ML20198B974

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Rev 2 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual
ML20198B974
Person / Time
Site: Three Mile Island  Constellation icon.png
Issue date: 06/17/1991
From: Danaky R, Shawn Williams
GENERAL PUBLIC UTILITIES CORP.
To:
References
6610-PLN-4200.0, NUDOCS 9106270231
Download: ML20198B974 (41)
v • d • e


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THI PROCEDURE INSTRUCTION MEMO UNIT 1 PROCEDURES .

l DATE d -/ 9 - 9/

CORRECT NAME/ ADDRESS Document Control Desk Office Nuc. Reactor Regulation IF NECESSARY U.S. Nuclear Regulatory Commision Washington, D.C. 20555 RETURN TO: BETTY NASH PROCEDURE DISTRIBUTION CONTROL JtOOM 130 U-2 ADMIN. BLDG. THI P10ase update your procedure file with the attached procedures listed below, destroy the superseded procedures, and post your Master Procedure Index accordingly. Also please sign the acknowledgment at the bottom of this memo and return to Betty Nash at the address shown above.

Procedure No. Rev. No. PCR No. Instructions /Comunents

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-ADDITIONAL INSTRUCTIONS / COMMENTS

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l 6610-PLN-4200.02 Radiological Centrois Department Revision No.

Title 2

TMI Emergency Dose Calculation Manual (EDCM) Responsible Office Applicability / Scope The EDCM is applicable to all qualified Radiological Assessment Coordinators. This manual provides the 6610 methods used to perform dose projections during emergencies No Effective Date This document is within QA plan scope X Yes X Yes No Safety Reviews Required List of Effective Pages Revision Page Revision Page Revision Page Revision Page 57.0 85.0 2 1.0 2 29.0 1 1 2

58.0 86.0 2.0 2 30.0 1 1 2

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1 68.0 1 96.0 12.0 1 40.0 1 97.0 2 1 69.0 13.0 1 41.0 1 98.0 2 42.0 1 70.0 14.0 1 1 99.0 2 43.0 1 71.0 15.0 0 16.0 1 44.0 1 72.0 1 100.0 2 1 73.0 1 El-1 0 17.0 0 45.0 1 74.0 1 El-2 0 18.0 0 46.0 1 75.0 1 El-3 0 19.0 1 47.0 El-4 0 20.0 1 48.0 1 76.0 1 21.0 1 49.0 1 77.0 1 22.0 0 50.0 1 78.0 1 23.0 1 51.0 1 79.0 1 24.0 1 52.0 1 80.0 1 25.0 1 53.0 1 81.0 1 26.0 1 54.0 1 82.0 1 27.0 1 55.0 1 83.0 1 28.0 1 56.0 1 84.0 2 ll Signature l Concurring Organizational Element I Date ,

OricinatorlI bI hCMM& N l Radiolocical Encineer I d-b-Y /

/ \ Environmental Scientist I /, - / 3 - 9/

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Nualear TMI Radiological controls Depart:nent 6610-PLN-4200.02 Title Revision No.

\w TMI Emergency Dose Calculation Manual (EDCM) 2 Table of Contents Section E*9*

l 1.0 PURPOSE 4.0 l 1

5.0 2.0 APPLICABILITY / SCOPE 6.0 3.0 DEFINITIONS 15.0 4.0 PREREQUISITES 3.0 PROCEDURE 16.0 5.1 Source Term Calculations 18.0 5.2 Selection of Release Pathways and Characteristics 19.0 5.3 Calculation of NRC Damage Clas and Isotopic Percentages 23.0 5.4 Radiation Monitoring System (RMS) Source Term Calculation 36.0

- 5.5 Post Accident Samples Source Term Calculation 40.0 l s 5.6 Contingency Calculations Source Term Generation 42.0 5.7 Decay Scheme Calculation 47.0 5.8 Noble Gas to Iodine Ratio Calculations 49.0 5.9 Effluent Releasa Flow Rates 52.0 5.10 Two-Phase Steam Flow Determination 65.0 5.11 Source Term Filtration 66.0 5.12 Meteorology Inquiry 68.0 5.13 Dispersion Model 69.0 5.14 offsite Air Sample Analysis 75.0 5.15 Liquid Release Calculation 78.0 5.16 Protective Action Recommendation Logic 84.0 5.*17 Dose Projection Model Overview THI-l 85.0 5.18 THI-2 Source Term Calculation 86.0 l'

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[ ) ' Title Revision No.

'%l TMI Emergency Dose Calculation Manual (EDCM) 2 Table of Contente (Cont'd) section Page 6.0 RESPONSIBILITIES 96.0

7.0 REFERENCES

97.0 8.0 EKHIBITS 100.0 None il'\

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TMI Emergency Dose Calculation Manual (EDCM) 2 5.16 Protective Action Recommendation Logic - The Logic Diagram is designed to enable the user to develop protective actions based upon plant conditions, release duration and dose assessments. The logic is diagramed in Procedure EPIP-THI .02.

