ML20043C251
| ML20043C251 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/25/1990 |
| From: | Reggie Sullivan GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20043C247 | List: |
| References | |
| 9300-ADM-4010.0, NUDOCS 9006040279 | |
| Download: ML20043C251 (89) | |
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g gf OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 Applicability / Scope Responsible Office
-All GPUN Employees Rad Con 9300 This document is within QA Plan scope X Yes No Effective Date Safety Reviews required X Yes No (04/23/90) 05/03/9 _0 Prior Revision 1 incorporated the This Revision a incorporates the following Temporary Changes: following Temporary Changes:
N/A N/A List of Effective Pa2EE 2A2g Revision Eagg Revision EAq2 Revision Pace Revision 1.0 4 20.0 4 39.0 4 58.0 4 2.0 4 21.0 4 40.0 4 59.0 4 j 3.0 4 22.0 4 41.0 4 60.0 4 l 4.0 4 23.0 4 42.0 4 61.0 4 l 5.0 4 24.0 4 43.0 4 62.0 4 j 6.0 4 25.0 4 44.0 4 63.0 4 i 7.0 4 26.0 4 45.0 4 64.0 4 ;
8.0 4 27.0 4 46,0 4 65.0 4 )
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J0.0 4 29.0 4 48.0 4 67.0 4 11.0 4- 30.0 4 49.0 4 68.0 4 12.0 4 31.0 4 50.0 4- 69.0 4 ,
13.0 4 32.0 4 51.0 4 70.0 4 14'.0 4 33.0 4 52.0 4 71.0 -4 !
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Oyster Creek Emergency Dose calculation Manual 4 List of Effective Paces- - - .
(continued)
.1 Pace Revision.
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Nuder or$rra carex a^orotoorcit couraots POLICY AND PROCEDURE MANUAL
=== der 9300-ADM-4010.03
. Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 Qyster Creek Emercenev Dose Calculation Manual (EDCM)
Section Table of Contents' Eggg l'.0 Purpose............................................................. 7 2.0 Applicability / Scope................................................. 7 '
3.0 Definitions......................................................... 8 i
4.0- Policy.............................................................1'8 5.0 Prerequisites...................................................... 19 6.0 Precautions........................................................ 19 7.0 Procedure.......................................................... 19 7.1 Operation.................................................... 19 7.1.1 Compu t e r Ope r a t io n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 7.1.2 overview............................................. 21 7.1.3 Source Term Calculations............................. 23 Y
7.1.3.1 Monitored.................................. 23 .
7.1.3.'1.1 Stack.......................... 23 7.1.3.1.2 Turbine Building............... 25 7.1.3.2 Unmonitored Releases....................... 26 ,
7.1.3.2.1 Field Monitoring Team Reading.. 26 7.1.3.2.2 Isocondenser Accident.......... 27 7.1.3.2.3 Augmented Offgas Accident...... 27 7.1.3.3 Contingency Calculations................... 28 7.1.3.3.1 Drywel1........................ 28 7.1.3.3.2 Reactor Building............... 29 7.1.3.3.3 Turbine Building............... 30 7.1.3.3.4 Fuel Handling............. .... 31 1
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Mf OYSTER CREEK RADIOLOGICAL CONTROLS l Number-POLICY AND PROCEDURE KANUAL 9300-ADM-4010.03 Title Revision No.
,1 Oyster Creek Emergency Dose Calculation Manual 4 Oveter Creek Emeroency Dose Calculation Manual (EDCE1 Table of Contents Secti.on - Eggg 7.1.4 Meteorology.......................................... 31 7.1.5 Other Functions...................................... 33 f 7.1.5.1 RAGEMS Direct Connection................... 33 7.1.5.2 Automatic Dose o rojection.................. 33 i i
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7.1.5.3 Ventilation................................ 34 7.1.5.4 Field Monitoring Team Readings............. 34 <
