.87E-13 3.26E-11 1 of 2 Amendment 19 12/12/75

SWESSAR-F1 TABLE 11.2-13 (CONT)

B&W C-E W Discharge Discharge Discha rge Activity Rate From Activity Rate From Activity Rate From Initial After Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treat 2nent posal Sys- Activity Treat 3nent posal Sys- Activity Treatment posal Sys-Nuclide fuci/cc) (uCi/cc) tem (C3/yr) (uci/cc) (uCi/cc) tem (Ci/yr) pCi/cc) uCi/cc) tem (Ci/yr)

CE141 6.6E-09 6.5E-13 7.4E-11 1.04E-09 1.02E-13 1.15E-11 1. 5 6 E-0 9 1.53E-13 1.74E-11 CE143 4.3E-09 2.9E-J3 3.2E-11 7.27E-10 4.78E-14 5.36E-12 1.04E-09 6.83E-14 7.76E-12 CE144 5.0 E-0 9 5.0E-13 5.6E-11 7.60E-10 7.78E-14 8.73E-12 1.17E-09 1.17E-13 1.33E-11 PR143 6. 4 E-0 9 6.1E-13 7.OE-11 1.01 E-0 9 9.68E-14 1.09E-11 1.52E-09 1.46E-13 1.66E-11 PR144 5.0E-09 5.0E-13 5.6E-11 7.80E-10 7.78E-14 8.73E-12 1.17 E-0 9 1.31E-34 1.49E-32 NP239 3.4 E-0 8 2.7E-12 3.0E-10 5. 60 E-0 9 4.38E-13 4.91E-11 8 . 20 E-09 6.42E-13 7.29E-11 CR$1 5. 8 E -08 5.7E-12 6.4E-10 9 .12 E -09 8.93E-13 1.00E-10 1.38E-08 1.35E-12 1.53E-10 ig MN54 9.5E-09 9.5E-13 1.1E-10 1. 4 9 E-0 9 1.49E-13 1.67E-11 2.26E-09 2.26E-13 2.56E-11 MN56 9.9 E-0 8 4.6E-14 5.2E-12 2 . 52 E-0 8 1.17E-14 1.33E-12 FE55 4.9E-08 4.9E-12 5.6E-10 7.70 E-0 9 7.70E-13 8.63E-11 1.16E-08 1.16E-12 1.32E-10 FES9 3.1 E-0 8 3.0E-12 3.4E-10 4 . 8 2 E -0 9 4.76E-13 5.34E-11 7.25E-09 7.16E-13 8.13E-11 C058 4.9E-07 4.9E-11 5. 5 E-0 9 7.70 E-0 8 7.64E-12 8.57E-10 1.16E-07 1.15E-11 1. 31E-09 CO60 6.1E-0 8 6.1E-12 7.0E-10 9. 6 5E-0 9 9.65E-13 1.082-10 1.46E-08 1.46E-12 1.66E-10 TOTAL 2.3E-04 1.8E-08 2.1E-0 6 4.65E-05 3 . 01E-0 9 3.38E-07 5. 52E-0 5 3.06E-09 1.66E-10 CN C?

CD i

i.

C :

C 2 of 2 Amendment 19 12/12/75

6 SWESSAR-P1 TABLE 11.2-14 ACTIVITY FROM WRBINE BUILDING SUMPS (DESIGN CASE)

Decontamination factor of waste disposal system for this source = 1.00E 00 Decay time in waste disposal system (hours) = 0.0 Plow rate (gal /yr) = 1.30E 05 B&W C-E W Discharge Discharge Discharge Activity Rate From Activity Rate From Activity Rate From Initial After Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treatment posal Sys- Activity Treat 2nent posal Sys- Activity Treatment posal Sys-Nuclide juCi/cc) (uCi/cc) t( m (Ci/yr) (uCi/cc) (uCi/ccl tem (Ci/yr) (uCi/cc) (uCi/cc) tem (Ci/yr)

BR83 5.7E-07 5.7E-07 2.8E-04 1.91E-07 1.91E-07 9.28E-05 1.91E-07 1.91E-07 9.40E-05 BRB4 2.5E-07 2.5E-07 1.2E-04 3. 8 0 E -0 8 3. 8 0E-0 8 1.85E-05 3.21E-0E 3. 21E-0 3 1. 58 E-05 BR85 2.9 E-0 8 2.9E-08 1.4E-05 6.52E-10 6.52E-10 3.17E-0 7 4.99E-10 4.99E-10 2.46E-07 1131 2.4E-05 2.4E-05 1.2E-02 8. 8 0E-06 8 . 8 0E -0 6 4.27E-03 9.90E-06 9.90E-06 4 . 8 7E-03 1132 6.6 E-0 6 6.6E-06 3.2 E-0 3 2. 5 4 E-0 6 2.54E-06 1.23E-03 3.08E-06 3.08E-06 1.52E-03 I133 3.3E-0 5 3.3E-05 1.6E-02 1.31E-4 5 1.31E-05 6.36E-03 1.48E-05 1.48E-05 7. 2 8 E-03 1134 3.5E-06 3.5E-06 1.7E-03 7.4 8 E-07 7.48E-07 3.63E-04 6.66E-07 6.66E-07 3. 28 E-04 I135 1.6E-05 1. 6E-0 5 7.6E-03 6.25E-06 6. 25E -06 3.04E-03 6. 84 E-0 6 6.8 4 E-06 3.37E-03 RB88 2.2E-05 2. 2E-0 5 1.1E-02 5.67E-07 5. 6 7E-07 2.75E-04 4.25E-07 4.25E-07 2.09E-04 SR89 4.1E-0 8 4.1E-08 2. 0E-0 5 6 .50 E-0 9 6.50E-09 3.16E-06 9. 75E-09 9.75E-09 4.80E-06 SR90 1.8E-09 1. 8E-0 9 9.0E-07 2.87E-10 2.87E-10 1.39E-07 4.30E-10 4.30E-10 2.12E-07 SR91 1.4E-08 1.4E-08 7.1E-06 2.39E-09 2.39E-09 1.16E-06 3. 05 E-0 9 3.0 5E-09 1.50E-06 Y90 3.8E-09 3. 8 E-0 9 1. 9 E-0 6 8.80E-11 8.80E-11 4 . 2 7E-0 8 2.36E-10 2.36E-10 1.16E-07 Y91M 1.5E-0 8 1.5E-08 7.6E-06 1.14 E-0 9 1.14E-09 5.54E-07 1.48E-09 1.48E-09 7.28E-07 Y93 6. 8 E-0 9 6 . 8 E-0 9 3.3E-06 4.17E-10 4.17E-10 2.03E-07 7.40E-10 7.40E-10 3.64E-07 19 ZR95 6.8E-09 6.82-09 3.3E-06 1.0 7E-0 9 1.07E-09 5.20E-07 1.60E-09 1.60E-09 7. 87E-07 NB95 7.1E-09 7.1E-09 3.5E-06 1.11E-09 1.11E-09 5.39E-07 1.67E-09 1.67E-09 8.22E-07 M099 4.3E-05 4.3E-05 2.1E-0 2 1.11E-0 6 1.11E-06 5.39E-04 2.75E-06 2.75E-06 1.35E-03 TC99M 1.6E-05 1.6E-05 7.6E-03 7. 4 5E-07 7.45E-07 3.62E-04 2.14 E-0 6 2.14E-06 1.05E-03 RU103 3.3E-09 3. 3E-0 9 1.6E-06 5.15E-10 5.15E-10 2.50E-07 7.70E-10 7.70E-10 3.79E-07 RU106 3.3E-10 3.3E-10 1.6E-07 5.20E-11 5.20E-11 2.53E-08 7.80E-11 7.80E-11 3.84E-08 RH103M 3.3E-09 3.3E-09 1.6E-06 5.15E-10 5.15E-10 2.50E-07 7.72E-10 7.72E-10 3.80E-07 CN RH106 3.3':-10 3.3E-10 1.6E-07 5.20E-11 5.20E-11 2.5 3E-0 8 7.80E-11 7.80E-11 3.84E-08 C;w TE125M 8.54-10 8.5E-10 4.2E-07 1.33E-10 1.332-10 6.46E-08 1.96E-10 1.96E-10 9.65E-08

~' TE127M 2.0E-)8 2.0E-OP 1.0 E-0 5 3.18 E-0 9 3.18 E-09 1.54E-06 4 . 77 E-0 9 4.77E-09 2.35E-06 TE127 8. 5E-0 9 8.5E-09 4.1E-0 6 1.95E-09 1.95E-09 9.47E-07 3. 67 E-09 3.67E-09 * . 81E-06 TE129M 3.7E-07 3.7E-07 1. 8 E-0 4 5.88E-08 5. 88E-0 8 2.86E-05 8 . 77E-0 8 8.7 7E-0 8 4.32E-05 TE129 1.9E-07 1. 9 E-07 9.3E-05 5.07E-08 5.07E-08 7.46E-05 8. 22E-0 8 8.22E-08 4 .05 E-05

( ! TE131M 1.9E-07 1. 9 E -07 9.5E-05 3 .27E-0 8 3. 27E-0 8 1.59E-05 4.62E-08 4. 6 2E-08 2. 2 7E-05

( ; TE131 7.6E-03 7.6E-08 3.7E-05 7.97E-0 9 7. 9 7E-0 9 3 . 8 7E-0 6 1.05E-08 1.0 5E-08 5.17E-06 g, TE132 2.4 E-0 6 2. 4 E-0 6 1. 2E -0 3 3.95E-07 3.9 5E-07 1.92E-04 5.80E-07 5.80E-07 2.85E-04 CS134 6.1E-06 6.1E-06 3.0E-03 1.21E-06 1.21E-06 5.88E-04 1. 4 3E-0 6 1.43E-06 7.04E-04 CS136 2.4E-06 2. 4 E-0 6 1.2E-03 1.2 5E-06 1.25E-06 6.07E-04 8.35E-07 8.35E-07 4.11E-04 CS137 3.1E-05 3.1E-0 5 1.5E-02 4 . 8 2 E-0 6 4.32E-06 2.34E-03 7.37E-06 7.37E-06 3. 6 3E -0 3 1 of 2 Amendment 19 12/12/75

G SWESSAR-P1 TABLE 11.2-14 (CONT)

B&W C-E W Discharge Discharge Discharge Activity Rate From Activity Rate From Activity Rate From Initial Af t er Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treatment posal Sys- Activity Treatment posal Sys- Activity Treatment poso! Sys-Nuclide (uci/cc) (uci/cc) tem (Ci/yr) (uci/cc) (uci/ce) tem (Ci/yr) (uci/cc) (uci/cc) tem (Ci/yr)

BA137M 1.BE-05 1.8E-05 8.7E-03 4.40E-06 4 . 4 0 E-0 6 2.14E-03 3.70 E-0 6 3.70E-06 1.82E-03 BA140 4.2E-08 4 . 2E -08 2. 0E-0 5 6.5 8 E-0 9 6.58E-09 3.20E-06 9. 8 2 E-0 9 9.82E-09 4 .8 3 E-0 6 LA140 1.7E-08 1.7E-08 8.5E-0 6 2.53E-09 2.53E-09 1.23E-06 4.05E-09 4.0$E-09 1.99E-06 CE141 6 .6 E-0 9 6.6E-09 3.3E-06 1. 0 4 E-0 9 1.0 4 E-0 9 5.05E-07 1.56E-09 1.56E-09 7.68E-07 CE143 4.3E-09 4.3E-09 2.1E-0 6 7.27E-10 7.27E-10 3.53E-07 1. 0 4 E-0 9 1.04E-09 5.12E-07 CE144 5.0E-09 5.0 E-0 9 2. 4 E-0 6 7.80E-10 7.80E-10 3.79E-07 1.17E-09 1.17E-09 5.76E-07 PR143 6.4 E-0 9 6.4E-09 3.1E-0 6 1.01E-0 9 1. 01E-0 9 4 . 91E-0 7 1.52E-09 1.52E-09 7.48E-07 PR144 5.0E-09 5.0E-09 2.4E-06 7.80E-10 7.30E-10 3.79E-07 1.17E-09 1.17E-09 5.76E-07 NP239 3.4 E-0 8 3.4E-08 1.7E -0 5 5.60E-09 5.b OE-0 9 2.72E-06 8.20E-09 8.20E-09 4 .0 4 E-0 6 g CR51 5.8 E-0 8 5.8E-08 2.8E-05 9.12E-09 9.12E-09 4.43E-06 1.38E-08 1.38E-08 6.79E-06 MN54 9.5E-0 9 9. 5E-0 9 4.7E-06 1. 0 9 E-0 9 1.4 9 E-0 9 7. 24 E-0 7 2.26E-09 2.26E-09 1.11E-06 MN56 9.9E 'a 9.9E-08 4.9E-05 2.52E-08 2.52E-08 1.24E-05 FESS 4.9 E- 18 4.9E-08 2.4E-05 7.70E-09 7.70E-0 9 3.74 E-0 6 1.16E-08 1.16E-0 8 5.71E-06 FE59 3.1E s: 3.1E-0 8 1.5E-0 5 4. 8 2E-09 4.82E-09 2.34E-06 7.25E-09 7.25E-09 3.57E-06 0058 4.9E-07 4 .9E-0 7 2.4E-04 7.70 E-0 8 7. 70E-0 8 3.74E-05 1.16E-07 1.16E-07 5.71E-05 CO60 6.1E-08 6.1E-08 3.0E-0 5 9.6 5 E-0 9 9. 6 5E-09 4 . 6 9E-0 6 1.46E-08 1.46F-08 7.18 E-06 TOTAL 2.3E-0 4 2.3E-OD 1.1E-01 4.63E-05 4.65E-05 2.26E-02 5. 52E-05 5.5ZE-05 2.72E-02 O

c;.m CD 2 of 2 Amendment 19 12/12/75

G SWESSAR-P1 TABLE 11.z-15 ACTIVITY FFDM CHEMICAL REGENERATIVE WASTE (DESIGN CASE)

Decontamination factor of waste disposal system for this source = 1.00E 04 Decay time in waste disposal system (hours) = 2.00E 01 Flow rate (galfyr) C-E , W-41, W-3S = 1.76E 06 g B6W = 1.40E 06 B&W C-E W Discharge Discharge Dis charge Activity Rate Prom Activity Rate From Activity Rate Prom Initial After Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treatment posal Sys- activity Treatment posal Sys- Activity Treatment posal Sys-Nuclide M 1/cc) (uCi/cc) tem (Ci/yr) (tfi/cc) (uCi/cc) tem (Ci/yr) (uCi/cc) uCi/cc) tem (Ci/yr)

BR83 2.2E-15 6.9E-12 3.7E-08 1.05E-05 3.25E-12 2.14 E-0 8 6.58E-06 1.60E-12 1.07E-0 8 BR84 2.1E-06 9.4E-22 4.9E-18 4.61E-07 2.01E-22 1.32E-18 2. 4 4 E -07 1.35E-22 9.00E-19 BR85 2.4E-02 9.0E-56 4.7E-52 7.46E-10 2.77E-57 1.83E-53 3.58E-10 0.0 0.0 I131 7.2E-02 6.7E-06 3.5E-02 3.60E-02 3. 35E-0 6 2.21E-02 2.54E-02 2.36E-06 1.582-02 1132 3.3 E -0 3 2.7E-07 1.4E-03 1.74 E-0 3 1.30E-07 9.10E-04 1.18 E-0 3 2.85E-10 1.90E-06 I 133 1.1E-02 5. 8 E-07 3.0E-03 6.23E-03 3.20E-07 2.11E-03 4 . 41E-0 3 2.28E-07 1.5 2 E-03 1134 5.0E-05 6.2E-16 3.3E-12 1. 4 9 E-0 5 1.85E-16 1.22E-12 8 . 33 E-0 6 1.10E-16 7.33E-13 1135 1.7E-03 2.1E-0 8 1.1 E-0 4 9.55E-04 1.20E-08 7.90E-05 6.56E-04 8.31E-09 5.53E-05 RB88 1.0 E-0 4 4.1E-29 2.2E-25 8.76E-06 3. ,E -3 0 2.26E-26 3.02E-06 2.73E-30 1.82E-26 SR89 2.8E-04 2.7E-08 1.4E-04 1.38E-04 1.37E-08 8.99E-05 9.54E-05 9.43E-09 6.28E-05 OR90 1. 5 E-0 5 1. 5E-09 7.9E-06 7.4 2 E-0 6 7.42E-10 4.88E-06 5.11E-06 5.11E-10 3. 4 0 E-06 SR91 2.3E-06 5.5E-11 2.9E-07 1. 21E-0 6 2.88E-11 1.90 E-0 7 7.11E-07 1.71E-11 1.14E-07 Y90 1.7E-0 5 1.7E-09 8.8E-06 6.75E-06 6.88E-10 4.53E-06 4 . 8 2 E-0 6 3.88E-10 2.59E-06 791M 1.6 E-0 6 3.5E-11 1.9 E-0 7 7. 6 3 E-0 7 1.86E-11 1.23E-07 3 .14 E-07 2.02E-18 1.34E-14 i33 1.1E-06 2.9E-11 1.5E-07 2.23 E -0 7 5.72E-12 3.76E-08 1.81E-07 4.51E-12 3. 0 G E-0 8 ZR95 4.8E-05 4 . 7E-09 2. 5E-0 5 2.38E-05 2.36E-09 1.55E-05 1.64E-OS 1.63E-09 1.08E-05 g NB95 4.4E-05 4.3E-09 2. 3E-0 5 2.18 E-05 2.14 E-09 1.41E-05 1.92E-05 1.89E-09 1.26E-05 MO99 4.7E-02 3. 8E-06 2. 0E -02 3.88E-03 3.15E-07 2.07E-03 4.41E-03 3.60E-07 2.40E-03 TC99M 4.3E-02 3.6 E-0 6 1.9E-02 3 . 6 5E-0 3 3.04E-07 2.00E-03 4 .15E-0 3 4 .11E-0 8 2.74E-04 RU103 2.1E-05 2.1E-0 9 1.1E-05 1.0 4 E-0 5 1.02E-09 6.74E-06 7.16 E-0 6 7.06E-10 4 .7 0 E-06 RU106 2.6E-06 2.6E-10 1. 4 E -0 6 1. 31E-0 6 1.31E-10 8.595-07 9.02E-07 9.01E-11 6.00E-07 RH103M 2.0E-05 2.0E-09 1.1E-05 1.02E-05 1.0 0E-0 9 6.51E-06 7.17E-06 4.00E-16 2.66E-12 c7s RH106 2 .6 E-0 6 2.6E-1C 1.4E-06 1. 31E-0 6 1.31E-10 8.59E-07 9. 02 E-07 0.0 0.0 C TE125M 5. 8 E- -0 6 5.8E-10 3.0E-06 2.9 0E-0 6 2.87E-10 1.8 9 E-0 6 1. 97E-0 6 1.95E-10 1. 30 E-06 C. O TE127M 1.5E-04 1.5E -08 7. 9 E-0 5 7. 4 8 E-0 5 7.44E-07 4.90E-05 5.1R.S-05 5.15E-09 3.43E-05 TE127 1.5E-04 1.5E-08 7.9E-05 7. 3 9 E-0 5 7.39E-s9 4.87E-05 5.18E-05 1.18E-09 7.89E-06 TE129M 2.3 E -03 2.2E-07 1. 2E-0 3 1.14 E-0 3 1.12N-07 7.38E-04 7.85E-04 7.71E-08 5.14E-04

(~  ; TE129 1.5E-03 1.4E-07 7.6E-04 7.3 2 E-0 4 7.18E-08 4.73E-04 .85E-04 1.20E-13 7 99E-10 TE131M 9.5E-05 6. 0E-0 9 3. 2E -0 5 5.14 E-05 3. 2 4 E -0 9 2.13E-05 3.34E-05 2.06E-09 1. 3 7E-05 C) TE131 1.8 E-0 5 1.1E-09 5.8E-06 3. 4 2E-0 6 5.91E-10 3.89E-06 6. 79 E-06 1.37E-24 9.10E-21 C3 TE132 3.1E-03 2.6E-07 1.4 E -0 3 1.60 E-0 3 1.34E-07 8.83E-04 1. 00 E-0 3 9.04E-09 6.02E-04 CS134 4.9E- 02 4.9E-06 2.6E-07 3.08E-02 3.08E-06 2.03E-02 1. 68 E-0 2 1. 6 8 E -0 6 1.12E-02 CS136 1.0F-02 9. 9E -0 7 5.2E-03 1.67E- 2 1. 61E-0 6 1.06E-02 5.14E-03 4.93E-07 3.28E-03 CS137 2 . 5E-01 2. 5E-0 5 1.22-01 1. 2 SE-01 1. 2 5E-O S 8.20E-02 8.76E-02 8.76E-06 5. 8 4 E-02 aA137M 2.3E-01 2.3E-05 1.2E-01 1.16E-01 1.16E-0 5 7.67E-02 4.40E-02 0.0 0.0 1 of 2 Amendment 19 12/12/75

SWESSAR-P1 TABLE 11.2-15 (CONT) acW C-E W Discharge Discharge Discharge Activity Rate From Activity Rate Prom Activity Rate From Initial After Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treatme nt posal Sys- Activity Treatment posal Sys- Activity Treatment posal Sys-N_gclide (uCi/cc) (uCi/cc) ten (Ci/yr) (uCi/cc) (uCi/cc) tem (Ci/Yr] (uCi/cc) uCi/ce) tem (Ci/yr)

RA140 1.7E-04 1.6E-08 8.4E-05 8.4 5E-0 5 8.08E-09 5.32E-05 5.81E-05 5.55E-09 3.70E-05 LA140 1.7E-04 1.7E-08 9.0E-05 8. 67E-0 5 8 .5 5 E-09 5.63E-05 6.00E-05 4.25E-09 2.83E-05 CE141 4.0E-05 3.9E-09 2.1E-05 2.0 0 E-0 5 1.96E-09 1.29F-05 1. 39 E-0 5 1.37E-09 9.09E-06 CE143 2. 3E-0 6 1.5E-10 8.1E-07 1. 2 6 E-0 6 8.25E-11 5.4 3E-0 7 8.26E-07 5.43E-11 3.62E-07 CE149 3.9E-05 3.9 E -0 9 2.1E-05 1.94E-05 1.9 4 E -0 9 1. 2 8 E -0 5 1.33E-05 1.33E-09 8. 8 4 E-06 PR143 2.7E-05 2.6E-09 1.3E-05 1.35E-05 1. 29 E-0 9 8.50E-06 9. 9 3 E-0 6 9.53E-10 6.35E-06 PR144 3.9 E-0 5 3. 9E-0 9 2.1E-0 5 1. 94 E-0 5 1.9 4 E-0 9 1. 2 8 E-0 5 1. 3 3 E-0 5 1.49E-30 9.93E-27 NP239 3.1E-05 2.5E-09 1. 3E-0 5 1.11E-05 8.69E-10 5. 7 9E-06 CRS1 3.3 E-0 4 3.3E-09 1.7E-0 4 1. 67 E-0 4 1. 6 3 E -0 8 1.07E-04 1.16E-04 1.14E-08 7.57E-05 3 MN54 7.5E-05 7.5E-09 4.0E-05 3.73E-05 3.72E -0 9 2.45E-05 2 . 60 E-05 2.60E-09 1.73 E-05 MN56 4.2E-06 1.9E-12 1.0E-08 1.57E-06 7.30E-13 4.86E-09 FESS 4 .0 E-0 4 4.0E-08 2.1E-04 1.97E-04 1. 97E-0 8 1.30E-04 1.37E-04 1. 3 7E-08 9.12E-05 FES9 2.0E-04 2.0E -0 8 1.0E-04 1.00E-04 9.88E-09 6.50E-05 6. 92 E-05 6.83E-09 4.55E-05 C058 3.5E-03 3.4E-07 1.8E-03 1.73E-03 1.72E-07 1.13E-03 1. 20 E-03 1.19E-07 7.9 3 E-0 4 CO60 5.0E-04 5.0E-08 2.6E-04 2.4 8 E-04 2. 4 8 E-0 8 1.63E-04 1.73E-04 1.73E-08 1.15E-04 TOTAL 7.4E-01 7.1E-05 3.7E-01 3 .4 8 E-01 3.39E-05 2. 2 3E-01 1.99E-01 1.43E-05 9.53E-02 O

C>

CO L1

( )

~ ~J 2 of 2 Amendment 19 12/12/75

@ O SWESSAR-P1 TABLE II.2-16 ACTIVITY PROM LAUNDRY DRAINS (DESIGN CASE)

Decontamination f actor of waste disposal system f or this source = 1.00E 00 3 Decay time in waste disposal system (hours)= 2.00E 01 Flow rate (gal /yr ) = 2.00E 05 P6W C-E W Discharge Discharge Discharge Activity Rate From Activity Rate From Activity Rate From Initial After Waste Dis- Initial Af t er Waste Dis- Initial After Waste Dis-Activity Treatment posal Sys- Activity Treatment posal Sys- Activity Treat 7me=nt posal Sys-Nuclide fuci/cc) (uCi/cc) ten (Ci/yr) (uci/cc) (uCi/cc) tem (Ci /yr) (uCi/cc) (uci/cc) tem (Ci/yr)

BR83 6.1E-07 1.9E-09 1. 4 t -0 6 5.6 8 E-07 1.76E-09 1.32E-06 5. 4 6 E-0 7 1.33E-09 1.01E-06 BR84 2.7E-07 1.2E-18 8.6E-06 2.62E-07 1.14E-18 8.57E-16 2.59E-07 1.4 3E-18 1.08E-15 BR85 3.6E-08 1.3E-51 1.0E-48 3. 61E-0 8 1.34E-51 1.01E-48 3. 60 E-08 0.0 0.0 1131 2.6E-05 2.4E-05 1.8E-02 1. 65 E-0 5 1.54E-05 1.15E-02 1.39E-05 1.29E-05 9.77E-03 I132 7.1E-06 2.EE -0 6 1.7E-03 5.86E-06 1.48E-06 1.11E-0 3 5 . 4 5 E-0 6 1.32E-08 9.96E-06 1133 3. 5E-0 5 1.8E-05 1.4E-02 2,61E-05 1. 34 E-0 5 1.01E-02 2.30E-05 1.19E-05 9.01E-03 1134 3.8 E-0 6 4.7E-13 3.6E-10 3. 6 9 E-0 6 4.57E-13 3.42E-10 3.62E-06 4.79E-13 3.62E-10 1135 1.6 E-0 5 2.1E-0 6 1.6E-0 3 1. 41E-0 5 1.77E-06 1.33E-03 1.31E-05 1.65E-06 1.25E-03 RB88 2.4E-05 9. 2E -0 6 7 .3 E-0 6 2.19 E-0 5 8.60E-26 6.44E-23 2.10 E-05 1.90E-25 1.44E-22 SR89 4.4E-08 4.4E-08 3.3E-05 2.72E-0 8 2.69E-08 2.01E-05 2. 27E -0 8 2. 2 4 E -08 1.70E-05 SR90 2.0 E-09 2. 0 E-09 1.5E-06 1.20E-09 1.20E-0 9 9.00E-07 9.97E-10 9.97E-10 7.54E-07 SR91 1.5E-08 3.7E-09 2. 8 E-0 6 1. 26 E-0 8 23.01E-09 2.25E-06 1.15E-08 2.76E-09 2.09E-06 Y90 2. 3E-0 9 2. 2E-0 9 1.7E-06 3.34E-10 5.03E-10 3.77E-07 2.61E-10 2.10E-10 1.59E-07 Y91M 9.2E-09 2. 4 E-0 9 1.8E-06 7.0 6 E-09 1.94E-09 1.46E-06 6.37E-09 4.09E-16 3.10E-13 Y93 4.0E-09 1.0E-09 7.8E-07 2.18 E-0 9 5.59E-10 4.19E-07 1.98E-09 4.93E-10 3.74E-07 11 ZR95 7.3E-09 7.22-09 5.5E -0 6 4 . 4 7E-0 9 4.44E-09 3.32E-06 3.73E-09 3.70E-09 2.80E-06 NB95 7. 6 E-0 9 7.5E-09 5.7E-06 4. 6 5 E-0 9 4.57E-09 3.42E-06 3. 87E-0 9 3.81E-09 2.89E-06 MO99 2.5 E-0 5 2 .1E-0 5 1. 6 E-02 4.8 2E-06 3. 9 2E -0 6 2.93E-03 4 .11 E-0 6 3.35E-06 2.54E-03 TC99M 1.7 E-0 5 1.9E-0 5 1.4 E-0 2 2.71E-0 6 3.59E-06 2.69E-03 2.15E-06 2.13E-07 1.61E-04 RU103 3.54-09 3.4E-09 2.6E-06 2.15E-09 2.12 E-0 9 's.59E-06 1. 80 E-09 1.77E -09 1.34E-06 RU106 3.5E-10 3.5E-10 2 . 7E-07 2.15 E-0 9 2.12E-09 1.59E-06 1.80E-09 1.77E-03 1.34E-06

?N RH103M 3.5E-09 3. 4 E-09 2.6E-06 2.16E-09 2.0 8 E-0 9 1.56E-06 1. 8 0 E -09 1.00E-15 7.60E-13

'X RH106 3.5E-10 3.5E-10 2. 7E-0 7 2.16-10 2.16E-10 1.62E-07 1.81E-10 0.0 0.0

~ 3 TE125M 9.0E-10 9.0E-10 6.8E-07 5.56E-10 5.51E-10 4 .13 E-0 7 4.5SE-10 4.50E-10 3.41E-07 TE127M 2.2 E-0 8 2.1E-0B 1. 6E -0 5 1. 3 3 E-0 8 1. 32 E-08 9.89E-06 1.11E-08 1.10E-08 8.35E-06 TE127 9.0E-09 1.9 E-0 8 1.4E-05 6.73-09 1.172-08 8 . 7 5E-0 6 6.90E-09 1.55E-09 1.18E-06 TE129M 4.0 E -07 3.9E-07 3.0 E -0 4 2.4 6E-0 7 2.41E-07 1.81E-04 2.05E-07 2.01E-07 1.5 2E-04

- 1 TE129 2.0E-07 2.5E-07 1.9E-04 1. 3 8 E-07 1.55E-07 1.16E-04 1. 21E-07 1.84E-13 1.40E-10

-

• TE131M 2.1E-07 1.3E-07 9. 9 E -0 7 1. 4 8 E-07 9.31E-08 6. 9 8 E -0 5 1. 29 E-07 7.95E-08 6.02E-05 ey~~

TE131 8.2E-08 2.4 E-0 8 i.8E-05 7.06E-08 1.70E-08 1.2 7E-0 5 6.67E-08 1.34E-22 1.02E-19 TE132 2.6 E-0 6 2 .2E-0 6 1.6E -0 3 1.7 0E-0 6 1.42E-06 1. 0 7E-0 3 1. 4 5 E-0 6 1.21E-06 9.16E-04 CS134 3.6E-06 3.6E-06 2.7E-03 2.80E-06 2.bOE-06 2.10E-03 1.83E-06 1.83E-06 1. 3 9 E -03 CS136 1. 4 E-06 1. 4 E -0 6 1.1E -0 3 2.94E-06 2.82E-06 2.11E-03 1.10E-06 1.06E-06 8.00E-04 CS137 1.8E-05 1.8E-05 1.4E-02 1.12 E-0 5 1.12E-05 8.35E-03 9.31E-06 9.312-06 7.05E-03 nA137M 1.7E-05 1.7E-05 1.3E-02 1. C 4 E -0 5 2. 04 E-0 5 7.81E-03 8.71E-06 0.0 0.0 BA140 4.46-08 4.2E-08 3.2E-0 5 2.77E-08 2.64E-08 1.98E-05 2.32L-08 2.21E-08 1.68E-05 1 of 2 Amen dment 19 12/12/75

SWESSAR-P1 TABLE s1.2-16 (CONT)

B&W C-E W Discharge Discharge Discrarge Activity Rate Frora Activity Rate Frau Activity Rate Frua Initial After Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity TreatJDent POSai SyS- Activity Treatw nt ponal Sys- Activity Treatment posal Sys-Nuclide (uci/ce) (uCi/cc) tem (Ci/yr) (uci/m) (uci/ce) ten (Ci/y r) (uci/cc) (uCi/cc) tesn (Ci/yr)

LA140 1.9E-08 2.6E-08 1.9E-05 9. 4 4 E-09 1.46E-08 1.09E-05 7.33E-09 5.19E-09 3.93E-06 CE141 7.1E-09 6. 9 E-0 9 5.3E -06 4.37E-09 4 .2 9E-0 9 3.22E-06 3. 65 E-0 9 3.58E-09 2.71E-06 CE143 4. 6E -0 9 3.0E-09 2.3E-08 3. 27E-0 9 2.15E-0 9 1.6 E-06 2.84E-09 1.87E-09 1.42E-06 CE144 5.3E-09 5. 3E -09 4.0E-06 3.2SE-09 3. 2 5E -0 9 2.43E-06 2.71E-09 2.70E-09 2.0 4 E-0 6 PR143 6.8E-09 6. 5E-0 9 4.9E-06 4 . 23 E-09 4.05E-09 3.04E-06 3.5?E-09 3.39E-09 2.57E-06 PR144 5.3E-09 5. 3E-0 9 4.0E-06 3. 2 5E-0 9 3.25E-09 2.43E-06 2.71E-09 3.04E-30 2.30E-27 NP239 3.6E-08 2.8E-08 2.1 E-O S 2.4 4 E-0 8 1.91 E-0 8 1. 4 3E-0 5 2.11E-08 1.65E.08 i ,2 5E-0 5 CRS1 6.2E-08 6.0E-08 7.7E-08 3.82E-08 3. 74 E -0 8 2.80E-05 3. 22 E-08 3.15E-08 2.39E-05 15 MN54 1.0E-08 1.0E-08 7.7E-0 6 6.22E-09 6.21E-09 4.65E-06 5. 23 E-0 9 5.22E-09 3.95E-06 MN56 1.1E-0 7 4.9E-10 3.7E-07 1.96E-07 9.11E-10 6.9 0E-07 PE55 5.2E-08 5.2E-0 8 4 . 0E -0 5 3.218-08 3.21E-0 8 2.41E -0 5 2 . 70 E-0 8 2.70E-08 2.04E.G5 FES9 3.3E-08 3.2E-08 2.4E-05 2.01E-08 1.99E-08 1.49E-05 1.69E-08 1. 6 7E -0 8 1.26E-05 C058 5.2E-07 5. 2E-07 3.9E-04 3.21E-07 3.19E-07 2 . 3 9E-0 4 2.71E-07 2.68E-07 2.03E-0, C060 6. 5E-0 8 6.5E-08 5.0 E-0 5 4 .0 ZE-0 8 4 .02E-0 8 3.01E-05 3. 3 8 E-0 8 3.38E-08 2.56E-05 TOTAL 2.0E-04 1. 3E -0 4 9.9E-02 1.27 E-0 4 6. 9 3 E-0 5 5.19E-02 1.11E-04 4.42E-05 3.35E-02 C'

r.

C~

(

- ~

2 of 2 Amendment 19 12/12/75

SWESSAR-P1 TABLE 11.2-17

'IUTAL ACTIVITY FROM RADIOACTIVE LIQUID WASTE SYSTEM MITH STIAM GENERATOR LEAKAGE (DESIGN CASE)

Calculated total discharge flow rate (gpm) B&W 3.77 l1s CE 4.46 W 4.06 B6W C-E W Actual Actual Actual Actual Discharge Actual Discharge Actual Discharge Activity Rate Activity Rate Activity Rate Nuclide fuci/cc) (Ci/yr) JuC1/ce) (Ci/yr) fuci/cc) (Ci/yr)

BR83 3.8E-08 2.9E-04 1. 2 8 E-0 8 1.12E-0 4 1.27E-08 1.13E-0 4 BR84 1.6E-08 1.2 E-0 4 2.30E-09 2.01E-05 1.97E-09 1.75E-05 BR85 1.9E-09 1.4E-05 3.86E-11 3.39E-0 7 3.02E-11 2. 6 8 E-07 1131 2.1E-05 1. 6E-01 1. 25E -0 5 1.10E-01 1.0 2 E-0 5 9. 0 4 E-0 2 1132 1.4E-06 1.0E-02 8.26E-07 7.25E-03 2.84E-07 2. 52E-0 3 1133 4.9E-06 3.7E-0 2 4.01E-06 3.51E-02 3.67E-06 3.26E-02 1134 2. 3E-07 1.7E-03 4.59E-08 4.02E-04 4.13E-08 3. 67E-0 4 1135 1. 3E-0 6 9.4 E-0 3 7.50E-07 6.58 E-0 3 7.53E-07 6.68E-03 RB88 1.4E-06 1.1E-02 4.04E-08 3. 54 E-0 4 1.12E-0 7 9.97E-0 4 SR89 8.1E-08 6. 0 E -0 4 4 .34 E-0 8 3. 81E-0 4 3.46E-08 3.07E-04 SR90 4.3E-09 3. 2 E-0 5 2.31E-09 2 . 02 E-0 5 1.82E-09 1. 62E-0 5 SR91 1.4E-09 1. 0 E-0 5 7.87E-10 6.91E-06 7.61E-10 6.76E-06 Y90 4.7E-09 3.5E-05 2. 01E-0 9 1.76E-05 1.36E-09 1. 20 E-0 5 Y91M 1.3E-09 9.7E-06 4.85E-10 4.2 6E -0 6 1.51E-10 1.34E-06 Y91 1. 5E-0 7 1.1E-03 8.89E-11 7.89E-07 Y93 5.8E-10 4 . 3E-0 6 1.45E-10 1.27E-06 1.49E-10 1.32E-06 ZR95 1.4E-08 1.0E-04 7. 4 5E-0 9 6.53E-05 5.92E-09 5. 2 5E-0 5 g Nb95M 6.26E-11 5.56E-07 NB95 1. 3E-0 8 9.6E-05 6. 89 E-09 6. 0 4 E-0 5 6.80E-09 6.0 3E-0 5 MO99 1.1E-05 8.6E-02 1.70 E-0 6 1.49E-02 1.61E-06 1.43E-02 TC99M 9. 3E-0 6 6. 9E-0 2 1.58 E-0 6 1.3 8 E-0 2 5.52E-07 4 . 90E-0 3 RU103 6.1E-0 9 4.5E-05 3. 28 E-0 9 2.8 8E-0 5 2.60E-09 2.31E-05 RU106 7.6E O 5.7E-06 4.06E-10 3. 56 E -0 6 3.22E-10 2.86E-06 RH103M 6.0E-09 4.5E-05 3.22E-O' 2 .8 2 E-0 5 1.87E-10 1.66E-06 RH106 7.6E-10 5.7E-06 4.06E-10 3.56E-06 1.93E-11 1.72E-07 TE125M 1.7E-09 1.3E-05 9.09E-10 7. 97E-0 6 2.06E-10 1.83E w6 TE127M 4.4E-08 3.3E-04 2. 34 E-0 8 2.05E-04 1.86E-08 1. 6 5E-0 4 TE127 4. 2E-0 8 3.2E-04 2. 2 9E-08 2. 01E -0 4 7. 7 3 E-0 9 6.86E-05 TE129M 6.7E-07 5.0E-03 3.61E-07 3.16E-03 2.86E-07 2.54E-03 rTs TE129 4.2E-07 3.2E-0 3 2. 32 E-0 7 2.03E-03 2.08E-08 1. 8 4 E-0 4

}ks TE131M 3.8E-08 2.9E-04 2. 8 2E-0 8 2 . 4 7E-0 4 2.46E-08 2.18E-04 TE131 9. 7E-09 7.3E-05 5. 27E-09 4. 63E -0 5 1.54E-09 1.37E-0 5 CD TE132 1.0E-06 7.8E-03 6.73E-07 5.90E-03 5.62E-07 4.99E-03 CS134 9.6E-Ob 7.1E-0 2 6. 3 8 E-0 6 5. 60E-0 2 3.91E-06 3.47E-02 CS136 2.1E-06 1.6E-02 3 .65 E-0 6 3.20E-02 1.29E-06 1.15E-02 t.4 CS137 4.9E-05 3.7E-01 2.57E-05 2. 2 6E -01 2. 02 E-0 5 1.7 9E-01

_4 CS138 - -

1.25E-09 1.11E-05

{Q 1 of 2 Amendment 19 12/12/75

SWESSAR-P1 TABLE 11.2-17 (COtfr) acw C-E W Actual Actual Actual Actual Discharge Actual Discharge Actual Discharge Activity kate Activity Rate Activity Rate Nuclide (uci/cc) (Ci/yr) (uci/cc) (Ci/yr) (uCi/cc) (Ci/yr)

BA137M 4.5E-05 3. 4 E-01 2.40E-05 2.11 E -01 9.23E-07 8.19E-03 BA140 5.0E-08 3. 8 E-04 2. 8 0 E-0 8 2.4 6E-0 4 2.25E-08 2.00E-04 LA140 5.0E-08 3.8E-04 2. 6 8 E -0 8 2.3 5E-0 4 1.70E-08 1.50E-04 CE141 1.2E-08 8.8E-05 6. 3 4 E-0 9 5.5 6E-0 5 5.07E-09 4 . 50 E -0 5 CE143 9.3E-10 6.9 E-0 6 6.37E-10 5. 90E-0 6 5.91E-10 5.25E-06 CE144 1.1E-08 8.5E-05 6.05E-09 5. 30 E-0 5 4.77E-09 4. 2 4 E-0 5 PR143 8. 0 E-0 9 6.0E-05 4.42E-05 3.8 8E-0 5 3.78 E-0 9 3. 3 6 E-0 5 PR144 1.1E-0 8 8.5 E-0 5 6.05E-09 5.31E-05 2. 8 9 E-10 2. 57E-0 6 NP239 1.1E-08 8. 4 E-0 5 7. 5 8 E-0 9 6.65E-05 3.0 3 E-0 9 2.69E-e5 CR51 1.8E-07 1.3E-03 1. 2 3 E-0 7 1.08E-03 7.05E-08 6. 2 6 E- i g MN54 5.4E-08 4.0E-04 3. 9 0 E-0 8 3. 4 2 E-0 4 6.29E-08 5. 59E-0 4 MN56 6.7E-09 5.0E-05 2.55E-09 2.27E-05 FESS 2.9E-07 2.2E-03 2.14 E-07 1.87E-03 5.18 E-0 8 4. 60 E-0 4 FES9 1. 2E-07 8.8E-04 8 .24 E-0 8 7.23E-0 4 6.92E-08 6.14E-04 C058 2. 2E-0 6 1. 6 E-02 1. 56 E -06 1.37E-oz 1.72 E-0 6 1.53 E-0 2 0060 3.7E-0 7 2. 8E-03 2.71 E-0 7 2.37E-0 3 1.22E-07 1. 0 8 E-0 3 H3 1.6E-01 1.2E 03 4 . 6 9 E-0 2 4.11E+02 1.91E-01 1.70E 03 TOTAL 1.6E-01 1.2E 03 4.69E-02 4.12E+02 1.91E-01 1.70E 03 TOTAL (NON-TRITIUM) 1.6E-0 4 1.2E 00 8.50E-05 7.46E-01 4 . 67 E-0 5 4.14E 01 O

( cs CD L1 tas 2 of 2 Amendment 19 12/12/75

SWESSAR-P1 TABLE 11.2-18 ACTIVITY AT l>ISCHARGE POII.T (DESIGN CASE)

Discharge dilution flow rate (gpm)= B6W 7.91E 03 11 CE, W-41, W-3S 3.60E 03 Tritium discharge rate (cur ies/ year) B&W 1.14E 03 CE 4.11E 02 W 1.70E 03 B&W C-E W W-3S Actual Actual Actual Actual Activity Activity Activity Activity Nuclide ,( uCi/cc) (uCi/ce) (uCi/cc) (uCi/cc)

RR83 1.8E-11 1.57E-11 1.57E-11 7.94E-11 BR84 7. 7E- 3 2 2.81E-12 2.4aE-12 3.09E-11 BR85 9.2E-13 4.73E-14 3.74E-14 3.88E-12 1131 1.0E-08 1.5 3E-0 8 1.26E-08 1. 6 7E-0 8 I132 6.4E-10 1.01E-0 9 3.51E-10 1.61E-09 I133 2. 3E- 39 4.90E-09 4.55E-09 6.91E-09 I134 1.1E-10 5.62E-11 5.12E-11 4.55E-10 1135 6.0E-10 9.18E-10 9.32E-10 2.42E-09 RB88 6. 7E- 10 4.94E-11 1.39E-10 2. 35E-09 SR89 3.8E-11 5.32E-11 4.29E-11 a.66E-11 SR90 2.1E-12 2.82E-12 2.25E-12 3.91E-12 SR91 6.6E-13 9.64E-13 9.43E-13 2.12E-12 Y90 2.2E-12 2.46E-12 1.68E-12 3.15E-12 Y91M 6.2E-13 5.94E-13 1.88E-13 1.27E-12 Y91 7.0E-11 1.10E-13 -

is Y93 2.7E--3 1.77E-13 1.8 5E- 13 6.70E-13 ZR95 6.6E-12 9.12E-12 7.33E-12 9.70E-12 NB95M -

7.76E-14 -

NB95 6.1E-12 8.43E-12 8.42E-12 9.01E-12 MO99 5.4E-09 2.08 E-0 9 1.93E-09 1.06E-08 TC99M 4.4E-09 1.9 3E-09 6.84E-10 8.97E-09 RU103 2.9E-12 4.01E-17 3.22E-12 4.28E-12 RU 106 3.6E-13 4.97E-13 3.99E-13 5.28E-13 RH103M 2.8E-12 3.94E-12 2.31E-13 4.21E-12 RH106 3.6E-13 4.97E-13 2.39E-14 5.28E-13 TE125M 8.1E-13 1.11E-12 2.55E-13 1.19E-12 C7N TL127M 2.1E-11 2.86E-11 2.30E-11 3.G5E-11 crs

~

TE127 2.0E-11 2.80E-11 9.57E-12 2.92E-11 gg TE129M 3.2E-10 4.41E-10 3.54E-10 4.71E-10 TE129 2.0E-10 2.84E-10 2.57E-11 3.02E-10 TE131M 1.8E-11 3.45E-11 3.04E-11 4.35E-11 TE131 4.6E-12 6.46E-12 1.91E-12 1.28E-11 L I TE132 5.0E-10 8.23E-10 6.96E-10 9.17E-10

-

• CS134 4.5E-09 7. 81 E-0 9 4.84E-09 5.8 2E-09

~

.. CS136 9.9E-10 4 . 4 6 E-0 9 1.60E-09 1.61E-09 CS137 2. 3E-08 3.15E-08 2.50E-08 2.95 E-0 8 Amendment 19 12/12/75

SWESSAR-P1 TABLE 11.2-18 (CONT)

E5w c-E w w-3s Actual Actual Actual Actua l Activity Activity Activity Activity Nuclide luci/cc) (uCi/cc) (uci /cc) (uci /ce)

CS138 - -

RA137M 2.1E-08 2. 9 4 E-0 8  ? .14 E-0 9 2.75E-08 BA14G 2.4E-11 3.43E-11 2.79E-11 3.67E-11 LA140 2.4E-11 3.29E-11 2.10E-11 3.44E-11 CE1c1 5.6E-12 7.76E-12 6.28E-12 8.31E-12 CE143 4.4E-13 8.23E-13 7.32E-13 1.02E-12 7.88E-12 U CE144 5.4E-12 7.40E-12 5.91E-12 PR143 3.8E-12 5.41F-12 4.68E-12 5.83E-12 PR144 5.4E-12 7.40E-12 3. 5 8 E- 13 7.88E-12 NP239 5.3E-12 9.2RE-12 3.75E-12 1.06E-11 CR$1 8.5E-11 1.50E-10 8.73E-11 1.55E-10 MN54 2.6E-11 4.78E-11 7.80E-11 4.84E-11 MN56 3.2E-12 3.16E-12 2.40E-11 VE55 1.4E-10 2.61E-10 5.42E-11 2.64E-10 FE59 5.6E-11 1.01E-10 8.57E-11 1.03E-10 C058 1.0E-09 1.91E-0 9 2.13E-09 1.9 5 E-0 9 CO60 1.7E-10 3.31E-10 1.51E-10 3.34E-10 H3 7.7E-05 5.73 E-0 5 2.37E-04 2 a37E-04 TOTAL 7.7E-05 5.74 E-0 5 2.37E-04 2.08E-04

?

c;rs

(,3 i

^

k' 2 of 2 Amendment 19 12/12/75

SWESSAR-P1 10 TABLE 11.2-19 is deleted

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h L I AAT( 13361228186865 11 222959581121351171 1 S B M A A T T y)

N 89145576767878 96 644777775555775353 O ltc 0C100000000000 00 000000000000000000 C aic - - - - - - - - - - - - - - - - - - - - - - - - - -

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o EEEEEEEEEEEEEEEEE EEEEEEEEEEEEEEEEEE r i s K i.r t eai cl ru eC 29756669223446433 411323295530061134 o d 4

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@ 9 SWESSAR-P1 TA3LE 11.2-20 (CONT)

BEW C-E W Discharge Discharge Discha rge Activit y Rate Prom Activity Rate Prom Activity Rate From Initial After Waste bic- Initial After Waste Dis- Initial After Waste Dis-Activity Treatment posal Sys- Activity Treatment posal Sys- Activity Treatment posal Sys-Nucli (uC1/cc) (uCi/cc) tem (Ci/yr) (uci/cc) (uCi/cc) tem (Ci/y r) (uCi/cc) uCi/cc) tosn (Ci/yr)

CS138 - - -

1.3/E-10 1.37E-14 8.48E-13 hA137M 2.2 E-0 3 2.2E-07 1. 4 E -0 5 1. 0 2 E-0 3 1. 04 E -07 6.36E-06 3. 8 8 E-0 4 3.88E-08 2.40E-06 RA140 3.76-06 3.6E-13 2.2E-08 1. 21E-0 6 1.16E-10 7.09E-09 5.13E-07 5.13E-11 3.18E-09 LA140 4.1E-06 4.OE-10 2.5E-08 1. 3 6 E-06 1.31E-10 8 .0 2 E-0 9 5. 57 E-0 7 5.57E-11 3. 4 5 E-0 9 CE141 3.1E-06 3.0E-10 1.9E -0 8 1.22E-36 1.20E-10 7.35E-09 4.77E-07 4.77E-11 2.96E-09 CE143 5. 4 E-0 8 3.7E-12 2.3E-10 9.0 7E-0 9 5.96E-13 3.65E-11 1.13E-08 1.11E-12 6.97E-11 CE144 3.8E-06 3.7E-10 2.3E-08 1.72E-06 1.72E-10 1.05E-08 6.52E-07 6.52E-11 0.04E-09 PR143 9.5E-07 9.0E-11 5.7E-09 3.07E-07 2.94E-11 1.80E-09 1.36E-07 1.36E-11 8.43E-10 d

Patos 3.8E-06 3.7E-10 2. 3E -0 8 1.72 E-0 6 1.72E-10 1.0 5E-0 8 6.52E-07 6. 5 2E-11 4.04E-09 NP239 3.1E-0 6 2.4E-10 1.5 E-0 8 5. 43 E-07 4.25E-11 2.60E-09 7.27E-05 7.27E-09 4.50E-07 CR$1 7.7 E -0 4 7 . 7E-0 8 4.6E-06 1. 5 5 E -0 3 1.52E-07 9.30E-06 8.28E-04 8.28E-08 5.13E-06 MN54 7.7E-04 7.7E-08 4.7E-06 1.59E-03 1.59E-07 9.73E-06 7.31E-04 7.31E-08 4 .5 3 E-06 FESS 4.5E-03 4.5E-07 2.8E-05 9.59E-03 9.58E-O r 5. 8 7E-0 5 4.42E-03 4.42E-07 2.74E-05 FE59 7.7E-04 7.7E-08 4.7E-0 6 1.60E-C3 1. 5 8 E-07 9.68E-06 7.84E-04 7.84E-08 4.86E-06 C058 1.9 E-0 2 1.9E-0 6 1. 2E -0 4 4 . 0 6E -02 4 .0 3 E-0 6 2 . 4 7E-0 4 1. 9 5 E-0 2 1.95E-06 1.21E-04 CO60 5.9E-03 5. 9E -07 3.7E-05 1. 25E-02 1.25E-06 7.66E-05 5.71E-03 5.71E-07 3.54E-05 TOTAL 4 .5 E-0 2 4.5E-06 2.8E-04 7. 25E-0 2 7.19E-06 4.41E-04 3.44E-02 3.44E-06 2.13E-04 is (TN CD 1

s L;

2 of 2 Amendment 19 12/12/75

O SWESSAR-T1 TABLE 11.2-21 ACTIVITY FPOM REAC'IOR PLANT SAMPLING SINKS (EXK.CTED CASE)

Decc>ntuminotion f actor of waste disp > sal system for this source = 2.00E 01 Decay time in waste disposal system (hours) = 3.00E 03 Flow rate (gal /yr) = 3.00E 03 ESW C-E W Discharge Discharge Discharge Activity Rate From Activity Rate From Activity Rate From Initial After Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treatment posal Syc- Activity Treatment posal Sys- Activity Treatment posal Sys-Nuclide (uCi/cc) (uci/cc) te m (Ci/yr) (uCi/cc) (uci/cc) tem (Ci/yr) (uCi/cc) (uci/cc) tem (Ci/yr)

