ML20206P054

Rev 3.2 to EDAMS/RADDOSE-V

ML20206P054
Person / Time
Site:	FitzPatrick
Issue date:	12/31/1998
From:	EARTH TECHNOLOGY CO.
To:
Shared Package
ML20198K675	List: ML20198K673 ML20206P054
References
PROC-981231, NUDOCS 9812310130
Download: ML20206P054 (100)

Text

T 3'{ ,

O Operator's Manual EDAMS/RADDOSE-V Rev. 3.2 O

December,1998 Prepared For:

Niagara Mohawk Power Corporation and New York Power Authority Submitted By:

Earth Tech 196 Baker Avenue Concord, MA 01742 (978)-3714 000 0

9812310130 981222 ~

hDR ADOCK 05000333 PDR

r- m i

1 TABLE OF CONTENTS Page 1-1

1. INTRODUCTION 1-1 1.1 Scope 1-1 1.2 Purpose 2-1 2.SYSTEMINSTALLATION 2-1 2.1 Hardware 2-1 2.2 Installation 2-2 23 Notes 2-3 2.4 Modem Setup 2-4 2.5 Running EDAMS 3-1 3.EDAMS OVERVIEW 3-1 3.1 Program Functions 3-1 3.1.1 EDAMS 3-1 3.1.2 Raddose-V 3-2 3.2 Input / Output Formats 3-2 33 Raddose-V Limitations / Characteristics 3-3 3.4 Performance 4-1

4. PROCEDURAL OVERVIEW

~

51 5.USERINTERFACE 5-1 5.1 Windows Terminology 5-3 5.2 Program Keys 5-3 53 Screen Formats 5-3 53.1 Menus (Windows Based Programs) 5-4 53.2 Menus (DOS Based Programs) 5-4 533 Data Entry Screens (Windows Based Programs) 5-4 53.4 Data Entry Screens (DOS Based Programs) 5-4 53.5 Output Screens 5-5 5.4 Warning and Error Messages 6-1

6. EDAMS 6-1 6.1 EDAMS 6-3 6.1.1 Release Rate Calculations 6-9 6.1.1.1 Nine Mile Point Unit 1 6-10 6.1.1.2 Nine Mile Point Unit 2 6-11 j 6.1.13 James A.Fitzpatrick 6-12 l 6.1.2 Protective Action Recommendations 6-13 6.1.3 RASCAL 1476 901/ptsiopman'OPMANRE'O. DOC Page i Contents

O TABLE OF CONTENTS (V Page 6-13 6.1.4 Field Team Calculations 6-16 6.2 Login 6.3 liistoric Meteorology (MetVAX Terminalicon) 6-18 6.4 Current Meteorology (Emergency Met Report icon) 6-19 6-20 6.5 Raddose-V Dose Assessment Model 6-20 6.6 Logoff 6-20 6.7 Ingestion Pathway / Environmental Analysis 6-21 6.7.1 Main Menu 6.7.1.1 Evaluate a New Sample 6-21 6.7.1.2 Load a Previous Sample 6-22 6-23 6.7.2 Sample Analysis 6-24 6.7.3 Results 6.7.3.1 Soil (Milk), Milk, and Forage (Milk) 6-25 6.7.3.2 Produce and Leafy Vegetables 6-25 6-25 6.7.3.3 Water 6-26 6.7.3.4 Soil (Relocation) 6-27 6.8 Defaults Program 6-31

' 6.9 NewPassword Program 6-33 6.10 Make Maps Program 7-1

7. RADDOSE-V 7-2 7.1 Start-Up Menu 7-2 7.1.1 Begin New incident 7-3 7.1.2 Continue With Previous incident 7-4 7.1.3 Save Data to Disk

, 7-4 7.1.4 Load Data From Disk l 7-5 j 7.2 Accident Scenario Definition 7-6 i

7.3 Main Menu 7-7 7.3.1 Source Term Data Entry 7.3.1.1 Accident Types 78 7.3.1.2 TotalIsotope Release Rate Methods 7-12 7-12 7.3.1.2.1 Nine Mile Point Unit 1 7-17 7.3.1.2.2 Nine Mile Point Unit 2 7.3.1.2.3 James A Fitzpatrick 7-21 7-25 7.3.1.3 lodine Release Ra'e Methods 7.3.1.4 Changing the Accident's isotopic Distribution 7-27 l 7-28 7.3.1.5 Accepting Data 7 29 7.3.2 Meteorological Data Entry - Elevated or Ground Level 7-31 7.3.3 Performing Real-Time Calculations p 7.3.4 Performing a Forecast 7-31

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TABLE OF CONTENTS

,7 e 6-13 6.1.4 Field Team Calculations 6-16 6.2 Login 6-16 63 Hinoric Meteorology (Met Summary Icon) 6-17 6.4 Current Meteorology (Met Report Icon) 6-17 6.5 Raddose-V Dose Assessment Model 6-18 6.6 Logoff 6-18 6.7 Ingestion Pathway / Environmental Analysis 6-19 6.7.1 Main Menu 6-19 6.7.1.1 Evaluate a New Sample 6-20 6.7.1.2 Load a Previous Sample 6-21 6.7.2 Sample Analysis 6-23 6.73 Results 6-23 6.73.1 Soil (Milk), Milk, and Forage (Milk) 6-24 6.73.2 Produce and Leafy Vegetables 6-24 6.733 Water 6-25 6.73.4 Soil (Relocation) 6-26 6.8 Defaults Program 6-30 6.9 NewPassword Program 6-32 6.10 Make Maps Program 7-1

7. RADDOSE-V -

7-2 7.1 Start-Up Menu 7-2 7.1.1 Begin New Incident 7-3 7.1.2 Continue With Previous incident 7-4 7.13 Save Data to Disk 7-4 7.1.4 Load Data From Disk 7-5 1 7.2 Accident Scenario Defmition 7-6 '

73 Main Menu 7-7 73.1 Source Term Data Entry 7-8 ,

73.1.1 AccidentTypes 7-12 73.1.2 Totalisotope Release Rate Methods 7-12 73.1.2.1 Nine Mile Point Unit 1 7-17 73.1.2.2 Nine Mile Point Unit 2 7-21 73.1.23 James A Fitzpatrick l 7-25 73.13 lodir.e Release Rate Methods 7-27 f 73.1.4 Changing the Accident's Isotopic Distribution 7-28 73.1.5 Accepting Data 7-29 73.2 Meteorological Data Entry - Elevated or Ground Level 7 31 733 Performing Real-Time Calculations 7-31 73.4 Performing a Forecast 1476-90liptsiopman/OPMANRl'O. DOC l Pageil coments l l

I O TABLE OF CONTENTS Page B33 7.4 Output Menu 7-34 7.4.1 Grid Receptor Doses 7-37 7,4.2 Plume Arrival Times 7-38 7.4310-Mile Maps and PARS 7-40 7.4.4 Survey Point Doses 7-41 7.4.5 Point-ofInterest Dose Rates 7-42 7.4.6 50-Mile Deposition Data 7-43 7.4.6.150-Mile Map i

7-44 7.4.6.2 Deposition Rate and Accumulated Deposition Data 7-45

( 7.4.63 Survey Points Deposition Data 7-46 7.4.6.4 Dose Rates From Deposition 7-47 7.4.7 Report Options Menu 7-47 7.4.7.1 Complete Dose / Dose Rate Report 7-48 7.4.7.2 Grid Receptor Isotope Report 7-48 7.4.7.3 Map Reports 7-48 7.4.7.4 Header Page 7.4.7.5 Print Reports and Maps (and Emergency Form in 7-48 Forecast Mode) 7-48 O 7.4.7.6 Print Notification Form Part 2 (Forecast 7.4.7.7 Print a Previous Step (Real Time Mode)

Mode) 7-49 7-49 7.4.8 Continue Calculations 7-49 7.5 ASCIIFiles 7-50 7.6 Map Editing )

l APPENDICES:

Appendix A- Chart Appendix B - Sample Raddose-V Printout Appendix C - Sample Ingestion Pathway Printout 1476-901/ptslopman'OPMANRVO. DOC Pagelii Contents

Proprietary Notice This document contains material which is proprietary to Earth Tech and has been provided to Niagara Mohawk Power Corporation (NMPC) and the New York P Authority (NYPA) for their sole and exclusive use. No part of this document may b distributed to individuals who are not employees of NMPC or NYPA without the written consent of Earth Tech. Furthermore, no employee or agent of NMPC or NYPA may retain any portion of this document for personal or professional use upon termination of his or her association with NMPC or NYPA.

O O

Page av models nmpc nradJose '613.' upman Opmunrvu doc Gontents $ 98

ra ooucnox O 2-1.1 Scope This document is the Operators Manual provided for Niagara Mohawk Corporation and the New York Power Authority for the Emergenc Assessment Modeling System (EDAMS) for the Nine Mile Point and Fitzpatrick Power Plants. The following topics are discussed and/o

. Installation and start-up procedures

. Data input procedures

. Calculation procedures

. Forecastingprocedures

. Reportmg procedures

. Error and Warning Messages

. Sample Screen Displays

. Sample Output Report

. Archiving of System Data e Model Limitations and Characteristics 1.2 Purpose The purpose of the Operators Manualis to provided the use necessary to run EDAMS; from installing the model EDAMStois producin tabular output reports for both real-time and forecasting modes. i Windows 2 based and its individual components are activated found in the EDAMS program group.

Data input procedures provide instructions to the d foruser for conditions that affect the transport and diffusion of a radioactive re entry of source term data for each advection step.

Dose, dose rate, and deposition calculation procedures b ii g a time and forecasting modes. The user is provided with instructio dose rates and cumulative doses, ground deposition at d corresponding dose rates from the material deposited y on th are provided the opportunity to print Parts 1 and 2 of the N Data Fonn.

O 1176-90liptsiopman!OPMANRVO. DOC Page1-1 Introduction

2. SYSTEM INSTALLATION 2.1 Hardware O

EDAMS is designed to be operated on an IBM compatible personal computer system with the following minimum conGguration:

. 80486/DX or Pentium processor

. At least 8 MB internal RAM

. 1.44 MB DSHD 3.5" Doppy disk drive

. At least 100 MB hard disk

. VGA Graphics Adapter Card

. VGA Color Graphics Display

. MS-DOS Version 5.0 (or later) Operating System 3.1, Wi..uows 95. or Windows NT

. Microsoft@ Windows

. Mouse The EDAMS program supports hard-copy output of both tabular and graphical data on any of the following printers:

. Hewlett-Packard Laserjet Series laser printers e Okidata dot matrix printer

. Okidata 321 IBM chip

. XL300 Paintjet f

Other printer drivers are available as long as Windows" includes a driver for the particular printer.

2.2 Installation it is assumed that Windows is installed on the computer and the printers are setup i

and con 0gured through the Windows' control panel. (See Microsoft Windows User's Guide or your computer group for assistance.) The procedure listed below describes how to add EDAMS to Windows.

1. Boot the computer normally.

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2. If running Windows 3.1, start Windows by typing:

WIN < ENTER >

at the DOS prompt.

3. Insert the setup disk in floppy drive a or b:.

4. If running Windows 3.1, from the Program Manager, select FILE then RUN and type:

A: SETUP or B: SETUP  !

If running Windows 95 or NT, click the START menu then RUN and type: l l

A: SETUP or B: SETUP

5. Follow the instructions provided in the setup program.

6. The setup program will inform the user when the model is installed correctly. If any errors occur, repeat the installation procedure.

7. After the installation is complete. the file EDAMS.INI in the main subdirectory must be updated (using a text editor) to set the parameters needed to access the Meteorological Data (see Section 2.4 below).

8. When done, click on the appropriate icon and the model will start.

2.3 Notes

1. If running under Windows 3.1. Visual Basic requires that SHARE.EXE be adde to the computer's autoexec. bat file. To accomplish this, add the following line to f the AUTOEXEC. BAT file found in the computer's main directory and then re- l boot the computer. '

l C:\ DOS \ SHARE.EXE j

This assumes DOS is located in a directory called DOS on drive C:.

To change the

2. The default password is EDAMS for the Defaults program.

This l password, use the New Password icon in the EDAMS program group.

l program creates a password. file (555).txt, in the \Defs subdirectory. If this  !

is deleted, the password reverts to the original password of EDAMS. To change l

(_)

Page 2-2 modcis.nmpt radJuse :6132,opman Opmanrvu duc System installatton - 5/98

.i the password, the user must know the current password and must confirm entry of the new one.

2.4 Modem Setup The setup parameters for the modem and direct connection to the Meteorological Monitoring System are located in the file EDAMS.INI. This file is installed in the directory that the user entered in the installation program. The follov,ing describes how to modify the default parameters listed in the file.

l NOTE: The EDAMS.lNI file is configured to work with a Hayes compatible or a U.S. Robotics modem. It is best to modify as few parameters as necessary.

In this file, there is a section for accessing the NMP MMS by modem and the NMP MMS by direct connect. Each section is grouped by parameter function (i.e.,

Communications Port. Modem). There are also sections for the MMS Codex a Telecor modem phone numbers and prompts, the DEC Server and MetVAX prompts and passwords, the automatic dial-in phone number sequence and the manual dial-in phone number. MMS phone numbers, passwords, prompts, auto and manual dial-in Note:

numbers should not be changed unless done by an authorized person.

Semicolons are comment lines and are ignored.

The following parameters may require updating:

• Under the Pon Section: (modem or direct connection)

- Comm Port: Enter the serial port number where the modem or direct connect cable is attached.

• Under Local Modem Section:(modem only)

- InitString: Initialization string for the modem (see your modem manual for details, but be sure to ignore the DTR and j

to force CD on). There are two standard initialization strings, one for Hayes and one for U.S. Robotics f modems. Uncomment (remove the :) the appropriate one for your modem and comment out the other (put a

) at the start of the line.

l

- Hangup: Hangup string for the modem (see your modem manual for details, but be sure to reset the modem and to reset the CD).

O xa,,, ,,_,,., - ,m e ., _,_ A,_ o,_ l l )

Gs e Under Codex or Telecor Modems Section:

(m

\

l

- Dial Prefix: Include a 9, I and/or the area code if necessary to dial the MMS from your location.

2.5 Running EDAMS l 1

l The normal operation procedure will be to conduct dose assessment and related activities from the EDAMS program group icons displayed in Windows. To start  !

EDAMS follow this procedure.

1. If cuaning Windows 3.1, start Windows by typing : l WIN < ENTER >

c the DOS prompt.

2. To run an application, double click on the program icon from the i EDAMS program group. (See Figure 2-1) er i n., .

. maE2 I 1

Ek Le > bau ,

O

- - e--, .. - ., ... -.

RaddoseV RaddoseV ReconseV Net Repen femww Pamway Y

toAMs Logan Esa i

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l I

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Figure 2-1: EDAMS Program Group o

Page 2 J nmpe \raddose .2864'1opman;UP A fA NR VO Systern Installation - 12'98 l

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3. EDAMS OVERVIEW ,

I 3.1 Prt. gram Functions 3.1.1 ED.4MS The EDAMS program is designed to be run on an IBM Compatible 80486/DX or Pentium microcomputer for use in the assessment of off site radiological doses in the event of an accidental release of airborne radioactive material from the Nine Mile Point Nuclear Power Plant (NMP) or James A. Fitzpatrick Nuclear Power Plant (JAF). The program is a Microsoft@ Windows based system allowing a user the ability to conduct multiple applications for either Units 1 or 2 of NMP or JAF.

These applications include:

. Release rate calculations

. Providing protective action recommendations

. Dose assessment using RASCAL e Conducting calculations using field team data

. Dose assessment using Raddose-V

= Evaluation of current 15-minute meteorological data at the NMP/JAF meteorological tow ers (Emergency Met Report)

. Reviewing current or historic meteorological data from the NMP/JAF meteorological towers (MetV AX Terminal)

. Printing Part 1 of the New York State Emergency Data Form (this is available from within the Emergency Met Report option)

. Conduct ingestion pathway / environmental calculations from field data 1

. View / edit program default values

. Change the password for the defaults program

(

3.1.2 Raddose-V l I The main dose assessment component of the EDAMS, Raddose-V, accommodates f both real time and forecast modes in the calculation of exposures to the general l public. The system provides results of the sum of the effective dose equivalent from t

external radiation (both the plume and ground deposition) and the committed f effective dose equivalent from inhalation of radioisotopes (this total is referred to as the TEDE), committed dose equivalent to the thyroid for a child (CDE Child j

Thyroid), as well as deposition rates and cumulative deposition at the ground.

Raddose V uses both meteorological and source term data screens patterned after l familiar spreadsheet formats with full-screen editing capabilities. allowing both easy l Page 3-1 nmpetradJose;2864 op. nan OPM.4NRIY)

ED.4MS (kerriew - 12/98

r. .

1 data-entry and the ability to review, edit, or update data entered for other time steps.

Error messages are provided upon entry of invalid data. The Raddose-V l meteorological data entry screen also allows for direct entry of data from the NMP 3 j

Meteorological Monitoring System (MMS) resident on the NMP VAX. Program '

results are presented both in tabular form, selected from an output menu, and in graphic form to facilitate visualization of the overall emergency situation. All information presented by the program is available in an ASCil file and for output to a printer for a permanent, hard-copy record.

Raddose-V uses a variable trajectory, puff advection model of dispersion to predict the position of both ground level and elevated radioactive plumes. Inside the ten mile Plume Exposure Pathway EPZ, the model uses finite cloud techniques to -

estimate external exposure received from the plume (s) while the standard concentration y/Q methodology is used to estimate doses received from inhalation of radioisotopes and external exposure over a four day period from material deposited on the ground. In addition,~ the model incorporates routines for computing total deposition and the current dose rate from radioactive material deposited on the

)

ground out to 50 miles.

The Raddose-V calculation routiner include those for considering source term and plume decay, as well as the effects of wet and dry deposition of iodines and particulates. The model also includes predefined Protective Action Guidelines for the plume and ingestion pathway EPZs to alert users of the program to any exceedances of pre-determined limits.

3.2 Input / Output Formats Data entry to EDAMS is accomplished through a series of icons, menu selection screens and data entry screens. Data entry screens contain labeled fields where data is entered manually or plant default values are selected from the model's' data files.

In the meteorological data screens, input data is automatically downloaded from the MMS,if available.

Output data is available at the end of the calculations and for Raddose-V at the end of real-time advection steps. In the Raddose-V model cumulative doses, dose rates and deposition are presented in both tabular and graphic form on the screen and can be sent to a printer for hard copy output. In the forecast mode, Protective Action Recommendations are also available, along with the ability to print Part 2 of the New York State (NYS) Emergency Data Form.

3.3 Raddose-V Limitations / Characteristics As with any PC-based software. limitations exist on the performance of the O Raddose-V model. Most of these restrictions are due to the limited disk storage Page 3-2 nmpc \raddosci286 E 7 nopman \UPA M NR I '0 ED A SOverview- 1M8

space available in microcomputers. One program run may have a m advection steps. A full 200 advection step run requires 54 MB of disk space advection step uses approximately 271,000 bytes. The user must be aware o limits for the program to operate successfully.

A calculational limitation of Raddose-V occurs when an extre shift takes place. The model may not calculate doses in sectors that the pl over entirely within a single 15 minute interval advection step.

Further EDAMS/Raddose-V characteristics and limitations include:

The EDAMS Menu (from the EDAMS icon) only allows the operation o one application at a time.

Dose rates and deposition rates reported by the model are the maximum the sector; not necessarily the dose rate or deposition rate at the center o sector. This avoids the situation of a narrow (stable) plume slipping betwee receptor points and being missed.

. Deposition data reported in Raddose-V is not intended for an en evaluation; its intent is to indicate areas of potentially high ground leve concentrations.

Forecast mode results may at times exceed real time results; this is due the forecast mode having a greater intemal time step.

3.4 Performance The following summarizes the performance of Raddose-V running on a 486/66 MHz computer for a real-time mode run. l Wind Speed Stability Computation Time Step #

(mph) Class (seconds)

C 5.0 1 10 C 6.0 2 10 C 6.8 3 10 C 7.4 4 10 C 7.7 5 5 C 7.8 6 5 C 7.9 7 5 C 8.0 8 5 A two hour forecast with a 6 mph wind speed and stability class of D, and 36.8 seconds to compute.

O 1476 90liptstopmaWOPMANRVO. DOC Page 3-3 EDAMS Overview

4. PROCEDURAL OVERVIEW (U')

This section is a textual " walk-through" of EDAMS. Before proceeding through the more detailed se:tions that follow, this overview provides the operator of the model with a feel for the program and offers him some sense of where he has been and where he is going as he works through each part of the dose . assessment process.

This overview is represented in "How chart" form in Charts 1 and 2 in Appendix A.

EDAMS attempts to trap for system errors and r.otify the user with a message if a problem occurs. Further, when possible, the user is given options to resolve the problem. For example, if there is a problem connecting to the MMS EDAMS gives the user the option of re-trying the connection or using manual entry. However, for some errors the program can not continue. For example, if there is not enough memory to run Raddose-V. {This will generally occur when the user attempts to run many applications at the same time in Windows .]

When Windowsm is loaded and the EDAMS program group is displayed, the user is presented with a set of icons to choose from. If data is to be accessed from the MMS, for any EDAMS application. the user must initially login to the NMP system using the Login icon within the EDAMS program group. If the user does not login to the MMS, manual entry of meteorological data will be required for Raddose-V and data will no. be available for display when selecting the Emergency Met Report and MetVAX Terminal icons. Once the method for entering meteorological data is selected, the user may begin choosing applications from the appropriate icons. From the EDAMS icon, the user is able to choor from one of four DOS based applications: (1) Release Rate Calculations (apart from Raddose V):(2) Protective Action Recommendations: (3) RASCAL model; and (4) Field Team Calculations.

The Release Rate Calculation option allows the user to calculate source term release rates for each plant or unit and print results. The Protective Action Recommendations (PAR) option provides a user with initial General Emergency PARS based on wind direction and whether there is a lake breeze. following declaration of a general emergency. The RASCAL and Field Team Calculation options are ones which NMPC/NYPA will provide and insert into EDAMS.

When logged into the MMS, the user may select the Emergency Met Report and MetVAX Terminal icons to review either current 15-minute or historic meteorological data. From the Emergency Met Report Screen , a user is able to print Part i of the NYS Notincation Form.

The ingestion pathway / environmental analysis calculation routines available from EDAMS (Ingestion Pathway icon) provide a user the opportunity to analyze this pathway using environmental Geld sample data. Inputs include the sample type n

(milk, water etc.), identi6 cation number, location. collection dateltime. and isotopic h concentrations. Results identify isotopes which exceed preventative or emergency l Pa,qe 4-1 nmpetraJJose.2364~ opman OPht:t YRl'a Procedural (kerview -12/98

PAGs for each population group of interest. For soil samples, year 1 dose det:rminations are made indicating any values exceeding the limits for relocation.

Year 2 and years 0-50 dose determinations are made to identify areas which may require other protective actions.

By using the defaults icon, the user may view or edit the default values (i.e inventories, dose conversion factors, etc.) used in Raddose-V and the ingestion pathway program. This is password protected to prevent accidental edits.

When the NewPassword icon is chosen, the user may change the password for th Defaults programs. The current password must be entered correctly before the u is allowed to change to a new password.

Raddose-V may also be started for either NMP1, NMP2, or JAF by selecting th correct icon. When Raddose-V is chosen, the accident must be initialized. This accomplished either by defining a new accident with the reactor trip date an release date and time, lake surface temperature and operator's initials, or by continuing a previous incident.

When the accident has been initialized, source term data is entered. Source term data entry consists of selecting the release pathway; the accident type (e.g., a steam line break, a fuel handling accident, etc.); and the methods for determining to isotope and iodine release rates (e.g., monitors, grab samples or defaults). T may define any number of time steps in the source term data screca befo proceeding to meteorological data entry and performing calculations.

Following completion of source term data entry, elevated and ground level meteorological data are entered. The required data, wind speed and direction stability class definition, temperature, and precipitation rate, are read from if connected, for each advection step. The user is given the opportunity to accept this data or manually overwrite it. Again the data is entered in individual advec steps, and any number of steps may be defined before continuing with ca When at least one advection step of both metecrological and source term data ha been defined, the Perform Calculation command button can be selected from Once doses have been calculated for the time step, the Raddose-V Main Menu.

model saves the input data and results to a spreadsheet format ASCII file, the displays the 10-mile ERPA map. The operator presses < ENTER > or c Continue button to remove the map and the model proceeds to the Output Men From here the operator may view the Grid Receptor Doses, Plume Arrival Time 10-mile EPZ and ERPA Maps, Suney Points data, calculate dose rates at User-Specified Locations, proceed to the 50-mile Depocition Data Menu, P Report Menu, Continue with Calculations or return to the Main Menu.

O 1476-90liptslopman/OPMANRVO. DOC Page 4-2 Procedural Overview

He Report Menu screen presents options for obtaining hard copies of the dose reports at the end of each time step. He operator may select to print a Complete Dose / Dose Rate Report, including meteorological and source term data used in the calculations, percera isotope abundances, and doses and dose rates at grid receptors and survey points; the 10-Mile EPZ and ERPA Maps; the 50-Mile Map; isotope accumulations on the ground at grid receptors; or the Header Page (which provides input data, release rates, plume arrival times and isotope relative abundance). Th model provides the option of having all reports for the advection step printed at once or each report may be selected singly. The user may also print the data for a previously calculated step. In the forecast mode a user is also provided the ab print a hghpy of the NYS Emergency Data Form, Part 2. This form will include data generated by Raddose-V.

When the program run is complete, data and results can be archived to floppy dis for future reference. )

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1 l

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O 1476-901/pwopman'OPMANRVO. DOC Page4 3 Pr edural Overview

i USERINTERFACE 5.

O 5.1 Windows Terminology terminology. For This section provides a brief overview of common Windows more information, see the Microsoft Windows User's Guide.

Click: to quickly press and release the mouse bunon.

Double-Click: to click the mouse beton twice in rapid succession.

Cursor:

In text boxes, the cursor is a flashing venical line. In menus, the cursor is a dotted rectangle around the menu option. In Raddose-V's meteorological and s term screens (see Figures 7-23 and 7-7), the cursor is a gray box in the curr The selection cursor (a highlight or a dotted rectangle) indicates Selection Cursor:

what item is selected.

In text boxes, a flashing venical line that indicates where the user's Insertion Point:

typing will appear.