7.1.5.5 Utility Functions.......................... 35 i
7.1.5.5.1 Leak Rate calculation.......... 35 l 1
i 7.1.5.5.2 Core Damage Estimation......... 36- -
7.1.5.5.3 Field Iodine Measurement....... 36 7.1.5.5.4 Unit Conversions............... 37 i.
7.1.5.5.5 Semi-Infinite Cloud Approx..... 39 l
! 7.1.5.5.6 Ca l cu l at o r . . . . . . . . . . . . . . . . . . . . . 3 9 1
7.1.6 Release Duration..................................... 40 j 7.1.7 Final Output................................ . ........ 40 ;
l i
7.2 Theory...................................................... 43 7.2.1 Source Term.......................................... 43 7.2.1.1 Spectrum Determination..................... 43 7.2.1.2 Monitored...................................45 7.2.1.2.1 Stack.......................... 45 7.2.1.2.2 Turbine Building............... 50 7.2.1.3 Unmonitored................................ 53 7.2.1.3.1 Field Monitoring Team Reading.. 53 (2720P) 4,o
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g g7 OYSTER CREEK RADIOLOGICAL CONTROLS Number l POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 i
Title -
Revision No.
[' Oyster Creek Emergency Dose Calculation Manual 4, n
?
Ovster Creek Emeroency Dose Calculation Manual (EDCM)
' I
, Table of Contents.
~Section Egg,g ')
7.2.1.3.2 Iso Condsneer Accident.........'.54 a ~
7.2.1.3.3 Augmented Offgas Accident...... 56.
7.2.1.4 Contingsney Calculations................... 56' i
7.2.1.4.1 Drywell........................ 57 7.2.1.4.2 Reactor Building............... 60 7.2.1.4.3 Turbine Building............... 61.
I 7.2.1.4.4 Fuel Handling.................. 62 7.2.2 Meteorology.......................................... 63 7.2.2.1 Stability Class............................ 64 7.2.2.2 Windepeed.................................. 65 4[
. 7.2.2.3 Wind Direction............................. 65 7.2.3 Dose Projections..................................... 66 si L 7.2.3.1 Release Height............................. 66 -
7.2.3.2 Building Effect............................ 66 7.2.3.3 Finite Model............................... 67 s
7.2.3.4 Semi-Infinite Model........................ 69-7.2.3.5 Maximum Calculation........................ 70 '
l 7.2.4 Other Functions...................................... 71 l '
7.2.4.1 RAGEMS Direct Connection................... 71 l
l-'
7.2.4.2 Automatic Dose Projection.................. 73 7.2.4.3 Ventilation................................ 74 l4 1
1 7.2.4.4 Field Monitoring Team Readings............. 74 i
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- e M fl OYSTER CREEK RADIOLOGICAL CONTROLS Number
-POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03
~
Title Reviston No..
Oyster Creek Emergency Dose Calculation Manual 4-Oveter Creek Emercenev Dose Calculation Manual __fEDCM)
Table of Contents Section. EAg.R -
7.1.4 Meteorology..............................'............ 31 7.1.5 other Functions...................................... 33 j 7.1.5.1 RAGEMS Direct Connection................... 33 !
I 7.1.5.2 Automatic Dose Projection.................. 33 l 7.1.5.3 Ventilation................................ 34 7.1.5.4 Field Monitoring Team Readings............. 34 i l
7.1.5.5 Utility Functions.......................... 35 i i
1 7.1.5.5.1 Leak Rate Calculations......... 35 ;
.i 7.1.5.5.2 Core Damage Estimation......... 36 -
, 7.1.5.5.3 Field Iodine Measurement....... 36 l
l l- 7.1.5.5.4 Unit Conversions............... 37 7.1.5.5.5- Semi-Infinite cloud Approx..... 39 l l
7.1.5.5.6 Calculator..................... 39 l 7.1.6 Release Duration..................................... 40 j l 7.1.7 Final output......................................... 40 l-Theory...................................................... 43 7.2 7.2.1 Source Term.......................................... 43-7.2.1.1 Spectrum Determination..................... 43-7.2.1.2 Monitored.................................. 45 ,
7.2.1.2.1 Stack.......................... 45 7.2.1.2.2 Turbine Building............... 50 7.2.1.3 Unmonitored................................ 53 7.2.1.3.1 Field Monitoring Team Reading.. 53 (2720P) 4.0
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l[(j (Ij Q gf OYSTER CREEK RADIOLOGICAL CONTROLS Number
-POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title .
'Revibion No.