HR83 5.6E-03 1. 7E-0 9 2.0E-08 5.19E-03 1.61E-09 1.80E-08 5.04E-03 1.23E-09 1.39E-08 BF84 2.9E-03 1.3E-18 1.4E-17 2 . 8 4 E-0 3 1.24E-18 1.39E-17 2.83E-03 1.57E-18 1.78E-17 BR85 3.3E-04 1.2E-51 1.4E-50 3.29E-04 1.22E-51 1.37E-50 3.31E-04 0.0 0.0 1131 4.3E-01 4.0E-05 4.6E-04 2.75E-01 2.56E-05 2.87E-04 2.33E-01 2.17E-05 2. 4 6E-0 4 I132 1.2E-0? 3. 6E-0 6 4.1E -0 5 1.08E-01 2.41E-06 2.70E-05 1.0$E-01 2.53E-08 2. 8 8E-07 1133 5.3E-01 2.7E-05 3.1E-04 3.96E-01 2.03E-05 2.28E-04 3.53E-01 1.82E-05 2.07E-04 1134 5 . 3 E-0 2 6.5E-13 7.4E-12 5.13E-02 6.35E-13 7.128-12 5.08E-02 6.71E-13 7.62E-12 I135 2.4E-01 3.0E-06 3.4E-05 2.02E-01 2.54E-06 2.84E-05 1.89E-01 2.39E-06 2.72E-05 Rb88 2.2 E-01 8.6E-26 9.8E-25 2.19E-01 8. 59E -2 6 9.64E-25 2.20E-01 1.99E-25 2.26E-24 SR89 5.7 E-0 4 5. 7E-0 8 6.5E-07 3. 55E-0 4 3.51E-08 3.94E-07 2.99E-04 2.96E-08 3.36E-07 SR90 1. 6 E-0 5 1.6E-09 1.9E-08 1.01F-05 1.01E-09 1.13E-08 8.53E-06 8.53E-10 9.69E-09 SR91 8.4E-04 2.0E-08 2.3E-07 6.87E-04 1.64E-08 1.84E-07 6.32E-04 1.52E-08 1.73E-07 Y90 2. 6 E-0 5 2.4E-09 2.8E-08 1. 7 4 E-0 5 1.60E-09 1. 79 E -0 8 1.50E-05 1.21E-09 1. 37E-0 8 Y91M 4.2 E-0 4 1. 3E -0 8 1.5E-07 4.15E-04 1.06E-08 1.19E-07 4.11E-04 2.64E-15 3.00E-14 Y93 1.7E-04 4.3E-09 4 . 9 E -0 8 1. 3 7E-0 4 3.52E-09 3.95E-08 1.2bE-04 3.10E-09 3.57E-08 ZR95 9 .9E-0 5 9.8E-09 1.1E-07 6 .0 9 E-0 5 6.04E-09 6 . 77 E-0 8 5.12E-05 5.07E-09 5.76E-08 NB95 8.2E-05 8.1E-09 9.2E-08 5.08E-05 5.00E-09 5.60E-08 4.28E-05 4.21E-09 4. 78 E-0 8 MO99 6. 9 E-01 5.6E-05 6.4E-04 4 . 6 2 E-01 3.75E-05 4 . 21 E-0 4 3.97E-01 3.24E-05 3.68E-04 U TC99M 4.7E-01 5. 2E-0 5 5.9E-04 4.06E-01 3.59E-05 4.02E-04 3.81E-01 3.78E-06 4.29E-05 RU103 7.4E-05 7.3E-09 8.3E-08 4.75E-05 4.50E-09 5.05E-08 3.85E-05 3 .7 9E-0 9 4. 31E-0 8 RU106 1.6E-05 1.6E-09 1.9E-08 1.01E-05 1.01E-09 1.13E-08 8.53E-06 8.52E-10 9.67E-09 kH103M 5.1E-05 7.1E-09 8.1E-0 8 4.91E-05 4.42E-09 4 .9 5 E-0 8 4.P5E-05 2.71E-15 3.08E-14 Rh106 1.1E-0 5 1.6E-09 1.9E-08 1.10E-05 1.01E-09 1.13E-08 1. tie-05 0.0 0.0 TE125M 4.8E-05 4.7E-09 5.4E-08 2.94E-05 2.91 E-09 3. 2 6 E-0 8 2.4tE-05 2.46E-09 2.79E-08 TE127M 4.6E-04 4.6E-08 5. 2 E -07 2. 8 4 E-0 4 2.82E-08 3.17E-07 2.392-04 2.38E-08 2.70E-07 TE127 1.1E- 0 3 6.0E-06 6.8E-07 9.00E-04 4.20E-08 4.71 E-0 7 8.28E-04 1.89E-08 2.15E-07 TE129M 2.3E-03 2.3E-07 2.6E-06 1. 4 2E-0 3 1.40E-07 1.57E-06 1.20E-03 1.18 E-0 7 1.34E-06 TE129 1. 8 E-0 3 1.4E-07 1.6E-06 1.74E-03 8.95E-08 1. 0 0 E-0 6 1.72E-03 2.63E-13 2.98E-12 C7' TE131M 1.6F-03 1.0E-07 1.1E-0 6 2.59E-03 1.63E-07 1.83E-06 2.27E-03 1.40E-07 1.59E-06 CT' TE131 1.2E-03 1.8E-08 2.1E-07 1.20E-03 2.98E-08 3. 34 E -07 1.20E-03 2.41E-22 2.74F-21 CO TE132 4. 2 E-0 2 3.5E-06 4.0E-05 2.7 7E-0 2 2.32E-06 2.60E-05 2.37E-02 1.98E-06 2.25E-05 CS134 4.1E-02 4.1E-06 4.7E-05 2.54E-02 2.54E-06 2.85E-05 2.14E-02 2.14E-06 2.43E-05 CJ136 2.1E-02 2. 0 E-0 6 2.3E-05 1. 3 3E -0 2 1.28E-06 1.43E-05 1.13E-02 1.08E-06 1.23E-05 CS137 3.0E-02 3.0E-06 3.4E-05 1.83Z-02 ).83E-06 2.05E-05 1.54E-02 1. 54 E-0 6 1.75E-05

, BA137M 1. s-02 2.8E-06 3.1E-05 1.76E-02 1.71E-06 1.42E-05 1.76E-02 0.0 0.0 BA140 a.bE-04 3.4E-08 3.9E-07 2.24E-04 2.14E-08 2.40E-07 1.89E-04 1.81E-08 2.05E-07

~-

1 of 2 Amendaent 19 1;/12/75 i

SWESSAR-P1 TABLE 11.2-21 (Coffr)

I'E W C-E W Discharge Discharge Discharge Activity Rate From Activity Rate Prom Activity Rate Prom Initial Af ter Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treatment posal Sys- Activity Treatment posal Sys- Activity Treatment posal Sys-Nuclide (uCi/cci (uCi/cc) t em (Ci/yr) (uCi/cc) (uCi/cc) tem (Ci/yr) (uCi/cc) (uCi/cc) tem (Ci/yr)

LA140 2.2E-04 2.6E-08 2.9E-07 1.55E-04 1. 74 E-0 8 1.95E-07 1.3sE-04 9.56E-09 1.09E-07 CE141 1.2E-04 1.1E-0 8 1.3E-07 7.11E-05 5.98E-09 7.8 3 E-0 8 5.99E-05 5.88E-08 6.68E-08 CE143 5.8E-05 3.8E-09 4.4E-08 4 .14 E-0 5 2.72E-09 3.0$E-08 3.6 2E-05 2.38E-09 2.70E-08 CE144 5.4E-05 5.4E-09 6.2E-08 3.35E-05 3.34E-09 3. 75E -0 8 2.82E-05 2.81E-09 3. 2 0 E-0 8 PE143 0 .1 E -0 5 7. 8 E-0 9 8.8E-08 5.08E-05 4. 87E -0 9 5. 4 6 E-0 8 4.30E-05 4.13E-09.4.69E-08 PR144 3.6E-05 5.4E-09 6.2E-08 3.61E-05 3. 34 E-0 9 3.75E-08 3.62E-05 4.06E-30 4.61E-29 NP239 1.8E-03 1.4E-07 1. 6E-0 6 1.23E-03 9.62E-08 1.08E-06 1.06E-03 8.30E-08 9 . 4 2 E-0 7 3 CRS1 3.1E-03 3.0E-07 3.5E-06 1.93E-03 1.89E-07 2.12E-06 1.63r-03 1.60E-07 1.81E-06 MN54 5.1E-04 5.1E-08 5.8E-07 3.14E-04 3.13E -0 8 3.51E-07 2.64E-04 2.6 3E-0 8 2.99E-07 FESS 2 . 6 E-0 3 2.6E-07 3.0E-06 1.62E-03 1.62E-07 1.82E-06 1.36E-03 1. 36 E-0 7 1.54E-06 FES9 1.6E-03 1.6E-07 1.8 E-0 6 1.02E-03 1.01E-07 1.13E-06 8.55E-04 8.44E-08 9.59E-07 C058 2.6E-02 2.6E-06 3.0E-04 1. 6 2E-02 1.61E-06 1.80E-05 1.37E-02 1.36E-06 1. 5 4 E-0 5 CO60 3.3E-03 3.3E-07 3.7E-06 2.03E-03 2. 0 3 E-07 2. 2 8 E -0 6 1.71E-03 1.71E-07 1.94E-06 TOTAL 3.0E 00 2.03E-04 2.3E-03 2.26E 00 1.37E-03 1.54 E-0 3 2.0 6 E- 00 8.77E-)5 9.9 6E-0 4 7

c:~

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0 2 of 2 Amendment 19 12/12/75

SWESSAR-P1 TABLE 11.2-22 ACTIVI'W FROM DORON RECOVERY LETDOWN (EXPECTED CASE)

Decontamination f actor of waste dispo al system f or this source = 1.00E 00 Decay thme in waste disposal system (hours) = 0.0 Flow rate (gal /yr) = ,

C-E 1.25E 0% II W 4.40E Oi L B&W C-E W Discharge Discharge Discharge Activity Rate From Activity Rate Fram Activity Rate From Initial Atter Waste Dis- Initial Af ter Waste Dis- Initial After Waste Dis-Activity Treatment posal Sys- Activity Treatment posal Sys- Activity Treatment posal Sys-Nuclide (uCi/cc) (uCi/cc) tem (Ci/yr) (uCi/cc) (uCi/cc) tem (Ci/yr) (uCi/cc) (uCi/cc) tem (Ci/yr)_

BR83 8.2E-10 8.2E-10 9 . 3 E-0 7 2.14 E-0 9 2.14E-09 9.99E-07 2.10 E-0 9 2.10E-09 3. 4 6 E-0 6 BR84 9.4E-11 9.4E-11 1.1E-07 2.58E-10 2.58E-10 1.21E-07 2.60E-10 2.60E-10 4.28E-07 BR85 1.0E-12 1.0E-12 1.1E-09 2.82E-12 2.82E-12 1.32E-09 2.87E-12 2. 8 7E- 12 4.73E-09 1131 2.9E-06 2.9E-06 3.3E-03 2. 3 8 E-0 6 2 . 38 E-0 6 1.11E-03 2.02E-06 2.02E-06 3.33E-03 1132 1.9 E -07 1.9E-07 2.2E-04 2. 3 2E -07 2.32E-07 1.08E-04 2. 04 E-07 2.04E-07 3.36E-04 1133 6.8E-07 6.8E-07 7.7E-04 1.33E-06 1. 3 3 E-0 6 6.21E-04 1.19 E-0 6 1.19E-06 1.9 6E-03 1134 2.BE-09 2 . 8 E-0 9 3. 2 E -0 6 7.67E-09 7.67E-09 3.59E-06 7.66E-09 7.66E-09 1.26E-05 1135 9.8E-08 9. 8 E-0 8 1.1E-04 2.31E-07 2. 31E-0 7 1.08E-04 2.19E-07 2.19E-07 3.61E-04 RB88 4.0 E-09 4 . 0E -0 9 4 . 5E -0 6 1.11 E-0 8 1.11E-08 5.18E-06 4 . 53 E-0 8 4.53E-08 7.46E-05 SR89 5.4E-09 5. 4 E -09 6.1E-06 3. 4 7E-0 9 3.47E-09 1.62E-06 2.92E-09 2.92E-09 4.81E-06 SR90 1.6E-10 1.6E-10 1. 9 E-0 7 1.01E-10 1.01E-10 4 . 72 E -0 8 8.52E-11 8.53E-11 1.40E-07 SR91 5.0E-10 5.9E-10 5.7E-07 1.14 E-0 9 1.14 E-0 9 5.32E-07 1.06E-09 1.06E-09 1.7 5E-06 Y90 2.0E-10 2.0E-10 2. 3 E-07 1.49E 10 1.49E-10 6.96E-08 1.28E-10 1.28E-10 2.11E-07 Y91M 3.2E-10 3.2E-10 3.6E-07 7.31E-10 7.31E-10 3.42E-07 4.82E-10 4.82E-10 7.94E-07 Y91 3.1E-0 8 3.1E-0 8 3.5E-05 3.75E-11 3.75E-11 6.17E-08 Y93 1.1E-10 1.1E-10 1.2E-07 2.39E-10 2.39E-10 1.12s-07 2.22E-10 2.22E-10 3.66E-07 19 ZR95 9.4E-10 9.4E-10 1.1E-06 5.98E-10 5.98E-10 2.802-07 5.03E-10 5.03E-10 8.28E-07 NB95M - - -

2.72E-11 2.72E-12 4 .4 8 E-09 NB95 7.5E-10 7.5E-10 8. 4 E-07 4.91E-10 4.91E-10 2.30E-07 4.30E-10 4.30E-10 7. 0 8 E-07 MO99 2.6E-06 2.6E-06 2.9E-03 3 .0 8 E-0 6 3.0 8E-06 1.44E-03 2.65E-06 2.65E-06 4.36E-03 TC99M 2.4E-06 2.4E-06 2.8E-03 2.9 4 E-0 6 2.94E-06 1. 3 7E -0 3 1.54E-06 2.54E-06 4.18E-03 RU103 6.8E-10 6.8E-10 7.7E-07 4.43E-10 4.43E-10 2.07E-07 3.74E-10 3.74E-10 6.16E-07 RU106 1.6E-10 1.bE-10 1.8E-07 1.01E-10 1.01E-10 4 .71 E-0 8 8.50E-11 8.50E-11 1.40E-07 s RII103M 6.7E-10 6. 7E-10 7.5E-07 4.36E-10 4.36E-10 2.04E-07 3.76E-10 3.76E-10 6.19E-07 7 RH106 1.6E-10 1.6E-10 1.8E-07 1.01E-10 1.01E-10 4.71E-0C 8.50E-11 8.50E-11 1. 4 0 E-07 TE125M 4.5E-10 4.5E-10 5.1E-07 2.88E-10 2.88E-10 1.35E-07 TE127M 4 .5 E-0 9 4 .5E-09 5.1E-0 6 2. 81E-0 9 2.81E-09 1.31E-06 2.36E-09 2.36E-09 3.89E-06 TE127 4 . 8 E-0 9 4. 8 E-0 9 5.5E-06 3 .78 E-09 3. 78E -0 9 1.77E -0 6 3.32E-09 3.32E-09 5.47E-06 TE129M 2.1E-08 2.1E-08 2. 4 E-0 5 1.37E-08 1.37E-08 6.41E-06 1.1bE-08 1.16E-08 1.91E-05 3 TE129 1.3E-08 1.3E-08 1.5E-05 8.95E-09 8 . 95 E-0 9 4.18E-06 1.17E-08 1.17E-08 1.93E-05 TE131M 2.9E-09 2.9E-09 3.3E-06 1.14 E-0 8 1.14E-08 5.34E-06 1.01E-08 1.01E-08 1.66E-05 TE131 5.6E-10 5.6E-10 6.3E-07 2.14 E-0 9 2.14 E -0 9 9.99E-07 2.10E-09 2.10E-09 3.46E-06 TE132 1.8E-07 1.8E-07 2.0E-04 1. 95 E-07 1.95E-07 9.11E-05 1.67E-07 1.67E-07 2.75E-04 1 of 2 Amendment 19 12/12/75

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)

- - r emssv g oi y/

rrDSi 444 466677776565545 2 aF C 000 000000000000000 0 h el( - - - - - - - - - - - - - - - - - - -

ceta EEE- EEEEEEEEEEEEEEE E stssm 693 11 1231218170787 2 iaaoe .

D R W pt 413 333116766353123 1 t

y n)

. ec 777 799900009898878 5 i mc 000 000011110000000 0

vrt/ - - - -

ieai EEE- EEEEEEEEEEEEEEE E W tt eC 1 60 887024440816553 1 6 cf ru B AAT( 413 222115656252123 1 y) ltc 777 739900009898878 5 aic 000 00001 1110000000 0 iv/ - - - - - - - - - - - - - - - - - - -

tii EEE- EEEEEEEEEEEEEEE E itc 160 88702444081 6553 1 ncu .

IA( 413 222115656252123 1 e

d M i 4678700134349 L l 333334444444314S980 A c

@ N u

11111111111 12S5SS56 SSSSAAAEEERRPRNEEOO CCCCBhLCCCPPNCMFFCC T T

O L Er C

OG'D

S I

) 95

- - r 17 emssy /

g oi y/ 448 424 2 t2 rrDSi 000 000 0 n1 aF C - - - - - - -

e/

h el( EEE EEE E m2 ceta 222 633 9 d1 stssm 474 810 2 n

iaaoe D R W pt 245 315 1 m

A t

414 y n )_ 660 645 4 000 t ec 001 000 0

EEE W ivrt/mc - - -

EEE EEE E 000 ieai 823 338 8 003 tteC 742 437 4 ctru 122 AAT( 256 415 1 y) 223 202 0 ltc 000 000 0 aic - - - - - -

iv/ EEE EEE E

) tii 434 918 0 E itC 843 437 5 S ncu 251 415 1 A IA(

C D )

F - r T enssy C g oi y/ 44 3433 2 E rrDSi 00 0000 0 P aF C - - - - - - -

X h el( EE EEEE E E ceta $1 8973 8

( stssm 03 2366 2 iaaoe l

I D R W pt 62 1481 1 3 S I

1 2 I P - I

- 2 F y t

R n1 66 5645 4 A 1 N t e c_ 00 0000 0 1 S 1 I E iv rmc - - - - - - -

S S - t f_ EE EEEE E f E v E C ieai 18 8918 9 o

W T R tteC 06 4008 4 S n cf ru 1 A T AATf 72 1511 1 T NE P y) 1201 S 22 0 ltc 00 0000 0 M aic - - -- -

O i v/ EE EEEE E R tii 68 8619 0 F itC 16 4108 5 m ncu 72 Y e IA( 1511 1 T t I s y

=

V ) )

I s s enssy r

T r C

A l

a o u r r"DSi g

iy/ 44 3433 2 s h aF C 00 0000 0 o ( h el( - - - - - - -

p ceta EE EEEE E s st ssm 13 3486 3 i m i aaoe D R W pt 62 1481 1 d t s

e y t s s t a l y ni w as t ec 66 00 5 6 4 *:

0000 4

0 i rc f o vrt/ - - - - - - -

o p ieai EE EEEE E s W tt eC 07 5109 5 r i T, ct ru o d B AATf 72 1511 1 t

c e=

a t) f sr y) eay ltc 22 1201 0 ncw/ aic 00 0000 0 or l iv/ -- - - -

iuna tii EE- EEEE E t oi g itc 17 5109 5 as ( ncu n e IAf 72 1511 1 isme miit ahta r e tt d n y i L 4 oraw coco l

c 1465980 S555S56 A

r

'I L

@ ef el D DF N u RNNEE0O u CMMFFCC T OPOC L F

5 1

)

- - r 95 emssy g oi y/ 98 5853658989599956995 8873726666 8 1 7 rrDSi 01 0001020000100000001 0001020000 0 /

aF C - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - t2 h el( EE EEEEEEEEEEEEEEEEEEE EEEEEEEEEE E n1 ceta 11 0490346648049288060 1948763607 7 e/

stssm 83027695932279642756200 577805916206 m2 iaaoe d1 D R W pt 12032293241213476455140 321323231202 n e

m A

t 414 y n) 10 7075870201711178127 0095948888 0 000 t ec 12 0101021111111100111 1101020000 1 i mc -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

EEE W vrt/ FE EEEEEEEEEEEEEEEEEEE EEEEEEEEEE E 000 ieai 93 1784348288865068004 2556753960 6 381533900507 000 tteC cf ru 15014753.?83415091167360 11022162128112344333820 211212121101 124 AAT(

y) 55633343368676677337877 665555444406 ltc 00000000000000000000000 000000000000 aic - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

lv/ EEEEEEEEEEEEEEEEEEEEEEE EEEEEEEEEEEE

) tii 16372454422661397715247 377817190024 E f tC 97220498193140291877370 301621301578 S ncu . . . .

281121221111 A IA( 42321341228614144333841 C

D )

E - r T emssy C g ai y/ 981565365898989995599999887778666668 E rrDSi 015000102000000000000000000030000000 P aP C - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

X h el( EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE E ceta 51941780638935420848757S344185916703

( st ssm 387759272143351834254442110333378651 iaaoe S D R W pt 211332931512215875561614462124331223 4 E 1 2 T P - S

- 2 A y t

R W n) 10376?588020101 11 7712121009090888880 A 1 t ec 125000102111111110011111110101000001 2 S 1 Y E i mc - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

S R - vrt/ EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE E F V C ieai 7190589782506339760931 34506290674879 f W L 'I tteC 521539143486504886538388713759242760 o S R A cf rU A R AAT( 111221628391113543349492241812221 112 1 T O B

A L y) 5563334336867667733787776655554n4446 ltc 0000000000000000000000000000000O0000 M ai c - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

O iv/ EEIEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE R tii 67 056074650054450665977788037080828 F itf 07 2 t08091427703995948708773751743771 m nc IAp 57 ,'.13512396141544349412281121221112 Y e T t I s y

=

V ) )

I s s emssy r

T r C l u g oi y/

A a o rrDSi aP C 9815653658989898855898998877786666C8 s h 015000102000000000000000000000000000 o ( h el( - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

p ceta EEEEEEEEEEEEEEEEEEEEEEEEEEEEEE3EEEEE s m i e st ssm iaaoe 698040643440694423714140893150219410 d t D R W pt 21165494182331611871212768321 2562445 s

e y t s s y t a l n) w as t ec 103787588010101117711111009900888880 ivrt/

mc 1250001021111111 10011111110011000001 f o o p ieai EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE s W tt eC 722957394560432595116066592488409973 r i & cf r2 o

t d B AATJ 11133262851221 4975571714452191341223 r e=

'a t) y)

f =eay sr ltc 556333433676766773377777655555444446 ncw/ aic 000000000000000000000000000000000000 or l iv/ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

i una tii EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE t oi g itc 482212131662516607626917512862100975 as n e

( ncu IAf 523415522518241986471414412111442213 i sme miit ahta e tt y

r d M MM M M M n i M36365779911246;70 oraw coco l 345123458901 M 559900002222233333334

@ ef el D DF N c

u 88833333889901 3999911111 1 11111111111 RRR11111BnRR999RBOCUUH1 FEEEEEEESSSAA BBB1I111RSSSYYYZNMTRRRRTTTTTTTTCCCBB 1

7N m3 L p "

C c?'

SWESSAR-P1 TABLE 11.2-24 (COffr) acW C-E W Discharge Discharge Discharge Activity Rate Prom Activity Rate Pram Activity Rate From Initial After waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treatment posal Sys- Activity Treatment posal Sys- Activity Treatment posal Sys-Nuclide (uCi/cc[ (uCi /cc) tem (Ci/yr) (uCi/cc) (uCi/cc) tem (Ci/yr) . (uCi/cc) (uCi/cc) tem (Ci/yr)

LA140 2.2E-06 2.5E-10 3.8E-08 51E-0 6 1.69E-10 2. 54 E-0 8 1.32E-06 9.32E-11 1.41E-08 CE141 1.lE-06 '.1E-10 1.7E-0 8 b . 3 3 E-07 6.81E-11 1.02 E-0 8 5.84E-07 5.74E-11 8.68E-09 CE143 5.7E-07 3.7E-11 5.7E-09 4 . 0 4 E-07 2.65E-11 3. 97E-0 9 3.53E-07 2.32E-11 3.51E-09 CE144 5.3E-07 5.3E-11 8.0E-09 3. 2 7E-07 3.26E-11 4.88E-09 2.75E-07 2.74E-11 0 .15 E-0 9 PR143 7.9F-07 7.6E-11 1. 2 E-0 8 4 .9 5 E-07 4.75E-11 7.11E-09 4.19E-0 7 4. 0 2E- 11 6.09E-09 Ph144 3.5E-07 5 . 3E-11 8.0 E-0 9 3.52E-07 3.26E-11 4.88E-09 3.53E-07 3.69E-32 5.99E .0 NP239 1. 8 E -0 5 1.4E-09 2.1E-07 1.20 E-0 5 9.38E-10 1.41E-07 1.03E-05 8.09E-10 1.23E-07 15 CR51 3.3E-05 3.0E-09 4.5E-07 1. 8 8 E-0 5 1. 8 4 E -0 9 2.76E-07 1. 5 9 E -0 5 1.5 6 E-09 2 . 3 6 E-07 MN54 5.0E-06 5.0E-10 7. 6E-0 8 3 .0 6 E-0 6 3.06E-10 4. 5 8E-0 8 2. 57 E-0 6 2.57E-10 3.89E-08 FESS 2. 6 E-0 5 2.6E-09 3.9E-07 1.58E-05 1.5 8 E-0 9 2.37E-07 1. 33 E-0 5 1.33E-09 2.01E-07 FES9 1.6E-05 1.6E-09 2.4E-07 9.9 5E-0 6 9.82E-10 1.47E-07 8. 34 E-0 6 8.23E-10 1.25E-07 C058 2.6 E-O w 2.5E-08 3.9E-06 1.58E-04 1.57E-08 2.35E-06 1.34E-04 1.32E-08 2.01E-0 6 CO60 3.2E-05 3. 2E -0 9 4 .9 E-0 7 1.98 E-0 5 1.9 8 E-0 9 2.96E-07 1.67E-05 1. 6 7E-09 2.52E-07 TOTAL 2.9E-02 2.0 E-0 6 3.0E-04 1. 21E-0 2 1.34E-06 2.00E-04 2.01E-02 8.55E-07 1.29E-04 c.N

(~x C_C t I f )

U1 2 of 2 Amendment 19 12/12/75

3 N

) 95

- - r 17 emssy 6762725454 /

g oi y/ 09 485466688858979745783 0001020000 t2 rrDSi 11 000102000010000000001 - - - - n1 aP C - - - - - - - - - - - - - - - - - - - - - - -

h el( EE EEEEEEEEEEEEEEEEEEEEE EEEEEEEEEE e/

ceta 22 827989972245944028300 1378121 850 m2 6007561915599341818829410 4479570360 d1 stssn iaaoe n D R W pt 3104647161514224242231510 1358532131 e m

A t ,

414 y n) 21 607588800070191967905 8983947676 000 t ec 12 010102011111101000011 0001020000 i mc -- - - - - - - - - - - - - - - - - - - - - - - - -

EEEEEEEEEE EEE W vrt/ EE EEEEEEEEEEEEEEEEEEEEE 892870979928973043025 2565882781 007 ieai 44 1163250045 004 tteC 4501700933383562222299160 cf ru 2581853251 121 AAT( 5107971292827336464442810 y) 5682325334656666575225656 4444453232 E 000000000G G ltc 0000000000000000000000000 A ai c EEEEEEEEEE K iv/ EEEEEEEEEEEEEEEEEEEEEEEEE 3523481721 A tii 4872669431708812177984363 1288376075 E itC 2707031304321475322199191 L ncu .

2237418212819532474542828 2288123251 IA(

M E

T - - r 1

S Y emssy S g ai y/ 00445546768888 97 744787876666775454 rrDSi 12500010200000 00 000000000000000000 T aF C - - - - - - - - - - - - - -

N h el( EEEEEEEEEEEEEE EE EEEEEEEEEEEEEEEEEE A ceta 83784350404945 31 898157519081687520 L stssm 71564281396013 74 421342466784413632 .

O iaaoe 43 2332626111646121 41 O) D R W pt 48752562316271 5 CE 1 2 S P - YA t

- 2 RC 966909098878997676 R A y n) 21567758989090 19 A 1 MD t ec 12500010200101 1 0 000010100000000000

- - - - - - - - - - - - 2 S 1 IE E i mc - - - - - - - - - - - - - -

S RT - vrt/ EEEEEEEEEEEEEE EE EEEEEEEEEEEEEEEEEE E E PC C ieai 63521548881785 98 704104057950190063 f W L E tteC 22167901080100 11 708584845507876558 o S B DP cf ru A EX AAT( 71183713521312 75 354393922216913261 1 T SE S(

E 65 522565654434453232 C y} 56823253445556 O ltc 00000000000000 00 000000000000000000 R aic - - - - - - - - - - - - - -

P i v/ EEEEEEEEEEEEEE EE EEEEEEEEEEEEEEEEEE tii 43967504911305 02 3616292799636011 43 M i tC 38027545290315 82 819584845608593588 O m ncu 22394182121118 25 365393922216124261 R e IA(

F t s =

Y y ) )

T s s r I r emssy V l u g oi y/

74477' 776656785454 I a o rrDSi 00445546767878597 T s b aP C 12500010200000000 00000C000000000000 C o ( h el( - - - - - - - - - - - - - - - - - - - - - - - - - - - -

A p ceta EEEEEEECEEEEEEEEE EEEEEEEEEEEEEEEEEE s m stssm 108817168812036780 i e i aaoe 2 4 7 1 7 1 1 5 4 1 1 6 2 7. H. 9 6 d t D R W pt 58793772331211155 454313122217473262 s

e y t s s t a l y n) 966999998877997666 w as t ec 21557658989090719 000000000000000000 i mc 12500010200101010 - - - - - - - - - - -

f o vrt/ - - - - - - - - - - - - - - - - -

EEEEEEEEEEEEEEEEEE o p i eai EEEEEEEEEEEEEEEEE 15276660227101 4100 s W tt eC 831 461171 76976794 r i f. cf ru o d B AAT( 71115113541312288 677515144411615413 t

c e=

a t) y)

f =eay sr 522555554433553222 ltc 56813253445555365 ncw/ aic 00009000000000000 000000000000000000 or l i v/ - - - - - - - - - - - - - - - - - - - - - - - - - - - -

iuna tii EEEEEEEEEEEEEEEEE EEEEEEEEEEEEEEEEEE t oi g i tC 59150160376680855 2278666023716851 10 as ( ncu .

69851514441191 6413 n e IAj 22317283141111238 isme miit ahta e tt r d M MM M M n y i M M363657799112467 55599000022222333333 oraw 345123458901 M l

coco c 88833333889901 13999991 l11 11111111111 ef el u RRR1111 1 BRRR9999RBbOCUuHHEEELEEEESSS D DF N BBB11111RSSSYYYY2NNMTRhRRTTTTTTTTCCC I

7'sO?; L0c CCc

SWESSAR-P1 TABLE 11.2-25 (CONTD)

B&W C-E W Discharge Discharge Discharge Activity Rate Prom Activity Rate Prom Activity Rate From Initial After Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treatment posal Sys- Activity Treatment posal Sys- Activity Treat 2nent posal Sys-Nuclide (uCi/cc) (uCi/cc) tem (Ci/yr) (uci/ce) (uCi/cc) tem (Ci/vr}, (uCi/cc) (uCi/cc) tem (Ci/yr)

CS138 - - -

2. 20 E-0 5 1.13E-20 7.54E-19 BA137M 2.8E-02 2.8E-06 1.8E-04 1.71E-02 1.71E -0 6 1.13E-04 1.39E-02 0.0 0.0 BA140 1.8E-04 1.7E-0 8 1.1E-06 1.11E-0 4 1.06E-08 6.97E-07 9.18 E-05 8.77E-09 5.84; 07 LA140 1. 9L-0 4 1.8E-08 1.2E-06 1.19 E-0 4 1.16E-0 8 7.63E-07 9.90E-05 7.01E-09 4. 67E-07 CE141 8 .5 E-0 5 8.3E-09 5.6E-07 5.25 E-05 5.16E-09 3.40E-07 4.35E-05 4.27E-09 2.84E-07 CE143 3.9E-06 2.5E-10 1.7E-08 2.74 E-0 6 1.80E-10 1.18E-08 2.34E-06 1.54E-10 1.0 3E-0 8 CE144 5.3E-05 5. 2E -09 3.5E-07 3.2 3 E-05 3. 22E-0 9 2.12E-07 2.67E-05 2.66E-09 1.77E-07 PR143 4. 2E-0 5 4.0E-09 2.7E-07 2.6 0 E-0 5 2.49E-09 1.64E-07 2. 34 E-0 5 2.25E-09 1. 50E-07 PR144 5.3 E-0 5 5.2E-09 3.5E -0 7 3 .23 E-0 5 3.22E-09 2.12 E-0 7 2.674-05 2.992-30 1.99E-28 NP239 2.1E-04 1.6E-0 8 1.1E-06 1.39E-04 1.09E-08 7.16E-07 g CR51 2.2E-03 2 .1E-0 7 1. 4E-0 5 1.36E-03 1. 3 3E-07 8.76E-06 1.13E-03 1.10E-07 7.34E-06 MN54 5.0E-04 4.9E-08 3. 3 E-0 6 3.0 4 E-04 3.30E-08 2.00E-06 2.51E-04 2.50E-08 1.66E-06 FESS 2.6 E-0 3 2.6E-0 7 1.7E-05 1.6 0 E-0 3 1. 60E -07 1.0 5E -0 5 1.32 E-0 3 1.32E-07 8.79E-06 PY59 1.3E-03 1.3E-07 8.7E-06 8.17E-04 8.06E-08 5.31E-06 6. 73E-04 6. 6 4 E -08 4.42E-06 0058 2. 3E-0 2 2. 3E-06 1. 5E-0 4 1. C 1E-0 2 1.3 9 E-0 6 9.18E-05 1.17E-02 1.16E-06 7.70E-05 0060 3.3E-03 3.3E-07 2.2E-0 5 2.02E-03 2.0 2E-07 1.33E-05 1.67E-03 1.67E-07 1.11E-05 TOTAL 5.1E-01 4.5E-05 3.0E-03 3. 3 2E-01 2. 91E -0 5 1.91E-03 1.67E-03 1. 67E -07 1.63E-03 7

(N g

L q

2 of 2 Amendment 19 12/12/75

d

)

- r 95 emssy 17 g oi y/ 839354955577717868633679 5658644343 /

rrDSL C 016000001000010000000000 0000010000 t2 aP - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - n1 h el( EEEEEEEEEEEEEEEEEEEEEEEE EEEEEEEEEE e/

cet a 452630861073966968224417 1C27100831 m2 stssm 3399359556594243848109440 4182032370 d1 iaaoe n D R W pt 7474161561535928242311510 1757782131 e n

A t

011 y n) 627243844466696657522568 4446423232 000 t ec 016000001000000000000000 0000010000 i a r c - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

EEEEEEE7EE EEE W vrt/ EEEEEFEEEEEEEEEEEEEEEEEE 006 ieai 039596747070390693497231 2849550J 01 007 tteC 1514979374392372272659120 1070023065 cf ru 111 AAT( 1617192392858131464412820 2181113251 y) 5682315334656666575225656 4444453232 ltc 0000000000000000000000000 0000000000 aic - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

M iv/ EEEEEEEEEEEEEEEEEEEEEEEEE EEEEEEEEEE E tii 4872669432708812177984363 3523481721 T itC 2707031304321475322199191 1280376075 S ncu . . . . .

2288123251 Y IA( 2237418212819532474542828 S

T )

N r A emssv g oi y/ 83334495657777 86 633676765555664343 l

O rrDSi 01500000100000 00 000000000000000000 O aF C - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

C3 h el( EEEEEEEEEEEEEE EE EEEEEEEEEEEEEEEEEE F ceta 89788052414807 42 063368620345309510 YS st ssm 58586399396227 34 565342467794145642 RA iaaoe AC D R F pt 83752715516472 93 2332626111648121 41 1

6 2

M ID P - RE

- 2 PT t R C y n) 62123284545656 65 522565654434453232 A 1 DE t ec 01500000100000 00 000000000000000000 S 1 EP E i mc - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 2 S SX - vrt/ EEEEEEEESEEEEE EE EEEREEEEEEEEEEEEEE E E SE C ieai 01547169101090 20 056317168256464003 f W L E( tteC 39190199190502 42 853584845607229578 o S B C cf ru .

A OE AAT( 15184128821614 15 355393922216123261 1 T RG PA NK y)

UA 56823253445556 65 522565654434453232 E ltc 00000000000000 00 000000000000000000 ML aic - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

O iv/ EEEECEEEEEEEEE EE EEEEEEEEEEEEEEEEEE R tii 43967504911305 02 361629279963601143 F itC 38027545290315 82 819584845608593588 Y

m e

ncu 22394182121118 IA( 25 365393922216124261 T t I s =

V y ) )

I s s r T r emssy C l u g oi y/

A a oh s

rrDSi aP C 83334495656767476 63366666554;674343 01500000100000000 000000000000000000 o

p

(

h el( - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

ceta EEEEEEEEEEEEEEEEE EEEEEEEEEEEEEEEEEE s m i e st ssm 40741900416324826 163817178813120700 iaaoe . . .

d t D R W pt 94794927531513115 455313122217594272 s

y e

t S s y t a l n) w as t ec 62113283545656365 522555554433553222 i mc 01500000100000000 000000000000000000 f o p

vrt/ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

o ieai EEEEEEEEEEEEEEEEE EEEEEEEEEEEEEEEEEE s W tt ec 40142501 176081884 130766602271 640100 cf ru t

md i &

B AAT( 16116131 841815218 688515144411716413 c e=

a t) f =eaysr y) ltc 56813253445555365 52255S554433553222 ncw/ aic 00000000000000000 00000O000000000000 or l iv/ - - - - - - - - - - - - - - - - -

EEEEEEEEEEEEEEEEE i una tii EEEEEEEEEEEEEEEEEE toig itC 5 9 1 5 0 1 6 0 3 7 6 6. P. 0 8 5 5 227866602371685110 as (

ncu n e IA( 22317283141111238 698515144411916413 i sme miit ahta e tt y

r d M MM M M n i M M363657799112467 oraw coco l

c 34512 458901 M 55599000022222333333

@ ef el D DF N u

88833333889901139999911 1111111111111 RRR11111 BRRR9999RBBOUUUHHEEEEEEEESSS BBB1I111RSSSYYYYZNNMTRkRRTTTTTTTTCCC 3D 7' 7' 'f C C ~L D C

SWESSAR-P1 TABLE 11.2-26 (Coffr) new C-E w Discharge Discharge Discharge Activity Rate From Activit y Rate From Activity Rate From Initial After Waste Dis- Initial After Wasta Dis- Initial After Waste Dis-Activity Treatme nt losal Sys- Activity Treatment posal Sys- Activity Treatment posal Sys-Nuclide fuci/cc) (ucifccl tem (Ci/yr) (uci/cc) fuci/cc) tem (Ci/yr) (uci/cc) (uci/ce) tem (Ci/yr)

CS138 - - -

2. 20 E-0 5 4.99E-11 3.332-12 RA137M 2.8E-02 2.8E-02 1.8E-03 1.71 E-0 2 1.71E-02 1.13E-0 3 1. 39 E -0 2 6.12E-73 4.08E-74 BA140 1.8 E-0 4 1.7E-04 1.2E-05 1.11E-04 1.08E-04 7.13-06 9.19 E-0 5 8 . 9 7E-05 5. 3 8 E-06 LA140 1.9E-04 1.9E-04 1. 2 E-0 5 1.19 E-0 4 1.18E-04 7.74E-06 9.90E-05 8.33E-05 5.55E-06 CE141 8 .5 E-0 5 8.4E-05 5.6E-06 5.25E-05 5.21E-05 3.43E-06 4. 3 5E-0 5 4.31E-05 2.87E-06 CE143 3.9E-06 3.1E-06 2.1E-07 2.74E-06 2. 22 E-0 6 1.46E-07 2. 3 4 E-0 6 1.90E-06 1.27E-07 CE144 5.3E-05 5. 3E -O S 3.5E-06 3.23E-05 3.23E-05 2.12E-06 2.67E-05 2. 6 7E-C 3 1.78E-06 Pk143 4. 2 E-0 5 4.1E-05 2. 7E-0 6 2. 6 0 E-0 5 2. 5 5E-05 1.68E-06 2. 34 E-0 5 2.30E-05 1.53E-06 PR144 5.3E-05 5.3E-05 3.5E-06 3 .2 3 E-05 3.23E-05 2.12E-06 2 . 67 E-0 5 8.93E-17 5.95E-16 NP239 2.1E-04 1.8E-04 1.2E-05 1.39E-04 1.23E-04 8 . 0 9 E-0 6 U CR51 2.2F-03 2.2E-03 1.4E-04 1.36E-03 1. 35E-0 3 8.85E-05 1.13E-03 1.12E-03 7.43E-05 MN54 5.0E-04 4.9E-04 3. 3 E-0 5 3. 0 4 E-0 4 3. 04 E-0 4 2.00E-05 2.51E-04 2.50E-04 1.67E-05 FESS 2. 5 E-0 3 2.6 E-0 3 1.7E-04 1. 60E-0 3 1. 60 E-03 1.05E-04 1. 3 2 E-0 3 1.32E-03 8.80E-05 FE59 1.3E-03 1. 3E -03 8.7E-05 8.17E-04 8.12E-04 5.34E-05 6. 73 E-04 6 . 6 8 E -04 4 .4 5 E-05 CO58 2.3E-02 2.lE-02 1.5E-03 1.41E-02 1.4 0 E-0 2 9.22E-04 1.17E-02 1.16E-02 7.74E-04 0060 3.3 E-0 3 3.3E-03 2.2E-04 2.02E-03 2.02E-03 1.33E-04 1. 67E-0 3 1.67E-03 1.11E-04 TOTAL 5.1E-01 4.8E-01 3.2E-02 3.32E-C1 3.09 E-01 2. 03E-0 2 2.79E-01 2.11E-01 1.4E-02 O

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( c 12 1112121111211111112 i mc -- - - - - - - - - - - - - - - - - - - - - -

EEEEEEEEEE E

EEE w vrt/ EE EEEEEEEEEEE2EEEEEEE 060430647241934115S 1442437748 7 000 ieai 64 000 tteC 41057308025368804244520 271961533508 cf ru 653232384504 123 AAT( 21081676261233419719130

) y) 90288708912121112872211 100909999981 E ltc 01100010011111111001111 111010000001 S aic - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

A iv/ EEEEEEEEEEEEEEEEEEEEEEE EEEEEEEEEEEE C tii 165382391346983b9835583 410196683849 itC 00512233235849915845581 252980235520 D ncu . .

623151484525 E IA( 12297155261945119829151 T

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P r X emssY g ai y/ 437010911343434440044444332223111113 E

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S D R W pt 311826861412214865661614482125263433 G

7 N 1 2 I t P - L y n) 659232133565656662266666554445333335 ec 125111213111111111 111111111111111111 R

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S 1 S C ieai 752434290112480716492720867381987511 f o

S tteC 002464301108618128110001050357348642 E E T cf ru 311725761411213764661614472124252333 1 W L N AAT(

S B A A L T P y) 002887089121211228722112100909999991 E ltc 111000100111111110011111111010000001 N aic I iv/ EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE B tii 209916150614318319282074061009689516 R itC 942920988106084239020641191112849693 U m ncu T e IA( 923771542417361765261614412241252323 t

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V p cet a EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE I s m st ssm 672990427523663111832225566093855877 T

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W vrt/ EEEEEEEEEEEEE E ieai 2129942689713 9 tteC 7471688110516 7 cf ru 2 AAT( 3136941363134 y; 1122111010090 7 lte 111111 1111101 0 aic - - - - - - - - - - - - - -

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- r emssy g ai y/ 3344443232212 9 rrDSi 1111111111111 0 aF C - - - - - - - - - - - - - -

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i eai EEEEEEEEEEEEE E W tteC 4771411506166 3 E cf ru .

1 B AAT( 1723439131111 y) ltc 011 11 19909989 6 aic 1111110010000 0 i v/ - - - - - - - - - - - - -

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n A

t 872211 100909999981 0 5 y n) 9028870891212111 01100010011111111001111 111010000001 0 0 t ec - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

E E ivrt/mc EEEEEEEEEEEEEEEEEEEEEEE EEEEEEEE%EEE W 16538239134698309835583 41019638?849 0 0 ieai 252980135520 003 tteC 00512233235849915845581 cf ru 623151484525 101 AAT( 12297155261945119829151 y) 90288708912121112872211 100909999981

) ltc 01100010011111111001111 11 1010000001 d aic - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

iv/ EEEEEEEEEEEEEEEEEEEEEEE EEEEEEEEEEEE E tii 16538239134698309835583 4101 96683849 C itC 00512233235849915845581 252980235520 ncu .

12297155261945119829151 623151484525 IA(

w u 1 E r P emssy X g ai y/ 779555756808989995590899887 o77666658 E rrDSi 000000000010000000001000000O00000000

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ceta el( EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE 270805756211719171155141922297965713 S

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U d R W pt 4 1133522124313733293437219111 612111 1 8 S 1 2 P - G

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----- 2 S 1 L ivrt/mc EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE S I -

20991615061 4318319282074061009689516 f E E U C ieai o W L B tt ec 942920988106084239020641 1911 12849693 S B cf ru 1 A E AATf 923771542417361765261 614412241252323 T N I

B R y) 00288708912121 1228722112100909999981 ltc 11100010011

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n) a l w as t ec 901787877010100117711121009900888880 ivrt/

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c e=

a t) f = sr yi eay ltc 901787877010100117711121009900888880 ncw/ aic 011

- - - 00000011111111

- - - - - - - - - - - -0011111110011000001 or iana l i v/

tii EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE t oi g i tC 945845761 11952137457123114417401 4605 as ( ncu 1 9727311131 4131644341373371197331111 n e IA(

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- r emssy g ai y/ 8999989788867 4 rrDSi 0000000000000 0 aP C - - - - - - - - - - - - - -

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i e ai EEEEEEEEEEEEE E W ttec 48216126261 66 9 6 cf ru 1 B AAT( 174342113111 1 y) ltc 01 11 1 19909989 6 aic 1 11111001 0000 0 iv/ - - - - - - - - - - - - -

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ceta 25 5256579329999131609 10949230687 m2 stssm 67048283005230791278570681653000790 d1 iaaoe n DRWpt 55011154151314979794120227121157140 e m

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4166 y n) 55 8290121232031189228 21106160899 0000 t ec 12 0102131111211100111 11110121000 i mc - -

EEEE W vrt/ EE EEEEEEEEEEEEEEEEEEE EEEEEEEEEEE 0069 ieai 43 83802049394707869S7 21869850676 0073 tteC 46017885662801423042210920489550640 cf ru 1211 AAT( 88022186172426111117240341231171270

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C iv/ EEEEEEEEEEEEEFEEEEEEEEEEEEEEEEEEEEE tii 7624336573910501 9370595632050166967 D itC 45831661772065923344242927552790748 E ncu .

T IA( 31121365172229511117272344223781276 C

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( g oi y/ 01646567878989978448888877667865555 rrDSi 12500010200000000000000000000000000 E aF C - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

T h el( EEEEEEEEEEEEEEEEEE2EEEEEEEEEEEEEEEE S ceta 1620110321 4016805660979666048794373 A stssm 13202761280535514002909256451997573 W iaaoe D R W pt 18927196162523119f 17171444212369266 9 E 1

P 2

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R A n) 44989991202323311881212211001298989 A 1 R t c 12500011311111111001111111111100000 S

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mc 125000113111111 1 1001111111111100000 f oW p

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EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE iuna tii t oi g itC 42110247110840949860797234657085832 as n e

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SWESSAR-P1 TABLE 11.2-29 (Cottr) ncW C-E w Discharge Discharge Discharge Activity Rate Prom Activity Rate Prom Activity Rate Prom Initial After Waste Dis- Initidl After Waste Dis- 2nitial After Waste Dis-Activity Trea t2ne nt posal Sys- Activity Treatment posal Sys- Activity Treatment posal Sys-Nuclide fuci/cc) _[uci/cc) tes (Ci/yr) (uci/cc) (uci/ce) tem (Ci/yr) (uci/cc) (uCi/cc) tem (Ci/yr)

RA140 6.3 E-07 6.0E-11 3.2E-07 3.79 E-0 7 3.62E-11 2.38E-07 2.52E-07 2.41E-11 1.60E-07 LA140 7.0E-07 6.7E-11 3.$E-07 4 . 4 7 E -07 4.25E-11 2.80E-07 3.00E-07 2.12E-Il 1.C2E-07 CE141 4.7E-07 4.6E-11 2. 4 E -07 1.59E-07 1.56E-11 1.03E-07 1.06E-07 1.04E-11 6.94E-08 CE143 2.3E-08 1.5E-12 7.8E-09 8.01E-0 9 5.27E-13 3.47E-09 5.63E-09 3.70E-13 2.47E-09 CE144 2.5E -07 2.5E-11 1.3E-07 1.2 0 E-07 1.20E-11 7.88E-03 8.90E-08 8.88E-12 5.92E-08 PR143 1.9E-07 1.9E-11 9.8E-08 7.81E-OB 7.48E-12 4.92E-08 5.59E-08 5.36E-12 3.57E-08 PR144 2.5E-07 2.5E-11 1.3E-O' 1.21E-07 1.20E-11 7.88E-08 8.93E-08 1.00E-32 6. 6 7E-29 NP239 1.1E-06 8.4E-11 4.4E-07 4.67E-08 3.65E-12 2. 4 0E-0 8 3.17 E-0 8 2.48E-12 1. 6 5E-08 II CR51 9.0E-06 8.8E-10 4.6E-Oo 4.23E-06 4.14E-10 2.73E-06 3. 0 5 E-0 6 2.99E-10 1.99E-06 KN54 2.5E-06 2.5E-10 1.3E-06 1.20E-06 1.20E-10 7.91E-07 8 . 9 3 E-07 8.91E-11 5 .9 4 E -07 YE55 1. 3 E-0 5 1. 3 E -09 6.7E-06 5.19E-06 5.18E-10 3.41E-0 6 3.65E-06 3.65E-10 2.43E-06 FES9 7.2E-06 7.1E-10 3.7E-0 6 2.56 E-06 2.53E-10 1.66E-06 1.89E-06 1. 8 7E-10 1. 2 4 E -0 6 C058 1.1E-04 1.1E -0 8 5. 8 E-0 5 4 . 6 3 E-0 5 4 . 5 9 E -0 9 3.02E-05 3.26E-05 3.21E-09 2.15E-05 CO60 1. 3E-0 5 1.3E-09 6.7E-06 6.84E-06 6.84E-10 4.50E-06 4.56E-06 4.56E-10 3.04E-06 TOTAL 2.7E-03 2.4E-07 1. 3E-0 3 1.31E-03 1.14 E-07 7.48E-04 9.08E-04 6.2CI-09 4.17E-04 T

(Tw OO t-(

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LI 2 of 2 Amendment 19 12/12/75

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O SWESSAR-P1 TABLE 11.2-30 (Cola) ncW ~~-

C-E W Discharge Discharge Discharge Activity Eate From Activity Rate Pram Activity Rate Prom Initial After Waste Dis- Initial After Waste Dis- Initial After Waste Dis-Activity Treat:ne nt posal Sys- Activity Trratment posal Sys- Activity Treatment posal Sys-buclide (uci/cc) (uci/cc) tem (Ci/yr) (uci/cc) (uci/cc) tem (Ci/yr) (uCi/cc) uCi/cc) tem (Ci/yr)

LA140 1.5E-09 1.7E-09 1.3E-06 1.02E-09 1.15E-09 8.58E-07 8.91E-10 6.31E-10 4.78E-07 CE141 7.6E-10 7.5E-10 5.7E-07 4.69E-10 4.61E-10 3.45E-07 3.95E-10 3.88E-10 2.94E-07 CE147 3.9E-10 2.5E-10 1.9E-07 2.73E-10 1.80E-10 1.34E-07 2.39E-10 1. 5 7E-10 1.19E-07 CE144 3.6E-10 3.6E-10 2.7E-07 2.21E-10 2.21E-10 1.65E-07 1.86E-10 1.86E-10 1.41"-07 PR143 5.4E-10 5.1E-10 L.9E-07 3.35E-10 3.21E-10 2.41E-07 2.84E-10 2.72E-10 2.06E-07 Pk144 2.4E-10 3.6E-10 2.7E-07 2.38E-10 2.21E-10 1.65E-07 2.39E-10 2.68E-31 2.03E-28 NP239 1.2E-08 9.4E-09 7.2E-06 8 .12 E-0 9 6.35E-09 4.76E-06 7.00E-09 5.48E-09 4.15E-06 CR51 2.1E-08 2.0E-08 1.5E-05 1. 27E -08 1. 25 E -0 8 9.35E-06 1. 08 E-08 1.05E-08 7.98E-06 MN54 3.4E-09 3.4E-09 2 . b E-0 6 2. 0 7E -0 9 2.07E-09 1.55E-06 1.74E-09 1.74E-09 1.32E-06 FESS 1.7E-08 1. 7E-0 8 1.3E-05 1. 07 E-0 8 1.07E -0 8 8.04F-06 8.93E-09 S . 9 7E-09 6.19E-06 FE59 1.1 E -0 8 f.1E-08 8 .1E -0 6 6.73 E-0 9 6.65E-09 4.98F-06 5.64E-09 5.57E-09 4.22E-06 C058 1.7E-07 1.7E-07 1.3E-04 1.07E-07 1.06E-07 7.9tE-05 9.04E-08 8 .9 7E-08 6.79E-05 CO60 2.2E-08 2. 2E-O b 1.7E-05 1.3 4 E-0 8 1.34E-08 1.00E-05 1.13E-08 1.13E-08 8.54E-06 TOTAL 2.0E-05 1.3E-05 1.0E-02 1. 4 9 E-0 5 9. 0 4 E-0 6 6.778-03 1.36E-05 5.79E-06 4.38E-03

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2 of 2 Amendment 19 12/12/75

SWESSAR-P1 TABLE 11.2-31 TOTAL ACTIVITY RELEASED FROM RADIGAL' RIVE LIQUID WASTE SYSTEM WITH STEAM GEUERATOR LEAKAGE (EXPECTED CASE)

Calculated total discharge flow rate (gpm) BSW 4.09 CE 4.46 hI W 5.05

'U' C-E W

\ctual Act ual Actual Actual scharge Actual Discharge Actual Dis charge Activity Rate Activity Rate Activity Rate Nuclide fuC1/cc) (Ci/vr) JuCi/ce) (Ci/yr) (uci/cc) (Ci/yr)