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MUClear TxI Radiological Controls Department 6610-PLN-4200.02 Revision No.

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TMI Erargency Dose Calculation Manual (EDCM) 2 5.17 Dose Projection Model Overview TMI-1 5.17.1 The dose projection model may be regarded as three distinct sections. Certain variables are passed bet **en those sections:

a. source term generation
b. met data input
c. dose calculation model Indeed, the operator may separately update any one of these sections using specially defined keys. To save time the operator, upon learning that the met conditions have changed and the source term has not, may update the met conditions and then update the dose calculation without having to re-enter the source term parameters. The program retains the most recent set of source term and met parameters.

5.17.2 Source term parameters that are used in the dose projection portion of the model ares f'

1. An array of the 15 isotopes of interest in pC1/sec.
2. The release flow rate in efm.
3. The release point stack height of 48.6 meters.
4. The release point stack diameter in meters - 1.7 meters for the Station Vent and 1.?. meters for the Reactor Building.
5. A single letter code for the type of release.

l a. o - Ground level i b. S - Split wake

c. E - Elevated l- 5. A character string describing the source, 1.4., RMA-6 300 cpm.
7. The date and time of the source term parameter entry.

The met conditions section requires as input the type of release, i.e., G, 5, or E. If this variable is not present the operator is required to specify it before the program continues.

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1, Title TMI Emergency Dose Calculation Manual (EDCM) 2 5.18 TMI-2 Source Term Calculation NOTE: Follow Figure 5.18-1 THI-2 RAC Program Flowchart following this section.

5.18.1 Source Term Calculations - The source term portion of the THI-2 dose assessment program is used to generate the quantity and radionuclide make up of the radioactive material released (or available for release) to the environment. Once the source term is measured or estimated, meteorological and dosimetry modele are t

applied to the assessment. Some specific accident scenarios are used to calculate radionuclide release factors and assess the accident consequences. These assessmonts are documented in Technical Evaluation Reports (TER's) or Safety Evaluation Reports

-(SER's). Source Term Calculations are performed by three methods, once the release pathway is chosen. These methods are 1) using Radiation Monitoring System readings, 2) Actual sample results, or 3) Continges.cy calculations.

5.18.2 The following facilities are considered as being radioactive

  1. ~'\ material release pathways for the THI-2 RAC program.

[O DEFAULT VENTILATION CURIES FACILITY RMS FLOW RATE (CFM) AVAILABLE 1 - WHPF EBERLINE PING 7100 100 2 - RLM EBERLINE PING 900 100 3 - CACE AMS-3 (2) 2000 100 4 - EPICCR II EBERLINE PING 9000 100 5-6 - STATION VENT HPR219 VICTOREEN PING 120F - 130K 100 7 - STATION VENT HPR219A EBERLINE PING 120K - 130K 100 l

l 8 - ISWSF/ PAINT SHED NONE NONE 100 9 - RAD. INST. SHOP NONE 4000 100 The above list shows the associated default data concerning each release point in the THI-2 RAC program. The station vent release 86.0 2042C

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[G } Title TMI Emergency Dose calculation Manusi (EDCM) 2 pathway also includes an option for a dropped fuel canister accident. Figure 5.18-2 shows the main TMI-2 ventilation.

5.18.3 Radiation Monitoring System (RMS) Source Term Calculation only the RMS channel available for a selected release pathway is offered to the user. The follo.ing parameters are used to calculate a THI-2 source terms

1. RMS reading (CPH, pCi)
2. RMS Channel Efficionew (CPM /pci/ce, CPM / min /pci/cc)
3. The release flow rate (CTM)
4. Cs-137/Sr-90 Ratio 5.18.4 Post Accident sample Source Term Calculation This option for a particular release pathway is to use actual sample results to develope a cource term. This option would be the most preferable method for calculating a TMI-2 source term since this method eliminates built in conservatisms from RMS or I

7 v contingency calculations. In this option the sample results or defaults, if required, will be used in conjunction with the release flow rate (CrM) to calculate a source ' ann.

5.18.5 contingency Calculation Source Term Calculation This option utilizes referenced technical documents, such as safety Evaluation Reports (SER's) and Technical Evaluation Reports (TER's), to define a maximum source term for each facility. The quantity of radioactive material for a given f acility along with the associated release flow rate are used to criculate a conservative source term.

5.18.5.1 Gource Term Filtration (Contingency Calc only)

During the final calculatior of a source term a filtration efficiency will be prompted to determine the fraction of the source term that will not reaah the environment due to filtration.

5.18.6 Dose Calculation once the source term is established for a release from a particular pathway. This section of the RAC program will proceed very similar to the THI-1 dose projection process. A meteorology option will gather meteorology data and combine it with the source term information to complete a dose projection.