Oyster Creek Emergency Dose Calculation Manual 4 Ov s t e t' Creek Emercenev Dose Calculation Manual (EDCM)
Table of Contents Section Egga 7.2.1.3.2 Iso Condenser Accident......... 54
- 7. 2.1.2. 3 Augmented Of f gas Accident. . . . . . 56 7.2.1.4 Contingency calculations..........'......... 56-7.2.1.4.1- Drywell........................ 57 7.2.1.4.2 Reactor Building............... 60 7.2.1.4.3 Turbine Building............... 61 7.2.1.4.4 Fuel Handling.................. 62 7.2.2 Meteorology.......................................... 63 7.2.2.1 S t ab ility C1a s s . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64 7.2.2.2 Wi nd s pe e d . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 5 A[
. 7.2.2.3 Wind Direction........~..................... 65 7.2.3 Dose-Projections..................................... 66 7.2.3.1 Re l e a s e He ight . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 6 7.2.3.2 Bu ilding E f f ect . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 6 7.2.3.3 Finite Model............................... 67 7.2.3.4 Semi-Infinite Model........................ 69 7.2.3.5 Maximum Calculation........................ 70-7.2.4 other Functions...................................... 71 7.2.4.1 RAGEMS Direct Connection................... 71 7.2.4.2 Automatic Dose Projection.................. 73 7.2.4.3 Ventilation................................ 74 e
7.2.4.4 Field Monitoring Team Readings............. 74 (2720P) 5.0 1 1
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( r}, g, ), j gg gf. OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Humber 9300-ADM-4010.03 Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4
, Ovster Creek Emercenev Dose Calculation Manual (EDCM)
Table of-Contents
'pection E,ggg i
7.2.4.5 Utility Functions.......................... 74 7.2.4.5.1 Leak Rate Calculation.......... 74 7.2.4.5.2 Core Damage Estimation......... 77 7.2.4.5.3 Field Iodine Measurement....... 77 7.2.4.5.4 Unit Conversionn............... 79 7.2.4.5.5 Semi-Infinite Cloud Approx..... 80 7.2.4.5.6 Calculator..................... 81 8.0 References......................................................... 81 Appendix A. Cloud Gamma Dose............................................A 1 l
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i N u d e r-orstra carex axozotoozc^t couraots need:r POLICY AND PROCEDURE MANUAL 9300-ADM-4010'03 Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 l '. 0 PURPOSE-F The purpose of this manual is to provide a document that describes the assumptions and methodology used in the current Oyster Creek Radiological Assessment Cocputer' Program (RACP). This includes, calculating projected offsite. doses from releases of radioactive material to the environment in accident' conditions upon implementation of the Emergency Plan. As such,
- this document describes methods of. projecting offsite doses during emergencies or for training purposes. Indications of these releases may result from Radiation Monitoring System-(RMS) readings, onsite or offsite sample results, or contingency calculation if RMS and sample results are not available. These dose projections are performod utilizing an IBM compatible computer and the current version of the RACP. The Radiological Assessment Coordinator, (RAC), and Environmental Assessment Coordinator (EAC) are responsible for implementing the dose projection process.
2.0 APPLICABILITY / SCOPE The Emergency Dose Calculation Manual, EDCM, is applicable to all qualified Emergency Plan personnel involved in the projection of offsite i doses during an emergency. This manual provides the methods used in !
performance of dose projections during emergency situations where radioactive material has been or is predicted to be released to the environment.
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h gf OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL
. Number 9300-ADM-4010.03- ,
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Title- Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 )
3.0 ' DEFINITION 2 3.1 BUILDING WAKE EFFECTS Effects on the dispersion of an atmospheric release occurring at, Air' flow
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near, or below the top of a building (or any structure).
over and around the structure from the prevailing wind tends to ,
drive the release down to the ground on the downwind side of the structure. This has two effects: it increases onsite concentrations dramatically, while slightly reducing concent, rations downwind for a short distance. Far downwind concentrations are $l.. ,
affected very little by building wake. Stack releases are high j enough above the building so that building wake does not affect the-plume significantly.
3.2 CONTINGENCY CALCULATION' A source-term calculation performed in the absence of effluent radiation monitoring system or post accident sample data. It is a mathematical calculation based upon a conservative model of accident plant conditions.
3.3 DOSE CONVERSION FACTOR - DCP A parameter calculated by the methods and models of internal-l- dosimetry, which indicates the committed dose equivalent (to the whole body or an organ) per unit activity inhalod or ingested.
l l This parameter is specific to the isotope and the dose pathwap.