BR83 2.4E-10 2.0E-06 1.90E-10 1.67E-06 4.09E-10 4.11E-06 UR84 7.0E-11 5.7E-07 2.71E-11 2.37E-07 5.27E-11 5. 30 E-07 BR85 4.7E-12 3.8E-08 3.33E-13 2. 9 2E -0 9 5.95E-13 5. 9 8 E-0 9 I131 1. 8E-0 6 1.5 E-0 2 1.07E-0 6 9 . 4 0 E-0 3 1.03E-06 1.03E-02 I132 9.4E-08 7.7E-04 6. 76 E-0 8 5. 9 3E-0 4 3.85E-08 3. 87E -0 4 I133 3.0E-07 2 .4 E-0 3 3 .12 E-0 7 2.74E-03 3.86E-07 3. 8 7E-0 3 1134 1.4E-09 1. 2 E-0 5 4.k2E-10 3.88E-06 1. 2 8 E-0 9 1. 2 9 E-0 5 I135 3.7E-08 3.0E-04 4.00c-08 3. 51E-0 4 5.93E-08 5.96E-04 RB88 6.9E-09 5.6E-05 7.46E-10 6.54E-06 7.54E-09 7.58E-05 SR09 5.2E-0* 4.3E-05 2.91E-0 9 2. 55E-05 2.47E-09 2.48E-05 SR30 1.8E-1) 1.5E-06 9.86E-11 8. 6 5E-0 7 8.20E-11 9 .2 5 E-0 7 SR91 2.0E-10 1.6E-06 2.33E-10 2.0 4E-0 6 3.15E-10 3.16 E-0 6 Y90 2.0E-t0i 1.6E-06 1.13E-10 9. 3 8E -07 8.98E-11 9.023-07 Y91M 1.3E-10 1.1E-06 1.51E-10 1.3 3Z-0 6 8.19E-11 8.23E-07 Y91 3.1E-08 2. 5E -0 4 3.31E-11 3.33E-07 Y93 4.4E-11 3. 6 E-0 7 4.98E-11 4 .37E-07 6.58E-11 6.61E-07 ZR95 9.4E-10 7.7E-06 S.18E-10 4.54E-06 4.36E-10 4.38E-06 tg NB95M '5.33E-12 5.15E-08 NB95 7.01-10 5.7 E-0 6 3.88E-10 3.4 0E-0 6 4.16E-10 4 .18 E-06 MO99 1. 2E-0 6 1.0E-02 9.00E-07 7.89E-03 9.87E-07 9. 92E-0 3 TC99M 1.2M-06 9.6E-03 8 .7 2E-0 7 7.65E-03 5.60E-07 5. 6 3E -0 3 RU103 6.52-10 5.3E-06 3.56E-10 3.13E-06 3.03E-10 3.05E-06 KU100 1.8E-10 1.4E-06 9.62E-11 8. 4 4 E-07 8.02E-11 8 . 0 6E-07 RH103M 6.3E-10 5.1E-06 3.53E-10 3.10E-0 6 6.49E-11 6. 52E-07 RH106 1.8E-10 1. 4 E -0 6 9.70E-11 8.51E-07 1.46E-11 1. 4 7E-07 TE125M 4.5E-10 3 . 6 E -06 2.44E-10 2 .14 E-0 6 1.83E-11 1. 8 4E-07 TE127M 4 .7E-09 3.8E-05 2. 54 E-0 9 2. 2 3 E-0 5 2.12E-09 2.13E-05

' TE127 4.8E-09 3.9E-05 2.73E-0 9 2. 4 0 E -05 1.4 3E-0 9 1.44E-05 TE129M 1.9E-08 1.6E-04 1. 07 E-08 9. 4 0E-0 5 9.19E-09 9.24E-05 TE129 1.2E-08 1. 0E -0 4 6. 99 E-0 9 6.13E -0 5 2.02E-09 2.03E-05 10 TE131M 1.3E-09 1.1E-05 2.81E-09 2. 4 7E-0 5 3.33E-09 3.34E-05 TE131 2.8E-10 2.3E-06 5.83E-10 5.12E-0 6 3.96E-10 3. 9 8 E-0 6 TE132 3. 7E-0 8 7.1E-04 6 .0 0 E-0 8 5. 2 7E-0 4 6.43E-08 6.47E-04 g CS134 4.5E-07 3.7E-03 2. 51E -07 2.20E-03 1.9 0 E-0 7 1.91E-0 3 CS136 1.2E-07 1.0E-03 7. 3 8 E -0 8 6 .4 8E-0 4 5.80E-08 5.R3E-04

'S CS137 3.2E-07 2.6E-03 1.82E-07 1. 60 E -0 3 1. 3 8 E-0 7 1.3 8 E-0 3 v

1 of 2 Amendment 19 12/12/75

SWESSAR-P1 TABLE 11.2-31 (Com')

B 5W C-E W Actual Actual Actual Actual Discharge Actual Discharge Actual Discharge Activity Rate Activity Rate Activity Rate Nuclide (uCi/cc) (Ci/yr) (uCi/cc) (Ci/yr) (uCi/cc) (Ci/yr)

CS138 - -

1.59E-10 1. 6 0 E-0 6 BA137M 3.OE-07 2. 5 E-0 3 1.72E-07 1.51S-03 2.46E-08 2. 4 7E -0 4 RA140 2.0E-09 1.7E-05 1.18E-09 1.04E-05 1.07E-09 1.07E-05 LA140 2.2E-09 1.8E-05 1. 2 2E -0 9 1. 0 7E-0 5 9.28E-10 9.32E-06 CE141 9.6E-10 7.8E-06 5.29E-10 4. 6 4 E-0 6 4.53E-10 4.55E-06 CS143 5.4E-11 4.4E-07 4.28E-11 4. 2 3E-07 5.70E-11 5.73E-07 CE144 5.8E-10 4.7E-06 3.18E-10 2.7 9E-0 6 2.65E-10 2. 66E-0 6 PR143 4.8E-10 3.9E-06 2.75E-10 2.41E-06 2.6SE-10 2.66E-06 PR144 5.8E-10 4 .7E-0 6 3.21E-10 2.8 2E-0 6 4.86E-11 4 . 8 8 E-07 NP239 2. 8E-0 9 2.3E-05 2.10 E-0 9 1.84E-05 5.66E-10 5. 6 9 E-0 6 CR51 1.0E-07 8.1E-04 8.37E-0 8 7. 3 5E-0 4 3.65E-08 3.67E-04 15 MN54 3.5E-08 2.8E-04 3. 04 E-0 8 2. 6 7E-0 4 4.99E-08 5.01E-04 MN56 5.40E-12 5. 4 2 E-0 8 FESS 1.9E-07 1.6E-03 1.6 8 E-0 7 1. 4 7E-0 3 1.57E-08 1.5 8 E-0 4 FE5') 6. 9E-0 8 5.7E-04 5.9 3 E-0 8 5. 20E-0 4 4.58E-08 4 . 6 0E -0 4 0058 1. 3 E-0 6 1.1E-02 1,16E-0 6 1. 01E-0 2 1.26E-06 1. 26 E-0 2 CO60 2.4E-07 2.0E-03 2.14 E-07 1. 8 8 E-0 3 6.99E-08 7. 0 3 E-0 4 11 3 1.5E-01 1.2E 03 4.69E-02 5.11E 02 1. 69 E-01 1.70E 03 TOTAL 1.5E-01 1.2E 03 4 . 6 9E-02 4.11E 02 1.69E-01 1.70E 03 TOTAL 73 8.0E-06 6. 5 E-0 2 5.7 5E-6 5.04E-02 5.04E-06 5.07E-02 (NON-TRITIUM)

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• 2 of 2 Amendment 19 12/12/75

SWESSAR-P1 TABLE 11.2-32 ACTIVITY AT DISCHARGE POIffI' (EAPECTED CASE) is Discharge canal flow rate (gpm) = B&W 7.91E 03 C-E , W-41, W-3S 3.60E 03 Tritium discharge rate (curies / year) BSW 1.14E 03 CE 4.11E 02 W 1.12E 03 B CW C-E W W-3S Act ual Actual Actual Actual Activity Activity Activity Activity Nuclide (uci/cc) (uci/cc) (uci/cc) (uci/qm)

ER83 1.3E-13 2.33E-13 5.71E-13 4.20E-12 BR84 3.6E-14 3.31E-14 7.39E-14 2.06E-12 BR85 2.4E-15 4.07E-16 8.34E-16 2.31E-13 I131 9.4E-10 1.31E-09 1. 4 4E-09 1.74 E-0 9 1132 4.9E-11 8.27E-11 5.40E-11 1.80E-10 I133 1.5E-10 3.82E-10 5.41E-10 7.27E-10 1134 7.4E-13 5.41E-13 1.80E-12 3.77E-11 1135 1.9E-11 4.90E-11 8.31E-11 2.10E-10 RB88 3.6E-12 9.13E-13 1.06E-11 1.56E-10 SR89 2.7E-12 3.56E-12 3.46E-12 4.28E-12 SR90 9.4E-14 1.21E-13 1.15E-13 1.43E-13 SR91 1.0E-13 2.85E-13 4.41E-13 8.30E-13 Y90 1.0E-13 1.38E-13 1.26E-13 1.69E-13 Y91m 6. 7E-14 1.85E-13 1.15E-13 5.08E-13 Y91 1.6E-11 -

4.64E-14 -

Y93 2.3E-14 6.10E-14 9.23E-14 1.70E-13 IR95 4.9E-13 6.34E-13 6.11E-13 7.59E-13 ,,

NB95m - -

7.47E-15 -

Nb95 3.6E-13 4.75E-13 5.83E-13 5.74E-13 M099 6. 4 E-10 1.10E-09 1.38E-09 1. 6 6E-0 9 TC99m 6.1E-10 1.07E-09 7.85E-10 1. 57E-0 9 RU103 3.3E-13 4.3bE-13 4.25E-13 5.27E-13 EU106 9. 2E-14 1.18E-13 1.12E-13 1.40E-13 RE103m 3.3E-13 4.32E-13 9.09E-14 5.23E-13 RH106 9.1E-14 1.19E-13 2.05E-14 1.41E-13 TE125m 2.3E-13 2.99E-13 2.56E-14 3.60E-13 TE127m 2.4E-12 3.11E-12 2.9 7E-12 3.71E-12 TE127 2.5E-12 3.34E-12 2.01E-12 4.42E-12

- TE129m 1.0E-11 1.31E-11 1.29E-11 1.60E-11

, TE129 6. 4 F -12 8.55E-12 2.84E-12 1.10E-11 q TE131m 6.8E-13 3.44E-12 4.66E-12 5.94E-12

TE131 1.4E-13 7.14E-13 5.55E-13 1.68E-12 TE132 4.5E-11 7.35E-11 9.02E-11 1.08E-10 g CS134 2.3E-10 3.07E-10 2.66E-10 3.56E-10 L- CS136 6.5E-11 9.04E-11 8.14E-11 1.12E-10

, CS137 1.7E-10 2.23E-10 1.93E-10 2.58E-10 cs' 1 of 2 Amendment 19 12/12/75

SWESSAR-P1 TABLE 11.2-32 (Corrr)

B&W C-E W W-3S Actual Actual Actual Actual Activity Activity Activity Activity Nuclide (uCi /cc) (uci/cc) (uCi/cc) (uCi/qm)

CS138 - -

2.23E-13 -

BA137m 1. 6E -10 2.10E-10 3.45E-11 2.43E-10 BA140 1.1E-12 1. 4 5E-12 1.50E-12 1.84E-12 LA140 1.1E-12 1.50E-12 1.30E-12 1.83E-12 CE141 5.9E-13 6.47E-13 6.35E-13 7.87E-13 CE143 2.8E-14 5.90E-14 8.00E-14 9.97E-14 CE144 3.OE-13 3.89E-13 3.71E-13 4.61E-13 PR143 2.5E-13 3.37E-13 3.71E-13 4.26E-13 PR144 3.0E-13 3.93E-13 6.81E-14 4.65E-13 NP239 1.5E-12 2.57E-12 7.94E-13 4.00E-12 CRS1 5.2E ** 1.02E-10 *

.12E-11 1.07E-10 MN54 1.56-11 3.73E-11 6.24E-11 3.77E-11 MN56 - -

2.20E-11 -

FESS 9.8E-11 2.06E-10 7.57E-15 2.07E-10 FES9 3.6E-11 7.26E-11 6.42E-11 7.45E-11 CO58 6.9E-10 1.41E-09 1.76E-09 1. 4 5E-0 9 C060 1.2E-10 2.62F-10 9.81E-11 2.63E-10 H3 7.7E-0 5 5.73E-05 2. 37E-04 2.07E-04 TOTAL 7. 7E -0 5 5.73E-05 2 .37E-0 4 2.07E-04 T

CD c0

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2 of 2 Amendment 19 12/12/75

SWFSSAR-P1 TABLE 11.2-6 ACTIVITY FROM DECONTAMINATION DRAINS (DESIGN CASE)

Decontamination factor of waste disposal system for this source = 1.00E 04 Decay time in waste disposal system (hours) = 2.00E 01 Flow rate (gal /yr) 1.64E 04 Discharge Rate Initial Activity After Frtrn Waste Activity Treatment Disposal System Nuclide (uCi/cm) (uCi/qm) (Ci/yr)

BR83 1.02E-06 3.16E-13 1.94E-11 BR84 1.02E-07 4.45E-23 2.73E-21 BR85 1.32E-09 4.91E-57 3.01E-55 1131 6.66E-03 6.20E-07 3.80E-05 I132 1. 94 E-0 4 1.56E-08 9.56E-07 I133 4. 93E-0 4 2.53E-08 1.55E-06 I134 2.37E-06 2.93E-17 1.80E-15 1135 7.46E-05 9.37E-10 5.74E-08 RB88 4.67E-06 1.83E-30 1.12E-28 SR89 7.10E-05 7.02E-09 4 .30E-0 7 H SR90 5.29E-06 5.29E-10 3.24E-08 SR91 9. 99E-0 8 2.38E-12 1.46E-10 Y90 5.32E-06 5.31E-10 3.26E-08 Y91M 4.52E-08 1.54E-12 9.44E-11 Y93 3.21E-08 8.24E-13 5.05E-11 ZR95 1.32E-05 1.31E-09 8.02E-08 NB95 1.55E-05 1.52E-09 9.34E-08 MO99 1.81E-03 1.47E-07 9.01E-06 TC99M 1. 69 E-03 1.42E-07 8.68E-06 RU103 4.95E-06 4.88E-10 2.99E-08 RU106 8.87E-07 8.86E-11 5.43E-09 RH103M 4.95E-06 4.79E-10 2.93E-08 RH106 8.87E-07 8.86E-11 5.43E-09 TE125M 1.56E-06 1.54E-10 9.47E-09 TE127M 4.56E-05 4.54E-09 2.78E-07 TE127 4.57E-09 4.52E-09 2.77E-07 TE129M 5.10E-04 5.01E-08 3.07E-06 Tr:129 5.11E-04 3.21E-08 1.97E-06 TE131M 4.38E-06 2.76E-10 1.69E-08 TE131 9.01E-07 5.04E-11 3.09E-09 TE132 1.81E-04 1.51E-08 9.28E-07 CS134 9.49E-03 9.48E-07 5.81E-05 CS136 9.71E-04 9.31E-08 5.71E-06 CS137 4.91E-02 4.91E-06 3.01E-04 BA137M 4.51E-02 4.59E-06 2.81E-04 BA140 2.21E-05 2.11E-09 1.29E-07 LA140 2.44E-05 2.36E-09 1.45E-07 CE141 8.83E-06 8.673-10 5.32E-08 W-3S 1 of 2 Amendment 17 9/30/75

~

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[>/r,GO J

SWESSAR-P1 TABLE 11.2-6 (CONT)

Discharge Rate Initial Activity After Frcun Waste Activity Treatment Disposal System Nuclide (uCi/qm) (uCi/qm) (Ci/yr)

CE143 1.10E-07 7.23E-12 4.43E-10 CE144 1.30E-05 1.30E-09 7.95E-08 PR143 3.75E-06 3.59E-10 2.20E-08 PR144 1.30E-05 1. 3 0E.-09 7.95E-08 NP239 1 66E-06 1.30E-10 7.96E-09 CRS1 1.24E-03 1.21E-07 7.44E-06 MN54 7.92E-04 7.91E-08 4.85E-06 MN56 n

4.24E-07 1.98E-13 1.21E-11 FESS 4.55E-03 4.55E-07 2.79E-05 FE59 1.09E-03 1.08E-07 6.60E-06 CO58 2.47E-02 2.45E-06 1.50E-04 CO60 5.84E-03 5.84E-07 3.58E-05

'IOTAL 1.55E-01 1.54E-05 9.45E-04 7

[3hb W-3S 2 of 2 ,

Amendment 17 9/30/75

SWESSAR-P1 TABLE 11.2-7 ACTIVITY FRQ4 REACTOR PLANT SAMPLING SINKS (DESIGN CASE)

Decontamination actor of waste disposal system for this source 1.00E 04 Decay time in waste disposal system (hours) = 2.00E 01 Flow rate (gal /yr) =

3.00E 03 Discharge Activity Rate From Initial After Waste Dis-Activity Treatment posal Sys-Nuclide (uCi/qn) (uCi/gm) tem (Ci/yr_)

BR83 8.71E-02 2.70E-08 3.03E-07 BR84 4.0OE-02 1.75E-17 1.96E-16 BR85 5.49E-03 2.04E-50 2.29E-4 9 1131 2.63E 00 2.45E-04 2.75E-0 3 I132 9.09E-01 2.34E-05 2.63E-04 1133 4.11E 00 2.11E-04 2.37E-03 1134 5.63E-01 6.97E-12 7.81E-11 1135 2.19E 00 2.75E-05 3.08E-04 RB88 3.30E 00 1.29E-24 1.45E-23 SR89 4.33E-03 SR90 4.28E-07 4.80E-06 1.92E-04 1.92E-08 2.15E-07 SR91 1.96E-03 Y90 4.67E-08 5.24E-07 2.32E-04 2.24E-08 2.51E-07 Y91M 1.18E-03 Y93 3.02E-08 3.39E-07 17 5.95E-04 1.53E-08 1.71E-07 ZR95 7.14E-6t!

NB95 7.08E-08 7.94E-07

7. 4 3E-04 7.31E-08 8.20E-07 M099 3.35E 30 TC99M 2.72E-04 3.05E-03 1.91E 00 2.50E-04 2.80E-03 RU103 3.44E-04 3.39E-08 RU106

3. 80E-07 3.46E-05 3.45E-09 3.87E-08 RH103M 3.44E-04 3.33E-08 RH106 3.73E-07 3.46E-05 3.45E-09 3.87E-0 8 TE 125M 8.92E-05 8.83E-09 9.90E-08 TE127M 2.12E-03 2.11E-07 2.36E-06 TE127 1.05E-03 1.86E-07 2.09E-06 TE129M 3.92E-02 3.85E-06 4.32E-05 TE129 2.18E-02 2.47E-06 TE131M 2.77E-05 2.33E-02 1.47E-06 1.65E-05 TE131 1.09E-02 2.68E-07 TE132 3.00E-06 2.70E-01 2.26E-05 2.53E-0 4 CS134 3.56E-01 3.56E-05 CS136 3.99E-04 1.78E-01 1.71E-05 1.91E-04 CS137 1.78E 00 1.78E-04 BA137M 2.00E-03 1.66E 00 1.66E-04 1.87E-0 3 BA140 4.41E-03 4.22E-07 LA A 0 4.73E-06 1.53E-03 2.34E-07 2.62E-06 W-3S 1 of 2 'enendment 17 9/30/75

-3

SWESSAR-P1 TABLE 11.2-7 (CONT)

Discharge Activity Rate From Initial After Waste Dis-Activity Treatment posal Sys-Nuclide -(uCi/gm) (uCi/en) tem (Ci/yr)

CE141 7.0 0E-04 6.88E-08 7.71E-07 CE143 5.17E-04 3.40E-09 3.81E-07 CE144 5.20E-04 5.19E-08 5.82E-07 PR143 6.78E-04 6.5GE-08 7.29E-0 7 PR144 5.20E-04 5.19E-08 5.82E-07 NP239 3.87E-03 3.03E-07 3.39E-06 CR51 6.10E-03 5.97E-07 6.70E-06 MN54 9. 95E-04 9.93E-08 1.11E-06 g MN56 3.00E-02 1.40E-08 1.57E-07 FESS 5.13E-03 S.13E-07 5.75E-06 FE59 3.21E-03 3.17E-07 3.55E-0 6 0058 5.13E-02 5.09E-06 5.71E-0 5 CO60 6.4 2E-03 6.42E-07 7.20E -0 6 TOTAL 2.36E 01 1.47E-03 1.64E-02 i

W-3S 2 of 2 .c Amendment 17 ifv

. 9/30/75

SWESSAR-P1 TABLE 11.2-8 ACTIVITY FROM BORON RECOVERY LETDOWN (DESIGN CASE)

Decontamination Factor of Waste Disposal System for this Source = 1.00E 00 Decay Time in Waste Disposal System 0 Hours) = 0.0 Flow Rate (gal /yr) = 1.25E 05 Discharge Rate Initial Activity After From Waste Activity Treatment Disposal System Nuclide (uCi/dm) (uCi/dm) (Ci/yr)

BR83 3.59E-08 3.59E-03 1.68E-05 BR84 3.64E-09 3.64E-09 1.70 E-0 6 BR85 4.71E-11 4.71E-11 2.20E-08 1131 2.27E-05 2.27E-05 1. 06E-0 2 1132 2.20E-06 2.20E-06 1.03E-03 I133 1.38E-05 1.38E-05 6. 4 4E-03 I134 8.42E-08 8.42E-08 3.94E-05 I135 2.51E-06 2.51E-06 1.17E-0 3 RB88 1.67E-07 1.67E-07 7.81E-05 SR89 4.23E-08 4.23E-08 1.98E-05 U

SR90 1.92E-09 1.92E-09 8.98E-07 SR91 3.24 E-0 9 3.24E-09 1. 52E-06 Y90 2.18E-09 2.18E-09 1.02E-06 Y91M 2.0 8E-09 2.08E-09 9.74E-07 Y93 1.04E-09 1.04E-09 4.85E-07 ZR95 7.01E-09 7.01E-09 3.28E-06 NB95 7.18E-09 7.18E-09 3.36E-06 MO99 2.23E-05 2.23E-05 1. 04E-02 TC99M 2.20E-05 2.02E-05 9. 46E-0 3 RU103 3.34E-09 3.34E-09 1. 56E-0 6 RU106 3.45E-10 3.45E-10 1.61E-07 RH103M 3. 27E-09 3.27E-09 1. 53E-0 6 RH106 3.45E-10 3.45E-10 1. 61E-07 TE125M 8.74E-10 8.74E-10 4.09E-11 TE127M 2 .10 E-0 8 2.10E-08 9.80E-06 TE127 1.92E-08 1.92E-08 '3 . 9 7E-0 6 TE129M 3.78E-07 3.78E-07 1.77E-04 TE129 2.42E-07 2.42E-07 1.13E-04 TE131M 1.03E-07 1.03E-07 4.80E-05 TE131 1. 9 2E-0 8 1.92E-08 8.99E-06 TE132 1.90E-06 1.90E-06 8.88E-04 CS134 3.5SE-06 3.55E-06 1.66E-03 CS136 1.63E-06 1.63E-06 7.63E-94 CS137 1.78E-05 1.78E-05 8.32E-03 BA137M 1. 66 E-05 1.66E-05 7.7 8E-0 3 BA140 4.02E-08 4.02E-08 1.88E-05 LA140 2.75E-08 2.75E-08 1.29E-05 CE141 6.75E-09 6.75E-09 3.15E-06 W-3S 1 of 2 Amendment 17 40 ~'/

.J 9/30/75

Uu

SWESSAR-P1 TABLE 11.2-8 (CONT)

Discharge Rate Initial Activity After From Waste Activity Treatment Disposal System Nuclide (uCi/91 (uCi/qm) (Ci/yr)

CE143 2.43E-09 2.43E-09 1.13E-06 CE144 5.18E-09 5.18E-09 2.42E-06 PR143 6.21E-09 6 . 2 11 .9 2.90E-06 PR144 5.18E-09 5.18E-0() 2.42E-06 NP239 2.41E-08 2.41E-08 1.13E-05 CRS1 5.84E-08 5.84E-08 2.73E-05 MN54 9.91E-09 9.91E-09 4.63E-06 MN56 1.33E-08 1.33E-08 6.21E-06 FE55 5.12E-08 5.12E-08 2. 4 0E-0 5 FES9 3.12E-08 3.12E-08 1.46E-05 C058 5.04E-07 5.04E-07 2.36E-04 CO60 6.42E-08 6.42E-08 3.00E-05 Total 1. 2'J E-0 4 1.27E-04 5.95E-02 W-3S 2 of 2 ~

Amendment 17 ro UvU

~_[

J '

9/30/75

SWESSAR-P1 TABLE 11.2-9 ACTIVITY FROM SPENT RESIN FLUSH (DESIGN CASE)

Decontamination factor of waste disposal system for this source = 1.00E 04 Decay tiJne in waste disposal system (hours) = 2.00E 01 Flow rate (gal /yr) = 2.30E 04 Discharge Rate 17 Initial Activity Af ter From Waste Activity Treatment Disposal System Nuclide (uCi/qm) (uCi/qm) (Ci/yr)

CRS1 7.15E-02 7.00E-06 6.04E-04 MN54 2.69E-02 2.68E-06 2.31E-0 4 MN56 5.20E-04 2.42E-10 2.09E-08 FESS 1.48E-01 1.48E-05 1.28E-03 FE59 5.13E-02 5.06E-06 4.37E-04 CO58 1.01E 00 1.01E-04 8.67E-03 CO60 1.88E-01 1.88E-05 1.62E-03

'Ibtal 1.50E 00 1.49E-04 1.2 8E-0 2 W-3S 1 of 1 Amendment 17

{ { n,'] 9/30/75

SWESSAR-P1 s TABLE 11.2-10 ACTIVITY FROM LABORATORY WASTES (DESIGN CASE) Decontamination Factor of Waste Disposal System for this source = 1.00E 04 Decay Time in Waste Disposal System (Hours; = 2.00E 01 Flow Rate (gal /yr) = 4.00E 04 Discharge Rate Initial Activity After From hste Activity Treatment Disposal System Nuclide _ (uCi/4m) (uCi/am) (Ci/yr) BR83 8.49E-04 2.63E-10 3.94E-08 BR84 3.90E-04 1.70E-19 2.55E-1*/ BR85 5.35E-05 1.99E-52 2.98E-50 I131 2. 56 E-02 2.39E-06 3.58E-04 1132 8.86E-03 2 .2 8 E-0 7 3.42E-05 1133 4,01E-02 2.06E-06 3.08E-04 1134 Te . 49 E-0 3 6.79E-14 1.02E-11 I135 2.14E-02 2.68E-07 4 .02E-0 5 RB88 3.22E-02 1.26E-26 1.89E-24 SR89 4.22E-05 4.17E-09 6 . 2 5E-07 g SR90 1.87E-06 1.87E-10 2.80E-08 SR91 1.91E-05 4.56E-10 6. 8 3E-0 8 Y90 2.26 E-0 6 2.19E-10 3.28E-08 Y91M 1.15E-05 2.95E-10 4.41E-0 8 Y93 5.80E-06 1.49E-10 2.2 3E-0 8 ZR95 6.96E-06 6.90E-1C 1.03E-07 NB95 7.24E-06 7.13E-10 1.07E-07 MO99 3.27E-02 2. 6 5E-0 6 3. 97E-0 4 TC99M 1. 8 6 E-0 2 2.4 4 E-0 6 3.65E-04 RU103 3.35E-06 3.31E-10 4.95E-0 8 RU106 3.37E-07 3.37E-11 5.05E-09 RH103M 3.35E-06 3.24E-10 4 . 8 6E-0 8 RH106 3.37E-07 3.37E-11 5.05E-09 TE125M 8.70E-07 8.61E-11 1.2sE-08 TE127M 2.07E-05 2. 0 f P.-0 9 3.09E-07 TE127 1.02E-05 1.812-09 2.72E-07 TE129M 3.82E-04 3 .76E-0 8 5.63E-06 TE129 2.13E-04 2.41E-08 3.61E-06 TE131M 2. 27E-0 4 1. 4 3E-0 8 2 .14E-0 6 YE131 1.06E-04 2. 61E-0 9 3.91E-07 TE132 2.63E-03 2. 20E-07 3.30E-05 CS134 3.47E-03 3.47E-07 5.20E-05 CS136 1.74E-03 1. 66E-07 2.4 9E-05 CS137 1.74E-02 1.74E-06 2.60E-04 BA137M 1.62E-02 1. 62E-0 6 2.4 3E-0 4 BA140 4.30E-05 4.11E-09 6.16E-07 LA140 1.49E-05 2 . 28 E-09 3. 42E-07 CE141 6.83E-06 6.70E-10 1.00E-07 CE143 5.04E-06 3.31E-10 4 . 96E-08 W-3S 1 of 2 Amendment 17 a>g 9/30/75 6 0, b)

SWESSAR-P1

                'lABLE 11.2-10 (CONT)

Discharge Rate Initial Activity Af t.er From %ste Activity Treatment Disposal System Nuclide juCi/qm) (uCi/qm) (Ci/yr) _ CL144 5.57E-06 5.06E-1G 7.58E-Os PR143 6.61E-06 6.3D: -10 9.4 9E-0 8 PR144 5.07E-06 5.06E-10 7.58E-08 NP239 3.77E-05 2.95E-09 4.42E-07 CRS1 5.95E-05 5.83E-09 8.73E-07 MN54 9.70E-06 9.68E-10 1.45E-07 MN56 2.93E-04 1.36E-10 2.04E-08 17 FESS 5.00E-05 5.0 0E-0 9 7.49E-07 FES9 3.13E-05 3.09E-09 4.63E-07 C058 5.00E-04 4. 9 6E-0 8 7.43E-06 CO60 6.26E-05 6.26E-09 9.38E-07 'IOTAL 2.30E-01 1.43E-05 2.14E-03 W-3S 2 of 2 _,_ Amendment 17 [3 j[j t ,sJ 9/30/75

SWESSAR-P1 TABLE 11.2-11 ACTIVITY FROM PROCESSED PRIMARY COOLANT SYiTZ.M LEAKAGE (DESTGN CASE) Decontamination Factor of Waste Disposal System for this Source = 1.00E 04 Decay Time in Waste Disposal System (Hours) = 2.00E 01 Flow Rate (gal /yr) = 1.76E 04 Discharge Rate Initial Activity After From Waste Activity Treatment Disposal System Nuclide (uCi/qm) (uCi/qm) (Ci/yr) BR83 3.93E-04 1.22E-10 8.02E-09 BR84 3.9 8E-05 1.74E-20 1.14E-18 BR85 5.16E-07 1.92E-54 1.26E-52 I131 8.86E-01 8.25E-05 5.43E-03 1132 4.59E-02 3.62E-06 2.38E-04 1133 1.61E-01 8.25E-06 5.43E-04 I134 9.22E-04 1.14E-14 7.52E-13 I135 2.75E-02 3.45E-07 2.27E-0 5 RB88 1.95E-03 7.66E-28 5.04E-26 SR89 3.55E-03 3.51E-07 2.31E-05 SR90 1.92E-04 1.92E-08 1.26E-06 n SR91 3.80E-05 9.06E-10 5. 96E-0 8 Y90 1.97E-04 1.96E-08 1.29E-06 Y91M 2 .4 4 E-35 5.85E-10 3.85E-08 Y93 1.22E-05 3.12E-10 2.06E-08 ZR95 '.12E-04 6.07E-00 3.99 E-06 NB95 5.61E-04 5.52E-08 3.63E-06 MO99 4 .47E-01 3.63E-05 2.39E-03 TC99M 4.16E-01 3.49E-05 2.30E-03 RU103 2.68E-04 2.64E-08 1.74E-0 6 RU106 3.36E-05 3.36E-09 2.21E-07 RH103M 2.63E-04 2.59E-08 1.71E-06 RH106 3.36E-05 3.36E-09 2.21E-07 TE125M 7.50E-05 7.42E-09 4.89E-07 TE127M 1.93E-0 3 1.92E-07 1.26E-05 TE127 1.90E-03 1.91E-07 1.26E-05 TE129M 2.94E-02 2.89E-06 1. 9 0E-04 TE129 1.88E-02 1.85E-06 *

                                                        ?2E-04 TE 131M           1.40E-03          8.82E-08            ,61E-06 TE131             2.61E-0 4         1. 61E-08         1.06E-06 TE132             4.20E-02          3.51E-06          2.31E-04 CS134             3.51E-01          3.51E-05          2.31E-03 CS136             9.16E-02          8.78E-06          5.78E-04 CS137             1.78E 00          1.78E-04          1.17E-02 BA137M            1.66E 00          1.66E-04          1. 09E-02 BA140             2.18E-03          2.08E-07          1.37E-05 LA140             2 .22E-0 3        2.20E-07          1.45E-05 CE141             5.17E-04          5.08E-08          3.35E-06 W-3S                           1 of 2            -  -     , Amendment 17 bbU   s-    !

9/30/75

SWESSAR-P1 TABLE 11.2-11 (CONT) Discharge Rate Initial Activity After From Waste Activity Treatment Disposal System Nuclide (uCi/qm) (uCi/qm) (Ci/yr) CE143 3.42E-05 2.25E-09 1.48E-07 CE144 5.01E-04 5.00E-08 3.29E-06 PR143 3.47E-04 3.33E-08 2.19E-06 PR144 5.01E-04 5.00E-08 3.29E-06 NP239 4 .37E -04 3.42E-08 2.25E-06 CRS1 4.30E-03 4.21E-07 2.77E-05 MN54 9.63E-04 9.61E-08 6 . 33E-06 n MN56 1.55E-04 7.23E-11 4.76F-09 FESS 5.08E-03 5.07E-07 3.34E-05 FES9 2.57E-03 2.54E-07 1.67E-05 C058 4.45E-02 4.41E-06 2 .91E-0 4 CO60 6.39E-03 6.38E-07 4.29E-05 Total 6.04E 00 5.70E-04 3.75E-02 W-3S 2 of 2 Amendment 17

                                   ,n
                                   ,      ' 'l 9/30/75 bLO     JaL

SWESSAR-P1 TABLE 11.2-12 ACTIVITY FROM UNPROCESSED PRIMARY COOLANT SYSTEM LEAKAGE (DESIGN CASE) Decontamination Factor of Haste Disposal System For this Source = 1.00E Of' Decay Time in Waste Disposal System (Hours) = 1.00E 01 Flow Rate (gal /yr) = 1.76E 01 Discharge Rate Initial ActiJity After From Waste Activity Treatment Disposal System Nuclide JuCi/qm) __ (uCi/qm) _ (Ci/yr) BR83 3.93E-04 2.19E-05 1.44E-06 BR84 3.98E-05 8.32E-11 5.48E-12 BR85 5.16E-07 1.92E-50 1.26E-51 1131 8.86E-01 8.55E-01 5.63E-02 I132 4.59E-02 3.97E-02 2.61E-03 I133 1.61E-01 1.15E-01 7.58E-03 1134 9.22E-04 3.24E-07 2.14E-08 1135 2.75E-02 9.74E-03 6.41E-04 RB88 1.95E-03 1.22E-13 8.04E-15 SR89 3.55E-03 3.53E-0 3 2.33E-04 SR90 1.92E-On 1.92E-04 1.26E-05 17 SR91 3.80E-05 1.85E-05 1.22E-06 Y90 1.97E-04 1.96E-04 1.29E-05 Y91M 2.44E-05 1.20E-05 7.89E-07 Y93 1, 7 2 E-O ' - 6.16E-06 4.06E-07 ZR95 6.12E-04 6.0 9E-0 4 4.01E-0 5 NB95 5.61E-04 5.56E-04 3.66E-05 M099 4.47E-01 4 .03E-01 2.65E-02 TC99M 4.16E-01 3. 8 4E-01 2.53E-02 RU103 2.68E-04 2.66E-04 1. 75E-0 5 RU106 3.36E-05 3.36E-05 2.21E-06 RH103M 2.63E-04 2.61E-04 1.72E-05 RH106 3.36E-05 3. 36E-0 5 2.21E-06 TE 125M 7.50E-05 7.46E-05 4.91E-06 TE127M 1.93E-03 1.92E-03 1.27E-04 TE127 1.90E-03 1.91E-03 1.26E-04 TE129M 2.94E-02 2. 91E-0 2 1.92E-03 TE129 1.88E-02 1.87E-02 1.23E-03 TE131M 1.40E-03 1.11E-0? 7.32E-05 TE131 2.61E-04 2.03E-04 1.34E-05 TE132 4.20E-02 3.84E-02 2.53E-0 3 CS134 3.51E-01 3.51E-01 2.31E-02 CS136 9.16E-02 8.97E-02 c 90E-03 CS137 1.78E 00 1.78E 00 1.17E-01 BA137M 1.66E 00 1.66E 00 1.0 9E-01 BA140 2.18E-03 2.13E-03 1.a0E-04 LA140 2.22E-03 2.21E-03 1.46E-04 CE141 5.17E-04 5.13E-04 3.38E-05 CB143 3.42E-05 2.77E-05 1.82E-06 W-3S 1 of 2 Amendment 17

                                              -          -- r '          9/30/75 Js) f);.6)

SWESSAR-P1 TABLE 11.2-12 (CONT) Discharge Rate Initial Activity After From Waste Activity Treatm 7t Disposal System Nuclide (uCi/qm) (uCi/q ) (Ci/yr) CE144 5.01E-04 5.01E-04 3.30E-05 "R143 3.47E-04 3.40E-04 2.24E-05 PR144 5.01E-04 5.01E-04 3.30E-05 HP239 4.37E-04 3. 8 7E-0 4 2.55E-05 CRS) 4.30E-03 4.25E-03 2.80E-04 MN54 9.63E-04 9.62E-04 6. 33E-0 5 MN56 1.55E-04 1. 06E-0 5 6.97E-07 g FESS 5.08E-03 5. 0 7E-0 3 3.34E-04 FE59 2.57E-03 2.55E-03 1.68E-04 CD58 4.45E-02 4.43E-02 2. 92E-0 3 CO60 6.39E-03 6.38 E-0 3 4.20E-04 'IOTAL 6.04E 00 5.86E 00 3.85E-01 W-3S 2 of 2 Amendment 17 9/30/75 (j b b JJ'r

SWESSAR-P1 TABLE 11.2-13 ACTIVITY FROM TURBINE PLANT SAMPLING SINKS (DESIGN CASES) Decontamination factor of waste disposal system for this source 1.00E 04 Decay time in waste ' disposal system (hours) = 2.00E 01 Flow rate (gal /yr) = 3.00E 04 Discharge Rate Initial Activity After From Waste Activity Treatment Disposal System Nuclide fuCi/cm) (uCi/qm) (Ci/yr) BR83 2.33E-07 7.22E-14 8.10E-12 BR84 4.00E-08 1.75E-23 1.96E-21 BR85 6.31E-10 2.35E-57 2.63E-55 I131 1. 32E-05 1.23E-09 1.38E-07 I132 3. 77E-06 6.28E-11 7 .04 E-09 I133 1.90E-05 9.76E-10 1. 0 9E -07 1134 8.22E-07 1.02E-17 1.14E-15 1135 8. 42E-0 6 1.06E-10 1.19E-08 RB88 5. 37E-07 2.11E-31 2.36E-29 n SR89 1.22E-08 1.21E-12 1. 3 5E-10 SR90 5.42E-10 5.42E-14 6.08E-12 SR91 3.70E-09 8.82E-14 9.89E-12 Y90 7. 8 2E-10 7.35E-14 8.25E-12 Y91M 1. 80E -09 5.70E-14 6.39E-12 Y93 1.31E-09 3.36E-14 3.77E-12 ZR95 2.01E-09 1.99E-13 2.23E-11 NB95 2.10E-09 2.07E-13 2.32E-11 MO99 1. 07E -05 8.69E-10 9.74E-08 TC99M 7.12E-0 6 8.08E-10 9.06E-08 RU103 9.67E-10 9.53E-14 1.07E-11 RU106 9.77E-11 9.75E-15 1.09E-12 RH103M 9. 67E-10 9.35E-14 1.05E-11 RH106 9. 77E-11 9.75E-15 1.09E-12 TE125M 2.53E-10 2.50E-14 2.81E-12 TE127M 5. 98E-0 9 5.95E-13 6.67E-11 TE127 4.00E-09 5.48E-13 6.15E-11 TE129M 1.10E-07 1.08E-11 1.21E-09 TE129 1.01E-07 6.93E-12 7.77E-10 TE131M 5.67E-08 3.57E-12 4.01E-10 TE131 1.29E-08 6.52E-13 7.31E-11 TE132 7.20E-07 6.02E-11 6.75E-09 CS134 1.23E-06 1.23E-10 1.38E-08 CS136 6. 07E-07 5.82E-11 6.53E-09 CS137 6.17E-0 6 6 .17E-10 6.92E-08 BA137M 5.67E-06 5.77E-10 6.47E-08 BA140 1.23E-08 1.18E-12 1.32E-10 LA100 5.17E-09 7.16E-13 8.03E-11 CE141 1.97E-09 1.94E-13 2.17E-11 W-3S 1 of 2 Amendment 17

                                              ,_               9/30/75 bLU    so

SWESSAR-P1 TABLE 11.2-13 (CONT) Discharge Rate I nit.t al Activity After From Waste Activity Treatment Disposal System Nuclide fuCi/qm) (uCi/qm) (Ci/yr ) CE143 1.27E-10 8.34E-14 9.36E-12 CE144 1.47E-09 1.47E-13 1.65E-11 PR143 1.91E-09 1.83E-13 2.05E-11 PR144 1. 47E-0 9 1.47E-13 1.65E-11 NP239 1.01E-08 7.90E-13 8.86E-11 CRS1 1.71E-08 1.67E-12 1.88E-10 I? MN54 2.80E-09 2.79E-13 3.13E-11 MN56 2.95E-08 1.37E-14 1.54E-12 FESS 1.45E-08 1.45E-12 1.63E-10 FE59 9.02E-09 8.91E-13 9. 9 9E-11 C058 1.45E-07 1.44E-11 1. 61E-0 9 CO60 1.81E-08 1.81E-12 2.03E-10 TOTAL 7.88E-05 5.54E-09 6.2i2-07 bbO W-3S 2 of 2 Amendment 17 9/30/75

SWESSAR-Pi TABLE 11.2-14 ACTIVITY FROM TURBINE BUILDING SUMPS (DESIGN CASE) Decontamination , factor of waste disposal system for this source = 1.00E 00 Decay time in waste disposal system 01ours) = 0.0 Flow rate (gal /yr) = 1.30E 05 Discharge Rate Initial Activity After From Waste Activity Treatment Disposal System Nuclide fuCi/qm) (uCi/qm) (Ci/yr) BR83 2.33E-07 2.33E-07 1.13E-04 BR84 4.00E-08 4 .0 0E-08 1.94E-05 BR85 6.31E-10 6.31E-10 3.07E-07 1131 1.32E-05 1. 32E-05 6.41E-03 I132 3. 77E-06 3.77E-0 6 1.83E-03 I133 1.90E-05 1.90E-05 9.23E-03 I134 8.22E-07 8.22E-07 3.99E-04 I135 8. 42E-0 6 8 . 4 2E-0 6 4.09E-03 RB88 5. 37E-07 5 .37E-07 2.61E-04 h, SR89 1.22E-08 1.22E-08 5.93E-06 SR90 5.42E-10 5.42E-10 2.63E-07 SR91 3. 70E-0 9 3.70E-09 1. 80E-06 Y90 7.82E-10 7.82E-10 3.80E-07 Y91M 1. 80E-0 9 1.80E-09 8.74E-07 Y93 1.31E-09 1.31E-09 6.36E-07 ZR95 2. 01E-0 9 2 .01E-0 9 9.76E-07 NB95 2.10E-09 2.10E-09 1.02E-06 MO99 1. 07E-05 1.07E-05 5.20E-03 TC99M 7.12E-06 7 . ',2E-0 6 3.46E-03 RU103 9.67E-10 9.67E-10 4 .70E-07 RU106 9. 77E-11 9.77E-11 4.75E-08 RH103M 9.67E-10 9.67E-10 4.70E-07 RH106 9. 77E-11 9.77E-11 4.75E-08 TE125M 2.53E-10 2.53E-10 1.23E-07 TE127M 5. 98 E-0 9 5.98E-09 2.90E-06 TE127 4. 00E-0 9 4 . 0'JE-0 9 1.94E-06 TE129M 1.10E-07 i.10E-07 5.34E-05 TE129 1.01E-07 1. 01E --07 4.91E-05 TE131M 5. 67E-0 8 5. 67E-0 8 2.75E-05 TE131 1.29E-08 1.29E-08 6.27E-06 TE132 7. 2CE-07 7.20E-07 3.50E-04 CS 134 1.23E-06 1.23E-06 5.98E-04 CS136 6. 07E-07 6 .07E-07 2.95E-04 CS137 6.17E-06 6.17E-06 3.00E-03 BA137M 5.67E-06 5.67E-06 2.75E-03 BA140 1.23E-08 1.23E-08 5.98E-06 LA140 5.17E-09 5.17E-09 2.51E-06 W-3S 1 of 2

                                                        ' ']
                                                         >J    Amendment 17

{ (-M 9/30/75

SWESSAR-P1 TABLE 11.2-14 (CONT) Discharge Rate Initial Activity After From Waste Activity Treatment Disposal System Nuclide _ [u Ci/qm) (uCi/qm) _ (Ci/vr) CE141 1. 97E-09 1.97E-09 9.57E-07 CE143 1.27E-09 1.27E-09 6.17E-07 CE144 1. 47E-0 9 1.47E-09 7.14E-07 PR143 , 1.91E-09 1.91E-09 9.28E-07 PR144 1. 47E-09 1.47E-09 7.14E-07 NP239 1.01E-OS 1.01E-08 4.91E-06 CRS1 1.71E-68 1.71E-08 8.31E-06 MN54 2.80E-09 2.80E-09 1.36E-06 MN56 2.95E-08 2.95E-08 1.43E-05 17 FESS 1.45E-08 1.45E-08 7.04E-06 FE59 9. 02E-0 9 9.02E-09 4.3 8E-0 6 0058 1.45E-07 1.45E-07 7.04E-05 CO60 1. 81E-0 8 1.81E-08 8.79E-06 TOTAL 7. 88E-05 7.88E-05 3.83E-02

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                                                    "~
                                                        .J (j 'J J W-3S                       2 of 2                          Amendment 17 9/30/75

SWESSAR-P1 TABLE 11.2-15 ACTIVITY FROM CHEMICAL REGENERATIVE WASTE (DESIGN CJdE) Decontumination Factor of Waste Disposal System for this Source = 1.00E 04 Decay Time in Waste Disposal System 0 Hours)= 2.00E 01 Flow Rate (gal /yr) = 1.60E 06 Discharge Rate Initial Activity After From Water Activity Treatment Disposal System Nuclide luCi/qm). (uCi/qm) (Ci/yr) BR83 1.01E-05 3.13E-12 1.87E-08 BR84 3. 82 E-07 1.67E-22 1.00E-18 BR85 5.69E-10 2.12E-57 1.27E-53 1131 4.26E-02 3.9 6E-0 6 2.37E-02 I132 1.91E-03 1.51E-07 9.05*-04 1133 7.13 E-03 3.66E-07 2.19E-03 I134 1.29E-05 1.60E-16 9.59E-13 I135 1.01E-03 1.27E-0 8 7. 64E-0 5 RB88 4.97E-06 1.95E-30 1.17E-26 SR89 1. 55 E-04 1.54E-08 9.21E-05 SR90 8.40E-06 8.40E-10 5.03E-06 SR91 1.12E-06 2.68E-11 1.603-07 Y90 3.88E-06 8.79E-10 5.27E-06 Y91M 7.10E-07 1.73E-11 1.04 E-07 Y93 4.19E-07 1.08E-11 6 .44 E-0 8 ZR95 2. 6 8 E-05 2. 65E-0 9 1. 59E-0 5 NB95 2.46E-05 2.42E-09 1.45E-05 g MO99 2.23E-02 1. 81E-0 6 1.09E-02 TC99M 2.10E-02 1.75E-0 6 1.05E-0 2 PU103 1.17E-05 1.15E-0 9 6. 92E-0 6 RU106 1.47E-06 1.47E-10 8.82E-07 RH103M 1.15E-05 1.13E-0 9 6.78E-06 RH106 1.47E-0 6 1.47E-10 8.82E-07 TE125M 3.30E-06 3.27E-10 1.9 6E-0 6 TE127M 8 . 4 4 E-0 6 8.4 0E-0 9 5.03E-05 TE127 8.35E-05 8 . 35E-0 9 5.00E-0 5 TE129M 1.28E-05 1.26E-07 7.55E-04 TE129 8.23E-04 8.08E-08 4.84E-04 TE131M 5.34E-05 3.36E-09 2.02E-05 TE131 9.78E-06 6.14E-10 3.68E-06 TE132 1.75E-03 1.47E-07 8.78E-04 CS134 1.89E-02 1.38E-06 1.13E-02 CS136 4.87E-03 4. 67E-07 2.80E-03 CS137 9.56E-02 9.56E-06 5.73E-02 BA137M 8.94E-02 8.94E-0 6 5.36E-02 BA140 9.47E-05 9. 0 6E-0 9 5.4 3E-05 LA140 9. 77E-05 9. 6 2E-09 5. 76E-05 CE141 2.26 E-05 2. 22E-0 9 1.33E-05 W-3S 1 of 2 ,r, Amendment 17 o _s  ! 9/30/75 (!O U

SWESSAR-P1 TABLE 11.2-15 (Colfr) Discharge Rate Initial Activity After From Water Activity Treatment Disposal System Nuclide (uCi/qm) (uCi/qm) (Ci/yr) CE143 1.32E-06 8.66E-11 5.19E-07 CE144 2.20E-05 2.19E-09 1.31E-05 PR143 1.52E-05 1.46E-09 8.75E-06 PR144 2.20E-05 2.19E-09 1.31E-05 NP239 1.78E-05 1.40E-09 8.37E-06 CRS1 1.87E-04 1.84E-08 1.10E-04 g MN54 4.20E-05 4.19E-0 9 2.51E-05 MN56 2.39E-06 1.11E-12 6.67E-09 FESS 2.22E-04 2.22E-08 1.33E-04 FE59 1.12E-04 1.11E-08 6.64E-05 C058 1.95E-03 1.94E-07 1.16E-03 CO60 2.80E-04 2.79E-08 1.67E-04 TOTAL 3.12E-01 2.96E-05 1.77E-01

                                      ,.~~
                                \.) '

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SWESSAR-P1 TABLE 11.2-16 ACTIVITY FROM LAUNDRY DRAINS (DESIGN CASE) Decontamination Factor Of Waste Disposal System For This Source = 1.00E 00 Decay Tjie In haste Disposal System (Bours) = 0.0 Flow Rate (Gal /Yr) = 2.00E 05 Initial Activity After Discharge Rate Activity Treatment From Waste Disposal System Nuclide (uCi/qm) (uCi/qm) (Ci/yr) BR83 5.75E-07 5.75E-07 4.31E-04 BR84 2.64E-07 2.64E-07 1.98E-04 BR85 3.62E-08 3.62E-08 2.71E-05 I131 1.74E-05 1.74E-05 1.30E-02 I132 6.00E-06 6.00E-06 4.49E-03 I133 2.71E-05 2.71E-05 2.03E-02 1134 3.72E-06 3.72E-06 2.7 8E-03 IS35 1.45E-05 1.45E-05 1.08E-02 RB88 2.18E-0 5 2.18E-05 1.63E-02 SR89 2.86E-08 2.86E-08 2.14E-05 SR90 1.27E-09 1.27E-09 4.49E-07 SR91 1.29E-08 1.29E-08 9.69E-06 Y90 1.53E-09 1.53E-09 1.15E -0 6 Y91M 7.79E-0 9 7.79E-09 5.83E-06 U Y93 3.93E-09 3.93E-09 2.94E-06 ZR95 4.71E-09 4.71E-09 3.53E-06 NB95 4.90E-09 4.90E-09 3.67E-06 MO99 2.21E-05 2.21E-05 1.66E-02 TC99M 1.26E-05 1.26E-05 9.44E-03 RU103 2.27E-09 2.27E-09 1. 70E-0 6 RU106 2.28E-10 2.28E-10 1.71E-07 kH103M 2.27E-09 2.27E-09 1.70E-06 RH106 2.28E-10 2.28E-10 1.71E-07 TE125M 5.89E-10 5.89E-10 .4.41E-07 TE127M 1.40E-08 1.40E-08 1.05E-05 TE127 6.93E-09 6.93E-09 5.19E-0 6 TE129M 2.39E-07 2.59E-07 1.94 E-0 4 TE129 1.44E-07 1.44E-07 1.08E-04 TE131h 1.54E-07 1.54E-07 1.15E-04 TE131 7.19E-08 7.19E-08 5.39E-05 TE132 1.78E-0 6 1.78 E-0 6 1.33E-03 CS 134 2.35E-06 2.35E-06 1.76E-03 CS136 1.17E-06 1.17E-0 6 8.80E-0 4 CS137 1.17E-05 1.17E-05 8.80E-03 BA137M 1.10E-05 1.10E-05 8.21E-03 BA140 2.91E-08 2.91E-08 2.18E-05 LA140 1.01E-08 1.01E-08 7.56E-06 CE141 4.62E-09 4.62E-09 3.46E-06 CE143 3.41E-09 3.412-09 2.5 6E-0 6 CE144 3.43E-09 3.43E-09 2.57E-06 l W-3S 1 of 2 Amendment 17 66 C) ] [' j 9/30/75

SWESSAR-P1 TAhLE 11.2-16 (CONT) Initial Activity After Discharge Eate

        ;, tivity    Treatment       From Waste Disposal System Nuclide  (uCi/cm)     (uCi/qmt                  (Ci/yr)

PR143 4.47E-09 4.47E-09 3.35E-06 PR144 3.43E-09 3.43E-09 2.57E-06 NP239 2.55E-08 2.55E-08 1. 91E-0 5 CRS1 4.03E-08 4.03E-08 MN54 3.02E-05 6.57E-09 6.57E-09 4.92E-06 MN56 1.98E-07 1.98E-07 1.48E-04 FESS 3.39E-08 3.39E-08 2.54E-05 11 FES9 2.12E-08 2.12E-08 1.59E-05 C058 3.39E-07 3.39E-07 2.54E-04 CO60 4.24E-08 4.24E-08 3.17E-05 TOTAL 1.56E-04 1.56E-04 1.17E-01 N-3S 2 of 2 gJ {h Amendment 17 9/30/75

SWESSAR-P 1 TABLE 11.2-17

 'IOTAL ACTIVITY EROM RADIOACTIVE LIQUID WASTE SYSTEM GENERATOR LEAKAGE (DESIGN CASE)

Calculated Total Discharge Flow Rate (gpm) 0.11 Actual Actual Activity Discharge Rate Nuclide JuCi/qm) (Ci/yr) BR83 6.87E-08 5.62E-04 BR84 2.68E-08 2.19E-04 BR85 3.36E-09 2.75E-05 I131 1.45E-05 1.19E-01 I132 1.39E-06 1.14E-0 2 I133 5.99E-06 4.90E-02 I134 3.94E-07 3.2 2E-0 3 I135 2.10E-06 1.72E-02 RB88 2.04E-06 1.67E-02 SR89 4.90E-08 4.01E 04 SR90 2.60E-09 2.13E-05 SR91 1.84E-09 1.50E-05 Y90 2.73E-09 2.24 E-05 Y91M 1.10E-09 9.00E-0 6 Y93 5.80E-10 4.75E-06 ZR95 8.41E-09 6.88E-05 NB95 7.80E-09 6.38E-05 MO99 9. 22E-0 6 7. 54 E-02 TC99M 7.7 7E-0 6 6. 36E-02 RU103 3.71E-09 3.04E-0 5 RU106 4.58E-10 3.74E-06 RH103M 3.64E-09 2.98 E-05 RH106 4.5GE-10 3.74E-06 TE125M 1.03E-09 8.45E-06 TE127M 2. 64 E-0 8 2.16E-0 4 TE127 2.53E-08 2.07E-04 TE129M 4.08E-07 3. 34 E-03 TE129 2.61E-07 2.14E-03 TE131M 3.77E-08 3.09E-04 TE131 1.11E-08 9.06E-05 TE132 7.94E-07 6.50E-0 3 CS134 5.04E-06 4.12E-02 CS136 1.4 0E-0 6 1.14 E-02 CS137 2.55E-05 2. 0 9E-01 BA137M 2.38E-05 1.95E-01 BA140 3.18E-08 2.60E-04 LA140 2.98E-08 2.44E-04 CE141 7.20E-09 5. 8 9E-15 CE143 8.84E-10 7.231 ,6 CE144 6.83E-09 5.59E v5 PR143 5.05E-09 4.13E-05 PR144 6.83E-09 5.59E-05 W-3S 1 of 2 Amendment 17