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THI Emergency Dose Calculation nanual (EDCM) 2 5.18.7 Dose oro$ection Model overview TMI-2 5.18.7.1 be regarded as three distinct The dose projection sections. model map lare passed batween those sections:

Certain variables'.

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a. source term generation
b. met data input i
c. dose calculation model Indeed, the operator may separately update any one of these sections using specially defined keys. To save time the operator, upon learning . -.c the met conditions have changed and the source term has not, may update the met conditions and then update the dose calculation without having to re-enter the source term parameters.. The program retains the most recent set of source term and met parameters.

5.18.7.2 Source term parameters that are used in the dose projection  !

portion of-the model are g" r 1. The radionuclides Sr-90 and Cs-137 in their chosen ratio.

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2. The releans flow rate in cfm.

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3. The choice of fuel related source term or not.
4. A single letter code for the type of release.
a. G - Ground level
b. S - Split wake
c. E - Elevated
5. The date and time of the source term parameter entry.

The met conditions section requires as input the type of release, 1.4., 0, S, or E. If this variable is not present the operator is required to specify it before the program continues.

5.18.7.3 Met parameters that are passed to the dose projection portion of-the model are:

1. Delta T in or per 117 feet.
2. Wind speed in mph.
3. Wind direction in degrees, from.

I 4. The date and time that met conditions were entered.

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MUClear .m1 Radiological controls Department 6610-PLN-4200.02 f-~~s Revision No.

(\, j) Title TMI Emergency Dose Calculation Manual (EDCM) 2 l

Upon being invoked, the dose calculation segment checks to see if the 15 isotopic values are defined. If they are not, the source term segment is invoked. After this the dose calculation segment ,

checks to see if the wind speed value is defined. If it is not, the met condition segment is called. Only after these two conditione are satisfied is the dose model started.

5.18.7.4 To perform aa entire does calculation with new source term and met, with user key-1, the source term and met variables are initialized to missing and the dose projection segment is called.

l The dose projection segment does not retain any variables for the /

program's use elsewhere in the program but sends all its output to the screen.

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THREE MILE ISLAND UNIT 2 RAC PROGRAM FLOWCHART A

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Nuclear TM, Radiol 3gical Controls Department 6610-PLN-4200.02 4 Title TMI Emergency Debe Calculation Manual (EDCM)

Revision No.

2 6O RKSPONSIBILITIES 6.1 The RAC is responsible to ensure that dose assessments using the methodology in the EDCM are performed upon implementation of the Emergency Plan.

( 6.2 The RASE has the responsibility to support the RAC in performance of

.-idiological controle and dose assessment using the methodology in the

' CM .

6.3 The Chemistry coordinator has the responsibility to support the RAC in the procurement and analysis of in-plant samples regul ed tc quantify the  %*

accident.

6.4 Radiological and Environmental Controls has the responsibility of proper reviw , and e"aluation of the E0CM and the RAC program soitware.

Radiological Controls is re.coonsible for reneuring that the EDCM and the RAC program softw.re are current and compatible.

6.5 The Techntent Support Center (TSC) has the responsibility to provide the RAC with appropriate fuel damage data and other inforttation pertinent to performing does caia lations.

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TMI Radic1.ogical Controls Department 6610-PLN-4200.02 g Title Revision No.

k TMI-Emergency Dose Calculation Manual (EDCM) 2 7.0 REFERENCma 7.1 Americtn National Standard (ANS), ANSI /ANS-18.1 - 1984, Radioactive Source Term for Normal Operations of Light Water Reactors 7.2 APS Source Term Report - Report to the American Physical Society of the Study Group on Radionuclide Releases From Severe Accidents at Nuclear Power Plants, February 1985 7.3 Dose Assessment Manual for Emergency Preparedness Coordinators, February 1986, INPo 86-008 7.4 EDCM Flowchart Block Diagram 7.5 Etficiency Check using an Air I 131 Source Cartridge and a Ba-133 Source Cartridge, Memorandum 9502-88-0139, September 28, 1988 7.6 Emergency Dose Calculation Manual (EDCM) Source Code Listing 7.7 EPA 520/1-75-001 - Manual of Protectiv$ Action Guides and Protective Actions for Nuclear Incidents l I I

/'~ \ 7.8 EPIP-TMI .07 - Off-site /On-site Dose /rojections

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7.9 Evaluation of a Front Loaded Iodine Cartridge uming Various Survey Equipment, Memorandum 9100-88-0194, May 12, 1988 7.10 Field Measurements of Airborne Re19ases of Radioactive Material, Memorandum 9502-88-0098, May 25, 1988 7.11 FSAR, TMI-1 Chapter 11, Radioactive Waste and Radiation Protection 7.12 FSAR, TMI-l Chapter 14 - Safety Analysis 7.13 FS Mt, THI-2, Volume 10, Section 15, Accident Analysis

~.14 GPUNC Emergency Plan, 1000-PLN-1300.01 7.15 1CRP Report of the Task Group on Reference Man, 1981 l 7.16 INPO SOER 83-2 " Steam Generator Tube Ruptures"

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l 7.17 Introduction to Health Physics, Herman Comber, 2nd Edition, 1985 7.18 NRC-8NL Source Tirm Report 7.*19 NUREG-0017 Rev. 1 - PWR - GALE Code; Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents fcom PWR, April 1976 7.20 NUREG-0133 - Preparation of Radiologiczi Ef fluent Technical Specifications for Nuclear Power Plants, October 1978.