The up arrow in the upper right corner of the screen. It is used to Maximize Burton:

' enlarge the window to fill the screen.

O Minimize Butten: The down arrow in the upper right corner of the screen to shrink an application to an icon. This suspends operation of the applica restore the application, double click the icon.

Mouse Pointer:

Usually, the mouse pointer is an arrow. It changes to an hourglass when the progrmn is processing and the user must wait.

Command Buttons: The user can choose a command butt action. See Figure 7-2 for an example. The user can move the selection curso the desired command button by performing one of the following:

• Use the mouse to click on the button.

• Use the cursor (arrow) keys to move the highlight.

• Use the < TAB > or < SHIFT >< TAB > keys to move the highlight.

Message Boxes: The program uses pop-up message boxes to ask yes or no questions, to display error messages, or to inform the user of a con can click on the appropriate command button or press and hold down <

O 1476-901/ptslopman'OPM4NRVO. DOC Page55 User 1merface

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l typing the underlined letter on the command buuon. For error message boxes, l O the OK button or press < ENTER > to remove the message box.

l Text Boxes: Position the cursor on the text box and type at the insertion point. Press

< ENTER > when done typing and the cursor moves to the next item.

l In date/ time entry boxes, use two digits for month, day, year, Date/ Time Boxes:

hours and minutes. When the date or time is completely entemd, the cursor moves to the next item to enter.

Option Buttons: Option buttons display a group of mutually exclusive optio one can be selected at a time. The selected option contains a filled-in dot. To select l

an option with the mouse, click on it. To select an option with the keyboard, us

< TAB > to move to the group of options and then use the arrows to move among them. Press < TAB > to move to the next item and keep the option selected. See Figure 6-13 for an example.

Some screens have more information than can be displayed at once.

Scroll Bars: l See Figure 6-15. These screens have scroll bars which move the informatio displayed. With the mouse do the following:

• Click the up or down scroll arrows to move one line of data.

• Click the scroll bar above or below the scroll box to move one c worth of data.

• Click and hold the mouse pointer on the up or down arrow to move the screen continuously. l l

With the keyboard, do the following:  !

• Use up or down anow keys to move one line of data.

• Use <PAGE UP> or <PAGE DOWN> keys to move one screen's worth data.

Files Dlolog Box: The dialog box appears when the user opens or saves files. It contains a labeled text box with the directory to save or lood files, a drive dro list box and a directory list box. The user can type the directory name in the or select it by using the drive and directory list boxes. To change the cur with a mouse, click the down arrow at the right of the drive box. Click the d This updates the directory listing. To change the drive using the keyboa

< TAB > to move to the drive list box and use the arrow keys to change the change directories with the mouse, double click the directory name CI the text box. To change directories using the keyboard, < TAB > to the dir 1476 901/ptstopmaWOPMANRVO. DOC Page 5-2 UserInterface

." I box, use the arrow keys to move to the directory, and press < ENTER >. See F 7-4.

5.2 Program Keys

<F> - In EDAMS, the " help" function key. When pressed, a pop up help window with relevant comments and/or instmetions for that particular screen are provide

<F5> - In the Release Rate Calculation screens (EDAMS), outputs screen information to a printer.

<F9> - In EDAMS, accepts and saves data entered in the data entry screens proceeds to the next screen.

< ESC > - In EDAMS, aborts the present screen and returns to the previous scree Also in Raddose-V, aborts the pop-up box for selection of accident types and rate methods.

< ENTER > - Selects options in menu screens and proceeds to the next scre key is also used for ar.:epting the data entered in each individual field on screens.

CURSOR MOVEMENT (ARROW) KEYS - Moves the cursor (or highlight) up and down the options on the menu selection screens, and moves the curs between data fields and within advection steps on data entry screens when da being entered or edited.

<F2> - In Raddose-V, displays a pop-up box for selection of accident types release rate methods (in the source term data entry screen) when the cu in the appropriate data field. l t

< ALT >< TAB > - Switches between open Windows applications.

5.3 Screen Formats EDAMS uses three types of screens--menu selection, data entry, and outp Rese screens are discussed in the following sections in an effort to familia user with their functions now and, thus, avoid repetition of the same direc similar screens in every section of this document.

BasedPrograms) 5.3.1 Menus (Windows The command button The menu screens display a group of command buttons.

performs the action indicated when the button is highlighted by the s and the user clicks the mouse or presses the < ENTER > key Menus cont of the program.

1476-901/ptstopman!OPMANRVO. DOC Page5 3 UserImerface d

5.3.2 Menus (DOSBased Programs)

The menus display a list of options available for selection. The selection is made by moving the cursor to the desired option (the choice is highlighted in a different color) and pressing the < ENTER > key. Menus control the flow of the program. A the bottom of the screen is a list of the function keys available with a one or two word description of the action performed when the key is selected.

5.3.3 Data Entry Screens (Windows BasedPrograms)

The data entry screens in EDAMS are displayed with titles, labeled data fields, the help / prompt line, and a group of co===d buttons located at the bottom of screen Note that the help line contains valid data ranges for appropnate fields in Raddose-V meteorological and source term data entry screens. Data entered into individual fields are amW using the < ENTER > key.

Screens that contain a list of advection steps (Raddose-V meteorological and sourcl l

term screens) appear with the cursor in the next step to be calculated. Move the cursor within and between the advection steps using the cursor keys or by clickingl '

on the step. To enter or overwrite data, move the cursor to the correct data type in the data (unless <F2> or double click is used-see Section 5.2), an

< ENTER >. In the meteorological arxi source term data entry screens, the adve O step number will change from cya:t. to red in any step where new data h entered or changes have been made. (See Table 5-1 for a summary of the E color code sequence.)

Once all data entry is complete, click the Accept command button to save the and continue to the next screen.

5.3.4 Data Entry Screens (DOS Based Programs)

The data entry screens in EDAMS' DOS based programs are displayed wit labeled data fields, the help / prompt line, and the list of function keys ava the screen. Data entered into individual fields are accepted using the < ENT Once all editing or data entry is complete, press the <F9> function key t!

data.

5.3.5 Output Screens EDAMS has two forms of output report screens. The first are tabular sc include titles and list release rates, meteorological data, dose rates, cum and deposition in clearly labeled columns. In the EDAMS' Release R screens, values have been color coded with green to indicate default val; indicate constants, yellow to indicate user entered data and red for a c rebase rate. In Raddose-V, dose and deposition values have been col 1476-90liptslopman/OPhMNRVO. DOC Page 5-4 UserInterface ,

i

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ease in recognizing Protective Action Guidelines (PAG). Low dose or deposition values which are less than the PAG are displayed in cyan. As preventative PAG levels are met the text color changes to yellow and then to red when values increase further. If Protective Action Recommendations are ma le they are displayed near the bottom of the screen.

In the Forecast mode, the model provides both dose related and General Emergency Protective Action Recommendations (PARS). PARS are given by a list of ERPAs to evacuate and those to shelter.

The second type of output report is the graphic screens (Raddose-V) which display the 10-mile and 50-mile EPZ maps and the 10-mile ERPA map with the plume represented by a series of blue (ground level plume) and yellow (elevated plum circles, corresponding plume centerline dose or deposition rates at each ring distance, and, ifin the forecast mode, Protective Action Recommendations. Each o these screens is labeled with the present mode (real-time or forecast), the current advection step number, the time at the end of the step, a summary of the current elevated and ground level meteorological data, and the operator's initials.

5.4 Warning and Error Messages Whenever warning or error messages are triggered, they appear in bright red above the help line at the bottom of the screen in DOS based applications or in a pop-up box for Windows" based applications. These messages occur if an invalid key is pressed, an out-of-range value is entered, or data needs to be verified. (See Sy Design Specification [SDS) Tables A-1, A-5, A-6, B-1, B-5, B-6, C-1, C-5 and C for valid data ranges.) Messages instructing the user to wait while the model performs an action also appear.

l l

9 Page 3-3 1476-901/ptstopmaWOPM4NRVO. DOC User Enterface 1 _ - _ _ - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Table 5-1: EDAMS/Raddose-V Color Coding Summary Meaning Screen Display Color Green Default value - can be EDAMS Release Rate overwritten Calculations  !

Blue Conversion factors - cannot be I modified Yellow User entered values Red Calculated values Cyan Data Raddose-V Source Term Screen Red Advection step and total release Yellow In path column indicates i

elevated release Green In path columnindicates ground level release Yellow Primary met tower data Raddose-V Meteorological Screen Green Backup met data Manually entered met data Cyan Advection step or bad data Red Cyan No PARS met for data Raddose-V Screen Output ,

Reports Yellow Shelter PAR met Red EPA-400 evacuate PAR met GeneralEmergency PAR based Raddose-V PAR Coding for Cyan on plant conditions ERPAs Raddose-V dose generated PAR Yellow O

1476-90 !/ptst opman'OPMANR l'O. DOC Page 5-6 UserInterface

6. EDAMS The NMP/JAF EDAMS provides users the ability to conduct a number of emergency O

related applications including detailed dose assessment based on the Raddose-V model. The system is provided through program icons available on the EDAMS program group. From the program group, the user is also able to log onto and out of the MMS.

Figure 6-1 shows the EDAMS program group. The overall function of each of these icons is discusset. In the following sections.

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Figure 6-l: EDAMS Program Group 6.1 EDAMS When the EDAMS icon is selected, the user is presented with the EDAMS Menu which provides access to four DOS based applications (see Figure 6-2). These are as follows.

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6.1.1 Release Rate Calculations Option 1 of the EDAMS Menu provides the opponunity to calculate source term release rates for either NMP Unit 1, NMP Unit 2 or the JAF nuclear power plan apart from the Raddose-V dose assessment model. Initially, the user sel specific plant / unit (see Figure 6-3); the system then proceeds to a me the source term calculation method is selected. Figures 6-4 through 6-6 show th Once a method is selected, the user is provided with the menu for each unit.

appropriate data entry screen from which an actual release rate is calcula sample data entry screen is shown in Figure 6-7. The user enters required in the screen for the release rate method selected. Default values (i.e., calibra factors, flow rates) are shown in green The system allows a user the ability to Necessary change these values if more appropriate information is available.

conversion factors are shown in blue and cannot be modified by the user. On data is entered, press <F9> to calculate the release rate. At the bottom of each entry screen, the calculated release rate is displayed in red. The user may press

<F5> to print the input data and results e. 2ay press < ESC > to return to the rate calculation menu. If < ESC > is pressed, the results and inputs will be lost.

The next three sections discuss the release rate calculation methods for each p O

O 1476-90liptslopmaWOPMANRVO. DOC Page 6-3 EDAMS

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1 SELECT ONE OF THE F0110WI!E UPTIONS: l l

Nine Mile Point thiit 1.

!!!ne Mile Point Unit 2 James A. Fitzpatrick Figure 6-3: EDAMS Plant / Unit Menu 1476 901/ptslopman/OPMANRVO. DOC Page 6-4 EDAMS

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Return to PlantAinit it:nu

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Figure 6-4: NMP1 Release Rate Menu 1

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Page 6-6 1476-9011 pts topman/OPMANR l 'O. DOC EDAAG

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Teletector Hoble Gas Grab Sample Back Calculate FSAR Containment High knge Ibnitor kturn to PlantAinit tenu Figure 6 6: JAF Release Rate Menu O

1476-90 liptslopman'OPMANR l'O. DOC Page 6-7 EDAMS

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EDAMS: BACE CALCULATE RELEASE 1 RATE CALCUIAfl0M ..

1 ENTER THE FOLLOWIMG INFORMAfl0M FOR BACK CALCULATE : 1 l

fine of Reading (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format) 13:00 4

Accident type (Enter number from list below)

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5.00 Wind Speed (aph)

G Elevated (E) or Ground (G) Release C

Stability Class (A-G)

Three foot, Closed Window Ganna Reading (nR/hr) 1.00E+03

<] Distance of Ganna Reading (miles) 1.11E+06 Hohle Gas Release Rate (Ci/sec)

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Figure 6-7: EDAMS Sample Release Rate Data Entry Screen O

1476-901/ptslopman/OPMANRl'O. DON Page 6-8 EDAMS

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6.1.1.1 Nine kille Point Unit 1 The procedure for each of the available release rate methods for Nine Mile Point Unit 1 is presented below.

OGE5h5 When OGESMS is selected from the Release Rate Calculation Menu, a sub menu is displayed in which the user selects an OGESMS monitor ( 7,8,10a or 10b). Once this selection is made, the data entry screen is displayed. Enter the time of reading in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format and press < ENTER >. Enter the monitor reading (cpm for monitor 7 or 8 or cps for monitor 10a or 10b) and press < ENTER >. Review the default calibration factor (uCi/cc/ cpm for monitor 7 or 8 or uCi/cc/ cps for monitor 10a or 10b) and the stack flow rate (kefm). Edit these if necessary. Press <F9> to calculate the release rate in Ci/s and then <F5k to print inputs and results. Press

< ESC > to retum to the OGESMS Monitor Menu. Either select another m press < ESC > to retum to the Release Rate Calculation Menu. (Use of the <

< ESC > keys are common to the following methods as well and is not repeated.)

RAGEh6 In the data entry screen, enter the time of reading in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format and press

< ENTER >. Enter the monitor reading (eps) and press < ENTER >. Enter the process computer calibration factor (uCi/cc/ cps) and press < ENTER >. Enter the dilu factor and press < ENTER >. Review the stack flow rate (kefm). Edit if necessary.

Press <F9> to calculate the release rate in' Ci/s.

Teletector In the data entry screen, enter the time of reading in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format and press

< ENTER >. Enter the monitor reading (mR/hr) and press < ENTER >. Review the default calibration factor (uCi/cc/mR/hr) and the stack flow rate.(kefm if necessary. Press <F9> to calculate the release rate in Ci/s.

Noble Gas GRAB Sample In the data entry screen, enter the time of reading in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format and press

< ENTER >.

Enter the Noble Gas grab sample total reading (uCi/ce) and press

< ENTER >. Review the default stack flow rate (kefm). Edit if necessary. Press

<F9> to calculate the release rate in Ci/s.

Back Calculation in the data entry screen, enter the time of reading in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format and press

< ENTER >. Enter the code for the appropriate accident type and press < ENTER Page 6-9 1476-901/ptslopmoWOPhtANR VO. DOC EDAAfS

Enter the wind speed (mph) and press < ENTER >. Enter E for an elevated release or G for a ground level release and press < ENTER >. Enter the stability class (A through G) and press < ENTER >. Enter the three foot, closed window gamma reading (mR/hr) and press < ENTER >. Enter the distance (in miles) for the readi and press < ENTER > Press <F9> to calculate the release rate in Ci/s.

FSAR Dis option displays a list of default total isotope release rates (Ci/s) for each accident type. There are no values to enter or calculate.

Containment High Range Monitor in the data entry screen, enter the containment radiation monitor ID and press

< ENTER >. Enter the time of reading in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format and press < ENTER >. the the date of the reading and press < ENTER >. Enter the time of shutdown in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format and press < ENTER >, then the date of shutdown and press < ENTER Enter the radiation monitor reading (R/hr) and press < ENTER >. Review the defa

flow rate (kefm). Edit if necessary. Press <F9> to calculate the release rate in C The concentration of radioactivity expected in containment (Ci/cc) and the expe dose rate (R/hr) are also calculated and displayed.

6.1.1.2 Nine Mile Point Unit 2 The procedure for each of the available release rate methods for Nine M Unit 2 is presented below.

GEh6 In the data entry screen, enter the time of reading in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format and pres

< ENTER >. Enter S for a stack reading or V for a vent reading and press < E Enter the monitor reading (uCi/sec) and press < ENTER >. Press <F9> to ca the release rate in Ci/s.

Noble Gas GRAB Sample In the data entry screen, enter the time of reading in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format and pr

< ENTER >. Enter S for a stack reading or V for a vent reading and press <

Enter the Noble Gas grab sample total reading (uCi/cc) and press < ENTE Review the default stack flow rate (kefm). Edit if necessary. Press <F9> to calculate the release rate in Ci/s.

O'V 1476- 90 i/ptstopman!OPMANR l'O. DOC Page 6-10 EDAMS t

Back Calculation In the data entry screen, enter the time of reading in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format and

< ENTER >. Enter the code for the appropriate accident type and press <

Enter the wind speed (mph) and press < ENTER >. Enter E for an elevated Enter the stability class (A G for a ground level release and press < ENTER >.

Enter the three foot, closed window gamma through G) and press < ENTER >.

reading (mR/hr) and press < ENTER >. Enter the distance (in miles) and press < ENTER >. Press <F9> to calculate the release rate in Ci/s.

USAR This option displays a list of default total isotope release intes (Ci/s accident type. There are no values to enter or calculate.

Containment High Range Monitor In the data entry screen, enter the containment radiation monitor ID and

< ENTER >. Enter the time of reading in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format and press <

the date of the reading and press < ENTER >. Enter the time of shutdo hour format and press < ENTER >, then the date of shutdown and pre Enter the radiation monitor r-ading (R/hr) and press < ENTER >. Revi flow rate (kefm). Edit if necessary. Press <F9) to calculate the releas The concentration of radioactivity expected in containment (Ci/cc) a dose rate (R/hr) are also calculated and displayed.

6.1.1.3 James A. Fittpatrick The procedure for each of the available release rate methods fo is presented below.

EPIC When EPIC is selected from the Release Rate Calculation Menu, a s displayed in which the user selects the particular EPIC monitor is made, the data entry screen is displayed. Enter the time of the rea format and press < ENTER >. Enter the monitor reading (in eps, cp depending on which EPIC monitor is selected) and press < EN default calibration factor, the normal flow rate (cfm) and the default stac (cfm). Edit these if necessary. Press <F9> to calculate the releas

< ESC > to return to the EPIC Monitor Menu. Either select another monit

< ESC > to return to the Release Rate Calculation Menu.

O i476-90itptsiopman'OPMANRVO. DOC Page 6-1i EDAMS

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l Teletector in the data entry screen, enter the time of reading in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format and press

< ENTER >. Enter the monitor reading (mR/hr) and press < ENTER >. Review the default calibration factor (uCi/cc/mR/hr) and the default stack flow ra these if necessary. Press <F9> to calculate the release rate in Ci/s.

Noble Gas GRAB Sanple In the data entry screen, enter the time of reading in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format and press

< ENTER >.

Enter the Noble Gas grab sample total reading (uCi/ce) and press

< ENTER >. Review the default stack flow rate (cfm). Edit if necessary. Press <F9>

to calculate the release rate in Ci/s.

BackCalculation In the data entry screen, enter the time of reading in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format and press

< ENTER >. Enter the code for the appropriate accident type and press < ENTEi Enter the wind speed (mph) and press < ENTER >. Enter E for an elevated releas Enter the stability class (A G for a ground level release and press < ENTER >.

through G) and press < ENTER >. Enter the three foot, closed window pmma l

reading (mR/hr) and press <ENER>. Enter the distance (in miles) for the l  ;

and press <ENER>. Press <F9> to calculate the release rate in Ci/s.  !

FSAR .

This option displays a list of default total isotope release rates (Ci/s) fo accident type. There are no values to enter or calculate.

Containment High Range Monitor In the data entry screen, enter the containment radiation monitor ID and p

< ENTER >. Enter the time of reading in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format and press < EN the date of the reading and press < ENTER >. Enter the time of shutdow hour format and press < ENTER >, then the date of shutdown and pres

) Enter the contamment monitor average value (R/hr) and press < ENTE f

the default flow rate (cfm). Edit if necessary. Press <F9> to calculate the rate in Ci/s.

6.1.2 Protective Action Recommendations Selecting this option from the EDAMS' Menu provides a user the opp review plant specific protective action recommendations. From the m

( Figure 6 8, the user selects from one of two options.

M6-MiptstopmaWOPMANRl'O. DOC Page 6-12 EDAMS

If General Emergency in Progress is selected from the menu, the following messa "These PARS must be transmitted to the State and County within 15 g is displayed: W minutes of the declaration of a General Emergency! Press any key to procee user is then presented with a data entry screen prompting for a wind directi whether there is a lake breeze. See Figure 6-9. Enter the wind direction (in deg and press < ENTER >. Enter Y if there is a lake breeze or N if there is n breeze. Press < ENTER >. Press <F9> and EDAMS displays the ERPAs to evacuate and those to shelter. The user may press <F5> to print a report or GSC> to return to the PAR menu. A reminder is displayed stating that the PARS mustle tran to the State and County within 15 minutes of declaration.

If Other Emergency in Progress is selected, the EDAMS provides the followi message "See Protective Action Recommendations Procedures". Press a proceed. EDAMS returns to the protective action recommendations menu.

6.1.3 RASCAL If this option is selected, a branch is provided to a dummy screen whiI designed) returns a user to the EDAMS' Menu. Routines to conduct will be developed and installed by NMPC/NYPA.

6.1.4 Field Team Calculations If this option is selected, a sub-menu is displayed from which the user Field Team Calculations or Emergency Worker Doses. A branch is provide dummy screen (as currently designed) which retums a user to the EDAM Routines to conduct these applications will be developed and installed b ,

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- DAMS:/GDERAL DIERGDiCY DifER THE FDIl0 WING INFORMATION :

Wind Direction from (degrees)

Is a IAE BREEZE possible (Y/H)? H EUACUATE the following ERPAs:

1,2,3,5,6,9, ,

l 10,11,12,26,27

4. 7. 8. 13. 14. 1s.

satttti it re i s a taras:

O 16,17,18,19,20,21, ZZ,Z3,24,25,28,29 E. M ._ M .._..._ N _.

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O 1476 901/ptstopman!OPMANEWo. DOC Page 6-15 EDAMS

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6.2 Login Selecting this icon from the EDAMS' program group allows a user to log into the MMS resident on the NMP MicroVAX. Access through either a direct line or modem is available from a menu selection (see Figure 6-10). To connect with a modem, there are two options:

(1) Automatic dial-in where the systems attempts to connect using a series of four preset phone numbers defined in the EDAMS.INI file (Section 2.4). If the first number is unavailable, the next one tried. etc.

(2) Manual dial-in where a pop-up list of phone numbers is displayed (see Figure 6-10a). The user clicks on which phone number to dial.

After connecting and logging in to the MMS, the model downloads the current 15-minute data file and the 24-hour historical data file. This may take a few minutes, j but the data will be readily available for Raddose V. This option must be selected before the user is able to access automatic meteorological data from the MMS for use in the Emergency Met Report, MetVAX Terminal or Raddose-V programs.

l l:- Di .ct conn.ct in u.t D ia . - . - - .

i Automatic DiaHn le Wet Data Wanoel DiaHn to Wet Data Netwurk Camnection to Met Date nun m Drill Data Madr-Do NOT Login (Wenuel Wet Mode) and Eoit Figure 6-10: Login Menu Selection User Inter) ace-l2 % Page 6-l6 nmpc\raJJuw;286Copman DPAfANRI*H

T v

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Codes 1: 2588 'OK (M 1gn c e.

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Concel Codes 4: 1898 C.4 e 23s2 C ded:2s23 Codem7: 4020 -

• Cedsas- 4 30 Do NOT Logni[Wanual Wst Nede) and Esk Figure 6-10a: Manual Dial-in Pop-up Menu O

O Page 6-l' nmpc traddose .:b 6Dopman ( JPA I.4 NR I 1)

Uwr Imerface-1: yh

6.3 Ifistoric Meteorology (MetVAX Terminal leon)

When this icon is selected, the model provides access to the MMS. EDAMS will emulate a terminal and allow users the ability to access historic 15-minute average data on the MMS. Once the user ties into the MMS under this application, the EDAMS user has the opportunity to rnove within the existing design of the MMS. l When the user is finished, type LOGOUT < ENTER > to quit the option. Click the l command button at the bottom of the screen to return to the EDAMS' program l

group. (See Figure 6-10b)

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Figure 6-10b: MetVAX Terminal Screen l'agc 6-18 nmpc ,radJose ..'b6C ,opman DP A fA NR l 'O 5cr interface-i.MS

~6.4 Current Meteorology (Emergency Met Report leon)

When this icon is selected from the EDAMS' program group, a tabular summary of O  :

the most recent available 15-minute average meteorological data is displayed on the screen (see Figure 6-11). This data is taken directly from a file on the MMS, which contains the most recent 15-minute meteorological data. The preferred data displayed is for the main NMP tower, and is shown in yellow. If data from the preferred location is not available, other data is substituted. A legend at the bottom of the screen shows the color coding for the data substitution. This Emergency Met Report Screen may be printed or the user may print Part 1 of the NYS Notification Form from this screen.

The Emergency Met Report automatically requires the MMS for new data. The system checks for whether there should be new data every 30 seconds. If new data (i.e.15 minutes has passed) should be available, the system downloads the current 15-minute data file. If the data is new, the program beeps and displays the new data.

The user may disable the automatic requery by clicking the option buttons on the screen. By default, this option is enabled. Note: For this option to function properly, the date and time of the computer must correspond to the date and time of the MMS.

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31 7 (deg i l l'ecuperatum (IS mm) D 09 Iml ltr An I rmersaluer i n..n o fontenuous Neuvery? Peelessed Data I;a l up Iwta OI naided 3 Des. stand Figure 6-11: 15-Minute Average Meteorological Data O

Page 6-19 nrnpc \radJose t2hM nopman \0PMA NR l 'O User Interface-12'9N

6.5 Raddose-V Dose Assessment Model Selecting the Raddose V icon for the appropriate plant / unit from the EDAMS' program group invokes the Raddose-V dose assessment model. Instructions for running Raddose-V are detailed below in Section 7.

6.6 Logoff Selecting this icon from the EDAMS' program group logs out of the MMS system.

Connection to the MMS is lost.

6.7 Ingestion Pathway / Environmental Analysis When the user selects the Ingestion Pathway icon from the EDAMS' program group.

the Title Screen (see Figure 6-12) is displayed. Click Continue and the Main Menu is displayed.

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and New York Pown s Authorsty r___.__

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Figure 6-12: Ingestion Pathway Title Screen i

l Page 6 20 nmpctraJJose36C,opmanDPMANRI'0 ther interface-129s

6. 7.1 Alain hienu When the Main Menu is displayed, the user is presented with a list of sample types to evaluate (Soil (Milk), Milk, Forage (Milk), Produce, Leafy Vegetables, Water and Soil (Relocation)). The user may evaluate a new sample, edit or view a previous sample or exit. The Main Menu is presented in Figure 6-13.

