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ACRS Presentation Chapter 11 - Radioactive Waste Management, PM-0219-64543, Revision 1
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Issue date:	03/11/2019
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"ACRS Presentation Chapter 11 - Radioactive Waste Management," PM-0219-64543, Revision 1 NuScale Power, LLC 1100 NE Circle Blvd., Suite 200 Corvallis, Oregon 97330 Office 541.360-0500 Fax 541.207.3928 www.nuscalepower.com

NuScale Nonproprietary ACRS Presentation Chapter 11 -

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Chapter 11 Radioactive Waste Management

NuScale personnel:

- Carrie Fosaaen - Licensing Project Manager

- Jim Osborn - Licensing Specialist

- Mark Shaver - Radiological Engineering Supervisor

- Jon Bristol - Health Physicist

- Mark Royal - l&C Engineer 2

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Chapter 11 Acronyms

ANSI -American National Standards Institute

CES - Containment evacuation system

COL - Combined license

CRUD - Corrosion and wear activation products

eves - Chemical and volume control system

DSRS - Design specific review standard

GAC - Granulated activated charcoal

GALE - Gaseous and liquid effluents

GRWS - Gaseous radioactive waste system

GWD/MTU - Gigawatt days per metric ton of uranium

HCW - High conductivity waste

LCW- Low conductivity waste

LLW - Low-level waste

LRWS - Liquid radioactive waste system

NPM - NuScale Power Module

ODCM - Offsite Dose Calculation Manual

PAM - Post-accident monitor

PCP - Process Control Program 3

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Chapter 11 Acronyms (continued)

PZR - Pressurizer

R/0 - Reverse osmosis

REMP - Radiological Effluent Monitoring Program

SCALE - Standardized Computer Analysis for Licensing Evaluation

SCFM - Standard cubic feet per minute

SFP - Spent fuel pool

SRWS - Solid radioactive waste system

TUF - Tubular ultrafiltration

UWS - Utility water system 4

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I I

Chapter 11 & 12 RAls

of Supplemental Responses 11.1 2 2 4 11.2 3 0 3 11.3 2 0 2 11.4 1 0 1 11.5 3 0 3 11.6 0 0 0 Total 11 2 13 12.1 0 0 0 12.2 34 9 43 12.3-12.4 61 16 77 12.5 0 0 0 Total 95 25 120 5

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Chapter 11 Radioactive Waste Management

11.1 Source Terms

11.2 Liquid Waste Management Sy~tem

11.3 Gaseous Waste Management System

11.4 Solid Waste Management System

11.5 Process and Effluent Radiological Monitoring and Sampling Systems

11.6 l&C Design Features for Radiation Monitoring 6

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11.1 Source Terms - Methodology

Two source term models are developed for both primary and secondary coolants:

- Design Basis and Normal Effluent ("Realistic") coolant source terms have three components:

Water activation products

>> Calculated from first principles

>> The same concentration for both Normal Effluent and Design Basis

Corrosion activation products (CRUD)

>> Utilized ANSI 18.1-1999, adjusted to NuScale plant parameters

>> The same concentration for both Normal Effluent and Design Basis

>> CRUD strictly used the regulatory guidance provided and past precedence

Fission products

>> Developed using first principles physics in SCALE 6.1 for core inventory 7

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11.1 Source Terms - Methodology

Being unique, and first of a kind, the NuScale design cannot rely solely on empirical source term data

The NuScale methodology will use:

- first principle physics based calculations, where appropriate

- operational experience from recent industry, where applicable

- lessons learned, where available

Water activation products will be estimated from first principles using:

G G RRx = I g=1

<PgCJx,gN = I g=1

<PgLx,g

- RRx: number of reactions of type "x"

- cf:>9 : neutron flux in energy group "g"

- G: maximum energy group

- Clx,g: Microscopic cross section for reaction "x" in energy group "g"

- N: Number density of target atoms

- rx,g = Clx,g N : Macroscopic cross section for reaction x in energy group "g" 8

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11.1 Source Terms - Methodology

Fission products* are conservatively Galculated using first principle physics in SCALE 6.1 Code to 60 GWD/MTU

Release of fission products from fuel to primary coolant based on industry operational experience through use of fuel failure fraction

NuScale evaluation of Corrosion and Wear Activation Products (CRUD) will use current large PWR operating data (ANSI/ANS 18.1-1999).

ANSI/ANS 18.1-1999

- There are no first principle physics models for CRUD generation, buildup, transport, plate-out, or solubility.

To help ensure the source terms are conservative, NuScale has incorporated lessons learned by:

- Using EPRls primary water chemistry and $team generator guidelines to ensure source term is conservative.