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Title 2

TMI Emergency Dose Calculation Manual (EDQ4),

7.71 NUREG-0591 - Environmental Assessment for use of EPICOR II at Three Mile Island Unit 2, October 3, 1979 7.22 NUREG-0654 - Revision I - Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support cf Nuclear Power Plants 7.23 NUREG-0737 - Clarification of TMI Action Plant Requirements, U.S. Nuclear Regulatory Commission, November 1980, Generic Letter 82-33, Supplement i to NUREG-0737 - Requirements for Emergency Response capability, U.S. Nuclear Regulatory Commission, Washington, D.C., December 1982 7.24 NUREG-1228 - Source Term Estimation during Incident Response to Severe Nuclear Power Plant Accident: Oc'cober 1988 7.25 NUREG/CR-3011 - Dose Projection Considerations for Emergency Conditions at Nuclear Power Plants 7.26 N1830 - Post Accident Reactor Coolant Sampling 7.27 NIS31 - Post Accident Atmospheric Saapling

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7.28 N1832 - Post Accid'Jnt Sample Analysis 7.29 N1833 - Post Accident Core Damage Calculations 7.?O OP 1202 Abnormal Transients Rules, Guides and Graphs 7.31 OP 120' RCS Super Heated 7.32 GP 1210 Excessive Radiation Levels 7.33 Operational Quality Assurance Plan,1000-PLN-7200.01 7.34 Proprietary Midas User Documentation, Pickard, Lowe, and Garrick 7.35 Radioactive Decay Data Ta!.h s, David C. Kocher, ORNL, DOE / TIC-11026, 1981.

7.36 Radiological Health Handbook, Revised Edition Jan. 1970, US Dept. HEW.

7.37 Reg. Guide 1.21 Measuring, Evaluating, and Reporting Padioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Erfluents from Ligh*.-Water Cooled Nuclear Power Plants, Rev. 1, June 1974.

7.38 Reg. Guide 1.109 - Calculation of Annual Doses to Man From Routine Releases of Reactor Ef fluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, October 1977, Rev. 1 1.39 SER-15737-2-G07-108, Rev. 4, March 5, 1985. Safety Evaluation Report for a TMI-2 Fuel Canister Accident s_,

7.40 SER-419628-003, Rev. 7, Instrument Calibration Facility, Feb. 12, 1988 98.0 2042C ,

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7.41- TDR *, - TMI-1) Primary-to-Secondary OTSG Leakage and its On-cite /Off-site )

Radioluvical Impact, April 1983 l l ..

7.42 TDR-405 - THI-1; Evaluation of Plant Radiation Release and its 10CFR50, Appendix I confermance for Different Operating conditions

- 1 I 7.43 TDR-431 - Method for Estimating Extent of Core Damage Under Severe Accident i

! Conditions l

l~ 7.44 TER-13587-02-G03-015, Rev. 6, January 21, 1985. Interim Solid Waste Staging Facility Technical Evaluation Report J l 7.45 TER-15737-2-003-104, Rsv. 5, May 8, 1985. Technical Evaluation Report for the.CACE l.-

! 7.46 TER-15737-2-003-107, Rev. 6, Feb. 2, 1987. Technical Evaluation Report for the WHPF.

7.47 WASH-1400 - 1975 Nuclear Safety Study WASH-1400 (also known as Rasmussen Report)

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,I % Revision No.

Title i \

2 THI Emergency Doem Calculatiog Manual lEDCM) 8.0 EIllIBITS 8.1 Exhibit 1, RAC Data Collection (Example)

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TMI Radiological Controls Department 6610-PLN-4200.02 Revision !!o.

