Text

Plant Procedures Manual 13.8.1, Revision 41, Emergency Dose Projection System Operations
	ML23163A055
Person / Time
Site:	Columbia, PROJ0736
Issue date:	05/25/2023
From:	; Energy Northwest
To:	; Office of Nuclear Reactor Regulation
References
	13.8.1, Rev 41
	Download: ML23163A055 (1)
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DISTRIBUTION -VOLUME 13-EMERGENCY PREPAREDNESS PROCEDURES Page 3 of 3 Distribution Date: 05125123 Filed By: Prepared by: CS --------------- ----------

Procedure Number Revision Procedure Number Revision Procedure Number Revision 13.8.1 041

TO: ENERGY NORTHWEST EXTERNAL CONTROLLED COPY PROCEDURE HOLDERS The following documents have been revised and are to be inserted into your controlled copy manual and the superseded revisions removed and destroyed. No receipt acknowledgement is required for the listed document(s).

Should you have questions on this distribution please contact Alan Page, Records and Information at (509)377-8595 or atpage@energy northwest.com.

I EXTERNAL DISTRIBUTION I Coov# Location Procedures 26 Region IV - US Nuclear Regulatory Commission All 52 State of Washington, Military Department All 55 Federal Emergency Management Agency (FEMA) All 57 Benton County - Department of Emergency Manaqement All,

87 Document Control Desk NRC All ____,

142 Hanford EOC/SMT All 164 Oregon State Department of Energy All 223 Franklin County Emerqency Management All 224 Washington State Department of Health - Office of Radiation Protection All

!fX 1-/5

& PPM 13.1. 1 and is printed in color, single sided, on 11 " x 17" paper, folded, 3-hole punched, sta pled on top and distributed by Ntf<

Document Control. All ERO Positional-Specific Binder procedures are stapled.

% Co ntact Security - All Security Procedures go to the sec for signature NOTE: Distribution of the PPM 13. 1. 1 wall flow charts is controlled by PPM 13.1. 1 A and distribution is performed by EP. Updated 03/08/2023 lverify_Revision Information Prior To Use: ~=!:Is [ I I

Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/ A

Title:

Emergency Dose Projection System Operations Page: 1 of 34

PLANT PROCEDURES MANUAL PCN#: N/A

Effective Date:

I IIIIII IIIII IIII IIIIII IIII IIIIII IIII IIII 13.8.1 05/25/23

Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/A

Title:

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DESCRIPTION OF CHANGES

Justification (require,d for rriajor; revision),

Revision 041 : Revised date of last refueling outage and revised a Notes for clarification purposes.

Page(s)..

_*Descriptjon (inch.:i~ing surnnu~ry,. reason, initiating document,:if applicable) 14,18,31 & 33 Revised date of last refueling shutdown to 5/5/23 31 Revised Note for guidance on SGT Carbon Filter Inlet moisture 32 Added Note to include guidance on a loss of SM-8 and SM-7 and which eDNA points to use 32 Removed Note regarding performing additional calculations 33 Revised Note for guidance on SGT Carbon Filter Inlet moisture 34 Revised Note to include guidance on a loss of SM-8 and SM-7 and which eDNA points to use

Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/A

Title:

Emergency Dose Projection System Operations Page: 3 of 34 TABLE OF CONTENTS

1.0 PURPOSE 4 2.0 DEFINITIONS.......................................................................................................................... 4 3.0 RESPONSIBILITIES................................................................................................................ 6 4.0 PROCEDURE.......................................................................................................................... 6

5.0 REFERENCES

...................................................................................................................... 11 6.0 DOCUMENTATION............................................................................................................... 11 7.0 ATTACHMENTS.................................................................................................................... 11 7.1 URI User Guidance................................................................................................................ 12 7.2 Air Sampling Worksheet Calculation...................................................................................... 25 7.3 Alternate Method for Obtaining Met Data............................................................................... 26 7.4 Computer Points Used in the eDNA View Radiological Status Screen................................... 28 7.5 Alternate Method for PRM Stack Monitor............................................................................... 29 7.6 Alternate Method for TEA-RIS-13 or WEA-RIS-14................................................................. 30 7.7 Dose assessment using Rapid URI........................................................................................ 31 7.8 Dose assessment using Detailed URI.................................................................................... 33

Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041

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Emergency Dose Projection System Operations Page: 4 of 34 1.0 PURPOSE This procedure provides instructions for the use of the computerized dose projection system Unified RASCAL Interface (URI) to predict offsite dose rates, integrated doses and radioactive material deposition for locations within the 10-mile Plume Emergency Planning Zone (EPZ) and the 50-mile Ingestion EPZ. Actual manipulation of system display terminals is described in document MAN-URl-01 referred to as the URI User's Manual. {R-5.1.1}

The dose projection system is used for estimating the whole body (TEDE) and thyroid (COE) doses of onsite and offsite persons in the event of potential or actual accidental release of radioactivity to the environment. The dose projection system used at Columbia consists of a computer software program that relies on precalculated, real time, site-specific relationships between effluent monitor readings (or sample results) and on-site and offsite dose rates.

The dose projection system is available in the Control Room, Technical Support Center (TSC),

Emergency Operations Center (EOF), and Alternate EOF. Having the dose projection system software loaded on multiple, stand-alone computers located in the various emergency centers maximizes dose projection capability. Field Team data may be used to calculate dose projections or validate previous projections.

The software program supports a rapid version of dose projection using limited pathways for a rapid evaluation of the release out to 10 miles. The software also supports a detailed dose projection based on more detailed pathways with dose projections from the site boundary out to 10 or 50 miles.

State and county organizations will have access to this system in the EOF or by transmission

of output information to their emergency centers.

2.0 DEFINITIONS 2.1 COE Thyroid - Committed Dose Equivalent to the thyroid.

2.2 Delta T (~ T) - The temperature difference between two sensors located at different elevations on a meteorological tower. ("Highest elevation" - "Lowest elevation" = ~ T) 2.3 Effective Dose Equivalent (EDE) - the external gamma dose that is normally monitored by emergency workers through their self-reading dosimeters 2.4 EDE to TEDE Ratio (EDE/TEDE) - Ratios computed by URI that are used for determining the Emergency Worker Dose Adjustment Factor. The EDE is the external gamma dose that is normally monitored by emergency workers through their self-reading dosimeters (electronic dosimeters or pocket ion chambers); and TEDE is the total dose from both EDE and the internal dose from inhaled iodines and particulates. **

2.5 Elevated Release - An effluent release point model that assumes that the release point is from a discreet true elevated (tall) stack.

2.6 Emergency Worker Dose Adjustment Factor (EWDAF) - An adjustment factor determined from the EDE/TEDE Ratio that is used by offsite emergency workers to monitor their TEDE whole body dose based on their EDE doses as measured on their self-reading dosimeters.

The adjustment factor is the inverse of the EDE/TEDE Ratio reported by URI, Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: NIA

Title:

Emergency Dose Projection System Operations Page: 5 of 34

2.7 Radioactive Release - A radioactive release is in progress when:

Effluent monitors indicate an increase in radiation levels from normal readings for plant operating conditions, OR Field teams detect environmental radiation 10 times Greater Than (GT) normal background.

AND The increased levels are attributable to the emergency event.

2.8 Radioactive Release Termination - A radioactive release is terminated when the following criteria have been met:

1. The source of the release has been isolated.

2. The effluent monitors are trending downward (if available).

3.. Environmental Field Team surveys indicate a decrease in radiation levels or airborne radioactivity.

2.9 RASCAL-NRC supported and distributed computer software for determining source term, atmospheric dispersion, and dose consequences.

2.10 Reactor Core Accident - This indicates core damage Greater Than or Equal To {GE) 0.1 %

as identified by process rad monitors (PRM, TEA and/or WEA) listed in PPM 13.1.1 Table 3 Effluent Monitor reading is Greater Than or Equal to Alert value.