1 L Dose conversion factors are commonl'y tabulated in units of mR/hr i
i per curie inhaled or ingested or mR/hr per CL/m in air or water.
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-y g gf OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 3.4 DOSE EOUIVALENT I-131 - DEI DOSE EQUIVALENT I-131 shall be that concentration of I-131 microcuries per gram which alone would produce the same thyroid
. dose as the quantity and isotopic mixture of I-131, I-132, 1-133,-
I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 6f Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluences for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix I".
L 3.5 ELEVATED RELEASE An airborne effluent plume which is well above any building wake effects so as to be essentially unentrained. Reg. Guide 1.145 defines an elevated release point as being higher than two and one-half times the height of adjacent solid structures. The source of the plume may be elevated either by virtue of-the physical height of the source above.the ground elevation and buildings or by a combination of the physical height and the jet plume rise.
Elevated releases generally will not produce any significant ground level concentrations within the first few hundred yards of the source. Elevated releases generally have less dose consequence to the public-due to the greater downwind distance to the ground concentration maximum compared to ground releases. All main stack releases at Oyster Creek are elevated releases.
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Oyster Creek Emergency Dose Calculation Manual 4
.3.6_ . EMERGENCY ACTION LFVEL - EAL y Predetermined conditions or values, including radiation dose rates; specific levels of airborne, waterborne, or surface-deposited contamination; events =such as natural disasters or fires; or specific instrument _ indicators which, when reached or exceeded, require implementation of the Emergency Plan.
3.7 EMERGENCY DIRECTOR - ED Y
Designated onsite individual having the responsibility and authority to implement the Emergency Plan, and who will coordinate efforts to limit consequences of, and bring under control, the emergency.
3.8 EMERGENCY DOSE CALCULATION MANUAL - EDCM A controlled document describing the-content, calculational methods, and use of the Radiological Assessment Computer L[
Program (RACP).
3.9 EMERGENCY OPERATIONS FACILITY - EOF The Emergency Operations Facility serves as the primary location for management of the Corporation's overall emergency response.
This facility is equipped for and staffed by the Emergency Support organization to coordinate emergency response with off-site support agencias and to assess the environmental impact of the emergency.
The EOF participates in accident assessment and transmits appropriate data and recommended protective actions to Federal, State, and Local Agencies.
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(I (Nj @ gf OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE KANUAL- 9300-ADM-4010.03 i Title Revision No.
! Oyster Creek' Emergency Dose Calculation Manual 4 3.10 EMERGENCY RESPONSE FACILITIES - ERF k The primary locations for management of the Corporation's overall emergency response. These facilities are equipped for and staffed by the Emergency Support-and Response Organizations to coordinate emergency response with offsite_ support agencies and assessment of the environmental impact of the emergency. The ERF partici',u'a n accident assessment and transmit appropriate data and recommendeo.
protective actions to Federal, State and Local agencies.
3.11 EMERGENCY PLANNING ZONE - EPZ A zone defined by a radial distance from the plant in which emergency planning considerations are given. There are two EPZs.
The first is the Plume Exposure Pathway EPZ and is located at approximately ten miles in radius around the site. In this EPZ, eraergency planning consideration is given in order to ensure that prompt and effective actions can be taken to protect the public and property in the event of an accident. The second EPZ is called the Ingestion Exposure Pathway EPZ and is located approximately 50 miles in radius around the site. Emergency planning considerations are given for the ingestion exposure pathway in this EPZ.
3.12 ENVIRONMENTAL ASSESSMENT COHMAND CENTER (EACC)
The EACC is located along side the EOF to provide a work area for
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the EACC staff. Under the direction of the EAC, environmental data are collected and dose projections performed in support of the EOF.
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Neler 1 orstra ca==x a^orotoorc^' courao's POLICY AND PROCEDVRE KANUAL au der 9300-ADM-4010.03 '
Title Revision No.
Oyster Creek Emergeney Dese Calculation Manual 4 3.13 ENVIRONMENTAL ASSESSMENT COORDINATOR fEAC)
A member of the emergency support organization, the EAC assumes responsibility for dose projections and offsite field monitoring Y
teams from the RAC when the EACC is activated. The EAC provides environmental data, calculations, and advice to the Group Leader n
R&EC.