Title 2

TMI Emergency Dose calculption Manual 4EDCM)

Applicability / Scope The ':DCM is applicable to all qualified Reisponsible Of fice Radiologi al Assessment Coordinators. This manual provides the methode used to perform dose pro 3ections duri.ig emergencies - 6610

__This document is within QA plan scope X Yes No Effective Date Jafety Reviews Required X Yes N 06/19/91 List of Effectivc 9acis Page Revision Page Revision Page Revision Page Revistun 1 57.0 1 85.0 2 1.0 2 29.0 58.0 1 86.0 2 2.0 2 30.0 1 87.0 2 3.0 2 31.0 1 59.0 1 4.0 0 32.0 1 60.0 1 88.0 2 61.0 89.0 2 5.0 0 33.0 1 1 5.0 1 34.0 1 62.0 1 90.0 2 7.0 1 35.0 1 63.0 1 91.0 2 l 8.0 1 36.0 1 64.0 1 92.0 2 l 9.0 1 37.0 1 65.0 1 93.0 2 l 94.0 2 l 10.0 1 38.0 1 66.0 1 95.0 2 l 11.0 1 39.0 1 67.0 1 40.0 1 68.0 1 96.0 2 12.0 1 13.0 1 41.0 1 69.0 1 97.0 2 14.0 1 42.0 1 70.0 1 98.0 2 71.0 1 99.0 2 15.0 0 43.0 1 44.0 1 72.0 1 100.0 2

( 16.0 17.0 1

0 45.0 1 73.0 1 El-1 0 74.0 1 El-2 0 18.0 0 46.0 1 1 47.0 1 75.0 1 El-3 0 19.0 20.0 1 48.0 1 76.~ l El-4 0 21.0 1 49.0 1 77.0 1 22.0 0 50.0 1 78.0 1 23.0 1 51.0 1 79.0 1 24.0 1 52.0 1 80.0 1 25.0 1 53.0 1 81.0 1 26.0 1 54.0 1 82.0 1 27.0 1 55.0 1 83.0 1 28.0 1 56.0 1 84.0 2 ll Signature l Concurring Organizational Element l Date Oricinatorll bI h4Mbee l Radioloolcal Encineer l d *b-Y /

l Environmental Scientist l /, - /3 - 9/ -

f Concurred ll btI[/

By ll_ M l Emergency Preparedness l d-/7-i[

l- h_ l Radiological Engineering Mgr.TMI l [#~/O-T/

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YUClear TMI Radiological Controls Department 6610-PLN-4200.02 Revision No.

} Title v TMI Emergency Dose Calculation Manual (EDCM) 2 Table of Contents Page Section 4.0 1.0 PURPOSE 5.0 2.0 APPLICABILITY / SCOPE 6.0 3.0 DEFINITIONS 15.0 4.0 PREREQUISITES 16.0 5.0 PROCEDURE 18.0 5.1 Source Term Calculattons Selection of Release Pathways and Characteristics 19.0 5.2 Calculation of KRC Damage Class and Isotopic Percentages 23.0 5.3 Radiation Monitoring System (RMS) Source Term Calculation 36.0 5.4 Post Accident Samples Source Term Calculation 40.0 3.5 7'~'

42.0 x 5.6 Contingency Calculations Source term Generation 47.0 5.7 Decay Scheme Calculation 49.0 5.8 Noble Gas to Iodine Ratio calculations 52.0 5.9 Effluent Release Flow Rates 65.0 5.10 Two-Phase Steam Flow Determination 66.0 5.11 Source Term Filtration 5.12 Meteorology Inquiry 68.0 69.0 5.13 Dispersion Model 5.14 offsite Air Sample Analysis 75.0 78.0 5.15 Liquid Release calculation 5.16 Protective Action Recommendation Logic 84.0 Dose Projection Model Overview THI-1 85.0 5.'17 86.0 5.18 TMI-2 Source Term Calculation s

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Radiological Controls Department 6610-PLN-4200.02

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Title Revision No.

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TMI Emergency Dose calculation Manual (EDCM) 2 Table of Contents (Cont'd)

Page section 6.0 RESPONSIBILITIEP 96.0

7.0 REFERENCES

97.0 8.0 EXHIBITS 100.0 None i

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MNuclear m Radiological Controls Department 6610-PLN-4200.02 TiL+e Revision No.

N Tl;I Etnergency Dose Calculation Hanual (EDCM) 2 5.16 Protective Action Recommendation Logic - The Logic Diagram is designed to enable the user to develop protective actions based upon plant conditions, release duration and dose assessments. The logic is diagramed in Procedure EPIP-TM1 .02.

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'- TMI Emergency Dose Calculation Manuti (EDCM) l 5.17 Dose Projection Model overview TMI-l 5.17.1 The dose projection model may be regardad-as three distinct sections. Certain variables are passed between tho9e sections

a. source term generation
b. met data input
c. dose calculation model Indeed, the operator may separately update any one of these sections using. specially defined keys. To save time the

' operator, upon learning that the met conditions have changed and the source term has not, may update the met conditions and then update the dose calculation without having to re-enter the source term parameters. The program retains the most recent set of source term and met parameters.

1 5.17.2 Source term parameters that are used in the dose projection .

j portica of the model aren l

r"'N 1. An array of the 15 isotopes of interest in pCi/sec.

\

\s 2. The release flow rate in cfm.