- Design of materials used cobalt reduction philosophy 9

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11.1 Source Terms - Failed Fuel Fraction

Fission products

- Normal Effluent ("Realistic") source term

0.0066°/o (-0.6 - 0.7 rods per reactor) failure rate is assumed

Supported by industry experience from large PWRs, which shows much improvement since the 1970s

>> 90-95°/o of US LWRs are zero-defect since 2010

Industry data shows that most failures are due to grid-to-rod fretting and debris

>> NuScale uses natural circulation, which mitigates these mechanisms

>> Technical Report TR-1116-52065, "Effluent Release (GALE Replacement)

Methodology and Results", Rev. 1

- Design Basis source term;

0.066°/o (-6-7 rods per reactor) failure rate is assumed

>> 1Ox normal effluent source term 10 >> Also, supported by Tech Spec 3.4.8 value based on this fuel failur~~!:l.~.~~-~.~-

11.1 Source Terms - Secondary Coolant

Secondary coolant source term

- Primary-to-secondary tube leaks scaled from NUREG-0017

Design Basis = 75 lb/day/NPM = 900 lb/day for 12 units

Realistic= 3.5 lb/day/NPM = 42 lb/ day for 12 units

- Direct neutron activation of secondary was determined to be negligible due to low neutron flux at the steam generators

- Conservatively small secondary coolant mass assumed, which tends to increase the calculated concentration

There are no COL Items associated with Section 11.1.

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GALE Replacement Methodology

Details provided in TR-1116-52065, "Effluent Release (GALE Replacement)

Methodology and Results," Rev. 1

GALE (NUREG-0017) was developed using empirical data from the existing (large) PWR fleet

NuScale design is outside the range of applicability for several parameters (thermal power, coolant mass, other flows)

Certain significant pathways in GALE were not modeled - e.g., Reactor Pool evaporation.

Replacement method explicitly calculates radionuclide transport through NuScale plant systems using applicable guidance from NUREG-0017 12 PM-0219-64543 Revision: 1 Copyright 2019 by NuScale Power, LLC.

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11.2 Liquid Waste Management

Objective: Collect, store, and process radioactive liquid waste

Subsystems:

- Low Conductivity Waste

- High Conductivity Waste

- Chemical Waste

- Detergent Waste

- Clean-in-Place

- Drum Dryer

System Classification:

- Non-safety related

- LRWS Degasifier is RW-lla, LCW collection tank is RW-llb, other components are RW-llc (RG 1.143)

Location:

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11.2 Liquid Waste Management

Design Features:

- Uses R/0 and TUF technologies for performance improvement

- Waste streams segregated to minimize waste generation

- Four waste collection tanks with approximately 60,000 gallons capacity

- Four sample tanks with approximately 60,000 gallons capacity

- Tanks in separate, steel-lined cubicles

- Integrated clean-in-place system

- Liquid discharge can be recycled to the reactor pool, primary coolant, returned to waste collection tank for reprocessing, or discharged offsite

Processing rate 25 gpm

- Can process a full (80%) collection tank in about 8.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />

Effluent

- Meets 10 CFR 20, Appendix B, Table 2

- Meets 10 CFR 50, Appendix I

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11.2 Liquid Waste Management GRWS eves Degasifier PZRVent A/B LCW LCW LCW Collection Processing Skid Sample ----~,-,__-----uws Equipment Drains Tanks (GAC/TUF/RO) Tanks A/B SFP Spent Fuel Pool (Demineralizers) A/B LRWS Sample Tanks LCW Collection Tanks HCW eves Drum Dryer Floor Drains Oil Decon Sump Separators Chemical Drains A/B LRWS Sample Tanks HCW HCW Collection HCW Dewatering Skid Processing Skid SAMPLE Tanks TANKS SRWS Transfer Pumps A/B (GAC/TUF/RO)

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11.2 Liquid Waste Management

Section 11.2 COL Items

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, 11.2-1 :: A COL applicant that references the NuScale Power Plant design cert1f1cat1on will :

i i ensure mobile equipment used and connected to plant systems is in accordance with I

ANSI/ANS-40.37, Regulatory Guide (RG) 1.143, 10 CFR 20.1406, NRC IE Bulletin 80- I

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I I: 10 and 10 CFR 50.34a. I

-* - - -- *. - - -- - -- --- J 11.2-2 A COL applicant that references the NuScale Power Plant design certification will calculate doses to members of the public using the site-specific parameters, compare those liquid effluent doses to the numerical design objectives of 10 CFR 50, Appendix I, and comply with the requirements of 10 CFR 20.1302 and 40 CFR 190.