3.14 EXIT VELOCITY AND PLUME RISE Atmospheric dispersion and ground concentrations are in part dependent on release height. Higher ra\ ease heights will cause lower maximum concentratipna at ground level and will cause that maximum to occur further downwind than would a lower release 4/
height. The effective height of a stack is not only dependent on its physical height, but also on whether the plume rises or not.
At high linear flow rates (exit velocity), the release plume behaves rsuch like a geyser and rises in a jet flow above the stack. The height.to which the jet flow rises becomes the effective stack height.
3.15 FINITE PLUME MODEL Atmospheric dispersion and dose assessment model which is based on the assumption that the horizontal and vertical dimensions of an effluent plume are not necessarily large compared to the distance that gamma rays can travel in air. It is more realistic than the
. semi-infinite plume model because it considers the finite 1
dimensions of the plume, the radiation build-up factor, and the air
! attenuation of the gamma rays coming from the cloud. This model can estimate the dose to a receptor who is not subiccrged in the (2720P) 12.0 l.
@ M7 OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number 9300-ADM-4010.03 Title Revision No.
oyster Creek cmergency Dose Calculation Manual 4 radioactive cloud. It is particularly useful in evaluating doses from an elevated plume or when the receptor is near the effluent source.
3.16 CAUSSIAN PLUME EOUATION An equation which takes input parameters of plume height, and lateral and vertical plume spread, which explicitly calculates the straight line Gaussian Plume Dispersion. The Gaussian Plume '[
equation actually averages short term variations to produce a mean effective plume, so short term measurements of the plume may not be duplicated by the Gaussian Plume Model.
3.17 CROUND LEVEL RELEASE An airborne effluent plume which contacts the ground essentially at the point of release either from a source actually located at the ground olevation or from a source well above the ground elevation which has significant building wake effects to cause the plume to be entrained in the wake and driven to the ground elevation.
Ground level releases are treated differently than elevated releases-in that the X/o calculation results in significantly higher concentrations at the ground elevation near the release point. Ground level X/Q values become essentially the same as elevated for larger distance downwind. All releases at Oyster creek, other than main stack, are ground level releases.
3.18 LOW POPULATION YONE - LPZ Y As defined in 10CFR100.3, "The area immediately surrounding the exclusion area which contains residents, the total number and density of which are such that there is a reasonable probability [
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e glgf OYSTER CREEK KADIOLOGICAL QONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title Revision No.
Oyster Creek Emergency Dose calculation Manual 4 that appropriate protective measures could be taken in their behalf B
in the event of a serious accider.t."
3.19 PROTECTIVE ACTION CUIDELINES - PAG
- l Projected radiological dose or dose commitment values to ,
individuals of the general populatJon and to emergency workers that f
warrant protective action before or after a release of radioactive I
material. Protective actions would be warrantad provided the reduction in individual dose expected to be schieved by carrying out the protective action is not offset by excessive risks to individual safety in taking the protective action. The PAG at ,
OCNGS is based on the Environmental Protection Agency low-level i guideli.ne of 1000 mR whole body or 5000 mR child thyroid. The PAG does not include the dose that h a unavoidably occerred prior to the evacuation. !
3.20 PROTECTIVE ACTION RECOMMENDATION - PAR Those actions recommended to the state of New Jersey to be taken -
during or after an emergency situation that minimize or eliminate the radiological hazard to the health and safety of the general public.
l- 3.21 RADI A1 JON MONITORING SYSTEM - RMS ,
The sy2 tem designed to detect, indicate, annunciate, and record the radiation level of effluent rc?, eases and radiation level at selected locations inside the plant to verify compliance with applicable Code of Federal Regulations (CFR) limits. The RMS l
l consists of the following subsystems: area monitoring, atmospheric
-monitoring, and liquid monitoring.
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Oyster Creek Emergency Dose Ct. .tistion Manual 4
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h22 BAproLOGICAL ASSESSMENT COORDINATOR - RAC A member of the initial response team of the emergency response crganization. Specific responsibi16 ties assigned to the RAC include directing of fsite and onsite survey teams. The RAC is relieved of offsite radiological monitoring teamn' responsibilities by the Environmental Assessment Coordinator (EAC).- The RAC performa dose projections, supplies source term estimates to the j EAC and ensuren a timely, accurate dose projection until the EAC
. Y assumes responsibility for dose. protection. The RAC's main responsibility is advising the ED of any radiological concerno.