3. The release point stack height of 48.6 meters.

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4. The release point stack diameter in meters - 1.7 meters for the Station Vent and 1.1 meters for the Reactor Building.
5. A single letter code for the type of release.

! a. G - Cround level l

l-

b. S - Split wake i
c. E - Elevated
6. A character string describing the source, i.e., RMA-6 300 cpm.

l 7. The date and time of the source term parameter entry.

The met conditions section requires as input the type _ of release, i.e., C, S, or E. If this variable is not present

-* the operator is required to specify it before the program

! continues.

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MUClear TMI Radiological Controls Department 6610-PLN-4200.02 Revision No.

Title

'N 2 TMI Emergency Dose Calculation Manual (EDCM) 5.18 TMI-2 Source Term Calculation NOTE: Follow Figure 5.18-1 TMI-2 RAC Program Flowchart following this section.

5.18.1 Source Term Calculations - The source term portion of the TMI-2 dose assessment program is used to generate the quantity and radionuclide make up of the radioactive material released (or availablo for release) to the environment. Once the source term to mcasured or estimated, meteorological and dosimetry models are applied to the assessnient. Some specific accident scenarios are used to calculate radionuclide release factors and assess the accident consequences. These assessments are documented in Techn!. cal Evaluation Reports (TER's) or Safety Evaluation Reports (SER's). Source Term Calculations are pecformed by three methods, once the release pathway is chosen. These methods are 1) u sir.g Radiation Monitoring System readings, 2) Actual sample results, or 3) Contingency calculations.

5.18.2 The following facilities are considered as being radioactive

[ material release pathways for the TMI-2 RAC program.

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\

DEFAULT VENTILATION CURIES FACILITY RMS FLOW RATE (CFM) AVAILABLE 1 - WHPF EBr:RLINE PING 7100 100 2 - RLM EBERLINE PING 900 100 3 - CACE APJ5-3 (2) 2000 100 EBERLINE PING 9000 100 4 - EPICOR II 5-VICTOREEN PING 120K - 130K 100 6 - STATION VENT HPR219 7 - STATION VENT HPR219A EBERLINE PING 120K - 130K 100 NONE NONE 100 8 - ISWSF/ PAINT SHED 4000 100 9 - RAD. INST. SHOP NONE The above list shows the associated def ault data concerning each

\

release point in the TMI-2 RAC program. The station vent release V

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6610-PLN-4200.02

[ ) Title Revision No.

Q/ - TMI Emergency Dose Calculation Manual (EDCM) 2 pathway also includes an option fer a dropped fuel canister accident. Figure 5.18-2 shows the main TMI-2 ventilation.

5.18.3 Radiation Monitoring System (RMS) Source Term Calculation only the RMS channel available for a selected release pathway is l offared to the user. The following parameters are used to calculate a TMI-2 source terms

1. RMS reading (CPM, pCi)
2. RMS Channel Efficiency (CPM /pci/ce, CPM / min /pci/cc)
3. The release flow rate (CFM)
4. Cs-137/Sr-90 Ratio 5.18.4 Post Accident Sample Source Term Calculation This option for a particular release pathway is to use actual sample results to develope a source term. This option would be the most preferable method for calculating a THI-2 source term

/"'N since this rethod eliminates built in conservatisms from RMS or I \ contingency calculations. In this option the sample results or j

'U defaults, if requir 4, will be used in conjunction with the release flow rate (CFM) to calculate a source term.

5.18.5 Contingency Cale';1ation Source Term Calculation This option utilizes referenced technical documents, such as Safety Evaluation Reports (SER's) and Technical Evaluation Reports (TER's), to define a maximum source term for each tacility.- The quantity of radioactive material for 1 given facility along with the associated release flow rate are used to calculate a conservative source term.

5.18.5.1 Source Term Filtration (Contingency cale only)

During the final calculation of a source term a filtration efficiency will be prompted to determine the fraction of the source torn that will not reach the environment due to filtration.

5.18.6 Dose calculation once the source term is established for a release from a particular pathway. This section of the RAC program will proceed very similar to the TMI-l dose projection process. A meteorology option will gather meteorology data and combine it with the source term information to complete a dose projection.

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Nuclear TM1 Radiological Controls Department 6610-PLN-4200.02

<~'e-Revision No.

g ) Title

.\ j TMI Emergency Dose Calculation Manual (EDCM) 2 5.18.7 Dose Projection Model overview TMI-2 5.18.7.1 The dose projection model may be regarded as three distinct sections. Certain variables are panned between those sections:

a. source term generation
b. met data input
c. dose calculation model Indeed, the operator may separately update any one of these sections using specially defined keys. To save time the operator, upon learning that the met conditions have changed and the source term has not, may update the met conditions and then update the dose calculation without having to re-enter the source term parameters. The program retains the most recent set of

' source term and met parameters.