2.11 Site Boundary (SB)- Closest distance between owner-controlled area boundary and core, set at 1.2 miles.

2.12 Source Term - The quantity and radionuclide makeup of the material in the release. The source term used in URI is based on NUREG-1228.

2.13 Stability Class - Values from A to G representing ranges of Delta T (AT) which in turn represent atmospheric mixing estimations. The NRC definitions of these ranges are used to define the stability classes used in URI. ("A" is extremely unstable, "G" is extremely stable).

2.14 Stack Door Monitor (SDM) - A portable radiation survey meter (e.g., Teletector) or radiation monitoring instrument (e.g., AMP-100) used for monitoring radiation levels at the exterior and center of the Elevated Release Stack Access Door {R-DOOR-R515). This provides an alternate means for monitoring Reactor Building post-accident effluent releases when the installed Process Radiation Monitor (PRM) Stack Monitor is inoperable or unavailable.

SDM readings (in mR/hr) are available from HP or, when set up for remote monitoring, through eDNA Real-Time Client or eDNA Trend from eDNA Point IDs EP99M (mid-range SDM) and EP99H (high-range SDM) in the ENW.WRM Service.

2.15 TEDE-Total Effective Dose Equivalent (TEDE)-The sum of the Deep Dose Equivalent (DDE) and the Committed Effective Dose Equivalent (CEDE).

2.16 Unified RASCAL Interface (URI) - Computer software which replaces the NRC issued RASCAL user interface for user input of dose assessment parameters and interpretation of results that interfaces to the RASCAL meteorological and dose processor modules.

Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041

Title:

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3.0 RESPONSIBILITIES

3.1 STA/ Incident Advisor Responsible for performing dose assessments until relieved by an on-call ERO Member.

3.2 Dose Projection HP Once the EOF takes control of offsite radiological assessment the Dose Projection HP is responsible for performing dose assessments until the event is terminated.

3.3 Chemistry Effluent Manager Once the TSC is manned, the Chemistry Effluent Manager is responsible for performing dose assessments if required for the TSC.

4.0 PROCEDURE 4.1 General Instructions 4.1.1 URI is not to be used for Unusual Event (UE) classification.

4.1.2 Detailed guidance on using URI is provided in Attachment 7.1, URI User Guidance.

4.1.3 In the event of a loss of SM-8,

CGS Meteorological System will be OOS, Refer to Attachment 7.3, Alternate Method for Obtaining Met Data.

Reactor Building Effluent Rad Monitor {PRM) will be Out of Service (OOS).

Refer to Attachment 7.5, Alternate Method for PRM Stack Monitor Use the readings from the SDM to input directly into URI.

4.1.4 In the event of a loss of SM-7,

Turbine (TEA) and Radwaste fl/lJEA) Buildings Effluent Rad Monitors will be OOS.

Refer to Attachment 7.6, Alternate Method for TEA-RIS-13 or WEA-RIS-14, readings must be converted for input to URI.

4.1.5 In the event of a loss of eDNA, (POIS, Process Computer)

Meteorological data will not be available on Rad Status or Containment Status, therefore; contact the Main Control Room to get Meteorological Data from Control Room Board "L".

Rad Monitor data and flows must be provided from the Control Room or local readings.

4.1.6 Use URI to estimate doses within 15 minutes of a start of a release or as information becomes available. Also use URI to estimate offsite dose during rapidly changing meteorological conditions or release conditions as appropriate.

Refer to Attachment 7. 7, Dose Assessment Using Rapid URI or Attachment 7.8, Dose Assessment Using Detailed URI.

Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/A

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4.1.7 IF Meteorological Data (Met Data) Channel "A" instrument data is not available,

THEN the corresponding Met Channel "B" data should be used.

4.1.8 If CGS Met Data is not available, THEN refer to Attachment 7.3, Alternate Method for Obtaining Met Data.

4.1.9 If intentionally venting the primary containment through the Hardened Vent Pathway, perform dose projection assessment using the Hard Vent Pathway and Containment Radiation Monitoring Data, RCS Leakage Data or Field Team Data as applicable.

4.1.10 Venting is a puff release and thus release duration for intentional venting is one hour.

4.1.11 In the EOF/TSC, if any data is suspect, request the EOF Radiation Detection System Engineer or the EOF/TSC Information Coordinator to verify the data.

4.1.12 In the event of unmonitored release paths or if instrumentation (including alternate instrumentation) is out of service or off-scale, Field Team results are used to calculate dose projections. Use one of the following processes to assess Field Team results:

Exp. Rate (mR/hr) range 0.1 to 99999.9 data must be based on observations in the centerline of the plume

Air sample Excel spreadsheet calculator found on the Dose Projectionist Computer Desktop.

Enter the cartridge and background readings and press the tab key to perform the calculation

Attachment 7.2, Air Sampling Worksheet Calculation.

Enter sample and background count rate and sample volume into calculations to determine micro curies/cc (µCi/cc)

Air Sample Calculator in URI Detailed assessment (preferred)

Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/A

Title:

Emergency Dose Projection System Operations Page: 8 of 34 4.1.13 Access the Plant Data Information System (POIS) through the electronic Distributed Network Architecture (eDNA) software to obtain and monitor key radiation monitor, meteorological, and Plant effluent data.

a. At a LAN supported computer:

1) Double click on the "eDNA View" icon on the Desktop, if available.

If no "eDNA View" icon is available, Then open eDNA through the network folder and select "eDNA", "eDNA View".

NOTE: "Containment Status" may also be used to retrieve URI data

2) Select "CGS", then "POIS", and "Rad Status" to obtain the "Radiological Status" screen.

A screen print of the "Radiological Status" screen may be used to capture the current values of radiation monitor, meteorological, and effluent data for tracking changes (setup printer to Landscape mode, and use the "Print Direct" function rather than "Print" from the "File" drop-down menu on the eDNA View "Radiological Status" screen or if the file menu is not available, right click the eDNA screen and select "Print Direct").

Access other eDNA View screens of POIS data by selecting the appropriate "eDNA View (*.rtv)" in the Application Service Utility window, as desired.

Graphical trends of the plant parameters displayed on the eDNA View screens can be displayed by clicking in the appropriate plant parameter display box. The time span of the graphical trend may be modified by selecting "Modify Graph Parameters" in the "Graph" pull-down menu, selecting the "Graph" tab, and entering the desired date and time range (click to check the "Y-Axis Auto Scale" box for a clearer graph).

3) Area Radiation Monitor (ARM), effluent monitor (TEA, WEA, PRM and SOM, and meteorological data are also available through eDNA applications (e.g.,

eDNA Real-Time Client or eDNA Trend) from the Start menu/All Programs/eDNA folder and selecting the appropriate ENW Service (e.g.,

ENW.CGS, ENW.WRM, etc.).

4.1.14 Distribution of Maps and Data

a. Maps selected for distribution should always be accompanied by the data.

This is very important because the plume projected on the map is not closed and without the data sheet, the plume may be misinterpreted

b. Any dose projection maps, or data printouts selected for distribution to offsite agencies should have the Emergency Director approval prior to release.

Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/A

Title:

Emergency Dose Projection System Operations Page: 9 of 34 4.1.15 Provide the Emergency Worker Dose Adjustment Factor (EWDAF) to the REM and Field Team Coordinator for their use in establishing field team exposure limits.

a. On page three of the detailed Dose Assessment Report, invert the EDE/TEDE ratios to acquire the EWDAF.

USE the EDE/TEDE Ratio with Iodine.

OR IF respiratory protection or a thyroid blocking agent (i.e., potassium iodide) is being used, THEN use the EDE/TEDE Ratio without Iodine.

Example:

EDE/TEDE ratio with iodine at 2 miles is 0.90 the EWDAF would be 1.1.

(1 divided by 0.9)

b. IF the EWDAF is 5 or'greater, THEN use EWDAF of 5.