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Figure 6-13: Ingestion Pathway Main Menu

6. 7.1.1 Evaluate a New Sample When the user selects a sample type and then clicks OK, the Sample Analysis screen is displayed. From here, the user enters the laboratory analysis results (see Section 6.7.2 below).

O Page 6-2I nmpc raJJme'.2h647mpman OPM.4NRl'a UserInterface-12 98

6. 7.1.2 Load a Previous Sample When the user selects a sample type and then clicks Previous Sample, a pop-up box is displayed listing files for that sample type. Click on the file name and then OK.

The Sample Analysis screen is displayed with the previous data filled in. If the user clicks Cancel from the pop-up box, the Main Menu is displayed. Figure 6-14 shows the Previous Sample pop-up box.

In estion Pathway Main Menu **

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Figure 6-14: Ingestion rathway Previous Sample Pop-up Box Page 6-22 nmpt sraJJosci2 h M 7,opmun \0P A fA NR I TI lher interface.12%

6. 7.2 Sample Analysis This screen is displayed when the user selects to enter a new sample ana'ysis or to edit or view a previous sample analysis. The top part of the screen allows the user to enter descriptive information on the sample of interest. The bottom part of the screen provides for the entry of isotopic data. The isotopes vary depending on the type of sample selected (based on isotopes contained in reference documents). See Figure 6-15 for an example.

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Figure 6-15: Ingestion Pathway Sample Analysis Screen The user must Gil in the sample ID number (the 6rst eight characters of the sample ID # becomes the file name), the sample location, a sample description. the collection date and collection time. Enter each sample concentration by isotope.

When Onished, click the Calculate button. The calculations are automatically saved.

If the Gle already exists, a warning message is displayed prompting the user whether to overwrite the previous calculations. Click yes to calculate and overwrite and no to return to data entry.

The isotopic concentrations are compared to derived response levels (DRLs) to determine if preventatise or emergency PAGs are exceeded. Similarly, the soil (relocation) isotopic concentrations are multiplied by consersion factors and summed to determine if the Grst year relocation PAG is exceeded. A PAG message Page 6 23 nmpctraJJose.286C.opman GPAfANRl'O Her Imcr1 ace-1.' ys

appears after calculations are complete to alert the user of the result.

Click OK to remove the message.

To view results, either from a , ample evaluation just calculated or from a previously evaluated sample, click the View Results button. The Results Screen is displayed (see Section 6.7.3 below).

To return to the Main Menu, click the appropriate button,

6. 7.3 Results The Results Screens display the results of calculations and the information entered by the user. The screens also ccntain a Print button to output the current information on the screen to the printer and buttons to return to the Sample Analysis screen or the I Main Menu. Some sample types contain more than one page of data and use the Next Page and Previous Page buttons. Note: the Print button p_nly prints the data on the screen displayed. Appendix B contains sample reports.

Different population groups and duration of interest are provided for each sample '

type based on the information contained in the reference documents. The values are displayed in red and are flagged with a double asterisk, "**", if they exceed the emergency limit and are displayed in yellow with a single asterisk. "*". if they exceed the preventative limit. See Figure 6-16. The following sections describe the Results Screen for the various sample types.

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i Page 6-24 nmpc \raddoseC 8647 mpman D P At 4 NR l *0 User interface.1 %

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Figure 6-16: Ingestion Pathway Results Screen

6. 7.3.1 Soil (MilkI, Milk, and Forage (Milk)

The results provided for Soil (Milk), Milk, and Forage (Milk) are the percent derived preventative response levels (DRL) for adult and child by each isotope.

6.~.3.2 Produce end Lea & l'e.getables l The results provided for Produce and Leafy Vegetables are the short-term (30 days) and long-term (one year) percent DRLs for adult, teen, and child. Use the scroll bar to view values not visible on the screen.

6. 7.3. 3 Water Click the Next or The results provided for Water are contained on two pages.

Previous Page button, as appropriate. Page one provides short-term (30 days) percent DRLs for adult. teen, child, and infant. Page two provides long-term (one y ear) values. Use the scroll bars to view values not visible on the screen.

O Page 6 25 nmpc\raJJosc:2^6&opmari UPAIA NRI'u Der Interface-12 vs

6.7.3.4 Soil (Relocation)

For the Soil (Relocation) samples, the 1,2, and 50 year dose determinations are made with values exceeding PAG limits noted. The relocation PAG pop-up box is shown only if the year ; dose exceeds 2 rem. The initial 1 meter exposure rate corresponding to the sample is also provided. The next two pages, accessed by clicking on the Previous and Next Page buttons, identify the isotopic concentration.

initial exposure rate, and integrated dose needed to exceed each of the 1. 2. and 50 year dose limits. Assuming a constant isotopic mix, the initial exposure rate can be used as a guideline in the field for identifying areas which exceed the limits.

The scroll bars can be used to view values not visible on the screen. See Figure 6-17.

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Figure 6-17: Ingestion Pathway Soil (Relocation) Results Screen Pagc 6 26 nmpcvaJJose;286hpman UPMANRi'O User Interface-t: n

6.8 Defaults Program To edit default values for Raddose-V (accident isotope inventories, dose conversion factors, ingestion pathway factors, etc.), click on the Defaults icon from the EDAMS program group. The Title Screen is displayed (see Figure 6-18). Click Continue and a pop-up password box is displayed. Enter the password and press < ENTER > or click OK. If the password is entered correctly, the Plant / Unit Selection Screen is displayed. See Figure 6-19.

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and Ne w York Power Authnrety ' ~

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Figure 6-18: Defaults Database Modification Program Title Screen i

O rsmpc .raJJose .28M " iopman 4 H'A IA NR I '0 Uwr Interface-l: VA Pa.cc 6 27

i Once the user chooses the plant site / unit, the Main Menu is displayed. See Figure 6-20.

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Figure 6-19: Defaults Plant / Unit Selection Screen Page (>.28 nmperadJoset2hM7,opman UPMANRl'0 L'scr Interface-12 ys

l From the Main Menu, the user can select what information to view or edit. Click on the appropriate command button and the data is displayed.

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~ SenosalEmmsgency ERPAs for a Lake Breese ledine Nethods A~h inventeries . - IP: Se5 fMR) DRL

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Figure 6-20: Defaults Main Menu O

Page 6-29 nmpe radJos e',2b 6Dopman \ 0 Ph fA NR l '0 L ser Imerface-l? 98

Figure 6-21 shows a sample screen. A qualified user can edit this information. l Initially the data is displayed in cyan. If the user changes a value, the color changes l to red. When the user moves the highlight to another row, either by clicking on another row or by using the arrow keys, the value that was modified changes back to When j cyan and the database file containing this data is automatically updated.

finished editing or viewing the data on the screen, click Done to return to the Main Meau.

Itaddose V .lAl . Drlault inventuries . .. .. ....... ...

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.: :.:.:.:.s Figure 6-21: Raddose-V Default Accident Inventories Screen l'a.ce 6-30 nmpe ;raJJosci286.I " .opman Dl'M:l NR I '0 Der Imerlace-l.' VS

6.9 NewPassword Program To change the password for the Defaults program, click on the New Password icon O

from the EDAMS' program group. The Title Screen is displayed (see Figure 6-22).

Click Continue and a pop-up box is displayed prompting for the current password.

See Figure 6-23.

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D W dk Purnt Unet ? and James A i st/ patrick E g9g) g Niesgera Mohawk Power Corporateon and Now York Power Authunty Og.psaght to)1 och I cced 39E 3s Figure 6-22: NewPass Title Screen O

Page 6 31 nmpc ,raddose .2862 .opman DP A I.4 NR l 'a L'scr truerface 12 W

Type the current password for the program and press < ENTER > or click OK. Click cancel to abort the process.

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. I.apynght lcj I adh i erAi 1996 Sie Figure 6-23: Current Password Pop-up Box l

L%er Interface 12 ys Page 6-32 nmpc\radJuwi:8647ropmanDPAfANRl'U

If the current password was entered correctly, another pop-up is displayed prompting for a new password. See Figure 6-24. Enter a new password in the pop-up box and press < ENTER > or click OK. The program prompts the user to enter the new password again to confirm it. Ifit is entered correctly, the password is changed and the user is returned to the EDAMS Program Group. If the new password is not confirmed, the program warns the user and displays the new password pop-up box allowing the user to try again.

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. y Figure 6-24: New Password Pop-up Box if the current password was incorrect, an error message is displayed if the current password is not correctly entered in three attempts, the program warns the user and exits to Windows.

6.10 Make Maps Program This utility program is discussed in Section 7.6.

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7. RADDOSE-V To run the dose assessment model, Raddose-V, click on the icon for the appropriate unit (i.e., NMP1, NMP2 or JAF). The Title Screen is displayed (see Figure 7-1).

Click the Continue button. If the user has not logged into the MMS for automatic meteorological data using the Login icon in the EDAMS Program Group Raddose-V warns the user that all meteorological data must be entered manually. The user may click Exit to return to the EDAMS Program Group and log into the MMS or click Continue to run Raddose-V in manual mode. If the user clicks Continue, the Start-Up Menu is displayed.

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7.1 Start-Up Menu The Stan-Up Memr(see Figure 7-2) provides the user with the options of startin new scenario, with or without saving the data from the previously run accident; continuing with an accident that has been previously defined and is resident in hard drive; restoring a previous incident to the hard drive; or exiting Raddose-V, L :iddeur V ' Start Up Menu . d

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Figure 7-2: Raddose-V Start-Up Screen 7.1.1 Begin NewIncident When the Start-Up Menu is displayed, the option for starting a new incident highlighted. If a new accident b being assessed, select this option to b program. A pop-up warning message indicates that all previous data previous accident (currently resident on the hard drive) will be delet is to be cleared, click the Yes button and continue to the Accident Definition S (see Section 7.2). If the data should not be erased, click the No button message is removed and the Stan-Up Menu is accessible again to save elsewhere (see Section 7.1.3 below).

O 1476- 90 lip:sfopman' OPAL 4NR l 'O. DOC Page 7-2 Raddose-l'

7.1.2 Continue With Previous incident To continue entering data and assessing an accident started previously and currently resident on the hard drive, select the " Continue Previous incident" option. A screen displaying the previous accident definition data is displayed. A sample of the screen is presented in Figure 7-3. It lists the trip date and time, the release date and time, whether a General Emergency has been declared, and the initials of the operator who executed the previous run. Click the Continue button to proceed with this incident.

At this point, the Main Menu is displayed. See Section 73 below.

O Figure 7-3: Raddose-V Continue Previous incident Screen O

Page 7-3 1476-90liptst opm a n'OPMA NR l 'O. DOC Raddose l'

7.1.3 Save Data to Disk If existing data on the local hard drive is to be saved to a floppy disk or to another location on the hard drive, select the "Save Data to Disk" option. The files dialog (discussed in Section 5.1 and shown in Figure 7-4) is displayed. Select drive an directory to save the files and click the OK button. Raddose-V copies the files an informs the user when the transfer is complete.

7.1.4 LoadData From Disk If needed data exists on floppy disks or in another location on the hard drive, select the " Load Data from Disk" option. The files dialog box (discussed in Section 5.1 and shown in Figure 7-4) is displayed. Select the drive and/or directory to load the f

data from and click the OK button. Raddose-V loads the data as the Raddose-V files on the local hard drive and informs the user when fin Continue Previous incident to run the re-loaded scenario.

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1476- 901/ptsiopman'OPMA NR l 'O. DOC Page 7-4 Raddose-l'

7.2 Accident Scenario Definition Following selection of the Begin New Incident" option, the Accident Scenario Definition Screen is displayed. The current date and time from the computer are entered as the reactor trip and release dates and times. Edit these if necessary in 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> format. Edit, if necessary, the lake surface temperature (degrees F) for the current date. Entry of the present operator's initials is mandatory before continuing.

Default values are shown in cyan while user entered values are shown in yellow.

Click the The Accident Scenario Definition Screen is presented in Figure 7-5.

If the Cancel Accept button to accept this data and proceed to the next screen.

button is clicked, the user is returned to the Start-Up Menu (Section 7.1).

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Figure 7-5: Raddose-V Accident Scenario Definition Screen 1476-90liptstopmaWOPMANRl'O. DOC Page 7-5 Raddose-l*

7.3 Main Menu Raddose-V's Main Menu provides the operator with the options of entering and editing source term data, entering and editing elevated and ground menu, level meteorological data, performing calculations, returning to the output performing a forecast, or returning to the start-up menu. These options are in the following sub-sections. The Main Menu is presented in Figure 7-6.

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1476- 901/ pts 'opman'OPA fANR l'O. DOC Page 7-6 Raddose-l*

7.3.1 Source Term Data Entry Each advection step of the Source Term Data entry screen (see Figure 7 7) displays the step number, the clock time of the step, the path number, data entry fields for three release pathways, and a total" line where the combined results are displayed.

Each pathway has data entry fields for accicient type; flow rate; the method of determining the total isotope release rate, monitor or grab sample reading, and release rate; and the method of determining the iodine release rate, monitor or grab samph reading, and release rate. (Accident types and monitor types are discussed greater detail below). The path data column also indicates whether the release for the pathway is elevated (yellow color coding with letter E inserted) or ground leve (green color coding with the letter G inserted). Every data field will not necessaril be filled for every method selected. Some methods display a calibration factor pop-up box (see Figure 7-8). 'Ihe user should make certain data is being entered in th proper release pathsvay. Data may be entered for any one release pathway or any combination of two or three pathways. These may be accepted or overwritten. Note the field specific help line at the bottom of the screen. The help line displays a description of what should be entered in the current field. Any units or default values for the field are also displayed.

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i DeutAr risch es peru f 1.to scacci susemic gas seicair meethod "F @S.'d E.s YDr-Figure 7-8: Raddose-V Sample Calibration Factor Pop-Up Screen 7.3.1.] Accident Types For a particular release pathway, move the cursor to the appropriately labele field and press <F2> or double click on the field to display the Accident Menu.

Move the cursor to the accident type to be selected and press < ENTER > or dou click. If a new selection is being made for a release pathway in which an accident has been previously selected, a warning prompt is displayed asking the use the accident type change. Click the Yes or No button. If Yes is selected (the accident type is changed), all other data previously defined for the pathway is deleted. The program returns to the source term data entry screen with the se accident entered in the data field and the cursor moved Next, to the No is selected, the accident type and associated data remain unchanged.

Raddose V prompts if the release is elevated. Click Yes or No. This determine which meteorological data to use for the calculations. A sample accident menu fo each plant / uni' .s presented in Figures 7-9,7-10 and 7-11.

O Page 7-8 1476-90liptsiopmaWOPMANRVO. DOC RaNiose-V

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p2-d @Md Ngd lWE$ ' 1'.M Figure 7-9: Raddose-V NMP1 Accident Menu The accident types available for a release from Nine Mile Point Unit I are the following:

CDBA - Containment Design Basis Accident CRD - Control Rod Drop RFA- Refueling Accident SLB - Steam Line Break LOCA - Loss of Coolant Accident SAST - Severe Accident Source Term USER-User-Defined Accident NONE- Clears Line of All Data 1476- 901tpts topman'OPh l4NR i 'O. DOC Page 7-9 Raddose l*

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Figure 7-10: Raddose-V NMP2 Accident Menu The accident types available for a release from Nine Mile Point Unit 2 are the following:

CDBA - Containment Design Basis Accidem CRD - Control Rod Drop RFA - Refbeling Accident SLB - Steam Line Break LOCA- Loss of Coolant Accident SAST- Severe Accident Source Term USER- User-Defined Accident RGWSL - Radioactive Gas Waste System Leak ILF -Instmment Line Failure FCD - Fuel Cask Drop NONE - Clears Line of All Data O

1476-90ltptsi opm an' OPAL 4 NR l *0. DOC Page 7-10 Raddose-l'

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- MGb NSWd LM$ l^0 Figure 7-11: Raddose-V JAF Accident Menu The accident types available for a release from James A. Fitzpatrick are the following:

CDBA - Containment Design Basis Accident CRD - Control Rod Drop RFA - Refueling Accident SLB1 - Steam Line Break (Steam Only)

LOCA - Loss of Coolant Accident SAST - Severe Accident Source Term USER-User-Defined Accident SLB2 - Steam Line Break (Two Phase)

NONE - Clears Line of All Data When the accident field is highlighted, a user may select the "AcciDescrip" butto the bottom of the Source Term Data Entry Screen and a pop-up box provides 1476-90lipts'opmaWOPMANRl'O. DOC Page 711 Raddose-l*

1

\

-I description of the accident type. Also, in the Accident Menu, the user may press

<F2> to display a description of the accident type.

Once an accident type is selected, the model initially uses the default isotopic distribution. A user may modify the isotopic distribution for this accident type by selecting the " Iso Distribution" button at the bottom of the Source Term Data Entry Screen when the accident fie:: is highlighted. This is discussed further in Section

)

7.3.1.4. 1 7.3.1.2 TotalIso: ope Release Rate Methods The method by which the total isotope release rate is determined is similar to the entry of the accident type. Pmss <F2> while on the Total Method field or double cl;ck this field. The Total Release Rate Method Menu is displayed. Select the release rate method and press < ENTER > or double click. If a new selection is being made for a release pathway in which a total release rate method has been previously selected, a warning prompt is displayed asking the user to verify the method change.

Click Yes or No. If Yes is selected (the method is changed), all other data previously defined for the total release rate method in that pathway is deleted. T model returns to the data entry screen with the selection displayed in the method field. If No is selected, the previously defined method remains unchanged. Data entry procedures for determining the total isotope release rate depend on the chosen. Some methods require the user to enter or edit additional information such as calibration factors. A pop-up box is displayed for this information. CI'.ek the OK button when done to accept the values and return to the Source Terrr. Data Entry screen. Directives for each method are presented below.

7.3.1.2.1 Nine Mile Point Unit 1 The Total Release Rate Method Menu for Nine Mile Point Unit 1 is presented in l l

Figure 7-12.

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Page 7-12 1476-9011ptstopman'OPMANRVO. DOC Raddose.y

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Figure 712: Raddose-V NMP1 Total Release Rate Method Menu OG78-OGESMS-7 or 8 When OG78 is entered, a pop-up box displaying the default calibration factor (uCi/cc/ cpm) is displayed. Edit as necessary; when finished click OK. Enter the reading (cpm) in the monitor reading field and press < ENTER >. The cursor then moves to the flow rate field. Enter the stack flow rate (kcfm) and press < ENTER >.

Note that the defauit stack flow rate is shown on the help line. The release rate is automatically calculated in Ci/s.

OG10-OGESMS-10a or 10b When OG10 is entered, a pop.up box displaying the default calibratic;i factor (uCi/cc/ cps) is displayed. Edit as necessary; when finished click OK. Enter the reading (eps)in the monitor reading field and press < ENTER >. The cursor moves to the flow rate field. Enter the stack flow rate (kefm) and press < ENTER >. Note that the default stack flow rate is shown on the help line. The release rate is automatically calculated in Ci/s.

RAGEM.RAGEMS Enter the When RAGEM is entered, the calibration pop-up box is displayed.

Enter the process computer calibration factor (uCi/cc/ cps) and press < ENTER >.

Page 713 1476 90liptstopman'OPM4NRI'O. DOC Raddose-l'

dilution factor and press < ENTER >. Click OK when done. Enter the reading (eps) in the monitor reading field and press < ENTER > The cursor moves to the flow rate field. Enter the stack flow rate (kefm) and press < ENTER >. Note that the defau stack flow rate is shown on the help line. The release rate is automatically calculated in Ci/s.

GRAB- GRAB Sample Selection of " GRAB" displays the Isotope Screen.

The screen contains a list of Enter the concentration (gCi/cc) of each isotopes followed by data entry fields.

isotope present in the efnuent based on the grab-sample analysis. (The Isotop Screen is presented in Figure 7-13). Click the OK button to accept the isotopj and return to the data entry screen. The total concentration (gCi/ce) of the isotope entered are displayed in the monitor fields. Enter the efHuent flow rate in kefm Both total press < ENTER >. The program calculates the release rates in Ci/s. Note:

and iodine method data and release rates are displayed after the calculation.

Particulate release rates are not shown on the screen outputs but are tracked If a j internally by the program for calculation of dose rates and deposition data.

GRAB sample analysis was previously defined, the individual concentrations w displayed except for the step where the GRAB is initially defined.

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Raddose '/ NMP1 GRAB Sample Screen O

Page 7-14 1476-90llptslopmaWOPMANRl'O. DOC Raddose-l'

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If the USER Accident type is selected, GRAB sample data is entered into the isotope O Screen in uCi/s for each isotope, no flow rate is necessary. Once GRAB sample data is accepted (click OK), the model converts the release rates to Ci/s and displays these values in the total and iodine release rate fields.

BACK-Back Calculation When BACK is selected, a pop-up box is displayed requesting information on the field data. Enter the field measurement (mR/hr) and press < ENTER >. Enter the distance (in miles) and bearmg (degrees) for the reading and press < ENTER > for each. Click OK when finished to return to the source term screen. The release rate is automatically calculated in Ci/s. Note: BACK calculation may not be used on Step 1.

TELET- Teletector When TELET is entered, the calibration pop-up box is displayed. Enter / edit the default calibration factor (uCi/cc/mR/hr). When finished click OK. The Enter the monitor reading (mR/hr) in the monitor reading field and press < ENTER >.

cursor moves to the flow rate field. Enter the stack flow rate (kefm) and press j

< ENTER >. Note that the default stack flow rate is shown on the help line. The release rate is automatically calculated in Ci/s.

/

FSAR- Default Release Rate - FSAR An accident specific default release rate (Ci/s) based on the accident type is l

' automatically displayed for both the total release and iodines.

l Note: If a user specified isotopic inventory exists, a warning prompt is displayed asking the user to verify that the distribution should be changed back to the defa inventory. Click Yes or No. If Yes is selected, the default inventory is used and the default release rates are displayed. If No is selected, the user specified inventory remains in effect and the user is allowed to enter another release method.

CHRM- Containment High Range Monitor in the monitor reading field, enter the radiation monitor reading (R/hr) and press

< ENTER >. The cursor moves to the flow rate field. Enter the flow press < ENTER >. Note that the default stack flow rate is shown on the help The release rate is automatically calculated in Ci/s.

t DRECT- Direct input ofRelease Rate Enter the total release rate in Ci/s directly into the release rate field.

Page 7-13 1476-90liptstopmaWOPMANRVO. DOC Raddose.V

SAST-Severe Acciderst Source Term When accident type and method is entered as SAST, the Severe Accident Source Term pop-up box is displayed. (The SAST Screen is presented in Figure 7-14.)

Move to the different fields using the Tab key (and arrow keys) or clicking on a selection. Enter the appropriate data for each of the fields: Leak Rate, Hold-up Time, Filters Status, and Sprays Status. Click OK to accept the selections and return to the source term screen. The program calculates the release rates in Ci/s. Note:

Both total and iodine release rates are displayed after this calculation.

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' 4[:; .s j er .t P ' p sa l' W'.

t 't e -a .-

• Or t af . i: i In, Deutdr dast es pects f 2 to select an amdesst appe for Hee pathanap

~ FFw"3-n_ r.

Figure 7-14: Raddose-V NMPI SAST Screen O

1476-901/ptsiopmaWOPM4NRl'O. DOC Page 7-16 Raddose-l*

7.3.1.2.2 Nine Mile Point Unit 2 The Total Release Rate Method Menu for Nine Mile Point Unit 2 is presented in Figure 7-15.

54addesr V : 1 ource Irrm Data f ntry ]

l HMt1 NWl';'

Ul">v/ L ..

I"W I hde h.dene lici Adv '.scs. Ac ident -

N ..ne er ,

l epe- E hneHeer Method H r .sdw ay ff Wrthud M ornine llatr U i/4

'.. t em l eone P<seh UU (*e i 4H A A . fF +0? f.tHiW 1 UDi .10 1 W .OJ Itc iltj 4 %) 04 r 4 di IH il ' . . . . . . . . . . . ...i.. ...... . . . . . . . . . . . , , . . . . .

. g,,,.

,' tesnr "-***'-"*"***.******- * * * * * -

Ahtuc, Dese ngshon unsts 6 fil us ./ t

-' "P C y t;, M',

u; .fn

'I

• DIi i . . tu . i,. at. *. upk I ttiw4st tm.t w -

(+.rcu 6ngur of 6.c6 row h dr ( ./ 3 JJ. Li IP.M; bef ..a5 C k . se- L aer U ../ H 12/r 1 on. s na,e n' l$a;t hanig M i r . ui 1. /tw i Hs!N n.1; tt..

I' /.I l i; ach (_41'.ul.ste

• h s

• melect e asethod any psessang (4 H Il H > er stundde W ,

~? w .

}M ' WmW Figure 7-15: Raddose-V NMP2 Total Release Rate Method Menu GEAG When GEMS is selected, enter the monitor reading (uCi/sec) in the monitor reading field and press < ENTER >. *Ihe release rate is automatically converted to Ci/s.

GMB- GMB Sample Selection of " GRAB" displays the Isotope Screen. The screen contains a list of isotopes followed by data entry fields. Enter the concentration (pCi/cc) of each isotope present in the effluent based on the grab-sample analysis. (The isotope Screen is presented in Figure 7-16). Click OK to accept the isotope data and retum to the data entry screen. The total concentration (pCi/cc) of the isotopes and iodines entered are displayed in the monitor fields. Enter the effluent flow rate in kefm and Both total press < ENTER >. The program calculates the release rates in Ci/s. Note:

and iodine method data and release rates are displayed after the calculation.

Particulate release rates are not shown on the screen outputs but are tracked internally by the program for calculation of dose rates and deposition data.

If a l

l Page 717 1476- 90 liptsiopman'OPMA NR l 'O. DOC Roddose l'

.I GRAB sample analysis was previously defined, the individual concentrations will be displayed except for the step where the GRAB is initially defined.

u nw .-

-nma 1.,,

.a. g.aq ,

' e es, 1., >

~ - .. -

av ,

i

) ,

4

-  ?

~ . , ,, w I  : ,,,

I '

o. . . . . . .

s l

.. 7,

. .: t, e .,

.,\w ~..' 3 I l I) y m

4 . lM d l 1

N A

( .Q1 .

Figure 7-16: Raddose-V NMP2 GRAB Sample Screen if the USER Accident type is selected, GRAB sample data is entered into the isotope Screen in uCi/s for each isotope, no flow rate is necessary. Once GRAB sample data is accepted (click OK) the model converts the release rates to Ci/s and displays these values in the total and iodine release rate fields.