                                          .' i,              9/3*/75 uud

SWESSAR-P1 TABLE 11.2-17 (CONT) Actual Actual Activity Discharge Rate Nuclide (uCi/qm) (Ci/yr) NP7.39 9.20E-09 7.52E-05 CR51 ~ 1.35E-0 7 1.10E-03 MN54 4.19E-08 3.0 3E-0 4 MN56 2.07E-08 1.70E-04 FESS 2. 28 E-07 1. 87E -0 3 FES9 8.96E-08 7.33E-04 C058 1.69E-06 1.38E-02 CO60 2.89E-07 2.37E-03 17 H3 1.80E-01 1.47E 03 TOTAL 1. 8 0E-01 1.47E 03 TOTAL (NON-TRITIUM) 1.04E-04 8.47E-01 (, 6 0 f , W-3S 2 af 2

                                             ' #  i Amendment 17 9/30/75

SWEdSAR-P1 TABLE 11.2-18 (W-3S) has been deleted. 19 W-3s 1 of 1 Amendment 19 12/12/75 7- ,

SWESSAR-P1 TABLE 11.2-20 ACTIVITY FRCH DECONTAMINATION DRAINS (EXPECTED CASE) Decontamination f actor of waste disposal system for this source = 1.00E 04 Decay time in waste disposal system (hours) = 2.00E 01 Flow rate (gal /yr) = 1.64E 04 Dis charge Activity Rate From Initial After Waste Dis-Activity Treatznent posal Sys-Nuclide (uCi/gm) (uCi/gm) tem (Ci/yr) BR83 6.19E-08 1.92E-14 1.18E-12 BR84 7.29E-09 3.18E-24 1.9 5E - 2 2 BR85 7.90E-11 2.94E-58 1.80E-56 I131 7.29E-04 6.79E-08 4.16E-06 1132 2.10E-05 1.68E-09 1.03E-07 I133 4.93E-05 2.53E-09 1.55E-07 I134 2.17E-07 2.69E-18 1.65E-16 I135 7.05E-07 8.85E-11 5. 4 3E-0 9 RB88 3.11E-07 1.22E-31 7.48E-30 SR89 6.1AE-06 6.07E-10 3.72E-0 8 SR90 2. 9 5E-07 2.95E-11 1.81E-0 9 SR91 3.60E-08 8.58E-13 5.26E-11 1.83E-09 U Y90 2.99E-07 2.98E-11 Y91M 1.63E-08 5.55E-13 3.40E-11 Y93 7.60E-09 1.95E-13 1.20E-11 ZR95 1.18E-06 1.17E-10 7.17E-0 9 NB95 1.21E-06 1.19E-10 7.30E-09 MO99 2. 6 ' E-0 4 2.12E-08 1.30E-0 6 TC99M 2.48E-04 2.05E-08 1.2 5E-06 RU103 6.9 2E-07 6.82E-11 4.18E-0 9 RU106 2.75E-07 . 75E-1*, 1.68E-09 RH103M 6.83E-07 6.69E-11 4.10E-09 RH106 2.7 5E-07 2.75E-11 1.6 8E-0 9 TE125M E . 41E-07 5.36E-11 3.2 8 E-0 9 TE127M 6. 4 3E-0 6 6.40E-10 3.92E-08 TE127 6.19E-06 6.39E-10 3. 91E-0 8 TE129M 1.96E-05 1.93E-09 1.18 E-07 TE129 1.9BE-05 1.24E-09 1. 57E-08 TE131M 5,08E-07 3.20E-11 . 9 6E-0 9 TE131 1.04E-07 5.84E-12 3.58E-10 TE132 1.95E-05 1.63E-09 1.00E-07 CS134 7.11E-04 7.10E-08 4.35E-06 CS136 7.57E-05 7.26E-09 4.4 5E-07 CS137 5.29E-04 5.29E-08 3.24 E-0 6 BA137M 4.87E-04 4.95E-08 3.03E-06 BA14G 1.18E-06 1.13E-10 6.91E-09 LA140 1.33E-06 1.28E-10 7.63E-0 9 W-3S 1 of 2 Amendment 17 a -o 9/30/75

SWESSAR-P1 TABLE 11.2-20 (CONT) Discharge Activity - Rate From Initial After Waste P 4s-Activit) Treatment posal Sys-Nuclide (uCi/gm) (uCi/gm) tem (Ci/yr) CE141 9.44E-07 9.27E-11 5.68E-09 CE143 9.15E-09 6.01E-13 3.68E-11 CE144 8.86E-07 8.84E-11 5. 42E-0 9 PR143 2.97E-07 2.85E-11 1.74E-09 PR144 8.86E-07 8.84E-11 5.42E-09 NP239 5.5 2E-07 4.32E-11 2.65E-09 CR51 1.19E-03 1.17E-07 7.14E-0 6 17 MN54 7.77E-04 7.76E-08 4 .75E-0 6 FESS 4 . 4 6E-03 4.46E-07 2.73E-05 FE59 1.06E-03 1.05E-07 6.41E-06 CO58 2.41E-02 2.39E-06 1.47E-04 CO60 5.73E-03 5.73E-07 3.51E-05 TOTAL 4.05E-02 4.01E-06 2. 4 6E-0 4 I) ,' Lv/ W-3S 2 of 2 Amendment 17 9/30/75

SWESSAR-P1 TABLE 11.2-21 ACTIVITY FROM REAC'ICR PLANT SAMPLING SINKS (EXPECTED CASE) Decontanu. nation f actor of waste disposal system 1.00E 04 for this source = Decay time in waste disposal system (hours) = 2.00E 01 Flow rate (gal /yr) = 3.00E 03 Discharge Rate Initial Activity After From Waste Activity Treatment Disposal System (uCi/qm) (uCi/qm) (Ci/yr) Nuclide BR83 5.26E-0 3 1.63E-09 1.83E-08 BR84 2.86E-03 1.25E-18 1.40E-17 BR85 3.30E-04 1.23E-51 1.38E-50 I131 2.89E-01 2.69E-05 3.02E-04 1132 1.10E-01 2.52E-06 2.82E-05 I133 4.11E-01 2.11E-05 2.37E-04 I134 5.17E-02 6.40E-13 7.18E-12 1135 2.07E-01 2.60E-06 2.91E-05 RB88 2.20E-01 8.63E-26 9.68E-25 SR89 3.74E-04 3.70E-08 4.15E-07 SR90 1.07E-05 1.07E-09 1.20E-08 Sn91 7. 06E-04 1.68E-08 1.89E-07 0 Y90 1.83E-05 1.68E-09 1.89E-08 Y91M C.18E-04 1.09E-08 1.22E-07 Y93 1.41E-04 3.62E-09 4.06E-08 ZR95 6.42E-05 6 .36E-09 7.14E-08 NE95 5.35E-05 5.2GE-09 5.90E-08 MO99 4.83E-01 3.92E-05 4.40E-04 TC99M 4.14 E-01 3.74E-0 5 4.20E-04 RD103 4. 81E-05 4.74E-09 5.32E-08 B'1106 1.07E-05 1.072-09 1.20E-08 RH103M 4. 94E-0 5 4.6SE-09 5.22E-08 RH106 1.10E-0 5 1.07E-09 1.20E-08 TE 125M 3.10E-05 3. 07E-09 3.4 4E-0 8 TE127M 2.99E-0 4 2.97E-08 3.34E-07 TE127 9. 24E-04 4 .27E-0 8 4.90E-07 TE129M 1.50E-03 1.47E-07 1.65E-06 TE129 1.76E-03 9.,45E-08 1.06E-06 TE131M 2. 70E-03 1.70E-07 1.91E-06 TE131 1. 21E-0 3 3.10E-08 3.48E-07 TE132 2.90E-02 2. 43E-0 6 2.7 2 E-0 5 CS134 2.67E-02 2.67E-06 2.99E-05 CS136 1.39E-02 1.33E-06 1.49E-05 CS137 1. 92E-02 1.92E-06 2.15E-05 BA137M 1.76E-02 1.80E-06 2.01E-05 BA140 2. 36E-04 2.26E-08 2.53E-07 LA140 1. 61E-04 1.81E s8 2.03E-07 CE141 7. 49E-05 7.36E-09 8.25E-08 W-3S 1 of 2 b, Y h0U Amendment 17 9/30/75

SEESSAR-P1 1ABLE 11.2-21 (CONT) Discharge Rate Initial Activity After From Waste Activity Treatment Disposal System Nuclide (uCi/qm) (uCi/qm) , (CA/yr) CE143 4. 31E-05 2.83E-09 3 .18E-0 8 CE144 3.53E-G5 3.52E-09 3.95E-08 PR143 5.35E-05 5.13E-09 5.75E-08 PR144 3. 63E-05 3. 52E-09 3.95E-08 NP239 1.29E-03 1.01E-07 1.13E-06 CR51 2.03E'03 1.9 9E-07 2 .23E -06 17 MN54 3. 32E-04 3.31E-08 3.72E-07 FESS 1.71E-03 1.71E-07 1.92E-06 FES9 1.07E-03 1.06E-07 1.18E-06 0058 1.71E-0 2 1.70E-06 1.90E -05 CO60 2.14E-03 2.14E-07 2.40E-06 TOTAL 2.34E-00 1.43E-04 1.60E-03 i W-3S 2 of 2 Amendment 17 b / ij) 9/30/75

SWESSAR-P1 TABLE 11.2-22 ACTIVITY FRG1 BORON RECOVERY LETDOWN (EXPECTED CASE) Decontamination Factor of Waste Disposal System For this Source = 1.00E 00 Decay Time in Waste Dist ,al System (Hours) = 0.0 Flow Rate (gal /yr) = 3.78E 05 Discharge Rate Initial Activity After From Waste Activity Treatment Disposal System Nuclide (uCi/qm) (uCi/qm) _(Ci/yr) BR83 2.17E-09 2.17E-09 3.07E-06 BR84 2.60E-10 2.60E-10 3.68E-07 BR85 2.83E 12 2.83E-12 4.01E-09 I131 2.50E-06 2.50E-06 3.54E-03 I132 2.42E-07 2.42E-07 3.42E-04 1133 1.38E-06 1.38E-06 1.95E-03 I134 7.73E-09 7.73E-09 1.09E-05 1135 2.37E-07 2.37E-07 3.36E-04 RB88 1.11E-08 1.11E-08 1.58E-05 SR89 3.65E-09 3.65E-09 5.17E-06 g Sh90 1.07E-10 1.07E-10 1.52E-07 SR91 1.17E-09 1.17E-09 1.65E-06 Y90 1.57E-10 1.57E-10 2.22E-07 Y91M 7.50E-10 7.50E-10 1.06E-06 Y93 2.46E-10 2.46E-10 3.48E-07 ZR95 6.30E-10 6.30E-10 8.93E-07 NB95 5.17E-10 5.17E-10 7.32E-07 M099 3 .22E-06 3.22E-06 ~.56E-03 TC99M 3.06E-06 3.06E-06  %.33E-03 RU103 4.67E-10 4.67E-10 6.61E-07 RU106 1.07E-10 1.07E-10 1.51E-07 RH103M 4.58E-10 4.58E-10 6.49E-07 RH106 1.07E-10 1.07E-10 1.51E-07 TE125M 3.04E-10 3.04E-10 4.30E-07 TF127M 2.96E-09 2.56E-09 4.19E-06 TE127 3.94E-09 3.94E-09 5.58E-06 TE129M 1.45E-08 1.45E-08 2.05E-05 TE129 9.44E-09 9.44E-09 1.34E-05 TE131M 1.19E-08 1.19E-08 1.69E-05 TE131 2.22E-09 2.22E-09 3.15E-06 TE132 2.04E-07 2.04E-07 2.89E-04 CS134 2.67E-07 2.67E-07 3.78E-04 CS136 1.27E-07 1.27E-07 1.80E-04 CS137 1.92E-07 1.92E-07 2.72E-04 BA137M 1.79E-07 1.79E-07 2.54E-04 BA140 2.15E-09 2.15E-09 3.04E-06 LA140 1.89E-09 1.89E-09 2.68E-06 CE141 7.22E-10 7.22E-10 1.02E-06 CE143 2.02E-10 2.02E-10 2.87E-07 W-3S 1 of 2 . Amendment 17 boI L,u 9/30/75

SWESSAR-P1 TABLE 11.2-22 (CONT) Discharge Rate Initial Activity After From Waste Activity Treatment Disposal System Nuclide (uCi/qm) JuCi/qm) (Ci/yr) CE144 3.51E-10 3.51E-10 4.98E-07 I PR143 4.90E-10 4.90E-10 6.94E-07 PR144 3.52E-10 3.52E-10 4.98E-07 NP239 8.04E-09 8.04E-09 1.14E-05 CR51 1.94E-08 1.94E-08 2.75E-05 MN54 3.31E-09 3.31E-09 4.68E-06 U FESS 1.71E-08 1.71E-08 2.42E-05 FES9 1.04E-08 1.04E-08 1.48E-05 C058 1.68E-07 1.68E-07 2.38E-04 CO60 2.14E-08 2.14 E-08 3. 03E-05 TOTAL 1.19E-05 1.19E-05 1.69E-02 ('O u- TU ', ii W-3S 2 of 2 Amendmant 17 9/30/75

SWESSAR-P1 TABLE 11.2-23 ACTIVITY FROM SPENT RESIN FLUSH (EXPECTED CASE) Decontamination Foctor of Waste Disposal System r his Source = 1.00E 04 DecTy time in Waste Disposal System (Hours) = 2.00E 01 Flow '< ate (gal /YR) = 2.30E 04 Initial Activity After Discharge Rate Activity Treatment From Waste Disposal II Nuclide (uCi/qm) (uCi/qm) System (Ci/yr) CRS1 7.14T -02 6.99E-06 6.03E-04 MN54 2.69E-02 2.68E-06 2.32E-04 FESS 1.48E-01 1.48E-05 1.28E-03 FES9 5.13E-02 5.07E-0 6 4.37E-04 C058 1.01E 00 1.01E-04 8.67E-03 CO60 1.88E-01 1.88E-05 1.62E-03 TOTAL 1.50E 00 1.49E-04 1.28E-02 W-3S 1 of 1 Amendment 17 Uu s b ; c, 9/30/75

SWESSAR-P1 TABLE 11.2-24 ACTIVITY FROM LABORATORY WASTES (EXPECTED CASE) I Decontamination Factor of Waste Disposal System For this Source = 1.00E 04 Decay Time in Waste Disposal System (Hours) = 2.00E 01 Flow Rate (gal /yr ) = 4.00E 04 Discharge kate Initial Activity After From Waste Activity Treatment Disposal System Nuclide (uCi/qm) (uCi/qm) (Ci/yr) BR83 5 .13E-05 1.59E-11 2.38E-09 BR84 2.79E-05 1.22E-20 1.82E-18 BR85 3.22E-06 1.20E-53 1.79E-51 1131 2.02E-03 2.62E-07 3.93E-05 I132 1.67 E-0 3 2.46E-08 3.68E-06 I133 4.01E-03 2.06E-07 3.08E-05 1134 5.04E-04 6.24E-15 9.35E-13 I135 2.02E-03 2.53E-08 3.80E-06 RB88 2.15E-03 8.42E-28 1.26E-25 SR89 3.65E-06 3.61E-10 5. 40 E-0 8 SR90 1.04E-07 1.04E-11 1.56E-09 SR91 6 .8 8E-06 1.64E-10 2. 46 E-08 Y90 1.78E-07 1.64E-11 2. 46E-09 11 Y91M 4 .08E-06 1.06E-10 1.59E-08 Y93 1.37E-06 3.53E-11 5.29E-0 9 ZR95 6 .26 E-07 6.20E-11 9.30 E-09 NB95 5.22E-07 5.13E-11 7.69E-09 MO99 4 .71E-03 3.82E-07 5.73E-05 TC99M 4.04E-03 3.65E-07 5.46E-05 RU103 4.69E-07 4.62E-11 6.92E-09 RU106 1.04E-07 1.04E-11 1.56E-09 RH103M 4.8 2E-07 4.53E-11 6.79E-09 PH106 1.07E-07 1.04E-11 1.56E-09 TE125M 3.02E-07 2.99E-11 4.48E-09 TE127M 2 .92E-0 6 2.90E-10 4 .34 E-08 TE127 9.01E-06 4.26E-10 6.39E-08 TE129M 1.46E-05 1.44E-09 2.15E-07 TE129 1.72E-05 9.22E-10 1.38E-07 TE131M 2.63E-05 1.66E-09 2.48E-07 TE131 1.18E-05 3.03E-10 4.53E-08 TE132 2.83E-04 2.37E-08 3 .54 E-0 6 CS134 2.60E-04 2.60E-08 3.90E-06 CS136 1.36E-04 1.30E-08 1. 95E-06 CS137 1.87E-04 1.87E-08 2.80E-06 BA137M 1.72E-04 1.75E-08 2. 62E-06 BA140 2.30E-06 2.20E-10 3.30E-08 LA140 1.57E-0 6 1.77E-10 2 . 65E-08 CE '. 41 7 .30E-07 7.17E-11 1.07E-08 CE143 4.20E-07 2.76E-11 4 .14E-0 9 W-3S 1 of 2 gg Amendment 17 U i , '/ L., .;J 9/30/75

SNESSAR-P1 TABLE 11.2-24 (Cob"r) Discharge Rate Initial Activity After Frcxn Waste Activity Treatment Disposal System (uCi/gm) (uCi/gm) (Ci/yr) Nuc116 _ 3.44E-07 3.43E-11 5.15E-09 CE144 7.49E-09 PR143 5.22E-07 5.00E-11 3.54E-07 3.43E-11 5.15E-09 PR144 1.47E-07 NP239 1.26E-05 9.84E-10 1.98E-05 1.94E-09 2.90E-07 CRS1 4.84E-08 MN54 3.24E-06 3.23E-10 1.67E-05 1.67E-09 2.50E-07 17 FE55 1.54E-07 FES9 1.04E-05 1.03E-09 1.o7E-04 1.65E-08 2.48E-06 CO58 3.13E-07 Cob 0 2.09E-05 2.09E-09 2.28E-02 1.40E-06 2.09E-Oi Total 2 of 2 Amendment 17 W-3S 9/30/75

                                 '/  L. i

SWESSAR-P1 TABLE 11.2-25 ACTIVITY FROM PROCESSED PRIMARY COOLANT SYSTEM LEAKAGE (EXPECTED CASE) Decontamination Factor of Waste Disposal System for this Source = 1.00E 04 Decay Time in Waste Disposal System (Hours) = 2.00E 01 Flow Rate (gal /yr) = 1.76E 04 Discharge Rate Initial Activity After From Waste Activity Treatment Disposal System Nuclide (uCi/qm) (uCi/qm) (Ci/yr) BR83 2. 37E-0 5 7.35E-12 4.84E-10 BR84 2.85E-06 1.24E-21 8.18E-20 BR85 3.10E-08 1.15E-55 7.59E-54 1131 9.73E-02 9.06E-06 5.97E-04 I132 4.98E-03 3.89E-07 2.56E-05 1133 1.61E-02 8.25E-07 5.43E-05 1134 c.47E-05 1.05E-15 6.90E-14 I135 2.60E-03 3.28E-08 2.15E-06 RBS8 1. 30 E-0 4 5.10E-29 3.36E-27 SR89 3.07E-04 3.03E-08 2.00E-06 17 SR90 1.07E-05 1.07E-09 7.04E-08 SR91 1.37E-05 3.26E-10 2.15E-08 Y90 1.17E-05 1.15E-09 7.55E-08 Y91M 8.78E-06 2.11E-10 1.39E-08 Y93 2. 8 8 E-0 6 7.40E-11 4.87E-09 ZR95 5.50E-05 5.46E-09 3.59E-07 NB95 4.04E-05 3.97E-09 2.61E-07 MO99 6.44E-02 5. 23E-0 6 3.44E-04 TC99M 6.17E-02 5.0FE-06 3.33E-04 RU103 3.75E-05 3.69E-09 2.43E-07 RU106 1.04E-05 1.04E-09 6.84E-08 RH 103M 3. 6 8E-05 3.62E-09 2.38E-07 RH106 1. 04 E-0 5 1.04E-09 6.84E-08 TE 125M 2.61E-05 2.58E-09 1.70E-07 TE127M 2.72E-04 2.71E-08 1.78E-06 TE127 2.83E-04 2.72E-08 1. 79E-06 TE129M 1.12E-03 1.10E-07 7.27E-06 TE129 7.22E-04 7.08E-08 4.66E-06 TE131M 1.62E-04 1.02E-08 6.73E-07 TE 131 3.02E-05 1. 87E-09

• 1.23E-07 TE132 4 . 51 E-03 3.77E-07 2.48E-05 CS134 2.63E-02 2. 6 3E-06 1.73E-04 CS136 7.15E-03 6.86E-6, 4.51E-05 CS137 1.92E-02 1. 92E-0 6 1.26E-04 BA137M 1.79E-02 1.79E-06 1.18 E-0 4 BA14C 1.17E-04 1.12E-08 7.34E-07 LA140 1.25E-0 4 1.22E-08 8.03E-07

                                            /    ta      G W-3S                             1 of 2                         Amendment 17 9/30/75

SWESSAR-P1 TABLE 11.2-25 (CONT) Discharge Ratt- , Initial Activity T.fter Prom Waste Activity Treatment Disposal System Nuclide (uCi/Gm) , (uCi/qm) (Ci/yr) CE141 5.53E-05 5.44E-09 3.58E-07 CE143 2.85E-06 1.87E-10 1.23E-08 CE 144 3.40E-05 3.40E-09 2.24E-07 PR143 2.74E-05 2.62E-09 1.73E-07 PR144 3.40E-05 3.40E-09 2.24E-07 NP239 1.46E-04 1.14E-08 7.51E-07 CR51 1.43E-03 1.40E-07 9.22E-06 g MN54 3.21E-0 4 3.21E-08 2.11E-06 FESS 1.69E-03 1.69E-07 1.11E-05 FES9 8.57E-04 8 . 4 6E =-0 8 5.57E-06 CO58 1.48E-02 1.47E-06 9.69E-05 CO60 2.13E-03 2.13E-07 1.40E-05 Total 3.47E-01 3.05E-05 2.01E-03 W-3S 2 of 2 Amendment 17 bu7 u,v 9/30/75

SWESSAR-P1 TABLE 11.2-26 I ACTIVITY PROM UNPROCESSED PRIMARY COOLANT SYSTEM LEAKAGE (EXPECTED CASE) Decontamination factor of waste disposal system for this sourcs = 1.00E 00 Decay time in waste disposal system (hours) = 1.00E 01 Flow rate (gal /yr) =

1. 7 6 E 01 Discharge Rate Initial Activity After From Waste Activity Treatment Disposal System Nuclide _(uCi/qm) (uCi/qm) (Ci/yr)

BR83 2.37E-05 1.32E-06 8.70E-08 BR84 2. 85E-06 5.95E-12 3.92E-13 BR85 3.10E-0 8 1.15E-51 7.59E-53 I131 9.73E-02 9.34E-02 6.18E-0 3 1132 4. 98E-03 4 .26E-0 3 2.81E-04 1133 1.61E-02 1.15E-02 7.58E-04 I134 8. 47E-0 5 2.98E-08 1.96E-09 I135 2.60E-03 9.21E-04 6.06E-05 RB88 1. 30E-04 8.15E-15 5.36E-16 SR89 3.07E-04 3.05E-04 2.01E-05 U SR90 1. 07E-0 5  ? 07E-Oh 7.04E-07 SR91 1.37E-05 6.68E-05 4.40E-07 Y90 1.17E-05 1.16E-0 5 7.61E-07 Y91M 8.78E-06 4 .3 2E-0 6 2.84E-07 Y93 2. 88E-0 6 1.46E-06 9.61E-08 ZR95 5. 50 E-05 5 . 4 8E-0 5 3.61E-06 NB95 4.04E-05 4.00E-05 2.64E-06 MO99 6. 44E-02 5. 81E-02 3.82E-03 TC99M 6.17E-02 5.59E-02 3.68E-03 RU103 3.75E-05 3.72E-05 2.45E-06 RU106 1. 04 E-05 1.04E-05 6.84E-07 RH103M 3.68E-05 3.65E-05 2.4 0E-0 6 RH106 1. 04 E-05 1.04E-05 6.84E-07 TE125M 2.61E-05 2.59E-05 1.71E-0 6 TE127M 2.72E-04 2.71E-04 1.79E-05 TE127 2.83E-04 2.76E-04 1.82E-05 TE129M 1.12E-03 1.11E-03 7.33E-05 TE129 7. 22E-04 7.14E-04 4.70E-05 TE131M 1. 62E-0 4 1.29E-On 8 . 4 8E-0 6 TE131 3.02E-05 2.35E-05 1.55E-06 TE132 4.51E-03 4 .12E-0 3 2.71E-04 CS134 2.63E-02 2.63E-02 1.73E-03 CS136 7.15E-03 7.00E-02 4.61E-04 CS137 1.92E-02 1.92E-02 1.26E-03 BA137M 1.79E-02 1.79E-02 1.18E-03 BA140 1.17E-04 1.14E-04 7.51E-06 LA140 1. 25E-0 4 1.24E-04 8.15E-06 W-3S 1 of 2 / i I: Amendment 17 9/30/75

SWESSAR-91 TABLE 11.2-26 (COtTr) Discharge Rate Initial Activity Af ter From Waste Activity Treatment Disposal System Nuclide '(u Ci/qm) (uCi/qm) (Ci/yr) CE141 5. 53E-0 5 5.49E-05 3.61E-06 CE143 2.85E-06 2.31E-08 1.52E-07 CE144 3.40E-05 3.40E-05 2.24E-06 PR143 2.74E-05 2.68E-05 1.77E-06 PR144 3. 40E-05 3.40E-05 2.24E-06 NP239 1.48E-04 1.29E-04 8.49E-06 CRS1 1.43E-03 1.41E-03 9.31E-05 MN54 3.21E-04 3.21E-04 2.11E-05 FESS 1.69E-03 1.69E-03 1.11E-04 l FES9 8.57E-04 8.51E-04 5.60E-05 C058 1. 48 E-02 1.48E-02 9.73E-04 C060 2.13E-03 2.13E-03 1.40E-04 TOTAL 3. 47E-01 3.24E-01 2.13E-02 W-3S 2 of 2 I; ' / b,b Amendment 17 9/30/75

SWESSAR-P1 TABLE 11.2-27 ACTIVITY FROM 'IURBINE PLANT SAMPLING SINKS (EXPECTED CASE } l Decontamination factor of waste disposal system for this source'= 1.00E 00 Decay time in waste disposal system (hours) = 2.00E 01 Flow rate (gal /yr) = 3.00E 04 Discharge Rate Initial Activity After From Waste Activity Treatment Disposal System Nuclide (uCi/qm) (uCi/qm) (Ci/yr) BR83 1.21E-09 3.75E-16 4.21E-14 BR84 2.53E-10 1.10E-25 1.24E-23 BR85 3.18E-12 1.18E-59 1.33E-57 1131 1.20E-07 1.12E-11 1.2SE-09 I132 8.76E-08 4.68E-13 5.25E-11 I133 1.53E-07 7.86E-12 8.81E-10 I134 6.49E-10 8.03E-21 9.01E-19 1135 6. 53E-0 8 8.20E-13 9.19E-11 RB88 2.71E-09 1.06E-33 1.19E-31 SR89 7.81E-11 7.72E-15 8.66E-13 SR90 1.91E-12 1.9 ?E-16 2.14E-14 g SR91 1.18E-10 2.81E-15 3.16L-13 Y90 5.49E-12 4.79E-16 5.37E-14 Y91M 7.38E-11 1.82E-15 2.04E-13' Y93 2.31E-11 5.93E-16 6.65E-14 ZR95 1.36E-11 1.35E-15 1.51E-13 NB95 1.18E-11 1.16E-15 1.30E-13 MO99 1.09E-07 8.85E-12 9.93E-10 TC99M 2.92E-07 1.04E-11 1.17E-09 RU103 1.18E-11 1.16E-15 1.30F-13 RU106 1.91E-12 1.91E-16 2.14E-14 RH103M 7. 25E-11 1.14E-15 1.2AE-13 RH106 1.41E-11 1.91E-16 2.1,E-14 TE125M 7.79E-12 7.71E-16 8.65E-14 TE127M 7.71E-11 7.67E-15 8.60E-13 TE127 3.02E-10 1.27E-14 1.43E-12 TE129M 3.95E-10 3.98E-14 4.36E-12 TE129 2.35E-09 2.49E-14 2.79E-12 TE131M 7.14E-10 4.50E-14 5.04E-12 TE131 1. 32E-0 9 8.21E-15 9.21E-13 TE132 5.21E-09 4.36E-13 4.89E-11 CS134 7. 03E-09 7. 0 2E-13 7.88E-11 CS136 3.82E-09 3.66E-13 4.11E-11 CS137 4.68E-01 4.68E-13 5.25E-11 BA137M 2. 80E-( . , 4.38E-13 4.91E-11 BA140 6.27E-1 s 5.99E-15 6.72E-13 LA140 6.38E-11 6.31E-15 7.07E-13 CE141 J.78E-11 1.75E-15 1.96E-13 W-3S 1 of 2 ( n  ; Amendment 17 I: ' ') 9/3G/75

SWESSAR-"1 TABLE 11.2-27 (Coltr) Discharge Rate lnitial Activity After From Waste Activity Treatment Disposal System & 'lide (uci/qm) (uci/qm) (Ci/yr) CE143 6.87E-12 4.51E-16 5.06E-14 CE144 7.66E-12 7.64E-16 b ~.-14 PR143 1.25E-11 1.20E-15 1.34E-13 PR144 5.37E-11 7.64E-16 8.57E-14 NP239 2.85E-11 2.23E-15 2.50E-13 CRS1 3.98E-10 3.90E-14 4.37E-12 MN54 7.65E-11 7.64E-15 8.56E-13 0 FESS 3.82E-10 3.82E-14 4.28E-12 FES9 1.96E-10 1.94E -14 2.17E-12 C058 3.88E-09 3 . 8 5E-- 13 4.32E-11 CO60 5.72E-10 5.72E-14 6.41E-12 TOTAL 8.92E-07 4.27F-11 4.79E-09 W-3S 2 of 2 _ Amendment 17

                                       , i ' ,_ [)          9/30/75

SWESSAR-P1 TABLE 11.2-28 ACTIVITY FROM TURBINE BULDING SUMPS (EXPECTED CASE) Decontamination Factor of Waste Disposal System For this Source = 1.00E 00 Decay Time in , Waste Disposal System (Hours) = 0.0 Flow Rate = 1.30E 05 Discharge Rate Initial Activity After From Waste Activity Treatment Disposal System (uCi/gml (uCi/qm) (Ci/yr) Nuclide_ BR83 1.21E-09 1.21E-09 5.88E-07 BR84 2.53E-10 2.53E-10 1.23E-07 BR85 3.18E-12 3.18E-12 1.54E-09 I131 1.20E-07 1.20E-07 5.83E-05 I132 8.76E-08 8.76E-08 4.26E-05 1133 1.53E-07 1. 53E-07 7.4 3E-0 5 I134 6.49E-10 6.49E-10 3.15E-07 I135 6.53E-08 6 .53E-0 8 3.17E-05 RB88 2.71E-09 2.71E-09 1.32E-06 SR89 7.81E-11 7.81E-11 3.79E-08 SRSO 1.91E-12 1.91E-12 9.28E-10 SR91 1.18E-10 1.18E-10 5.73E-08 Y90 5.49E-12 5.49E-12 2.67E-09 g Y91M 7.38E-11 7.38E-11 3.59E-0 8 Y93 2.31E-11 2.31E-11 1.12E-0 8 ER95 1.36E-11 1.;6E-11 6 . 61E-0 9 NB95 1.18E-11 1.18E-1t 5.73E-09 MO99 1.09E-07 1.09E-0 7 5. 29E-0 5 TC99M 2.92E-07 2.92E-07 1.42E-0 4 RU103 1.18E-11 1.18E-11 5.73E-09 RD106 1.91E-12 1.91E-12 9.28E-10 RH103M 7.25E-11 7. 25E -11 3.52E-08 RH106 1.41E-11 1.41E-11 6.85E-09 TE125M 7.79E-12 7.79E-12 3.78E-09 TE127M 7.71E-11 7.71E-11 3.75E-08 TE127 3.02E-10 3 . 02E-10 1.47E-07 TE129M 3.95E-10 3.95E-10 1.92E-07 TE129 2.35E-09 2. 35E-0 9 1.14E-0 6 TE131M 7.14E-10 7.14E-10 3.47E-07 TE131 1.32E-09 1.32E-09 6.41E-07 TE132 5.21E-09 5.21E-0 9 2.53E-06 CS134 7.03E-09 7. 03E-0 9 3.42E-06 CS136 3. 82 E-0 9 3 . 82E-0 9 1. 8 6E-0 6 CS137 4.68E-09 4. 68 E-0 9 2.27E-06 BA137M 2.80E-08 2. 80E-0 8 1.36E-05 BA140 6.27E-11 6.27E-11 3.05E-08 LAn0 6.38E-11 6.38E-11 3.10E-08 CE141 1.78E-11 1.78E-11 8.65E-09 CE143 6.87E-12 6.87E-12 3. 34 E-0 9 W-3S 1 of 2 . _ , , . Amendment 17 h ,1 S b_,i 9/30/75

FWESSAR-P1 TABLE 11.2-28 (CONT ) Discharge Rate Initial Activity After From Water Activity Treatment Disposal System Nuclide (uCi/qm) (uCi/qm) (C1/yr) CE144 7.66E-12 7.66E-12 3.72E-0 9 PR143 1.25E-11 1.25E-11 6.07E-09 PR144 a.37E-11 5.37E-11 2. 61E-0 8 NP239 2.85E-11 2.85E-11 1.38E-08 CRS1 3.98E-10 3.98E-10 1.93E-07 MN54 7.65E-11 7.65E-11 3.72E-08 g FESS 3.82E-10 3.82E-10 1.86E-07 FE59 1.96E-10 1.96E-10 9.52E-08 C058 3.88E-09 3. 8 8E-0 9 1. 8 8E-0 5 CO60 5.72E-10 5.72E-10 2.78E-07 TOTAL 8. 92 E-07 8.92E-07 4.33E-04 1 W-3S 2 of 2 Amendment 17 (' I' ['] 2 9/30/75

SWESSAR-P1 TABLE 11.2-29 ACTIVITY FROM CHEMICAL REGENERATIVE WASTE (EXPECTED CASE) Dec 4

      .4mination Factor of Waste Disposal System for this Source =                                         1.00E On Decay Time in Waste Di-~osal System (Hours) =              2.00E 01 Flow Rate (gal /yr)     =                                  1.60E 06 Discharge Rate Initial       Activity Af ter           From Waste Activity          Treatrcist         Disposal System Nuclide         (uCi/gmL           (uCi /

gm ) (uCi/yr *, BR83 5.24E-08 1.62E-14 9.73E-11 BR84 2.42E-09 1.06E-24 6.33E-21 BR85 2.87E-12 1.07E-59 6.39E-56 I131 3.87E-04 3.60E-08 2.16E-04 1132 1.72E-05 1.17E-09 7.00E-06 1133 5.74E-05 2.95E-09 1.7 7E-0 5 1134 1.02E-08 1.26E-19 7.57E-16 1135 7.87E-06 9.88E-11 5.92E-07 RB88 2.68E-08 1.05E-32 6.31E-29 SR89 1.13 E-06 1.12E-10 6.7 2E-07 SR90 3.37E-08 3.37E-12 2. 02E-08 SR91 3.34E-03 7.96E-13 4.77E-09 C Y90 3.96E-08 3.84E-12 2.30E-08 Y91M 2.19E-08 5.15E-13 3.08E-09 Y93 8.44E-09 2.17E-13 1.30E-09 ZR95 1. 88 E-0 7 1.87E-11 1.12E-07 NB95 1.58E-07 1.55E-11 9. 31E-0 8 M399 2.19 E-0 4 1.78F-08 1.07E-04 TC19M 2.44E-04 1.75E 08 1.05E-04 RU103 1.30E-07 1.28E-11 7. 65E-0 8 RU106 3.28E-08 3.28E-12 1.96E-08 RH103M 1. 2 9 E-0 7 1.2SE-11 7. 50E-08 RH106 3. 2 8 E-0 8 3.28E-12 1. 9 6E-0 8 TE125M 8.05E-08 7.97E-12 4.77E-08 TE127M 8.62E-07 8.57E-11 5.14E-07 TE127 9.29E-07 8. 69E- 11 5.21E-07 TE129M 4.27E-06 4.20E-10 2.52E-06 TE129 2.81E-06 2.69E-10 1.61E-06 TE131M 5.78E-07 3.64E-11 2.18E-07 TE131 1.24E-07 6.65E-12 3.98E-08 TE132 1.35E-05 1.13E-09 6.79E-06 CS134 1.13E-04 1.12E-08 6.74E-05 CS136 3.07E-05 2.94E-09 1.76E-05 CS137 7.76E-05 7.76E-09 4.65E-05 BA137M 7.26E-05 7.26E-09 4.35E-05 BA140 4.39E-07 4.19E-11 2.51E-07 LA140 5. 0 8 E-07 4.85E-11 2.91E-07 CE141 1.86E-07 1.82E-11 1.09E-07 W-3S 1 of 2 - , - Amendment 17 L , , 9/30/75

SWESSAR-P1 TABLE 11.2-29 (CONT) Discharge Rate Initical Activity After From Waste Activity Treatment Disposal System Nuclide (uCi/gmL (uCi/gm) (uCi/yr) o CE143 8'.10 E-0 9 5.32E-13 3.19E-09 I CE144 1.31E-07 1.30E-11 7.81E-0 8 PR143 9.04E-08 8.67E-12 5.19E-08 PR144 1.31E-07 1.30E-11 7. 81E-0 8 NP239 5.04 E-0 8 3.94E-12 2.36E-08 CRS1 4.66E-06 4.57E-10 2.74E-06 g MN54 1.31E-06 1.31E-10 7.8 3E-07 FESS 5.86E-06 5.86E-10 3.51E-06 FES9 2.78E-06 2.74E-10 1. 6 4 E-0 6 0058 5.22E-05 5.18E-09 3.10E-05 CO60 8.01E-06 8.01E-10 4 . 8 0E-0 6 Total 1.33E-03 1.15E-07 6. 87E-0 4 W-3S 2 of 2 ,., Amendment 17 b c '/ I;u 9/30/75

SWESSAR-P1 TABLE 11.2-30 ACTIVITY FROM LAUNDRY DRAINS (FXPECTED CASE) Decontamination Factor Of Waste Disposal System For This Source = 1.00E 00 Decay Time In Waste Disposal System (Hours) = 0.0 Flow Rate (gal /yr) = 2.00E 05 Initial Activity After Discharge hate Activity Treatment Prea Waste Disposal Nuclide (uCi/cm) (uCi/gm) SL7 tem _( Ci/vr) BR83 3.47E-08 3.47E-08 2.60E-05 BR84 1.89E-08 1.89E-08 1.41E-05 BR85 2.18E-0 9 2.18E-09 1.63E-06 I131 1.91E-06 1.91E-06 1.43E-03 I132 7.26E-07 7.26E-07 5.44L-04 1133 2.71E-06 2.71E-06 2.03E-03 1134 3.41E-07 3.41E-07 2.56E-04 1135 1.37E-06 1.37E-0 6 1.02E-03 RB88 1.45E-06 1.4 5E-0 6 1.09E-03 SR89 2.47E-09 2.47E-09 1.85E-06 SR90 7.06E-11 7.06E-11 5.29E-08 SR91 4.66E-09 4.66E-09 3.49E-06 Y90 1.21E-10 1.21E-10 9.05E-08 17 Y91M 2. 76E-0 9 2.76E-09 2.07E-06 Y93 9.31E-10 9.31E-10 6.97E-07 ZR95 4.24E-10 4.24E-10 3 .17E-07 NB95 3.53E-10 3.53E-10 2.65E-07 MO99 3.19E-0 6 3.19E-06 2. 39E-0 3 TC99M 2. 73E-0 6 2.73E-0 6 2.05E-C' RU103 3.17E-10 3.17E-10 2 .38 E-07 RU108 7.06E-11 7.06E-11 5.29E-08 RH103M 3.26E-10 3.26E-10 2. 4 4E-07 RH106 7.26E-11 7.26E-11 5.44E-08 TE125M 2.05E-10 2.05E-10 1.53E-07 TE127M 1.97E-09 1.97E-0 9 1.48E-06 TE127 6.10E-09 6.10E-09 4.57E-06 TL129M 9.90E-09 9.9 0E-09 7.4 2 E-0 6 TE129 1.16E-O b 1.16E-08 8.70E-06 TE131M 1.79E-08 1.78 E-0 8 1. 33 E-05 TE131 7.99E-09 7.99E-09 5.98E-06 TE132 1.91E-07 1.91E-07 1.43E-04 CS134 1.76E-07 1.76E-07 1.32E-04 CS1J6 9.17E-08 9.17E-0 8 6.87E-05 CS137 1. 27E-07 1.27E-07 9.49E-05 BA137M 1.16E-07 1.16E-07 8 .70E-0 5 BA140 1.56E-09 1.56E-09 1.17E-06 LA140 1. 06E-09 1. 0 6E-09 7.96E-07 CE141 4.94E-10 4.94E-10 3.70E-07 CE143 2.84E-10 2.84E-10 2.13E-07 CE144 2.33E-10 2.33E-10 1.75E-07 W-3S 1 of 2 'O , - Amendment 17 J' ' L'J 9/30/75

SWESSAR-P1 TABLE 11.2-30 (CONT) Initial Activity After Discharge kata Activity Treatment Prom Waste Di_?osal Nuclide (uCi/cm) (uCi/qm) System _( C1/yr) PR143 3.53E-10 3.53E-10 2.65E-07 PR144 2.40E-10 2.40E-10 1.79E-07 NP239 8. 51E-0 9 8.51E-09 6.35E-06 CRS1 1. 34 E-0 8 1.34E-08 1.00E-05 MN54 2.19E-0 9 2.19E-09 1.64E-06 FESS 1.13E-08 1.13E-08 8.45E-06 FE59 7.06E-09 7.06E-09 5.2 9E-0 6 U C058 1.13E-07 1.13E-07 8.45E-05 CO60 1.41E-08 1.41E-0 8 1.06E-05 TOTAL 1. 54 E-05 1.54E-05 1.16E-02 W-3S 2 of 2 i Amendmant 17 _ , , - t 9/30/75 2-

SWESSAR-P1 TABLE 11.2-31 TOTAL ACTIVITY TROM RADIOACTIVE LIQUID WASTE SYSTEM WITH STEAM GENERATOR LEAKAGE (EXPECTED CASE) Calculated Total bischarge Flow Rate (gpm) = 4.60 Actual Actual Activity Discharge Rate Nuclide (uCi/qm) (Ci/yr) BR83 3.26E-09 2.98E-05 BR84 1.60E-09 1.46E-05 BR85 1.79E-10 1.64E-06 I131 1.35E-06 1.24E-02 1132 1.40E -07 1.27E-03 I133 5.65E-07 5.16E-03 I134 2.92E-08 2.67E-04 I135 1.53E-07 1.49E-03 RB88 1.21E-07 1.10E-03 SR89 3.32E-09 3.03E-05 SR90 1.11E-10 1.01E-06 SR91 6.44E-10 5.88E-06 Y90 1.31E-10 1,. S-06 Y91M 3.95E-10 3.c. B-06 Y93 1.32E-10 1.20E-06 17 ZR95 5.90E-30 5.38E-06 NB95 4.45E-10 4.07E-06 MO99 1.29E-06 1.18E-02 'IC99M 1.22E-06 1.11E-02 RU103 4.09E-10 3.74E-0 6 RU106 1.09E-10 9.92E-07 RH103M 4.06E-10 3.71E-06 RH106 1.10E-10 1.00E-06 TE125M 2.80E-10 2.55E-0 6 TE127M 2.08E-09 2.63E-05 TE127 3.43E-09 3.14E-05 TE129M 1.24E-08 1.13E-04 TE129 8.51E-09 7.77E-05 TE131M 4 . 61E-0 9 4.21E-05 TE131 1.30E-09 1.19E-05 TE132 8.42E-08 7.69E-0 4 CS134 2.77E-07 2.52E-03 CS136 8.67E-08 7.92E-04 CS137 2.01E-07 1.83E-03 BA137h 1.89E-07 1.72E-03 BA140 1.43E-09 1.30E-05 LA140 1. 42 E-0 9 1.30E-05 CE141 6.11E-10 5.58E-06 CE143 ~7.74E-11 ' . 06E-07 CE144 3.56E-10 3.27E-06 PR143 3.31E-10 3.02E-06 W-3S 1 of 2 ' ' ' Amendment 17 9/30/75

SWESSAR-P1 TABLE 11.2-31 (CONT ) Actual Actual Activity Discharge Rate Nuclide (uCi/qm) (Ci/yr) PR144 . 3.61E-10 3.29E-06 NP239 3.10E-09 2.83E-05 CRS1 8.27E-08 7. 55E-0 4 MN54 2.93E-08 2.67E-04 FESS 1.61E-07 1.47E-03 FE59 5.78E-08 5.28E-04 n CO58 1.12E-06 1.30E-02 0060 2.04E-07 1.86E-03 H3 1.6*E-01 1.47E 03 TOTAL 1.61E-01 1.47E 03 TOTAL (NON-TRITIUFO 7.43E-06 6.78E-02

                                      /      .
                                         /

{j g_ (; W-3S 2 of 4 Amendment 17 9/30/75

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SWESSAR-P1 TABLE 11.2-37 LIQUID WASTE DAILY INPUT FLOWS Source Average Maximum gal / day cal / day High Level Waste Drain Tanks Samples

• 90 200 Reactor plant lectage 48.2 150 to sumps
• Spent resin flush 40 2,000 Laboratory wastes
• 110 500 Decontamination drains
• 52 650 'g Boron recovery tanks 0.e 25,000 Regenerant Chemical Evaporator Regeneration Chemicale *
• 3,700 48,000 Low Level Waste Drain Tanks Reactor plant leakage .05 .15 to sumps
• Turbine plant leakage 0 5,000 to sumps Boron recovery test 0 4,000 tanks Contaminated Laundry Waste Drain Tanks Laundry 550 2,000 Direct Discharge through liquid radioactive waste monitor f rom boron recovery test tanks af ter sampling 350 12,000
• Liquids from these sources can enter the radioactive liquid waste system from the aerat< ' vent and drain system. Due to the manner in which these liquids are collected, an 1 of 2 bv'/ V" Amendment 9 4/30/75

SWESSAR-P1 TABLE 11.2-37 (CONT) additional amount of originally nonradioactively contaminated liquid is also collected and mixed with these liquids. It is estimated that, on the average, an additional 1,650 cal / day enter both the high and low level waste drain tanks by this route. A maximum flow is estimated at 5,000 gal / day for each subsystem (high and low level waste) .

• • The regenerant chemical waste normally is f ed directly to the regenerant chemical evaporator. The storage tanks for this evaporator are located within the condensate polishing 1 system.