4.1.16 The Washington Senior State Official approves release data for distribution during the ingestion phase.

4.2 Dose Assessment Using Rapid URI See Attachment 7.7, Dose Assessment Using Rapid URI.

4.3 Dose Assessment Using Detailed URI See Attachment 7.8, Dose Assessment Using Detailed URI.

Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/A

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Emergency Dose Projection System Operations Page: 10 of 34 4.4 Summing dose assessments from multiple release points.

In order to assess the consequences of multiple releases occurring at the same time, the Sum Assessment allows the user to select result output files from previously performed assessments and combine them into a single summed assessment result. No new dispersion or dose calculations within RASCAL are performed with this process, only the previously saved results from the selected assessments are added together spatially per the layout of the model elements in the two RASCAL models.

After opening but prior to performing a URI Dose Assessment (either Rapid or Detailed),

1. Select the Sum Results for Simultaneous Releases.~: (sigma icon) in the upper left of the screen, this will bring up the Assessment Summations Page. Minimize(-) this screen for later use.

2. Perform the Dose Assessment and then select the Transfer Results to the Summation Page* +-(plus icon) in the upper left of the screen, this will add the latest assessment to the summations page. Minimize(-) this screen for later use.

3. Perform a new dose assessment from a different path and select the Transfer Results to the Summation Page.+ (plus icon) in the upper left of the screen, this will add the latest assessment to the summations page.

4. Select the Sum Results for Simultaneous Releases :~:(sigma icon) for the Assessment Summations of the performed assessments perform ea* earlier. from multiple release points.

5. An Assessment Summations report will be produced for the combined dose assessments.

Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/ A

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5.0 REFERENCES

5.1 Documents 5.1.1 EP-01, Emergency Plan 5.1.2 NUREG-0654, FEMA REP-1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 5.1.3 NUREG 1228, Source Term Estimation During Incident Response to Severe Nuclear Power Plant Accidents 5.1.4 RSCS TSD-13-035 (CVI 1057-00, 131) TEA and WEA replacement 5.1.5 NE-02-09-12, CGS Emergency Action Levels Technical Bases 5.1.6 NE-02-10-05, URI-RASCAL DOSE PROJECTION SOFTWARE 5.1.7 FW-SOFT-COTS-RASCAL 5.1.8 FW-SOFT-COTS-URI 5.1.9 Radiation Protection Calculation 15-04, Calculation of Iodine Air Sampling Cartridge Efficiencies 5.2 Procedures 5.2.1 PPM 13.1.1A, Classifying the Emergency - Technical Bases 5.2.2 PPM 13.2.1, Emergency Exposure Levels/Protective Action Guides 5.2.3 PPM 13.2.2, Determining Protective Action Recommendations

6.0 DOCUMENTATION All logs, forms and records completed as the result of implementing this procedure during an actual declared event shall be retained as permanent plant records.

Transmit documents to the Permanent Plant File under DIC 2304.2.

A sub-set of documents generated during drills shall be maintained in the Emergency Preparedness Department files, as necessary, to support completion of drill/exercise commitments.

7.0 ATTACHMENTS 7.1 URI User Guidance 7.2 Air Sampling Worksheet Calculation 7.3 Alternate Method for Obtaining Met Data 7.4 Computer Points Used in the eDNA View Radiological Status Screen 7.5 Alternate Method for PRM Stack Monitor 7.6 Alternate Method for TEA-RIS-13 or WEA-RIS-14 7.7 Dose Assessment Using Rapid URI 7.8 Dose Assessment Using Detailed URI Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/A

Title:

Emergency Dose Projection System Operations Page: 12 of 34

URI User Guidance

1.0 OVERVIEW 1.1 For ease of explanation, the different sections of the URI screen will be described as "groupings" with the name in the upper left of the grouping as the title of that grouping.

1.2 The red octagons with the exclamation point inside are warnings that an option needs to be selected or information filled in before the calculation can be performed. A message also appears in the lower left-hand corner of the page stating that all errors must be resolved to complete the calculation. If the cursor is placed over the octagon, a message is provided that will describe the range of the input variable.

1.3 Holding the cursor over a box will often result in the program providing information about the contents of the box.

1.4 Options used in the Source Term Grouping will determine which options will be available in succeeding grouping.

1.5 Options used in the Release Point Pathway Grouping will determine which inputs to the Process Reduction Factor will become available.

1.6 Options used in the Release Point Pathway Grouping will determine which options will be available in the Assessment Methodologies Grouping.

1.7 CGS has committed to performing ground release assessments; therefore, only ten-meter

Meteorological Data (Met Data) conditions should be selected.

1.8 FFTF Delta -Temp (~ T) is a direct input for stability class.

1.9 Meteorological conditions from other than CGS Met Data or FFTF Met Data should be entered into the CGS 33' Tower input.

1.10 If the wind direction value is greater than 360°, then subtract 360 from value before entering it into URI program.

1.11 Stack Door Monitor (SOM) is a direct input option.

Refer to Attachment 7.5 Alternate Method for PRM Stack Monitor.

1.12 Turbine Building Effluent (TEA) and Radwaste Building Effluent (WEA) Alternate data must be converted for URI input..

Refer to Attachment 7.6 Alternate Method for TEA-RIS-13 or WEA-RIS-14.

1.13 During the ingestion phase, determine manual contour lines on the 10-50 mile map by selecting grid and balloon options to determine the projected 500 µR (relocation boundary),

20 µR and 0.4 µR (food control boundary).

Attachment 7.1, URI User Guidance Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041

Title:

Emergency Dose Projection System Operations Page: 13 of 34 Minor Rev: N/A 2.0 Rapid URI

NOTE: Use of Rapid URI requires that the release pathway matches one of the limited options in the Rapid URI software.

Rapid URI is not usable for Rad Waste Building or Unmonitored release.

Rapid URI is not usable if release path is through SGT _and SGT is "Not Working".

From ARP 4.811.K2 4-3 Continued operation of the SGT system with a high relative humidity (as indicated on SGT-Ml-4A / 48) can result in a decrease in charcoal filter efficiency due to increased charcoal moisture content, this decrease in efficiency occurs at 70% relative humidity. Decreased filter efficiency is required to be accounted for in the Off-Site Dose Calculations. This is accomplished by selecting "Not Working" for SGT.

2.1 Activate Rapid URI by.

If not a real event, then SELECT "This is a drill".

SELECT the "Rapid" option (Lightning Bolt icon) on the URI main screen.

The Rapid Assessment page is now available for data input.

2.1.1 Source Term Grouping (This grouping provides input on what type of damage to the fuel has occurred)

a. SELECT Qn! of the following

IF the release is from the Reactor and Fuel Clad Damage is suspected, (PPM 13.1.1 Table 3 Effluent Monitor reading Greater Than or Equal to the Alert value, or Field Team data shows a release in progress),

THEN SELECT "Yes" for Fuel Clad Damage. This causes the assessment to include isotopic mix and inventory for fuel clad damage.

IF the release is from the Reactor and Fuel Clad Damage is NOT suspected, (No PPM 13.1.1 Table 3 Effluent Monitor reading is Greater Than or Equal to Alert value or Field Team data shows a release is not in progress),

THEN SELECT "No" for Fuel Clad Damage. This causes selection of normal coolant concentrations as the basis of the source term. This also activates the question, "Have the Conditions for Coolant Spiking been met?"

Then Select "Yes" or "No" if Reactor Building process radiation monitors spiked following a plant transient.

IF the release is from the Spent Fuel Pool, THEN SELECT "Damaged Spent Fuel Assembly" Attachment 7.1, URI User Guidance Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041

Title:

Emergency Dose Projection System Operations Page: 14 of 34 Minor Rev: N/A NOTE: For A TWS Conditions:

IF reactor power is GT 1%: leave the Time Since Reactor Shutdown value set to zero unless the Main Control Room (MCR) states the reactor is shutdown.

IF reactor power is LE 1 %: Contact the MCR, use the amount of time from when the MCR declares reactor shutdown.

b. IF the release is from the Reactor, and reactor power is Less than 1 % power, THEN Check the "Reactor Shutdown" box and enter date and time of shutdown using the pull-down calendar. (Overwrite the indicated time as necessary.)