Initially the Oroup Radiological Controls Supervisor-assumes the -
role of the RAC until relieved by the Initial Response Emergency Organization RAC.
3.23 RADIOLOGICAL ENGINEERING SUPPORT k [)
Individuals assigned to assist the RAC in performing dose calculations, source term calculations, and overall assessment and control of radiological hazards. j 3.24 RAGEMS I. RAGEMS II !
4 I1 The RAGEMS I and RAGEMS II Systems monitor gaseous effluent 1.
i releases from the main stack and the turbine building stack, l
respectively. They monitor particulates, iodines, and noble gases.
l 3.25 REACTOR COOLANT SYSTEM - RCS ' y-i .' !
This system 'contains the necessary piping and coraponents to provids
.4 sufficient water flow to cool the reactor.. This system provides i for the transfer of energy f' rom the reacter core to the [
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Oyster Creek Emergency Dose calculation Msnual 4 turbine in the form of a pressurized steam, acts as.a moderator for.
thermal fission, and provides a boundary to separate fission products from the atmosphere.
3.26 EELIAS$ DURATION g Release duration refers to the time interval during which radionuclides are released from the nuclear facility. Releases may be monitored, unmonitored, actual, or projected. The time interval used to estimate a release of unknown duration should reflect best estimates of the plant technical staff. In the absence of other information, seven hours is used as the expected release duration from the reactor building and one hour le used as the expected release duration from the turbine building.
3.27 RELEASE RATE This term refers to the rate at which radionuclides are released to the environment. Normally, it will be expressed in uCi/sec.
l l 3.28 SEMI-INFINITE PLUME MODEL L[
Dose assessment model which is based on the assumption that the dimensions of an effluent plume are large compared to the distance
'that gamma rays can travel in air. The ground is considered to be l
l an infinitely large flat plate and the receptor le located at the l
p origin of a hemispherical cloud of infinite radius. The 1
l radioactive cloud is limited to the space above the ground plane. l I
The semi-infinite plume model is limited to immersion dose l l
calculations.
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3.29 SOURCE TERM q ,
The activity release rate, or concentration of an actual release or potential release. The common units for the source term ar C1, i
C1/sec, and C1/ce, or multiples thereof (e.g., uct). i F
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3.30 STABILITY CLASS A measure of the amount of mixing occurring between the plume and I the atmosphere around the plume. Conditions which create good mixing are unstable and conditions which create poor mixing are stable. Pasquill stability classification is a breakdown of the relativo atmospheric stabt11ty into eight groups, denoted as A through G, from most unstable to most stable. In the Pasquill stability classification system, stability is related to the change l in temperature with height and the standard deviation of wind l
'- direction measurements. The more negative the change in ,
l temperature with increasing height, the more unstable the atmosphere is. Standard deviation of wind direction (o g ) is not g used in stability clase determination.
3.31 TECHNICAL SUPPORT CENTER ITSC)
Emergency response facility utilized by engineering personnel to provide engineering support for emergency operations. 'This is the location of the ED and the RAC.
3.32 TERRAIN FACTOR - TP The terrain height above plant grade at distances from the release point. The terrain factor accounts for increases in local ground level concentrations d,ue to terrain effects. The terrain factor is (2720P) 17.0
o ,
@ Mf SYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number 9300-ADM-4010.03 Title Revision No.
oyster Creek Emergency Dose Calculation Manual 4 the terrain height in meters at a given distance for each sector.
3.33 X/o - (" CHI over 0")
The dispersion factor of a gaseous release in the environment calculated by a point. source gaussian dispersion model. Normal units of X/Q are sec/m3 . The X/Q is used to determine environmental atmospheric concentrations by multiplying the source term, represented by Q (in units of uC1/see or Ci/sec). Thus, the plume dispersion, X/Q (sec/ cubic meter) multiplied by the source term, Q (uci/see) yields an environmental concentration, X (uci/m3 ). X/Q is a function of many parameters including wind speed, stability class, release point height, building size, and release velocity, 4.0 POLICY This procedure is to serve as documentation for use of the oyster 4 Creek Radiological Assessment Computer Program (RACP). f.ny change to the program shall firrt be voted on by the RAC term committee. ,
Changes agreed upon by,the source term committee shall be followed by a revision to this procedure incorporating the change. The RAC committee shall consist of representatives from Rad Engineering, Emergency Planning, and Environmental Controle.
l EQIg Non-substantive changes to the computer program which have been voted on by the source term committee and documented in the minutes of the committee meeting, may be implemented I '
without a revision to this procedure.