BACK- Back Calculation When BACK is selected, a pop-up box is displayed requesting information on the field data. Enter the field measurement (mR/hr) and press < ENTER >. Enter the distance (in miles) and bearing (degrees) for the reading and press < ENTER > for each. Click OK when finished to retum to the source term screen. The release is automatically calculated in Ci/s. Note: BACK calculation may not be used on Step 1.

USAR - Default Release Rate An accident specific default release rate (Ci/s) based on the accident type is automatically displayed for the both the total release and iodines.

O a ,. ene n,, 1 .n,,,,..,-oe- noc

c-1 i

Note: If a user specified isotopic inventory exists, a warning prompt is displayed asking the user to verify that the distribution should be change! back to the default inventory. Click Yes or No. If Yes is selected, the default inventory is used and the default release rates are displayed. If No is selected, the user specified inventory remains in effect and the user is allowed to enter another release method.

CHRM- Containment High Range Monitor in the monitor reading field, enter the radiation monitor reading (R/hr) and press

! < ENTER >. The cursor moves to the flow rate field. Enter the flow rate press < ENTER >. Note that the default stack flow rate is shown on the help lin The release rate is automatically calculated in Ci/s.

DRECT-Directinput ofRelease Rate Enter the total release rate in Ci/s directly into the release rate field.

lO  !

1 1

l i

I l

l t

O s 1476-90Hptslopman'OPMANRVO. DOC Page 7-19 Raddose.y i-

-l l

-1 SAST- Severe Accident Source Term Whm accident type or method is entered as SAST, the Severe Accident Source 9l l

Term r op-up box is displayed. (The SAST Screen is presented in Figure 7-17.) .

Move to the different fields using the Tab key (and arrow keys) or clicking on a selection. Enter the appropriate data for each of the fields: Leak Rate, Hold-up Time, Filters Status, and Sprays Status. Click OK to accept the selections and return to the source term screen. The program calculates the release rates in Ci/s. Note:

Both total and iodine release rates are displayed after this calculation. 1

_y g .;..( g.~_q

[ ;3 3 3 :. x s,M + a _

e-,4 rw , . ,

c.,.e ..m

'" i l e ..iirw- todern h e-I W ood os Ad, 'trp Ar i nier t w. .s.a wo, .. n ...r it., ;i T M" r ..n, i.,.- re o ., wrisoo i . . a.,,o

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, , . . . I:41u

. . o .,

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'u v" ..

rm Dender tied a psen F 2 to sricci an auudent type Joe the

~M- *5535*.

Figure 7-17: Raddose-V NMP2 SAST Screen l

1 l

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i i

I 1476- 901/ptsiopman'OPhfA NR VO. DOC  ?

Page 7 20 1 Raddose-V l J

7.3.1.2.3 James A Fit: patrick The Total Release Rate Method Menu for JAF is presented in Figure 7-18.

~

fladdoEr-V ' Sourcr $rren Data i ntry l I NYT*A JAf fMI%. la

'"**' d e .eter.e 4.whe fic.4 N .nsam 8 Adv "6+

- , As i nl+ ni '

• Methud M u,mtes h ei, H ./ d l ygn- l ooseh as, M,4hud h e deng

'a e-g , l en.* l'eth 5, , bl C ' Lt.llO ? DM D2 1 1Ci 03 1 Ir : e', 1[ [ DI:A 1 Cd .!f'. I. I t ' O 1 ' W . 51 1 - - ~ ~ t N .no

'.. 01 1 14 0L 11110 t I. .h. . . .. . .i. . 1 ',f i UJ p h ,1. 4 3 g,,

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> 02 2 o 3;,; ,,o.., ,, '

8t ' DH i ...: 1. l # h e'i .iz i I t ,an 1 '.. Alf t./-.

, , , #,-m ,,, i n e 4.,. c ,,...n ., e ,,,,

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t.e a .no

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ip

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i J

' cders e method by asses.ssng <f N1F H > es donhar r% Asia M E IIM$3 Figure 7-18: Raddose-V JAF Total Release Rate Method Menu TELET- Teletector When TELET is entered, the calibration pop-up box is displayed. Enter / edit the calibration factor (uCi/cc/mR/hr). When finished click OK. Enter the monitor The cursor reading (mR/hr) in the monitor reading field and press < ENTER >.

moves to the flow rate field. Enter the stack flow rate (cfm) and press < ENTER >.

The release rate is automatically calculated in Ci/s.

GRAB - GRAB Sample Selection of " GRAB" displays the isotope Screen. The screen contains a list of isotopes followed by data entry fields. Enter the concentration (gCi/cc) of each isotope present in the effluent based on the grab-sample analysis. (The Isotope Screen is presented in Figure 7-19). Click OK to accept the isotope data and return to the data entry screen. 7he total concentration (pCi/ce) of the isotopes entered are displayed in the monitor fields. Enter the effluent flow rate in efm and press Both total and

< ENTER >. The program calculates the release rates in Ci/s. Note:

iodine method data and release rates are displayed after the calculation. Particulate Page721 1476-901'Ptsiopman'OPMANRVO. DOC Raddose l'

release rates are not shown on the screen outputs but are tracked internally by If a GRAB sample program for calculation of dose rates and deposition data.

analysis was previously defined, the individual concentrations will be dis except for the step where the GRAB is initially defm' ed.

-y Ev> W x. g r_.: y e.,ns*

kg yu 3 ww,- ss.> % = scqrv.y 3. g:& R n , + ; .s ta s u ',a u h*' M (statJ hartspir I ntry di H i/rl Adv 'ob j

', te p lu r : ;,..

.*a  : c- -..

.' M

• 00

. , -; i , c, ~ . . . . _

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,:m 1 e .' -  :.

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. . . L; ;.

i 1 f 7.

d~

4 E.3 ,

~

g ff@i.jf.iffl.

Figure 7-19: Raddose-V JAF GRAB Sample Screen If the USER Accident type is selected, GRAB sample data is entered into the is Screen in uCi/s for each isotope, no flow rate is necessary. Once GRAB sam is accepted (click OK) the model converts the release rates to Ci/s and d values in the total and iodine release rate fields.

' BACK- back Calculation When BACK is selected, a pop-up box is displayed requesting information o field data. Enter the field measurement (mR/hr) and press < ENTER >. En distance (in miles) and bearing (degrees) for the reading and press < EN each. Click OK when f'mished to return to the source term scre is automatically calculated in Ci/s. Note: BACK calculation may not be use Step 1.

O 1476-90lipts i opmarv0PMA NR l 'O. DOC Page 7-:2 Raddose l*

e.

FSAR- Default Release Rate An accident specific default release rate (Ci/s) based on the accident type is antamatically displayed for both the total release and iodines.

Note: If a user specified isotopic inventory exists, a warning prompt is displayed ,

asking the user to verify that the distribution should be changed back to the defaul inventery. Click Yes or No. IfYes is selected, the default inventory is used and the default release rates are displayed. If No is selected, the user specified inventory remains in effect and the user is allowed to enter another release metho CHRM- Containment High Range Monitor in the monitor readmg field, enter the radiation monitor reading (R/hr) and press

< ENTER >. De cursor moves to the flow rate field. Enter the flow r press < ENTER >. The release rate is automatically calculated in Ci/s.

f STKLO-Stack Low Range- )

Enter the When STKLO is entered, the calibration pop-up box is displayed.

calibration factor (Ci/sec/ cps) and normal flow rate (cfm). Click OK when finished to return to the source term screen. In the monitor reading field, enter the monitor O reading (cps) and press < ENTER >. The cursor moves to the flow rate field. E the stack flow rate (cfm) and press < ENTER >. The release rate is automatically calculated in Ci/s. .

STKHI-Stack High Range When STKH1 is entered, the user must first identify the monitor number (6 or 7).

Then, the calibration pop-up box is displayed. Enter the calibration factor (Ci/sec/mR/hr) and normal flow rate (cfm). Click OK when source term screen. In the monitor reading field, enter the monitor reading (mR and press < ENTER >. De cursor moves to the flow rate field. Enter the s rate (cfm) and press < ENTER >. The release rate is automatically calcula EFFLO- Efluent Monitor Low Range 1 I

When EFFLO is entered, the user must first identify the monitor number (1-4).

Enter the calibration factor Then, the calibration pop-up box is displayed.

(Ci/sec/ cpm) and normal flow rate (cfm). Click OK when finished to re source term screen. In the monitor reading field, enter the monitor reading (

and press < ENTER >. The cursor moves to the flow rate field. Enter the (cfm) and press < ENTER >. The release rate is automatically calculate O

1476-901/ptslopman!OPMANRVO. DOC Page 7-23 Raddose-V l

EFFHI- E.[ fluent Monitor High Range When EFFH1 is entered, the user must first identify the monitor number (8 or 9).

Then, the calibration pop-up box is displayed. Enter the calibration factor (Ci/sec/mRihr) and normal flow rate (cfm). Click OK when finished to ret source tertn screen. In the monitor reading field, enter the monitor reading (mR/hr) and press < ENTER >. The cursor moves to the flow rate field. Enter the flow rate (cfm) and press < ENTER >. The release rate is automatically calculated in Ci/s.

DRECT- DirectInput ofRelease Rate Enter the total release rate in Ci/s directly into the release rate field.

SAST-Severe Accident Source Term When accident type and method is entered as SAST, the Severe Accident Source Term pop-up box is displayed. (The SAST Screen ir presented in Figure 7-20.)

Move to the different fields using the Tab key (and arrow keys) or clicking on a selection. Enter the appropriate data for each of the fields: Leak Rate, Hold-up Time, Filters Status, and Sprays Status. Click OK to accept the selections and retum to the source term screen. The program calculates *.he release rates in Ci/s. Note:

Both total and iodine release rates are displapd af*.er this calculation.

b-.- '

E. 1%G- ti's f*AJAl l ot 4 ,

p,,,,,,,,,

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w. etw yo,m, g y,, gjg I gowig aie y,tkuW 5,e .dn.g

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pg Figure 7-20: Raddose-V JAF SAST Screen Page 7 24 1476-90liptstopman'OPMANRVO. DOC Raddose-V

7.3.1.3 lodine Release Rate Methods The iodine release rate method is input to the Source Term Data Entry screen by This screen is making a selection from the Iodine Release Rate Method Menu.

accessed by moving to the Iodine Method field and pressing <F2> or double clicking on this field. If a new selection is being made for a release pathway in which an iodine release rate method has been previously selected, a pop-up box is displayed asking the user to verify the method change. Click Yes or No. If Yes is selected (the method is changed), all other data previously defined for the iodine release rate method in that pathway is deleted. The model returns to the data entry screen with the selection displayed in the method field. If No is selected, the method renv.ains unchanged. Data entry procedures for determining die iodine release rate depend on the method chosen. Directives for each method are presented below. The lodine Release Rate Method Menu is presented in Figure 7-21. (Because of similarities from one plant or unit to another, these are discussed as a common set of options.)

Haddo .c V : Source Term Data i ntry {

I ' NNPL NMI'1 ID*'G b

' I "' *I I ti.d.nc (<ws.ne het tu < evirne

• M orut.u Arts ' .e cs, "' N orwean flate 11.4/5)

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16. e II l 'l

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IWC f aee, temri inta He scaw- i I lii i','i. (s, f oyle lle;4 ease ILitr- l '.tsi l 12/.or DPi i I ' t +virrt dragus, or he+:rr ls ete-

)

l see.c . eet n hr cu.no d NH Ha e a ct rasig D Dd M l

Figure 7-21: Raddose-V lodine Release Rate Method Menu SAST- Severe Accident Source Term Use of the SAST method is the same as discussed above for determining isotope release rate.

1476- 901/ptsiopman'OPM4 NR I'0. DOC Page 7-25 Raddose-V

.I RA TIO - Ratiofrom Totalisotope Release If RATIO is selected, the model automatically inserts a ratio value in the iodine monitor / sample field based on the accident type. The model then calculates the iodine release rate (Ci/s) by multiplying the total isotope release rate by this ratio.

Raddose-V displays the release rate value in the iodine release rate field.

GRAB- GRAB Sample Use of the GRAB method is the same as described above for determining the total isotope release rate. Selection of GRAB for the iodine method will cruse the m to override previous data entered Sr the total method and deterraine a total isotope release rate from GRAB sample data (concentrations in uCi/cc) as well. If a GRAB sample analysis was previously defined, the individual concentrations will be displayed. (For accident type USER, individual release rates in uCi/s are dis DRECT-Direct input ofRelease Rate Enter the iodine release rate in Ci/s directly into the release rate field.

FSAR/USAR - Default Release Rate An accident specific default releas: rate (Ci/s) is automatically displayed for iodin O

l l

l 1

l Oi 1476 901/ptslopmaWOPMANRVO. DOC

, Page 7 26 t

7.3.1.4 Changing the Accident's isotopic Distribution To change the isotopie distribution for an accident, move to the accident type field (where the accident type is displayed) and click the " Iso Distribution" button at the bottom of the screen. 'Ihe isotopic Distribution Screen will be displayed. The screen provides a list of isotopes followed by data entry fields. If a user specified isotopic distribution already exists, these values will be displayed; otherwise, the fields will be zero. Enter or edit the activity (in Curies) of each isotope. (The isotopic Distribution Screen is presented in Figure 7-22.) Click OK to accept the isotope data and return to the source term screen. From the current step on, the model will use this new isotopic distribution for this accident type (unless changed again later).

MMr%ffiHif&n@h9&+MhtfMyp ^*. -

m, .,. ;,u

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lsotoper Destrabutton I,ctrrn ' f.wl**v Ile-l

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Adv St. (

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- i :;^ g, y,; i .r l L" , e r 3; g;g MA Ulll;3

~

'g ' & ~ pg GC "O I

Figure 7-22: Raddose-V Isotopic Distribution Data Entry Screen If the user enters FSAR as the total release rate calculation met specified isotopic distribution exists, a pop-up box is displayed asking the u verify that the distribution should be changed back to the default invento Yes or No. If Yes is selected, the default inventory is used and the default relea rates are displayed. If No is selected, the user specified inventory remains in and the user is allowed to enter another release method.

If the user enters GRAB as the total isotope release or iodine method while a us specified isotopic distribution exists for the current advection step, a war i

I476-90liptstopmaWOPMANRVO. DOC Page 7 27 Raddose-V

7.3.1.4 Changing the Accident's isotopic Distribution To change the isotopic distribution for an accident, move to the accident type field (where the accident type is displayed) and click the " Iso Distribution" button at the bottom of the screen. The Isotopic Distribution Screen will be displayed. The screen provides a list of isotopes followed by data entry fields. If a user specified isotopic distribution already exists, these values will be displayed; otherwise, the fields will be zero. Enter or edit the activity (in Curies) of each isotope. (The Isotopic Distribution Screen is presented in Figure 7 22.) Click OK to accept the From the current step on, the isotope dats and return to the source term screen.

model will use this new isotopic distribution for this accident type (unless changed again later).

Wx%i6kiintY*?21 M 1 M 5 M %&% W A v . ~ . ., .

,; , vi .,.s eg g ([ e/.,l

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. /4 h 7 7<,  ; ,

n,. , , t:: , , , 'sm , , a m, fmiil,l

}

W NDf& ?M M Figure 7 22: Raddose-V isotopic Distribution Data Entry Screen I

If the user enters FSAR as the total release rate calculation metho specified isotopic distribution exists, a pop-up box is displayed asking the us verify that the distribution should be changed back to the default inventor Yes or No. If Yes is selected, the default inventory is used and the default releas i

rates are displayed. If No is selected, the user speci6d inventory remains in and the user is allowed to enter another release method.

If the user enters GRAB as the total isotope release or iodine method while a us specified isotopic distribution exists for the current advection step, a warn l

1476-90liptsiopmaWOPM4NR VO. DOC Page 7-27 Raddose-V

is displayed requesting the user verify that the distribution be changed according to a <

grab sample. Click Yes or No. If Yes is sdected, the user is allowed to enter a grab sample analysis and the earlier entered isotopic distribution is ignored. If No is selected, the user specified inventory remains in effect and the user is requested to enter another total isotope or iodine release method.

NOTE: If a grab sample analysis is in effect for either the total or iodine release l

method, an isotopic distribution can NOT be entered. The GRAB sample is the primary method to change an accident's isotopic distribution.

7.3.1.5 Accepting Data When data entry for the step is complete, define another step through the use of the Add New Step button at the bottom of the screen or click the Accept button to accept the source term data and proceed to the next screen.

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7.3.2 Meteorological Data Entry - Elevated or Ground L.evel From the Main Menu, select either elevated or ground level meteorological data.

Data entry is the same. (Raddose-V will prompt the user for ground level and/or I

elevated data depending on the type of release.) When the selection for either level is entered, Raddose-V downloads the appropriate meteorological data from the MMS and displays these values for the screen selected. If the data is available from If the primary meteorological tower, this data is used and is displayed in yellow.

information is from a backup source, the data is displayed in green If any data is not available, a 999 is displayed (in red). At this point the user may manually ovenvrite any data. In the event the current 15-minute data is unavailable due to a communications malfunction or operating in manual mode, Raddose-V provides the following message "NO AUTOMATIC hETEOROLOGICAL DATA. ENTER DATA MANUAL.LY", The Elevated Meteorological Data Input screen is presented in Figure 7-23 and the Ground Level Meteorological Data Input screen is presen in Figure 7-24.

{

Haddosr V : I levatre Meteorologetal Data inppt ' W FY p;Mi'/

flD% !a .

As l'ir c ip J wind W i id l o Ls bura .g j I rn.priatwe I .,t e-

,, q l empe c.etwe I bet o g S en d f inni Mcqlg 4.uf l Smay

, , java 6 l l o.,p ec t) tnnt l 1.t. r ewl 7: 0 15

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Of? 45 45 2/L 15 " " ' ( 73 , 13 Vf DD , 4/  ? f's o l

-- t 73 m v5 43 m is

- . -  ?: s at m, 2v t m ni t /b b 350 I .f . J * * - ~

O't 45 l

a,*

w i naci della tesupciatee betweevi 4f ared 70 degiacs i to congside stabddy class ym -wg M

Figure 7 23: Raddose-V Elevated Meteorological Data Input Screen if MMS data is not yet available for the current time step or an earlier advectio is selected, Raddose will check the historical data file downloaded when the u logged in for the date/ time of the advection step needed. If the data and is not more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the past, Raddose will provide the user wit following message " Met data is not in current file or in current historica 1476-901/ptslopman'OPM4NS7. DOC Page 7 29 Raddose-V

Yes to download the newest histwical data or No to use manual entry." The user should click Yes to have Raddose-V download the newest 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> historical d and search for the correct meteorological data for the advection step or No to enter data manually. Manually entered data is displayed in cyan.

The meteorological data may be entered for a single advection step or several at a time. Note the field specific help line, including a brief description of what to enter in the field and valid ranges, where appropriate, at the bottom of the screen. The data line for each time step displays the step number and time of the step.

For manual entry, input the wind speed in miles per hour and the direction from which the wind is blowing in degrees. The Pasquill-Gifford Staoility Class may be entered directly (A through G) or may be calculated by entering delta-temperature in degrees F or sigma-theta in degrees. Move to the appropriate field to determine the Pasquill-Gifford Stability Class. Enter the air temperature in degrees F and the precipitation rate in inches per 15 minutes.

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Figure 7-24: Raddose-V Ground Meteorological Data input Screen Another time step may be entered using the Add New Step button at the bottom the screen or the user may edit existing time steps. Again, if the advection step for which data is requested does not match the current data on the MMS or in the curren historical data file, the user will have the opportunity to download the newest historical data from which to enter this infortnation or else enter the data manually Page 7 30 1476-90lipistopman'OPM4NS7. DOC Raddose V

7 -

)

When finished, click the Accept button to accept the data entered and proceed to the O- next screen.

7.3.3 Performing Real-Time Calculations l To perform calculations for an advection step just defined, click the Perform Calculations button on the Main Menu. The subsequent pop-up box displays the  ;

time step being calculated and indicates the doses and receptors being assessed.

When calculations are complete the model displays the 10-mile ERPA map. Click the Continue button or press < ENTER > to remove the map. The model l I

automatically saves data from the current advoction step to spreadsheet ASCII files and then proceeds to the Output Menu (see Section 7.4).

In the Output Menu, selectmg Return to Main Menu allows a user to return to the Main Menu and define inputs for the next advection step.

To continue calculations for subsequent advection steps already defined in the j meteorological and source term screens, click Continue with Calculations from the Output Menu. The model will then calculate and display the output options for t next advoetion step. This procedure may be repeated until all defined advection steps have been calculated. If this option is selected and there is no meteor and/or source data remaining to calculate dose / deposition information for the next O time step, the Main Menu will be displayed.

Before calculations can be performed from the Main Menu for any advection step, both meteorological and source term daui == he verified. If either data set has not been verified, the model will wam the user and will not perform calculations until that data screen is displayed and the data accepted if several advection steps have been entered, but the user returned to the Main Menu instead of Continuing with Calculations from the Output Menu, the data must also be verified before calculations can be performed.

7.3..I Performing a Forecast The procedures for performing a forecast are similar to pmcedures for rea calculations. Meteorological and source term data must be verified and the mode calculation routines invoked.

From the Main Menu, select Enter / Edit Source Term Data and enter data for forecast period in the current time step. Repeat the process for the appmpr meteorological data entry screen. Click " Perform a Forecast" to calculate the forecast doses. In the following pop-up box, the default forecast period,4 ho displayed. Accept the default or enter a new forecast period, in hours, O or press < ENTER >. The user must then indicate whether or not a General Emergency has been declared. If Yes is selected, the model calculates 1476-901/ptstopman/OPMANS7. DOC Page 7-31 Raddose-V

Emergency PARS along with dose related PARS. General Emergency PARS are determined using the methodology outlined in Section 6.1.2 and the meteorology entered for the Forecast period. (The Forecast Period Definition screen is presented in Figure 7-25).

une,:

em Em e. h c ,=i.4 in liows I

I ID

- dh5WW.3%

I# dd hi @ & dt#4 6 4.N EPWfB%$6#5B Figure 7-25: Raddose-V Forecast Period Definition Screen Upon completion of the Forecast calculations, the 10 mile ERPA map f forecast mode is displayed. Protective Action Recommendations including ER to evacuate and/or shelter are displayed in the forecast mode on the map sc on the repons. PARS based on dose alone are shown in yellow, while tho the General Emergency classification, if declared, are shown in cyan.

The model Click the Continue button or press < ENTER > to remove the map.

automatically saves the data for the forecast period to a spreadsheet AS proceeds to the Output Menu. Obtain dose reports, or retum to the continue forecast calculations, or retum to real time mode calculations. If Emergency was declared, the model prompts "Should the General Em be saved?" when the user returns to the Main Menu. If the user clicks Yes, based on General Emergency are saved and are included in the next fo run.

It should be noted that source term data for the forecast will remain displ screen the next time this data entry screen is invoked. When proceeding w 1476 9011ptsiopmaWOPMANSTDOC Page 7-32 Raddose-l'

time mode calculations after having performed a forecast, be certain the source term data in the current advection step is corrected (edited) for the real-time calculation.

7.4 Out},ut Menu Raddose-V's Output Menu allows the operator to view and obtain hard copy output of the results of dose calculations. Options are available to view grid receptor doses, plume arrival times, the 10-mile EPZ and ERPA maps, survey point dose The user also accesses the 50-mile deposition menu of interest dose rates.

(containing deposition reports and the Ingestion Pathway EPZ map) and the R Options Menu (for hard copy reports) from this menu. In addition, the Outp provides the options for Continuing with Calculations, or returning to th Menu without performing any of the reporting functions. The Output Menu is presented in Figure 7-26.

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. ~ acc y&w_7;; r < wGA- ~ : . -.- - k Figure 7-26: Raddose V Output Menu 1476-9011ptsiopman'OPAMNS7. DOC Page 7-33 ddose V

7.4.1 GridReceptor Doses Selecting to view the grid receptor doses leads the operator to a menu fro the user may chose to view the TEDE exposure, EDE Plume exposure, ED exposure, CDE-Child Thyroid exposure, ground level concentration va CEDE from Inhalation. Click on the appropriate selection. The menu is presen in Figure 7-27.

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wiv ' Li Heal Imam Mode IWh .;o...,,,# an,e ..a...no opuyns

- a s

, / ,

Figure 7-27: Raddose-V Grid-Point Receptor Menu Each report contains dose rates and/or cumulative doses at each ring 10-mile EPZ for each of the 16 sectors and color coding of dose values ba in the forecast mode, Protective Action Protective Action Guideline levels, Recommendations are provided based on both a General Emergency cla and on dose. Sample grid receptor screens are presented in Figures 7-2 30.

O 14*6-90liptsiopmaWOPhfANS7. DOC Page 7-34 Raddose-l'

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Figure 7 29: Raddose-V Sample Plume EDE Screen 1476-901iptstopman!OPMANS7. DOC Page 7 35 Raddose-V

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Figure 7-30: Raddose-V Sample CDE Child Thyroid Screen O

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1476-90]iptsiopman'OPMANS7. DOC Page 7-36 Raddose-l*

7.4.2 Plume Arrival Times The plume anival time report, displays the arrival time (in hours) to each major ring distance (.87,1,2,5, and 10 miles) for both the elevated and ground level plumes.

Click on the Continue button to retum to the Output Menu (see Figure 7-31).

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Figure 7-31: Raddose-V Plume ArrivalTimes Screen 1476-90lipta.'opmanDPM4NS". DOC Page737 Raddose l'

7.4.3 10-Mile Maps andPARs Selection of 10-Mile Maps and PARS displays either the 10-mile EPZ map an Both maps PARS or the 10 Mile ERPA map, depending on which was chosen.

display circles representing the position of the elevated and ground level p The elevated plume is yellow and the ground level is blue. The corresponding plu centerline dose rates for Plume EDE and CDE-Child Thyroid are also displayed.

the forecast mode, Protective Action Recommendations are also provided based dose and emergency classification (if a General Emergency is declared). A sam 10-Mile EPZ Map and PARS screen is presented in Figure 7-32 while a sample mile ERPA map is presented in Figure 7-33. Return to the Output Menu by cli Continue or pressing < ENTER >.