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11.2-3 :; Not used

11.2-4 A COL applicant that references the NuScale Power Plant design certification will perform a site specific evaluation using the site-specific dilution flow.

j 11.2-5 !'. A COL applicant that references the Nu Scale Power Plant design certification will *

!, perform a cost benefit analysis as required by 10 CFR 50.34a and 10 CFR 50,

! Appendix I, to demonstrate conformance with regulatory requirements. This cost-

. i. benefit analysis is to be performed using the guidance of Regulatory Guide 1.110. i

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11.3 Gaseous Waste Management

Objective: Collect, store, and process radioactive gaseous waste

Subsystems:

- None - single system design

System Classification:

- Non-safety related

- GRWS guard bed and decay beds are RW-lla, other components are RW-llc (RG 1.143)

Location:

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11.3 Gaseous Waste Management

Design Features:

- Uses charcoal decay beds to allow for noble gas decay

- Prevent degradation of decay beds by using moisture separators and guard bed

- Dual monitors for oxygen and hydrogen concentration to prevent flammable mixtures

- Includes nitrogen deluge for fire suppression capabilities High radiation condition will initiate effluent isolation

- Low operating pressure (-2 psig), low flow design

Processing rate -1.5 scfm

- Mostly nitrogen, to keep Hydrogen <1 %

Effluent

- Meets 10 CFR 20, Appendix B, Table 2

- Meets 10 CFR 50, Appendix I

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11.3 Gaseous Waste Management Vapor Condenser Pdt.:li.at1~ A:.:.~111ulv From LRWS To Exhaust From CES Charcoal Guard Bed Charcoal Decay Beds 19 PM-0219-64543 Revision: 1 Copyright 2019 by NuScale Power, LLC.

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11.3 Gaseous Waste Manage ment

Section 11.3 COL Items

11.3-1 : A COL applicant that references the NuScale Power Plant design certification will perform a site specific cost-benefit analysis.

11.3-2 A COL applicant that references the NuScale Power Plant design certification will calculate doses to members of the public using the site-specific parameters, compare those gaseous effluent doses to the numerical design objectives of 10 CFR 50, Appendix I, and comply with the requirements of 10 CFR 20.1302 and 40 CFR 190.

11.3-3 : A COL applicant that references the NuScale Power Plant

design certification will perform an analysis in accordance with

. Branch Technical Position 11-5 using the site-specific parameters.

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11.4 Solid Waste Management

Objective: Collect, store, process, and package radioactive solid waste

Subsystems:

- Dry solids

DAW

HVAC filters

- Wet solids

Spent resins

Cartridge filters

Spent charcoal

System Classification:

- Non-safety related

- SRST is RW-lla, PST is RW-llb, other components are.RW-llc (RG 1.143)

Location:

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11.4 Solid Waste Management

Design Features:

- Two spent resin storage tanks (16,000 gallons each)

- Two phase separator tanks (5,000 gallons each)

- Tanks in separate, steel-lined cubicles

Storage Capacity:

- Class B/C: 4 years

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11.4 Solid Waste Management Sµemt Filter.5 Dewat,e,ring Skitl Sperrt Wet ChaICOal Container Stora,go Spent Resin Storage Tanks Non-C.o mpactable Diy Soli~ Waste

-B Oo mpactable Ory Compactor Packa!ling Solid \"laste Sper.t OryCharcool Hazanfous Waste Potentially Sorting Mixed Wast;,

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11.4 Solid Waste Management

Section 11.4 COL Items

~ . ~ ~ .

CC>L Item# * *

Description *

11-~4~ 1* - - - - - - *---;/ A--CC)L appli~~~t- that references the NuScale Power Plant i

!) design certification *will describe mobile equipment used and i connected to plant systems in accordance with ANSI/ANS

40.37, Regulatory Guide 1.143, 10 CFR 20.1406, NRC IE 11

Bulletin 80-10, and 10 CFR 50.34a.

.. I: . - - . ... - - --- - - - .

11.4-2 A COL applicant that references the NuScale Power Plant design certification will develop a site-specific process control program following the guidance of Nuclear Energy Institute (NEI) 07-1 QA (Reference 11.4-3).