,4.1 Three (3) non-controlled copies of this procedure will be sent to l
l the Licensing Manager, Oyster Creek. ;
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l h gf OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number 9300-ADH-4010.03 Title Revision No.
Oyster Creek Emergency Dose calculation Manual 4 5.0 PREREOUISITES 5.1 The following are prerequisites for projecting doses using the methods in the EDCM, and current version of the RACP.
5.1.1 The Emergency Plan is being implemented.
5.1.2 The RAC and/or EACC station are manned and functional.
6.0 PRECAUTIONS - None 7.0 PROL*EDURE This section of the EDCH is divided into two sections, 7.1 Operation ,
and 7.2 Theory.
. 7.1 Ope, ration This section will describe the operation of the RAC computer code 4 including which calculation to use in different circumstances and what inputs are required for each calculation. The computer operator is urged to read sections 7.1.1 and 7.1.2 before beginning any calculations.
t 7.1.1 Computer Operation I
The RAC computer code is run on computers in the Emergency Control Center (ECC), Technical Support Center (TSC), and the 1 l
Emergency Operations Facility (EOF). The computer, printer, and j auxiliary equipment are all turned on an off by a master power-switch located near the computer. In the control room this
! switch is under the display monitor. In the TSC the switch is l
mounted on the wall behind the computer. At the EOF the master switch is under the cabinet where the computer is kept. The RAC i
code will automatically be loaded in the control room when tue -
computer is turned on. . Type 'RAC" and hit the carriage return to !
load the program in the TSC and EOF (2720P) 19.0
m gglgf OYSTER CREEK RADI@ LOGICAL CON'IROLS Nutrber POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 FICURE 1 Ragems Auto Ventilation FMT Readings Utilities Offsite Dose Projection Program for Oyster Creek Nuclear Power Station 1 (
F1 Update All F2 Source Term F3 Met Data F4 Update Dose F9 Quit l l
t I
The initial screen will be displayed (Figure 1) at the j l
beginning of the program. The F1, F2, F3, F4, and F9 listed j at the bottom of the screen refer to the function keys across the top of the keyboard. The functions displayed across the top of the screen are accessed through the use of l
" Hot Keys". In this case the " Hot Keys" are R, A, V, F, and i U pressed in combination with the Alt key. For example, to l l
access the AUTO function, hold down the Alt key and press l the A key!
The program operates through a combination of full screen displays, pull.down menus, and pop up windows..'The function (2720P) 20.0 f
j Nuder orstra carex xxDzotoazcat courRots POLICY AND PROCEDURE MANUAL
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Title . Revision No.
oyster Creek Emergency Dose calculation Manual 4 4
l keys and " Hot Keys' which are active at the current position in the program are displayed on the top and bottom l
lines. When in the menus, choices are made by eithe'r '
directly pressing the letter which is hi-lited in red or moving the hi-lite bar using the up and dowr arrow keys to the desired function, then pressing the Enter key. The ESC '
key will always back the user out of a function or '
calculation in the case of an error.
Full screen editing is used for all user input. Input fields are hi-lited in blue. If numerical values are being entered, the minimum and maximum values which may be f entered are displayed on either the top line or the bottom lime of the screen. Move between the input fields using the up and down arrow keys or the enter key. Once all inputs have been entered, pressing the F10 key signifies the computer to accept the valtas displayed on the screen.
7.1.2 Overview After the code has been loaded, the operator should establish a connection with the RAGEMS computer. See L section 7.1.5.1. This is done using Alt-R.- Once the connection has been established, RAGEMS data will automatically be entered into the computer by the RAGEMS computer.
i.
l The RAGEMS system provides real time noble gas effluent monitoring and release point flow rates. Stack high range monitor reading, flow rate, T.B. low and high range monitor (2720P) 21.0 L
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J glgf OYSTER CREFK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE KANUAL Number 9300-ADM-4010.03 Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 readings, and T.B. vent flow rates are available via the RAGEMS direct connection. Because the RACEMS computer will I allow only one RAC computer to be connected at at time, each computer must " hung up" from the RAGEMS computer before being relieved of responsibility for dose projectione.