IF the release is from the "Damaged Spent Fuel Assembly". This will change the Reactor Shutdown date/time box to Spent Fuel "Last Irradiated" and allow input of when the spent fuel was last irradiated. THEN this should be 5/5/2023.

NOTE: Meteorological conditions from other than CGS Met Data or FFTF Met Data should be entered into the CGS 33' Tower input.

Data must be entered into the CGS or FFTF Met Data row for URI to run.

2.1.2 Meteorological Data Grouping (This grouping allows input of meteorological data pertinent to the release)

a. Select.Q!!.! of the four choices of "site" met tower input to be used.

(The two FFTF towers are considered "site" met towers.)

Meteorological parameters from the CGS met tower are normally available on the Radiological Status or Containment Status screen.

If the CGS Met tower (default) is not selected, the program will provide a notification of this.

b. Input Wind Speed and Wind Direction (W/D) data.

(Double clicking on the Wind Direction box will bring up a depiction of a compass that may assist in selecting wind direction.)

Wind Speed range is GEO to LE 60 mph.

Wind Direction range is GE 0 and LT 360.

c. Input delta T (Ll T) or select appropriate Stability Class from the pull-down menu.

(Double clicking on the "Stab" Class box will open a Stability Description.)

Attachment 7.3 has additional information in determining Stability Class.

AT range is GT -10 to LE 10

Stability is "A"- "G"

d. Use the pull-down menu to select the appropriate level of precipitation.

Attachment 7.1, URI User Guidance Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041

Title:

Emergency Dose Projection System Operations Page: 15 of 34 Minor Rev: N/A 2.1.3 Release Duration Grouping (This grouping allows input on how long the release has been in progress)

Provide "Release Duration" in hours and minutes. This function defaults to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

If End of Release is not known, a default value of the time of the release is rounded up to the next hour plus two hours should be used.

Release duration must be input in 15-minute increments.

Range is 15 minutes to LE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

EXAMPLE: Release has been in progress for 25 minutes.

Round 25 minutes up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and add 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to give a release duration of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

If the release has been in progress for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 10 minutes, round up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and add 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for a release duration of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Selections made in the Source Term Grouping will determine which release paths are available.

2.1.4 Release Point Pathway Grouping (This grouping allows input on where the release originates from and its path for leaving the plant).

Select the appropriate release path from the available list.

Choose the pathway that best matches the conditions of the release in progress.

A description of the pathway will appear as the cursor is held over the individual pathways.

A list of available monitors will also be displayed.

The release path selected will determine which effluent monitors will be available.

The release path selected will also determine the Process Reduction Factor (PRF) applied to the calculation of the offsite dose.

If SGT is running, the Rx Building hold up time changes to "2-24" hours.

The pathway and assumptions for the input to the PRF are displayed in the lower right portion of the screen.

Attachment 7.1, URI User Guidance Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/A

Title:

Emergency Dose Projection System Operations Page: 16 of 34

2.1.5 Release Point Information Grouping

(This grouping allows input on the condition of the monitors at the release point)

a. If effluent monitors are available, Select "Yes".

Depending on the Pathway selected, Turbine or Reactor Building monitors will be made available for selection in the Monitor Grouping.

1) Select the monitor to be used

2) Provide the appropriate reading in the Reading box, ensuring the units are correct

3) Verify the "Release Point Flow Rate" is correct or revise default value to accurately reflect plant conditions.

If SGT is running and Reactor Building Exhaust Fans are shutdown; use the total of the running SGT train flowrates.

If (REA or TEA) building exhaust flow indication is lost, the Control Room should be contacted to determine flow rate via ODCM 6.1.2.D method.

b. If effluent monitors are not available, Select "No".

This action will bring up several options for input.

1) If RCS leakage is suspected, select "Estimated RCS Leak Rate", fill in a known leak rate or select the "I Don't Know" option.

2) If "Containment Leakage" is selected (only available if a Pathway from the Drywall has been selected), select either containment high rad monitor and provide an appropriate reading in the R/hr box or select "No HRA Available or

Applicable".

c. If "Damaged Spent Fuel Assembly" is selected in the Source Term Grouping and no effluent monitors are available, then.

Select "Unmonitored Damaged Spent Fuel Assembly".

2.1.6 Select the "Process Assessment" button to run a Rapid Assessment based on the supplied input data.

2.1. 7 To preview the "Dose Assessment Report",

Select "Print Preview Option" (magnifying glass icon) directly above the source term grouping 2.1.8 To print the Dose Assessment Report, either

a. Select the "Printer" icon to print or

b. Select "Close" to return to the main screen.

2.1.9 If printing is desired from the main screen, Select "Print to Default Printer" (printer icon)

Attachment 7.1, URI User Guidance Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041

Title:

Emergency Dose Projection System Operations Page: 17 of 34 Minor Rev: N/A

3.0 Detailed URI

3.1 Activate Detailed URI by.

If not a real event, then SELECT This is a drill".

SELECT the "Detailed" option (Cloud icon) on the URI main screen.

The Detailed Assessment page is now available for data input.

3.1.1 Source Term Grouping (this grouping provides input on what type of damage to fuel has occurred}, In the Source Term box.

SELECT ~ of the following

Select "Normal Coolant", if there is no core damage (No PPM 13.1.1 Table 3 Effluent Monitor reading is Greater Than or Equal to Alert value or Field T earn data shows a release is not in progress).

Select "Spiking Factor if Reactor Building process radiation monitors spike following a plant transient. The numerical Spiking Factor defaults to "30".

Select "Reactor Core Accident", if there is actual or suspected damage to fuel assemblies {PPM 13.1.1 Table 3 Effluent Monitor reading Greater Than or Equal to Alert value). Technical support or core damage procedures should be used to estimate the extent of core damage.

o The "Clad" damage option is selected if the core conditions have caused the

fuel pin cladding to fail but the core temperature has not become sufficiently high to cause melting of the ceramic fuel matrix.

o The "Melt" option is selected if SAGs are entered and core has been uncovered for greater 30 minutes.

Select "Spent Fuel Accident" option if the incident involves damage to spent fuel in a depressurized condition.

Checking the "Unmonitored Spent Fuel Accident with No other method applicable" box is only done when there is no other option for determining spent fuel source term due to loss of building integrity, loss of monitors, or other major failure making source term assessment unavailable.

Attachment 7.1, URI User Guidance Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/A

Title:

Emergency Dose Projection System Operations Page: 18 of 34 NOTE: Meteorological conditions from other than CGS Met Data or FFTF Met Data should be entered into the CGS 33' Tower input.

Data must be entered into the CGS or FFTF Met Data row for URI to run.

Met Data from the other listed locations can also be entered into their respective row when used when performing a URI Dose Assessment.

3.1.2 Meteorological Data Grouping (this grouping allows input of meteorological data pertinent to the release) Select.Q.!!! of the four choices of "site" met tower input to be used.

(The two FFTF towers are considered "site" met towers.)

Meteorological parameters from the CGS met tower are normally available on the Radiological Status or Containment Status screen.

If the CGS Met tower (default) is not selected, the program will provide a notification of this.

a. Input Wind Speed and Wind Direction 0Af/D) data.

(Double clicking on the Wind Direction box will bring up a depiction of a compass that may assist in selecting wind direction.)

Wind Speed range is GE O to LE 60 mph.

Wind Direction range is GE O and LT 360.

b. Input delta T (AT) or select appropriate Stability Class from the pull-down menu.

(Double clicking on the "Stab" Class box will open a Stability Description.)

Attachment 7.3 has additional information in determining Stability Class.

AT range is GT "10 to LE 10

Stability is "A"- "G"

c. Use the pull-down menu to select the appropriate level of precipitation.

3.1.3 Reactor Status Grouping (this grouping allows input of reactor status or time since the last time the spent fuel was irradiated)

NOTE: For A TWS Conditions:

IF reactor power is GT 1%: leave the Time Since Reactor Shutdown value set to zero unless the Main Control Room (MCR) states the reactor is shutdown.