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11.5 Process & Effluent Radiological Monitoring Instrumentation & Sampling

Objective: Measure and record radioactivity levels of selected liquid and gaseous process streams and effluents

Function:

- Monitor liquid and gaseous process streams and effluent paths for radioactivity

- Indicate potential malfunctions of radioactive systems and generate alarms and controls

Classification: Non-Safety

Design Features:

- High radiation condition initiates isolation of the liquid and gaseous radioactive waste effluents

- Main steam line monitors will monitor for Ar-41, since N-16 is decayed away

- There is a single liquid waste discharge line

- The plant vent stack releases most of the gaseous waste

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11.5 Process & Effluent Radiological Monitoring Instrumentation & Sampling

Gaseous Monitors

- Auxiliary boiler system

- Annex Building ventilation system

- Condenser air removal system - effluent (PAM variable)

- Containment evacuation system

- Containment flood and drain separator tank

- Normal control room ventilation system

- Main control room supply air duct

- Gaseous radioactive waste system decay bed and system discharges

- Main steam lines

- Pool surge control system storage tank vent - effluent

- Reactor Building ventilation stack exhaust - effluent (PAM variable)

- Radioactive Waste Building ventilation system

- Turbine gland sealing steam exhaust - effluent

All monitors are non-safety related, but are augmented quality 26 PM-0219-64543 Revision: 1 Copyright 2019 by NuScale Power, LLC.

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11.5 Process & Effluent Radiological Monitoring Instrumentation & Sampling

Liquid Monitors

- Aux boiler system return flow to module heating system

- Balance of plant drain system

- Chemical and volume control system RCS sample line

- Containment evacuation system sample vessel discharge line

- Condensate polisher resin regeneration skid

- Demineralized water system headers

- Liquid radioactive waste discharge line - effluent

- Reactor component cooling water system

- Radioactive waste drain system

- Site cooling water

- Utility water system outfall - effluent

All monitors are non-safety related, but are augmented quality 27 PM-0219-64543 Revision: 1 Copyright 2019 by NuScale Power, LLC.

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11.5 Process & Effluent Radiological Monitoring Instrumentation & Sampling

Section 11.5 COL Items 11.5-1 A COL applicant that references the NuScale Power Plant design certification will describe site specific process and effluent monitoring and sampling system components and address the guidance provided in ANSI N13.1-2011, ANSI N42.18-2004 and Regulatory Guides 1.21, 1.33 and 4.15.

11.5-2 A COL applicant that references the NuScale Power design certification will develop an offsite dose calculation manual (ODCM) that contains a description of the methodology and parameters used for calculation of offsite doses for gaseous and liquid effluents, using the guidance of Nuclear Energy Institute (NEI)07-09A (Reference 11.5-8).

11.5-3 A COL applicant that references the NuScale Power design certification will develop a radiological environmental monitoring program (REMP),

consistent with the guidance in NUREG-1301 and NUREG-0133, that considers local land use census data for the identification of potential radiation pathways radioactive materials present in liquid and gaseous effluents, and direct external radiation from systems, structures, and components.

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11.6 l&C Design Features for Radiation Monitoring

New Section added to the NuScale DSRS

Information is already contained in other Sections

Monitors for gaseous and liquid process and effluent streams are described in Section 11.5

Sampling system information is described in Section 9.3.2

Fixed area and airborne radiation monitors are described in Chapter 12

Post-accident monitoring (PAM) variables from radiation monitors are described in Chapter 7

There are no COL Items associated with Section 11.6 29 PM-0219-64543 Revision: 1 Copyright 2019 by NuScale Power, LLC.

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Portland Office Richland Office 6650 SW Redwood Lane, 1933 Jadwin Ave., Suite 130 Suite 210 Richland, WA 99354 Portland, OR 97224 541. 360. 0500 971.371.1592 Arlington Office Corvallis Office 2300 Clarendon Blvd., Suite 1110 1100 NE Circle Blvd., Suite 200 Arlington, VA 22201 Corvallis, OR 97330 541. 360. 0500 London Office 1st Floor Portland House Rockville Office Bressenden Place 11333 Woodglen Ave., Suite 205 London SW1 E 5BH Rockville, MD 20852 United Kingdom 301. 770.0472 +44 (0) 2079 321700 Charlotte Office 2815 Coliseum Centre Drive, Suite 230 Charlotte, NC 28217 980. 349. 4804 http://www. nuscalepower. com

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11.5 Process & Effluent Radiological Monitoring Instrumentation & Sampling l

Reactor Building Ventilation System Cont;ilnmcnt Flood and Drain System Gaseous Radwaste Systt!m Chemical and LiquldRadwastc Vo!umc Control System System 11 11 Plant Sampling System Site Cooling Circulating Water Water System System Spent Fuel ~f--~------

Poo1Coolin6 L-'----------

Utility Wiltcr 8

Sy5tem

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