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1476-901/ptstopman/OPMANS7. DOC Page 7-38 Raddose-l'

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Figure 7-33: Raddose-V 10-Mile ERPA Map Screen 1476-90lipwopman'OPMANST. DOC Page 7-39 Raddose-l'

7.4.4 Survey Point Doses By selecting to view survey point doses, the user is provided with a lis NMPC/NYPA designated survey points. For each point the screen displays the number, its distance from the plant site, the sector, a NMPC/NYPA Location Description, the "TEDE" and CDE-Child Thycid dose rates, and TEDE an Child Thyroid cumulative doses. The list is more than one screen in length a user may scroll through the list using the scroll bar on the right of the table. An example of one screen of the survey point doses is presented in Figure 7-34.

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Raddose-V Survey Point Dose Data Screen m *

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7.4.5 Point-ofInterest Dose Raies Point-of-interest dose rates allow the user to obtain data at any point within the 50-mile EPZ. When the screen is first entered, the maximum dose rates at each grid network ring distance (0.87,1.0,2.0,5.0 and 10.0 miles) are displayed. For any other location, enter the ring distance in miles (up to 50 in the data entry screen),

press < ENTER >, then enter the bearing in degrees, and click the Cale @

miles / degrees button. The model calculates a plume EDE dose rate, a "TEDE" d rate and a CDE-Child Thyroid dose rate as well as a deposition rate at the user-defined point and displays these results. In addition to the dose rates, the report contains the sector letter in which the point falls. The user may also enter "M" in the bearing field and the model will displayed the maximum at that ring distance.

Continue defining points and calculating the related dose rate information or return to the Output Menu. A sample Points-of-Interest dose data screen is presented Figure 7-35.

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Me.- 59 Figure 7-35: Raddose-V Point-of-Interest Dose Rates Screen Note: The data and results for each Point-of-Interest are written spreadsheet ASCII file for the advection step.

o 7.4.6 30-Mile Deposition Data Selection of 50-mile deposition data presents a menu from which the user may opt to view the 50-mile EPZ map, deposition data, current dose rates due to ground deposition, or retum to the Output Menu. Selections are made by highlig appropriate option and pressing < ENTER > or clicking on the button.

Deposition Menu is presented in Figure 7-36.

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t Figure 7-36: Raddose-V 50-Mile Deposition Menu O

1476-90liptsiopman'OPAfANS7. DOC Page7 42 Raddose l*

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l 7.4.6.1 50-Mile Map 5 'lection of 50-Mile EPZ MAP allows the user to view the 50-mile EPZ map and con esponding plume centerline deposition data. In the forecast mode, the m inch les the 10 mile EPZ PARS. A sample 50-Mile EPZ MAP screen is presente Return to the 50-Mile Deposition Menu by clicking the Continue Figun 7 37.

button , r pressing < ENTER >.

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• ai74 4 4 susci A g Figure 7-37: Raddose-V 50-Mile Map Screen I

1476 90]ipts:opmarv0PMANS". DOC roge 143 bas,.s.

7.4.6.2 Deposition Rate and Accumulated Deposition Data View the ground deposition rates or accumulated deposition by clicking appropriate option. Either option displays the ground deposition d distances defmed for the 50-mile EP2 for each sector. Note the color deposition levels to indicate PAG levels. (PAG's are defined in Ta and C-20 of the SDS.) Protective Action Recommendations based on dep displayed near the bottom of the screen. A sample Accumulated G Data screen is presented in Figure 7-38. (To see which isotope met th the Grid Receptor Isotope Report from the Report Options Menu.)

_f

, Itaddo!.r V As tumulated ( Arposition f.wei e,m a

. .., a 4

w. e w iest g...- 2., n. ii b ', i dt..y,<sm A . e i . . am .2t i .1 i ii r ,,, . el eier. l ! s 'siJ 7)

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Figure 7-38: Raddose-V Sample Accumulated Ground Deposition O

1476-901/ptsiopman'OPMANS7. DOC Page 7-44 Raddec. 1*

7.4.6.3 Survey Points Deposition Data By selecting to view survey point data, the user is provided with a list of ,

NMPC/NYPA designated survey points. For each survey sector point receptor, the screen displays the point number, its distance from the plant site, the location Use the scroll bars to description, deposition rates and accumulated deposition.

display the complete list. An example screen is presented in Figure 7-39.

{

. .fladdu'.c V : Survt y l'umts Depossimn Data Step 8 4 s.r4W Wi'?

04 '3 hisJ 1 nan Mode

a.s- y + r,g e . I ,,o. om 1. c a I . .ti t '. fs . i uit.

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/r . .. .i i 1.i n .v 3 9 k h o l'Al' N Steelen Figure 7-39: Raddose-V Survey Points Deposition Screen 1476-90liptsiopman'OPMANS7. DOC Page 7-45 Raddose V

7.4.6.4 Dose Rates From Deposition Current dose rates from material deposited on the ground are available by selec this option. The screen displays these dose rates at each ring distance in each of the 50-mile EPZ. A sample Dose Rate from Deposition screen is presented in Figure 7-40.

l Haddose V . Dose Rates frorn Deposenson i

h 110t Step 8 4 NwPr M4s'?

h D% :' 'sa .

,,ite (isaw Mede D ov flatc. f .on. larg>u: st in l < u .e e . .a t b e m/hi j Al (1 m 41 O me Sb (1 me S U ene ill il m /b U me

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ll D 1. O ll (J fl il 4 8 (J 11 (I P.h W e * , l r>M re n as Figure 7-40: Raddose V Sample Dose Rates from Deposition Screen O

Page 7-46 1476-90liptsiopmanOPMo'S7. DOC Raddose-l'

~.

l 7.4.7 Report Options Menu "Ibe Repon Options Menu provides the user with several choices for obtaining hard copy output of the dose repons after each advection step. Each of the reports (i.e.,

complete dose / dose rate repon, the 16-mile maps, the 50-mile map, Header Page An the Grid Receptor Isotope Report) may be selected individually for printout.

option also exists that allows the user to print all of the reports at once. Each pag a report has a header containing the model name and version, plant name, current i date and time, the operator, the time step number, and the step date and time. In the forecast mode, the Report Options Menu also allows a user the opportunity to print Part 2 of the NYS Emergency Data Form (Notification Form). The Report Options Menu is displayed in Figure 7-41 while Appendix B contains sample reports. This l menu also allows the user to print a previous step's data in the Real Time Mode.

5 2. . _T i _= 2. =.- s .t. r._

ld_i ?_,"YSQ jfggM%

rWQbf ..[ iMZW W W @

$NTMM.T. W4.6--2 %,.8

~

3YZq @ W ME Figure 7-41: Raddose-V Report Options Menu 7.4.7.1 Complete Dose / Dose Rate Report Selecting a Complete Dose / Dose Rate Report provides the operator with a h report containing the trip and release dates and times; meteorological and term input data; isotope percent abundance at the elapsed time; plume arri The remaining pages of the report and grab sample analysis data, if available.

include TEDE dose rates and doses, Plume EDE dose rates and doses, CD Thyroid dose rates and doses, CEDE dose rates and doses, ground EDE 1476-90liptstopman'OPMANS7. DOC Page 7-47 Raddose-l'

1 and doses, ground plume concentration values, current dose rates from ground deposition, ground deposition rates and accumulated deposition, and data a survey points, if any points-of-interest were defined, these will be printed on a for each time the option is selectci Protective Action separate page Recommendations are printed below the data.

7.4.7.2 Grid ReceptorIsotope Report The Grid Receptor Isotope Report contains accumulations of individual isotopes deposited on the ground at each grid receptor. There is a separate page distance in the 50-mile Ingestion Pathway. From this report, the user can see I

isotopes met PAR levels for deposition.

7.4.7.3 Map Reports Each of the three maps, the 10-mile EPZ,10-mile ERPA and the 50-mile EPZ, be printed separately. These may take several minutes to print dependI printer chosen when the model was installed.

7.4.7.4 Header Page This option prints a hard copy repon containing the trip and release date meteorological and source term input data; isotope percent abundance time; plume arrival times; and grab sample analysis data, if available.

7.4.7.5 Print Reports and Maps (and-Emergency Form in Forecast Mode) ,

This may take a few minutes to Selecting this option, prints all of the reports.

complete. 1 l

7.4.7.6 Print Notification Form Part 2 (Forecast Mode)

In the forecast mode, a user is provided the option to print the NYS Emerg Form, Pan 2 from the Report Options Menu. Selecting this option pro the Notification Form along with pertinent data available from Raddose-V.

I l

O 1

l .

,,, 7.as is1s.9oriersiormaniorusNsr.coc Raddose-l'

7.4. 7. 7 Print a Previous Step (Real Time Mode)

This option allows the user to enter a previously calculated step number and have this advection step's data printed. The user must enter the step number from a pop-up box and click OK (see Figure 7-42). Then the Report Options Menu is dis Select a report as discussed above. After the Report Options Menu is aborted, th advection step returns to the current one.

Emer the previous step to was

~

1 11 Wil5%WX-%V "8 S ?~ 5 N dNF. N e$Nd 5NMENM5i35 Figure 7-42: Raddose-V Print A Previous Step Pop Up Screen 7.4.8 Continue Calculations This option continues calculations if more than one meteorological and sour step was defined. If not, the user is returned to the Main Menu.

7.5 ASCII Files For each advection step defined and calculated, two ASCII files are cre stored in the plant's Raddose-V sub directory \ DATA. These files contain assessment data for each advection step stored in ASCll form and are a importation to LOTUS @ 123 and Microsoft@ Excel.

If real-time calculations have been performed, the files are of the form ADVnnn.DAT contains the real time ADVnnn.DAT and GISOnnn.DAT.

1476-901tptstopmawOPALANS7. DOC Page 7-49 Raddose-V

r 0

meteorological and source term input data and the dose and deposition results for advection step number nnn, GISOnnn.DAT contains the accumulated isotopes deposited on the ground at each grid receptor.

If a forecast has been performed, the files created are of the form FCSTnnn.DAT and FISOnnn.DAT.. File FCSTnnn.DAT contains the meteorological and source term input data and the dose and deposition results for advection step number nnn durin which a forecast was made. FISOnnn.DAT contains the accumulated isotopes deposited on the ground at each grid receptor.

7.6 Map Editing l

MakMaps.exe is a supplemental Visual Basic program which is provided with EDAMS to allow a qualified user the ability to edit the Raddose-V maps. This program takes ASCII files of coordinates from digitized (using ArcInfo) EPZ background maps and converts them to a format required by the model. (See the DDM Section 3.12.3.4 for a list of the ASCII files containing the coordinates for the I maps.) Because the plume position is overlaid on the map background, the digitized scale and coordinate system must be retained for puffs to appear in th correct position. The Raddose-V source code would not have to be re-compiled long as the scale and coordinate system is maintained. The following provides l

brief overview of editing the background maps:

1. Double click on MapMaps.exe to start the program.

2. From the Main Menu (see Figure 7-43), select the map to edit.

l l

I l

l O

,noin.,-nnu - x u_c e.,e ,.so j

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~

~~

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ei.as.se vs.ie ti.p*.i,.. ~~ ~ l L

i

1. If '

,s "p

+.

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=J .J-Figure 7-43: MakMap Main Menu

3. From the Map Screen (see Figure 7-44), click Draw Map and the program read the ASCII files containing the lines (shoreline, roads, etc.) and draw the background of the map.

4. Click Save Map and enter a filename for the bitmap.

5. Press < Alt >< Tab > to switch to the Windows Program Manager.

6. Start Paintbrush (usually located in the Accessories Group).

7. Open the bitmap file saved in step #4. Use the Paintbrush tools to rivers, lakes and land on the map. Save the file.

8. Press < Alt >< Tab > to switch back to MakMap.

9. Click Load Map and select the filename of the map saved in step #8.

10. Click Draw Grid to place the radial grid or the ERPAS over the ba the map.

11. Click Draw Labels and the program will label the sectors or ERPAs background.

12. Save the bitmap. See the DDM Section 3.12.2.2 for the filename e Raddose-V for each map.

1476- 90 liptstopman'OPM4 NR l '0. DOC Page 7-51 Raddose-l'

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Figure 7-44: MakMap Map Screen 0

O Page 7-52 1476-Y0liptsiopman/OPMANS7. DOC Raddose.V

i l

I

)

Appendix C J. A. Fitzpatrick Tables O -

J f

e O i i

Table C-1: Meteorological Data Ranges Sitt Umis Range Innijd O

Main Tower Wind Direction (200',100',30') degrees 0 to 360' 999.9 Wind Speed (200',100',30') mph 0 to 100 999.9 Delta Tempemture (200'- 30') 'F -8 to +20 99.99 Sigma Theta (200',100',30') degrees 0 to 999.9 999.9 Temperature (30') 'F -40 to +110 999.9 Precipitation (15-minutes) inches 0 to 99.99 99.99 Backup Tower Wind Direction (90') degrees 0 to 360 999.9 Wind Speed (90') mph 0 to 100 999.9 Sigma Theta (90') degrees 0 to 999.9 999.9 Inland Tower Wind Direction (30') degrees 0 to 360 999.9 Wind Speed (30') mph 0 to 100 999.9 Sigma Theta (30') degrees 0 to 999.9 999.9 l

O J. A. Fit: patrick Tables Page C-1 g/ pts /1476nimo/sds/appe

Table C-2A: Miscellaneous Data . ,

- Data llnha Value t degrees 43' 31' iga Latitude .2

( Longitude 12 degrees 76* 24'20" .

8 Plant Elevation feet 272 Shore Angle degrees 240*-90' Distance from Plant to Shore miles 0.12 Wind Directions for a Sea Breeze degrees 245'-65* (0-10 mph)

Wind Directions for Shoreline Fumigation degree 270'-55' (0-22 mph)

Elevated Release Points:

Stack Base 3 feet 272 Stack Height Above Basel feet 385 Gas Exit Velocity 1 feet /sec 4.62 Stack TopInside Diameter 1 feet 6

~

Gas Exit Temperature 'F ambient i

I l

l

' 'AF, Meteorological Monitoring and Radiological Assessment System for the James A. Fitzpatrick Nuclear Power Plant, Vol. III, Part 1, Class A Model Formulation, Revised March 1987.

• JAF/NMP, Radiological Emergency Plans and Procedures, Map Number 1, Ten Mile EPZ (Plume Exposure Pathway) l

' Plant Grade Plan provided by Mr. Nicholas Avrakotos, JAF, June 4,1993 Page C-2 g/ pts /1476nimalsds/appc J. A. Ficpatrick Tables 1

p .

1 l

Table C-2B: Average Seasonal Afternoon Mixing Heights Season Months Mixing Height (mf O

Winter December,Januarf, February 860 Spring March, April,May 1400 Summer June, July, August 1700 Autumn September, October, November 1200

~

G l Holzworth. George, C. Mixine Heichts Wind Soeeds. and Potential for Urban Air Pollution Throuchout the conticuous United States. USEPA, Ap-101, January 1972.

l J. A. Fit: patrick Tables Page C-3 g/ pts /1476nimo'sds/appe

E. .

l Table C-2C: Average Surface Water Temperatures (by Month or Week)* ,

O .

beenenedLahn Cesario Surfees Tenapsressee Menah Trem Te T_ , - -- e Mead Tran Te Temperasers Jassary 1 11 37 Jaty is 22 87 Jaamary 12 23 38 July 23 28 48 January 24 31 35 July 29 31 40 February 1 8 35 Angues 1 4 es February 7 25 34 August 5 13 70 February 28 28 - 33 Angues 12 14 71 E rak 1 8 33 August 19 26 70 Ersh 9 27 34 Angues 27 31 og Ersh 28 31 35 Sepsamber 1 1 og April 1 u 35 96 2 8 88 April 12 30 38 Sepsesaber 9 14 87 April 21 27 37 Sepsesaber 15 19 es April 28 30 38  ?;

• 20 u e5 my 1 2 38 Sepsesaber 25 28 64 Wy 3 8 39 Sepsamber 29 30 43 Ey 7 9 40 Ocsehsr 1 1 83 by 10 12 41 Ocseber 2 4 82 Ey 13 15 W Ocseber 5 7 61 Ey 18 la 43 Ocseber 8 9 to Ey 19 21 44 Ocseber 10 11 59 my 22 34 45 Ocseber 12 13 58 O . Ey Ey Wy 25 28 31 27 30 31 48 47 48 October Ocseber Oeseber 14 16 18 15 17 19 57 so 55 Jane 1 2 48 Ocseber 20 21 54 Jane 3 4 49 Ocseber 22 23 53 Jane 5 7 50 Ocseber 24 26 52 Jane 8 9 51 October 27 29 51 Jane 10 11 82 October 30 31 50 Jye 12 13 58 November 1 1 50 Jane 14 15 54 Noveenbar 2 4 49 Jane 16 17 55 Nevesiber 5 7 48 Jane is 19 34 November 8 10 47 June 20 21 57 Nevesaber 11 13 48 Jane 22 23 58 Nevesaber 14 16 45 44 I Jane 24 25 59 Novesaber 17 20 June 26 27 80 November 21 24 43 Jane 28 29 01 November 25 29 42 Jane 30 30 82 November 30 30 41 July 1 1 02 December 1 4 41 July 2 4 43 December 5 10 40 July 5 8 64 December 11 18 39 July 9 12 45 December 19 30 38 July 13 17 e6 December 31 31 si l

I j

• These values have been included to allow activation of the TIBL height routine only.

Source: Ballentine, IU., "Fonnulation And Testing Of An Index To Predict The Onset Of Lake Breezes Along De South Shore Of Lake Ontario." Provided by Mr. Tom Galletta, NMPC, Project Meeting, May 12,1993.

l 1

Page C-4 g! pts!!476nimo/sdslappe J. A. Ficpatrick Tables

r .

l l

Table C-3: Accident Types O

Abbreviation Accident Descriotion Elevated Release CDBA Containment DBA Elevated / Ground Level CRD ControlRod Drop Elevated / Ground Level RFA Refueling Accident ElevatteWGround Level SLB1 Steam Line Break (Steam Only) Ground Level SLB2 Steam Line Break (Two Phase) Ground Level LOCA Loss of Coolant Accident Elevated / Ground Level J SAST Severe Accident Ground Level  ;

USER ** USER-Defined Accident Elevated / Ground Level I

i

)

g l

l l

l I

1

Reference:

Personal Communication, Mr. Nicholas Avrakotos, NYPA, June 4,1993 and June 8,1993, and JAF, Metecrolocical Monitorinc and Radiolocical Assessment System for the James A. Fitrardek Nuclear Power Plant. Vol. III, Part I, Class A Model Formulation, Revised March,1987, Tables 2-3 and 2-4.

'Ihis accident type allows only GRAB sample as the total and iodine release rate calculation method.

l J. A. Fitrpatrick Tables Page C-5 g/ pts /1476nima'sds/appe I

)

i Table C-4: Default Release Rates

• l Accident Total (Ci/s) Iodine (Ci/s) l l CDBA' O.812** 1.694E-2 CRD 0.1189 1.168E-3 RFA 36.64 4.548E-3 SLB1 0.04144 3.802E-2 SLB2 0.04144 3.802E 2 LOCA 101.3 3.006E-1 SAST See Table C-7 See Table C-7 USER N/A N/A O -

1 l

Reference:

JAF, Meteorological Monitoring and Radiological Assessment System for the James A. Fitzpatrick Nuclear Power Plant Vol. III, Part I, Class A Model Formulation, Revised March,1987, Tables 2-3 and 2-4. i

Reference:

Fax, Mr. Peter Cullinan, NYPA, October 8,1998.

' J. A. Fit: patrick Tables 12/98 Page C-6 nmpc\raddoset28647\sds\appe l

1 l

L . .

_ Table C-5: Total Release Monitor Types O

Abbreviation Monitor Unita Rangs TELET Teletector (mR/hr) 1E9 GRAB Grab-Sample Effluent Analysis (pCi/cc) 1E12 DRECT Direct Input ofRelease Rate (Ci/s) 1E9 FSAR Default Release Rate'- FSAR (Ci/s) 1E9 CHRM Containment High Range Monitor (R/hr) 1E9 BACK Back Calculate (mR/hr) 1E9 STKLO Stack Low Range (eps) 1E9 STKHI Stack High Range (mR/hr) IE9 <

EFFLO Effluent Monitor Low Range (cpm) IE12 EFFHI EfDuent Monitor High Range (mR/hr) 1E9 GRAB (USER) USER Accident GRAB-Sample ( Ci/s) N/A I

l

Reference:

Per>onal Communication, Mr. Nicholas Avrakotos, NYPA, June 4,1993 and January 16,1995. f l

J. A. Ficpatrick Tables Page C-7 g! pts /1476nimalsds/appc j

L ,

Table C-6: Iodine Methods ,

\

Abbreviation Method h g GRAB Grab-Sample EfUuent Analysis (pCi/ce) lE12 DRECT Direct Input of Release Rate (Ci/s) lE9 RATIO Ratio from TotalRelease (dimensionless) 0-1.0 FSAR Default Release Rate - FSAR _ (Ci/s)' IE9 GRAB (USER) USER Accident GRAB-Sample (pCi/s) N/A O

~

O V

Reference:

Personal Communication, Mr. Nicholas Avrakotos, NYPA, June 4,1993 and January 16,1995.

Page C-8 g/ pts /1476nimalsdsfappc J. A. Ficpatrick Tables

Table C-7: Monitor Methodology i

I STACK / EFFLUENT LOW AND HIGH RANGE MONITORS (EPIC)

Reference:

EAP-4

. Monitors 1 through 5 Release Rate (Ci/s) = Monitor Reading (cpm)

• Calibration Factor (Ci/sec/ cpm) * [ Entered Flow Rate (cfm)/

Norrnal Flow Rate (cfm)]

or Release Rate (Ci/s) = Monitoring Reading (eps)

• 60 (sec/ min)

• Calibration Factor (Ci/sec/ cps) * [ Entered Flow Rate (cfm)/

Normal Flow Rate (cfm)]

e Monitors 6 through 9 Release Rate (Ci/s) = Monitor Reading (mR/hr)

• Calibration Factor (Ci/sec)/(mR/hr) * [ Entered Flow Rate (cfm)/ Normal Flow Rate (cfm)]

G where:

Default Normal Calibration Flow Rate Monitor Factor (cfm) 1 - Low (Turbine Bldg) 8.0 E-8 107,000 2 - Low (Reactor Bldg) 1.0 E-7 61,000 3 - Low (Refuel Floor) 3.0 E-8 70,000 4 - Low (Rad Waste Bldg) 1.0 E 7 32,500 5 - Low (Stack) 3.0 E-8 6,600 6 - High (Stack -1 SBGT) 1.40 6,600 7 - High (Stack -1 SBGT + 1 Dil. fan) 2.54 12,000 8 - High (Turbine Bldg) 22.6 107,000 9 - High (Rad Waste Bldg) 6.35 32,500 0

J. A. Fit: patrick Tables-12/98 Page C-9 nmpctraddoset28647\sds\appe

I Table C-7: Monitor Methodology (cont'd)

TeIetector

Reference:

EAP-4 Release Rate (Ci/s)

= Monitor Reading (mR/hr) * -

Calibration Factor (pCi/cc/mR/hr)

• Stack Flow Rate (cfm)

• 472 (cc min /cf-sec)

• IE-6 (Ci/pCi) where:

Default Calibration Factor = 0.5 CI/cc/mR/hr CHRM - Containment High Range Monitot

Reference:

EAP-4 Release Rate (Ci/s)

= Monitor Reading (R/hr)

• Conversion Factor (Ci/cc per mR/hr)

• Flow Rate (cfm)

• 472 (cc-min /cf-sec)

GRAB - Grab Samnle Analysis

~

Reference:

EAP-4 Release Rate (Ci/s) = [I Concentration ( Ci/cc))

• Stack Flow Rate (CFM) *

=

472 (cc-rain /cf-sec)

• 1E-6 Ci/ Ci GRAB (USER)- GRAB Ramnle Annivsis for USER Accident Tyne ReleaseRate(Ci/s) = [Ihetope Release ( Ci/s))

• 1E-6 (Ci/ Ci) l O

i Page C-10 gipts/1476nimdsds/appc \

J. A. Ficpatrick Tables

Table C-7: Monitor Methodology (cont'd)

BACK-CALCULATE O

A. EDAMS CWG (mR/ hr)

• WS(mph)

• 0.447

• 8 Release Rate (Ci/t)= ' mR / hr ' f DCF

• xu 1' 2

( Ci/ m' s Qsm, where; CWG = three foot, closed window gamma reading (mR/hr)

WS = wind speed (mph) 0.447 = conversion factor from mph to m/s DCF = accident type specific dose conversion factor (based on default inventories in Tables A-9 through A-17) 2

= nonnalized concentration (1/m )

xu/Q B. .RADDOSE-V

= RR (Ci/s) * [CWG (mR/hr)/EDEp (mR/hr))

Release Rate (Ci/s) where: RRm = the release rate entered by the user for the puff, predicted by Raddose-V, found closest to the sample point (Ci/s)

CWG = three foot, closed window gamma reading (mR/hr)

EDEp = plume EDE calculated by model (Raddose-V) at field sample location (mR/hr)

FSAR See Table C-4 O

J. A. Ficpatrick Tables Page C-11 g/ pts /l476nimdsds/appe

. . . Table C-7: _. . Monitor Methodology (cont'd)

SAST - Severe Accident Source Term

• Source: NUREG 1228 i enk Rate Relene, pare (Ci/s) 0.1 %/ day NG: 4.99 I + Pan: 7.67

• FF

• SF 100 %/ day NG: 4.99E+3 I + Part: 7.67E+3

• FF

• SF 100 %/ hour NG: 1.20E+5 I + Pan: 1.84E+5

• FF

• SF where:

FF = 0.01 Through Filters (Filters On)

'13 .

U l.0 No Filters (Filters Off)

SF = 0.40 Sprays Off/0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> hold up 0.04 Sprays Off/2-12 hour hold up 0.01 Sprays Off/24 hour hold up 0.03 Sprays On/0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> hold up 0.02 Sprays On/2-12 hour hold up 0.002 Sprays On/24 hour hold up

Reference:

Personal communication, Mr. Nicholas Avrakotos, NYPA, June 8,1992.

l J. A. Ficpatrick Tables Page C-12 g/ pts /1476nimdsds/appe

.]