IF reactor power is LE 1%: Contact the MCR, use the amount of time from when the MCR declares reactor shutdown.

If "Normal Coolant" or "Reactor Core Accident" is selected in the Source Term Grouping, "Reactor Status" will be shown next to the check box. If the Reactor is shutdown, click in this box. Change the date/time box to reflect actual shutdown if needed. The "TAS" box will update automatically. Time after shutdown can be entered directly into the "TAS" box by double clicking in the box.

If "Spent Fuel Accident" is selected in the Source Term Grouping, for any spent fuel accidents in the Spent Fuel Pool, this will change the Reactor Shutdown date/time box to Spent Fuel "Last Irradiated" and allow input of when the spent fuel was last irradiated. This should be 5/5/2023.

Attachment 7.1, URI User Guidance Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041

Title:

Emergency Dose Projection System Operations Page: 19 of 34 Minor Rev: N/A 3.1.4 Release Duration Grouping (this grouping allows input of the duration of the release)

Provide "Release Duration" in hours and minutes. This function defaults to 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

If End of Release is not known, a default value of the time of the release is rounded up to the next hour plus two hours should be used.

Release duration must be input in 15-minute increments.

Range is 15 minutes to LE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

EXAMPLE: Release has been in progress for 25 minutes.

Round 25 minutes up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and add 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to give a release duration of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

If the release has been in progress for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 10 minutes, round up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and add 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for a release duration of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Attachment 7.1, URI User Guidance Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041

Title:

Emergency Dose Projection System Operations Page: 20 of 34 Minor Rev: N/A 3.1.5 Selected Pathway Options Grouping (allows input as to the release flow path and inputs to the Process Reduction Factor)

NOTE: Building Hold"Up Time (HUT) causes the Process Reduction Factor to account for the plate out of iodines and particulates on building surfaces due to physical and chemical surface action. HUT is dependent upon the building or location. It indicates how long the release remains within the specific building for both decay and for residual radiation leaving the building once the leak is isolated. For the containment, HUT is dependent upon leak rate. Inputs based on the status of the OW, WW or Reactor Bldg have an impact on the dose projection outcome. The HUT is selectable in the URI program based on the status of the building or location. Careful consideration should be taken before changing HUT for OW, WW, Turbine Bldg and Rad Waste Bldg.

a. To view the list of available pathways, click on the small yellow box to the right of the "Pathway" box. This action will take you to the Pathways screen.

Available pathway options will depend on selections made in the Source Term Grouping. Choose the pathway that matches the conditions of the release in progress. A description of the pathway will appear as the cursor is held over the "Path" box to the right of the pathway to be selected. A list of available assessment methodologies will also be displayed. The pathway chosen will determine which

"Process Reduction Factors" {PRF) will be used in the dose calculation. HUT can be changed from the default values. Other options include use of Drywell sprays, condition of the Suppression Pool, and whether SGBT is working (operable with no high moisture alarms}.

IF SGT is running, and the release is through SGT, THEN Rx Building hold up time needs to be changed to "2"24hrs".

b. When pathway has been selected and PRF options have been made, click on the "Accept button. This action will return you to the main Detailed Assessment screen. The pathway chosen will be displayed in the "Pathway box. The PRF will be displayed under the "Pathway" box along with inputs to the PRF.

Attachment 7.1, URI User Guidance Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/A

Title:

Emergency Dose Projection System Operations Page: 21 of 34 3.1.6 Assessment Methodologies Grouping (allows input to the dose assessment calculation depending on available monitors, leakage rates, samples taken, or field team results, depending on available information)

a. Monitored TAB (available when chosen Pathway is monitored by installed or temporary plant radiation monitor)

1) Release Point: The release point is based on the Selected Pathway chosen.

No input required

2) Monitor: Select the radiation monitor you wish to use or select the building as appropriate.

3) Release Point Flow Rate: Input real time data from plant computer system/instrument readings.

IF SGT is running and Reactor Building Exhaust Fans are shutdown.

THEN use the total of the running SGT train flowrates.

Range for Reactor Building is GE 0 to LE 2E6 CFM, Range for Turbine Building is GE 0 to LE 5E6 CFM.

Radwaste Building is GE 0 to LE 2E6 CFM

IF building (RB, RW, TB) exhaust flow indication is lost, THEN the Control Room should be contacted to determine flow rate via ODCM

6.1.2.D method.

4) Monitor Reading: Input real time data from plant computer system or instrument readings. Ensure units match those in the program.

Reactor Bldg Exhaust (PRM) Stack Monitor Range is GE 1 E-7 to LE 1 E+6 µCi/cc,

Turbine Bldg Exhaust (TEA) Monitor Range is GE 0 to LE 1 E3 µCi/cc,

Rad Waste Bldg Exhaust (WEA) Monitor Range is GE 0 to LE 1 E3 µCi/cc

b. Containment Leakage TAB, (available when chosen Pathway originates inside containment)

1) Method

Normal Coolant /w Spiking Factor

% Fuel Damage range is GE 0 to LE 100%

Containment Radiation Monitors range is GT 0 to LE 1 E7 R/hr

2) Release Mode

Leakage range is GT Oto LE 100%

Failure to Isolate

Catastrophic Failure

Calculated Containment Leak Rate range is GT 0 cfm

Venting using Pressure Change (PSIG)

Attachment 7.1, URI User Guidance Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041

Title:

Emergency Dose Projection System Operations Page: 22 of 34 Minor Rev: N/A

c. RCS Leakage TAB

(available for all chosen Pathways except Spent Fuel Pool) is used when the release pathway does not include normal plant effluent monitors ( or they are unavailable).

1) Method

Normal Coolant /w Spiking Factor

% Fuel Damage range is GE 1 to LE 100%, used when the Core Damage option is selected in the Source Term Grouping. The amount of core damage should be entered as obtained from TSC Core Thermal Engineer or STA.

2) Release Mode

Unknown Release Mode

Calculated RCS Leak Rate range is GE 1 to LT 1 E6 gpm

d. Release Pt. Sample TAB (available for all chosen Pathways except those directly releasing to the environment) is used when there is a valid sample collected from the effluent release point.

1) Release Point Data, no discernable range in SCFM, enter actual release point flow rate from the time of sample.

IF SGT is running and Reactor Building Exhaust Fans are shutdown,

THEN use the total of the running SGT train flowrates.

IF building (RB, RW, TB) ~xhaust flow indication is lost, THEN the Control Room should be contacted to determine flow rate via ODCM 6.1.2.D method.

2) Isotope Box range is GE O to 1 E4 µCi/cc, enter the observed concentrations of each identified isotope

Attachment 7.1, URI User Guidance Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/A

Title:

Emergency Dose Projection System Operations Page: 23 of 34

e. Field Team TAB

(available for all chosen Pathways) is used to estimate the source term and to calculate a complete dose projection based on readings obtained from monitoring teams in the field.

1) Analysis Basis a) Downwind (Miles) range 0.25 to 10 miles (1.2 miles is SB) b) Exp. Rate (mR/hr) range 0.1 to 99999.9 data must be based on observations in the centernne of the plume c) 1-131 Cone. (µCi/cc) range 1E-11 to 1E11 µCi/cc, data must be based on observations in the centerline of the plume. This field is auto filled in when using the Air Sample Calculation. To use the Air Sample Calculation:

(1) Bring up Air Sample Calculation screen by selecting it from the Calculations TAB in the upper left of the URI Detailed screen.

(2) Select Count Rate Meter from the Iodine Cartridge Instrument pulldown menu.

(3) Enter Background and Cartridge Gross count rate (4) Enter Sample Flow Rate and Sample Collection Time (5) Press Enter and then the 'Transfer to Field Team Cale" button

(6) The Iodine concentration is transferred to the Field Team Tab for use in the assessment.

d) Survey Date/Time, enter date and time of sample taking

2) Travel Information a) "Travel Time" is derived from the "Downwind (Miles)" input and the Wind Speed used in the Meteorological Data Grouping section. No input required.

b) "Release Time" is derived from "Travel Time" and the date/time used in the "Survey Date/Time" box. No input required.

