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Enclosure 1: ACRS Presentation Chapter 12 - Radiation Protection, PM-0219-64534, Revision 1
	ML19073A053
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Site:	NuScale
Issue date:	03/11/2019
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To:	; Office of New Reactors
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"ACRS Presentation Chapter 12 - Radiation Protection," PM-0219-64534, 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 12 -

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Chapter 12 Radiation Protection Overview

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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Acronyms

ALARA -As Low as Reasonably Achievable

BWR - Boiling Water Reactor

CM - Contamination Minimization

CNV - Containment Vessel

COL - Combined Operating_ License

HOPE - High Density Polyethylene

HVAC - Heating, Ventilation, Air Conditioning

NPM - NuScale Power Module

PWR - Pressurized Water Reactor

REM - Roentgen Equivalent Man (unit of dose)

RG - Regulatory Guide

RPV - Reactor Pressure Vessel 3

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Chapter 12 Radiation Protection

12.1 Ensuring that Occupational Radiation Exposures are ALARA

12.2 Radiation Sources

12.3 Radiation Protection Design Features

12.4 Dose Assessment

12.5 Operational Radiation Protection Program 4

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12.1 Ensuring that Occupational Radiation Exposures areALARA

Policy Considerations

- Design philosophy incorporates radiation reducing features

- Experienced engineers/operators

- Current design guidance from industry (EPRI, URD, RG's, etc.)

- Material selection based on service environment and minimize cobalt

Design Considerations

- Followed guidance of RG 8.8, RG 4.21

- Material selection

- Water chemistry control

- Facility layout

- Equipment design

- HVAC design

Operational Considerations

- ALARA Program - COL Item 5

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12.2 Radiation Sources

Contained Sources Isotopic source terms based on design basis source term from Chapter 11 Radioisotopes include fission products, water activation products and corrosion products Reactor pool is a significant body of tritiated water

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12.2 Radiation Sources

Airborne Sources

- Above reactor pool due to evaporation

- Rooms with occupancy and potential for primary coolant leaks

- Accounts for HVAC operation, designed for potential sources

The core is also a large source of gammas and oeutrons

. Energy spectra source terms generated using SCALE 6.1

Shielding calculations are performed using MCNP6

Accident Source terms are developed per Accident Source Term Methodology Topical Report (TR-0915-17565), currently under evaluation

COL Item

- Identify additional contained sources >100 mCi 7

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12.2 Radiation Sources Typical PWR Design *not representative of NuScale design Pressurizer Steam Reactor Steam Generator Pressure Generator Vessel Reactor Coolant Reactor Coolant Pump Pump 8

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12.2 Radiation Sources Graphic of the NPM Containment Pressurizer Primary Coolant Steam Generators - - - -

Reactor Pressure Vessel Reactor Core - - - - - -

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12.2 Radiation Sources

Because of the close proximity of things to the core, activation was also investigated and accounted for:

- Activation of components are calculated and incorporated

- Activation of the secondary water in the steam generator was determined to be negligible

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12.3 Radiation Protection Design Features

Design features

- Plant layout - use of shield walls , labyrinths, steel lined cubicles , pipe chases , valve galleries

- Equipment arrangement - separated , sloped lines

- System design - clean-in-place , minimize embedded piping , segregated

- Radiation shielding - materials utilized include concrete , HOPE, steel, borated water (reactor pool)

Shielding design based on Industry proven conservative sources providing attenuation margin

- Building ventilation - once through design, flows from areas of lower to higher contamination

- Radiation monitors - strategically located to provide indication of plant radiological conditions

- RG 4.21 features to minimize contamination

- COL Items to develop administrative controls

Refueling, decoupling the module, and core belt-line in-service-inspections remote under water 11 PM-0219-64534 Revision: 1 Copyright 2019 by NuScale Power, LLC.

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12.3 Radiation Protection Design Features

Bioshield

- Horizontal part is reinforced concrete ; vertical part is steel-lined, borated HOPE panels arranged to allow air flow, but prevents radiation streaming

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12.4 Dose Assessment

Dose estimates are intended to be

Refueling realistic and are informed by:

Special Maintenance operating experience

In-Service Inspections staffing and operation s plans

Operations and Su rveill ance shield ing analyses.

Routin e Maint enance

Waste Processing Table 12.4-1: Estimated Total Annual Occupational RadlaUon !Exposures Ad ivity Category Perce nt of Tota l Estimat ed Annual Dose (man-rem )

IReactor operations.& su rv,e illance 8% 2.6 iRoutine maintenance & inspections 7% 2,2 lnservice inspection 15% 5.0 Special maintenance 30% 10 Waste proces.sing 4% 1.4 iRefueling 35% 11.5 Total, 100% 33 iNote: Estimates assume a p lantwith 12 NPMs on a two year refueli ng cycle.