5.18.7.2 Source term parameters that are used in the dose projection portion of the model are:

I

' . / 1. The radionuclides Sr-90 and Cs-137 in their chosen ratio.

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2. The release flow rate in cfm.

I 3. The choice of fuel related source term or not.

f

4. A single letter code for the type of release,
a. G - Ground level l
b. S - Split wake l-1
c. E - Elevated
5. The date and time of the source term parameter entry.

The met conditions section requires as input the type of release, i.e., G, S, or E. If this variable is not present the operator is required to specify it before the program continues.

5.18.7.3 Met patameters that are passed to the dose projection portion of the model are j

1. Delta . in oF per 117 feet.
2. Wind speed ir mph.

i

3. Wind direction in degrees, from.

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I l 4. The date and time that met conditions were entered.

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Nuclear TM1 Radiological Controls Department 6610-PLN-42OO.02 Revision No.

Title O5 TMI Emergency Dosa Calculation Manual (EDCM) 2 Upon being invokou, the dose calculation segment checks to see if the 15 isotopic values are defined. If they are not, the source tere segment is invoked. After this the dose calculation segment checks tc see if the wind speed value is defined. If it is not, the met condition segment is called. Only after these two conditions are satisfied is the dose model started.

5.18.7.4 To perform an entire doso cr.lculation with new source term and met, with user key-1, the source term and met variables are initialized to missing and the dose projection segment is called.

The dose projection segment does not retain any variables for the program's use elsewhere in the program but sends all its output to the screen.

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YUClear rMI 6610-PLN-4200.02

.O Radiological Controls Department Revision No.

'.k Title TMI Emergency Dose Calculation Manual (EDCM) 2 FIGURE 5.18-1 THREE MILE ISLAND UNIT 2 RAC PROGRAM FLOWCHART ..

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TMI Emergency Dose calculation Manual (EDCM) 2 FIGURE 5.18-1 (Cont'd) l THREE MILE ISLAND UNIT 2 l RAC PROGRAM FLOWCHART A

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v TMI Emergency Dose Calculation Manual (EDCM) 2 FIGURE 5.18-1 (cont'd)

THREE MILE ISLAND UNIT 2 RAC PROGRAM FLOWCHART A

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TMI Emergency Dose Calculation Manual (EDCM) 2 FIGURE 5.18-1 (Cont'd)

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MUClear TMI Radiological Controls Department 6610-PLN-4200.02 f Revision No.

Title TMI Emergency Doce Calculation Manual (EDCM) 2 FIGURE 5.18-1 (Cont'd)

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FIGURE 5.18 2 6610-PLN-4200.02 STATION VENT Revision 2 a L ~142.000 cf m HP-R-219 HP-R-219 A (P..l..N.G.)

HP-R-21SAUX (NO DETECTOR)

HP-R-21ST (TRITUM BUSSLER) 70.000 cfm j , 0-20.000 cf m AUXILIARY HP-R- I d lHP-R- A-FILTERS BulLDING ] HP-R- FILTERS 222 228 -

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MUClear TM1 Radiological Controls Department 6610-PLN-4200.02 l -Title. Revision No.

TMI Emergency Dose Calculation Manual (EDCM) 2 6.0 RESPOSESIBILITIES 6.3 The RAC is responsible to ensure that dose assessments using the methodology in the EDCM are performed upon implementation of the Emergency Plan.

l 6.2 The RASE has the responsibility to support the RAC in performance of l

radiological controls and dose assessment using the methodology in the EDCM.

6.3 The Chemistry coordinator has the responsibility to support the RAC in the procurement and analysis of in-plant samples required to quantify the accident.

l 6.4 Radiological and Environmental Controls has the responsibility.of proper l review, and evaluation of the EDCM and the RAC program software. l Radiological Controls is responsible for ensuring that the EDCM and the RFC program software are current and compatible, 6.5 The Technical Support Center _(TSC) has the responsibility to provide the RAC with appropriate fuel damage data and other information pertinent to performing dose calculations.

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'~'- Radiological Controls Department 6610-PLN-4200.02 g Title Revision No.

TMI Emergency Dose Calculation Manual (EDCM) 2

7.0 REFERENCES

7.1 American National Sta' , ASI/ANS-18.1 - 1984, Radioactive Source Term for Normal Opera c Water Reactors 7.2 APS Source Term Report :he American Physical Society of the Study Group on Radionuclide .ehdvs From Severe Accidents at Nuclear Power Plants, February 1985 7.3 Dose Assessment Manual for Emergency Preparedness Coordinators, February 1986, INPO 86-008 7.4 EDCM Flowchart Block Diagram 7.5 Ef ficiency Check using an Air I-131 Source Cartridge and a Ba-133 Source Cartridge, Memorandum 9502-88-0139, September 28, 1988 7.6- Emergency Dose Calculation MA tal 'EDOM) Source Code Listing 7.7 EPA 520/1-75-001 - Manual of Protective Action Guides and Protective Actions for Nuclear Incidents