Attachment 7.1, URI User Guidance Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/A

Title:

Emergency Dose Projection System Operations Page: 24 of 34 3.1. 7 When all needed data has been entered, the "Process Assessment" may be selected.

Select either the "10 miles" or "50 miles" Process Assessment button.

A green progress bar will be displayed.

Typical calculation times will be less than 20 seconds.

Results for dose assessment by distance will be displayed.

3.1.8 To view Evacuation Area Overview,

Select the "View Evacuation Area Graphic" (GLOBE ICON) below "Monitored" TAB for PAR graphic.

3.1.9 To perform an update or different calculation,

Change any or all input values as needed and Select the Process Assessment button again.

If only changing one field, it may be necessary to click out of that field to get the Process Assessment button to appear.

3.1.10 To preview the Dose Assessment Report,

Select "Print Preview Option" (magnifying glass icon) directly below the "Monitored" TAB and then select Preview Dose Assessment Report.

The Receptor Point Report is not used at CGS.

3.1.11 To print the Dose Assessment Report, either

Select the "Printer" icon to print or

Select "Close" to return to the main screen.

3.1.12 If printing is desired from the main screen,

Select "Print Options" (printer icon) directly below the "Monitored" TAB and

Select Print Dose Assessment Report.

3.1.13 For Plume map, select "View Receptor Point Locations" (world icon) in the upper left of screen under "View"

Recommend selecting RASCAL puff grids and Show Balloons.

Hover above grid point with cursor to obtain grid projected dose.

Print option is in lower right-hand corner of map screen.

END Attachment 7.1, URI User Guidance Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/ A

Title:

Emergency Dose Projection System Operations Page: 25 of 34 Air Sampling Worksheet Calculation

1. Cartridge Filter: AgZ Filter I NOTE: 1.89 x 108 = 0.003 ( eff) x 2.83 x 104 cc/ft3 x 2.22 x10 6 dpm/µCi

(Sample CPM: ____ ) - (Background CPM: ____ ) = Net CPM ___ _

= Net CPM cc I Activity (1.89 x 10 8 ) x (sample volumeft 3 ) µCi/ ----

2, Particulate Filter

I NOTE: 5.65 x 109 = 0.09 (eff) x 2.83 x 104 cc/ft3 x 2.22 x 106 dpm/µCi.

(Sample CPM: ____ ) - (Background CPM: ____ ) = Net CPM __ _

= Net CPM cc Particulate Activity (5.65 x 10 9 ) x (sample volume ft 3 ) µCi I ----

END Attachment 7.2, Air Sampling Worksheet Calculation Number: 13.8.1 j Use Category: REFERENCE Major Rev: 041

Title:

Emergency Dose Projection System Operations Minor Rev: N/A Page: 26 of 34

Alternate Method for Obtaining Met Data

NOTE: In the event of a loss of SM-8, the MET tower will be out of service.

1. IF CGS Met data is not available via eDNA View, THEN request data from Main Control Room Board "L".

2. IF neither CGS Met Data is available, THEN obtain Met Data from one of the following alternate sources in the order given:

a. Hanford Internet Site Weather Page:

1) Select the Hanford weather icon to access the FFTF (400 Area, Station #9) meteorological information via the Internet, or

2) IF the icon is not available, THEN use the following Internet address: http://www.hanford.gov/page.cfm/hms When the icon is selected on the desktop, either a Hanford site map or the data for FFTF will be displayed.

IF the Hanford site map is displayed, THEN select the 400 Area (Station # 9) to view the FFTF data.

IF Station #9 is not available,

THEN use Station #11, or Station #13.

Use the 10-meter height for the wind speed and direction.

These 3 Stations have AT, which can be used to determine Stability Class.

3) IF necessary, to determine AT, THEN use the 60-meter temperature reading minus the 10-meter temperature reading.

b. Hanford Weather at 373-2716 or 373-2610.

Request wind speed, direction, and differential temperature for the FFTF met tower.

If this information is not available from the Hanford Weather forecaster, contact the National Weather Service.

c. Telephone the National Weather Service (NWS) Forecaster (tertiary alternate) at one of the following locations:

1-541-276-8234 Pendleton, Oregon (Primary) 1-206-526-6083 Seattle, Washington (Secondary)

Request the following met data for the Hanford weather station:

Wind speed (in MPH), wind direction, and atmospheric stability.

The NWS does not provide a temperature differential.

The NWS will describe the stability category as neutral, moderately stable, etc.,

Use step 2 to convert to A - G.

d. National Weather Service website: http://www.nws.noaa.gov/

Attachment 7.3, Alternate Method for Obtaining Met Data Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041

Title:

Emergency Dose Projection System Operations Page: 27 of 34 Minor Rev: N/A

3. IF the Stability Class is not shown on the eDNA View THEN determine Stability Class as follows:

a. IF the LiT can be obtained from Panel H13-P823 Board L,

{Met System located in the Control Room via the Information Coordinator),

THEN input AT into URI to obtain Stability Class.

NOTE: The following table represents Stability Class vs CGS AT Main Control Room Board L Operator Aid will require updating if the below table is revised

Stability Class vs. Temperature Change for Station Met Tower

Stability Classification NRC Categories Temperature Change with Height Stability (°F/212 ft-75m - 10m)

Extremely unstable A AT :S -2.2 Moderately unstable B -2.2 < AT s -2.0 Slightly unstable C -2.0 < AT s -1.7 Neutral D -1.7 < AT :S -0.6

Slightly stable E -0.6 <AT:S1.7 Moderately stable F 1.7 < AT :S 4.7 Extremely stable G AT> 4.7

b. IF no AT is available, THEN use the following table to determine Stability Class:

Stability Class DeternJin~tion Daytime Solar Radiation (For moderate cloud cover move one column to Nighttime Conditions Surface the right)

Wind Speed <3/8 (mph) Summer Spring/Fall Winter Heavy Thin overcast Heavy Clear Sky Clear Sky Overcast (>1/2 cloud cloud Overcast Rain cover) cover Rain

<4.5 A B B D F F D to6.7 A B C D E F D to 11.0 B C C D D E D to 13 B D D D D D D

> 13 C D D D C D D Table developed using guidance in EPA-454/R-99-005 {2000).

END Attachment 7.3, Alternate Method for Obtaining Met Data Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041 Minor Rev: N/ A

Title:

Emergency Dose Projection System Operations Page: 28 of 34

Computer Points Used in the eDNA View Radiological Status Screen

Radiplogic~I ~tatu$ ENW.CGS.TIMET

. Reactor-*fl!ower Q012 % 1

Met; Channel A Met. Ctian11el ~

Pelta:T META69 deg F METB69 deg F Stab,lity Class META70. Q224A METB70 Q224B Wind Velocity META58 mph METB58 mph Wind Direction From META60 deg A,ii! METB60 cjeg,A_z.