                                         /

• Uu/ U /d 2 of 2 Amendment 7 2/28/75

SWESSAR-P1 TABLE 11.2-38 TANK OVEhPIDW PFOTEC'rIO!; Figure Level Monit oring Monitoring or Overflow Pr oces s i ng Ta n k s No. and Ala'ms Alarm Location Provisions of Overtlow Bef ueling Water 6.2.2-1A Indicat or MCB Located in Transferred to Storage Tank I'iqh MCB diked area PLWS Ixw MCL Low-Iow-1 MCB I4w - 14w - 2 MCB Feactor Plant 9.2.2-1A I?iqh MCB Overflows Aerated drains t ransf erred Comp sient Cooling B Iow MCB to annulus t o RIMS Wat er Sur ge a C@ buildirq sump anks Reactor Plant 9.2.2-1A hmi t or ed by By surge Over f lows t o In RIXS Camp sient Cooling B surqc- t ank tank building sump Water Chemical C (W) Addition Tanks 1 - Primary Grade 9.2.7-1A Indicator "y gJ MCB Floatinq Lead In RIES Water Storace Tanks liiqh Ixw L. m

                                                                 .)             MCB MCB tank 6 located in diked area
                                                                   -)

prirury Drain 9. 3.1-2 A Indicator . MCB Over f lows t o In RIAS Transter Tank building suzm> >

                                                          -m
  +gboron Recovery          9.3.b-1A       Iruli ca t or         e/             BRP          Over f lows t o In boron recovery Tanks'                            liigh                                BRP          seccmd tank     sy st m Ixw           .
                                                              "J

_o BRP s. L s 7-

       , Doron Test Tanks 9.3.6-1A         Indicator             . ,            BRP          Overf lows t o  In RIAS
                                           !!igh                    a           BRP          building sump leu           .     .au              BRP

• s ,y boron Distillate 9.3.6-1A Ifiah "f- BRP Clc, sed t ank in RIMS Tank Indicator I-. DhP overflow to g'. s' building surp x0 Ca ticzi Fegen- 10.4.6-1B Indicator CPCP Incated in Contents of eration Vessel liigh diked area. sumps are processed Overtlows to in cmdensate polishing area sump syst em and t hen pumped CJ to PIAS for additional s processing s

Anion Pegen- 10.4.6-1B IrC i ca tor CPC' Incot ed in Contents of eration Vessel liigh diked area. sumps are processed overt lows t o in condensate polishing area sump systm anci then pugd 1 of 4 Amendment 7 2/28/75

SWESSAR-P1 TABLE 11.2-38 (Cot."P) Fioure Level Monitoring Moaitoring or Overflow Processing Ta n k s P4 5 and AlarTes A l a riti 14mation Pr ovi si ons of Overflow to RLWS for additional processing i<r sin Mix and 10. 4 . 6- 1 B Indicator CPCP Incated in contents of Storage Vessel liiqh dikal area. sumps are processed Ove rf lows to in condensate polishing area s12mp sfstOm dnd then pum{ d to RIES toi additional processing 1 ecowrn! Acid 10.4 . 6- 1B Indi ca t or CPCP Incated in Contents of Tank liiqh diked area. sumps are processed Ixw overf lows t o in cond-nsate polishing area sump syst m and then pumped to RIMS for additional processing Fecovered 10.4.b-1B Indicator CPCP Incated in Contemts of Caustic Tank liigh diked area. sumps are processed low Overf lows t o in ccr<.;ensat e polishing area sump syst m and then pumped to RIMS for additional processing i Eesin Receiver 10.4.6-1B Irx11 ca tor CPCP Incated in Contents of Unit liig h diked area. sumps are processed Overf Icus to in condeusate polishing D area sump systm and then purrped g to RIMS f or additional processinq x_ hecovered Water 10.4.b-1B Indicator CPCP Incated in contents of Ta rik  !!igh diked area. sumps are processed r.. Im overflows to in condensate polishing ? area sinrip systm and then pumg*M k to RIMS for additional C processing Low (bnduc- 10.4.6-1B Indicator CPCP Incated in Contents of t.'vit y Waste Ifigh diked area. sumps are processed Surg' Tank Im Overflows to in condensate polishing area sump syst m and then pumped to RLWS for additional processino Low Coneuc- 10.4.6-1B Indicator CPCP Incated in Contents of tivity Kaste fligh diked area. sumps are processed 11olding Tank low Overf lows t o in ecmdensate polishing 2 of 4 Amendrient 7 2/28/75

SWESSAR-P1 TALLE 11.2-38 (CONT) F igur e Level Monitoring Monitoring or Overflow Processing Ta n ks tn . and Alarws Alarm Location Provisions of Overflow area sump syst m and t hen pumped to RIBS for additional processing Iligh Conduc- 10.4.6-1B Indicator CPCP 14) cat ed in Contents of tivity Waste liigh diked area. sumps are processed Neutra lizing lew Overflows to in condenrate tuolishing Tank area sump syst m and then pumped to RIMS for additional processing liigh Conduc- 10.4.6-1R 1rulicator CPCP Loc.at ed in Contents of tivity Waste IIiqh dikal area. sumps are processed Storage Tank Ixw Overtlows to in condensate polishing g' area sump syst m and then purped s to RLWS for additional

                    ~#                                                                                    processing r j; 10.4.7-1  Indicator                  MCB         Suroes to this     None, tank is sized

((- f (g; Condensate tank are t reat ed to preclude overflow

                " Storage Tank                  111gh 1xw                                     in the condens-

• ate polishing 7 ,* i. system 111gh Level Waste 11.2- 1A Indicator RWP Overflows to In RIMS Drain Tanks fligh RWP second tank

  -                                             14w                        FWP 1

Wast e Distillate 11.2-1B lliqh RWP Closed tank In RIMS Tank Indicator RWP overflows to building surp Indicator RWP Tank In RINS

        ,    -ina Waste Test Tanks 11.2-1C                                 RWP          in diked area High Ixw                       RWP          overflows to building surp Low level Waste    11.2-1E    Indicator                 RWP          Overf lows t o     In RIMS 1?igh                     RWP          second tank CN       Drain Tanks RWP L ,N Irw Laundry Waste       11.2-1F   Indicator                 RWP          To solid waste     In RIMS Drain Tank

• High RWP & decontamination building surp Laundry haste 11.2-sF Indicator, local None To sol id wa st e In RIMS l 'l liottm Tank
• 6 decontamination building sump 3 of 4 Amendment 7 2/28/75

SWESSAR-P1 TABLE 11.2-38 (CONT) Fic, ar e Level Monitoring Monitoring or Overflow Processing Ta n k s to . and Ala rrns Alarm Incat ion Provisions of Overflow Laundry Waste 11.2-1F fligh RWP '!b solid wast e In RIMS Distillate Test & decont amination Tank

• building surg)

Spent Resin 11.5-1C Indicator WSP Ta solid waste In RIMS Surge Tank  !!igh WSP & decontamination Iow WSP tmilding sump Spent Resin l'. 5-1C Irulica tor WSP Overflows to In RINS liold Tank syent resin surge tank Wast e Sludga 11.5-1C Indicator WSP Overflows to In RIMS Tank liigh solid waste E low decontamination building sump 1 Waste Decant 11.5-1C Indicating WSP Overflow to In RIMS Tank by overflow waste sludge to waste sludge tank tank Evaporator 11.5-1E Indicator WSP Overf lows t o In PIMS lott(ns Tank solid waste and decontamination building sump liRP=Ioron Renwery Panel MCB=Knin Control 1surd INP= Radioactive Waste Panel WS P = Was t e Solidification Panel RIMS = Radioactive Liquid Waste System CPCP=-Condensate Polishing Cantrol Panel 7

• If Applicable CA sO C

C_ 4 of f4 Amendment 7 2/28/75

A MMld-IB [FlG 1l 2 lC l 1 I i I

                                                                                                        ;                                                                   ('

I WASTE l DEMINERALIZER m LLATE M i WASTE TEST TANKS I sASTE DISilLLATE i r C00MR r, _ r1

                                                                              <  r     i s                  ,,

_ y jy' l -

                                                                                                                         ~

6 l sASTE DEElNER&ll?ER Fit'ER Og GrA l o WASTE EVAFORATOR TO O TO PRIMA 9Y GRADE 80TTDMS PUNP RADICACTIVE I O C &

                               $n   _                                                                                                                                r'- EATER SVSTEu
                                                                                                                                    ']

_ _ SOLIO l s ( ' TASTE I IASTE TEST i , SYSTEN yggg pgups

                                                            .. ]                                                               _
                                                                   ~-                                                                                - ~         ~~-                 -~-~-

GENEENT CEMI Al--- I~-~ -- MOMT0@ ~ -- ~l APORATOR CONDENSER I RECnVERY SYSTEM 9 A,, p p llNE 10 DISCHARGE I

                                                 'l iFR0r i
                                                                                                                                              ~ -- ~ ~ ~ ~ ~ - ] FIG.it.2 lf
                                                                                                                                 '                       ~                    ~

EGEkERANT CHEulCAL 9 P ILAUNDRY I ' J D g l\ iSTILLATE TANK i

                                                      ;ggg7g ,

l ORAINS LAUNDRY WASTE I l gy , EVAPORATOR

                                 -T0         1       l                       LAUNDRY IASTE                                               LIQUID WASTE CCNCENSATE                                        ORAIN TANK
                                                                                                             /         \                 EVAPORATOR l

REGENERANT CHEulCAL POLISHING I n CONDENSER DISitLLATE COOLER SYSTEu l l

                                                                  \/

Z, r ' SKID rS Ia ,1, E0VNT 0

                        ]3                   l      l                                                                                  LAUNDRY l                                                    __                  i         D Si l_aiE                                   8AUNDRY WASTE I

l p 'N TEST TANK O DISilLLATE TlSi TAM E I l I Q) LAUPORY EASTE b d p gp l DRAIN PU'IP LAUNDRY Y . TD RADI0 ACTIVE [ REG NERANT CHEEICA[ ' I WASTE 80TT055 LAUNDRY WASTE - SOLIO WASTE SYSTEN I ' EVAPORATOR BOTTORS TANK B0 Tins 5 PUNP PuiP _ _ _j ' - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

                                                                            =

FIG.ll.2-1 RADI0 ACTIVE LICUID WASTE (nITH LAUNDRY) SYSTEN PTR STANGARD PLANT I,

                                                                        ;,                          1                        SAIETT ANALYSIS REPORT U'       '

ls- . i SIESSAR-Pl ARENDRENT 12 6/16/T5

i 1

                                                                                                                                                                                                    ~

FIG.11.2-1A FRCM RA010 ACTIVE sASTE EVAPORATOR SOLIO WASTE e- I CONCENSER S' EM , FROM BORPN - l ' RECOVERY

• SYSTEM l TASTE FROM AERiTED -- =

                                                                  -                                            l               l EVAPPRt!OR VENT AND (T

I ORAIN SYSTEM 3 j l

a

                                                                    \

i v I HIGH LEVfL (N l WASTE DRAIN ln f - TANKS N/ l WASTE l EVAPORATOR d p l REBOILER g 1 - y  : $ _g n M l ' V. 'd I i i - l Q-] [WASTEEVAFORATO: sASTE DISTILLATE REBOILER PUNP Puur WASTE EVAPOR ATOR -- FEED PUMPS  : [------------' A __ _ _ . _ FIG.11 2-10 - i i i FROM BORON + 1 REGENERANT CHEMICAli , , i I RECOVERY SYSTE4 a i E V A PD'I ATOR , FROM AERATED VENT I (y AND ORAIN ==>= 1 SYSTEM I / \ l  : __l  ; (/

                                                                                    !_F I G .11. 2 -l E                            9                                                                   "

I LOW LEVEL IN i 9 [\/ CE L IASTE DRAIN I FRCN EVAPCRATOR i t TANKS ' CONDENS EAT, REBullER < lPOLISHING

              \/                                             9         )[TO       iSYSTEM o
                                                                                                                                ;    N                                   O a i                                          :
                                                                                      '- - - ~ ~ ]                         , REGENERAN d

REGENERANT i 0,. , CHEMICAL EVAPORATOR est,icAt DiSiitt

                                                                  '                                                           REBulLER PUNP
                                  -                             1

_ i pggp LOW d y LEVEL l_ _ _ _ __._ _ _ _ _ _ _ _ _ _ _ LO LEVEL WASTE F WASTE F _ DRAIN PUMPS EFFLUENT _- FILTERS NOTES: l

l. ALL BYPASSES, INTERCONNECTIONS, VENTS, [

ORAINS, INSTRUMENTS, ECNITORS AND VALVES ARE SHCIN ON THE FOLLOIING SHEETS. f . 1 I >

                                                                                                                          --     /

l_ . g

3*,

             .N r #'                -

TO AERATED VENTS 2

d FIG.9.3.3-1 ' ' 3 O , Nv 8 1

                                                                                             ) 6T'          l RIP I

I y 4 t/2* T 3' RATED ~ f G l. 2- c 'S $1 STET

.3.3-1                                                                              /
                                                                                       ^

x HIGH r2*

                                                                                                                        /           '-           CONT. FRCW LEVEL
                         /M                                                          '

IIS Il 2-I D ggg hfP

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URIP s

3. ;

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WP 2* l A/S m' A /S 2

• _l s q, 2
• s i

                                                               / g.

p*q[2" CONT. ON FIG.II.2.lg y

1. 0. r) ,

       /                                                                                         ;      CON T , ON 2*l:              FIG.11.2-lE

y. ,j 2*l il -10 M PIB FIG ll.2-IA RADIOACTIVE LIWID WASTE (hITH LAUNDRY) SYSTEN

(>, ' G/, f. PER REFERENCE PLANT S AFETY ANALYSIS s!EPORT SIESSAR.Pl AMENDNENT 12 6'l6/75

a FKW A! RATED 3'] ( 3*  ?; DRAINS FIG 9.3.3-1

                                                                                                    ,'7 2*

FROP BORCN . 2b

                                              /

RECOVERY

                                         '      IP FIG 9.3.6-1 V       ID                           ,

WASTE I FIG 11.5-1C CONT. FRCW g 7 FIG 11.2-18 CONT. FRCM 2]'

                  /

s FIG 11.2-1E Ab TC FROM REACTOR _ CR PLANT SAMPLlhG ^ F FIG 9.3.2-1A y \ g 2* Hi@ l H LEVEL tsS-1 )  : BASTE ORAIN HV FRCM CHEMICAL AND " IAhK C A/S VOLUNE CONTROL (NSSS SCOPE)

  ---____J O.n-O-F-                            s p

I I

M \/ I j

           ~VR t P MaV \ AfP

=' ^ ts l;

                                                                                                                   -40         e ::.;:

pig g 2, e glitPr - - @y, rT

                                    't                             r - - - -'- -- - - - l' b jyp                                          -

AM g S d 6 3"Y ,

                                                                               ,A/S 2=T                        " 2-
                                                               ~1 g 2,

dE L.D. , , 2\ 2=J

                                                        & O                               WASTE EVAPORATOR FEED PuuPS P1A NOTES:                                                                                                                '

i' i' THf $ PORil0N OF THE Sf STEN IS NON-NUCLE AR SAFETY CL ASS (NNS). [', '

6 RIP A/S , -8 /4" TO AERATED V g VENTS TOR PLANT C 3' 62 { FIG.9.3.3 ' )NENT - 3/4" thG IATER l.2.2-1 , ,

                                                                                       -              N RO           +      IASTE RIP DISTILLATE lga                                      j ,                        TANK                           LI ---- ,--i- 3 NOTE 2
                                                                             -                                                                   '       i M                   l._1                                                                                           LC              h RTP RIP                      Sr                         YM                                                          p,p U

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c UI. STEAR & l 'r 'E FIG.10.4.12-1 l

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                      ][           }                                                              COOLER r,

( l 1 2" REACTOR PLANT M RIP

                                                               ]                                    COMP 0NENT                   AU             F3 8' EVAPORATOR i                           i X                  COOLING IATER IIG 9 2 2-3 ri b$

CCOLER IASTE DISTILLATE PLINP P3 CONT. FROM PLANT NT COOLING n Fig )) 2_][ ,) 16.8.2.2-1 . v { ( S N A/3 CON

                 ?                                                                            2*

h F I G.11.2-1 ARt ) h* ( Li i,2 ) 2s cip "' , ( ( A/S (( TO RADIDACTIVE SOLIO IASTE STSTEM g N  : d r FIG.ll.5-1E FIG.11.2-1B OR RADI0 ACTIVE LIQUID nASTECRITH LALMAY) SYSTEM PER STANDARD PL ANT SAFETT ANALTSl3 elEPORT [i 'I' (, SIESSAR-Pi U,j AMENOMENT 12 S/16 /75

k 4 IP P, , , Rb g ggp _T, I 4 I PV TO RADIDACTIVE GASECUS IASTE FIG.ll.3-lF

                                                                                 ,                 h                     l I
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RfA l BASTE EVAPORATOR CDu s , l CONDENSER C00

f. l- - - .

FIG I

                                                                                     /N                                                I m              -

w ' P01 y l I FR0u RE ACTOR PLANT GAS SUPPLY SYSTEM , l FIG.9.5 8-1 l

                                                                                                                                              ~                       ~ ~ ~

yp RIP i i ggg I I l ln RC RIP P

                                                                                                                                                            )

I " t._u_c-- a_---_--__.. _d _ _ _ _i---

                                                   $_ - - - . e* Y      - - -- -

u-, l 3 s-c 2" '4' ri S CONDEh! A 1 EASTE CONT. FROM FIG.ll.2-IA 7 N U N,iv ~14- EVAPORATOR RE60fLER , _ _ , 0

                                                                                            )FR0u PRiuARY pgp                     2e m                             (                '

M P M AI Y b*2 Y n p 5 FIG.9.2.7-1 SYSTEM A ,-S

                                   ' r                                                          O             -                      A                         FIG.9 2.7-:
                                                                                                                                    )                       x r2,                 I _- _            -

RIP / Q ( g AS-

                                                                                                                                                                            $3,;

l ' Y Lg. IASTE EVAPORATOR jA/S s REB 0llER PUuP

                                                                                       ,    [/-3,     TQ AERATED DRAINS                       25             P2                       REAC' l

F I C. S. 3. 3-1 Cour-FROM PRluARY l GRADE WATER N,a _

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                            'r' i'

N y [I, SY STEu {" 7 i p,

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n FIG.9 2.7-1 l

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i - - - - -- - j L EVEL gr 1 3xl

                                                                                                                     -N                    =           [

NOTES: f , o E WASTE EVAPOI Uv / U BOTTOuS Puui

1. THIS PORTION OF THE SYSTEM IS NON-NUCLEAR SAFETY (NNS).

P4

2. TR-MulTIPOINT RECORDED.

' \_3*

3, [ PC WASTE DEMihERAllZER 0LSL0SH SEE NOTE 2 8' Ys CTOR 3* w q SANFLING v 3.2-IA TO AERATED 74 {l L DRAINS SYSTEM "3" IASTE F I G. 9. 3. 3 -1 F JEulhERAllIER FILTER

                $                                                                               w  r;
                                                                                     ,           s .
               'X I                               -                   ;

y TO E AERATED OR AINS SYSTEW TO PRIMARY GRADE

                      ,,   ~,
                           ~             ; IATER SYSTER MRIP             FIG.S.217-1 S U 3'           ; A/S

{O=

                          - CONT.ON
                          ' FIG.11.2 1A
                          - CONT.ON
                          ' FIG.11.2-10 FIG.11.2-IC RADI0 ACTIVE LIQUID WASTE (WITH LAlNDRY)

PER REFERENCE PLANY f f () ( SAFETY ANALYSIS REPORT () U '/ U ' ' 57ESSAR P1 ARENDEENT 12 Ull ' 75

                                                                                                                                                             =
                ^

g c4" fASTE TEST TANKS f r4"

                                                                                                                                                        ~

[ 8- 8 1._-f_ _- r:

                ^^~^~                                                                                                                -  _^3 l
                                                ;                        72-                       _

TO AERAIED ORAINS FIG.9.3.3-1 t g

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RIP Hy j , i n A$

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d Ptf RnP . g p r i t 1 i fffN V '

                                              . W        '
                                                              ' TO REACTOR PLANT                 '

(jg----F1 Q, 7 , SAMPLING SYSTEM J

                                                                                                               ] [-Q +

A $d e 3a m , , pg J d-l FIG. CONT.FFOM y - FIG.11.2-1 \ _2

• l M

i/2-y; Q c G I 2-1E /' "

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{3' 7h RfD @ v Qb i I 5' 3 A 'S L 3* g iT _I . b O  : 6h-- 4-] gh ,e 3* dad d C A/S g -3*

                                                                                                                     'd
                        , m >-                                                            .- ,

g\_3= Q LA MASTE TEST TANK PUMP (TTP) P58 i THis PORT!ON OF THE SYSTEM IS NCN-NUCLEAR SAFETT (NNS).

2. FOR DiplNER AllZER DET All CONNECTIC'45. SEE FIE II I"I-

                                                                                                                      , ,q              p      ,3 V/                b.V

RTP

                  ' T
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      /             \       \

'S L' LEVEL IASTE lhb I RIP I DRAIN W RTP 2* E d / p A 'S CCNT. ON FIG 11.2-1A 21 CONT. FR05

                                                          ' FIG.11.2-1F 2* CONT. FROM
                                                                              }
                                                                      ' ' ' , l L 11. 2-lE 2'

V 1 , r3 4 ek b [DI D R$if HP IP L 74 j[ RI_P ___ T LOW LEVEL BASTE r

                                                                                                                       ,                              gj$

(t EFFLUEMT FILTERS 2,' '; J( l s ,y TO AERATED l g RT (bSH_g DRAINS FIG 9.3.3-1(TYP) g gyp N " FT IP py i < Aid a RE CONT. FR05  : A, , FIC 11.2-1F 2"- 2'T S, ' ' TD i DI SCH ARGE FC 2* T NPLING FC /3 . LINE

                                                                .                          FE FR0u BORON          ;                                                                             FI G. 9. 3. 2-1 A RECOVERY F I G.9. 3. 6-1

3. /

7 g FIG 11.2-10 CONT. FROM -

                                                      '                             M         ,

e FIG.11.2-1C 3.] ' g

• RADI0 ACTIVE LICUID WASTE (nliH LAUNDRY) LYSTEM PIR REFERENCE PL ANT M- SAFETY ANALYSi$ REPORT M VP SIESSAR-Pl f zq , _

doi lq _. ') EP AMENCMENT 12 6,16'75

h J

                           ~
                             ~

FR0u BCRCN RECCVERY SYSTEM FIG 9 3.6-1 ^ FROM O 3' 7 AERATED HS 3 VENT & T '" AERATED CR AIN Tr$ TEM l

                                 @               q 2p                                         3"                                                   :

FIG 9.3.M @ ,, qg 8 g,;,g,3,3,3 , A/S Q em - r F U- Q/

                                                 \                                            8 LO,                                                 ,  ,

TO AER ATED [UnlNS SYSTEM F l lp OLSL Ai LEVEL

                                                       " -             - ' ~ ~ -

_ _ _~'j l RsP MASTE - A 'S 1 DRAIN l , l

                                                       ;                                                                                                                 n e;,3c-                                                         :

j l i l RtP A 'S Ph f$ h 1 l I c

                                                                                                    -g     a 'Q"3   TO SAMPLING SYSTER (TYP) i I

F I G. 9,3,2-I A 2a i e,

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i CONT. >(- __ __ __ __ _ d 2* " FRCu f Fl311.2-IA ~ l g

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P8A P68 LOM LEVEL MASTE DRAIN PuuPS I'J L. qj [,  ; NOTE: THIS PORil0N OF THE SYSTEu IS NON-NUCLE AR SAFETY (NNS)

_ --- M RIP A,$ s / 7 ' HV TO 1EhATED e3" Q( Xt VENTS

FIG.9 3 3-1

                                                                                                            #~

R PLANT ENT - g 'G f1TER .2.2-1 , ,

                                                                         ,  "N REINER#li CHEulCAL                                                 RIP b.j                         , ,                     OfSTILLATE                      -~~--- l 7 7 TR NOTE 2              gi,                                                   Q                               g                M ET                                                  l                              ' RIP p.]                                        E                                        .       ;
                                  $N          $              c'                                       --

REP ,

~ ~ ~ '

O O IO ' ' pgp I J f p p " O 0 i RIP t 1 R l i;-_s ?._ _ s IP J, IT f

1. STIAN &

FIG.10.4.12-1 ( - 3 ty i g& d I  ; - +

                                                               =                                               A         &            -

f ) 'F I I'2 REGENERAhi d 'J 0 g wr CHEulCAL g to DISTILLATE < d6 f COOLER b FT

                                                                                                                                       b l 1 2           ON FIG.ll.2-1C NT

{ .] REACTOR PLANT b 00L ) C 34' C G REGENERANT CHEulCAL OR PLANT DISilLLATE PUNP BATER FIG g 2.2_1 g7/ NEhi COOLING P8

                                                                                                                               /    LOW CONDUCTIVITY p

WASTE SUuP /

.2.2-1                      3,j e            b I 2"                      RIP FIG.ll.2-1A       ) , es

( HV ( h 1/2' b , , 2,3 A/S .e k M U r [, -FIG.ll.2-1B

                                                                              ,      CON T , ON FIG.11.2-lE RADI0 ACTIVE LIGUID \ASTE RITH LAUNDRY SYSTEM AL       pg                                                                                              pyR STANDARD PLANT I

SAFETT ANALYSIS REPORT SIESSAR-Pl e p p-Uu / Uv i AE(W0e(NT 12 6 '16 J7

R s, P _ _. PC RtP RV PT ) TO RADIDACTIVE e k l PW L3 4" GASEOUS WASTE 1- Y\ r-4 i FIG.11.3-lF  ; I RE8 REGENERANT COI 25' CHEMICAL EVAPORATOR  :

                                                                                        ',- Ba                  { CONDENSE" i

l ew I

                                                                                            -C                               :

I I' CON 0ENSATE FRCu REACTOR PLANT POLISHlhG SYSTEM I i;nS SUPPLY r FIG.10.4.6-1B $ STEM l F G.S.5 B-1 -- g------- LY l (a v RIP QutRIP REGrum1 O(MICAL _Y U Ll R SH SL 12" PT R I P L. _ _ _ _. ,' RIP , p ty

         .'L   _ CONT. CN l

i @ N/ l t

         (2, FIG.11.2-10                   Lv            r- .                                                                                                              FROM TC TI
                                                     '$[i                                               REGEhtRAhi                            db s,

CHEMICAL EV AP. T[ REBOI LER

                                                                                                                                                                               ~~

CONT 2" d' FRCM ON * $ RIP 1a

                                                                                       3 FIG 11 2-IA                                                     V                        /FROM PRIMART                     I i

{2' ( GR ADE E ATER g,p

                                                                                                                                                  '         ~

NN g SYSTEg GRADE SATE-A$ a r

                                                                        '                   IkI'2I-2 v          -

HS , CHEl I_ _ sp {} l SAs S L. l

• REGENERANT

                                      -2"                         jA $                 , [         TO AER'ATED                   _                   CHEMICAL EVAP.                  R I                                DRAINS                        &                   REBOILER PUMP                   Cl FROW PAINARY                                                      l                       -3*      Fig,g 3,3 1                                       p;                              ,

GRACE WATER .,& l , g , y SYSTEN vi n - w v (- {2" FIG 9.2.7-1 I I h P P9--

                                                                                                . STO t"                                   ,                   $

l @,,$ 9,!' l,_6

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l- -----l ,-3* 9n, T T [Q , t

                                                                                                                                                        \               f NOTES-                                                                                                                                                  l

1. THIS PORil0N OF THE SYSTEM is NON-NUCLEAR SAFETY (hWS).

REGENERANT CH

2. TR-uulTIPOINT REC 0IDED.

                                                                                                             /        q            l              3             EVAPORAT01 BC Jv         e          UvL                          puisp pg

       $4                                     _ c2-                                                l PT         y 0       ' '

l l h  ; TO AERATED VENTS l

                          ,, c             t                                       ri G. 9. 3. 3-i ;

LAUNDRYWASTE; EVAPORATOR  ! E5L CONDENSER l FROM TO REACTOR l

                               +                     3h          PLANT CauP0hENT                    l NM '3 FROM TO AullL ARY
                                                               -l$"!'."I'"                        l STEAM 1 CONDE45 ATE l                              O                     SKID MOUNTED PORATOR FIG 10.4.12                    _l
                       ~         !n_                        %      TO AERATED ORAINS j               -              V                  __ 2 FIG.9 3.3-1 M

7

\/            l PT
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t g' LAUMLRY 5 8.aT E DISTILLATE 3/8"

                                                                                    'll l           RIP              Y           N                                                            $

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                                                                            )b                                  "           - CONT. ON

k l [ F I G.11. 2-10 E

iOES 0]P \ 6 I LAUNDRY IASTE DIST. TEST - - TANK PUNP P12 h/ TT dr C TO RADIDACTIVE SOLIO IASTE l' 1 [ Q N 7 FIG.11.5-1E 0:E' M C b3 t_J LAUNDRY IASTE BOTT0ES PUMP Pil FIC ll.2-1F RADI0 ACTIVE LICUID nASTE WITH LAUNDRY SYSTEM PER STANDARD PLANT SAFETY ANALYSIS REPORT SIESSAR-PI

                                                                                                                              /     .t' tj u i           s. .. . s AMENOMENT 12 b/[3/75

1

                                                                                                                                       ~

i TO RAD'0 ACTIVE FROM LAUNDRY ,7-2a I gas [0gs gast[ IASTE DRAINS FtG.11.3 1F

                          '                                                                               l 2 i.2-                                                          l U

7 l m h f' I C' _

                                                             , c.                                         1 RIP r'                    3 '4" LAUNDRY 3 8" l lT                   RA N S{                            ,

g -h l FT FV g y D g

         ; tsp t';                 M-                                                                                        '

E T0 LAUNDRY

                                         ,a                                                                  dI TO AERATED                                                                                  .

WASTE PUWF gpggg3 l FE CCNTROL p;g,g,3 3.j , PI 7 l 3 m n l k) )['

                                                                  ^ l i

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P 2 se D b[JCRAIN L AUNDRY IASTE PUNP a

                                                                                                    - CONT. ON
                                                                                                       ' F I G.11. 2-I D                 ,

TO AERATED CRAINS F I G 9. 3. 3-10 t, El FRCM PRIMARY _ BC GRADE RAVER ' T8 SYSTEM L1 ' FIG.9.2.7-1 3 l' NOTES:

1. THis PORTION OF THE SYSTEM l$ NON4UCLEAR SAFETY CLASS (NNS).

f g p. - a f j ,,, / Us ,

SWESSAR-P1 Fig. 11.2-1I i.s deleted . 29 LWS-1 not applicable. Amendment 29 10/29/76

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                                                                   ;     Ot44SIFit A COOL Amt Lt TDOW4                                                                      at ACTom PL Au f                  DE CouTAulN A TION Ltas AGE TO SuuPS                           Da Atal 3 0 e 10'        I f e s0' I 74 s 80*         A2               e 44 e 40*     e 3 se0-'

Gat /V F C /CC L T pe 3AL/TR pCe/CC RE ACTOA C00L ANT Ot tt0 TO BO#0m TUR9tutPLAmt R E C0vt av 4 A M PL E S 1 SuuP 17 0 s iO' 3 0 seo. S l e s0-8 eAL/vn

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• ' GAL /TA p Ce /C C 6AL/YR GAL /TR b' 90A0m at Covt NY

                                                                                                                                                ' '                                               '3 TEST Taust                                                                                                             g,3 i r                                    i  p                                                                                                                                            '-

16S eiO* GAL /?R L0e Ltytt wignLtytt eASit sASTE TO tuvimOnut m7 70 t uvimonut ui De Aim pa Aim S e sto-8 Ce / Te T e sio's Ce/YR Taust TANS 3 PaluART GR ADE TOtuvlRomut4T WAf t e SYSites S T s 10 8 C s /T R SPluf REStu LABORATORY FLUSM WalitS

                                                                                                                              'O tuvipomut u ?                    T0 t uvimoesu r n?

j t e e t0" 10:10 - ' Cs/YR 4 S s IO* IS 4 0 e 00

• Rt f umu 70 e3 10 - ' Cs/YR

$AL/YA pCe/CC GAL /TA pCe/CC RE ACTOR PL ANT ST sit ul E*W RE Glut R A TIVE g. p*2W CMEutCALS TUR9 tut Pt Amt Lt As Act TO sumps I FS e10* 2 O sIO-s p GAL /YR p Ci/C C gg,y 19 e 10 ' S$s10 8 GAL /TR pC/CC i r 1r j f peesee LE Vf L If MtGM Livil

                                                                                                      #tSINi#Auf CHIE8 CAL WASTE DAAlu Taust                       WASTE DAAIN TAmtS                                               tvAPORATOM SuuP FIG lt 2-3 i,
                                                                                                             ,                           ESTIM ATED SOURCE QUANTITIES TO
            < r RADIOACTIVE LIQUID WASTE SYSTEM 70 t uvimonet e?                       TO tuvin0mut af               T0 t uvimousut ui             To tavia0mut m?

(DESIGN CASE) i S e to ' Ce/T R S S s 10 '* C./ v m 2 7se0 ' Ca/im S Sa to 8 C /vm PWR RE FE RE NCE PL AN T SAFE T Y AN ALYSIS REPORT SWESSAR-PI W Auf mDuf m T IO S /IS/ TS

REACTOR PLANT REACTOR LE KAGE DECONTAMIN ATION DEG ASIFIER S A M PLES COOL ANT LETDOWN TO SUMPS DRAINS { 3 0 m 103 2.3 1.76 x IO* 3.5 x104 1. 6 4 x 10 4 4.1 x10-2 GAL /YR. pCi/CC GAL /YR p Cl /CC GAL /YR Ci/CC RFACTOR u COOLANT BLEED TO BORON \' TURBINE PL ANT RECOVERY S AM PL ES ' '

                          ---.e.          SUMP              1. 7 0 m lO 6  GAL /YR.

3.0 m10* 8.9 alO-7 AERATEQ

                                                                         '                                                                 VENTS AND DRAINS GAL /YR pCi /CC                                                             '

BORON RECOVERY 1

                                               '                                            'OW                      l . 8 x 10 1                                              3 A a 10" CONTAMIN ATED                                                                             wgsT DRA N LAUNDRY                           HIGH LEVEL                                               TANKS               GAL /YR.                                                   G AL / YR.

WASTE DRAIN WASTE DRAIN TANKS TANKS l' 3.78 x IO 5 1.2 x 10-5 1r l ' 2.On105 1.5 x10-5 BORON RECOVERY GAL /YR p i /tC "' g g G AL / YR Ci/CC TEST TANKS L V LEVEL 1.34 a lO8 GAL /YR. WASTE WASTE DRAIN DRAIN f 3

                                                                                                    ,                        TANKS                                  TA N KS TO ENVIRONMENT                    TO ENVIRONMENT              PRIM ARY GRADE            TO ENVIRONMENT WATER SYSTEM             1.7 x 10-2       Ci/YR.

1.2 x10-2 Ci/YR. I.6 x 10-s Ci/YR. q , i r SPENT RESIN LABORATORY REA PLANT FLUSH WASTES SYSTEMS C i/ YR, 2. 3 x 10-3 Ci/YR. 2.1 x 10-2 2.3 x 10 4 1.5 4.O x 10 4 2.3 x 10-2 G AL /YR. p Ci/CC GAL /YR. Ci/CC REGEN ER ATIVE TURBINE PL ANT CHEMIC ALS LEAKAGE 1. 6 x 10s i,3x10-3 TO SUMPS GAL /YR Ci/CC 1.3 x 10 5 8.9 x10-7 G A L / YR pi/CC FIG.11. 2 - 2

           "                                  "__                         o ESTIM ATED SOURCE QUANTITIES TO HIGH LEVEL                         HIGH LEVEL                                          REGENERANT           RADIOACTIVE LIQUID WASTE SYSTEM WASTE DRAIN                        WASTE DRAIN                      SUMP                   CHEMICAL TANKS                             TANKS                                             E VA PO R ATOR       (EXPECTED CASE )

PWR REFERENCE PLANT SAFETY AN ALYSIS REPORT TO ENVIRONMENT TO E N VIRON M EN T TO ENVIRONMENT TO ENVIRONMENT SWE S S AR- P1 1.3 x10-2 C i/ Y R. 2.1x10-9 Ci/YR. 4. 3 x 10-

• Ci / Y R. 6.9 x 10-* Ci/YR g,y AME N DMENT 17 9/30/ 75

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                                                                      #f C0vf RT 1           SuuP                 S**C' 50s40*           2 3se0'*                                      GAL /Tm                                                                                             .

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                                                               $2FSeiO'           GAL /TR                                               Low LtvfL              MiGM LEvil TO EnviAONuf 47                  70 E nvim0=uf 4T                                                                                         WA5TE                eASTE 9 9 e I0 8          Cs/TR      22 10' '            Ci/ve                                                                                  On a a m              onAim 144R5                 T&485 1'                                P Pnimany GRADE                  TO E 4 WiRO4mE NT WATE R $75f f u         l     G ie s0 '        Ci/f#

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GAL /vn C i/C C I 5 e so 5 2 3 si0 gat /TR M C /CC 1 P 1P ir

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• 19 4 0 s10 ' 22 10 RETURNTD 8 v- ' l GAL /vm GAL /vn p Ci/CC Z U JO C./vR 24 10 ' Ci/vm Cl/CC RE ACTOR Pt a m r
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                                                                                   &&L/YR           p C1/C C t

r i i p MiGM LEVEL MiGMLivEL 'I RE GE N E R A N T w ASTF OR A#N TAasu s easif ORaig TANas CHEMICAL SUMP E V A POR A TO R FIG Il 2-2

                                                                                                                               ,   ,                             ESTIM ATED SOURCE QUANTITIES TO TO ENylRGeM ENT                     TO ENviRONasENT                    TO FNvt RONMf NT                 TO E Nv eRONw f M T RADIOACTIVE LIQUID WASTE SYSTEM I5.i0-'               Ci/vR         2 0.io -*                Ci/v4    3 0.io

• C./ vR T s.10
• Ci/vm ( E XPECTED CASE)

PWR REFERENCE PL AN T SAFETY AN A LY SIS REPOR T S WE S SAR - Pi C-E Auf M 0 MENT so s/ ss / rs

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• 3 0 s to-'

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                                            ;           soup               S 4 s 10 8 30s10'            4 7 a s0 a                                  gatfyn Gat /vm           p C , /C C                                                                                                                qr             qr CONT Autu ATE D                          1P               90RON RECOVERY                                                                   AI " E II S LAUNDar                                                                                Lo* LEVEL                                  vE NTS aNo omatNs WASTE 04 Asa Tames          W                                                          Wa$ff DRAINTAND$

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  ,gy%       S 2 s t0          Ci/Ym         12 s io-L       Ce/yR                                                                               OR Alm                DRAIN TANWS                 Tamas
        )                                                                    PRiu ARv Gna0E EATER SYSTEu YO ENvim0NME NT 4 4 s t0 '          Ca/YR T.,g ,      SPE NT SE Sim                   L ABOR ATORT FLUSH                           eASTES arewi sers'.88 TO ENVIRoseME NT                        TO E MvlR0huf esT 2 3 s IO*            IS          40:10

• 1 9 s 10 " RETunu TO pCe/CC 3 4 s 10 Ci/ vm 36 e so 8 Ci/TR
• GAL /YR GAL /YR pCe/CC RE ACTOR PL ANT "s"t" e F

          ==                                                                     SysTEus
  %'t                                                                                                  REGEnf R AfivE MF 3 C HE esiC AL $

f TU ASIseE Planif I T6 s C' 3Samd LE AR AGE YO SuuPS GAL /YR # C s/C C 3 3 s10 ' 4 Tal0 e GAL /YA pC/CC 1r 1 r i P HIGet L E VE L HIGN L E VE L RE GE NE R A se T WASTE DN Aise Yaults WASTE DR Aree TANMS CHEMICAL Suur EVAPOR ATOR FIG.Il2-3

                         ,  ,                            q,                                                       q,                          ESTIMA(ED SOURCE QUANTITIES TO TOfavinomuf%T                     TO f uvinoessf ur RADIOACTIVE LIQUID WASTE SYSTEM TO EnviRossuENT            TO EnviRoquf wi e 3 a t0~ '         C./vm        i S r0 -'        C /vR      2 3 e 80 '       Ci/vn    2 2 s 60 -'         C,/YR                (DESIGN CASE)

PWR REF ERENCE PL ANT SAFETY AN ALYS13 REPORT SWE SS AR - Pi C-E Auf NOuf MT 10 S/tS/ 75

VOLUME 8 PRESSURI7Fn WATER REACTOR REFERENCE NUCIEAR POWER PL_ ANT SAFETY ANALYSIS REPORT SWESSAR-P1 STONE & WEBSTER ENGINEERING CORPORATION P. O. BOX 2325 BOSTON, MASSACHUSEITS 02107 Copyright 1974 by Stone & Websrec Erigineering Corporation. All material herein is the property of said corporation under which all copy and other rights have be-s reserved and no such rights have been granted to others. Stone & Webster Engineering Corporation willin allinstances take such steps as are necessary for the preservation ofits rights and the enforcernent of applicable law. ( >. v / g, , _o y

SWESSAR-P1 TABLE OF CONTENTS Section Volume CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT

1.1 INTRODUCTION

1 1.2 GENERAL PLANT DESCRIPTION 1 1.3 COMPARISON TABLES 2 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS 2 1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION 2 1.6 MATERIAL INCORPORATED BY REFERENCE 2 1.7 TERMINOLOGY AND FLOW DIAGRAM SYMBOLS 2 1.8 INTERFACE WITH NSCS VENDOR AND UTILITY-APPLICANT SAR 2 CHAPTER 2 13 SITE CHARACTERISTICS 2.1 GEOGRAPHY AND DEMOGRAPHY 2 2.2 NEARBY INDUSTRIAL, TRANSPORTATION, AND MILITARY FACILITIES 2 2.3 METEOROLOGY 2 2.4 dYDROLOGIC ENGINEERING 2 2.5 GEOLOGY AND SEISMOLOGY 2 CHAPTER 3 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS 3.2 CONEDRMANCE WITH NRC GENERAL DESIGN CRITERIA 2 3.2 CLASSIFICATION OF STRUCTURES, SYSTEMS, AND COMPONEttrS 2 i Amendment 13

t. ,

6/30/75

SWESSAR-P1 TABLE OF CONTENTS (CONT) Section Volume CHAPTER 3 (CONT) 3.3 WIND AIO TORNADO LOADINGS 2 3.4 WATER LEVEL (FLOOD) DESIGN 2 3.5 MISSILE PROTECTION 2 3.6 PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED 2 WITH THE POSTULATED RUPTURE OF PIPING 3.7 SEISMIC DESIGN 3 3.8 DESIGN OF CATEGORY I STRUCTURES 3 3.9 MECHANICAL SYSTEMS AND COMPONENTS 3 3.10 SEISMIC DESIGN OF CATEGORY I INSTRUMENTATION 3 AND ELECTRICAL EQUIPMENT 3.11 ENVIRONMENTAL DESIGN OF MECHANICAL AND 3 ELEC'"RICAL EQUIPMENT APPENDIX 3A CONFORMANCE WITH NRC REGULATORY GUIDES 3A.1 DIVISION I REGULATORY GUIDES, POWER REACTORS 3 3A.2 OTHER DIVISION REGULATORY GUIDES 3 APPENDIX 3B 20l COMPUTER PROGRAMS FOR ANALYSIS OF 3 THE CONTAINMENT STRUCTURE CHAPTER 4 20 REACTOR 3

                                                        /
                                                         /   /    e   j ii                       Amendment 20 1/23/76

t SW1 'SAR-P1 TABLE OF CONTENTS (CONT) Section Volume CHAPTER 5 REACTOR COOLANT SYSTEM AND CON?ECTED SYSTEMS

5.1 INTRODUCTION

3 5.2 INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY 3 5.3 THERMAL HYDRAULIC SYSTEM DESIGN 3 5.4 REACTOR VESSEL AND APPURTENANCES 3 5.5 COMPO?ENT AND SUBSYSTEM DESIGN 3 CHAPTER 6 ENGINEERED SAFETY FEATURES 6.1 GE?ERAL 4 6.2 CONTAINMENT SYSTEMS 4 6.3 EMERGENCY CORE COOLING SYSTEM 4 6.4 HABITABILITY SYSTEMS 4 APPENDIX 6A DATA FOR DETERMINING THE IODINE REMOVAL EFFECTIVENESS FOR THE CONTAINMENT ATMOSPHERE 6A.1 THE SPRAY DROP DISTRIBUTION AND CHARACTERISTIC SPRAY DROP DIAMETERS FOR THE SPRAY HEADERS 4 6A.2 THE SPRAY COVERAGE OF THE CONTAINMENT 4 ATMOSPHERE 6A.3 ANALYSIS OF SLCRS PERFORMANCE 4 APPENDIX 6B LOCTTC INTERFACE WITH NSSS SUPPLIED DATA 20 6B.1 POST - i'EFLOOD PERIOD 4 6B.2 LONG TEFM MASS - ENERGY RELEASES 4 iii _, Amendment 20 [, _ j Lv/ 1/23/76

SWESSAR-P1 TABLE OF CONTENTS (CONT) Section Volume CHAPTER 7 INSTRUMENTATION AND CONTROLS

7.1 INTRODUCTION

4 7.2 REACTOR TRIP SYSTEM 4 7.3 ENGINEERED SAFETY FEATURES SYSTEM 4 7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 4 7.5 SAFETY RELATED DISPLAY INSTRUMENTATION 4 7.6 ALL OTHER INSTRUMENTATION SYSTEMS REQUIBID FOR 4 SAFETY 7.7 CONTROL SYSTEMS NOT REQUIRED FOR SAFETY 4 7.8 INTERFACE REQUIREMENTS 5 CHAPTER 8 O ELECTRIC POWER

8.1 INTRODUCTION

5 8.2 OFFSITE POWER SYSTEM S 8.3 ONSITE POWER SYSTEM S 8.4 INTERFACE DESIGN INFORMATION 5 20 8.5 ELECTRIC HEAT TRACINC 5 CHAPTER 9 AUXILIARY SYSTEMS 9.1 FUEL STORAGE AND HANDLING 6 9 iv ,. Amendment 20 b 0 ', [ g j' 1/23/76

SWESSAR-P1 TABLE OF CONTENTS (COtTT) Seetion Vc1ume CHAPTER 9 (CONT) 9.2 WATER SYSTEMS 6 9.3 PROCESS AUXILIARIES 6 9.4 AIR CONDITIONING, HEATING, COOLING, AND 6 VENTILATION SYSTEMS 9.5 OTHER AUXILIARY SYSTEMS 6 CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM 10.1

SUMMARY

DESCRIPTION 7 10.2 TURBINE-GENERATOR AND TURBINE STEAM SYSTEM 7 10.3 MAIN STEAM SYSTEM 7 10.4 OTHER FEATURES OF STEAM AND POWER COtWERSION 7 SYSTEM CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 SOURCE ITEMS 7 11.2 RA"IOACTIVE LIQUID WASTE SYSTEM 7 11.3 RADIOACTIVE GASEOUS WASTE SYSTEM 9 11.4 PROCESS AND EFFLUENT RADIATION MONITORING d SYSTEM 11.5 RADIOACTIVE SOLID WASTE SYSTEM 6 11.6 OFFSITE RADIOLOGICAL MONITORING PROGRAM 8

                                        /

Li/ U, v Amendment 20 1/23/76

SWESSAR-P1 TABLE OF CONTENTS (CONT) Section Volume CHAPTER 12 RADIATION PROTECTION 12.1 SHIELDING 8 12.2 VENTILATION 8 12.3 HEALTH PHYSICS PROGRAM 8 12.4 RADIOACTIVE MATERIALS SAFETY (FSAP) 8 CHAPTER 13 CONDUCT OF OPERATIONS 13.1 ORGANIZATION STRUCTURE 9 13.2 TRAINING PROGRAM 9 13.3 EMERGENCY PLANNING 9 13.4 REVIEW AND AUDIT 9 13.5 PLANT PROCEDURES 9 13.6 PLANT RECORDS 9 13.7 INDUSTRIAL SECURITY 9 CHAPTER 14 INITIAL TESTS AND OPERATIONS 9 CHAPTER 15 ACCIDENT ANALYSIS 15.1 GENERAL 9 CHAPTER 16 TECHNICAL SPECIFICATIONS 16.1 DEFINITIONS 9 16.2 SAFETY LIMITS IuND LIMITING SAFETY SYSTEM SETTINGS 9 vi Amendment 20 h bI) (j((J 1/23/76

SWESSAR-P1 TABLE OF CONTENTS (CONT) Section Volume CHAPTER 16 (CONT) 16.3 LIMITING CONDITIONS FOR OPERATION 9 16.4 SURVEILLANCE REQUIREMENTS 9 16.5 DESIGN FEATURES 9 16.6 ADMINISTRATIVE CONTROLS 9 CHAPTER 17 QUALITY ASSURANCE 17.1 QUALITY ASSURANCE DURING DESIGN AND 9 CONSTRUCTION 17.2 QUALITY ASSURANCE FOR STATION OPERATION 9 APPENDIX A ENCLOSUPE BUILDING WITHOUT MIXING 9 APPENDIX B ENCLOSURE BUILDING WITH MIXING 9 vii Amendment 20

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SWESSAR-P 1 11.3 RADIOACTIVE GASEOUS WASTE SYSTEM The radioa ctive gaseous waste system consists of two portions: the process gas (hydrogenated) and the low activity process vent (aerated) streams. Relief valves and ventilation releases are also discussed as releases. Process Gas Portion of Radioactive Gaseous Waste System The process gas (hydrogenated) portion of the radioactive gaseous waste system is designed to remove fission product gases from the reactor coolant letdown stream and from the liquids collected in the reactor coolant drain tank and the primary drain transfer tank (Section 9. 3.3) . The noncondenshble gases removed from these liquid streams and the gases from the reactor plant gaseous vent header (Section 9.3.3) are dehumidified in the process gas retrigerant dryers, passed through the process gas charcoal bed udsorbers (which provide a minimum of 60 days of xenon decay and 4 days of krypton decay), compressed, and released to the environment through the ventilation vent. Provisions are included to recycle the purified hydrogen stream back to the reactor coolant system through the volume control tank (NSSS Vendor 's scope) . Process Vent Portion of Radioactive Gaseous Waste System The process vent (aerated) portion of ti.e radioactive gaseous waste system is designed to collect the low activity aerated gas streams from the reactor plant aerated vents header (Section 9.3.3) , steam jet air ejectors (Section 10.4.2), the degasifier vent, the dilution air exhaust blowers (Section 6.2.5) , and the process gas adsorption bed gas drain. The process vents, except from the steam jet air e jector , are filtered, monitored, and discharged to the ventilation vent. The 19 gas stream from the steam jet air ejector is monitored and discharged, but is only filtered on a high activity alarm. 11.3.1 Design Obiectives The design objectives of this system are: 1 . The radioactive gaseous waste system shall be designed in accordance with the requirements of 10CFR20, 10CFR50, and General Design Criterion 60 (Section 3.1.60) .

2. Table 11.3-1 gives the criteria used in obtaining the radioactive gaseous release data that shall be used for design. The expected case is based on Regulatory Guide 1.42 (Section 3A.1-1.42) .

3. The process gas equipment is designated Seismic Category I and Safety Class 3, and shall be designed in accordance with ASME III, Class 3.

r .i 11.3-1 . t:! '9 Amendment 19 12/12/75

SWESSAR-P1

4. The low activity process vent streams and the filter assembly are not safety related and are designated nonnuclear safety class (NNS) .

11.3.2 System Description The radioa ctive gaseous waste system is shewn in Fig. 11.1-1. These drawings indicate the piping within the system and show the instrumentation and the automatic valving. Tables 11.3-2 and 11.1-3 list the estimated gaseous effluents from all sources for both the design bacis and expected conditions of fuel cladding defects. The radioactive gaseous waste system treats specific gas streams. The treated effluent is discharged to the ventilation vent. Fig. 11.4-2 shows the flow paths for all potentially radioactive gas stremms. 11.3.3 System Design 11.3.3.1 Process Gas Portion of Radioactive Gaseous Waste System Reactor coolant letdown, containing the dissolved hydrogen and fission gases, is directed to the degasifier which operates at ISl 3 psig, from the letdown line upsteam of the volume control tank in the chemical and volume control system (NSSS Vendor's scope). Liquid collected by the reactor plant gaseous drains system (Section 9.3.3) is also directed to the degasifier. Dissolved gases are separated f rom the liquid in the degasifier . The USSS design and operating purification flow rates are given in Table 11.3-8. If the degasifier is not operating, it is in the standby mode. Under this operating condition, liquid in the degasifier is recircula ted through the degasifier feed preheater and back into the body of the degasifier. Thus, in the standby mode, the degasifier vapor space remains filled with steam. Effluent gases from the degasifier contain primarily hydrogen and water vapor. A small amount of nitrogen and traces of xenon, krypton, and iodine are also present in the effluent gases. These gases and any hydrogenated gas stream trom the reactor plant gaseous vent header (Section 9.3.3) are dehumidified (dew point 35 F) in the process gas ref rigerant dryers, and passed through and filtered by the ambient temperature process gas charcoal bed adsorbers (to limit the buildup of long-lived tission product gases dissolved in the reactor coolant) and released to the environment via the ventilation vent. The heating effect due to radioactive decay is small and does not affect the adso rption of noble gases on the charcoal. The 11.3-2 Amendment 19 f(O

                                              + ' -   gJ         12/12/75 u.

SWESSAR-P1 charcoal beds are designed to delay xenon isotopes for a minimum of 60 days. In addition, a decontamination f actor of 106 for iodine is obtained during passage through the charcoal beds. The charcoal is divided evenly between two vertical tanks in series. Provisions are also included for the recycle of the purified hydrogen stream to the volume control tank. A process gas receiver is located af ter the process gas compressor aftercooler to ensure an adequate supply of purified hydrogen to the volume control tank under changing operating conditions when the system

 .  .7 the recycle mode.        An in-line monitor iprocess gas monitor
- Section 11.4.2) is provided for this streau to monitor the rate at which dctivity is released to the ventilation vent.

11.3.3.2 Process Vent Portion of Radioactive Gaseous Waste System 19 Effluents from the degasifier vent, the reactor plant aerated vents, combustible gas control system, and the process gas charcoal bed adsorber gas drain are filtered and monitored before being released to the environment via the ventilation vent. The steam jet air ejectors (af ter condensation of excess stedu) dre normally monitored and discharged directly. On a high act.:vity signal, the tlow is diverted through the filters. 11.3.3.3 Ventilation and Reliet Valve Releases The release due to litting of the relief valves in the evaporators or the degasifier is insignificant for a number of reasons. Lif ting of the relief valves on the evaporators or the degasifier is considered to be a low order probability occurrence (frequency less than once per year). Coupled with this fact would be the small potential release of activity to the environment for such an occurrence. Since evaporator bottoms have been degassed, there is negligible release of noble gases to the environment from these sources. The partial pressure of noble gases in the degasitier, at any time, is small and any release from this source would consist of only the inventory or the degasifier vapor space. Ventilation effluents are discussed in Sections 9.4 and 6.2.3.1. It iodine activity in these air streams is high, the streams may be diverted through filter banks before discharge via the ventilation vent. The turbine building ventilation exhaust is untreated. The combustible gas control system (Section 6. 2. 5) is capable of operation in both a recombiner mode and a dilution mode. In the recombiner mode, no activity is released to the environment because the processed atmosphere is returned to the containment st ructure atmosphere. The dilution mode is used as a backup to the recombiner mode. The dilution air exhaust is discharged through the process vent filters to the ventilation vent. 11.3-3 Amendment 19 f _, 12/12/75 hr 1  !). b

SWESSAR-P1 Section 6.2.5 describes the design combustible gas control system. and operation of the f 11.3.3.4 Components Table 11.3-4 summarizes the design and operating conditions of the radioactive gaseous waste system components. 11.3.3.5 Monitore A complete discussion of the process gas monitor and the process vent monitor follows in Section 11.4. 11.3.4 Operating Procedures 11.3.4.1 Process Gas Portion of Fadioactive Gaseous Waste System Prior to operation, the process gas portion or the system is flushed free of air and filled with nitrogen. During normal power operation, the degasifier operates continuously on the reactor coolant letdown flow. Pure or recycled hydrogen gas is introduced into the volume control tank for adsorption in the reactor coolant. The contaminated hydrogen stream from the degasifier is d ehumidified , decayed, compressed, and normally discharged to the ventilation vent. The discharge to the ventilation vent is monitored for radioactivity. The liquid recirculation rate of the degasifier is controlled by the pressure upstream of the degasifier nozzles. This pressure is an indication of the total flow into the degasifier and, in turn, of the spray characteristics inside the degasifier. The liquid level inside the degasifier controls the amount of degassed liquid discharged through the degasifier recovery exchanger to the chemical and volume control system. In case of the failure of an operating degasifier recirculation pump, a 19 le vel transmitter on the degasifier detects a high level, activates un alarm, and starts the standby degasitier recirculation pump. A pressure higher than the normal 1 psig in the gas stream af ter the process gas charcoal bed adsorbers a ctivates the second compressor (each compressor has a desian flow of 2 scfm) . The compressor (design flow of 3 scfm) is controlled by a pressur e on-off switch. When the suction press ure reaches 1.5 psig, the compressor activates and shuts down when the 19 suction pressure drops to 0.5 psig. If the compressor suction rises to 2.0 psig, the redundant compressor activates and shuts down when the suction pressure drops to 1.7 psig. The hydrogen gas stream, contaminated with nitrogen, krypton, xenon, and iodine, passes through the process gas churcoal bed 11.3-4 g .,, Amendment 19

                                                        /
                                                                'l /       12/12/75

SWESSAR-P1 adsorbers which provide holdup time for decay of the radioactive isotopes prior to discharge. Provisions are made to recycle this purified hydrogen, to the reactor coolant system. However, the normal mode of operation is the discharge of this gas stream to the ventilation vent, in order to limit the buildup of long-lived gaseous fission products, namely krypton 85, in the reactor coolant. 11.3.4.2 Process Vent Portion of the Radioactive Gaseous Waste System Low activity ae rated gas streams enter the process vent filter assemblies, are monitored, and are discharged to the environment via the ventilation vent. 11.3.4.3 Ventilation Streams Ventilation streams with potential activity, except the turbine building ventilation exhaust, are discharged through the ventilation vent. The turbine building ventilation exhaust discharges through release points on top of the turbine building. Upon the detection of significant activity in any ventilation stream, except that from the turbine building, these ventilation streams are diverted through filters before being discharged into the ventilation vent, 11.3.5 Performance Tests The initial performance tests are carried out to verify the operability of the canponents, instrumentation, and control equipment of the radioactive gaseous waste system. During plant operation, the system is used at all times and is under continuous surveillance; therefore, periodic testing is not required except for safety class valves which require testing as specified in Section 16.4-2. 11.3.6 Estimated Releases The potential sources of radioactive cascous errluents re given in Fig. 11.4-2. The design basis and the expected case releases tor each potentially radioactive gaseous isot.pe are given in l19 Tables 11.3-2 and 11.3-3, in curies per year per nuclide. These tables do not include the solid waste and decontamination building ventilation, relief valves from the evaporators und degasifiers, and the combustible gas control system which are insigni f icant . Values used in these calculations are listed in Table 11.3-1. Noble gases are the only significant isotopes contributing to whole body dose and the iodines are the only significant isotopes contributing to the internal doses . The results given in Tables 11.3-2, 11.3-3 for BiW are generally taken f rom previous analyses which were based on values of 19 11.3-5 q ', J 3 Amendment 19 "CI 12/12/75

SWESSAR-P1 parameters slightly different than those given in Table 11.3-1. Since the results are consistent with those already presented for h D the W and C-E NSSS, revisions in the calculations are unnecessary for this application for Preliminary Design Approval. 11.3.7 Release Points Radioactive gaseous effluents from the process gas portion und process vent portion are released through the ventilation vent. Turbine building ventilation is released from local vents on top of the turbine building. Annulus building ventilation, solid waste and decontamination building ventilation, fuel building ventilation, and containment purge air are discharged through the ventilation vent located on top of the annulus building. The ventilation vent is clearly identified on the plot plan. 11.3.8 Dilution Fa ctors Radionuclides will be released in gaseous effluents from the ventilation vent. The actual release point is at the top of the unnulus building and dispersion will be greatly influenced by joint windspeed and atmospheric stability frequency at the site. Wind direction and building wake effects also influence the location and magnitude of the maximum concentration. Thus, the annual average normalized concentration (CHI /Q) can vary markedly from site to site. Although the actual release point is at an elevation above grade, a conservative analysis can be made using the assumptions of a ground level release. A review of the atmospheric dispersion at 42 sites, based on a ground level release assumption, was performed as summarized in Chapter 2-The average values of ground level CHI /Q as a function of distance from the release point are presented for scushore, lakeshore, and river sites in Section 2.3.5 (Fig. 2.3. 5-1 through 2 . 3 . 5-B ) . The values are for ground-leve] releases in the sector having the largest values and span the distance from 0.5 to 50 miles. The (2 ) 95 percent confidence interval about the mean is also s hown in these figures. Average values for each sector have also been determined in this fashion. The population density as a function of distance for the year 2000, as reported by the AEC in WASH 1258 and summarized in Chapter 2, was used ror representative cases of each type of site (2) in the conputation of population doses. Reference for 11.3.8

1. U.S.A.E.C. " Final Environmental Statement Concerning Proposed Rulemaking Action: Numerical Guides for Design Objectives and LCOs to Meet the Criterion "ALAP" for Radioactive Materials in Light Water Cooled Nuclear FOwer Reactor Ef fluents ," WASH 1258, July 1973.

f (. j l;l / ;) U!a 11.3-6 Amendment 19 12/12/75

SNESSAR-P1 11.3.9 Estimated Doses A detailed discussion of potential exposure pathways is presented in Section 11.6.2. The annual whole body dose to an individual and to the population from the gaseous effluents has been calculated on the basis of these analyses, using the conservative ground level release assumption and the semi-infinite hemispherical cloud submersion method. The whole body population dose equivalent rate was computed using average CHI /Qs for each sector and a population distribution out to 50 miles appropriate to each type of site. Population doses and average individual doses are shown in Tables 11.3-5, -6, and -7. The mean and +2 values relate to the data obtained for 42 sites evaluated in obtaining CHI /Q values. The average value for each of the 16 sectors was used, not the maximum downwind directions as in the case of individual doses reported graphically in Section 11.6.2. The infant thyroid dose estimates are conservatively based on the method specified in Regulatory Guide 1.4 2 and a consumption rate of 1 liter per day. More realistic analyses would result in much lower calculated dose rates. Credit has not been taken for that portion of the year when cows are not on pasture and, consequently, do not ingest iodine. For example, when cows are on pasture only 6 months of the year, dose equivalent rates would be reduced by a factor of 2. A discussion of the infant thyroid doses and other organ doses is presented in Section 11.6.2. As can be seen from the date presented in Sections 11.3.1 and 11.3.2, a B&W or W-3S NSSS has releases of the same order of magnitude as a W-41 or C-E NSSS . Consequently, Tables 11.3-5, 11.3-6, and 11.3-7 are not duplicated for BSW or W-3S. 25 11.3.10 Interface Requirements The radioactive gaseous waste system continuously degasifies the CVCS letdown as modified in Fig. 9.3.4-1 (sh 1) . This design meets all NSSS Vendor requirements for coolant degasification. Radioactive nuclide inventories, liquid volumes, and shielding requirements utilized for the SWESSAR-P1 design are calculated by Stone & Webster. NSSS Vendor interface information on the applicable systems and components are compared to Stone S Webster calculEtions. The applicable NSSS Vendor information is used to 11.3-7 Amendment 25 b L, '!/ ~4/ o/76 000

SWESSAR-P1 complement the Stone & Webster calculation if the comparison indicates that it is more conservative. Doses will be estimated on a case-by-case basis in the U-A SAR to account for site-dependent variables such as dilution factors and pathways and to indicate conformance with 10CFR50, App. I "ALARA" 25 criteria. Realistic dose models will be used in those analyses. The data reported herein represent conservative analytical ap-proaches. O

                                                         , ,     O, 11.3-8                    Amendment 25 4/30/76

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                                                                                                                   'O Ventilation Ventilation  Wtol              sg 1-131            -

1.8 E-02 9.7 E-04 3.5 E-01 2.5 E-01 8.9 E-02 8.6 E-04 7.0 E-01 I-132 - 6.1 E-03 1.2 E-04 1.2 E-01 7.0 E-02 2.5 E-02 2.9 E-04 2.2 E-01 1-133 - 2.7 E-02 9.6 E-04 5.4 E-01 3.5 E-01 1.3 E-01 1.1 E-05 1.1 E 00 I-134 - 3.8 E-0 3 4.4 E-05 7.5 E-02 1.5 E-02 5.6 E-03 - 9.9 E-02 I-135 - 1.5 E-02 4.2 E-04 2.9 E-01 1.6 E-0I 5.7 E-02 - 5.2 E-01 Kr-83m 3.6 E 01 1.1 E-02 1.2 E 01 9.9 E 01 1.1 E-02 - 1.5 E 02 17 Kr-8Nm 6.6 E-02 2.7 E-02 1.1 E-01 4.5 E 01 3.8 E 02 4.3 E-02 - 4.3 E O2 Kr-85 5.1 E 03 - 1.4 E 00 9.2 E-01 7.9 E 00 8.9 E-04 1.7 E-01 5.1 E 01 Kr-87 - - 2.0 E-02 3.2 E 01 2.7 E 02 3.1 E-02 - 3.0 E 02 Kr-88 2.1 E-05 - 1.2 E-0* 8.7 E 01 7.5 E 02 8.4 E-02 - 8.3 E O2 Kr-89 - - 7.2 E-05 2.7 E 00 2.3 E 01 2.6 E-01 - 2.6 E 01 Xe-13tm 9.5 E 01 7.1 E 00 9.0 E-02 3.0 E-01 2.5 E 00 2.8 E-04 4.5 E-03 1.0 E 02 Xe-133m 1.0 E-04 2.8 E 01 7.9 E-01 1.6 E 01 1.4 E 02 1.5 E-02 4.3 E-03 1.H E 02 Xe-133 1.5 E 03 4.3 E 02 8.4 E 01 6.9 E 02 5.9 L 03 6.7 E-01 6.1 E-01 8.7 E 01 Xe-135m - 4.8 E 02 2.2 E-02 3.0 E 01 2.5 L 02 2.8 E-02 1.2 E-06 7.6 E O2 Xe-135 - 7.4 E 02 6.5 E-01 1.0 E 02 9.0 E 02 1.0 E-01 H.5 E-05 .7E 01 Xe-137 - - 1.3 E-04 4.3 E 00 3.7 E 01 4 .1 E -0 3 - 4.1 E 01 Xe-138 - - 1.8 E-03 1.5 E 01 1.3 E 02 1. 5 E -0 2 - 1.5 E O2 w-3S 1 of 1 *

                                                                                                           . 1?

f> . s_s C _.C ( A g 7 1 v 2 2 2 3 2 0 0 2 0 0 1 1 0 2 1 1 1 0 l 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e a - - - - E E 5j t E E E E E E E F E E E E E E E E D

                               '   5    4    9        4     4    0    5     1    2     0     5       7     8     6      3      5       7           r R.                           .                                                                    .