I Table C-8: Radionuclide Characteristics Considered in Dose Assessment 7 Half Life 9

Radionuclide Group (days) Parent Fract 1

A. Noble Gases j Kr-83m 0.07625 none 0.0 Kr-85m 0.1867 none 0.0 Kr-85 3915 Kr-85m 0.211 Kr-87 0.0530 none 0.0 Kr-88 0.118 none 0.0 Kr-89 0.00219 none 0.0 Xe-131m 11.84 I-131 0.01086 Xe-133m 2.19 I-133 0.0288 Xe-133 5.245 I-133 0.9712 Xe-135 0.380 I-135 0.835 Xe-135m 0.01067 I-135 0.165 Xe-137 0.00266 none 0.0 Xe-138 0.00981 none 0.0 B. Iodmes I-131 8.040 none 0 1-132 0.0958 Te-132 1.00 I133 I-134 0.867 0.0365 none none 0

0 g

I-135 0.275 none 0 C. Others Cs-137 1.102E+4 Xe-137 1.00 Te-132 3.26 none 0 Sr-89 50.55 none 0 Sr-90 10,446 none 0 Ba-140 12.79 none 0 La 140 1.676 Ba-140 1.00

Reference:

Pacific Nonhwest Laboratory, The Mesorad Dose Assessment Model, NUREG/CR-4000, Vol.1, March 1986, Table C.l.

J. A. Ficpatrick Tables Page C-13 g/ptsfl476nimotsds/appe

n 1

l L

Table C-9: Default Radionuclide Abundances Severe Accident Source Term 3 O Assume: 827 MWe

~ ~

Release Available for Isotope Inventory (Ci9 Fraction 3 Release (Cil Kr-83m NA 1.0 NA Kr-85m 1.98E7 1.0 1.98E7 Kr-85 4.63E5 1.0 4.63E5 Kr-87 3.89E7 1.0 3.89E7 Kr-88 5.62E7 1.0 5.62E7 i

Kr-89 .

NA 1.0 NA.

Xe-131m 8.27E5 1.0 8.27ES Xe-133 1.41E8 1.0 1.41E8 Xe-133m 4.96E6 1.0 4.96E6 Xe-135m NA 1.0 NA Xe-135 2.81E7 1.0 2.81E7 Xe-138 1.41E8 1.0 1.41E8 Xe-137 NA 1.0 NA I-131 7.03E7 1.0 7.03E7 I-132 9.92E7 1.0 9.92E7 I-133 1.41E8 1.0 1.41E8 I-134 1.57E8 1.0 1.57E8 1-135 1.24E8 1.0 1.24E8 l Te 132 - 9.92E7 0.3 2.98E7 Cs-137 3.89E6 1.0 3.89E6 Sr89 7.77E7 0.07 5.44E6 Sr 90 7.77E7 -

0.07 5.44E6 Ba-140 1.32E8 0.2 2.64E7 La-140 1.32E8 IE-4 1.32E4 Total Available for Release 1.09E9 Ci l

l 3

! Source Term (available) = Inventory x Release Fraction.

2 Inventory in core = MWe x Fission Product Inventory (from NUREG 1228, Table 2.2)

• Release Fraction (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> release)(from NUREG 1228, Table 4.1)

NA = Not Available J. A. Fitrpatrick Tables Page C-14 gqts'l476nimo/sds/appc

Table C-10: Default Radionuclide Abundances Containment DBA Source Radionuclide Group Strength (Ci/sec)

A. Noble Gases Kr-83m 1.154E-2 Kr-85m 1.508E-4 Kr-85 3.658E-9 Kr-87 0.0 Kr-88 0.0 Kr-89 0.0 Xe-131m 7.994E 5 Xe-133 2.769E-2 Xe-133m 1.934E-3 Xe 135m 5.686E-1 Xe-135 1.952E-1 Xe-137 0.0 Xe-138 0.0 B. Todmes 1-131 1.918E-3 I-132 2.803E-3 I-133 4.0llE-3 1-134 I-135 4.417E-3 3.789E-3 g

C. Others Cs-137 2.019E-4 Te-132 4.606E-4 Sr-89 1.201E-4 Sr-90 1.255E-5 Ba-140 2.306E4 La-140 2.443E-6 i

Reference:

Personal Communication, Mr. Nicholas Avrakotos, NYPA, September 11,1995.

J. A. Fit: patrick Tables Page C-13 g/ pts /1476nimatsds/appc

V.: ,.

t .

Table C-11: Default Radionuclide Abundances Refueling Accident

• O Source Radionuclide Group Strength (Ci/sec) l A. Noble Gases Kr-83m 3.552E-4 Kr-85m 1.657E-1

. Kr-85 - 9.144E-1 l 10-87 2.695E-5 Kr-88 5.252E-2 l

Kr-89 _. .- - 0.0 Xe-131m 1.669E-1 Xe 133 5.379E+1 Xe-133m 1.991 i Xe-135m 6.803E-1 Xe-135 1.238E+1 Xe-137 0.0

! Xe-138 0.0 L

- B. lodines 1-131 2.439E-2 l l-132 2.794E-5 1-133 2.498E-2

[ 1-134 3.467E-10 l l-135 4.233E-3 C. Others Cs-137 3.360E-3 Te-132 0.0 l

l Sr-89 0.0 l . Sr-90 0.0 Ba-140 0.0 La-140 0.0 l

(

l l

l i

l l

l l

P

Reference:

Fax, Mr. Peter Cullinan. NYPA, December 15,1998

' J. A. Fit: patrick Tables-12/98 Page C-16 nmpc\raddose128647isdslappc

Table C-12: Default Radionuclide Abundances Steam Line Break (Steam Only)"

Source 9

Radionuclide Group Strength (Ci/sec)

A. Noble Gases Kr-83m 1.517E-5 Kr-85m 2.725E-5 Kr-8$ 8.917E-8 Kr-87 8.917E-5 Kr-88 8.917E-5 Kr-89 5.800E-4 Xe-131m 6.692E-8 Xe-133 3.658E-5 Xe-133m 1.292E-6 Xe-135m 1.158E-4 Xe-135 9.833E-5 Xe-137 6.692E-4 Xe-138 3.975E-4 B. Iodmes I-131 9.808E-4 I-132 7.628E-3 I-133 6.536E-3 l'-134 I-135 1.380E-2 9.075E-3 g

C. Others -

Cs-137 1.198E-5 Te-132 6.900E4 Sr-89 1.489E-4 Sr-90 1.126E-5 Ba-140 4.358E-4 La-140 0.0

Reference:

Personal Communication, Mr. Nicholas Avrakotos, NYPA, September 11,1995.

J. A. Fit patrick Tables Page C-17 g' pts!!476nimo/sds/appc

r~, .

Table C-13: Default Radionuclide Abundances Steam Line Break (Two Phase)" ,

Source Radionuclide Group Strength (Ci/sec)

A. Noble Gases l Kr-83m 1.517E-5 l Kr-85m 2.725E-5 I Kr-85 8.917E-8 l Kr-87 8.917E-5 Kr-88 8.917E-5 ,

Kr-89 5.800E-4 Xe-131m 6.692E-8 Xe-133 3.658E-5 Xe-133m 1.292E-6 Xe-135m 1.158E-4 Xe-135 9.833E-5 Xe 137 6.692E-4 3.975E-4 I Xe 138 j

B. Todmes I-131 9.808E-4 l I-132 7.623E-3 6.536E-3 l 1-133

, r-134 1.380E-2 j I-135 9.075E-3 i C. QIhm Cs-137 1.198E-5 Te-132 6.900E-4 Sr-89

• 1.489E-4 Sr-90 1.126E-5 Ba-140 4.358E-4 La-140 0.0 1

l i

I I

Reference:

Personal Communication, Mr. Nicholas Avrakotos, NYPA, September 11,1995.

l Page C-18 g/ pts /1476nimo/sds/appe J. A. Fl= patrick Tables

Table C-14: Default Radionuclide Abundances Control Rod Drop" Source O

Radionuclide Group Strength (Ci/sec)

A. Noble Gases Kr-83m 1.577E-3 Kr-85m 3.386E-3 Kr-85 1.156E-4 Kr-87 6.494E-3 Kr-88 9.200E-3 Kr-89 1.144E-2 Xe-131m 7.953E-5 Xe-133 2.781E-2 Xe-133m 1.159E 3 Xe-135m 5.2392-3 Xe-135 3.589E-3 Xe-137 2.440E-2 Xe-138 2.316E-2 B. Indines I-131 1.323E-4 I-132 1.933E-4 I-133 2.766E-4 T-134 I-135 3.044E-4 2.612E-4 g

Qthm C.

Cs-137 1.671E 5 Te-132 0.0 Sr-89 0.0 Sr-90 0.0 Ba-140 0.0 La-140 0.0

Reference:

Personal Communication, Mr. Nicholas Avrakotos, NYPA, September 11,1995.

J. A. Fit: patrick Tables Page C-19 g! pts /1476nimotsdslappe

f . .

Il e Table C-15: Default Radionuclide Abundances Loss of Coolant Accident' <

Source Radionuclide Group Strength (Ci/sec)

A. Noble Gases Kr-83m 1.353E+0 Kr-85m 2.906E+0 {

Kr-85 1.301E-1 Kr-87 5.572E+0 Kr-88 7.894E+0 Kr-89 9.817E+0 Xe 131m 6.825E-2 Xe-133 2.386E+1 Xe-133m 9.942E-1 Xe-135m 4.494E+0 Xe-135 3.081E+0 Xe-137 2.094E+1 1.988E+1 I Xe-138 B. Iodmes I-131 3.406E-2 I-132 4.975E-2 1-133 7.119E-2 I"-134 7.839E-2 I-135 6.725E-2 C. Others Cs-137 3.583E-3 Te-132 8.178E-3 Sr-89 2.132E-3 Sr-90 2.228E-4 .

Ba-140 4.094E-3 La-140 4336E-5

Reference:

Personal Communication, Mr. Nicholas Avrakotos, NYPA, September 11,1995.

J. A. Ficpatrick Tables Page C-20 g/ pts /N76nimotsdslappc

f . T Table C-16: Default Radionuclide Abundances Source O

Radionuclide Group Strength (Ci/sec)

A. Noble Gases (Reserved For Future Use,If Necessary)

Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133 Xe-133m Xe-135m Xe-135 Xe-137 Xe-138 B. Todmes .

1-131 1-132 I-133 h

I-134 {

I-135 -

C. Others Cs-137

• Te-132 Sr-89 Sr-90 Ba-140 La-140

. l l

l l

J. A. Ficpatrick Tables Page C-21 g/ pts /1476nimcvsds/appe 1

1

i . .

Table C-17: Default Radionnelide Abundances -

O Source Radionuclide Group Strength (Ci/sec)

A. Noble Gases (Reserved For Future Use,If Necessary)

Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m i Xe-133 Xe-133m Xe-135m Xe-135 1 1

Xe-137 Xe-138 B. Iodines 1-131 1:132 1-133 1-134 1-135 C. Others Cs-137 Te-132 i Sr-89 Sr-90 Ba-140 La-140 l

O J. A. Fit patrick Tables Page C-22 gipts/1476nimalsds/appe

Table C-18: Dose Factors Four Day O

_ ". Exposure from External Material Exposure from Inhalation Thyroid Deposited on Plume (rem /hr '(rem /hr per Ground (rem /hr (rem /hrfer o pCi/cm3 )a A. Mohlg_Gassa eer uCi/cm3)* Ci/cm )" ner uCi/cm3)+

Kr-83m 5.4E-2'* 0.0 0.0 0.0 Kr-85m 93E+1 0.0 0.0 0.0 Kr-85 1.3E4 0.0 0.0 0.0

~

Kr-87 5.lE+2 0.0 0.0 0.0 Kr-88 1.3E+3 0.0 0.0 0.0 Kr-89 1.2E+3 0.0 0.0 0.0 Xe-131m 4.9E4 0.0 0.0 0.0 Xe-133 2.0E+1 0.0 0.0 0.0 Xe-133m 1.7E+1 0.0 0.0 0.0 Xe-135m 2.5E+2 0.0 0.0 0.0 Xe-135 1.4E+2 0.0 0.0 0.0 Xe-137 1.lE-2 0.0 0.0 0.0 Xe-138 7.lE+2 0.0 0.0 0.0 B. Iodmes I,-131 2.2E+2 3.9E+4 1.3E+6 13E+4 I-132 1.4E+3 4.6E+2 7.7E+3 3.1E+3 I-133 3.5E+2 7.0E+3 2.2E+5 73E*3 1-134 1.6E+3 1.6E+2 ~

1.3E+3 13E+3 I-135 9.5E+2 1.5E+3 3.8E+4 5.7E+3 C. Others Cs-137 3.5E+2 3.8E+4 0.0 2.4E+3 Te-132 1.2E+2 1.1E+4 0.0 6.6E+2 Sr-89 8.2E-2 5.0E+4 0.0 5.2E-1 Sr-90 0.0 1.6EM 0.0 0.0 Ba-140 1.lE+2 4.5E+3 0.0 7.0E+2 La-140 1.4E+3 5.8E+3 0.0 4.1E+3 EPA 400, Table 5-3 EPA 400, Table 5-4 EPA-400, Table 5 5

~

DO-88, U.S. Department of Energy, External Dose-Rate Conversion Factors for Calculation of Dose to the Public, DOE /EH-0070. U.S. Dept. of Energy, Washington 1988.

J. A. Ficpatrick Tables Page C-13 g' pts /l476nimalsds/appc

p .. ,

l ,q Table C-18: Dose Factors (Cont'd) v Dose Rate From Material Deposited on Ground (rem / day per A. Noble Gass C.jlm2 )~

Kr-83m 0.264 Kr-85m 54.5 Kr-85 0.693 Kr-87 213 Kr-88 675 Kr-89 213 Xe-131m 5.8 Xe-133 15.3 Xe-133m 14.1 Xe-135m 233 Xe-135 83.3 Xe-137 0.0 l Xe-138 0.0 )

B. Iodmes A hl31 123 U I-132 660 I-133 185 I-134 742 ,

I-135 433 C. Others Cs-137 168 Te-132 77.5 Sr-89 0.0 Sr-90 0.0 Ba-140 46.8 La-140 635 i

l l

I 1

l l

l O ~ Pacific Nonhwest Laboratory, The Mesored Dose Assessment Model,NUREG/CR-4000, Vol.1, March 1986, Table C.4.

J. A. Ficpatrick Tables Page C-24 gipts/1476nimalsds/appe

Table C-19: Survey Point Receptors Distance (mi) Direction (deg) Descriction O

b]D 1 0.9 180.0 ERPA1 2 1.4 101.5 ERPA 2 3 1.0 221.0 ERPA 3 4 2.7 131.5 ERPA 4 5 2.3 179.0 ERPA5 6 2.5 222.0 ERPA 6 1

7 4.8 109.0 ERPA 7 8 5.5 121.0 ERPA 8 1

9 3.6 146.0 ERPA 9 10 3.6 147.0 ERPA 10 11 4.0 196.0 ERPA11 12 4.5 225.0 ERPA 12 O )

13 6.3 231.0 ERPA 13 -

14 8.2 87.0 ERPA 14 15 6.9 90.0 ERPA 15 16 8.6 111.0 ERPA 16 17 7.9 117.0 ERPA 17 18 6.2 157.0 ERPA 18 19 5.9 213.5 ERPA 19 20 7.6 172.0 ERPA 20

Reference:

Personal Communication, Mr. James DJones, NMPC, September 20,1993.

J. A. Finpatrick Tables Page C-25 g/ pts /1476nima'sdslappe

p.

i l

• SurveyPointReceptors (Cont'd)

Table C-19:

l h Dietmare (mi) Direction (deel Descrintion l '21 7.4 211.0 ERPA 21

22. 7.8 223.5 ERPA 22 23 6.5 230.0 ERPA 23 24 7.7 207.0 ERPA 24 25 9.5 195.0 ERPA 25 -

26 2.0 270.0 ERPA 26 27 2.0 79.0 ERPA 27 28 5.0 270.0 ERPA 28 29 5.0 79.0 ERPA 29 30 6.6 229.0 LS 31 . 7.8 95.0 E7 32 9.3 117.0 F7 33 6.1 135.0 -

G7 34 9.2 156.0 H7 35 11.1 176.0 J7 36 9.0 201.0 K7 37 9.6 220.0 L7 38 2.2 178.0 J3 39 2.6 205.0 K3 40 3.1 221.0 L3 O *

Reference:

Personal Communication. Mr. James D. Jones, NMPC, September 20,1993.

J. . Repatrick Tables Page C-26 g/ pts /l476nimo/sds/appi

~

Table C-20: Protective Action Recommendations Forecast Doses (rem) .

O PAR TEDE CDE Thyroid Shelter 2 0.1 2 0.5 Evacuate 2f.0 25.0 Initial Denosition (uci/m2)

PAR

• I-131 Cs-137 Sr-90 Sr-89 Initiate preventative 0.13 3 0.5 8 agricultural actions Initiate emergency agricultural 1.3 30 5 80 actions

~

G l

l

Reference:

Personal Communication, Mr. James D. Jones, NMPC, May 24,1993, and June 7,1993.

Reference:

EPA, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, EPA 400-R-92-001, May,1992.

l l

J. A. Ficpatrick Tables Page C-27 g! pts /1176nimo/sds/appe j

Table C-21: Sectors Affecting ERPAs by Distance and Direction' acc mexs -

Sector 2jdlic 5 Mile 10 Mile 1

N 27,26 - 28,29 {

l NNE 27 - 29 NE 27 - 29 ENE 27,1 - 29 E 27,1,2 4, 7 14,15,29 ESE 1, 2 4, 7 8,15,16,17 SE 1,2 4,5,9 8,17,18 SSE 1, 2, 3 4,5,9,10 18,19,20 ,

S 1, 3 5,10 19,20 SSW 1,3 5,6,10,11,12 13, 19, 20, 21, 22,

'O 23,24,25

~

SW 1,3 6,11,12,26 13, 21, 22, 23,

- 24,28 WSW 1,3,26 6,12 13,22,28 l

W 26 - 28 WNW 26 - 28 NW 26 - 28 NNW 26 - 28 Personal Communication, Mr. James D. Jones, NMPC, June 1,1993.

- In the event TIBL fonnation is predicted and shoreline fumigation occurs, an additional sector on both sides of those shown above are considered in determining dose and deposition within ERPAs.

l Page C-28 g/ pts /1476nimo'sds/appc J. A. Ficpatrick Tables

r d l

. I r

ATTACHMENT A

'O 1

EDAMS - DEFAULT ISOTOPIC RELEASE RATES TO THE ATMOSPHERE

1. INTRODUCTION Default isotopic release rates to the atmosphere were prepared for the following design-basis accidents:

(a) Less of Coolant Accident (LOCA) - Drywell Leakage.

(b) LOCA - Enginee' red Safety Feature (ESF) Component Leakage, (c) Main Steam Line Break (MSLB), ,

(d) Control Rod Drop Accident (CRDA), and l (e) Refueling Accident (RA).

Note that there are three differences between the above set of accidents and those currently j in the EDAMS software, as follows:

(1) ESF component leakage [ Item (b) above] is a standard contributor to offsite and control room radiation exposures; it is not currently in EDAMS.

1 (2) The MSLB accident is for a two-phase break flow; there is no scenario in the f

(]

V UFSAR where only steam is being released from the break (as assumed in one of the EDAMS scenarios).

(3) The current EDAMs software includes an accident identified as " Containment DBA". Since there is no description of what this accident represents, it was not included in the new analyses.

It is recommended that the ESF component-leakage scenario replace the EDAMS MSLB steam-release scenario.

Section 2 which follows presents the basic assumptions employed in the analyses of the various accidents. Section 3 presents the results in tabular and graphical forms (as a function of post-accident time), and Sec. 4 presents listings of the files which will supersede the existing EDAMS files.

2. BASIC DATA AND ASSUMPTIONS 2.1 General (a) In addition to halogens and noble gases, EDAMS was programmed to O accommodate certain particulates (such as Cs137, Sr90, etc.) which are not b typically considered in the evaluation of offsite radiation exposures following

1 e.

l 4

design-basis accidents at existing nuclear power plants. In order to provide a consistent set of release rates for all isotopes of interest, use was made of recent information provided in NUREG-14652 regarding the post-accident core-release ,

fractions into containment. The halogen and noble-gas release fraction.c (and gap  !

I fractions) in this reference differ from those used in the JAF UFSAR analyses. For instance, the post-LOCA airborne halogen fraction is now 30%, slightly higher that the 25% value in the UFSAR.

However, for the control rod drop and refueling accidents, where the released activity is that in the fuel gaps, the NUREG-1465 model reduces the release rates to the atmosphere by a factor of 2.

(b) The analyses were carried out using the CRE ELISA computer code. The list of radionuclides provided as input to the code corisisted of the following:

1. Nuclides in the EDAMS data base, and

2. Important precursors of these nuclides.

1 1

The final tabulations for EDAMS were then prepared by extracting the information for the nuclides of interest from the ELISA computer runs. Release rates for the precursors and other decay products not in the EDAMS data base were ignored.

(c) Core inventories for the radionuclides of interest were extracted from information provided by GE for the FitzPatrick nuclear power plant2 (adjusted to the pre-uprate power level of 2436 MWt plus 2% uncertainty).

1 The subsections which follow present the basic data and assumptions used in the various l accident scenarios analyzed.

2.2 LOCA - Drywell Leakage (a) A LOCA takes place at full power.

(b) The fractions of core inventories (for the radionuclides of interest) becoming airborne within the drywell at the time of the accident are as follows (gap plus early in-vessel release fractions, from NUREG-1465):

Noble gases (Kr, Xe) 100 %

Halog:ns (Br, I) . 30%

Alkali metals (Cs, Rb)  : 25 %

' NUREG-1465. " Accident Source Terms for Light-Water Nuclear Power Plar.ts". 2/1995 2 GE letter addressed to Richard Chau. NYPA from G. H. Stoll. GE Plant Performance Engineering.

titled "J. A. FitzPatrick (JAFNPP) Power Uprate Program - Formal Transmittal of Final Source Term Anal.ssis Results" (5/2/91)

d o

i A Tellurium group (Te)  : 5%

V Barium / Strontium (Ba, Sr) :  : 2%

Lanthanides (La)  : 0.02 %

1 (c) Plateout within the drywell is ignored and all initially airborne radionuclides are available for release. Izakage from the drywell is at the rate of 1.5% per day.

)'

(d) All radionuclides leaking from the drywell are exhausted to the atmosphere via the Standby Gas Treatment System (SGTS) and the main stack without mixing in the reactor building.

(e) The SGTS filter efficiency is 99% for the removal of all radionuclides, except noble gases. I l

2.3 LOCA - ESF Component Leakage l (a) The entire released inventory listed under Sec. 2.2, with the exception of the noble l gases, mixes uniformly with the coolant in the RHR system (113,400 cu ft). l (b) The ESF leakage rate is 5 gpm, and is constant from the start of the LOCA through the duration of the accident. (Gross failure of a passive component, typically I assumed to take place 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the accident and amounting to 50 gpm for 30

(']

(_) minutes, was ignoted.)

(c) 10% of the radionuclide inventory in the leaking fluids becomes airborne and is instantly released to the atmosphere (without mixing in the RB) through the SGTS (with 99% filtration). (Note: Mixing within the RB is normally accounted for, leading to a release rate to the atmosphere which initially increases with time, as the materiai accumulates within the RB, and then decreases.)

2.4 Main Steam Line Break 1

(a) A main steam line break occurs outside containment during full power operation.

l (b) The MSIVs close in 10.5 seconds after the break (UFSAR Sec. 14.6.1.5.1.e)

(c) The location of the break and the steam /two-phase flow rates through the break are as shown in Supplement 25 to the original FSAR, Special Report, titled Effects of High Energy Piping System Breaks Outside of Primary Containment", pg 21 (7/22/74).

(d) The ensuing high fuel temperatures do not lead to fuel damage (UFSAR Sec.14.6).

(

( (e) The noble gas fission product concentrations in the steam correspond to the design

b I

values which would yield the standard release rate to the atmosphere during normal operation (i.e., 100,000 pCi/sec following a 30-minute decay). Fifty percent of all noble gases leaving the reactor vessel during the 10.5-sec MSIV closure time (via all four steam lines) are released through the break.

The halogen and particulate source term in the discharged liquid was selected to represent the limit in the GE Standard Technical Specifications for the maximum permissible reactor coolant system (RCS) activity, namely 0.2 pCi/gm I-131 Dose Equivalent) .

(f) 100 % of the radioactivity discharged into the turbine building becomes airborne and is released to the atmosphere over a period of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The release rate was selected to be equivalent to 3 air changes per hour.

2.5 Control Rod Drop Accident (a) The reactor has been operating at full power for an extended period of time. It is shut down, taken critical, and brought back to the initial temperature conditions within 30 minutes of the departure from design power.

(b) A CRDA takes place leading to the failure of 850 fuel rods

• at a core location with a radial power peaking factor of 1.5.

(c) All activity within the gaps of the failed fuel rods is released to the reactor coolant and is instantaneously and uniformly mixed with the coolant in the pressure vessel at the time of the accident. The released activity corresponds to the following release fractions from each failed fuel rod (from NUREG-1465, gap release):

Noble gases (Kr, Xe) . 5%

Halogens (Br,1) . 5%

Alkali metals (Cs, Rb)  : 5% 1 Tellurium group (Te)  : 0%

Barium / Strontium (Ba, Sr) . 0%  !

Lanthanides (La) . 0% 1 (d) 100% of the noble gases and 10% of the halogens and alkali metals released in the pressure vessel reach the turbine and condensers.

i

' The current technical specification limit for RCS radioactivity is 3.1 pCi/gm 1-131 DE.

Revision of this value to 0.2 Cilgm I-131 DE is pending.

General Electric Report NEDO-31400. " Safety Evaluation for Eliminating the BWR Main Steam isolation Valve Closure Function and Scram Function of the Main Steam Line Radiation Monitor" (Mav ~

1987)

i n (e) As a result of elimination of the MSIV-closure and reactor-shutdown functions of the j main steam line radiation monitors, the pathway of post-CRDA atmospheric releases at JAF has changed. Under the new CRDA scenario, the MSIVs stay open and the release is to the offgas system. The eventual release to the atmosphere will then depend on the post-CRDA operating mode of the offgas system.

In the current analysis, it was assumed that, as a result of plant shutdown following a CRDA, or as a result of offgas system automatic isolation (following a 15-minute delay) due to high radiation fields at the offgas monitors, the released radioactivity will be retained within the turbine, condensers and the offgas system. Release to the environs for this scenario would then be due to leakage from the various contaminated systems into the turbine building. [ Note: This release pathway is equivalent to the standard CRDA scenario with MSIV closure, as defined in the Standard Review Plan (NUREG-0800).]