1 E:ich X213cfm A~M19 *Main CR Qd92 mR/hr TGExh X19Bcfm Rx Sti1ckComp X415UCi/cc w 1 60& fJJel Pool Q093 mRihr CO!VIP :X409 uCi/cc,-;

Stack Lo X396uCi/cc J:"34 606 DiSEP ooss l'/hr NG Low L107 uCi/cc Stacklht X397UCi/cc N 8.572,SGTS ooasmR/hr Effluent X394uCi/s

$tac!< H.! X400UCi/cc S 6 57;i! Rc;>A Q096'11Rlh.r Plnr,iA X079 mRihr E4 572 CRD 0094 mRfhr. RWExh X366 cfm Plnrn C X094 mR/hr.W5 512 CRD Q095mR/hr-COMP X408 uCi/cc Cntrrit E X432 Rlhr MW"33 50*1 Entry ooa4 Rittr NG Low L109 uCi/cc cntmtF X399 Rlhr NE7 501 TIP. 0091mRihr.* Effluent X393 uCi/s DWPress 0022 psip NE"32 471 Elev#1 Q083Rlhr DWTemp Q047 dee, F w 24 471 Valve Q099mRlht Critmt NG X469UCi/cc FDRSumjJ 0041 gpin W9422RHR-A.Q087 rriRJhr 1 Part X470. uCl/cc J:DRS,ump 0039 gpm W 10 422 RHR,B qoasmR/ht 2NG X398 uCi/cc N11422 RMR~ Q089 mRJhr 2 Part X413 uCi/cc

'SOTSA1 X466 cfrit S,23,422 CRD Q09B*mR/hr SGTSA2 X356cfril N:12 422 RCIC ao9omRJhr Treatment SOTSB1 X452cfm E 13.422 HPCS Q091 mRJhr Pre-Treat X073 mR/hr SGTSB2 X371 Cfm Post-Treat xoaauCi/cc

END

Attachment 7.4, Computer Points Used in the eDNA View Radiological Status Screen Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041

'----------------1 Minor Rev: N/A

Title:

Emergency Dose Projection System Operations Page: 29 of 34 Alternate Method for PRM Stack Monitor

NOTE:

When the low range detector purges and transfers to the medium range detector the low range will show downscale. The alarms on H13-P602 will clear during the purge process and then come back in after the purge is complete; this takes about three minutes.

The medium range and composite will remain reading at all times (power allowing).

eDNA will turn red on the Composite and remain red at the Alert alarm value; the Alert alarm is NOT an ALERT EAL but is a warning you are approaching a UE EAL.

GOS Overview has the stack composite value at the bottom of the screen.

The E 1 Containment and eDNA Containment Status reads the Composite for all PRMs.

If the sample rack loses power for GT 4 seconds, the Sample Rack (and pumps) will go through an auto-reboot process where no data is available to the MCR for ~ 2 to 3 minutes after power is regained; expect this if regaining SM-8 power from DG2.

A portable radiation survey meter or an installed radiation monitoring instrument measuring radiation levels at the exterior center of the Elevated Release Stack Access Door (R-DOOR-R515) provides an alternate means of monitoring radioactive effluent releases through the Reactor Building Stack when the installed post-accident effluent monitor PRM Stack Monitor is unavailable.

The radiation level readings (in mR/hr) from this Stack Door Monitor (SOM) can be input into the

Monitor Reading field in URI to perform a dose projection. The technical basis for this SOM to PRM equivalency can be found in Engineering Calculation NE-02-09-12. The use of the table may be used for Table 3 equivalency if needed i.e., URI is not available.

Note: for the UE value, background at 100% power is ~4.1 mr/hr.

Data from eDNA Points EP99M (mid-range SOM, 5 mR/hr to 1 E6 mR/hr) and EP99H (high-range SOM, 1000 mR/hr to 1 E7 mR/hr) is updated approximately every minute and is displayed in mR/hr.

Always round to the nearest whole number (e.g., 23.645 mR/hr should be rounded to 24 mR/hr).

When Stack Table 3 Door Monitor net reading is Equivalent (mR/hr) (µCi/cc) Action Notes (based on filtered releases)

8 3.05E-3 (11) PPM 13.1.1 Table 3 Unusual Event EAL threshold*

12,100 2.82E+01 (12) PPM 13.1.1 Table 3 Alert EAL threshold*

1.21E5 7.50E+01 (13) PPM 13.1.1 Table 3 Site Area Emergency EAL threshold*

1.21E6 7.50E+02 (13) PPM 13.1.1 Table 3 General Emergency EAL threshold*

If URI is not available END

Attachment 7.5, Alternate Method for PRM Stack Monitor Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041

~-------------1 Minor Rev: N/A

Title:

Emergency Dose Projection System Operations Page: 30 of 34 Alternate Method for TEA-RIS-13 or WEA-RIS-14

Compensatory Noble Gas Monitor (CNGM) sample cart(s) will be available to measure radiation levels as a compensatory measure when the normal sample racks forTEA-RIS-13 and/orWEA-RIS-14 are unavailable. There is one cart for TEA, and a one cart for WEA readings. While the equations below apply directly to the readings from either cart, it is critical to ensure that the WEA cart readings are only used for WEA dose assessments and TEA readings be used for TEA dose assessments.

IF both WEA and TEA are non-functional, THEN both carts will be in operation and dose assessments must be derived from the respective cart.

The technical basis for this compensatory measure equivalency can be found in RSCS TSD-13-035 (CVI 1057-00, 131). The conversion equations below are used for calculating equivalent inputs for URI.

Data from the CNGM will be available to the Main Control Room for monitoring a release during this compensatory measure. There is a slide at the frisker which is inserted for normal readings Less Than or Equal to (LE) 400,000 cpm and withdrawn for readings Greater Than (GT) 400,000 cpm.

1) IF URI is unavailable, THEN use Table 3 of PPM 13.1.1 to classify.

2) IF frisker reading is GT 400,000 cpm, THEN direct Chemistry to withdraw the CNGM slide.

3) IF calculating TEA values to input into URI,

THEN use the following conversion factors, otherwise N/A this step:

IF TEA frisker reading is LE 400,000 cpm, (slide inserted) (Low Range Input)

THEN TEA URI INPUT (µCi/cc)= [Frisker output (cpm)] / 1.01E7 cpm/µCi/cc Example: the frisker reading obtained from the sample cart is 80,000 cpm.

The equivalent URI input for either TEA or WEA would be:

TEA 80000 cpm divided by 1.01 E7 cpm/µCi/cc = 7.92e-3 µCi/cc Enter this value into URI for the TEA monitor.

IF TEA frisker slide is withdrawn, THEN TEA URI INPUT (µCi/cc)= [Frisker output (cpm)] / 3.87E6 cpm/µCi/cc

4) IF calculating WEA values to input into URI, THEN then use the following conversion factors, otherwise N/A this step:.

IF WEA frisker reading is LE 400,000 cpm, (slide inserted) (Low Range Input)

THEN WEA URI INPUT (µCi/cc) = [Frisker output (cpm)] / 1.01 E7 cpm/µCi/cc

IF WEA frisker slide is withdrawn, THEN URI INPUT (µCi/cc)= [Frisker output (cpm)] / 3.98E6 cpm/µCi/cc END

Attachment 7.6, Alternate Method for TEA-RIS-13

or WEA-RIS-14 Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041

Title:

Emergency Dose Projection System Operations Page: 31 of 34 Minor Rev: N/A

Dose Assessment Using Rapid URI

NOTE: Use of Rapid URI requires that the release pathway matches one of the limited options.

Rapid URI is not usable for Rad Waste Building or Unmonitored release.

Rapid URI is not usable if release path is through SGT and SGT is "Not Working".

From ARP 4.811.1<2 4-3, If SGT Carbon Filter inlet moisture (SGT-Ml-4A / 48) is GE 70% then SGT is "Not Working".

The following steps will provide guidance on performing a Rapid URI dose assessment with normal met tower and radiation monitors available.

1. START the URI software with icon (software on "C" drive if icon missing).

2. IF not a real event, THEN SELECT "This is a drill".

3. SELECT "Rapid" (LIGHTNING BOLT) icon on the URI main screen

4. SELECT one of the following.

IF PPM 13.1.1 Table 3 Effluent Monitor reading is Greater Than or Equal to Alert value, THEN SELECT Fuel Clad Damage "Yes",

IF PPM 13.1.1 Table 3 Effluent Monitor reading is Less Than the Alert value, THEN SELECT Fuel Clad Damage "No", and

SELECT "Yes" or "No", Have the Conditions for Coolant Spiking been met?

IF from Spent Fuel Pool, THEN SELECT Damaged Spent Fuel Assembly.

5. PERFORM one of the following.

IF Fuel Clad Damage was selected, and reactor power is LE 1 %,

THEN CHECK Reactor Shutdown and INSERT the time of shutdown.