2 2 3 1 3 6 3 1 3 1 4 5 2 2 3 2 2 6 r m n 5 go 4 5 6 2 4 4 2 ni 0 0 0 0 0 0 0 0 li t eda E E E E E E E E ull Fii 0 5 3 - - - - 0 - - - 5 1 3 - 0 - - ut tin 1 3 1 2 5 5 7 1 e V

            )                   n F                    o                                                                   5     3     3      4      5       5 egn       4    4    4    6   4     5    4    6     5    4     6     6 C

J nnt 0 0 0 0 0 0 0 0- 0 0 0 0- 0 0 0 0- 0 0 C ii a - - - - - - - - - E E E E E bdl E E E E E E E E E E E E E D rli 0 6 5 E uit 5 7 3 5 5 2 4 5 5 8 8 2 6 7 0 T Tun 3 3 3 3 9 2 8 9 6 2 2 4 1 7 C Be 6 4 8 1 E V P X E ( 2 2 1 1 1 0 1 1 3 3 3 6 4 1 0 2 1 0 r 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S - - - - - - - m o - - - - - - - E E L atrt E E E E E E E E E E E E E E E L C eeic 9 4 9 3 R tJAe 8 3 3 7 7 2 1 6 5 0 1 8 4 0 1 - U t S i E. P 3 O n E 1 1 2 9 9 2 1 3 0 2 8 8 5 2 2 2 1 6 1

 -          S    a H     1          l                                                                                                                                  f A     1      P f   P                n                                                                                                                    o S            f   /                o S     E      E    r       s gi 1            0       1      0           1 E     L U        Y        unt       2    2    2    3   2     1    0    2     0    0     1     1       1           1 W     B      L /         li   a     0    0    0    0   0     0    0    0     0    0     0- 0          0     0     0      0       0      0 N     A      F   1        s
                         - dl        -    -     -   -   -     -          -                      -      -            -

T F C nlf E E E E E E E E E E E E E E E E E E E nit 3 0 Aun 1 2 4 5 2 1 8 6 2 6 2 2 5 5 0 1 S Be 1 U V 3 1 4 5 2 4 1 4 1 3 1 1 8 3 3 4 2 O 6 F 0 S t 0 3 6 4 E A n 4 5 5 6 5 4 3 2 4 3 6 2 2 2 G e 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 m - - - - - - - - - - - - - - - - - 0 D ne E E E E E E E E E E E E E E E E E E 1 E ig 2 7 5 2 5 T A ar t u 1 5 6 0 0 0 2 8 7 4 8 1 4 M nP 1 1 9 4 4 5 5 6 9 6 3 4 5 5 1 3 8 1 I o s T C e S t E 3 4 3 4 3 0 3 1 0 1 1 1 a s n 0 0 0 0 0 0 0 0 0 0 0 0 c s eti o E E E E E E E E E E E E i d cnt n oer 5 9 2 8 1 7 3 - - - - 2 2 4 6 6 - - i rVo 6 2 3 3 5

• P P 1 5 2 2 1 1 1 3 2 1 5 1 -

s n 0 0 0 0 0 s o E E E E E esi cat oGr - - - - - - 6 5 - - - 4 3 8 - - - - P r oP 2 2 2 5 7 " g m m3 m o 1 2 3 4 5 3 mm S 5 7 8 9 1 3 3 3 3 5 3 5 3 7 3 8 3 t 3 3 3 3 3 8 8 8 8 8 8 1 1 1 1 1 1 1 S

                                                                                                   -           -      -      -       -      -         3 r r- rK rK rK r Ke e o 1    1    1     1   1       -          -          -     -             -

I s I I I I 1 K K X eX eX e X X X e e X W

Qd M :-. SWESSAR-P1 TABLE 11.3-2 rw C.D ESTIMATED GASEOUS EFFLUEffP SOURCES (DESIGN CASE) Q Ci/Yr/ Plant s

                                                                                                                               'J.D Process    Process                    Annulus             Steam Jet Turbine     Fuel                              x3 Building                Air   Building    Building Gan      Vent         Containment                                                          1btal Portion         Purge      Ventilatio:s        Eiect or  Ventilation Ventilation Isotope    Portion

1. 0 E -01 5.0 E-01 1.7E-01 9.1E-04 8.6E-01 I-131 -

8 . 4 E -0 2 2. 0 E-0 3 2.8E-02 1.3E-01 4.5E-02 3.2E-04 2.3E-01 1-132 - 2.3E-02 1.5E-04

1. 4 E-01 6.7E-01 2.2E-01 1.4E-05 1.1E 00 1-133 - 1.1E-01 1.4E-03 4.6E-05 1. 5E -0 2 7.2 E-0 2 2.4E-02 -

1. 2E-01 I-134 - 1.2E-02

6. 6E-0 2 3.2 E-01 1.0E-01 -

5. 4 E-01 1-135 - 5. 3E-0 2 5.2E-04 1.2E 01 1.0E 02 1.1E-02 - 2.4E 02 Kr-81m - 1.2E 02 1.2E-02 4.2E 02 4.4E-02 -

4.7E 02 Kr-85m 4.9E-02 8. 6E-0 2 1. 2E-01 5.0E 01 1.4E 00 1.2E 01 1.3E-03 2.0E-01 5.3E 03 Kr-85 5.3E 03 - 2.1E 00 Kr-87 - - 2.0E-02 3.3E 01 2.8E 02 2.9E-02 - 3.1E 02 8.0E 02 8.3E-02 - 9.0E 02 Kr-88 1.5E-05 - 1.3E-01 9.4E 01 7.1E-OS 2.7E 00 2.3E 01 2.4E-03 - 2.6r 01 Kr-89 - 3.8E 00 3.9E-04 4.7E-03 1.3E 02 Xe-131m 9.5E 01 3.4E 01 1.4E-01 4.5E-01 1.1E 00 2.3E 01 2.0E 02 2.0E-92 4.9 E-0 3 3.3R 0 2 Xe-133m 9.2E-04 1.*E 02 8.8E 03 9.1E-01 6 . 6E-01 1.3E G4 Xe-133 1.5E 03 1.8K 03 1.2E 02 1.0E 03 3.OE 01 2.5E 02 2.6E-D2 2 . 8 E-0 6 2.0E 03 Xe-135m - 1.7E 03 2.6E-02

2. TE 03 5.4E-01 8.5E 01 7.3E 02 7.5F-02 1.5E-04 3.5E 03 Xe-135 -

4.2E 00 3.6E 01 3.8E-03 - 4.1E 01 Xe-137 - 1.3"-04 Xe-138 - - 1.8E-03 1.5E 01 1.3E 02 1.4E-02 - 1.5E 02

   " " indicates < 1.0E-0 6 7enen % nt l ';

B&W 1 of 1 1 '/1 ? f'

SWESSAR-P1 OD TABLE 11.3-3 c3 C_7 ESTIMATED GASEOUS EFFLUENT SOURCES ( EXPECWD CASE)

                                                                                                                                ;~,

ci/Yr/ Plant C Steam s3 Process Process Annulus Jet Turbine Puel Gas Vent Containment Building Air Building Huilding I sotope Portion Port ion Purqe "ent ilat ion Eject >r Ventilat-ion Ventilation Tbtal I-131 - 7.4E-03 2.2E-04 9.2E-03 4.5E-03 1.5E-03 1.1E-04 2.3E-02 I-132 - 2.0E-03 1.7E-05 2.5E-0 3 1.2E-03 4.0E-04 3.8E-05 6.1E-03 1-133 - 9.0E-03 1.4E-04 1.1E-02 5.6E-03 1.9E-03 1.7E-06 2.8E-02 q I-134 - 8.9E-04 4.2E-06 1.1E-03 2.8E-04 9.2E-05 -

2. 4 E -0 3 I-135 -

4 .0E -0 3 5.0E-05 5.0E-03 2.5E-03 8.4E-04 -

1. 2 E-02 Kr-83m - 5.9E 00 5.2h-04 4.3E-01 3.0h-01 3.1E-05 -

6.6E 00 Kr-85m 2.OE-03 4.1E-03 5.8E-03 2.02 00 1.4 E 00 1.4E-04 - 3.4E 00 Kr-85 2.6E 02 - 1.0E-01 7.0E-02 4.8E-02 5.0E-06 2.4E-02 2.6E U2 Kr-87 - - 1.0E-03 1.3E 00 8.8E-01 8.9E-05 - 2.2E 00 Kr-88 - - 6.9E-03 3.9E 00 2.7E 00 2.8E-04 - 6.6E 00 Kr-89 - - 3.8E-06 1.2E-01 7.9E-02 8.0E-06 -

1. 9 E-01 Xe-131m 2.4E 01 3.0E 00 6.2E-02 1.8E-01 1.2E-01 1.3E-05 5.6E-04 2.8E 01 Xe-133m 4. 9 E-0 5 9.1E 00 7.4E-02 1.2E 00 8.3E-01 8.6E-05 5.9 E-0 4 1.1E 01 Xe-133 7.7E 01 1.4E 02 8.0E 00 5.2E 01 3.6E 01 3.7E-03 7.9E-02 3.2E O2 Xe-135m -

1.3E O2 2.1E-03 3.0E-01 2.0E-01 2.4E-03 - 1.3E 02 Xe-135 - 2.0E 02 4.1E-02 5.1E 00 3.5E 00 4.HE-04 1.8E-05 2.1E 02 Xe-137 - - 8.2E-06 2.1E-01 1.4E-01 1.5E-05 - 3.5E-01 Xe-138 - - 1.5E-05 1.0E 00 6.9E-01 6.9E-05 - 1.7E 00 "r indicates <1.0E-06 nt,w 1 of 1 An e n< !ro nt 1e 1.? 12 f,

[hh Y L 2 tJ [.-)}

                      'O O P

C# e~ ne

                                                                                                 \

emp e e N N m N N e N N m m e.e N hk Ee 000000o0000000000o e m' 1 e 1 e a e WWW t WWEWWWWWWWWWWW h N.e.d.e.O.N. N e. e o.N. o. m. m.m. . P. e. e. ( V AN#=fNetesN*NewNew b CT wl me o mmP#e C g, *e# e

• mi 00 Q C0 e ooQo T se i 1 4 i e f e 4 i f M m ef W W W W WW W WWWWW w C. f P. *. C. l #. e. e. l o. l Ne 2. ce e. a. l 1 f $, P am #. he N cetN%

_ _E ' W L 4C9 7* NNNmNNNmNemeNeNemN hN kkk k k k k 4 m =! WWWWWWWWWWWWWWWWWW f k= C 9M9eN&PNSNweeeeere M 2? m> O P W e e e d e s e' m' M' N e' e' e e N o w M 6 pNeNe*NONNeoNmNNP N W E wC 000000000o00000000 9wm I e i e e N 0 g L04 we 4 WWWWWWWWWWWWWWWWWW e 5 p n e m. m. 6 4. m. em m.e e M. e. m. e. m. b. e. c. h. e. G m t O C W. PrNewemhNNNN*eN4Me e i e g e b m w e z C M W Cl e W 0, t*t + Q M M w m W2G' ql weeNeweeewoweNewee S b A V C+* Mtw o oooooooooooooooo e I I i M D Dev A C WWWWWWWWWWWWWWWWWW e i 34 m.m e eN e.ze e. e.h. N. a. eh e.c. ee e. &.M e re Q &> M*chNeemmmNNe@Nhee O W p C

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• l i eNmeN i l wtO NeweN A > A, e*Erwem m C Nm e N3m e C 00 o 003 i

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                                      **            Q                                                                                                                   e           *= E er
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bl W@ e W e W W W W W W W W W W W in: W Ia3 W 'N m C O O cc P *= O W O # P h 4 # C i e P e e e e e e e e e e e e e e e e o e m e # @ N @ m N N @ N N c N e= P m s= C m - e, e r 4 e e N e a N 4 # QC1 e o O O c C O O O i O o T o T se se m

                                -             a        4     e            T               i W

e l W a N W e W laa ( 3e W W W l W l N M N 4 l r** N 4 O P 1 LL m O 4 & o e e e e e e e e e t e e m (C m P N @ CD

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                %                      =s ,i L                 tr wi                             @     e e e                  @     c e           4         @      e m m                     e      e c C+Mi C ciO a eO e O                   O      3     o Q             O     O      O      O        O       O        O        O       O      O      O I                                   e                             6      e         6        4       6     I      i w t wl            e        6             6     4      4       6              4             4 W      W         W       W        W      W     W e sj W             W        4      W     W      W       W       N     W      W       N m cc             ee      a     @
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g &> a m e m N N P m G3 N h W be P O e= *= 6 m mm @ e e O N P O N N P P Cd ww0 O O O E - C. O. O. O. W W

o. ?o W W O,

W O, O, W

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                                  *p         N me     N la3     4 cc e ** ecc e               N        O iaJ    ial ee e eo cc                     @         m        P in3 ee     a     e e

a e e e e e e e e e e e A N N N P @ d i e P *= e c N *= m to N cc & M & t

• C

      *=. M      (d    9                Cf                                                                                                                                             P D. e   U    e.e               a                                                                                                                                              me t'                                                                                                                                          O L1         v     k     m C g, l

N N N m N *= 0 N O O s= ** * *= *= 0 *= O O O O O O O O O O O O O O O L1 laj L1 > D = a6 O O O O i i s i I e s= W n N a =J e i e e e e e W W W M W 3 @ b

• CM w W W W W W W &aJ .s3 W IaJ W W e N ssl

                                                                                                                                                                        *=     0 bl  8C     Z    Q      C*C              e              N      ee *=o *= e          G3       e      N     @      N         P      N        er b                  c lll 4             e    '"e        e                           e       e     e       e      e        e       e       e         e e

e e e aC E > N *= e A N e P e P m *= *= cc m N N P ina s L1 a e m N e M 4 N N O M N 4 e C4 e # @ @

                                                                                                                                                          ?      ? ? ?

3"b ?  ? ? ? ? ? ? ? ? ?W ? ?W ?

                                   ~

f W W W W W 2 W W W W W W W W W m *= W O W O N e N 4 G C

                                   ^

O. # A O N e N @ @ e W e e e ED e e e e e e e e e e o e e e d P *= *= a e e e @ e @ m W A A P m CC *=

                 ]

h es e C; m m - e m e m O O N N N F m ce C Oi o O O O O o o O O c 6 6 e i e 4 1 L] iN Q M eJ W W W W W W la3 1 6 i W W W is3 W l 1 O C Leg #e E O e m m o co e O *= e 6 e e e e e e e e e e 6 0-

                                  >M          e        P      @      mm            A       e                                     P      @        P        P       P e          C                                                 m       N             @               P      +         P e          C                                                 O       O             O               O      O        O
                              &m*                                                             4                   e                        6 W

01& 1 8 e 1 I 4 W W 4 la3 1 W N 4 1 1 1 QU6 O @ 03 p e (D. O. . . E' e. m N P N e a k,l P N m e @ ma ee e 6 m e m s mAm m m m m a# e o = m C m *= *= *= *= ** *= *=

                                        &      M       M       m      m            CD       G      CD            CD      G3 g
                                               *=      P       P      5"    P        l        l      l             4        l      l        l       {         l      l      l     {

W  % @ & 4 & 4 f i uH mH H i I I l h ,h,

                                                                                                                                   %                        M       M     M      M       Q M      M       M       M      M      M      tre     ur                    K      nc       M       M       W

SWESSAR-P1 TABLE 11.3-4 RADIOACTIVE GASEOUS WASTE SYSTEM COMPONENT DATA Process Gas Charcoal Eed Adsorbers' Number 2 Capacity, height (max) x diam, ft x ft W-41 24 x 7.5 W-3S 16 x 7.5 BSW 22 x 7.5 U C-E 20 x 7.5 Weight of charcoal, lb W-41 44,000 1 W-3S 23,000 17 BSW 38,000 C-E 32,000 Operating pressure, psig 1 Design pressure, psig 335 Design temperature, F 200 Material of construction 304 SS Degasifier* Number 1 Capacity, gpm W-41 500 j7 W-3S 150 BSW 250 C-E 150 Operating pressure, I sig 2 Design pressure, psig 100/ full vacuum Design temperature, F 350 Material of construction 304 SS Process Gas Receiver

• Number 1 Capacity, ft3 40 Operating pressure, psig 75 Design pressure, psig 125 Design temperature, F 300 Material of construction 304 SS
• Designed in accordance with ASME Section III, Class 3 1 of 5 {g9 09} Amendment 17 9/30/75

SWESSAR-P1 TABLE 11.3-4 (CONT) Degasifier Recovery Exchanger

• Number 1 Duty, Btu /hr W-41 13,000,000 g W-3S 3,900,000 ESW 6,500,000 C-E 3,900,000 Tube side - Letdown stream (Feed)

Operating pressure, psig 50 Design pressure, psig 300 Operating temperature, in/out 115/157 Design temperature, F 400 Material of construction 304 SS Shell side - Degasified letdown stream (liquid ef fluent) Operating pressure, psig 50 Design pressure, psig 175/ full vacuum Operating temperature, in/out, F 219/167 Design tanperature, F 350 Material of construction 304 SS Degasifier Feed Preheater* Number 1 Duty, Btu /hr W-41 20,900,000 lj7 W-3S 3,900,000 i B&W 10,500,000 C-E 16,300,000 Tube side - Letdown stream (feed) Operating pressure, psig 40 Design pressure, psig 300/ full vacuum Operating temperature, in/out F 167/250 Design temperature, F 400 Material of construction 304 SS Shell side - Saturated steam Operating pressure, psig 100 Design pressure, psig 175/ full vacuum Operating temperature, in/out F 338/338 \17 Design temperature, F 400 Material of construction CS

• Designed in accordance with ASME Section III, Class 3 2 of 5 , Amendment 17 e)

L/dgn 9/30/75 U U '1

SWESSAR-P1 TABLE 11.3-4 (CONT) Degasifier Condenser

• Number 1 Duty, Btu /hr W-41 7,800,000 2,400,000 U W-3S B&W 3,900,000 C-E 2,400,000 Tube side - Degasifier ef fluent (steam and gas mixture)

Operating pressure, psig 2 Design pressure, psig 100/ full vacuum Operating temperature, in/out F 219/190 Design tm.perature, F 350 Material of construction 304 SS Shell side - Component cooling water Operating pressure, psig 125 Design pressure, psig 150 Operating temperature, in/out F 105/135 Design temperature, F 220 Material of construction CS Process Gas Compressors

• Number 2 Capacity, setm 3 Operating pressure, psig 75 Design pressure, psig 1,800 Design temperature, F 300 Material of construction CS Process Gas Compressor Aftercooler*

Number 2 Duty, Btu /hr 2,000 Tube side - Ccxnponent cooling water Operating pressure, psig 125 Design pressure, psig 150 Operating temperature, in/out F 95/96 Design temperature, F 200 Material of construction CS Shell side - Process gas (noncondensables) Operating pressure, psig 75 Design pressure, psig 1,800 Operating temperature, in/out F 220/110 Design temperature, F 300 Material of construction CS

• Designed in accordance with ASME Section III, Class 3 3 of 5 /,y nPi Amendment 17 0C/ U/J 9/30/75

SWESSAR-P1 TABLE 11.3-4 (CONT) Process Gas Compressor Prefilter* Number 2 Capucity, scfm, noncondensable gas 8 Operating pressure, psig 1 Design pressure, psig 335 Design temperature, F 200 Material of construction CS Process Gas Refrigerant Dryer

• Number 2 Capacity, scfm saturated water vapor at 190 F 5 scfm noncondensable gas 8 Operating pressure, psig 1 Design pressure, psig 335 Design temperature, F 366 Material of construction 304 SS Process Vent Filter Assemblies Number 2 Capacity, scfm 300 Operating pressure, psig 0.2 Design pressure, psig 0.5 Design temperature, F 300 Material of construction CS Process Vent Blowers Number 2 Capacity, scfm 300 operating pressure, psig 2 Design pressure, psig 15 Design temperature, F 300 Material of construction CS Trim Cooler
• Number 1 Duty, Btu /hr W-41 13,000,000 W-3S 3,900,000 U BSW 6,500,000 C-E 3,900,000 Tube side - Degasified letdown steam (effluent)

Operating pressure, psig 85 Design pressure, psig 175/tu11 vacuum Operating temperature, in/out F 167/115 Design temperature, F 350 Mate, rial of construction 304 SS

• Designed in accordance with ASME Section III, Class 3 4 of 5 .

                                                   ,3i Amendment 17 h bkl  !) <          9/30/75

SWESSAR-P1 TABII 11.3-4 (Cottr) Shell side - Component cooling water Operating pressure, psig 60 Design pressure, psig 125 Operating temperature, in/out F 105/115 Design temperature, F 220 Material of construction CS L* gasifier Recirculation Pump

• Number 2 Capacity, gpm K-41 250 W-3S 150 U BSW 250 C-E 150 Operating pressure c psig (discharge) 100 Design pressure, psig 200 Design temperature, F 350 Material of construction 304 SS
• Designed in accordarce with ASME Section III, Class 3 5 of 5 Amendment 17

                                         / t. u O p,
                                                  / ;J       9/30/75 0o/

E e=NNNNmmmm I I I 4 0 0 I i 1 e" e e o O O O O O c m & c *= 0 a) a> w 6 e= A C 8 8 8 1 *= 6 e a N a2a m N e= 6 1 CD h m e m M A N e 4 e e e e o e o e e \

                            &     N e al e= N e 4 0) e                       L    000000000                                       4,s o L       e e e e e e e e e                                                                             cm OOOOOOOOO                                                                                           \

c 3 a 3 4 1 6 **

• e= N N N N m M t e- 0 O O O O *= *= *= + 4 8 I I e i I I l w I G e= N a3 e e e e to P .O O6N@mee@O N e= ** co a e- ** re 4 N 4 e e= e N e o e e e e e e N @e *=e "e e e e e e e N <a

                            +     000000000

• 000000000

      /.

O em ee=eNNNNmm 4 6 8 4 I I I e I l a C00000000 m C eNeJheOON D C m e N e= e a N e @ m

                                                                               -     e e e e e e e e e o                      4 o    emaeoo@Ne emmemeNmm                                  f    000000000 u                 2.      e e e e e e e e e 000000000 e

g Ian C 4 CW O c1 - >

       -w                                                     v4          i DA        Ce     M                                       a         G 0-      I                                    s O        Q e.,  **4     (,)

• = 5 g W 4 A m 1 & e=

I e M e4 E g q s= A & W u % e g%

e. 9 4 t C M et Oi >

D o o o o e *= e- *= e aC CeP*=NNNNN e t) W bp (L c

                             *                                                .a         4 I I I I I i i 4          Z      N c co*=CD e m a3 O                        W    OeeO@NNeo

$ ad 8C se

                  >W                N e @ e *= m a 4 a3                             e a N N e e N e *=

O WC ime N e e e e e o e e e N e e e o e e o e e b Z sg -,4 4 + 000000000 O V Ca.

• C00000000 WG Sw bD e9 39.

E'd 9C "x M*

        -G F

z os 6 M o a 2 9 7 m , e M s= e O il v= i e O a c SH Ue

                                                                                                                             -m Um Ce W

4 00000 o Se 00000 eNmaD m4 y o-e NmdA*NmmA & 9 -" ne Ns m d b,

                                         # 4     8 st i l                              e l i t i s i l i a.g
                           --        000000000                              ..e.sm 0000c0000 a                                                n-
                                                      - P. m g

e . A S p +ar J r.e>n, ) p 7

                                                     /bga         p 4 ' 4 t. o             ,'f t -
                                                                                               ,4
                                                                  '# d L E Gl g h g !J 'j *

• b O; 'l n () 0 U/

9 SWESSAR-P' TAliLE 11.3-d DOSE TO Tl!E POPUIATION AT A IAKESh0F E SITE FRm SimMERSIO2. IN T1tE GASEOUS EFFLUENT (WPOLE BODY GAPS 3) Cumulative Pop 11ation Dose (rerson-Rem /yr)

• Dist.ince Ist.W C-1 W igi_le s) +2 sigra Pean + 2 81<ra Pean 0-2 0.44 0 0.19 0 9.21 0 0.86-1 0-3 0.74 0 0.33 3 0.35 0 0.14 0 0-4 0.11 1 0.47 0 0.52 0 0.20 0 0-5 0.13 1 0.55 0 n.59 0 0.23 0 0-10 0.22 1 0.10 1 0.11 1 0.43 0 0-20 0.39 1 0.18 1 0.18 1 0.74 0 0-30 0.58 1 0.27 1 0.27 1 0.11 1 0-40 0.77 1 0.36 1 0.35 1 0.14 1 0-50 0.91 1 0.42 1 0.41 1 0.16 1 Average Individual Dose (mPem/yr)

Distance P f,W C-F W (miles) +2 Si g Fean +2 Sigma Mean 0-2 0.10 0 0.44-1 0.24-1 0.10-1 0-3 0.47-1 0.21-1 0.17-1 0.65-2 0-4 0.31-1 0.13-1 0.12-1 0.45-2 0-5 0.20-1 0.91-2 0.98-2 0.37-2 0-10 0.96-2 0.47-2 0.42-2 0.17-? 0-20 0.44-2 0.21-2 0.18-2 0.72-3 0-30 0.22-2 0.10-2 0.95-3 0.38-3 0-40 0.15-2 0.68-3 0.65-3 0.26-3 0-50 0.11-2 0.47-3 0.51-3 0.21-3 Os CD -c

• Notation 0.21 0 = 0.21 x 10e.

C. 'D .- 1 of 1 feendmen t 11

 -                                                                                                               5/30/75

SWESSAP-P1 TABLE 11.3-7 DOSE M Tlit IOPULATION AT A SFASIKJRE SITE FFOM SUDFIRSION IN T1:1. GASEUIS EFFLULUT (Wi! OLE PODY CAFFA) Cumulative Poynilation Dost? (twrson-Rem /yr)

• Distance C-E W (n.i les ) BEW +2 Sigma Mean + 2 Signi Mear.

0-2 0.14 0 0.72-1 0.82-1 0.38-1 0-3 0.27 0 0.13 0 0.14 0 0.67-1 0-4 0.41 0 0.19 0 0.22 0 0.99 1 0-5 0.46 0 0.21 0 0.24 0 0.11 0 0-10 0.12 1 0.56 0 0.65 0 0.30 0 0-20 0.27 1 0.11 1 0.14 1 0.61 0 0-30 0.40 1 0.17 1 0.20 1 0.87 0 0-40 0.56 1 0.23 1 0.27 1 0.12 1 0-50 0.73 1 0.31 1 0.34 1 0.15 1 Average Individual Dose y, fmFem/yr) 0-2 0.78-1 0.39-1 0.22-1 0.10-1 0-3 0.39-1 0.17-1 0.14-1 0.65-2 0-4 0.23-1 0.10-1 0.95-2 0.44-2 0-5 0.17-1 0.73-2 0.84-2 0.39-2 0-10 0.86-2 0.39-2 0.32-2 0.15-2 0-20 0.39-2 0.16-2 0.14-2 0.64-3 0-30 0.19-2 0.78-3 0.84-3 0.37-3 0-40 0.13-2 0.52-3 0.55-3 0.24-3 0-50 0.91-3 0.39-3 0.40-3 0.18-3

• Notation 0.82-1 = 0.82 x 10-n.

CS CP .a C. 1 of 1 Amendment 11

%O                                                                                 5/30/75 c f;

SWESSAR-P1 TABLE 11.3-8 NSSS DESIGN AND OPERATING PURIFICATION FLOW RATES Maximum Normal Maximum Expected Design Vendor (qpm) Normal (qpm) (qpm) (qpm) Westinghouse-41 100 250 450(1) 500 17 Westinghouse-3S 75 120 120 150 Babcock & Wilcox 50 200 200 250 Combustion Engineering 84 128 128 150 (1) This rate occurs during refueling. enq Uii [l} 1 of 1 Amendment 17 9/30/75

I l If_l.G11.3-1A FIG. 11.3-18 IFIG. 11.3-1 I I FROM /TO , l - - GASEOUS l VENT g l l l ' l I l l i I DEGASIFIER DEGASIFIER CONDENMR J k IP EATER 5 i DEGAS 1FIER RECOVERY I A *6 - l I "A" l I FROM CHEMICAL O U V- l AND VOLUME O i l CONTROL FROM l \/ l GASEOUS l l OESASIFIER  ; DRAINS _ _ _ _j TRIM COOLER i j

                                                                        ]                                                                       l a                            l I /N TO CHEMICAL                                                                                                                                 l l                                                                   '
                    %[

d AND VOLUME l 3 l p CONTROL l l I DEGASIFIER 8 RECIRCULATION PUMPS CV ------ ------ ---- - PROCESS

                  ------~~----

T- BE0 A FRCM AERATED r l VENTS l I FROM y I COMBUSTIBLE GAS I CONTROL U  ; TO I I VENTILAT10N l Q FRCM CONDENSER AIR REMOVAL

                           ~

Fy g ENT l d b PROCESS VENT FILTER 3 g MBUES PROCESS VENT BL0rERS l

                                                                                 -                                             l l

FROM BORON s RECOVERY I FROM I RA010 ACTIVE

I L10Ul0 MASTE l

NOTE: F I G. 11. 3-1F 1 ALL STPASSES. INTERCONNECTIONS, VENTS. DRAINS, INSTRUMENTS. MONITIORS AM VALVES ARE SHOIN ON THE FOLL0flNG SHEETS. 4 qn i ViJ

,                                                                                                                     6 @)

i

s J i PROCESS GAS PROCESS GAS iFIG. 11.3-10 I FIG. 1.3-1E REFRIGERANT l COMPRESSOR PROCESS BAS l I PROCESS GAS DRYERS PREFILTERS PROCESS GAS COMPRESSOR I l C0sPPES$0RS AFTERCOOLERS l RECEIVER TANK . I I A', L I l I

                                                                                  >                      )( : TO ILATluN N-d* ]       l l                           l lY I

l REACTOR PLAhT S GAS SUPPLY -- r=

                                                                                                            - TO CHEMICAL
                                                                                                            " AND VOLUME SYSTEM                 CONTROL l                                     l I                       i l                                     I I                                     I I                                      I l                                      I j

i n ~ 1 l L___________________. KID MOUNTED C l l . I xx ' l XX l i AS CHARC0AL SORBERS ,; I I i I I I I I I I I i i l i I I F I G.11. 3-1 I ' I RADI0 ACTIVE GASEOUS RASTE SYSTEM l PER REFERENCE PLANT l 3 e, i SAFETTANALYSISREPORT,(-/ SIESSAR-PI g; ' i e I AietN94ENT 12 t/16H5 ,

I \ / DEGASIFIER RECOVERY E

                                                                                                          \*4
                      \

O CIS-3 SC-2 I

                                   -^

3'  : k SC-3 4" l Q s n 9' cc . FR04 L=4 GASE0 S NNS SC-3 0R FIG 9. 3.3-2 FROM BORON RECOVERY SYSTEif

                                                                                     ;      h'             O                   e FIG 9. 3 6-1                                       \_4,

_a  : - sa g \c 3

                                                                                                 ' t NN%   5.'e-SC-3 TRIM                                              i COOLER                       TO REACTOR PLANT GASEOUS DRAINS COMPONENT CCOLING BATER         --
                                                   -h -     - /
                                                               ) A'/S FIG 9.3.3-2

___ _ _ q FIG.9.2.2-1 l 'gy i TIC CATWCM-- p i r FIG II.3-1B , '7,7

                                                                                                                                  - T TO AERATED                                                                             p                  ' RE DRAINS                                             V l*w       y-hNNS               $3 SYSTEM FIG.9.3.3 1 r

g ri Il O r, NOTES:

1. THl3 PORTION OF THE SYSTEM IS SAFETY CLASS 3 (SC-3)

EXCEPT WHERE OTHERIISE NOTED.

2. THIS SYSTEM IS LOCATED IN THE ANNULUS BUILDING.

3. ALL (SC-3) PORTIONS ARE SEISMIC CATEGORY I.

                                                                                                          ) !            -
 ?  .

f NANGER CONT.0N FIG.ll.3 IB r l TI r 2 ,

                                              ,j,

(. _ ~ CONT.0N

                                                                                                                       ~ ; FIG.11.3-18
                                                   ,        e    l CONT FROM P7                       FIG 11.3-1B d     i

{v} - r, c--W . L hk . (b - - - - A4 L -- __ __ ._ fu OTI Q'- ~

                                                          ,                                                  [IP CONT.FRCid t-FIG.11.3 IB SC-3_         1" NNS
                         'i r TO AERATED DRAINS FIG 9.3.3-1 RIP                      tjuEGASli!ERCONTROLLOGIC q
              -       ~

p g HV CTOR PLANT \ PLING TT)T N 9.3.2-1 s kN ( 4, Z lGIS-4 ) F0, s r.c.

                                                     \- 4 "                        S C >+ SC-2 SC-3 u
                                                            _ TO BORON
                                                              ' RECGYERY NNS (4"        FI G 9. 3.6-1 F I G.11. 3-1 A RADI0 ACTIVE GASE0US WASTE SYSTEM PIR REFERENCE PLANT SAFETT ANALYSl! REPORT SIESSAR-Pl r

f 4 Ou/ !t > AREN05ENT 12 6/16M5

 +

CONT.ON $ f FIG.II.3 1F -/\ 4 CONT FRUM 1 1/2" FIGll.3-1Ap DEGA$lFIER _ _ _ ,

                                                                                                                                      /

h 4 O. F G.1. 12-P s 6 DEGAS!FIER D G SIFIER

                                                                        ,            CONDENSER PREHEATER                     e FF0M REACTDR {4 R$T                       r,                            py 0)lF@ENT C00LlHG IATER (                      /4"
                                                     %                   FIG 9.2.2-1 2 1/2"                                         #

CONT FROM i yyy FIG 11 3-1A I4a l h I f/2 , vvy 4a i g rif myy C0hi DM -- PSL PT [4a " F 10 11. 3- 1 A RIP OEGAS!FIER N/9 6 LT FGi 3-1A 5 ' RIP B" y I i CONT.FRCM _ FIG.11.3-1C , I I i l I I l

                                                                                                              -2           ix!

6" D NOTES:

1. THis PORTION OF THE SYSTEM IS SAFETY CLASS 3 (SC-3)

EXCEPT WHERE OTHERelSE N3TED.

2. THis 1YSTEM 15 LOCATED IN THE ANNULUS ButLDING.

3. ALL (50 3) PORTIONS ARE SEISMIC CATEGORY I

[., f) \ I] h-b

CONT. FROM _ F I G . l l . 3-1E FR0u/TO - CV GASEOUS ' NNS VENTS FIG.9.3.3-2 d C SC-3 P _S i

                                                                                            + CONT. ON p                                                       L 3 /4a      FIG.11.3-lC

_-_--_____q ,

                                 -~

RIACTOR PLMT RIP CON T. ON GAS SUPPtY SYSTDI -

                                                                - -g p y g, j j ,3, g a w FI G.S.5.3 1          I                  i           /fih I                  i'          U pgP
       - 83 h-                       I h q,,

@ '- E s 4 ;--

     , >   t ,

CONT ON (4 -4> F I G ll . 3-1 A s s (pv L.D. 4" (. s 1 N g Y l J. x t. 0 PI vC :Y $ >p t a-x< T 0)) TO AERATED ORAINS E I U* I I' 3-i O

                                                   C 3'3

RADI0 ACTIVE GASE0US RASTE SYSTEM DEGASiflER RECI RCUL ATION PfR REFERENCE PLANT pggp3 SAFETY ANALYSIS REPORT SIE S S A.<-P I f, G -t 3J y, U !

                                                                                                                                             )

Ap[h84LNI 12 6 ' I ti l t 4

i ( CONT.FROM FIG.ll.3-IB  ! ROM R% GAS SUPPLY

                                                                  "               kNS                plg,g,$,g.

m CONT.CN NNS ( FIG.11.3-10 ._ 3fg._ _. S SC-3 SC-3 , da J; l: (,( PORCES! GAS CHARC0AL BE0 N3/4 ADSORBERS

                                        /' h                                                              >
                  . 6 X' X X                 ,-3/4-            XXX                       g X X' X                                   XXX
                                       %J                                       <J
                                                                                        ' 3/4" M

y SC-3 $ SC-3 J L) ) d' {-) b NNS NNS i r

                                                                                                         \

L3/4" NOTES:

1. THIS PORil0N OF THE SfSTFM IS SAFETY CLAS5 3 (SC-3)

EICEPT WHERE OTHE1ttlSE NOTED.

2. THIS SYSTEM 13 LOCATED IN ?HE ANNULUS BullulNG.

3. ALL (SC 3) PORTl0NS ARE 'liSMIC CATEGORTI f 669 10r 0 I

o

i FROM REACTOR PLANT GAS SUPPLY SYSTEM FIG.9.5.8-1 RPLANT/ 3/4* SYSTEM SKID MOUNTED j PROCESS GAS REFRIGERANT g NNS ORYERS(TYP) F-l J ) 3

                                     /                '                               SC-3 l

q{ I 3/4" A-J l l r.c- , S -3/4" i r* + i i 1 1 1 l-CONT.FROM l FI G. ll .3-1B I- -- - - r- _ _ v u l L. M -3/4'

                                      /                               A /S 3 1

• F.C.

                                                                                      =

l T-l RIP * * [. TSH _ /TIlh ' RIP l ' b SKID MOUNTED FROM/TO REACTOR PLANT COMPONENT COOLING IATER FIG.9.2.2-1(TYP) L 3/4' i

                                                                                                             ' CONT.0N RIP                AE                                                  FIG.11.3-1B
                                        '~'             ~~

i 3-IF gp Fila. l l . 3-I C RADI0 ACTIVE GASE0US WASTE SYSTEM PER REFERENCE PLANT SAFETY ANALYSIS REPORT SIES S All-P l O 1] I AMENDEENT 12. 6/16/75 +

4 l SKl0 b0UNTE0 l TO COMPRESSOR I CONTROL S CCNT FROM . l 7 _. a FIC 11. 3-10 ' 3fg._f fpkg _ _ pg 93 g FROM REACTOR PLANT p, Y T r GAS SUPPLY SYSTEM: r, - I l l FIG.9.5.8 1 - - - - - - - - --- ' " NNS - -S C-3 [3/4'l U p d,a r I D PROCESS GAS PROCESS

                                                                                                                                          ' PDM      COMP E P0'                          FL           (TYP)

(b,

                                                                                                                ~1 r

TO CCMPRESSOR CONTROLS FROM REACTOR FLANT 4 i p-- GAS SUPPLY SYSTEM - r, Flb.9.5.8-1 3l NNS -h SC-3 l l I F---- l PT b vm

                                                                    -h                F                   g                          --                 --

b b I 4 i i

                                                                                                                                                      ~

l fDAd TNP l SKID MOUNTED NOTES

           . THIS PORTICN OF THE SYSTEM 15 SAFETY CLASS 3 (SC-3)

EXCEPT WHERE OTHERWISE NOTED.

2. THIS SYSTEM IS LOCATED IN THE ANNULUS aullDING.

3. ALL (SC-3) ARE SEISMIC CATEGORY I.

fLG ] fi : UU/ I LU /

                                                                                                                               /

l

                                                                          '   COMPRESSOR RV                                                      PANEL I                  I
                  .1                             PROCESS GAS COMPRESSOR               1) 4 AFTERCCOLERS               /

( 3_ (TY P) ' SQ [k , I kg  : CONT ON

                                                                                                                '~

GAS O 3/4' ORS SC-3 h y l J_s b eL l h [] lygg ?_h) T I I I __ l _ _ __ _

                                                                                                        /,

l u A e I y SC-3 __ ir b l i 6 i

                             ,  ,         ,6            __

NNS -

                                                                 )      ,

FR0u/TO T 2 1 ' REACTOR PLANT I COMPONENT COOLING TO l WATER GASEOUS ORAINS FIG.9.2.2-1(TYP) l FIG 9.3.3-2 F I G.11. 3-10 RADI0 ACTIVE GASE0US WASTE SYSTEM PER REFERENCE PLANT SAFETY ANALYSIS REPORT SIESSAR-Pl bY l

                                                                                                                               )

AMEN 01EKT 12 6/16M5 t

d Gil3-IF s PROCESS GAS M 4 ( JREP CONT. FROM F I G. 11 10 RECEIVER TANK [

                                                                          ,       WP ,[ VRIP T

i 3/4" ASH - - - - - - - - - ----- i RIP RIP l i

                                                                           ,         i                                     1
                                                                      /    '-        '-                                  'P T PS j

I I3/4" DM

                                                                                                                                                                         =

I I r- - - - ' - - RT l

                                                                                            ,___7__                            _ _7_ __@ 7 I

RIP 9tP RIP NOTES:

1. THis PORil0N OF THE SYSTEM is SAFETY CLASS (SC-3)

EICEPT WHERE OTHERulSE NOTED.

2. THIS SYSTEM is LOCATED IN THE AhNULUS Bull 0IN3.

3. ALL (SC-3) PORTIONS ARE SEISulC CATESBRY 1.

O b .) lO

                                                                                                              /

h HV PCV

                    ,,                   CONT. CM F.C.             F.C.                  FIG.11.3-1B SC      - NNS
   $              p VRIP Y

g f4 d A/S Tsh ' i M

                                                              "  /j. M V

TO VENillATION VENT F I G. 6. 2. 3.1-1 0)b I I t._; s l& Is/s* - - - - . - - - . - - - - h i

                 ~

R PC

                                             ,O FROM REACTOR PLANT                           T)                         TO CHEMICAL G.!b1

• S CT  !"

0] (NSSSSCOPE)

                                       " ch NN S ->4-SC-3 f l G.11. 3-1 E RADI0 ACTIVE GASE0US WASTE SYSTEM PIR REFERENCE PLANT SAFETT ANALYSIS REPORT SIESSAR Pl bl h'l I t

AIEh03ENT 12 6/16/75 I,

I 1 h m FROM BORON [g. EVAPORATOR - - REllEF VALVE [4 F I G.9.3.B -1 FROM RADIDACTIVE LIQUlO MASTE - EVAPORATOR REllEF VALVE I [4 FIG.II.2 1B P i FROM REGENERANT FROM LAUNDRV CHEM! CAL EVAP. MASTE EVAPORATOR REllEF VALVE REllEF VALVE FIG.ll.2 lE FIG.ll.2-IF VMUuE CONTRnt GMS-1 (NS$$ SCOPE) , CONilNUED FROM _ - FIG.ll.3-1B b3' CONTINUE 0 FROM . . FIG.ll.3-lE - ' FROM O AERATED VENTS e FIG.9.3.3-1 b-3 dih FROM s V COMBUSTIBLE GAS CONTROL FIG.B.2.5-1 I k [B' FROM CONCENSER . O AIR REMOVAL /fD'l\ FIG.10.4.2-1 V O F CONTINUED FROM _ L' B FIG.ll.3-lC ' PROCESS VENT [3f4 FILTER ASSEMBLIES NOTES:

1. TH'S PORil0N OF THE SYSTEM 15 NON NUCLEAR SAFETY CLASS (NSt) 4LG **S, UUi 1 *'

LOCATED IN THE ANNULUS Bull 0 LNG. I I

r I i M SL _O IP Y, RIP .

                                                       '____I     M SEE V RIP

[ FIG.11.4-1 p ARM TO VENTILATION "l' - VENT h, ' FI G.6.2.3.1-1

        ;               )l  7 a',

P1 a L mummum L" 8 Pi 8" lm g PROCESS VENT BLOWERS p;g,jy,3_;p RADI0 ACTIVE GASEOUS nASTE SYSTEM PER REFERENCE PL ANT SAFETY ANALYSIS REPORT,- p 1 1 SIESSAR-Pl Od/ iJ T AMENDMENT I2 S/16'75

                                                                                                  )

SYSTEM INTERFACE POINTS - RADIOACTIVE GASEOUS WASTE SYSTEM (GWS) B-SAR 205 CESSAR ID NO. RhSAR-41 RESAR-35 N/A t;/A From chmical and volume control GWS-1 N/A system valve CH105 (Fig. 9.3.4-2) From radioactive gaseous waste GhS-2 From radioactive From radioactive From radioactive systs to chemical and volume gaseous waste system gaseous waste system gaseous waste system to volume control tank to volume control tank control system valve 01107 to volume control tank supply line to CVCS- (Fig. 9 . 3 . 4 -2 ) supply line to valve supply line to valve 1-8316 (SWESSAR-P1 1-8156 (SWESSAR-P 1 Mod 3 (SWESSAR-P1 Fig. 9.3.4-1 Sh ?) Fig. 9.3.4-1 Sh 2) Fig. 9.3.4-1 Sh 2) From makeup and purifi- From valve C1418, CVCS-Mod 1 GWS-3 From valve 1 -8 2 i> 6 , From valve 1-8422 (SWESSAR-P1 Fig. 9.3.4-1 Sh 1) CVCS-Mod 1 (SWESSAR- cation system valve V54 CVCS-Mod 1 (SWESSAR- (Fig. 9. 3-2) P1 Fig. 9.3.4-1 Sh 1) P1 Fig. 9.3.4-1 Sh 1) Tb valve 1-IEV-112A H2 supply to makeup tank To valve CH500 CVCS-Mod 2 GWS-4 Tu valve 1 -ILV- 112A , (SWESSAR-P1 Fig. 9.3.4-2 Sht) g CVCS-Mod 2 (SWESSAR- *o valve MV-115A CVCS-Mod 2 (SWESSAR-P1 Fig. 9.3.4-1 Sh 1) (Fig . 9.3-1) P1 Fig. 9.3.4-1 Sh 1) +,

. 3 F IG. II. 3.-l G RADIOACTIVE GASEOUS WASTE

  "*                                                                                                      SYSTEM F'WR REFERENCE PL ANT S AF E T Y AN ALYSIS RE POR T SWESS AR -PI AMENDMENT 29 80/29/76

                                 ,y-      .
                                                                                                                                                    ..p p4
                                                                                                                                                                                                    .d Y

u( 'y

                    .s                                                                                                                                                                              ..

Y ,J e,

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                                                                                                                                                                                                                           ,.44
                                                                                                                                                                                                                 ,       -m 4              "'*f      .
  . 8                                                                                                                                                                                               . .

g ..-

                                                                                                                                                                                                                     /

[

• s(

t of

.. g .,

                                                                                                                                                                                                         .g                    .

e s

                                                                                                                                                                                                       ; r
                                                                                                                                                                                             ,f     '1....T              -

u

                                                                                                                                                                                                ,i-9 Q

m O f S .+ d i

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             *.                                                                                                                                                                                                  :        e.

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      .                                                                                                                                                                                               .6
                                                                                                                                                                                                              . 0 t

• g.

e 1 4 *

                                                                                                                                                 /

l g /_ !% sf UU/ 1 9 6 .t4. pe D g + 4- e ' s g = . . ,.8- .. . t9. .-

                                                                                                                                              ^

e* s e* '#" , f

                                                                                                                                                             ~

. , . 4

SWESSAR-P1 11.4 PROCESS AND EFFLUENT RADIATION MONITORING SYSTEM 11.4.1 Design Obiectives The process and effluent radiation monitoring system is designed ja accordance with NRC General Design Criterion 64. l3 Normal and potential paths for release of radioactive materials, both during normal operation and during anticipated operational occurrences, are continuously monitored to ensure compliance with the requirements of 10CFR20, 10CFR50, and Regulatory Guide 1.21 (Section 3A .1-1.21) . 8 Continuous monitoring means that the monitor operates essentially uninterrupted for extended periods during normal plant operation and does not preclude periods when the monitor may be out of service for maintenance, repair, calibration etc. The reactor coolant system (RCS, NSSS Vendor's scope) is monitorec continuously for gross activity level. Maintaining the 8 RCS activity within acceptable levels ensures that the activity levels in the normally radioactive auxiliary systems are at acceptable levels. Nonradioactive systems which may become contaminated by leaks from radioactive systems are monitored continuously to ensure that no conditions develop that are hazardous to the operating l8 ' personnel or to the general public. In the event of an accident, the process and effluent radiation monitoring system, the area radiation monitoring system (Section 12.1. 4 ) , and the airborne radiation monitors (Section 12.2.4) provide information on the concentration and dispersion of radioactivity throughout the plant, enabling operating personnel to evaluate the severity, and to mitigate the consequences, of the accident. 11.4.2 Process and Effluent Monitorina The process and effluent radiation monitoring system consists of separate and independent monitors:

1. Each monitor has one or two radiation detectors. Each detector has a remotely operated check source.

2. Each detector has a readout device in the control room equipped with alarms to indicate equipment malfunction, high radiation level, and high-high radiation level.