/ 7.8 EPIP-TMI .07 Off-site /On-site Dose Projections k 7.9 Evaluation of a Front Loaded Iodine Cartridge using Various Survey Equipment, Memorandum 9100-88-0194, May 12, 1988 7.10 Field Measurements of Airborne Releases of Radioactive Material, Memorandum 9502-88-0098, May 25, 1988 7.11 TSAR, THI-1 Chapter 11, Radioactive Waste and Radiation Protection 7.12 FSAR, TMI-1 Chapter 14 - Safety Analysis 7.13 FSAR, THI-2, Volume 10, Section 15, Accident Analysis 7.14 GPUNC Emergency Plan, 1000-PLN-1300.01 7.15 ICRP Report of the Task Group on Reference Man, 1981 7.16 INPO SOER 83-2 " Steam Generator Tube Ruptures" 7.17 Introduction to Health Physics, Herman Comber, 2nd Edition, 1985 7.18 NRC-BNL Source Term Report 7.'19 NUREG-0017 Rev. 1 - PWR - GALE Code; Calculation of Releases of Radioactive Materiale in Gaseous and Liquid Effluents from PWR, April 1976-

~g 7.20 KUREG-0133 - Preparation of Radiologict.1 Effluent Technical Specifications

[s for Nuclear Power Plants, October 1978.

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r MUClear TM1 6610-PLN-4200.02 Radiological Controls Department Title Revision No.

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% 2 TMI Emergency Dose calculation Manual (EDCM) i 7.21 NUREG-0591 - Enviro .w ntal Asses ms?M for use of EPICOR II at Three Mile Island Unit 2, Oct var 3,1975 7.22 NUREG-0654 - Revision . I - Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants 7.23 NUREG-0737 - Clarification of TMI Action Plant Requirements, U.S. Nuclear Regulatory Commission, November 1980, Generic Letter 82-33, Supplement 1 to NURA:G-0737 - Requirements for Emergency Response Capability, U.S. Nuclear Regulatory Commission, Washington, D.C., December 1982 7.24 NUREG-1228 - Source Term Estimation during Incident Response to Severe Nuclear Power Plant Accidents, October 1988 7.23 NUREG/CR-3011 - Dose Projection Considerations for Emergency conditions at Nuclear Power Plante 7.26 N1830 - Post Accident Reactor Coolant Sampling

).27 N1831 - Post Accident Atmospheric Sampling

'~'g 7.28 N1632 - Post Accident Sample Analysis

\' ' 7.29 N1833 - Post Accident Core Damage Calculattens 7.30 OP 1202 Abnormal Transients Rules, Guides and Graphs 7.31 OP 1202 RCS Super Heated 7.32 OP 1210 Excessive Radiation Levels 7.33 Operational Quality Assurance Plan, 1000-PLN-7200.01 7.34 Proprietary Midas User Documentation, Pickard, Lowe, and Garrick 7.35 Radioactive Decay Data Tables, David C. Kocher, ORNL, DOE / TIC-11026,1981.

f.36 Radiological Health Handbook, Revised Edition Jan. 1970, US Dept. RIW.

7.37 Reg. Guide 7.21 Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants, Rev. 1, June 1974.

7.38 Reg. Guide 1.109 - Calculation of Annual Doses to Man From Routine Roltases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, October 1977, Rev. 1 7.39 SER-15737-2-G07-108, Rev. 4, March 5, 1985. Safety Evaluation Report for a THI-2 Fuel Canister Accident kx 7.40 SER-419628-003, Rev. 7, Instrument Calibration Facility, Fob. 12, 1988 98.0 2042C

Nuslear TxI Radiological Controls Department 6610-PLN-4200.02

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-5 Title Revision No.

TMI Emergency Dose Calculation Manual (EDCM) 2 7.41 TDR-390 - TMI-1; Primary-to-Secondary OTSG Leakage and its On-site /Off-site Radiological Impact,. April 1983 7.42 TDR-405 - TMI-1; Evaluation of Plant Radiation Release and its 10CFR50, Appendix I Conformance for Different Operating Conditions 7.43 TDR-431 - Method for Estimating Extent of Core Damage Under Severe Accident Conditions 7.44 TER-13587-02-G03-015, Rev. 6, January 21, 1985. Interim Solid Waste Staging Facility Technical Evaluation Report 7.45 TER-15737 2-003-104, Rev. 5, May 8, 1985. Technical Evaluation Report for.

the CACE 7.46 TER-15737-2-003-107, Rev. 6, Feb. 2, 1987. Technical Evaluation Report for the WHPF.

WASH-1400 - 1975 Nuclear Safety Study WASH-1400 (also known as Rasmussen j 7.47 Report)

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Nu:alear z Radiological controls Department 6610-PLN-4200.02 Title Revision No.

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