' It is assumed that 90% of the halogens and alkali metals plate out on system internal surfaces. The leakage rate amounts to 1% per day. The release to the atmospnere I is instantaneous without holdup within the turbine building.

2.6 Refueling Accident (a) The reactor has been operating at full power for an extended period of time.

'o k,) (b) The reactor is shutdown, refueling operations are initiated and a refueling accident takes place at 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after shutdown.

(c) The accident involves the dropping of a fuel assembly (from the maximum height allowed by the fuel handling equipment) and the ensuing rupture cf 125 fuel rods (a conservative estimate, from GE Technical Report NEDE-31152P, "GE Fuel Bundle Designs," Rev. 3, February 1993).

(d) The failed fuel rods were at a core location with a radial power peaking factor of {

1.5. l i

(e) All activity within the gaps of the failed fuel rods is released to the fuel pool water. l The released activity is conservatively assumed to correspond to gap release fractions listed under Item (c) in Sec. 2.5 above.

(f) 1 % of the halogens and alkali metals released as a result of the accident are assumed to be retained by the water in the fuel pool. The retention of noble gases by the pool water is negligible.

(g) Radioactive material which escapes the pool and becomes airborne within the RB is released to the atmosphere first through the reactor building vent for 8 seconds 73 (unfiltered) and then via the SGTS and the main stack -over a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period. The Cl release rate was selected to be equivalent to 3 air changes per hour.

(

't

3. RELEASE RATES TO THE ATMOSPHERE Release rates to the atmosphere associated with the accident scenarios described in Sec. 2 were O

computed using the CRE computer code ELISA. The results for the radionuclides in the EDAMS data base are presented in the figures and tables which follow as a function of post-accident time. The time dependence accounts for both radioactive decay and source depletion resulting from the release to the atmosphere. (Note: Refer to CRE JAF-ARC-RAD-027 for information on the other radionuclides considered in the analyses.)

Note that, as a result of precursor decay, the release rate to the atmosphere 01 any particular radionuclide does not necessarily decrease with time after the accident. This is particularly obvious in the case of noble gas releases as a result of ESF component leakage. In this case the noble gas release is entirely attributable to the decay of halogens accumulating on the SGTS charcoal filtration system. Indeed, as can be seen from the attached tables and figures, the total noble gas release rate peaks at about 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the accident. Note also that different nuclides peak at different times.

The release rate for refuel accident takes into consideration first the ground level, unfiltered portion, and then the elevated, filtered remainder. The user must manually enter the isotopic mix for the ground level unfiltered portion of the refuel accident. For use in the first time step only.

O O

Fs t

i JAF - DEFAULT ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL l

DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec) i Decay Time (hrs): 0.0 Ground Level Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Refueling Kr 83m 1.353E+00 0.000E+00 1.517E-05 1.577E-03 3.057E-03 3.552E-04 .

Kr 85m 2.906E+00 0.000E+00 2.725E-05 3.386E-03 1.422E+00 1.657E-01 l Kr 85 1.301E-01 0.000E+00 8.917E-08 1.516E-04 7.834E+00 9.144E-01 Kr 87 5.572E+00 0.000E+00 B.917E-05 6.494E-03 2.324E-04 2.695E-05 Kr 88 7.894E+00 0.000E+00 8.917E-05 9.200E-03 4.513E-01 5.252E-02 Kr 89 9.817E+00 0.000E+00 5.800E-04 1.144E-02 0.000E+00 0.000E+00 Xe131m 6.825E-02 0.000E+00 6.692E-08 7.953E-05 1.430E+00 1.669E-01 Xe133m 9.942E-01 0.000E+00 1.292E-06 1.159E-03 1.706E+00 1.991E+00 Xe133 2.386E+01 0.000E+00 3.658E-05 2.781E-02 4.609E+02 5.379E+01 Xe135 3.081E+00 0.000E+00 9.833E-05 3.589E-03 1.061E+02 1.238E+01 Xe135m 4.494E+00 0.000E+00 1.158E-04 5.239E-03 5.817E+00 6.803E-01 Xe137 2.094E+01 0.000E+00 6.692E-04 2.440E-02 0.000E+00 0.000E+00 Xe138 1.988E+01 0.000E+00 3.975E-04 2.316E-02 0.000E+00 0.000E+01 f- Subtotal 1.010E+02 0.000E+00 2.120E-03 1.177E-01 6.010E+02 7.014E+01 I131 3.406E-02 1.918E-03 9.80BE-04 1.323E-04 2.090E+00 2.439E-02 I132 4.975E-02 2.803E-03 7.628E-03 1.933E-04 2.402E-03 2.794E-05 I133 7.119E-02 4.011E-03 6.536E-03 2.766E-04 2.141E+00 2.498E-02 I134 7.839E-02 4.417E-03 1.380E-02 3.044E-04 2.998E-08 3.467E-10 I135 6.725E-02 3.789E-03 9.075E-03 2.612E-04 3.631E-01 4.233E-03 Subtotal 3.006E-01 1.694E-02 3.802E-02 1.168E-03 4.620E+00 5.391E-02 Cs137 3.583E-03 2.019E-04 1.198E-05 1.671E 2.878E-01 0.000E+00 3.360E-03l 0.000E-00 Te132 8.178E-03 4.606E-04 6.900E-04 0.000E+00 Sr 89 2.132E-03 1.201E-04 1.489E-04 0.000E+00 0.000E+00 0.000E-00 Sr 90 2.22BE-04 1.255E-05 1.126E-05 0.000E+00 0.000E+00 0.000E-00 Ba140 4.094E-03 2.306E-04 4.35BE-04 0.000E+00 0.000E+00 0.000E.00 La140 4.336E-05 2.443E-06 0.000E+00 0.000E+00 0.000E+00 0.000E.00 Subtotal 1.825E-02 1.028E-03 1.298E-03 1.671E-05 2.87BE-01 3.621E-03 Total 1.013E+02 1.797E-02 4.144E-02 1.189E-01 6.059E+02 7.021E+01 O

I JAF - DEFAULT ISOTOP.IC INVENTORIES FOR THE "EDAMS" MODEL DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec)

Decay Time (hrs)- 0.1 Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 1.367E+00 1.663E-03 3.547E-05 1.576E-03 2.842E-04 Kr 85m 2.886E+00 5.650E-04 2.445E-05 3.358E-03 1.346E-01 Kr 85 1.301E-01 0.000E+00 6.606E-08 1.516E-04 7.503E-01 Kr 87 5.278E+00 0.000E+00 6.256E-05 6.150E-03 2.133E-05 Kr 88 7.703E+00 0.000E+00 6.447E-05 8.978E-03 4.241E-02 Kr 89 2.644E+00 0.000E+00 1.157E-04 3.081E-03 0.000E+00 Xe131m 6.828E-02 1.028E-06 5.153E-08 7.956E-05 1.370E-01 Xe133m 9.942E-01 3.025E-05 1.139E-06 1.158E-03 1.633E+00 Xe133 2.386E+01 4.256E-04 2.967E-05 2.781E-02 4.413E+01 Xe135 3.275E+00 4.872E-03 1.168E-04 3.767E-03 1.013E+01 Xe135m 4.517E+00 2.936E-02 3.106E-04 4.942E-03 5.737E-01 Xe137 7.069E+00 0.000E+00 1.674E-04 8.236E-03 0.000E+00 Xe138 1.482E+01 0.000E+00 2.196E-04 1.727E-02 0.000E+00 Subtotal 7.461E+01 3.692E-02 1.148E-03 8.655E-02 5.753E+01 I131 3.403E-02 1.917E-03 7.264E-04 1.322E-04 2.001E-02 I132 4.853E-02 2.733E-03 5.497E-03 1.875E-04 2.247E-05 I133 7.100E-02 4.000E-03 4.825E-03 2.756E-04 2.045E-02 I134 7.242E-02 4.081E-03 9.447E-03 2.814E-04 2.700E-10 1135 6.653E-02 3.747E-03 6.653E-03 2.584E-04 3.449E-03 Subtotal 2.925E-01 1.648E-02 2.715E-02 1.135E-03 4.416E-02 Cs137 3.583E-03 2.019E-04 8.878E-06 1.671E-05 2.757E-03 Te132 8.169E-03 4.603E-04 5.108E-04 0.000E+00 0.000E+00 Sr 89 2.133E-03 1.202E-04 1.103E-04 6.089E-08 0.000E+00 Sr 90 2.228E-04 1.255E-05 8.342E-06 0.000E+00 0.000E+00 Ba140 4.092E-03 2.306E-04 3.228E-04 0.000E+00 0.000E+00 La140 5.033E-05 2.836E-06 5.558E-07 0.000E+00 0.000E+00 Subtotal 1.825E-02 1.028E-03 9.617E-04 1.677E-05 2.757E-03 Total 7.492E+01 5.442E-02 2.926E-02 8.771E-02 5.759E+01 6

F 1 e'

JAF - DEFAULT ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec)

Decay Time (hrs): 0.5 Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 1.401E+00 7.339E-03 3.528E-05 1.556E-03 6.953E-05 Kr 85m 2.716E+00 4.847E-04 7.325E-06 3.167E-03 3.615E-02 Kr 85 1.300E-01 3.344E-10 1.990E-08 1.515E-04 2.149E-01 Kr 87 4.242E+00 0.000E+00 1.515E-05 4.944E-03 4.869E-06 Kr 88 6.983E+00 0.000E+00 1.761E-05 8.142E-03 1.097E-02 Kr 89 1.390E-02 0.000E+00 1.833E-07 1.620E-05 0.000E+00 Xe131m 6.833E-02 5.133E-06 1.786E-08 7.958E-05 3.937E-02 Xe133m 9.933E-01 1.495E-04 5.603E-07 1.156E-03 4.676E-01 Xe133 2.386E+01 2.106E-03 1.200E-05 2.781E-02 1.265E+01 Xe135 4.008E+00 2.413E-02 8.931E-05 4.433E-03 2.896E+00 Xe135m 4.961E+00 1.165E-01 2.312E-04 4.239E-03 3.525E-01 Xe137 9.181E-02 0.000E+00 6.550E-07 1.070E-04 0.000E+00 Xe138 4.581E+00 0.000E+00 2.044E-05 5.339E-03 0.000E+00 Subtotal 5.405E+01 1.507E-01 4.297E-04 6.114E-02 1.666E+01

) I131 3.397E-02 1.915E-03 2.185E-04 1.320E-04 5.724E-03 I132 4.392E-02 2.475E-03 1.485E-03 1.662E-04 5.677E-06 I133 7.011E-02 3.950E-03 1.434E-03 2.719E-04 5.778E-03 1134 5.27BE-02 2.972E-03 2.074E-03 2.050E-04 5.562E-11 1135 6.378E-02 3.594E-03 1.921E-03 2.478E-04 9.459E-04 Subtotal 2.645E-01 1.491E-02 7.133E-03 1.023E-03 1.252E-02 Cs137 3.583E-03 2.019E-04 2.674E-06 1.671E-05 7.897E-04 Te132 8.139E-03 4.586E-04 1.533E-04 0.000E+00 0.000E+00 Sr 89 2.138E-03 1.203E-04 3.322E-05 3.572E-07 0.000E+00 Sr 90 2.227E-04 1.255E-05 2.512E-06 0.000E+00 0.000E+00 Ba140 4.089E-03 2.303E-04 9.714E-05 0.000E+00 0.000E+00 La140 7.808E-05 4.400E-06 8.339E-07 0.000E+00 0.000E+00 Subtotal 1.825E-02 1.028E-03 2.897E-04 1.707E-05 7.897E-04 Total 5.434E+01 1.667E-01 7.853E-03 6.218E-02 1.668E+01 c . - .

JAF - DEFAULT ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec) l I

Decay Time (hrs): 3.0 Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 1.404E+00 1.256E-02 1.278E-05 3.505E-03 1.285E-05 Kr 85m 2.513E+0C 4.467E-04 1.513E-06 2.931E-03 7.473E-03 Kr 85 1.300E-01 6.958E-10 4.442E-09 1.515E-04 4.801E-02 Kr 87 3.228E+00 0.000E+00 2.574E-06 3.764E-03 8.282E-07 Kr 88 6.181E+00 0.000E+00 3.478E-06 7.203E-03 2.169E-03 Kr 89 1.968E-05 0.000E+00 0.000E+00 2.294E-08 0.000E+00 Xe131m 6.844E-02 1.025E-05 4.636E-09 7.967E-05 8.969E-03 Xe133m 9.919E-01 2.947E-04 1.843E-07 1.153E-0.' 1.064E-01 Xe133 2.388E+01 4.156E-03 3.519E-06 2.778E-02 2.855E+00 Xe135 4.831E+00 4.681E-02 3.456E-05 5.181E-03 6.971E-01 Xe135m 5.800E+00 1.920E-01 6.078E-05 3.836E-03 3.156E-01 Xe137 4.025E-04 0.000E+00 6.408E-10 4.692E-07 0.000E+00 Xe138 1.056E+00 0.000E+00 1.051E-06 1.230E-03 0.010E+00 Subtotal 5.008E+01 2.563E-01 1.204E-04 5.481E-02 4.041E+00 I131 3.392E-02 1.911E-03 4.867E-05 1.317E-04 1.276E-03 k I132 3.889E-02 2.192E-03 2.897E-04 1.429E-04 1.019E-06 I133 6.897E-02 3.886E-03 3.147E-04 2.674E-04 1.269E-03 I134 3.553E-02 2.002E-03 3.117E-04 1.380E-04 8.367E-12 1135 6.050E-02 3.408E-03 4.069E-04 2.351E-04 2.005E-04 Subtotal 2.378E-01 1.340E-02 1.372E-03 9.151E-04 2.761E-03 Cs137 3.583E-03 2.019E-04 5.967E-07 1.671E-05 1.764E-04 Te132 8.100E-03 4.564E-04 3.406E-05 0.000E+00 0.000E+00 Sr 89 2.138E-03 1.203E-04 7.411E-06 4.814E-07 0.000E+00 Sr 90 2.226E-04 1.254E-05 5.606E-07 0.000E+00 0.000E+00 Ba140 4.083E-03 2.300E-04 2.165E-05 0.000E+00 0.000E+00 La140 1.124E-04 6.336E-06 3.703E-07 0.000E+00 0.000E+00 Subtotal 1.824E-02 1.027E-03 6.464E-05 1.719E-05 1.764E-04 Total 5.033E+01 2.707E-01 1.557E-03 5.574E-02 4.045E+00 0

r i

JAF - DEFAULT ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec)

Decay Time (hrs): 2.0 Elevated Nuclide LOCA' ESF Leak MSLB CRDA Refueling Kr 83m 1.326E+00 .1.839E-02 8.922E-07 1.348E-03 4.391E-07 Kr 85m 2.152E+00 3.825E-04 6.453E-08 2.508E-03 3.194E-04 l Kr 85 1.299E-01 1.339E-09 2.212E-10 1.514E-04 2.396E-03 l Kr 87 1.871E+00 0.000E+00 7.431E-08 2.181E-03 2.396E-08 l Kr 88 4.839E+00 0.000E+00 1.356E-07 5.642E-03 8.480E-05 Kr 89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe131m 6.861E-02 2.042E-05 2.953E-10 7.978E-05 6.729E-04 Xe133m 9.894E-01 5.731E-04 1.488E-08 1.148E-03 8.339E-03 Xe133 2.389E+01 8.097E-03 2.565E-07 2.777E-02 1.854E-01 Xe135 6.228E+00 8.619E-02 3.008E-06 6.447E-03 1.166E-01 Xe135m 7.433E+00 3.036E-01 2.908E-06 3.397E-03 2.831E-01 Xe137 7.739E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe138 5.606E-02 0.000E+00 2.781E-09 6.533E-05 0.000E+00 j

Subtotal 4.898E+01 4.173E-01 7.358E-06 5.073E-02 5.969E-01 O

( ,) I131 3.378E-02 1.904E-03 2.414E-06 1.312E-04 6.346E-05 1132 3.086E-02 1.739E-03 1.111E-05 1.057E-04 4.027E-08 I133 6.672E-02 3.761E-03 1.516E-05 2.585E-04 6.126E-05 I134 1.610E-02 9.078E-04 7.036E-06 6.25bE-05 1.894E-13 I135 5.444E-02 3.069E-03 1.824E-05 2.116E-04 9.009E-06 Subtotal 2.019E-01 1.138E-02 5.396E-05 7.696E-04 1.344E-04 Cs137 3.581E-03 2.018E-04 2.969E-08 1.670E-05 8.803E-06 Te132 8.022E-03 4.522E-04 1.681E-06 0.000E+00 0.000E+00 Sr 89 2.136E-03 1.202E-04 3.689E-07 5.206E-07 0.000E+00 Sr 90 2.225E-04 1.254E-05 2.792E-08 0.000E+00 0.000E+00 Ba140 4.069E-03 2.294E-04 1.076E-06 0.000E+00 0.000E+00 I

La140 1.801E-04 1.015E-05 3.653E-08 0.000E+00 0.000E+00 Subtotal 1.E21E-02 1.026E-03 3.219E-06 1.722E-05 8.803E-06 l Total 4.920E+01 4.297E-01 G.454E-05 5.152E-02 5.971E-02 l

1 l

l

1 iI JAF - DEFAULT ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec) 1 Decay Time (hrs): 3.0 Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 1.1G6E+00 2.022E-02 4.744E-08 1.161E-03 1.500E-08 Kr 85m 1.842E+00 3.275E-04 2.752E-09 2.148E-03 1.366E-05 l Kr 85 1.298E-01 1.890E-09 0.000E+00 1.514E-04 1.195E-04  !

Kr 87 1.084E+00 0.000E+00 2.145E-09 1.264E-03 6.932E-10 l Kr 88 3.789E+00 0.000E+00 5.289E-09 4.417E-03 3.314E-06 l Kr 89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe131m 6.881E-02 3.053E-05 0.000E+00 7.992E-05 2.591E-04 }

Xe133m 9.864E-01 8.356E-04 1.011E-09 1.142E-03 3.409E-03 l Xe133 2.390E+01 1.183E-02 1.666E-08 2.774E-02 5.148E-02 l Xe135 7.333E+00 1.180E-01 2.024E-07 7.456E-03 8.134F-02 l Xe135m 8.722E+00 3.881E-01 1.309E-07 3.056E-03 2.5c -01 j Xe137 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l Xe138 2.975E-03 0.000E+00 0.000E+00 3.469E-06 0.000E+00 Subtotal 4.904E+01 5.393E-01 4.086E-07 4.862E-02 3.915E-01 1131 3.364E-02 1.896E-03 1.197E-07 1.307E-04 3.155E-06 h I132 2.489E-02 1.403E-03 4.311E-07 7.817E-05 1.4B6E-09 I133 6.453E-02 3.639E-03 7.300E-07 2.499E-04 2.957E-06 1134 7.300E-03 4.117E-04 1.589E-07 2.836E-05 4.285E-15 I135 4.900E-02 2.763E-03 8.178E-07 1.905E-04 4.048E-07 Subtotal 1.794E-01 1.011E-02 2.258E-06 6.776E-04 6.548E-06 Cs137 3.578E-03 2.017E-04 1.479E-09 1.669E-05 4.392E-07 Te132 7.947E-03 4.481E-04 8.292E-08 0.000E+00 0.000E+00 Sr 89 2.134E-03 1.201E-04 1.835E-08 5.225E-07 0.000E+00 Sr 90 2.224E-04 1.254E-05 1.389E-09 0.000E+00 0.000E+00 Ba140 4.058E-03 2.288E-04 5.342E-08 0.000E+00 0.000E+00 La140 2.463E-04 1.389E-05 2.701E-09 0.000E+00 0.000E+00 Subtotal 1.819E-02 1.025E-03 1.603E-07 1.722E-05 4.392E-07 Total 4.924E+01 5.504E-01 2.826E-06 4.932E-02 3.915E-01 0

I

l JAF - DEFAULT' ISOTOPIC-INVENTORIES FOR THE "EDAMS" MODEL DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec)

Decay Time (hrs): 4.0 Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 1.024E+00' 1.978E-02 2.251E-09 9.731E-04' 5.125E-10 Kr 85m 1.577E+00 2.806E-04 1.174E-10 1.839E-03 5.837E-07 Kr 85 1.297E-01 2.361E-09 0.000E+00 1.513E-04 5.965E Kr 87 6.283E-01 0.000E+00 0.000E+00 7.328E-04 2.005E-11 Kr 88 2.967E+00 0.000E+00 2.063E-10 3.458E-03 1.296E-07

}Q: 89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00-Xe131m -6.897E-02 4.056E-05 0.000E+00 8.003E-05 2.377E-04 Xe133m 9.831E-01 1.083E-03 0.000E+00 1.136E 3.068E-03 Xe133 2.390E+01 1.537E-02 1.016E-09 2.772E-02 4.345E-02 Xe135 8.194E+00 1.432E-01 1.219E-08 8.242E-03 7.215E-02 Xe135m 9.681E+00 4.525E-01 5.872E-09 2.750E-03 2.295E-01 Xe137 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe138 1.580E 0.000E+00 0.000E+00 1.843E-07 0.000E+00-Subtotal 4.915E+01 6.322E-01 2.165E-08 4.708E-02 3.484E-01

) I131 3.350E-02 1.889E-03' 5.942E-09 1.301E-04 5.781E-05 1.569E-07 5.487E-11 I132 2.046E-02 1.154E-03 1.694E-08 I133 6.239E-02 3.519E-03 3.514E-08 2.416E-04 1.427E-07 I134 3.308E-03 1.866E-04 3.589E-09 1.286E-05 9.698E-17 I135 4.408E-02 2.487E-03 3.667E-08 1.714E-04 1.819E-08 Subtotal 1.637E-01 9.236E-03 9.828E-08 6.139E-04 3.192E-07 Cs137 3.575E-03 2.016E-04 0.000E+00 1.669E-05 2.192E-08 Te132 7.872E-03 4.439E-04 4.092E-09 0.000E+00 0.000E+00 Sr 89 2.131E-03 1.200E-04 9.131E-10 5.222E-07 0.000E+00 Sr 90 2.222E-04 1.253E-05 0.000E+00 0.000E+00 0.000E+00 Ba140 4.047E-03 2.282E-04 2.654E-09 0.000E+00 0.000E+00 La140 3.111E-04 1.755E-05 1.776E-10 0.000E+00 0.000E+00 Subtotal 1.816E-02 1.024E-03 7.836E-09 1.721E-05 2.192E-08

. __.___. __.....__ .._______ .....____ .._______ j Total 4.933E+01 6.425E-01 1.278E-07 4.771E-02 3.484E-01 L

l'

)

l k,

i JAF -

DEFAULT ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL DESIGN-BASIS ACCIDENT RELEASE RATES TO. ATMOSPHERE (Ci/sec)

Decay Time (hrs): 8.0 Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 4.700E-01 1.154E-02 0.000E+00 4.100E-04 6.983E-16 Kr 85m 8.472E-01 1.508E-04 0.000E+00 9.889E-04 1.949E-12 Kr 85 1.294E-01 3.658E-09 0.000E+00 1.511E-04 3.697E-01 Kr 87 7.081E-02 0.000E+00 0.000E+00 8.267E-05 1.405E-17 Kr 88 1.114E+00 0.000E+00 0.000E+00 1.300E-03 3.024E-13 Kr 89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe131m 6.969E-02 7.994E-05 0.000E+00 8.053E-05 2.333E-04 Xe133m 9.664E-01 1.934E-03 0.000E+00 1.109E-03 2.675E-03 Xe133 2.385E+01 2.769E-02 0.000E+00 2.757E-02 3.773E-02 Xe135 9.819E+00 1.952E-01 0.000E+00 9.733E-03 4.740E-02 Xe135m 1.117E+01 5.686E-01 0.000E+00 1.808E-03 1.509E-01 Xe137 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe138 1.256E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Subtotal 4.851E+01 8.052E-01 0.000E+00 4.324E-02 2.389E-01 I131 3.294E-02 1.860E-03 0.000E+00 1.281E-04 0.000E+00 I132 1.150E-02 6.492E-04 0.000E+00 1.728E-05 0.000E+00 I133 5.447E-02 3.075E-03 0.000E+00 2.111E-04 0.000E+00 I134 1.396E-04 7.883E-06 0.000E+00 5.433E-07 0.000E+00 l

I135 2.892E-02 1.633E-03 0.000E+00 1.125E-04 0.000E+00 Subtotal 1.280E-01 7.225E-03 0.000E+00 4.696E-04 0.000E+00 Cs137 3.567E-03 2.014E-04 0.000E+00 1.666E-05 0.000E+00 1

! Te132 7.581E-03 4.278E-04 0.000E+00 0.000E+00 0.000E+00 Sr 89 2.121E-03 1.195E-04 0.000E+00 5.203E-07 0.000E+00 '

l Sr 90 2.217E-04 1.251E-05 0.000E+00 0.000E+00 0.000E+00 l Ba140 4.000E-03 2.259E-04 0.000E+00 0.000E+00 0.000E+00 i La140 5.572E-04 3.147E-05 0.000E+00 0.000E+00 0.000E+00 l

Subtotal 1.805E-02 1.019E-03 0.000E+00 1.718E-05 0.000E+00 Total 4.865E+01 8.134E-01 0.000E+00 4.373E-02 2.389E-01

r~% JAF - DEFAULT-ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL t

DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec)

Decay Time Ihrs): 12.0 Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 1.856E-01 5.100E-03 0.000E+00 1.516E.04 5.953E-06 Kr 85m 4.553E-01 8.114E-05 0.000E+00 5.317E-04 0.000E+00 Kr 85 1.291E-01 4.353E-09 0.000E+00 1.508E-04 0.000E+00 Kr 87 7.983E-03 0.00CE+00 0.000E+00 9.325E-06 0.000E+00 Kr 88 4.183E-01 0.000E+00 0.000E+00 4.889E-04 0.000E+00 Kr 89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe131m 7.036E-02 1.183E-04 0.000E+00 8.097E-05 1.118E-04 Xe133m 9.456E-01 2.593E-03 0.000E+00 1.079E-03 1.151E-03 Xe133 2.373E+01 3.750E-63 0.000E+00 2.737E-02 1.623E-02 Xe135 9.656E+00 1.994E-01 0.000E+00 9.572E-03 1.498E-02 Xe135m 1.049E+01 5.517E-01 0.00uE,00 1.189E-03 4.775E-02 Xe137 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Subtotal 4.609E+01 7.964E-01 0.000E+00 4.063E 02 8.023E-02 O