3. Each detector has an independent power supply located in the control room.

11.4-1 Nnendment 8 3/28/75 bb/ l)b

SWESSAR-P1

4. Fach det ector has associated electronic equipment and g

cablino . A permanent record of radiological events is maintained for each detector. Each hiah alarm setpoint is set at a level determined by operating personnel to allow observation of dif ferential changes in activity. The high-high alarm setpoints for potential effluent paths are chosen to ensure that the instantaneous release rates are within the quidelines of 10 CFR 20. Values for these alarm settings depend on the maximum anticipated flow rates for each etiluent. The failure indicator actuates an alarm if the monitor loses its voltage s upply, if there is a samole line break, or if there is a filter failure. 8 Mea ns are provided to purge each fixed volume sample chamber in the system with clean fluid to minimize contamination of the chambers. Sample lines and all surfaces of each samuler exoosed to the sample are stainless steel. The operability of each detector is checked as required with a a check source which is remotely positioned from the control room. To assist in the calibration and maintenance of the system, each detector has a local readout device. Power is provided to the process and ef fluent radiological moni-toring system by the 120 V a-c vital buses (Section 8. 3.1) . Sample pump motors are connected to the emergency buses (Section 8.3.1) . 8 Each detector is connected to automa tic annunciators in the control room to warn of equipment malfunction, high, or high-hich radiation levels. 11.4.2.1 Locations to be Monitored The number and location of airborne process and effluent radiation monitors are presented in Table 11.4-1. The nu r and locations of liquid process and effluent radio-logical onitors are presented in Table 11.4-2. Euch of the above airborne monitors, the liquid waste monitor, the plant discharoe line blowdown monitor, and the turbine building drains monitor, is situated on a potentially radioactive effluent path. Therefore, the sample points are downstream of the last point of possible fluid addition to the effluent being monitored. The auxiliary condensate and component cooling water monitors ensure that leaks from the steam and power conversion system, the 8 containment recirculation coolers and primary system components 11.4-2 Amendment 8 3/28/75 C O 'l l;/

SWESSAR-P1 are detected at levels well below those representing any potential radiological problem. The steam generator blowdown monitor and the steam line monitors provide indication of a primary to secondary leak in the steam generators. The service water monitor ensures that radioactive leaks from the conponent cooling wates system are detected at levels well below those representing any radiological hazard to the environment. 11.4.2.2 Anticipated Concentrations, Sensitivities, and Ranges The sensitivity and range of each detector are given in Tables 11.4-1 and 11.4-2. A detector is deemed to have the required sensitivity when the indicated count rate, with the detector exposed to the specified nuclide concentration, equals or exceeds twice the count rate due to background. Each detector is located in an easily accessible area and is provided with sufficient shielding to ensure that the required sensitivity is achieved when the background radiation level is at the design maximum for the area, as given in Section 12.1. Each detector monitors for gross concentrations; the output is measured in counts per minute (cpm) with a minimum range of four decades. The expected concentrations for each monitor can be found from information provided in Tables 11. 4-1 and 11. 4-2. The results given in Table 11.4-4 for BSW are generally taken from previous analyses which were based on values of parameters slightly different than those given in Table 11.3-1. Since the results are consistent with those already presented ror the W and M C-E NSSS, revisions in the calculations are unnecessary tor this application for Preliminary Design Approval. The purpose of the component cooling, service water, turbine building drains, and auxiliary condensate monitors is to detect leaks or spills into normally nonradioactive systems or areas. The expec+ 4 concentrations of nuclides in the streams they monitor a those due to normal background. The containment purge air exhaust monitors are exposed to the gaceous and volatile tission products that may build up in the containnent atmosphere due to RCS leaks. The predominant isotope is expected to be Kr-85, although Xe-133 and I-131 may be present in significant amounts . Tritium levels are determined by sampling the containment atmosphere prior to purging. The reactor coolant letdown activity may range trom negligible, when the plant is at the beginning of the f uel cycle, to about 50 uCi/cc it there is 1 percent failed fuel. Two detectors, with 11.4-3 Amendment 19 12/12/75 o: u. a } , c,

SWESSAR-P1 overlapping ranges, monitor reactor coolant letdown activity. Two detectors are used because of the expected increase in radioactive nuclide concentration during the fuel cycle. 11.4.2.3 Description of Radiation Monitors The tollowing paragraphs contain a brief description of each of the monitors in the process and effluent radiation monitoring system. 11.4.2.3.1 Airborne Process and Effluent Monitors Each location listed in Table 11.4-1 with two detectors has one or more standard packages known as an airborne radiation monitor (Fig. 11.4-1) , equipped with both particulate und gas detectors. Isokinetic nozzles are used for uniform sample quality control. The sample is drawn through stainless steel lines to a moving or fixed filter paper which collects particulates greater than 0.3 micron. The activity of the deposited material is continuously scanned by a radiation detector . After passing through the tilter paper, the sample passes through an in-line , easily removable, carbon adsorber cartridge arrangement and then into a fixed, shielded volume where it is monitored for gaseous activity. The sample is then returned to the main line at some point downstream of the monitor sample inlet. A direct drive pump provides a constant sample flow at some predetermined value, normally between 4 and 10 cfm after line and filter losses. , Air flow is automatically regulated to 15 percent of the set flow rate. The airborne radiation monitor detector outputs are transmitted to the control room. Here, the activity levels (cpm) are displayed and simultaneously recorded. The high activity level is indicated by both audible and visible alarms. A complete set of data output and instruments is provided for both the particulate detector and for the gas detector in every airborne radiation monitor. Sample tubing is run with the care afforded all instrument piping to ensure that interf erence with sample integrity is minimized. Process Vent Moni tor This monitor is an airborne radiation moni"or which draws a sample from the process vent ef fluent line (Sect in 11.3). The sample point is downstream of the last point where radio-activity could be introduced to the aerated vent flow prior to its release to the ventilation vent. bb0 llQ 11.4-4 Amendment 19 12/12/75

SWESSAR-P1 Process Gas Monitor The process gas monitor continuously analyzes the effluents from the process gas receiver tank of the radioactive gaseous waste sy s tem (Section 11. 3) . Thesa effluents normally are directed to the CVCS and are not released to the environment.

                                                       ..e 11.4-4 A       h u, ',/ i Jdaendment 19 12/12/75

SWESSAR-P1 When the release is to the environment and the alarm warns of high activity, the flow is automatically diverted to the CVCS. Ventilation Vent Monitor This monitor is an airborne radiation monitor with a multiprobe isokinetic sampler because thi ventilation vent sample point is in a large duct (Section 9.4) . High activity causes an alarm in the control room which alerts the operators that the release of activity is at the limit specified in Section 16.3.8 ar.d ' chat corrective action is required. This monitor acts as a backup unit for a series of monitors as shown in Fig. 11.4-2. Ventilation Vent High Range Monitor The ventilation vent high range monitor continuously monitore the airborne radiation levels in the ventilation vent by means of a p radiation detector located in the well of an in-line sampler. This monitor allows the operator to observe the radioactivity release which could result from abnormal occurrences including the accidents described in Chapter 15 and which is discharged via the ventilation vent. Containment Purge Vent Monitors The containment purge air is monitored by two redundant in-line detectors. High activity indication from either of these red undant monitors automatically terminates containment purge (Section 9.4.5.2) . The sample points are upstream of the containment purge line isolation valves. The contdinment purge air exhaust monitors, in conjunction with the containment atmosphere airborne radiation monitor (Section 12.2.4), provide the information required for the conduct of the containment purging operation. Containment purge air exhaust flow may be diverted through annulus building filter banks by the operators if the activity levels in the containment atmosphere indicate that the containment filtration units are partially or totally ineffective. Steam Jet Air Eiector Monitor The steam jet air ejector monitor continuously analyzes the gaseous effluents from the steam jet air ejector discharge (Section 10.4.2) by means of a radiation detector located in a well of an in-line sampler. Activity readings are indicative of primary-to-secondary leakage. bbh 11.4-5 Amendment 17 9/30/75

SWESSAR-P1 11.4.2.3.2 Liquid Process and Ef fluent Monitors Reactor Plant Component Cooling Water System Monitor This detector ccntinuously monitors the component cooling water (Section 9.2.2) . Samples are withdrawn from the component cooling water subsystem downstream of the component cooling pumps discharge and monitored by a detector mounted in an off-line, shielded liquid sampler. After passing through the detector, the sample is returned to the component cooling water. Activities significantly above background are indicative of a leak into t.he component cooling water system from the reactor coolant system (Chapter 5) or one of the other systems containing radioactive fluids which exchange heat with the reactor plant component cooling water system. Liquid Wastes Monitor This monitor continuously monitors the liquid waste ef fluent dis-charge pipe (Section 11.2), downstream of the last possible point of radioactive liquid addition, by means of a detector maunted in a well of cih in-line lead shielded sampler accombly. High activity initiates closure of a discharge valve, thereby preventing discharge of high activity effluent to the environment. Steam Generator Blowdown Sample Monitor (C-E and W only) This monitor sanples the steam generator blowdown (Section 10.4.8) for radioactivity which would be indicative of primary-to-secondary leakage. Samples from each of the steam generators are mixed in a cmmon header, and the comon sample is continuously monitored. After being monitored, the sample passes back to the steam generator blowdown system. If significant activity is detected, a valving arrangement allows each steam generator to be sampled individually to determine the source of activity. Steam Line Monitors (B&W only) Each once-through steam generator has its outlet steam monitored by means of a detector mounted close to a steam line in a low background area. If a significant primary-to-secondary leak occurs in a steam generator, the N-16 activity is detected to indicate the leak. bbh l2?

                                                                         -- c 11.4-6                   Amendment 17 9/30/75

SWESSAR-P1 Reactor Coolant Letdown Gross Activity Monitors gross activity of the reactor coolant is continuously The monitored by a low range and a high range detector. The samples are drawn from the reactor coolant letdown line (Section 9.3.2) and delayed to permit suf ficient decay of the N16 isotope before the samples pass by the detectors. Large variations in activity levels are possible depending on the amount of fission products leaked to the reactor coolant. The detectors are located adjacent to the off-line sample tubing. The ranges and sensitivities of the detectors provide one decade overlap of the highest decade of tne low range detector. Collimating plugs are used with the low range detector after the reactor coolant activity builds up to provide redundancy for the high range channel. bD Y I23 11.4-6A Amendment 17 9/30/75

SWESSAR-P1 Plant Discharge Line Monitor This detector monitors the plant liquid discharoe (Section 11.2.4) beyond the last point of possible radioactive liquid addition, using a detector mounted in an of f-line sampler. g This monitor is analogous to the ventilation vent monitors in that it acts as a backup unit for other monitors upstream. Auxiliary Condensate Monitor The auxilia ry cond ensa te monitor continuously analyzes samples drawn from the auxiliary steam condensate header (Section 10.4.12) by means of an off-line shielded liquid sampler. After passing through the detector, the sample is returned to the auxiliary steam system from the steam and power 8 conversion system. Turbine Building Drains Monitor This detector continuously monitors the turbine buildino drains discharge line (Section 11.2). The sample point is downstream of 8 any possible fluid addition to the turbine building drains discharge. High activity automatically diverts the drain discharge to the radioactive liquid waste system. Service Water Monitor The detector continuously monitors the service water (Section 9 . 2 .1 ) in a manner similar to the component cooling water monitor. Samples are withdrawn from the service water side of the component cooling water system just downstream of each component coolina water heat exchancer (Fig. 9 . 2.1 - 1) and monitored by a detector mounted in an off-line shielded liquid l8 s ampler . After passing through the sample chamber the sample is returned to the service water. 11.4.3 Sampling Refer to Section 9.3.2 for a discussion of various process and effluent samples periodically taken for chemical and radio-chemical analysis. Liquid process and effluent samples to be periodically taken and monitored for radioactivity are listed in Table 11.4-3. Those not covered in Se ction 9. 3. 2 are included in the individual system designs. Sampling of these fluid systems is via local sampling conne ct ions , e.a., the fuel pool cooling and purification system (Section 9.1.3) . Refer to Section 16.4 for a description of various periodic licoid samples analyzed for gross beta-gamma activities, including the sampling frecuencies. For the maximum concentrations of radionuclides expected in the 11.4-7 b b '- 17 1i k Amendment 8 3/28/75

SNESSAR-P1 various periodic process and effluent liquid samples, see Section 11.2. Additionally, the process and effluent radiation monitorina system has provisions for periodic ventilation samples. Refer to Section 12.2.4.6 for o description of the periodic ventilation samples monitored for airborne radioactivity by the ventilation systems multi-sampler particulate and gas monitor. In addition 8 to the proarann.ed periodic sampling of various ventilation systems, the ventilation systems multi-sampler particulate and gas monitor can be utilized to manually locate a specific source of high airborne radivaetivity. Prior to collectino a sample, liquid sample lines are purned of stagnant water and undiscolved solids for a sufficient time to ensure that a representative sc .nple in obtained . The lengths of sample lines are determined ptior to plant operation and recorded so that a ppropriat e nurce periods and flow are known for each line. Sample taps suituhle for connection to a sampling chanbor are provid ed for the process gas line, the ventilation vent line, and the process vent line to obtain a sanple for laboratory camma spectrum analysis. The analysis provides the ratio of nuclides needed to evaluate the gross radioactivity measurements provided by the airborne radiation monitors in the ventilution vent line and process vent line and the process cas radiation monitor. f Gas samples are collectea either in a steel sample vessel with valves on each end or a class sanpling bulb. After adequate purgina of the sample vessel, the gas sample is collected by closing valves at both ends of the sample vessel. 11.4.4 Innervice Tnsoection, Calibration, and Maintenance This section is within the Utility-Apolicant's scope and SAP. b/ f[h 11.4-8 Amendment 8 3/28/75

    @                                                           SWESSAR-P1 TABLE 11.4-1 AIRBORNE PROCESS AND EFFLUENT MONIW RS Minimum Sensitivity              Range        Ex1Med Monitor            Number    Medium         fuci/cc)              (Decades 1   Concentrations      Location Process Vent                 1    Air                                              Table 11.4-4      Fig. 11.3-1F (2 detectors)

Particulate 1x10-se (I-131) 4 Gas 1x10-* (Xe-133) 4 Process Gas 1 Gas 1x10-6 (Xe-133) 4 Table 11.4-4 Fig. 11.3-1E Ventilation Vent 1 Air Table 11.4-4 Fig. 6.2.3.1-1 (2 detectors) Particulate 1x10-so (I-131) 4 Gas 1x 10-4 (Xe-133) 4 Ventilation Vent 1 Air 1x10-3 uCi/cc/Xe133) 4 6 uCi (maximum) Fig. 6.2.3.1-1 g High Range Containment 2 Air 1x10 * (Xe-133) 4 Table 12.2.3-6823 Fig. 9.4.5.3-1 Purge Air Exhaust C7w 4 Table 11.4-4 Fig. 10.4.2-1 g-j Steam Jet Air 1 Gas 1x10-5 (Xe-133) E]ect or

%C3

( n > Iodine concentrations should be reduced by a f actor of 10. (%Q LT-

                  #N C9 p#2@2 f'

(r. v p- -a 5 -s h, t>,31

                                 -y c': L:.s W       ,Y 1 of 1                                    Amendment 17 9/30/75

G SWESSAR-P1 TABLE 11.4-2 LIQUID PROCESS AND EFFLUDfr MONITORS Minimum Sensitivity Range Expected Number Medium (uCi/cc) (Decade s) Con &ntritions Location _ Monitor Reactor Plant 3 Liquid 1x10-* (Cs-137) 4 Background Fig. 9.2.2-1 Canpc.nent Cooling Water (W-41 ) 1x10-* (Cs-137) 4 Background Fig. 9.2.2-1 m g- Reactor Plant 2 Liquid g '. . Ccanponent C ) Cooling Water (v } (B&W, C-E, W-3S) e- d Liquid Waste 1 Liquid 1x10-* (Cs-137) 4 Table 11.2-31 Fig. 11.2-1 4 Table 11.1.3-1 Fig. 9.3.2-1 Steam Generator 1 Liquid 1x10-6 (Cs-137) {J g,3 S r- .- Blowdown Sample (C-E, W-41, W-3S) l21 ms, 1x10-6 (N-16) 4 Table 11.1.3-2 (Later) h) it c y Steam Line (B&W) 2 Steam cI" i , Reactor Coolant 1 Liquid 1x 10-4 (Cs-137) 4 Table 11.1.2-2 Fig. 9.3.2-1 1x10-1 (Cs-137) 4 {J% Letdown Gross Activity

 -p%

(2 detectors) Plant Discharge 1 Liquid 1x10-* (Cs-137) 4 Table 11.2-32 (Utility-Applicant Scope) Line Auxiliary Condensate 1 Liquid 1x10-* (Cs- 137) 4 Background Pig. 10.4.12-1 Turbine fsuilding 1 Liquid 1x10-* (Cs-137) 4 Table 11.2-28 Fig. 9.3.3-1 Drains O Reactor Plant 1x10-* (Cs-137) 4 Background Fig. 9.2.1-1 & Service Water (W-41) 3 Liquid 21 Reactor Plant Service Water 2 Liquid 1x10-* (Cs-137) 4 Background Fig. 9.2.1-1 (B&W, C-E, W-3S) __.s N N 1 of 1 Amendment 21 2/20/76

SWESSAR-P1 TABLE 11.4-3 RADIOLOGICAL SAMPLES TAKEN AT REACTOR PLANT SAMPLE SINK NO Required By i Samples SSW BSW C-E W ' Reactor Coolant bystem (Chapter 5) Loop No. 1 (hot leg) - later later 1 Loop No. 3 (hot leg) - later later 1 Pressurizer vapor space - later later 1 Pressurizer liquid space - later later 1 RHR System (Chapter 5) RHR - later later 3 Reactor Plant Component Cooling Water System (Section 9.2.2) Pump discharge 6 - - - 3 Primary Grade Water System (Section 9.2.7) Primary grade water tanks 2 - - - Chemical and Volume Control System (Section 9.3.4) Letdown heat exchanger outlet - later later 2 Reactor coolant filter inlet - later later 1 Volume control tank - later later 1 Boron thermal regeneration outlet - later later 1 Boron Recovery System (Section 9.3.6) Boron recovery tanks 2 - - - Boron test tanks 2 - - - Steam Generator Blowdown System (Section 10.4.8) Blowdown sample 1 - - - Radioactive Liquid Waste System (Section 11.2) Degasifier liquid 1 Degasifier vent cooler 1 1 of 1 Amendment 3 h6y 20 10/5/74

SWESSAR-P1 TABLE 11.4-4 EXPECTED CONCEh"fRATIONS IN VARIOUS AIRBORNE PROCESS AND EFFLUENT MONITORS (uCi/cc) Process Process Ventilation Steam Jet Vent Gas Vent Air Eiector I-131 7.6E-10 -(t) 2.4E-11 2.4E-09 I-132 4.9E-10 - 1.1E-11 1.9E-09 I-133 1.1E-09 - 3.6E-11 3.1E-10 I-134 7.8E-11 - - 1.4E-11 1-135 5.3E-10 - 1.9E-11 1.4E-09 Kr-83M 5.4E-07 - 2.1E-09 4.4E-07 Kr-95M 3.2E-07 9.6E-07 2.5E-09 1.8E-06 Kr-85 7.0E-09 7. 9E-02 2.4 E-07 4.0E-08 Kr-87 2 . 3E-07 - 1.8E-09 1.3E-06 Kr-88 6 .7E-07 3.3E-10 S. 2E-0 9 3.8E-06 U Kr-89 2 .2E-0 8 - 1.7E-10 1.3E-07 Xe-131M 1.6E-07 7.6E-03 2. 4 E-0 8 1.0E-07 Xe-133M 6.7E-07 1.7E-08 2.7E-0 9 7.7E-07 Xe-133 1.4E-05 2.5E-02 1.5E-07 3.2E-05 Xe-135M 9 .3E-0 6 -

2. '3E-0 8 3.2E-07 Xe-135 1.5E-05 -

5.1E-0 8 4.2E-06 Xe-137 4.0E-08 - 3.1E-10 2.3E-07 Xe-138 1.9E-07 - 1.5E-09 1.1E-06 (1) " " implies <1.0E-11 W 1 of 1 bb9 )29 Amendment 17 9/30/75

SWESSAR-P1 TABLE 11.4-4 EXPECTED CONCENTRATIONS IN VARIOUS AIRuGRhE PROCESS AND EFFLUENT MONITORS (uCi/cc) Process Process Ventilation Steam Jet Vent Gas Vent Air Eiector I-131 9.3E-10 -(1) 3.0E-11 2.9E-09 I-132 5.3E-10 - 1.2E-11 2.1E-09 I-133 1.6E-10 , 4.2E-11 3.7E-09 I-134 8.0E-11 - 5.1E-12 1.6E-11 I-135 5.8E-10 - 2.1E-11 1.6E-09 Kr-83M 5.7E-07 - 2.2E-09 4.5E-07 11 Kr-85M 3 .5E-0 7 7.7E-07 2.7E-09 2.0E-06 Kr-85 8 .8 E-0 9 7.4E-02 2.2E-07 5.0E-08 Kr-87 2 .4 E -0 7 - 1.9E-09 1.4E-06 Kr-88 7.0E-07 2.6E-10 5.4E-09 4.0E-06 Kr-89 2.2E-08 - 1.7E-10 1.3E-07 Xe-131M 2.0E-07 7.0E-03 2.2E-08 1.3E-07 Xe-133M 7 .8 E-0 7 1.5E-08 3.2E-09 9.3E-07 Xe-133 1.7E-05 2.3E-02 1. 5E-07 3.9E-05 Xe-135M 1.0E -0 5 -

3. 2E-0 8 3.3E-07 Xe-135 1.7E-05 -

5.6E-08 4.7E-07 Xe-137 4 .0 E-0 8 - 3.1E-10 2.3E-06 Xe-138 1.9E-07 - 1.5E-09 1.1E-06 (1) "" implies <1.0E-11 W-3S 1 of 1 , Amendment 17 D b y/ l ;, ,,j 9/30/75

SWESSAR-P 1 TABLE 11.4-4 EXPECTED CONCENTRATIONS IN VARIOUS AIRBORhE PROCESS AND EFFLUEb"r MONITOPS (uCi/cc) Process Process Ventilation Vent Steam Jet Gas Vent Air Eiector I-131 2.06E-09 I-132 1.93E-11 8 . 35 E -0 9 5.59E-10 - - 2.24E-09 I-133 2.46E-09 I-134 2.28E-11 1.04E-08 2.46E-10 - - 5.22E-10 I-135 1.12E-09 - 1.03E-11 4.77E-09 ,, Kr-83m 1.63E-06 - 5.83E-09 Kr-85m 1.16 E-0 9 5.52E-07 8.83E-07 3.00E-09 2.54E-06 Kr-85 - 1.17E-01 Kr-87 - 2.36E-07 8.95E-08 Kr-88 1.92E-09 1.64E-06 2.83E-10 5.91E-09 5.0 7E-0 6 Kr-89 - 1.71E-10 1.48E-07 Xe-131m 8.28E-07 1.06E-02 Xe-133m 2.43E-08 2.24E-07 2.46E-06 2.19E-08 9.61E-09 Xe-133 4.03E-05 1.49E-06 3.43E-02 2.76E-07 6.71E-05 Xe-135m 3.58E-05 - Xe-135 1.14E-07 3.88E-07 5.59E-05 - 1.86E-07 Xe-137 - 6.56E-06 Xe-138 - 3.14E-10 2.69E-07 1.53E-09 1.28E-06 bT, W 1 of 1 Amendment 19

                                                 }}}          12/12/75

SWESSAR-P1 TIdLE 11.4-4 EXPECTED CONCENTRATIONS IN VAPIOUS AIRBORNL PROCESS AND EFFLUENT PONI'1TJRS (uCi/cc) Process Process Ventilation Steam Jet Vent Gas Vent Air r iector I-131 1.7E-09 -(1) 1.1F-11 2.1c-09 I-132 8.5E-10 - 4.7E-12 1.9E-09 I-133 2.4E-09 - 1.5E-11 2.6E-09 I-134 2.5E-10 - 1.7E-12 1.oE-11 1-135 1.2E-09 -

7. 5E - 12 1.3E-09 Kr-83M 1.6E-06 -

5.4E-09 4.5L-07 Kr-85M 3.4E-07 6.9E-07 2.6E-09 1.9E-06 Kr-85 8.4E-09 6.4E-02 2.4E-07 4.6E-08 Kr-87 2.4E-07 - 1.8E-09 1.4E-06 Kr-88 6.9E-07 2.3E-10 5 . 4 E -0 9 4.0E-06 1.7E-10 1.3E-07 U Kr-89 2.2E-08 - Xe-131M 5.5E-07 b.1E-03 2. 5E -0 8 1.2E-u7 Xe-133M 2.1E-06 1.3E-08 7.3E-09 8.9E-07 Xe-133 3.6E-05 2.0E-02 2.2E-07 3.7E-05 Xe-135M 3.1E-05 - 9.9E-08 3.2E-07 Xe-135 5.0E-05 - 1.6E-07 4.6E-06 Xe-137 4.0E-08 - 3.1E-10 2.3E-07 Xe-138 1.9E -07 -

1. 5E-0 9 1.1E-06

(*) "" implies < 1.0E-11 669 132 Amendment 17

                                                ~

C-E 1 of 1 9/30/75

SAMPLE _ RAH RI INLET I RSH l l E __L_j- - - - d NOTEI P ARTI CUL %TE CHARCOAL FILTE R PURGE AIR r- - - r-- - --- NOTEI PURGE GAS RSH l OUTLET g SAMPLE 4 RAH RI OUTLET ARM NOTE: 1 TC CTHER AL ARMS AND INDICATORS AS RECU' RED FIG. II .4 - 1 AIRBORNE RADI ATION MONITOR (TWO DETECTORS) PWR STANDARD PLANT SAFETY ANALYSIS REPORT SWESSAR- Pl () (, '), k .y) ,D AMENDMENT 6 1/17/75

5 7

                                                                                                                  /

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SWESSAR-P1 11.5 RADIOACTIVE SOLID WASTE SYSTEM The radioactive solid waste system is designed to provide holdup, solidification, packaging, and storage facilities for radioactive materials prior to their shipment offsite and ultimate disposal. The radioactive solid waste system is shown in Fig. 11.5-1. 11.5.1 Desian Obiectives Tbc following specific requirements apply to the radioactive solid waste system design.

1. The filling of containers, the solidification, and the storage of radioactive solid wastes conform to 10CFR20 and 10CFR50 requirements in terms of "as low as practicable" doses to plant personnel and the general public.

2. The waste storage facilities in the solid waste and decontamination building are shielded to provide protection of operating personnel in accordance with the radiation protection design objectives in Section 12.1.1. g

3. Health physics personnel conducting periodic surveys usina portable radiation detectors ensure dbat radiation levels outside shielded areas are less than design levels and establish access limitations within the shielded areas.

4. This system is not safety related and is classified as nonnuclear safety (NNS).

5. That part of the solid waste and decontamination building's foundation, which houses portions of the system whose failure could affect the collection, processing, and storage of radioactive liquids, is Seismic Category I.

6. Those portions of the system that handle radioactive liquid waste will meet the design objectives items 6, 7, 8, 9, and g 10 of Section 11.2.1.

11.5.2 Svstem Inputs Materials handled as solid wastes include concentrated waste solutions from he waste evaporator, regenerant chemical I eva porator and the laundry waste evaporator in the radioactive , 8 liquid waste system (Section 11. 2) , concentrated boric acid discarded from Uhe boron evaporator in the boron recovery system (Section 9. 3.6) , spent resin from radioa ctive process demineralizers and ion exchangers, spent filter cartridaes, and miscellaneous solid materials which become contaminated during plant operation and maintenance.

                                                             /?          7 Ob()      lJD' 11.5-1                         Amendment 8 3/28/75

SWESSAR-P1 Fig. 11.5-2 is a flow chart of the estimated quantities and activity levels of the radioactive solid waste that are generated by the plant. Gross activities and weights or volumes for radioactive solid waste sources are also given in Fig. 11.5-2. Isotopic breakdowns of the radioactive solid waste sources are not given, because insuf ficient operating experience is presently available. Additional information will be presented at a later date. The results given in Fig. 11.5-2 for BSW are generally taken'from previous analyses which were based on values of parameters g slightly dif f erent than those given in Sections 11.1 and 11.2. Since the results are consistent with those already presented for the W and C-E NSSS, revisions in the calculations are unnecessary i for this applicdtion for Preliminary Design Approval. The prediction of realistic activities of specific nuclides for the solid waste isotopic inventories is dif ficult and has been stated temporarily in terms of gross activity for the following reasons:

1. The residual activity in solid waste tends to be due to corrosion / activation products of longer lived species.

2. The rate of transport within the plant systems of insoluble fractions of radioactive corrosion products is one to two orders of magnitude slower than for soluble fission products and is therefore more difficult to predict because it is more sensitive to upsets than to steddy operation.

3. There is much uncertainty in the exact isotopic mix of an end product of many sequential operations. The normal expected isotopic mix of solid waste from predictive mathematical and empirical models will be compared to data giving isotopic mixtures in solid waste. because primary concerns, heretofore, have been with container surface dose and the gross activity of contents only, not much data of a more specific nature are available in public records. However, since it is preferable that the range of a ctivity can be fairly represented, the applicant will continue to examine what information is available during the design process and to a sse ss its impact on the predictive models now in developm ent .

4. Table 11.5-4 lists the estimated principal nuclides expected in the waste from the boron evaporator bottoms, waste evaporator, and spent resins.

17~ DD t i 11.5-2 Amendment 19 12/12/75

SWESSAR-P1 11.5.2.1 Spent Resins Fig. 11.5-2 gives the estimated volumes of spent demineralizer and ion exchanger resins per year. These resins come from a variety of different services, and the total volume estimated is based on the individual resin bed volumes and the expected frequency of replacement (see Table 11. 5-1) . 11.5.2.2 Waste Evaporator Bottoms The waste evaporator in the radioactive liquid waste system is operated so as to discharge bottams at about 15 percent by weight solids concentration to the solid waste system for solidification and ultimate shipment offsite. The volume of bottons solution to be shipped offsite is given in Fig. 11.5-2. The calculated activity of these bottoms, also given in Fig. 11.5-2, is based on the inputs of the radioactive liquid waste system (Section 11. 2) . 11.5.2.3 hegenerant Chemical Evaporator Bottoms The regenerant chemical evaporator is operated so as to discharge bottoms at about 24 percent by weight solids concentration to the solid waste sys tem for solidification and ultimate shipment offsite. The volume and activity of the waste are given in Fig. 11.5-2. 11.5.2.4 Laundry Waste Evaporator Bottoms The o n s .i.t e laundry facilities produce low level laundry waste effluent which is treated in a laundry waste evaporator (Section 11.2) . The volume and activity of laundry waste evaporator bottons to be shipped offsite are given in Fig. 11.5-2. 669 i38 11.5-2A Amendment 19 12/12/75

SWESSAR-P1 11.5.2.5 Boron Evaporator Bottoms The boron evaporator in the boron recovery system processes reactor coolant letdown to the boron recovery system in order to recover and recycle boric acid and water for reuse. It is estimated that, approximately once every 2 years, one boron evaporator volume is solidified. The volume given in Fig. 11.5-2 for the boron evaporator bottoms is a 1-year average of the contents requiring processing for eventual offsite disposal. The activity shown for these bottoms, given in Fig. 11.5-2, is based on the expected performance of the boron recovery system (Section 9.3.6). 11.5.2.6 Miscelluneous Radioactive Solid Wastes It is estimated that approximately 2,500 ft3 per year of additional waste requiring disposal is processed in the radioactive solid waste system. This volume of spent filters, contaminated cloths, and other radioactive material and their activity, given in Fig. 11.5-2, were estimated from operating experience at the Point Beach Unit 1 and Connecticut Yankee Power Stations. 11.5.3 Equipment Descrintion The radioactive waste solidification system equipment is similar in design philosophy to the principles in use for several years at the Nuclear Engineering Burial Site at Moorehead, Kentucky. The system is operated on a batch basis, and the equipment capabilities are designed to meet maximum expected through put rates. The system consists of a filling station where a liquid waste stream is injected into a shielded disposable shipping container in controlled anounts after being blended with a urea formaldehyde compound. The waste to urea formaldehyde solidification agent ratio is 2.5:1 on the average. Catalyst is added simultaneously with injection. Spent filter cartridges may be inserted into the shipping container prior to fi 7 ling. The system can process liquid wastes from the waste, reg enerant 1 chemical, laundry waste, and boron recovery evaporators. 12 Radioactive demineralizer resins are slurried to the waste sludge tank where excess water is removed, and are then processed through the same fill station with urea formaldehyde and catalyst as described for liquid waste atreams. Waste containers are sealed in various ways depending on the system chosen trom a number of solid waste system suppliers. In general, remotely operated copping mechanisms are used to seal the conta iners . Where required, epoxy adhesives are used in 9 conjunction with the renote capping mechanism to bond and seal the cap. { { '; }}g 11.5-3 Amendment 12 6/16/75

SWESSAR-P1 The sealed container and its shipping shield, when required, are transported to a burial site. Shields are reusable and are returned by the shipper from the burial site. The shipping 12I container size is 50 ft3 although smaller and larger con tainers can be readily accommodated. Thg, container may contain spent filters or other incompressible waste in addition to evaporator bottoms. Containers are handled entirely by a 30 ' ton capacity overhead bridge crane. The crane is operated from the floor by the radwaste operator. The systems are designed to prevent external contamination of containers by use of reliable container sealing, appropriate system flushing into the container, and necessary mechanical design or instrumentation interlock signals that prevent overfilling of containers. Water sprays are provided to decontaminate containers in the unlikely event that containers are contaminated. The decontamination area is located in the vicinity of the container fill position as illustrated in Fig. 1.2-9. Spillage in container fill areas and pump areas will be retained in walled and curbed cubicles whose walls and floors are suitably finished to facilitate decontamination. The system consists of a filling station mechanism, process equipment modules, a power panel, a control panel, waste sludge tank, and storage tanks for the urea formaldehyde and catalyst. The system is highly automated to require a minimum of operator att entio' and along with the building design is designed to minimize the dose to the operator while operating the system. 11.5.3.1 Boron, Waste Evaporator, and Recenerant Chemical Evaporator Bottoms Fand1ing Concentrated liquids from the boron evaporator, waste evaporator, 12{ and regenerant chemical evaporator are pumped to an evaporator bottoms tank or directly to the solidification sta tion , if available. The tank provides holdup until solidification is desired. Then it is pumped to a shielded shipping container in the waste solidification area of the solid waste and decontamination building. The amount of waste liquid allowed per container is determined by prior analysis of the waste. Radiation levels are also monitored while filling the container to ensure DOT shipping ihmits are not exceeded. After the container is filled and solidified, it is sealed and shielded as necessary. The laundry waste evaporator bottoms are processed directly frcxn the laundry evaporator bottoms tank and are processed the same as the boron, waste, and regenerant chemica,1 D evaporator bottoms. . . } .$ U

                                                                                ~

u u, ,4 11.5-4 Amendment 12 6/16/75

SWESSAF-P1 The contact radioactivity level of the container surface is measured and recorded, and a record of the radioactivity level is shipment in attached to the container prior to storage or accordance v;ith AEC reculations 10CFR20 and 10CFR50 and Department of Transportation regulations 49CFR171 throuch 179. The shipping containers are stored in the solidification area , (Eection 11.5.6) until they are to be shipped to a licensed burial oround for ultimate disposal. 11.5.3.2 Spent Fesin Handling Fenin in a demineralizer or ion exchanger is considered spent when the decontamination factor falls below a predetermined value or when the demineralizer or ion exchanaer surface dose approaches a predetermined lbmit. The demineralizer or ion exchanger is then isolated and water f rom the spent resin surce tank is used to 11ush the spent resin into the spent resin hold tank utilizing the spent resin transfer pumn. The flush water passes out of the spent resin hold tank, through a s creened element to prevent any resin carryover, and is recirculated. When the resin is to be packaged for disposal, it is pumped as a resin-water slurry to the waste sludae tank adjacent to the fillino sta tion . Excess water is decanted fram the waste sludce tank and returned to the resin hold tank. The remaining resin- 8 water mixture is mechanically acitated, pumped through the waste forwarding pump, combined with urea formaldehyde, and injected into the container with catalyst as described above for liquid waste streams. Af ter solidification, the container is sealed, labeled, and then stored in the storage area of the solid waste and decontamination building (Sections 4.4. 3.2 and 11.5.6) until shipped offsite. 11.5.3.3 Filter Handlina Cartridge filter elements are removed from service when the surf ace dose on the filter housing reaches a predetermined level or when the element pressure drop be comes excessive. The operation is carried out using remote handling eauipment and a tilter removal shield, when required. High activity filter cartridges are raised into the shield and are transported to, and lowered in to , the shipnina container for immobilization and subsequent shipment offsite. 11.5.3.4 Incompressible Waste Handling Contaminated metallic materials and solid objects are placed in 50 ft3 shipping containers. Either evaporator bottoms or water plus a solidification agent are added to the shippina container to immobilize the waste. 11.5-5 //9 Amendment 8 00e [ 4.! 3/28/75

SWESSAF-P1 11.5.3.5 waste Balino Operation Contaminated compressible materials are stored in suitably labeled waste hampers or polyethylene baas in different plant locationn. These materials are transported to the waste luler for compression into high density bales within a 55 cal drum. Additional compressible material is added and the drun content recompacted until the drum is filled. These sealed drums are itorea in the solid waste and decontamination buildina until shipped offsite (Section 11.5.6). During the waste lulina operations , the air flow in the vicinit y et the waste buler is directed by an exhauster throuqt a filter and then to the solid waste and decontamination buildina ventilation system (Section 9.4.3) . The total volume of g compressible and incompressible waste is estimated to bo 2,500 ft3/vr. 11.5.3.6 components Tables 11.5-2 and 11.5-3 sumnurize the design and operatina conditions of the solid waste syster components. 11.5.4 Expected Volumes Table 11.5-1 presents a listing of the expected volumes of spent resins from various sources entering the radioactive solid waste system. Pia. 11.5-2 nresents gross activities and weights or volumes for radioact ive solid waste sources. Containers of evaporator bottoms, resins, and miscellaneous incompressible waste are considered " wet." In order to solidity the amounts given in Fic. 11.5-2, 470 containers per year are 8l r eq uir ed . Ccanpacted or compressible waste is " dry" and contained in 55 cal d rums . ILised on experience at point 9each and Connecticut Yankee, approximately 300 containers per year can be 8 expected.

                                                                         ,u' v

1l fnL': 11.5-6 Amendment 8 1/28/75

SWESSAR-P1 11.5.5 Packaging Based on the gross activities given in Fig. 11.5-2 container activity will vary between negligible for most compressible or compacted wastes to less than 300 Ci/cc for reactor water purification demineralizer resins. The specific radionuclide content of the solid wastes is not yet available as explained in Section 11.5.2.

 ' Die filling of containers and the storage of radioactive solid wastes conform with 10CFR20 and 10CFR50 requirements.           Packages meet shipping regulations of 49CFR171-179.

Urea formaldehyde and catalyst are added to the container prior to, during, and after filling with waste to minimize the possibility of free liquids existing in the container. Complete solidification and absence of free liquid are ensured by the implementation of a process control program and preoperational testing as described in Sections 9.2.3 and 10.4 of 32 ANSI N198 (Draft American National Standard - Solin Waste Processir.g System, October 1976 ) . 11.5.6 Storage Pacilities A solidification area is located on the ground floor of the solid waste and decontamination building. The waste baler, urea formaldehyde tanks, catalyst tank, shipping containers, and drum storage space are located in this area. Wastes are packaged to allow for immediate shipnent after processing. Therefore, no decay time is assumed in the given estimate of package contents and activity levels. Shipping containers with high activity level are stored in the solidification area and placed in shields if necessary until ready for shipnent. An average of nine 50 cu ft containers of waste will be processed per week, based on the waste quantities given in Fig. 11.5-2. On this basis, the storage facilities allow approximately 5-1/2 weeks depending on the rate of solid waste accumulation. eeq 1 *7 CD; IbJ 11.5-7 Amendment 32 5/11/77

SWESSAR-P1 Storage capacity and storage time are based solely on anticipated operational factors. Holding capacity for radioactive decay is not provided, since individual containers are shielded as necessary. Operating data illustrating peak operating period solid waste quantities are not available in any clear and consistent form. The waste storage area has, therefore, been designed based on limited operating data and conservative engineering estimates and calculations to handle the following unusual operational occurrences:

1. Approximately 2-1/2 times average expected processing rates for periods such as refueling. Connecticut Yankee and Point Beach operating reports were reviewed in establishing this f a cto r .

2. Startup conditions that require unusually frequent regeneration of deep bed condensate polishing system demineralizer beds.

3. Continuous operation for a condenser tube leak of 0.3 gpm and I the resultant processing of approximately 2.3 times the average amount of regenerant chemical wastes.

Under any of the above conditions, the storage area can accommodate more than 2 weeks solid waste production. As noted a bove , radioactive decay time is not considered a significant factor in sizing the storage area for the majority of wastes encountered during any of these anticipated operational occurrences. Thus, the storage area is designed to handle waste production with offsite shipping delays of from 2 to 5-1/2 weeks. Spent core components whose activity levels are very high are handled under water within the reactor refueling cavity and fuel transfer canal and stored in the fuel pool until adequate packaging is provided for of fsite shipment. Components of low activity can be packaged in available or specially designed shipping containers and stored, if necessary, in the solid waste building. However, it is expected that the latter type components are shipped immediately. Various components have been handled, as discussed above, at the Connecticut Yankee and Yankee Rowe installations. 11.5.7 Shipment The shipment of radioactive solid waste conforms with 10CFR20 and 10CFR50 requirements and 49CFR171 throuch 179. Solid waste is transferred either directly to a licensed disposal contractor or to a common carrier for delivery to a licensed disposal burial site, as appropriate.

                                                                /

1t ,M ~': 0 b< o< 11.5-8 Amendment 7 2/28/75

SWESSAR-P1 11.5.8 Interface Requirements 8 Interface information given in the applicable interface sections of the NSSS Vendor's SARs is addressed in Table 11.5-5. bb/ It 11.5-9 Amendment 8 3/28/75

SWESSAR P1 TABLE 11.5-1 VOLUME OF SPEffr RESIN GENERATED ANIRJALLY Number Volume Frequency of of Replacement, Demineralizers Beds ft3/ bed beds /yr Required by SSW Fuel pool demineralizer 1 35 1 Cesium removal ion exchangers 2 35 4 (mixed bed) Boron demineralizer 1 35 2 waste demineralizer 1 35 2 Condensate polishing 9 235 1 demineralizer Required by B&W Purification demineralizers 3 50 6 19 Deborating demineralizers 3 65 2 Required by C-E Purification ion exchangers 2 35 2 Deborating ion exchangers 1 35 1 (anion) Required by Westinghouse 41 Mixed bed demineralizers 2 75 1 Cation bed demineralizers 2 75 1 Thermal regeneration deminer- 5 75 1 alizers Required by Westinghouse 3S Mixed bed demineralizers 2 30 1 Cation bed demineralizers 1 30 1 Thermal regeneration deminer- 5 75 1 @ alizers 1 of 1 Amendment 19 [g (., g

                                                  ,       ) z} 6 12/12/75

SWESSAR-P1 TABLE 11.5-2 RADIOACTIVE SOLID WASTE SYSTEM COMPONENT DATA Spent Resin Hold Tank

• Number 1 Capacity, gal 3,200 Operating pressure, psig 50 Design temperature, F 200 Material of construction SS Spent Resin Surge Tank l10 Number 1 Capacity, gal 500 Operating pressure, psig Atmosphere Design temperature, F 200 Material of construction SS or 10 fiberglass Urea Formaldehyde Tanks Number 2 Capacity, gal 5,000 Operating pressure, psig Atmosphere Design temperature, F 200 Material of construction SS or fiberglass 10 Catalyst Tank Number 1 Capacity, gal 500 Operating pressure, psig Atmosphere Design temperature, F 120 Material of construction Reinforced fiberglass Evaporator Bottoms Tank l10 Number 1 Capacity, gal 4,000 Operating pressure, psig Atmosphere Design temperature, F 212 Material of construction SS or fiberglass Shipping Container Number As required Capacity, ft3 50 Operating pressure, psig Atmosphere Design temperature, F 212 Material of construction Carbon steel 3
• Designed in accordance with ASME VIII, Division I.

1 of 2 Amendment 10 h()9 l [l 7 5/15/75

SWESSAR-P1 i TABLE 11.5-2 (CONT) Waste Sludge Tank Number 1 Capacity, gal 2,250 Operating pressure, psig Atmosphere Design temperature, F 212 Itaterial of construction SS Waste Sludae Decant Tank Number 1 Capacity, gal 150 Operating pressure, psig Atmospheric 12 Design temperature, F 212 Material or construction SS or fiberglass Amendment 12 2 of 2 ) 4 fj 6/16/75 K {, Cf

SWESSAR-P1 TABLE 11.5-3 RADIOACTIVE SOLID WASTE SYSTEM PUMP DATA Spent Resin Recycle Pump Number 1 Capacity, gym 120 Operating pressure, psig 150 Desion temperature, F 200 Material of construction SS Spent Resin Transfer Pump Number 1 Capacity, gpm 240 l8 Operating pressure, psig 150 Design temperature, F 200 Material of construction SS Waste Forwarding Pump

• Number 1 Urea Formaldehyde Pump
• Number 1 Catalyst Pump
• Number 1 Dewatering Pump
• l8 Number 1 Mixer Number 1 Urea Formaldehyde Unloadinr2 Pump Number 1 Capacity, gpm 75 Operating pressure, psig 100 Design temperature, F 200 Material of construction SS Spent Resin Transfer Pump Filter Number 1 Capacity, gpm 240 Design pressure, psig 225 Design temperature, F 250 Material of construction SS l Of 2 b69 l ij ) Amendment 8 3/28/75

SWESSAR-P1 TABLE 11.5-3 (CONT) Evaporator Bottoms Tank Pump Number 1 Capacity, gpm 20 Operating pressure, psig 50 Design temperature, F 200 Material of construction SS

          *These items are being bought as a complete package including instrumentation and are designed to handle the solidification process

@ r y 1"D Ou' Isd 2 of 2 Amendment 2 8/30/74

SWESSAR-P1 TABLE 11.5-4 PRINCIPAL NUCLIDES PRESENT IN SOLID WASTE Spent Boron Evaporator Waste Evaporator Nuclide Resins Bottoms Bottoms I-131 x x x I-133 x x x I-135 x x x Sr-89 x x x Sr-90 x x x Y-90 x Zr-95 x Nb-95 x Mo-99 x x Tc-99m x x Sb-127 x Sb-129 x Te-127m x x x Te-129m x x x Te-131m x x 5 Te-132 x x x Cs-134 x x x C3-136 x x x Cs-137 x x x Ba-13'!;c. x x x Ba-140 x x x La-140 x x x Ce-141 x Ce-144 x Pr-143 - Pr-144 x Cr-51 x x x Mn-54 x x x Fe-59 x x x Co-58 x x x Co-60 x x x 1 of 1 - - Amendment 5 UO7 i l' i 12/2/74

SWESSAR-P1

                             'I"LBLE 11.5-5 RADIOACTIVE SOLID WASTE SYSTEM INTERFACE IWYVRPATIO!1 The interface items are s,tated in RESAR 41, Appendix    11A.2,todated possible,         the December 1974. Responses    are given, whenever SWESSAR section in which compliance with the interface item is             .

described. Response to Interface Item RESAR 41 Interface Item Solid Waste Inputs from CVCS Flushing water and resin transfer connections are shown on Fig. 11.5-1. Interfaces from the liquid Not applicable. 'Ihese systems waste and steam generator are in Stone & Webster scope blowdown systems. of design responsibility. D U/ (, 0 il !~ J L-

                                                                                  ')

1 of 1 Amendment 8 4 W 3/28/75

SWESSAR-P1 TABLE 11.5-5 RADIOACTIVE SOLII WASTE SYSTEM INTERFACE INFORMATION The interiace items are stated in RESAR-3S, Appendix 11A.2. Responses are given, whenever possible, to the SWESSAR section in which compliance with the interface item is described. j7 RESAR 3S Interf ace Item Response to Interface Item Solid Waste Inputs f rom CVCS Flushing wcter and resin transfer connections are shown on Fig. 11.5-1. Interfaces from the liquid Not applicable. These system.3 waste and steam generator are in Stone & Webster scope blowdown systms. of design responsibility. [i (. 9 ) II 5 V-3S 1 of 1 Amendment 17 9/30/75

SWESSAR-P1 TABLE 11.5-5 RADIOACTIVE SOLID WASTE SYSTEM INTERFACE INFORMATION _B-SAR-205 Interface Item SNESSAR Interface Desian Resin Volumes Section 11.5.2.1 3C 9.3.4.1.4.16.1.a 11.5.4 9.3.4.2.6.16.1.a Isotopic Distributions Section 11.5.2 9.3.4.1.4.16.1.b 9.3.4.2.6.16.1.d Filters Section 11.5.2.6 9.3.4.1.4.16.1.c

9. 3. 4 . 2. 6.16 .1. e BSW 669 154 1 of 1 Amendment 30 1/28/77

SWESSAR-P1 TABLE 11.5-5 RADIOACTIVE SOLID WASTE SYSTEM INTERFACE INFORMATION CESSAR Interface Item SWESSAR Interface Design 9.3.4.3.2 Spent resin from the ion ex- Modification Fig. 9.3.4 (Sh 3) changer is transferred by shows the radioactive solid sluicing with water and air. waste system interface to CVCS The source of sluice water as modified. The SWESSAR-P1 is f rom the reactor makeup design requires only water for water pumps (at 100 gpm max- resin sluicing. The source of imum). 100 scfm (maximum) of water is the spent resin trans-air will be available from the fer pump. The sluice water air supply system for this may contain as much as the operation. shutdown concentration of boric acid. Except for the effects H of this boric acid, the sluice water meets the makeup water requirements of CESSAR Table 9.2.3-1. The demineral-izers are drained of sluice water prior to the additior of new resin. Tables 11.5-2, Radioactive nuclides inventor-12.1-1, ies, liquid volumes, and shield-12.1-2, ing requirements utilized for 12.1-3, the SWESSAR-P1 design are cal-12.1-4, cuJated by Stone 6 Webster. 12.1-Sc NSSS Vendor interface b3 forma-12.1-6 tion on the applicable systems and components are compared to Stone & Webster calculations. The applicable USSS Vendor in-form.ition is used to complement the Stone & Webster calculation if the comparison indicates that it is more conservative. 9.3.4.3.21 Not applicable. Stone & Webster designs the boron recovery system. C-E 1 of 1 Amendment 26

                                           ,       ;,         6/2/76 00'/    tJJ

j - BORON WASTE ' l

 )          p l

DEMINERAllZERS DEMINERAllZER I GRA?E I PATER Sf51EN

                      /l_

I l [flT (3 SPENT l T RESIN SURGE I EA

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                                                                                                                                                                                ~ SYSTEM
                                 ^

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                                                                                                                                                      -                 I                                          I SPENT RESIN TA                                                                                                                  I TRANSFER PUMP                         F                                 FROM PRIMARY ;

x- < r FILTER L.--l - I GRADE WATER I SYSTEM l

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PUM - m -J SPENT RESIN /' WASTE SLUDGE i 4 RECYCLE PUMP TANK i h ' oc -f4- i M h I EVAP. BOTTOMS i TANK HEATER l O NOTES: ALL BYPASSES, INTERCONNECTIONS, VENTS, ORAINS, l WASTE DECANT Q l. TANK EVAP. BOTT INSlRUMENTS, MONITORS, AND VALVES ARE.SHOWN.

                                                                                                                         \                                                                            TANK PUMP ON THE FOLLOWING SHEETS.                                                              ,

- fig .n .s-iC i rig .n .3-u j 66/! l 'J U 'i

6-IA IIE II b-IOl ' ANION AND CATION NSSS DEMINERAlllERS FUEL POOL CELSIUM REMOVAL RESIN MIX ANJ {

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A l i t t I t 2I r, 1 - I l COMPRESSIBLES y , l URE A FORM ALDEHYCE T ANKS - em I 55 GAL. > l DRUM [ I TRUCK FILL lp  ; i I STATION (,UREAFORMALDEHYDE l' l CATALYST WASTE BALER. l UNLOADING PUMP i ric1153  !

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puuP FORWARDING PUMP j h MIXER

                                                                                                                 >                   I FROM RADIDACTIVE LIQUID WASTE SYSTEu
                                                                     -1                        SHIPPING
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                 '  I FIG 11.2-1H                        y{

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             ;                  :      LIQUID WASTE SYSTEM                -             /

TANK FlG'11'2-1P FROM 99RON REC 0/ERY G 9 3.6-1 FI G 11.5-1 RADI0 ACTIVE SOLIO VIASTE SYSTB4 PnR STANDARD PLANT 3 SAFETY ANALYSIS REPORT SWESSAR-PI r I i AMENOM(NT 1261675 hh' I i

s I i I WASTE BORON I DEMINERALIZER I DENINERAlllERS I RESlN FILL ~ (IYP) 2 l'2" l _- I (TYP) -

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l 1 L2 1/2" l 1 G1 5-1C 1 1C SOLIO WASTE AND DECONTAMINATION BUILDING NOTE:

1. THIS PORTION OF THE SiSTEM 1S NON-NUCLEAR SAFETY CL ASS (NNS) EXCEPT WHERE OTHERWISE NOTED.

LOCATED IN THE ANNULJS BUILDING. f" l' - 3 O O (/ I J U)

I NSSS DEMINER)llZERS SC3 ->'q-NWS g.SC3 SC3 4 fins g SC3 SC3 NNS g-S C 3 SC3 NNS g SC3 I (WSS-10 Q (wSS-ly h 7, (WSS-22h'f'(WSS 23M I I i i w m, l' (TYP) i \$s l

                    -- 2 1:2" 8SSi3')   MM-19 )                                     C h tSS-20) C h ,8SS-21 )

l I SC3 mr ss1_ ss o d i NNS , i , 2 6 d L y

                                                                                                               . CONI. ON
                                                                                                               ' F I G. 11.5-18 CONT. FROM FIG. 11.5-1B NNULUS pig ;;,$_;g UllDINC RADI0 ACTIVE SOLIO WASTE SYSTEtt PWR STANDARD PLANT SAFETY ANALY$15 REPORT                      r-SWESSAR-?l                     hOj          [)
                                                                                      ,* MEN 0 MENT 12 6 'IS S5 o

i a f s l NSSS PtMINERAlllERS ] 2 3 t*

      .C SC34 NNS + Sc3           SC3 ->4- hN S  + SC3           SC3h NNS + SC3 SC3 & k NNS k SC3             SC3-     NNS + SC3 (fSS25      (WSS 27 % (W55 20             (WSS31     G (WSS 33 h ii -           .
                                <m           a L"j         h g k wSS 28) g WSS-24)        g3326)                             ,     !wSS-3 SC3
                        '        9          9 PJ

_' ' s ~1 _ s 6_ J b NNS 3p i k l CONT. FROM  : FIG. 11.5-1A - 2 1/2" CONT. ON m m - FI G. II. 5-1 A ' i 2 1/2" NOTE:

1. THis ICRil0N OF THE SYSTEM IS NON-NUCLEAR SAFETY CL ASS (NNS) EXCEPT WHERE OTHER31SE NOTED.

LDCATED IN THE ANNULUS Bull 0lNC. e i-, l 669 l .0

l 1 i l l FUEL. PODL 1 ANION AND CATICN

    ,     DEMINERAlllER                 l                  CESIUM REMDVAL IGN EXCHANGERS                        l RESIN WlX A:4D            g l                                   l                                                                            STDRAGE VESSEL I

l l l _ _ I l I n m n I l

                 \                                                           [                 \               l l

I l l l l l l i ,l l l l l r i l l I i I l l l I i l  ! l s i l l . n - M- ,

                %                    i l

1 l [h I b.h I I

                +440-M[5                            ' '

h ,' l i r l i I e + ca . I I i i I l I I I 2 11 P ]? '] : '] ;l P -] 1 I I a, l ' ' I l L____ i l a, l I I l a a i I 3 ,3  ; I l d ' i l i I FG i I i J-l l m I I _ m r. l _'_J FROM PRIMARY l ' ' 'I TURBINF l + FUEL _ BUILDING ?j GRADE WATER SYSTEM  : 1 M BUILDING F I G. 9. 2. 2 -1 FIG.II.5-IB RADIDACTIVE SOLID WASTE SYSTEM PER STANDARD PLANT SAFETY ANALYSIS PEFDRT SNESSAR-PI 0l $f \

                                                                                                                                           \

AMENDMENT 12 6/16'75

                                                                                                                   }A/S
                                                                                                                                       .                   M                 RAT
                                                                                                                                      '1"
                                                                                            ._ __ M                                                                   FIG. '

esp ( FROM PRIMARY GRADE WATER

                                                                           *s ./, Qm ,

SYSTEM 1 1 l '2" FIG.9.2.7-1 _

                                                                                                     ,s                                                                         .