1 13 PM-02 19-64534 Revision : 1 Copyrig ht 20 19 by Nu Scale Power, LLC .

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12.4 Dose Assessment

More proportional expected dose (-80°/o) from work around module

Disconnecting and Reconnecting the module in the operating bay is a new evolution

However, it is similar to those of a conventional PWR prior to RPV head lift in which personnel incur dose. The difference is that the entire module is moved as opposed to just the RPV head .

Maintenance doses are in different proportions

The SG and pressurizer are shielded , but next to each other

ISi Geometry is different

RPV and CNV provide shielding to workers

All Automated and Digital Systems

More proportional expected dose from Calibration and Maintenance as compared to Operations

Unlike current generation facilities, a NuScale plant will not require significant outside resources for refueling/maintenance outages.

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12.4 Dose Assessment

Comparison of NuScale Estimated Dose to Industry Average (NUREG-0713, Vol38,2016)

NuScale*

Operating Dose Yearly Average 42 man-rem 111 man-rem 33 man-rem Dose per Individual Yearly Average 0.08 rem 0.11 rem 0.1 rem Dose per Individual Yearly Average 0.09 rem 0.12 rem 0.1 rem Adjusted for transient workers Dose Based on Power Production 0.05 0.12 0.06 man-rem/MW-yr man-rem/MW-yr man-rem/MW-yr

Assumes all 12 modules operating at full power, 95% capacity factor, two year cycles

Conclusion:

The NuScale estimates are comparable to the current industry, demonstrating ALARA.

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12.5 Operational Radiation Protection Program

COL Item: Operational programs for ensuring occupational doses remain within regulations 16 PM-0219-645 34 Revision : 1 Copyright 2019 by NuScale Power, LLC .

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Chapter 12 COL Items COL Item# Description 12.1-1 A COL applicant that references the NuScale Power Plant design certification will describe the operational program to maintain exposures to ionizing radiation as far below the dose limits as practical, as low as reasonably achievable (ALARA).

12.2-1 A COL applicant that references the NuScale Power Plant design certification will describe additional site-specific contained radiation sources that exceed 100 millicuries (including sources for instrumentation and radiography) not identified in Section 12.2.1.

12.3-1 A COL applicant that references the NuScale Power Plant design certification will develop the administrative controls regarding access to high radiation areas per the guidance of Regulatory Guide 8.38.

12.3-2 A COL applicant that references the NuScale Power Plant design certification will develop the administrative controls regarding access to very high radiation areas per the guidance of Regulatory Guide 8.38.

12.3-3 A COL applicant that references the NuScale Power Plant design certification will specify personnel exposure monitoring hardware, specify contamination identification and removal hardware, and establish administrative controls and procedures to control access into and exiting the radiologically controlled area.

12.3-4 A COL applicant that references the NuScale Power Plant design certification will develop the processes and programs necessary for the implementation of 10 CFR 20.1501 related to conducting radiological surveys, maintaining proper records , calibration of equipment, and personnel dosimetry.

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Chapter 12 COL Items continued COL Item# Description 12.3-5 A COL applicant that references the NuScale Power Plant design certification will describe design criteria for locating additional area radiation monitors.

12.3-6 A COL applicant that references the NuScale Power Plant design certification will develop the processes and programs necessary for the use of portable airborne monitoring instrumentation , including accurately determining the airborne iodine concentration in areas within the facility where plant personnel may be present during an accident.

12.3-7 A COL applicant that references the NuScale Power Plant design certification will develop the processes and programs associated with Objectives 5 and 6, to work in conjunction with design features , necessary to demonstrate compliance with 10 CFR 20.1406, and the guidance of Regulatory Guide 4.21.

12.3-8 A COL applicant that references the NuScale Power Plant design certification will describe the radiation shielding design measures used to compensate for the main steam and main feedwater piping penetrations through the Reactor Building pool wall between the NuScale Power Module bays and the Reactor Building steam galleries near the 100 ft elevation (Shown on Figure 3.6-16 and Figure 3.6-17).

12.4-1 A COL applicant that references the NuScale Power Plant design certification will estimate doses to construction personnel from a co-located existing operating nuclear power plant that is not a NuScale Power Plant.

12.5-1 A COL applicant that references the NuScale Power Plant design certification will describe elements of the operational radiation protection program to ensure that occupational and public radiation exposures are as low as reasonably achievable in accordance with 10 CFR 20.1101 .

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"-I Twitter: @NuScale_Power NUSCALE '

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