IF Fuel Clad Damage was selected, and reactor power is GT 1 %,

THEN LEAVE Reactor Shutdown blank.

IF Damaged Spent Fuel Assembly was selected, THEN UPDATE "Last Irradiated" to 5/5/2023.

NOTE: If SM-8 is deenergized, the MET tower will be out of service.

6. ENTER Meteorological data

SELECT CGS 33ft Tower, if not available, then select FFTF #9 10m.

ENTER Wind Speed

ENTER Wind Direction (W/D)

SELECT Stab Class

SELECT Precipitation

Attachment 7.7, Dose Assessment using Rapid URI Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041

~--------------< Minor Rev: N/A

Title:

Emergency Dose Projection System Operations Page: 32 of 34

7. ENTER Release Duration - for ongoing release round up to next hour and add two.

8. SELECT Release Point Pathway.

NOTE:

If SM-8 is deenergized, PRM System is unavailable, use SDM points EP99M and EP99H as needed.

If SM-7 is deenergized, TEA is unavailable, if sample cart is in service, convert reading by using Attachment 7.6

If release is from the Reactor Building Stack, use Stack Comp (Composite) if available; select Monitor based upon value as shown below:

o PRM-RE-11 (low) if radiation level is LE 1 E-2 µCi/cc o PRM-RE-12 (mid) if radiation level is GT 1 E-2 thru LE 1 E1 µCi/cc o PRM-RE-13 (hi) if radiation level is GT 1 E 1 µCi/cc o Stack Door Monitor (if in service as compensatory measure)

If release is from the Turbine Building Exhaust, use the COMP reading

9. SELECT an Effluent Monitor that has valid and on-scale data for selected pathway.

10. ENTER the monitor reading for the selected monitor.

11. ENTER the Release Point Flow Rate. (If SBGT is running and Reactor Building Exhaust Fans are shutdown; use the total of the running SBGT train flowrates.)

12. SELECT "Process Assessment" button.

A green progress bar will be displayed. Typical calculation times will be less than 20 seconds.

13. When complete, a graphic of affected areas that may require PARs will be displayed.

14. Double CLICK on the protective action display to show a pop-up of the dose results table.

15. SELECT Print to Default Printer (printer icon, upper left corner of page) to produce a paper output.

16. REVIEW dose projection printouts, note any qualifying factors as appropriate and BRIEF the Shift Manager, REM or RPM on the dose projection.

17. COMPARE URI output at 1.2 miles for EALs per PPM 13.1.1 and for potential PARs.

18. Shift Manager, RPM or REM SIGNS printed data for distribution.

19. FORWARD to the Emergency Director for approval prior to releasing data for distribution.

Attachment 7.7, Dose Assessment using Rapid URI Number: 13.8.1 I Use Category: REFERENCE Major Rev: 041

Title:

Emergency Dose Projection System Operations Page: 33 of 34 Minor Rev: N/A

Dose Assessment Using Detailed URI

The following steps will provide guidance on performing a Detailed URI dose assessment.

1. START URI with icon (software on "C" drive if icon missing).

2. IF not a real event, THEN SELECT "This is a drill".

3. SELECT "Detailed" (CLOUD) icon on the URI main screen.

4. SELECT one of the following Source Term

Normal Coolant-IF Normal Coolant is selected, THEN SELECT Spiking Factor if Reactor Building process radiation monitors spike following a plant transient.

Reactor Core Accident -IF Reactor Core Accident (PPM 13.1.1 Table 3 Effluent Monitor reading Greater Than or Equal to Alert value), THEN SELECT core condition.

o CLAD (EOPs) or o MELT (SAGs entered).

Spent Fuel Accident -IF Spent Fuel Accident, is SELECTED, specify age based on last refueling outage shutdown, THEN UPDATE "Last Irradiated" to 5/5/2023.

NOTE: If SM-8 is deenergized, the MET tower will be out of service.

5. ENTER Meteorological data.

SELECT CGS 33ft Tower, if not available, then select FFTF #9 10m.

ENTER Wind Speed

ENTER Wind Direction (W/D)

SELECT Stab Class

SELECT Precipitation

6. IF reactor power is LE 1 % (shutdown), THEN SELECT box for Reactor Shutdown.

7. VERIFY shutdown date/ time-CHANGE if needed.

8. VERIFY TAS (time after shutdown)- CHANGE if needed.

9. ENTER Release Duration - for ongoing release round up to next hour and add two.

10. DOUBLE CLICK yellow Pathway bar to show pathways selection screen.

11. SELECT best matching pathway.

NOTE: Factor groupings that are grey do not apply to the selected pathway.

From ARP 4.811.K2 4-3, If SGT Carbon Filter inlet moisture (SGT-Ml-4A / 4B) is GE 70%, then SGT is "Not Working".

12. REVIEW the process reduction factor selections on the bottom of the pathway page. Defaults are specified but these may be changed as needed to better represent the plant status.

IF pathway is through Standby Gas Treatment (SBGT),

THEN CHANGE "Reactor Building Reductions" Hold-Up Time to 2-24 Hours.

THEN SELECT SBGT Status (Working or Not Working)

13. SELECT "Accept" on the pathways page.

Attachment 7.8, Dose Assessment using Detailed URI Number: 13.8.1 / Use Category: REFERENCE Major Rev: 041

Title:

Emergency Dose Projection System Operations Page: 34 of 34 Minor Rev: N/A NOTE:. If TAB cannot be selected, then the pathway selected does not support monitored release assessment.

14. IF pathway is from the RB Stack, TB Exhaust or RW Exhaust, THEN SELECT Monitored TAB top center.

NOTE:

If SM-8 is deenergized, PRM System is unavailable, use SOM points EP99M and EP99H as needed.

If SM-7 is deenergized, TEA and WEA is unavailable, if sample cart is in service, convert reading by using Attachment 7.6

If release is from the Reactor Building Stack, use Stack Comp (Composite) if available; select Monitor based upon value as shown below:

o PRM-RE-11 (low) if radiation level is LE 1 E-2 µCi/cc o PRM-RE-12 (mid) if radiation level is GT 1 E-2 thru LE 1 E1 µCi/cc o PRM-RE-13 (hi) if radiation level is GT 1 E1 µCi/cc o Stack Door Monitor (if in service as compensatory measure)

If release is from the Turbine Building Exhaust, use the COMP reading

If release is from the Radwaste Building Exhaust, use the COMP reading

15. SELECT a monitor that has valid and on-scale data for selected pathway.

16. ENTER the Monitor reading for the selected monitor.

17. ENTER the Release Point Flow Rate. (If SBGT is running and Reactor Building Exhaust Fans are shutdown; use the total of the running SBGT train flowrates.)

18. SELECT the 10 miles or 50 miles Process Assessment button.

A green progress bar will be displayed. Typical calculation times will be less than 20 seconds.

19. SELECT "View the Evacuation Area Graphic" (I) (Globe icon) for PAR graphic.

20. To perform an update or different calculation, CHANGE any or all input values as needed and, SELECT the Process Assessment button again. If only changing one field, it may be necessary to click out of that field to get the Process Assessment button to appear.

21. SELECT Print Preview Options (@. ;) (Magnifying glass icon) to view the Dose Assessment report.

The Receptor Point Report is norused at CGS.

Either SELECT the "Printer" to print or SELECT "Close" to return to the main screen.

22. IF printing is desired from the main screen, THEN SELECT Print Options (. ~~) (printer icon) to print out a copy of the Dose Assessment report.

23. REVIEW dose projection printouts, note any qualifying factors as appropriate and BRIEF the Shift Manager, REM or RPM on the dose projection.

24. COMPARE URI output at 1.2 miles for EALs per PPM 13.1.1 and for potential PARs.

25. Shift Manager, RPM or REM SIGNS printed data for distribution.

26. FORWARD to the Emergency Director for approval prior to releasing data for distribution.

Attachment 7.8, Dose Assessment using Detailed URI

ML23163A055

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