FROM BORON RECOVERY SYSTEM 1 ri , f I FIG. 9.3.6-1 <2" t y. I-FROM BORON " r SPENT RESIN 7-N RECOVERY SYSTEM FI G. 9. 3.6-1 SURGE TANK FROM FUEL POOL i l- i g g FRCM CHEMICAL r ---- AN D Y0 LUM E i M(WSS4 CONTROL SYSTEM  ! FROM CHEMICAL (NSSS SCOPE) E~' AND VOLUME 1 4 LT -- -3 CONTROL SYSTEM ' WSS-1 )H .J FROM CHEMICAL H \ (NSSS SCOPE) ~ 11,2 I/ __ AND YOLUME g 5 'SS-7 CONTROL SYSTEM WSP g TO FROM CHErlCAL (NSSS SCOPE) r4 l i 1 2a 2 DR AND VOLUME -- q [ii pg CONTROL S'l STEM WSS-2 (NSSS SCOPE) p /W FRCM CHEMIC AL A ' S #-

                                                                                                                                 )        5

__ AND VOLUME - / g 'N CONTROL SYSTEM (NSSS SCOPE) CONT. FROM - b FROM CH FMI C AL _ _ FIG. 11.5 1A ~ t 2 L/2" ANC VRUME iW CON T Rl SY S T EM - SS-3_h FROM CHEMIC AL f (9555 SCOPE) F/ - ~ ~ ' - SOUNDING d ' L

                                         %'WSS-9 CCNTROL  'AND VOLUME SYSTEM          FP09 PRlH.RY FPC4 CHovlCAL AND                                 (NSSS SCCPE)                   AD WATER                                   r--          w I W   s h                                                                              FIG.b.2.7-1                                                                 IC @
                       ! WSS-4

[LT] V __i ( C 3 SC6P!) FROM SORON p

                                                   - RECOVERY SYSTEM                                                '

RES FROM BORCN L) HOLD N r" T AN K RECOVERY SYSTEM _ p FIG. 9.3.6-1 rT g FFCM RADIDACTIVE S - , , '3" FROM CHEMICAL AND r, ll0UID WASTE asp ML LONikt>L FIG.11.2- I F-(NSSS SCOPE) WSS-5yh , 33W QL, e , u i a VENT HEADER FOR THE DEMINERALfZERS ^

                                                                                                                           ;p h
                                                                                                                                                     ?"         -

b-'

                                                                                             '~~~

NOTES: g3p ,, ,

l. THIS FORil0N OF THE SYSTEM 15 NCN-NUCLE AR SAFETY CL ASS Azs H .( 2 5 3"-

(hNS) LOCATED IN THE SOLID WASTE AND / DEC3NTAMINATICN Bull 0 LNG. s NY ) q. l 3" 3 r. W . _ _{f 0 al WSP A'S 669 162 1 I l t

                                                                                                                                              , f- ' - -              gg, VEN TS AS d]

p - - - #- --- - CONT. ON C FIG. 11.5-1A 3- ,,y-3" ir Q __ /F I

                                                                                                                                                                                         ~

J WSP p-v_((g ]l V; EFIGDl0tCilvE #ASTE SYSTEM II.2-IA L10' ID J . 7 g 3.'4 "

                                                                                                                                         -ba                           \/

w r a C S _ . _ _ _ - - - - - - - - -

-                                                                                           1 SPENT RESIN I                           ' 45?

F TRANSFER l

                                ,3p         2'm, 3               I           r,   [

3--6 WSP I l L

                                                                                                                   / PD h AEPATED                                                                                                                                                           d '

l ( '/ INS

                                                                                                                       - TSP l

. 9.3.3-1 i _q {;7 --.

                  ^

l A's ) _3'A" l

    / 212=                                                                                                                                                    TO AERATED ORAINS l

FIG.9.3.3-1 I i3"

              -                                                                          l                  n                                                      ~
              '                                                      <   r    <

r n ( R0 'HCV

                                                                                                          -                                                                   ' , _ f HS T gsp Q                            a t ,s, 5

(-;/ RD @ -$>

                                                                                               \

FRC4 FIG.11.5-lE \

                                                                                                     \                 r[1 (j- }- - - - -               H ST - 3 "                                                       \            Y   db
   - {, ad$ et A S
         '                                                                            SPENT RESIN \ _                                -

• WSP "

a TRANSFERPLMP[ l' 4 -" 3 - L.f _3- ,' HS (SP Lu sg ,W ~l I 4A5 TO AERATCO

         -{            M A. S              SP VENTS F}G 9 1
                                                                                                                               }                             A w
                                                                                                        -. -             -y 3,

p.____

                                                                                      ~4      '

p- <D=4l~t wSP ' CCNT. FRCW TO AERATED ORAINS

                "              a3                                                                                               FIG ll.5-lE

[i n 3 FIG 9.3 3-1 NASTE F SLUDGF

 .h                           '

TANK ' 4 ""

4) 3" f ogl 2 l '2 '

l

                                                                                                                                   &%R, FRW

[""" 3' GRADE W TLR FIG.ll.5-lC

      ;,;;s                          F                                                                                               -r>

C n g ,. i nSiN iSe mucnuum s<se m,m me <,s e, m., CcNt DN

                                                                                                                                                 ,-                  _ Pn REFERnCE etANT
                                                               , o 1,                                                                                                    ,S,ESS,R..I
                                                                                                                                                                           ,, , T , , ,, < , , , 5oo R <,c, Tc, m-v
                                                                                                                                                                                                                 \

AWENDWENT 12 6 16 75 6

O OUTSIDE BulLDING _ , L l"

                                                                              -4" i

DRUM

                                                                                  <G

[ 3- , , m r R C A i WS { ~'I r-c "g ao

                             '[ [                                                              13P[

S ON ' {} ' 2p C { 4, I A-, u UREA FORuALDEHYDE L)[ i r 0)h a

                                        ;  5   UNLOADING PUMP 4

1' THIS PORil0N OF THE SYSTEM IS NON-NUCLEAR SAFETY CLASS (NNS) LOCATED IN THE SOLID WASTE AND DECCNTAMINAT10N BUIL0 LNG. e < . . 007 1'd ib-I

                                                                                                                                                             ?

t

                        ?

i INSIDE

~ 8UILCING I                                                                 -

L4 " L_4 s_ 4-L. L-3 ' M - ,'<s-2- _ FROM DEMINERAlllED WATER r:G.s.2.3-i 3 oa 6e e r a k [ g ,[ LIREA FORMALDEHYDE b 4= L.b. TANK (TTP)

                                                                                                                                     .SP

) h 4)j - - -- 3 d.' A LAHT

                           \                                                         _M                                              WSP      SSP

) i r ' r WSP I /2" ~7 r m; 1 j .2" 7 S g r,

                                                                                          --,r,               3g 3 /4"                                                              3 /4 "

q, iC 3m <. r, .,, g, ri j- 4 " 4- i t d 6 q6 o u a ,

                                                    ~j          s__ 4 =

L.2

                                                            ~
                                                    'G-               " ' '
                                                                                                   - CONT. ON r'                ^-           l               ' FIG ll.5-lE L

FI G 11.b-10 RADI0 ACTIVE SOLID WASTE SYSTEM PRR REFERENCE PL ANT SAFETY ANALYSIS REPORT SWESSAM-PI

                                                                                                                                   / , rs
                                                                                                                                                  ;/,      ,

00/  ; f;) AVENDMtNT 12 6 '16'75

s FROM DEMINERAlllED WATER FIG.9.2.3 ' , _ _, ,. w ~. - - i r - 2 1/2" l

                         ,r                        FROM R ADIC ACTIVE /~ 2'
                                                                               +

d' Li0010 WASTE

                              ,;.                  SYSTEN                                   ' FRou PA010 ACTIVE 2                   W         SYSTEW FROM BOPON REC 0VERf SYSTE's b"'4 -
                                                                               -               FIG ll,2-1H              .,

I ^ ^ FIG.9 3 6-1 i i 1/2" T [O m,2 r'

                                                                                                                         )
                              /                                                                                     _
                            /         ~

TO AERATE 0 DRAINS i I pcy icy

         '4                           FIG 9.3.3-i                                                          I LC
         'y CATALYST TANK l ' \'         I f           j (h'3
                                                                                                                             'y

[ _ M k ')FROM I I PRIMARY GRADE WATER lq( l H f,' D: , N /N ( hSYSTEM

                                             / y FIG 9.2.~-1 t)

L* 1 e-

                                                                                                           \

1

                                                                                                                                    \ ;72-
                                                                                                                                                                               -     -[

( [-- G1 -C I

                                                                                                                               --- -- ~
                                                                                                                                                                  ~
                                                                                                                                                                      'l            ~-

3/4 A Lk l i s

                 \ "_                                                                                                                                IbI 3/Ei)                      esp           vgsp            CONT. IROM                                   '/'

O FIC.11.5-10 ' 5 QD i IRA I U DEHYDE pyyp \ '(7)l a i,,, o - k , v I M gr 0 3p ( h.

                         $                                            HV }
                                                                                             ~~~f A/Sl                                                 bl N                                   l                                         C

_f ~3' CONT. ON I sl I(2" -

                                                                                                           '[*11/2"-           '-~

FIG.11.5-IC 7'

                                                                                       -tf                  I l                                         Cl OEWATERING m

CONT. FR0 1r FIG.fi 5-TO AEFATED 09AINS FIG.9.3.3-1 3a COMPRESSIBLES Q p , t U WASTE DECANT TANK j L

b. L 55 GAL. DRUM gASTE BALER NOTES: Cf3

1. THIS PnRil0N OF THE SYSTEM IS NON-NUCLEAR SAFETY CL AS$ (NNS)

LOCATED IN THE SOLIO WASTE AND DECONTAMINATION Bull 0lNu. s - t 669 160

a.

                                                                                                                                                                                               /

O 3

                                                                                    .}.                         A RATED VENTS 2' x                                           'IO S 3 3~I
                                 ^f                   ' f'                                 ,p            _ _ _ _ _ , _ _             _                         _

33 /2"N lisp BTC __ i 95P TANK gr bFR04'TO AUX 1L AIRY sk r -_ a __ g L T g l BOTTOWS STEAM & CONDENSATE 'V , at H TER TS} ,

          .l                                                         I N$

A SP

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L __ _J T q",'

             \

wr i (

          ^                   CONT. ON                                 , ,

l

       .,_ M FIG 11.5-1;                                                                         (

_ _ _ _ _ _ _ _ _ _ _ r 2" {~ TO AERATE? ORAINS l 1 O FI G 9. 3. 3-1 FAH ( l 1/2",; ,,{U

                                                                                                                            ~

l O l b b ummmens FS I _PS ' - _ PAL I ' -

                        !            I                        I EVAPORATOR B0TTOWS
                                           , ,7               ,

)[ _ _ . ,n . ' ' ] I TANK PUMP

  )!   WASTE                                                  I i

~ PUMP FORf AR0 LNG PROCESS l, Y M11ER l' I TO

AERAffD VENTS  %'g FIG.9.3.3-1 r-7 ,, l r I y n i sl_ i i 1" RO ---H SH fJ STOP PROCESS T i _ '3. '

      - 1/2"                                                                                                                                       ON HIGH
  .__                       __p.          _____________j                                           --

1 PAL [A l 'l/2' _ PS L _ _ P AH_ I l V l _ _d iSP I Si S~ l ' ' ' r - _ I~d ___L l UMP

                                                              !                 ~~

j f LTp.__________y ___---__-l r y, mi rip

                                                                                                                     '                                           , - __ __ _ gt_  

TO AERATED VENTS l FIG.9.3.3-1 ql RE j ART

 -la                                 DERA RING   '             Nf                                                         i             T-                 ' LSH               IL N                                                                                                       _ _ _ D~M PUMP                                                                                               l                                             75SP J

{} 7-. _ _ LSH Q

                                                                                                                                        -r                  ,_ - 49) s

( 01SPOSABLE LINER s I l _S R.- -

                                                                                                                                                                     ~

l h - k's}4 '--(L). 6 \ x N Wmn.s x'j XWk STOP PROCESS FIG.ll.5-lE STOP, ON HIGH DERATERING RADIATION RADI0 ACTIVE SOLID WASTE SYSTEM PUMP SHIPPING SHIELD PWR REFERENCE PLANT SAFETY ANALYSIS REPORT SWESSAR-PI bhCf 1il AMEN 0 MENT 12 6/16/75 e

91 5 r

                                                                                                                                                                   /

2 1

                                                                                                                                                                   /

E O 2 1 T S T 91 A R T W TO N D NP E M I A E D

                                                                                                                                           )

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r xr S xrAS l t r S e AS e BS e CS e DS t i e1 1 ie3 b ae2 hn.2 hn.2 hn.2 hn.2 T mz mz41 a c cz31 too11 t oo11 iN0 - t oo11 iN0 - too11 iN0 - O i e- i5 - i5 - iN0 - P ml v3 ml83 i ml83 mt 73 73 mt 73 mt 73 E S 3 oal rr a9 oa-rr19 l p oa-rr19 oar-rre19 mt rre19 ar- oar-rre19 oar-rre19 C A F R A

        -    f ev.

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 ?

R Vdf( Vdv( N Vdv( Vrev( Vrev( Vrev( Vrev( I N F T d d S d2 d1 e2 e1 n - n -m ncu ncu nom be. Y e B b B b B no S l .1 ) ) 0) 0) li r a

                                                                                    )    li r         )  li r        )  li r a
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o32 l a nf 4 4 dP b 2 4 4 dN2 e 8h e h i mPb42 2 8h i 8h mPO42 2 mmf rd1 h amf rd2 h ma rd3 h mmf rd4 h xrS xrAS trS trS e AS e BS e CS e DS i e1 ie1 ae1 ae1 hn.2 hn.2 hn.2 hr 2 mz i e-1 mz31 i2 - cz ie-1 cz ie-1 too11 iN0 - too11 iN0 - too11 iN0 - too11 iN0 - ml v3 nl83 u a- mlv3 nl u v3 mt 73 mt 73 mt 73 nt a 73 1 4 oal rra9 c rr19 oal rra9 cal rra9 oar-rre19 oar-rre19 oar-r r e J'9 c ar-rre19 R A

        -    f ev.

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M STIN I ?frEF FACF NINTS - PADIOACTIVE SOLID WASTT SYSTFM (W SS) ID NO. RESAF -41 MSAF-3S b-SAF 205 CESSAP flush line t o CVCS-M0010 cation desin-eralizer 2 (SW ESS 8@ - P1 Fig. 9.3.4-1 Sh 3) W SS -2 4 Resin sluice bwder Fesin sluice header Besin sluice leader Not Applicable flush line to CVCS- f lush line to CVCS- flush line to CVCS-MOD 11 thermal re- MUD-9 thermal re- MOD 9 deborating de-generation demin- generat ion demin- mineralizer X1A eralizer 1 (SW ESSAR- eralizer 1 (SWESSAR - (SWESSAR-P1 Fig. 9.3.4-1 P1 Fig. 9.3.4-1 Sh 4) P1 Fig. 9.3.4-1 Sh 4) Sh 4) WSS-25 kesin sluice header kesin slui& header hesin sluice header Not Applicable flush line to CVCS- flush line to CVCS- flush line to CVCS-MOD 12 thermal re- MOD 10 therinal re- MOD 10 deborating de-generation desin- generation desin- mineralizer X1B eralizer 1 (SW ESSAh- eralizer 1 (SWESSAk- (ShESSAR-P1 Fig. 9.3.4-1 P1 Fig. 9. 3. 4 - 1 Sh 4 ) P1 Fig. 9.3.4-1 sh 4) Sh 4) ig WSS-26 Resin sluice header Fesin sluice header Resin sluice header hot Applicable flush line to LVCS- flush line t o CVCS- flush line to CVCS-MOD 13 t hermal re- MOD 11 thermal re- MOD 11 delorating de-generatim demin- generatim dmin- mineralizer XIC eralizer 2 (SWELSAR- eralizer 2 (SWESSAk- (SWkSSAR-P1 Fig. 9.3.4-1 P1 Fig. 9.3.4-1 Sh 4) P1 Fig . 9.3.4-1 Sh 4) Sh 4) WSS-27 hesin sluice header Resin sluice header Not Applicable Not Applicable flush line to CVCS- flush line to CVCS-MOD 14 t herma l re - R)D12 t hermal re-generatim demin- generation demin-eralizer 2 (SWESSAR- eralizer 2 (SWESSAk-P1 Fig. 9.3.4-1 Sh 4) P1 Fig. 9.3.4-1 Sh 4) WSS-28 kesin sluice hmder Resin slui& header Not Appli ca ble Not Applicable flush line to LYCS - flush line to CVCS-mod 15 thermal re - n>D13 t hermal re-generat ion demin- generation demin-eralizer 3 (SWESS AF - eralizer 3 (NESSAR-P1 (Fig. 9.3.4 -1 Sh 4) P1 Fig. 9.3.4-1 Sh 4) WSS -2 9 kesin sluice hmder Resin sluice header hot Applicable Not Applicable flush line to (VCS- flush line to CVCS-

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                                                           '                                                OF F SI T E NSSS= 430                                  CO N TAIN ER OTHER                     S LW = 850 SERVICE               :

(4p Ci/cc 4s SHIELD!NG C ASKS AS WASTE REQUIRED R ADIOACTIVE EVAPORATOR LIQUID BO T TO M S WASTE  : 7,500 GAL / YR SYSTEM W.41, C.E = ( 1.4 Ci/cc FIG.11. 2 - 3 8 LW = (iJp Ci/cc W -3S = ( 4.1 Ci/cc L AUNDRY WASTE EVAP. BOTTOMS 270 GAL /YR W -41 = ( 3.7 x 10~5 Ci /cc 8 L W = (7.6 a 10-*y Ci /cc C.E. = ( 4.3 x 10-3g Ci/cc E ORATOR BORON BOTT M RECOVERY ' 575 GAL /YR SYSTEM W - 41 = ( 1.4 x 10' C i /cc FIG. 9. 3.6-1 B C W = (8.0 m 10' Ci/cc RW C. E. = ( 2.1 x 10 Ci/cc CHEMIC AL W - 3 S = ( 3.1 x 10' Ci/cc EVAPORATOR BOTTOMS 86,000 G AL / YR W ( 2.5 a lO-2p Ci/cc B C W =(4.8 xIO 2p CI/cc SPENT F(LTERS <6 C E. = (3 0 x 10-2p Ci/cc ( 7 5 x 103 Ci/cc W.3 S = ( 2.4 x 10-2 Ci/cc MISCE LL ANEOUS INCOMPRESSIBLE WASTES OPERATION & 250 FT3 /YR. M AINTEN ANCE NEGLIGlBLE ACTivlTY

DRUMS  : BALER ---> D RU M S O F F S I T E OPERATION L MISCELL ANEOUS M AINTEN ANCE _ COMPRESSIBLE NEGLIGIBLE WASTES ACTIVITY 2,250 FT / 3Y R F I G.11. 5 - 2 RADIOACTIVE SOLID WASTE SYSTEM ESTIM ATED QUANTITIES

@ PWR REFERENCE PL ANT S AFETY AN ALYSIS REPOR T SWESSAR-P1

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A M E N D M E N T 19 12 /i 2 / 7 5

e t 669 174

SWESSAR-P1 11.6 OFFSITE RADIOLOGICAL MONITORING PROGRAM The principal objective of the offsite radiological surveillance in the program is to measure radiation and radioactivity levels doses to the environs in order to ensure that radiation below population from normal low level radionuclide releases regulatory authorities. are The the dose limits prescribed by distinct phases: surveillance program consists of two preoperational and operational. The preoperational radiation surveillance program at a site will approximately two years prior to station generally commence operation. The objectives of the preoperational phase of the surveillance program are to:

1. Identify the probable critical exposure pathways and population groups; media and sampling locations along

2. Select sample critical pathways; Measure the background levels and their variations; and 3.

equipment, and techniques, and

4. Evaluate procedures, train personnel.

The operational radiation surveillance program commences with in-designed to evaluate itial station operation. This program is the effects of station oyuration on environmental radioactivity based on and radiation levels. The operational program will be the experience obtained during the preoperational monitoring prog ram . The Utility - Applicant's SAR will provide the specific offsite monitoring program for the particular site location. 11.6.1 Expected Background External background radiation levels result primarily from emis- of sions from natural radioactive materials in the soil and rock the upper several inches of the terrestrial surface, from cosmic detonations of sources, and from fallout from the atmospheric nuclear weapons. Temporal variations in the background exposure rate occur at a given location; in addition, background radiation varies in different geographic areas. Natural terrestrial radiation is dependent upon the content and distribution of naturally occurring radionuclides in the surface soil and rock. Variations in different areas are due to the the surface. The physical characteristics andtothe thisgeology component of are potassium-40 and significant contributors the decay series of uranium-238 and thorium-232(2). The temporal variations in the terrestrial exposure rate (usually less thanwith 20 percent) which occur at a location are primarily associated in the outgassing of radon from the soil due to changes 11.6-1

                                                                  <tr UUY j7L l J

SWESSAR-P1 barometric pressure and soil moisture. Precipitation from rain or snow can shield gamma rays emitted from soil or rocks, thu s reducing the exposure rate in the air above the ground. On the other hand, increased soil moisture reduces radon emanation f rom the ground and may result in increased gamma ray fluxes from the uranium decay series which tend to of fset the shielding ef f ect of increased soil moisture. Cosmic radiation is composed primarily of high energy protons and helium nuclei which interact with the upper atmosphere to produce an ionizing component in the lower atmosphere consisting of muons, electrons, and a minor neutron component (2). The cosmic ray exposure rate is dependent on many factors, the most significant of which is altitude. Two other factors whi-h influence cosmic radiation are the solar cycle and geograph'.c latitude. O' Brian and McLaughlin(3) have s ummariz ed the variations in cosmic ray exposure rates. Another variable component of background radiation is fallout from atmospheric nuclear weapons testing. Measurements in various parts of the United Statest+) have indicated that fallout accounts for less than 10 percent of the background exposure rate. The major fallout nuclides which have been detected in the continental United States are cesium-137, zirconium-niobium-95, and strontium-90. The exposure rate from fallout will slowly decrease if th er e is no further atmospheric testing of nuclear wea pons . 11.6.1.1 External Backcround Exposure Rates Measurements 01 background radiation exposure rates in the United States have been made by many individuals and groups since 1960. The most extensive measurements were made during aerial surveys sponsor ad by the U.S. Atomic Energy Commission. These aerial radiological measurement surveys (ARMS) were conducted by the U.S. Geological Survey and EGSG. These measurements were used by Oakley(5) to estimate the exposure of man to natural radiation sources in the United States. In this connrehensive study, the author calculated cosmic and terrestrial background dose rates throughout the United States for ma jor population areas. The data from Oakley's study have been used in this section as the basis for estimating a range of expected background dose rates for the major geographic subdivisions in the continental United States. Three distinct areas of terrestrial radiation can be found in the continental United States; they are outlined in Fig. 11.6.1-1. The calculated dose rates range from approximately 23 to 90 mrem per year. The lowest rates are found on the Atlantic and Gulf Coastal Plains, while the highest occur on the eastern side of the Rocky Mountains near Denver, Colorado. In the Denver region, the elevated terrestrial dose rates have been attributed to the 11.6-2

                                                                     <   t-
                                                                        ,1  1, ' ..[

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SWESSAR-P1 high radionuclide content of surface rock. In the remaining areas of the United States (those not mentioned above) , the dose rate was approximately 46 mrem per year. However, within this region certain locations were found to have dose rates which were both lower and higher than 46 mrem per year. The most notable of these were the San Francisco area (28 mrem per year) ; Las Vegas, Nevada (20 mrem per year) ;several areas in Connecticut (approxi-mately 65 mrem per year) ; and the area near Wheeling, Ohio (69 mrem per yedr) . The estimated comnic ray dose rate ranges for areas in the United States are shown in Fig. 11.6.1-2. It can be seen from this figure that the dose rates are fairly uniform in the eastern and midwest areas of the country, while they increase markedly in the western mountainous regions. The cosmic dose rates range from 40 to greater than 80 mrem per fear; the highest rates are found in the Rocky Mountain ranges, while the lower dose rates are found in areas near sea level. The upper limit for a populated community in the United States can probably be considered to occur in the vicinity of Leadville, Colorado (elevation between 10,000 and 10,500 feet) where the cosmic dose rate was calculated to be approximately 160 mrem per year. Total dose rates are the sums of the cosmic and terrestrial dose rates. A map showing the ranges in the total dose rates throughout the United States is given in Fig. 11.6.1-3. The calculated total dose rates generally range from 63 to 165 mrem per year. The lowest total dose rate (63 to 74 mrem per year) is found in the Atlantic and Gulf Coastal Plains due to the relatively low cosmic and terrestrial components. In New England, the Midwest, and states bordering the Atlantic and Gulf Coastal Plains, the dose rates are higher (86 to 96 mrem per year) due to an increase in the terrestrial dose rate. In the areas farther west, the increase in the total dose rate can be attributed to the increase of the cosmic ray component (altitude increases) since the terrestrial dose rate in these areas is fairly uniform. On the west coast, the total dose rates again become lower due to a lower cosmic component as altitude above sea level decreases. The maximum total dose rate for a populated community can be found in the area of Leadville, Colorado, where the calculated dose rate is 206 mrem per year. The cosmic component accounts for approximately 78 percent of the total. 11.6.1.2 Interna) Background Exposure Rates The internal dose to man is the result of the irradiation of body tissue and bone caused by emissions from radioactive substances found within the body. Naturally occurring radionuclides derived from the earth's crust are, on the average, the major contributors to this dose. These materials enter the body through the skin, by inhalation, and by ingestion of food and water. As with external exposure, the internal dose received

                                                                        .m bbi      5'#

11.6-3

SWESSAR-P1 from these sources may vary markedly with geographic location and living habits. Natural potassium-4 0 is the major contributor to man's natural internal exposure. Due to its relative natural abundance of 0.0118 percent and energetic beta and gamma emissions, it is the predominant radioactive component in normal foods and human tissue. A man weighing 70 kilograms contains approximately 140 grams of potassium (6). Thus the potassium-40 content amounts to approximately 0.1 uCi. This isotope delivers a dose of about 20 mrem per year to tissues and approximately 15 mrem per year to bone. Other sources of natural internal exposure are f rom the radio-nuclides in the uranitrn and thorium decay series and from carbon-

14. Radium-226 in the uranium series is selectively absorbed by the bone. The dose rate from radium varies markedly in locations throughout the United States primarily due to the uranium content of soils and underlying rock; variations exceeding a factor of 10 have been recorded (7). Other members of the uranium and thorium series, such as the radiogases radon and thoron, also con tribute to internal exposure as do their particulate daughter products.

Carbon-14, another naturally occurring radionuclide, makes only a relatively small contribution to man's internal exposure. A summary of estimated average internal dose equivalent rates to man from natural radiation sources (a) is given in Table 11.6.1-1. The sources of radionuclides and doses in a given area are subject to the variations mentioned previously. Fallout nuclides from the testing of nuclear weapons which have become incorporated into dhe natural environment also contribute to the internal dose. These nuclides enter the body in the same manner as the natural emitters. The levels of these nuclides throughout the United States are highly variable. Table 11.6.1-2 lists the estimated whole body dose from inhalation of radioactive fallout for 1963, 1965, and 1969. The fallout nuclides of greatest importance for internal exposure from inhalation are cerium-144 10l and strontium-90. Whole body dose rate estimates from ingestion of f allout nuclides in the United States f rom 1963 to 2000 are presented in Table 11.6.1-3. Strontium-90 is presently the largest contributor to the whole body dose and is expected to remain so through the year 2000. Carbon-14 contributes a larger percentage of the whole body dose than cesium-137. 11.6.2 Critical Pathways The three general types of sites considered are river, lakeshore, and seashore. The effluent monitoring system is described in Section 11.4 and the data obtained will be in conformance with R egula tory Guide 1.21. The confirmation of site specific critical pathways will be through a program such as that described in this section and will conform to Regulatory Guide 4.1. Exposure pathways which must be considered for these types 11.6- 4 Amendment 10 5/15/75

                                                        'n /    I /0

SWESSAR-P1 of sites will differ somewhat in the assumptions employed for dilution and dispersion. In some cases, drinking water icr example, the pathways are not identical. The following sections consider these exposure pathways based on the releases from the gaseous and liquid waste systems described in Sections 11.2 und 11.3, and the average values of site specific parameters determined for operating plants or plants under construction. Since the liquid and gaseous releases from a W-3S NESS are of the same order of magnitude as a W-41 NSSS (Sections 11.2.1, 11.3.1, and g 11.3. 2) , f or W-3S. Fig. 11.6.2-1 through 11.6.2-25 are not duplicated 11.6.2.1 Liquid Releases During routine operation, small quantities of radionuclides will be releasec and discharged into the receiving body river, lake, or ocean. The estimated annual averageofradionuclide water: a concentra tions in the liquid eff1uents are listed in 11.2-32. Table Release of the radionuclides into the receiving body in creases levels of radiation and radioactivity in the environment und muy result in doses to man. The various human exposure pathways that are considered include: Liquid discharge - water --+ external exposure Liquid discharge water- _ sediments - external exposure Liquid discharge water-  : drinking water -- man Liquid discharge _. water  : fish and invertebrates _ mun Liquid discharge - water - aquatic and marine plants.-man Liquid discharge water - irrigation - vegetation  : man These pathways are common to all the general types 01 sites with the exception of the drinking water and irrigation pathways, which are not applicable to seashore sites. The relative significance of the various exposure pathways is determined by comparing the dose to man through each pathway. External exposure to the liquid effluents is primurily due to recreational use of the receivina body waters in the vicinity the plant. of A hypothetical individual the concentra tions of radionuclides is assumed to be exposed to i.n the plant 's liquid effluents with nominal estimates of tilution while engaged in recreational activities. r.xposure to the emitted gamma and beta radiation occurs through immersion in water while swimming in the receiving body for 100 hours per year. A person boating on the receiving body will primarily be exposed to the emitted gamma 11.6-5 Amendment 17 OD.'I 9/30/75 l l7 'r)

SWESSAR-P1 raf4 ' ion and is assumed to be so exposed for 200 hours per year. Shoreline accivity, such as walking, fishing, or sun bathing on a beach, may result in exposure to the radiation emitted by radionuclides in the receiving body and sediments in which the radionuclides have accumulated. An individual is assumed to be engaged in shoreline activity for 500 hours per year. The dose rates through these pathways are directly proportional to the concentration of the radionuclides in water at the point considered und are essentially independent of the type of receiving body. The only factor which modifies dose rates is the shore width f actors used f or exposure to sediment. Shore width f a ctors ot 0.2, 0.3, and 0.5 were used for the river, lakeshore, and seashore sites respectively. Dose equivalent rates through these pathways are presented as a function of effluent dilution in Fig. 11.6.2-1 und 11.6.2-2 for lake, river, and ocean sites. Because of the potentially low plant discharge rate, rapid dilution of the effluent is expected. Effluent dilution tactors typical of the various sites for a nmmber of pa thways ( S ) are listed in Table 11.6.2-1. Dilution factors are included as appropriate in the following figures. Internal doses trom the radionuclides in the liquid ef fluents may occur from drinking 'ater at river and lake sites anc from eating aquatic and :narine organisms containing these radionuclides at any or the type sites considered. Water containing radionuclides f rom the liquid ef fluent may be drawn t rom the receiving bocy f or use as private or municipal potable supplies. The dose equivalent rates to the whole body and organs of an individual assumed to drink 1.2 liters per day or water containing the discharged radionuclides are shown in Fig. 11.6.2-3 as a function of dilution. Fish and invertebrates may be harvested f rom the receiving body, commercially or f or sport. If they reside in the vicinity of the plant discharge, they may contain concentrations of the radionuclides released in the plant's liquid ef fluent as a result of bioaccumulation. The concentrations of radionuclides in biota can be computed as the product of the water concentration and a bioaccumulation or concentration factor. Concentration factors are available for stable elements and radionuclides for freshwater (20) and marine organisms (31) as shown in Table 11.2.8-1. An individual is assumed to consume 50 grams per duy at fish und of invertebrates. The whole body and organ dose equivalent rates to this individual are shown in Fig. 11.6.2-4 tor fresh water fish and invertebrates and in Fig. 11.6.2-5 throuuh 11.6.2-7 tor marine fish, mollusks and crustacea as a tunction 01 dilution. The assumed consumption of mollusks and crustacea is 25 g/ day ot each, for a total 50 g/ day of marine invertebrates. Aquatic and marine plants which grow in the vicinity of a plant discharge may accumulate the radionuclides released in the liquid

                                                                  't 1

0;l J' 11.6-6 Amenduent 17 9/30/75

SWESSAR-P1 effluent. In most cases, human consumption of these plants is negligible. However, in some cases plants may be used directly as food or as stabilizers in foods. The time associated with processing and distribution allows decay for 2,000 hours between harvest and ingestionC *). The dose equivalent rates to a person 11.6-6A Amendment 17 9/30/75 669 18i

SWESSAR-P1 assumed to consume 2 grams per day of aquatic or marine plants are shown in Fig. 11.6.2-8 and 11.6.2-9 for various dilutions. The water of rivers and lakes may be used for irrigation of cro ps . It is assumed that this water contains radionuclides discharged in the liquid effluent. Spray irrigation of leafy vegetation will result in deposition of radionuclides on the veg etation and root uptake from the soil. It is assumed that an individual consumes 50 grams per day of lettuce which is spra y-irrigated. This lettuce is assumed to be irriga ted by 110 1/m2/ month, having a growing season of 3 months, a plant density of 2.3 kg/m2 and a leaf retention factor of 30 percent for foliar deposition. The dose equivalen" rates through the 10 irrigated vegetation pathways are shown in Fig. 11.6. 2 -10 f or river and lake sites. The actual dilution factor would be approximately 300 at the site boundary as opposed to 1.0 f or undiluted effluent. Considering dose equivalent rates and the dilution factors from Table 11.6.2-1, the critical pathway for external whole bo dy irradiation is shoreline activity. The critical pathway for seashore plants is the consumption of saltwater crustacea. The critical organ is the gastro intestinal tract and the dose is attributable primarily to cobalt 58 and 60. Reductions would be expected if realistic assumptions were employed as far as biological half-life in man and fish and the time necessary for equilibrium to be reached. 10 The critical pathway for lake and rivershore plants is the consumption of fish. The dose equivalent rate to the critical organ, the whole body, may be considerably less if actual dilution is considered. 11.6.2.2 Ap arne Radioactivity Releases Small quantities of radionuclides will be discharged to the atmosphere during routine op eration as described in Section 11.3. Table 11.3-3 lis ts annual airborne radionuclide release rates under normal conditions. The radioactivity discharges will occur primarily from the station ventilation vent and will be transported and diluted in a manner determined by the prevailing meteorological con ditions . Annual average meteorological conditions as determir.ed for river, lakeshore, and seashore sites (see Se ction 11.3.C) are used in assessing the potential radiation doses to individuals and the general population. The tollowing exposure pathways are considered for atmospheric releases from all standard plants: Atmospheric discharge man (whole body external exposure @ and inhalation)

                                                                     </o gO1       )0)
                                                                                .UL 11.6- 7                    Amendment 10 5/15/75

SWESSAR-P1 Atmospheric discharge deposition on vegetation milk -~- man 10 Atmospheric discharge deposition on soil and vegetation--man The significance of these potential exposure pathways is evaluated by comparing the calculated dose equivalent rates which are based on the estimated radionuclide releases and average site meteorological conditions f or each of the three general types of sites. Dose estimates for a hypothetical individual who receives the maximum exposure through the various atmospheric release pathways are calculated at the mean exclusion distances of selected plants for each general type of site. The normalized ground level c on centra tion (CHI /Q) for each type of site consists of the mean and +2 level in the worst case sector for operating or proposed units on that type of site. The values of these CHI /Qs versus distance for river, lakeshore, and seashore sites are described in Section 2.3.5 (Fig. 2.3.5-1 through 8) . For external and inhalation doses, the hypothetical individual is assumed to be located continuously at a distance 0.5 mile from the release point in the worst case sector. The calculated whole body gamma dose equivalent rates as a function of distan ce are shown in Fig. 11.6.2-11, 11.6.2-12, and 11.6.2-13 for lakeshore, 10l river, and seashore sites. The highest rate of 0.12 mrem /yr occurs at the river site. These calculated dose rates result primarily from the radioisotopes of xenon and krypton and assume no protective credit for housing or clothing. The beta skin dose equivalent rates are shown in Fig. 11.6.2-14, 11.6.2-15, and 11.6.2-16 and follow the same pattern as whole body doses. The inhalation of radioactive iodine results in Daternal expo-sures. The critical organ is the infant thyroid from inhalation of radioiodine . The calculated dose rates to the infant thyroid f rom inhalation at river, lake, and seashore sites are shown in Fig. 11.6.2-17, 11.6.2-18, and 11.6.2-19. As in the case of submersion, the dose equivalent rate is concentration dependent and the maximum occurs at the river site. The deposition of radionuclides in the gaseous effluents on vege-totion may result in doses to an individual via the milk pathway or through the consumption of vegetables. In the case of the milk pathway, the critical organ is the thyroid of an infant who cons umes milk solely from the dairy herd with the hichest radiciodine intakes . This herd is assumed to be on pasture continuously at a dis tance 1.0 mile from the release point. These assumptions are additionally conservative as the nearest dairy animal may be miles distant and also because dairy animals, especially in northern latitudes, are on pasture and can ingest 10 radioiodine for only a portior. of the year. The dose equivalent ratesofto the inf ant thyroid for individuals consuming 1 liter per day whole ndlk are shown in Fig. 11.6.2-?0, 11.6. 2-21, and

                                                                     0       1n7 b it l !

11.6- 8 Amendment 10) 5/15/75

SWESSAR-P1 11.6.2-22 for each general type of site. The method of computation is that specified in Regulatory Guide 1.42 (Section 10 3A.1-1.42) The deposition of radioactive particulates may result in indivi-dual doses through the consumption of leafy vegetables. Foliar deposition and deposition on soil and uptake through the roots are the means of entry of radionuclides to the veg etation pathway. The critical organ for this pathway is the thyroid of an adult, assuming infants consume a negligible amount of fresh vegetables, and the critical nuclides are iodine-131 and 133. The leafy vegetable considered is lettuce, which has a plant density of 2.3 kg per m2, retains 30 percent of the radiciodine deposited on it, and has a growing season of 3 months. The thyroid dose equivalent rates to adults consuming 18 kilograms of 10 lettuce during the 3 month growing season are shown in Fig. 11.6.2-23, 11.6.2-24, and 11.6.2-25 for river, lake, and ocean sites respectively. The critical pathway is the radioiodine-grass-cc7-milk-infant chain. The critical organ is the infant thyroid and the largest dose equivalent rate is at the river site. Inclusion of a pasturage tactor and consideration of the actual dairy animal location would reduce the dose through this pathway at most sites. 11.6.2.3 Assumptions for Dose Calculations Liquid Releases The pathways of human exposure from the release of radionuclides in the liquid ef fluents include (a) the consumption of water and foods containing radionuclides, (b) bodily contact with the receiving waters, and (c) external exposure from the receiving water and sediments.

a. The calculated concentrations of radionuclides in the water and f ood are the bases for estimating the internal doses fram ingestion. The dose from ingestion can be calculated from the dose factors and methodology presented by Soldat.(12) Using these dose factors 10 presumes that the rates of ingestion, organ sizes, effective half-lives, and radionuclide distributions in the body are those associated with the " standard man."

Dose estimates for the consumption of aquatic and marine organisne (e .g . , fish) require the application of appropriate concentration or bioaccumulation factors when calculating concentrations.

b. The calculation of the dose to the whole body from swimming is based on the water immersion dc e factors 10

_@ and methodology of Soldat.cs2) It is assumed that this 11.6- 9 Amendment 10

                                                      ,                5/15/75 OU"       }3 4

SWESSAR-P1 whole body dose consists of ona-half of the " skin" component and all of the " body" component. The " skin" cunponent is that dose resulting from the beta and low energy garma radiation which could penetrate 7 mg/cm2 of M tissue. Since these radiations are not highly penetrating, half of this value is used to approximate the whole body dose component. The " body" component consists of penetrating gamma radiation which will contribute directly to a whole body dose. This component is calculated at a 5 cm depth in tissue.

c. Direct radiation from the water must be considered in estimating the doses to boaters and for shore a ctivity (i . e . , fishing) . In the case of exposure while boating or standing on the shore, direct radiation fraa the water must be considered, and the dose to the individual can be approximated by relating it to the (jamma exposure rate in the water and an appropriate geometry factor.

The dose to individuals on the shore from exposed sediments with radionuclide accumulations requires that the concentration of accumulated radionuclides first be determined and then the exposure rate at a predetermined height can be calculated. Sediment accumulations in this study were based on an empirical model of Soldat et al published in the AEC Report WASH-1258(23). Gaseous Releases The critical pathways considered for gaseous releases include: (a) direct exposure from a cloud of radioactive gases, (b) inhalation of radioactive particles, and (c) consumption of foods containing deposited radionuclides.

a. The dose f roi direct exposure to radioactive gases can be estimated by assuming submersion of the individual in a semiinfinite cloud or some known concentration. The relation of concentration and average energy per disintegration proposed by the ICRP(14 ) can then be used for estimating the dose from many radionuclides.

b. The inhalation dose is a.etermined by means of the methodologies presented in Regulatory Guide 1.42 (Section 3A .1- 1.4 2)

c. One of the more important food chain exposure pathways is via milk consumption. The dose equivalent rate to the thyroid is calculated from the ground level release g method outlined in AEC Regulatory Guide 1.42 Revision 1 in order to provide very conservative dose estimates.

The dose rate reduction associated with elevated (root top) release points would be used in a case-by-case basis when actual sites are considered for this plant. ci iO ]OI

                                                                      ,  ;3 11.6- 10                 Ameadment 10 5/15/75

SWESSAR-P1 11.6.3 Sampling Media, Locations and Frequency Detailed preopera tional radiological environmental monitoring prograns should be designed on a site specific basis. The design of the preoperational program will be af f e cted by numerous factorn(15). These include: 10

1. The -radionuclides expected to be released, the activity released, and the methods and locations of the releases;

2. The behavior of these radionuclides in the environment:

3. Natural and man-made environmental features which affect radionuclide behavior;

4. The utilization of adjoining areas for agriculture, fisheries, food supplies, industry, and recreation; and

5. Population distribution and habits.

Since only one of these items can be explicitly defined, the sampling media, locations, and frequency can be assigned in only a general fashion. While environmental media on the oreviously defined potential critical pathways will be sampled and analyzed during the preoperational program, the media sampled will vary, in detail, among sites. General types of samples to be collected, approximate frequency of collection, and relative locations are shown in Table 11.6.3-1. 11.6.4 Analytical Sensitivity The types of samples and approximate sample sizes appear in Table 11.6.3-1 along with type of analysis. The analytical sensitivity of the program depends largely on the equipment and methods employed for analysis. Typical analytical sensitivities for gross activity detection procedures are listed in Table 11.6.4-1. Current mininum practical detectable concentrations of specific radionuclides in environmental samples are listed in Table 11.6.4-2. Sensitivities are typical of those r equired by regulatory agencies or offered by commercial radiological laboratories. Estimated annual dose equivalent rates corresponding to the minimum practical detectable concentrations are included in the tabulation. 11.6.5 Data Analysis and Presentation The measurements of radioactivity in environmental pathways during the preoperational and operational radiological monitoring program will, in general, employ analytical techniques for the identification of specific radionuclides rather than such nonspecific techniq ues as gross beta or gross gamma analysis. The analytical results should be reported with the associated statistical errors. The meas urements will be reviewed and 11.5- 11 Amendment 10 _ 5/15/75 669 100

SWESSAR-P1 evaluated by comparing the measured radioactivity with the levels determined during the preoperational phase of the program. Since the natural radioactivity of most environmental samples will vary from season to season, and to a lesser extent from year to 10 year,(15) the use of specific analytical techniques will allow assessment of the plant's contribution to environmental radioactivity, in the absence of other than natural sour ces of radioactivity. In the event fresh fallout from nuclear detonations contributes significantly to environmental radioactivity, it may prove necessary to base comparisons on wider scale fallout programs. An alterna tive approach, and one which is applicable to nonspecific techniques such as the use of gross beta analysis for air particulate samples and the use of thermoluminescent dosimeters to measure environmental radiation levels,' involves comparisons with data from distant or control sampling locations. The measured preoperational levels of radiation or radioa ctivity at the location of interest and the control location are compared, and the average difference and standard deviation computed. Measurements during operation can then be interpreted in terms of dif ference between control and sampling locations. Significant changes in the difference between measurements at nearby and distant locations resulting from increases at the nearby plants would indicate possible contributions from direct radiation or the radionuclides released in gaseous effluent and would be cause f or f uther investigation. MEb W The results of the radiological environmental monitoring program will be routinely reported in a format compatible with Regulatory Guide 4.1 or other currently acceptable guides at the time of submission. 11.6.6 Program Statistical Sensitivity The minimum detectable dose to man that can be reliably determined by an environmental radiation surveillance program is a f unction of the measurement sensitivity and natural background variations. Further, the minimum detectable dose is influenced by the location of monitoring points, site-specific environmental conditions, and the major contributing radionuclides. Table 11.6.4-2 lists the potential individual doses that might result from environmental radioactivity levels equal to the meas urement s en sitivi ty . Exte rnal gamma exposure (as measur ed by thermoluminescent dosimeters) and the possible consumption of iodine-131 on leaf y vegetation appear to be the least sensitive exposure pathways. The minimum detectable doses for each of these pa thways could be on the order of 10 mrem per year. The sensitivity of the overall environmental radiation surveillance program is dependent on the sensitivities along the various exposure pathways.

                                                             .         i   /

11.6- 12 Amendment 10 5/15/75

SWESSAR-P1 References for Section 11.6

1. Lowder, W.M. and Solon, L.R., " Background Radiation, o Literature Search," USAEC Document NYO-4712 (1956).

2. Oakley, D.T., " Natural Radiation Exposure in the United States," USEPA, ORP/SID 72-1, June 1972.

3. O'Brien, K. and McLaughlin, J.E., " Calculation of Dose and Dose Equivalent Rate to Man in the Atmosphere from Galactic Cosmic Rays," USAEC Document HASL-228 (1970).

4. Iowder, W.M. and McLaughlin, J.E., " Environmental Radiation in the Continental United States," USAEC/HASL TM71-21 (1971).

5. Oakley, P.J., Ibid.

6. International Commission on Radiological Protection. 1959.

         "Repo rt   of   ICRP Committee II on Permissible Doses for Internal     Radiation," ICRP Publ. 2, Pergamon Press, New York.

7. Russell, R.S., " Radioactivity and the Human Diet," Pergamon Press, Glasgow, Scotland. 1955 p 17.

8. Klement, A.W. et al, " Estimates of Ionizing Radiation Doses in the United States 1960-2000," U.S. Environmental Protec-tion Agency, Office of Radiation Programs, Division of Criteria and Standards, Rockville, Maryland (1972).

9. U.S.A.E.C. " Final Environmental Statement Concerning Proposed Rulemaking Action: Numerical Guides for Design Objectives and LCOs to Meet the Criterion 8ALAP8 for Radioactive Materials in Light Water Cooled Nuclear Power Reactor Ef fluents," WASH 1258, July 1973.

10. Thompson, S.E., Buron, C.A., Quinn, D.J., and Ng, Y.C. 1972.

         " Concentration Factors of          Chemical Effluents in        Edible Aquatic      Orga ni sms , "  USAEC    Report UCRL-50564, Rev.        1, University of California, Lawrence Radiation Laboratory.

11. Freke, A.M., "A Model for the Approximate Calculation of Safe Rate s of Discharge of Radioactive Wastes into Marine Environ-ments," Health Physics 13: 743-758, (1967).

12. Soldat, J.K. et al, "Model and Computer Code for Evaluating Environmental Radiation Doses," BNWL-1754, February 1974. M

13. Soldat, J.K., Shipler, D.B., Baker, D.A., Denham, D.H., and Robin son , H .H . , 1973. " Computational Model for Calculating Doses from Radionuclides in the Environment," In AEC Final Environmental Statement--ALAP-LWR Effluents. Volume 2, NTIS Report WASH-1258.

                                                                       <ro (gg                                                                   007      1O}

io 11.6- 13 Amendment 10 5/15/75

SWESSAR-P1

14. International Commission on Radiological Protection. 1959.

   "Repo rt  of  ICRP Committee II on Permissible Doses      for Internal Radiation, ICRP Publ. 2, Pergamon Press, New York.

15. Interna tional Commission on Radiological Protection, 1965,

   " Principles of   Environmental Monitoring Related to     the Handling of Radioactive Materials," ICRP Publication 7, Pergamon Press, London.

9 66y 139 0 11.6- 14 Amendment 10 5/15/75

SWESSAR-P1 TABLE 11.6.1-1 ESTIMATED AVERAGE ANNUAL INTERNAL WHOLE-BODY DOSE RATES FROM NATURAL RADIOACTIVITY IN THE UNITED STATES (a) Annual Whole Body Dose Rate Radionuclide (mrem) H-3 0.004 C-14 1.0 K-40 17 Rb-89 0.6 Po-210 3.0 Rn-222 3.0 Ra-226 - Ra-228 __ Tot 51 25

a. Adapted from Reference 8 (Section 11.6) 1 of 1 bO9 190

SWESSAR-P1 TABLE 11.6.1-2 ESTIMATED PER CAPITA WHOLE BODY DOSE EQUIVALENT RATES FROM INHALATION OF RADIOACTIVE FALLOOT IN THE UNITED STATES (a) Radionuclide Whole Body Dose Equivalent Rate (mrem / year) 1963 1965 1969 Sr-90 0.40 0.09 0.01 Zr-95 0.16 - - Mr-54 0.01 - - Sr-89 0.03 - Cs-137 0.02 - - Ce-144 0.55 0.02 0.02 Pu-238 0.01 - - Pu-239 0.19 0.04 0.01 Total 1.4 0.2 0.04

a. Adapted from Reference 8 (Section 11.6) 1 of 1

                                                    //<-    <n*

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SWESSAR-P1 TABLE 11.6.1-3 ESTIMATED WHOLE BODY DOSE EQUIVALENT RATES FROM INGESTION OF RADIOACTIVE FALLOUT IN THE UNITED STATES (a) Whole Body Dose (mrem) Year C-14 Cs-137 Sr-90 1963 0.3 4.3 7.3 1965 0.7 2.3 7.2 1969 0.6 0.4 3.2 1980 0.6 0.4 3.2 1990 0.6 0.4 3.2 2000 0.6 0.4 3.2

a. Adapted from Reference 8 (Section 11.6) i 1 of 1

{ .3 '.) }92

SWESSAR-P1 TABLE 11.6.2-1 EFFLUENT DILUTION FACTOR 5* FOR SINGLE REACTOR SITES Dilution Factor Pathway River Site Lake Site Seacoast Site Swimming 33 8.3 8.3 Boating 33 8.3 8.3 Shoreline activity 333 300 300 Eating fish 33 8.3 e .3 Eating invertebrates - - 8.3 Eating algae - - 200 Drinking water 333 300 -

• Dilution factor = 1/ dilution 1 of 1 e, '

c'

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SWESSAR-P1 TABLE 11.6.4-1 TYPICAL SAMPLE SIZES AND SENSITIVITIES FOR GROSS ACTIVITY ANALYSIS Typical Sample Sample Type Analysis Size Sensitivity TLD dosimeter 1 month 1 mrem Air particulate Gross beta 270 m3 1 x 10_2 uCi/m3 Gross gamma 270 m3 3 x 10-2 cpm /m3 (a) Gamma spectrum 1,080 m3 2 x 10-2 uCi/m3 (b) Precipitation Gross beta 250 ml 200 uCi/m2 (c) Gross gamma 250 ml 2,000 uCi/m2 (c) Gamma spectrum 250 mg 2,000 uCi/m2 (c) Soil, bottom Gross beta 1g 4 pCi/g Gross gann 1,000 g 2 x 10-2 cpm /g (d) Gamma spectrum 1,000 g 5 x 10-2 uCi/g (b) Vegetation, Gross beta 10 g 0.2 uCi/g fish Gross gamma 1,000 g 2x 10-2 cpm /g (d) Gamma spectrum 1,000 g 5x 10-2 uCi/g (b) Well/ river Gross beta 1 liter 1 uCi/l water Gross gamma 3 liters 4 cpm /1 (d) Gamma spectrum 3 liters 20 uCi/l (b)

a. 1 cpm = 1.5 uCi for Cs-137.

b. For Cs-137 assuming no interferences from other nuclides.

c. Sensitivity depends on amount of rainfall.

d. 1 cpm = 4.5 uCi for Cs-137 1 of 1 b b -) lb

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