N ,/ I131 3.242E-02 1.832E-03 0.000E+00 1.261E-04 0.000E+00 I132 8.619E-03 4.872E-04 0.000E+00 5.169E-03 0.000E+00 I133 4.756E-02 2.688E-03 0.000E+00 1.845E-04 0.000E+00 I134 5.894E-06 3.331E-07 0.000E+00 2.295E-03 0.000E+00 I135 1.897E-02 1.072E-03 0.000E+00 7.38SE-05 0.000E+00 Subtotal 1.076E-01 6.079E-03 0.000E+00 3.896E-04 0.000E+00 Cs137 3.558E-03 2.011E-04 0.000E+00 1.663E-05 0.000E+00 Te132 7.297E-03 4.125E-04 0.000E+00 0.000E+00 0.000E+00 Sr 89 2.111E-03 1.191E-04 0.000E+00 5.181E-07 0.000E+00 Sr 90 2.211E-04 1.250E-05 0.000E+00 0.000E+00 0.000E,00 Ba140 3.956E-03 2.235E-04 0.000E+00 0.000E+00 0.000E+0L La140 7.836E-04 4.428E-05 0.000E+00 0.000E+00 0.000E+00 Subtotal 1.793E-02 1.013E-03 0.000E+00 1.715E-05 0.000E+00 Total 4.622E+01 8.035E-01 0.000E+00 4.103E-02 8.023E-02 l

l l

O V

JAF - DEFAULT ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec)

Decay Time (hrs): 18.0 Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 4.075E-02 1.244E-03 0.000E+00 3.050E-05 1.045E-06 Kr 85m 1.793E-01 3.200E-05 0.000E+00 2.097E-04 0.000E+00 Kr 85 1.286E-01 4.836E-09 0.000E+00 1.504E-04 0.000E+00 Kr 87 3.022E-04 0.000E+00 0.000E+00 3.533E-07 0.000E+00 Kr 88 9.633E-02 0.000E+00 0.000E+00 1.127E-04 0.000E+00 Kr 89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe131m 7.131E-02 1.736E-04 0.000E+00 8.161E-05 1.094E-04 Xe133m 9.083E-01 3.292E-03 0.000E+00 1.032E-03 9.419E-04 Xe133 2.344E+01 4.833E-02 0.000E+00 2.698E-02 1.329E-02 Xe135 8.028E+00 1.683E-01 0.000E+00 8.028E-03 7.983E-03 Xe135m 8.103E+00 4.361E-01 0.000E+00 6.336E-04 2.545E-02 Xe137 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.0COE+00 Xe138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Subtotal 4.099E+01 6.575E-01 0.000E+00 3.726E-02 4.777E-02 I131 3.161E-02 1.789E-03 0.000E+00 1.231E-04 0.000E+00 h I132 7.203E-03 4.122E-04 0.000E+00 8.453E-07 0.000E+00 I133 3.878E-02 2.196E-03 0.000E+00 1.507E-04 0.000E+00 I134 5.111E-08 2.894E-09 0.000E+00 1.993E-10 0.000E+00 I135 1.007E-02 5.703E-04 0.000E+00 3.928E-05 0.000E+00 Subtotal 6.774E-02 4.968E-03 0.000E+00 3.138E-04 0.000E+00 Cs137 3.544E-03 2.006E-04 0.000E+00 1.659E-05 0.000E+00 Te132 6.894E-03 3.903E-04 0.000E+00 0.000E+00 0.000E+00 Sr 89 2.096E-03 1.184E-04 0.000E+00 5.150E-07 0.000E+00 Sr 90 2.203E-04 1.247E-05 0.000E+00 0.000E+00 0.000E+00 Ba140 3.886E-03 2.200E-04 0.0]OE+00 0.000E+00 0.000E+00 La140 1.088E-03 6.161E-05 0.000E+00 0.000E+00 0.000E+00 Subtotal 1.773E-02 1.003E-03 0.000E+00 1.710E-05 0.000E+00 Total 4.110E+01 6.635E-01 0.000E+00 3.759E-02 4.777E-02 O

II f -1 JAF - _ DEFAULT ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL I

DESIGN-BASIS ACCIDENT: XELEASE RATES TO ATMOSPHERE (Ci/sec) 1 Decay Time.(hrs): . 24.0-Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 8.342E-03 2.740E-04 0.000E+00 5.756E-06 1.834E-07 Kr 85m 7.058E 1.262E-05 0.000E+00 8.267E-05 0.000E+00 Kr 85 1.281E-01 5.019E-09 0.000E+00 1.501E-04 0.000E+00 Kr 87 1.144E-05 0.000E+00 -0.000E+00 1.339E-08 0.000E+00 1 l

Kr 88 2.218E-02 0.000E+00. 0.000E+00 2 597E-05 0.000E+00 Kr 89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe131m 7.217E-02 2.266E-04 0.000E+00 8.219E-05 1.071E-04 Xe133m 8.661E-01 3.717E-03 0.000E+00 9.808E-04 7.714E-04 Xe133 2.303E+01 5.558E-02 0.000E+00 2.650E-02 1.088E-02 Xe135 6.058E+00 1.267E-01 0.000E+00- 6.125E-03 4.256E-03 Xe135m 5.653E+00 3.081E-01 0.000E+00 3.378E-04 1.357E-02 Xe137 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1

\

Subtotal 3.591E+01 4.946E-01 0.000E+00 3.429E-02 2.958E-02 O

( ,) I131 I132

'3.083E-02 6.739E-03 1.748E-03 3.822E-04 0.000E+00 0.000E+00 1.201E-04 1.383E-07 0.000E+00 0.000E+00 I133 3.164E-02 1.794E-03 0.000E+00 1.231E-04 0.000E+00 I134 4.433E-10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I135 5.350E-03 3.033E-04 0.000E+00 2.088E-05 0.000E+00 Subtotal 7.456E-02 4.228E-03 0.000E+00 2.642E-04 0.000E+00

'Cs137 3.531E-03 2.002E-04 0.000E+00 1.655E-05 0.000E+00 Te132 6.511E-03 3.692E-04 0.000E+00 0.000E+00 0.000E+00 Sr 89 -2.081E-03 1.178E-04 0'.000E+00 5.119E-07 0.000E+00 Sr 90 2.194E-04 1.244E-05 0.000E+00 0.000E+00 0.000E+00 Ba140 3.819E-03 2.166E-04 0.000E+00 0.000E+00 0.000E+00 La140 1.356E-03 7.686E-05 0.000E+00 0.000E+00 0.000E+00 Subtotal 1.752E-02 9.931E-04 0.000E+00 1.706E-05 0.000E+00 l

l

. Total 3.600E+01 4.998E-01 0.000E+00 3.457E-02 2.958E-02 l

i l

l l

'()  !

I

JAF - DEFAULT ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec) i Decay Time (hrs)- 36.0 Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 3.186E-04 1.161E-05 0.000E+00 1.888E-07 5.647E-09 Kr 85m 1.094E-02 1.964E-06 0.000E+00 1.285E-05 0.000E+00 Kr 85 1.272E-01 5.103E-09 0.000E+00 1.493E-04 0.000E+00 Kr 87 1.638E-08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr 88 1.175E-03 0.000E+00 0.000E+00 1.380E-06 0.000E+00 Kr 89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe131m 7.372E-02 3.256E-04 0.000E+00 8.322E-05 1.026E-04 Xe133m 7.750E-01 4.025E-03 0.000E+00 8.761E-04 5.172E-04 Xe133 2.202E+01 6.269E-02 0.000E+00 2.538E-02 7.294E-03 Xe135 2.989E+00 6.119E-02 0.000E+00 3.097E-03 1.209E-03 Xe135m 2.360E+00 1.303E-01 0.000E+00 9.597E-05 3.856E-03 Xe137 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Subtotal 2.836E+01 2.586E-01 0.000E+00 2.969E-02 1.298E-02 I131 2.933E-02 1.668E-03 0.000E+00 1.145E-04 0.000E+00 I132 5.989E-03 3.406E-04 0.000E+00 3.697E-09 0.000E+00 I133 2.105E-02 1.198E-03 0.000E+00 8.208E-05 0.000E+00 I134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1135 1.509E-03 8.583E-05 0.000E+00 5.906E-06 0.000E+00 Subtotal 5.788E-02 3.292E-03 0.000E+00 2.025E-04 0.000E+00 Cs137 3.506E-03 1.994E-04 0.000E+00 1.646E-05 0.000E+00 Te132 5.811E-03 3.306E-04 0.000E+00 0.000E+00 0.000E+00 Sr 89 2.051E-03 1.165E-04 0.000E+00 5.061E-07 0.000E+00 Sr 90 2.178E-04 1.239E-05 0.000E+00 0.000E+00 0.000E+00 Ba140 3.689E-03 2.099E-04 0.000E+00 0.000E+00 0.000E+00 La140 1.793E-03 1.020E-04 0.000E+00 0.000E+00 0.000E+00 Subtotal 1.707E-02 9.707E-04 0.000E+00 1.697E-05 0.000E+00 Total 2.843E+01 2.628E-01 0.000E+00 2.991E-02 1.298E-02 O

__9

t JAF - DEFAULT ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec)

Decay Time (hrs): 48.0 Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 1.149E-05 4.503E-07 0.000E+00 5.936E-09 1.740E-10 Kr 85m 1.697E-03 3.056E-07 0.000E+00 1.998E-06 0.000E+00 Kr 85 1.262E-01 5.100E-09 0.000E+00 1.485E-04 0.000E+00 Kr 87 0,000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr 88 6.231E-05 0.000E+00 0.000E+00 7.333E-08 0.000E+00 Kr 89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe131m 7.503E-02 4.161E-04 0.000E+00 8.403E-05 9.825E-05 Xe133m 6.822E-01 3.900E-03 0.000E+00 7.728E-04 3.467E-04 Xe133 2.085E+01 6.372E-02 0.000E+00 2.411E-02 4.889E-03 Xe135 1.340E+00 2.666E-02 0.000E+00 1.421E-03 3.436E-04 Xe135m 84831E-01 4.914E-02 0.000E+00 2.728E-05 1.096E-03 Xe137 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Subtotal 2.396E+01 1.438E-01 0.000E+00 2.657E-02 6.773E-03

) I131 2.789E-02 1.592E-03 0.000E+00 1.091E-04 0.000E+00 1132 5.342E-03 3.050E-04 0.000E+00 0.000E+00 0.000E+00 I133 1.401E-02 7.994E-04 0.000E+00 5.475E-05 0.000E+00 1134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I135 4.256E-04 2.429E-05 0.000E+00 1.670E-06 0.000E+00 Subtotal 4.766E-02 2.721E-03 0.000E+00 1.655E-04 0.000E+00 Cs137 3.478E-03 1.985E-04 0.000E+00 1.638E-05 0.000E+00 Te132 5.186E-03 2.958E-04 0.000E+00 .0.000E+00 0.000E+00 Sr 89 2.022E-03 1.152E-04 0.000E+00 5.000E-07 0.000E+00 0.000E+00 I Sr 90 2.162E-04 1.234E-05 0.000E+00 0.000E+00 I

Ba140 3.564E-03 2.034E-04 0.000E+00 0.000E+00 0.000E+00 La140 2.121E-03 1.211E-04 0.000E+00 0.000E+00 0.000E+00 Subtotal 1.659E-02 9.464E-04 0.000E+00 1.688E-05 0.000E+00 Total 2.402E+01 1.475E-01 0.000E+00 2.675E-02 6.773E-03 l

O l  !

3 JAF - DEFAULT ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec)

Decay Time (hrs): 60.0 Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 4.036E-07 1.667E-08 0.000E+00 1.841E-10 0.000E+00 Kr 85m 2.632E-04 4.753E-08 0.000E+00 3.106E-07 0.000E+00 Kr 85 1.252E-01 5.081E-09 0.000E+00 1.478E-04 0.000E+00 Kr 87 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr 88 3.303E-06 0.000E+00 0.000E+00 3.897E-09 0.000E+00 Kr 89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe131m 7.608E-02 4.983E-04 0.000E+00 8.467E-05 9.408E-05 Xe133m 5.942E-01 3.569E-03 0.000E+00 6.756E-04 2.324E-04 Xe133 1.961E+01 6.164E-02 0.000E+00 2.279E-02 3.278E-03 Xe135 5.719E-01 1.105E-02 0.000E+00 6.192E-04 9.769E-05 Xe135m 3.108E-01 1.739E-02 0.000E+00 7.750E-06 3.114E-04 Xe137 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Subtotal 2.129E+01 9.415E-02 0.000E+00 2.432E-02 4.013E-03 I131 2.652E-02 1.519E-03 0.000E+00 1.040E-04 0.000E+00 1132 4.767E-03 2.730E-04 0.000E+00 0.000E+00 0.000E+00 I133 9.322E-03 5.339E-04 0.000E+00 3.653E-05 0.000E+00 I134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I135 1.200E-04 6.872E-06 0.000E+00 4.7222-07 0.000E+00 Subtotal 4.073E-02 2.333E-03 0.000E+00 1.410E-04 0.000E+00 Cs137 3.453E-03 1.977E-04 0.000E+00 1.630E-05 0.000E+00 Te132 4.628E-03 2.650E-04 0.000E+00 0.000E+00 0.000E+00 Sr 89 1.993E-03 1.139E-04 0.000E+00 4.942E-07 0.000E+00 Sr 90 2.146E-04 1.229E-05 0.000E+00 0.000E+00 0.000E+00 Ba140 3.444E-03 1.972E-04 0.000E+00 0.000E+00 0.000E+00 La140 2.364E-03 1.354E-04 0.000E+00 0.000E+00 0.000E+00 Subtotal 1.610E-02 9.214E-04 0.000E+00 1.679E-05 0.000E+00 Total 2.135E+01 9.741E-02 0.000E+00 2.448E-02 4.013E-03 e

i 9

7-4:

.?.

JAF - ' DEFAULT ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL O DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec)

Decay Time (hrs): 72.0 Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 1.392E-08 5.986E-10 0.000E+00 0.000E+00 0.000E+00 Kr 85m 4.081E-05 7.394E-09 0.000E+00' 4.828E-08 0.000E+00 Kr 85- 1.243E-01 5.058E-09 0.000E+00 1.470E-04 0.000E+00 Kr 87 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr 88 1.750E-07 0.000E+00 0.000E+00 2.070E-10 0.000E+00 <

Kr 89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe131m 7.694E-02 5.731E-04 0.000E+00 8.517E-05 9.014E-05  ;

Xe133m 5.133E-01 3.161E-03 0.000E+00 5.867E-04 1.558E-04

Xe133 1.838E+01 5.811E-02 0.000E+00 2.146E-02 2.198E-03 Xe135 2.373E-01 4.467E-03 0.000E+00 2.618E-04 2.776E-05 Xe135m 1.053E-01 5.914E-03 0.000E+00 2.203E-06 8.847E-05 Xe137 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l

Subtotal 1.944E+01' 7.223E-02 0.000E+00 2.254E-02 2.560E-03

() I131.

I132-2.522E-02 '1.449E-03 4.256E-03 2.444E-04 0.000E+00 0.000E+00 9.908E-05 0.000E+00 0.000E+00 0.000E+00 I133' 6.203E-03 3.564E-04 0.000E+00 2.436E-05 0.000E+00 I134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I135 3.386E-05 1.945E-06 0.000E+00 1.335E-07 0.000E+00 Subtotal -3.571E-02 2.052E-03 0.000E+00 1.236E-04 0.000E+00 Cs137 3.425E-03 1.968E-04 0.000E+00 1.622E-05 0.000E+00 Te132 4.131E-03 2.372E-04 0.000E+00 0.000E+00 0.000E+00 Sr 89 1.965E-03 1.127E-04 0.000E+00 4.883E-07 0.000E+00 Sr 90 2.129E-04 1.223E-05 0.000E+00 0.000E+00 0.000E+00' Ba140 3.325E-03 1.911E-04 0.000E+00 0.000E+00 0.000E+00 l La140 2.538E-03 1.458E 0.000Ee00 0.000E+00 0.000E+00 l Subtotal 1.560E-02 8.958E-04 0.000E+00 1.671E-05 0.000E+00 L Total 1.949E+01 7.517E-02 0.000E+00 2.268E-02 2.560E-03 i

i 1

I e

t I

! JAF - DEFAULT ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL l DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec) O becay Time (hrs): 96.0 Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr 85m 9.811E-07 1.789E-10 0.000E+00 1.167E-09 0.000E+00 Kr 85 1.224E-01 5.014E-09 0.000E+00 1.455E-04 0.000E+00 Kr 87 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr 88 4.917E-10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr 89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe131m 7.806E-02 7.017E-04 0.000E+00 8.564E-05 8.269E-05 Xe133m 3.775E-01 2.346E-03 0.000E+00 4.364E-04 7.003E-05 Xa133 1.603E+01 4.989E-02 0.000E+00 1.888E-02 9.878E-04 Xt135 3.914E-02 7.044E-04 0.000E+00 4.447E-05 2.242E-06 Xe135m 1.120E-02 6.331E-04 0.000E+00 1.778E-07 7.144E-06 Xe137 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Subtotal 1.666E+01 5.427E-02 0.000E+00 1.959E-02 1.150E-03 I131 2.280E-02 1.319E-03 0.000E+00 9.000E-05 0.000E+00 i 1132 3.389E-03 1.959E-04 0.000E+00 0.000E+00 0.000E+00 l I133 2.746E-03 1.588E-04 0.000E+00 1.084E-05 0.000E+00 I134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l 1135 2.693E-06 1.558E-07 0.000E+00 1.068E-08 0.000E+00 Subtotal 2.894E-02 1.673E-03 0.000E+00 1.009E-04 0.000E+00 Cs137 3.375E-03 1.952E-04 0.000E+00 1.606E-05 0.000E+00 Te132 3.289E-03 1.902E-04 0.000E+00 0.000E+00 0.000E+00 Sr 89 1.909E-03 1.102E 0.000E+00 4.769E-07 0.000E+00 l Sr 90 2.097E-04 1.213E-05 0.000E+00 0.000E+00 0.000E+00 l Ba140 3.103E-03 1.795E-04 0.000E+00 0.000E+00 0.000E+00 La140 2.731E-03 1.579E-04 0.000E+00 0.000E+00 0.000E+00 Subtotal 1.462E-02 8.451E-04 0.000E+00 1.653E-05 0.000E+00 l

Total 3. 670E+01 5.679E-02 0.000E+00 1.971E-02 1.150E-03 0

c. ,

(~ DEFAULT ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL JAF - l

(~' DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec)

Decay Time (hrs): 120.0 Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr 85m 2.359E-08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr 85 1.206E-01 4.972E-09 0.000E+00 1.441E-04 0.000E+00 Kr 87 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr 88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr 89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe131m 7.850E-02 8.053E-04 0.000E+00 8.561E-05 7.586E-05 Xe133m 2.743E-01 1.683E-03 0.000E+00 3.208E-04 3.147E-05 Xe133 1.391E+01 4.231E-02 0.000E+00 1.652E-02 4.439E-04 Xe135 6.283E-03 1.096E-04 0.000E+00 7.297E-06 1.810E-07 Xe135m 1.119E-03 6.358E-05 0.000E+00 1.436E-08 5.769E-07 Xe137 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l Xe138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 '

Subtotal 1.439E+01 4.497E-02 0.000E+00 1.707E-02 5.520E-04

) I131 2.061E-02 1.200E-03 0.000E+00 8.175E-05 0.000E+00 I132 2.698E-03 1.570E-04 0.000E+00 0.000E+00 0.000E+00 I133 1.216E-03 7.078E-05 0.000E+00 4.822E-06 0.000E+00 1134 0.000E+00 0.000E+00 0.000E+00 0.000E+0C 0.000E+00 I135 2.143E-07 1.247E-08 0.000E+00 8.533E-10 0.000E+00 Subtotal 2.453E-02 1.428E-03 0.000E+00 8.657E-05 0.000E+00 Cs137 3.325E-03 1.935E-04 0.000E+00 1.589E-05 0.000E+00  :

I Te132 2.619E-03 1.524E-04 0.000E+00 0.000E+00 0.000E+00 Sr 89 1.855E-03 1.078E-04 0.000E+00 4.656E-07 0.000E+00 Sr 90 2.066E-04 1.203E-05 0.000E+00 0.000E+00 0.000E+00 i Ba140 2.897E-03 1.686E-04 0.000E+00 0.000E+00 0.000E+00  !

l La140 2.786E-03 1.621E-04 0.000E+00 0.000E+00 0.000E+00

_......__ ......... ......... ._...___. ........_ j Subtotal 1.369E-02 7.965E-04 0.000E+00 1.636E-05 0.000E+00 Total 1.442E+01 4.719E-02 0.000E+00 1.718E-02 5.520E-04 (G

l l

1 l

l JAF - DEFAULT ISOTOPIC INVENTORIES FOR THE "EDAMS" MODEL DESIGN-BASIS ACCIDENT RELEASE RATES TO ATMOSPHERE (Ci/sec)

Decay Time (hrs): 168.0 Elevated Nuclide LOCA ESF Leak MSLB CRDA Refueling Kr 83m 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr 85m 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr 85 1.170E-01 4.886E-09 0.000E+00 1.412E-04 0.000E+00 Kr 87 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr 88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Kr 89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe131m 7.775E-02 9.508E-04 0.000E+00 8.419E-05 6.383E-05 Xe133m 1.426E-01 8.431E-04 0.000E+00 '. 701E-04 6.356E-06 Xe133 1.041E+01 3.075E-02 0.000E4'O 1.254E-02 8.967E-05 Xe135 1.579E-04 2.676E-06 0.000E+00 1.885E-07 1.181E-09 Xe135m 1.004E-05 5.753E-07 0.000E+00 0.000E+00 3.764E-09 Xe137 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Xe138 0.0000+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Subtotal 1.075E+01 3.255E-02 0.000E+00 1.293E-02 1.599E-04 I131 1.684E-02 9.931E-04 0.000E+00 6.744E-05 0.000E+00 k I132 1.711E-03 1.009E-04 0.000E+00 0.000E+00 0.000E+00 I133 2.383E-04 1.405E-05 0.000E+00 9.550E-07 0.000E+00 1134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 l 1135 1.356E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00

( Subtotal 1.879E-02 1.108E-03 0.000E+00 6.840E-05 0.000E+00 l

! Cs137 3.225E-03 1.902E-04 0.000E+00 1.558E-05 0.000E+00 l Te132 1.661E-03 9.792E-05 0.000E+00 0.000E+00 0.000E+00 Sr 89 1.752E-03 1.031E-04 0.000E+00 4.442E-07 0.000E+00 Sr 90 2.005E-04 1.183E-05 0.000E+00 0.000E+00 0.000E+00 Ba140 2.522E-03 1.487E-04 0.000E+00 0.000E+00 0.000E+00 La140 2.670E-03 1.575E-04 0.000E+00 0.000E+00 0.000E+00 Subtotal 1.203E-02 7.093E-04 0.000E+00 1.602E-05 0.000E+00 i

Total 1.078E+01 3.436E-02 0.000E+00 1.302E-02 1.599E-04  !

l O

6 EDAMS DEFAULT-INVENTORY REPLACEMENT FILES D)4 V

The following table provides a listing of the new EDAMS files containing the default release rates to the atmosphere for the five release scenarios considered in the analyses. With the exception of the noble gas releases as a result of post-LOCA ESF component leakage, they correspond to the values at the start of an accident, prior to any decay or depletion of the source in each case. For the noble gases resulting from ESF component leakage, the entries correspond to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> af ter the accident, the time at which the total noble gas release rate to the atmosphere is a maximum.

EDAMS Default Inventory Files (Release Rates, Ci/sec)

Nuclide loca.jaf esf.jaf slb2.jaf crd.jaf rfa.jaf Kr 83m 1.353E+00 1.154E-02* 1.517E-05 1.577E-03 3.552E-04 Kr 85m 2.906E+00 1.508E-04 2.725E-05 3.386E-03 1.657E-01 Kr 85 1.301E-01 3.658E-09 8.917E-08 1.516E-04 9.144E-01 1 Kr 87 5.572E+00 0.000E+00 8.917E-05 6.494E-03 2.695E-05 Kr 88 7.894E+00 0.000E+00 8.917E-05 9.200E-03 5.252E-02 Kr 89 9.817E+00 0.000E+00 5.800E-04 1.144E-02 0.000E+00 Xe131m 6.825E-02 7.994E-05* 6.692E-08 7.953E-05 1.669E-01 1 Xe133m 9.942E-01 1.934E-03 1.292E-06 1.159E-03 1.991E+00 Xe133 2.386E+01 2.769E-02 3.658E-05 2.781E-02 5.379E+01 r~N Xe135 3.081E+00 1.952E-01 9.833E-05 3.589E-03 1.238E+01 l

( Xe135m 4.494E+00 5.686E-01 1.158E-04 5.239E-03 6.803E-01 ,

Xe137 2.094E+01 0.000E+00 6.692E-04 2.440E-02 0.000E*00 Xe138 1.988E+01 0.000E+00 3.975E-04 2.316E-02 0.000E+00 l

I131 3.406E-02 1.918E-03 9.808E-04 1.323E-04 2.439E-02 I132 4.975E-02 2.803E-03 7.628E-03 1.933E-04 2.794E-05 I133 7.119E-02 4.011E-03 6.536E-03 2.766E-04 2.498E-02 I134 7.839E-02 4.417E-03 1.380E-02 3.044E-04 3.467E-10 I135 6.725E-02 3.789E.03 9.075E-03 2.612E-04 4.233E-03 Cs137 3.583E-03 2.019E-04 1.198E-05 1.671E-05 3.360E-03 Te132 8.178E-03 4.606E-04 6.900E-04 0.000E+00 0.000E+00 Sr 89 2.132E-03 1.201E-04 1.489E-04 0.000E+00 0.000E+00 ,

Sr 90 2.228E-04 1.255E-05 1.126E-05 0.000E+00 0.000E+00 Ba140 4.094E-03 2.306E-04 4.358E-04 0.000E+00 0.000E+00 La140 4.336E-05 2.443E-06 0.000E+00 0.000E+00 0.000E+00

• Noble gas (Kr and Xe) release rates in this case are due entirely to the decay of halogens accumulating on the SGTS filters; the entries correspond to a post-accident time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

O

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