Dose projections are broken down into three sectier-te source term, meteorology, and dose calculation. Meteorology-should automatically be updated through contact with the met tower computer. Dose calculations are done with no input by the operator. The source term portion is where most of the inputs and operator decisions are required.
When "F1 Update All" or "F2 Source Term" is pressed the source term menu will appear. Source term calculations fall into three categories: Monitored, Unmonitored, and ;
Contingency. Monitored releases use the RAGEMS monitors on the stack and turbine building vents to develop a source term for e release as it occurs.
Unmonitored calculations are for release points which are not monitored by RAGEMS. an isocondenser failure and an
! AoG accident are the two specific accidents currently available under this option. Also, a downwind Field Team reading mo- be used to develop a source term for any ground level release. Unmonitored release calculations may be used to develop a source term for either a release as it occurs or as a "what if" calculation.
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r' t-h gf OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title . Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 contingency calculations provider generic methods to develop a source term for "what if" situations. Calculations are available for events which may happan .n the drywell, reactor building, turbine building and the refuel floor.
The drywell calculation includes drywell venting and drywell leakage into the reactor building.
At several places in the code the user is prompted for the most recent DEI. This value een be obtained from chemistry or is posted on the white board just inside the control room door.
7.1.3 Source Term Calculations l 7.1.3.1 Monitored i Stack 7.1.3.1.1
, The stack soucce term calculation l 1
develops a source term based or, che RAGEMS I monitored rea9<cjJ or PASS l_ sample. If a RAGEMS I PASS sample is ayallable, the se.mple will be used along with the stack flow rate to i calculate the source term.
l If no RAGEMS I PASS sample is j l
available, the RAGEMS I monitors are used. Three values may be entered:
l low range in cps, high range in amps, ,
and hich range in uC1/cc. The RAGEMS computer will enter only the high (2720P) 23.0
Q gf OYSTER CREEK RADIOLOGICAL CONTROLS ' Number POLICY AND PROCEDURE t3NUAL 9300-ADM-4010.03 Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4
. .. range valve in C1/cc. If the other values are available they should also be manually entered to develop a meaningful source term. The program containo logic to choose between the-values if more than one is entered.
The stack flow rate will be entered j by the RAGEMS computer if available.
If the stack flow rate is not available,. entering 0 to this prompt.
.will cause a fan flow table which k' prompts the user f>t fan status to appear.
.i SBGTS filtration should only be used !
if Stand-by Gas is running and the I reactor building fans are inciated.
The code can take credit for the lodine washout which would occur if the airborne activity is in the l
l containment and the containment spraye are on. Choose these two 1 i-options only if the release is from l- the drywell.
l l Finally, the computer will ask for l
the core condition. It the user 11 knows the current core condition it (2720P) 24.0 1
@ M7 OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number 9300-ADM-4010.03 Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 .
can be entered directly. Otherwise, the user chooses the "Not Sure" option and is prompted for plant conditiono to determine the core condition.
e 7.1.3.1.2 Turbine Building
. Because the turbine building has release points monitored by both the ;
RAGENS I and RAGENS II systems, both are used for this calculation. It RAGEMS PASS samples are available, .,
they are used along with the stack and turbine building vents flow rates to develop the source term. Be aware that the elevated and ground level wind directions may be different.
, In the absence of PASS samples, the RAGEMS monitors are used to develop the source term. If on-line, the RAGEMS computer will ento: the stack high range reading in uCi/ce, the stack flow rate, the turbine building high and low range readings, and the turbine building vent readings. If the user has the stack low range l
reading and the high range reading in (272DP) 25.0
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e Qhgf , OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE mar *J?L Number 9300-ADM-4010.03 Title Revision No.
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Oyster Creek Emergency Dose Calculation Manual 4 l
amps, they should be manually entered. The Computer will pick whichofthemonitorreadi$gs'to use. .
If no RAGEMS PASS sample results have been entered, the computer will
~
prompt the user for the core condition. If the core condition is known, it should be entered i
directly. Otherwise, the code will i
prompt the operation for plant Lf .
conditions from which it will choose the core condition.
7.1.3.2 Unmonitored Releases 7.1.3.2.1 Field Monitoring Team Reading A downwind field monitoring team reading may be used to develop a source term for a ground level release. The reading must be a closed windgy reading taken at the plume centerline. The distance to the site must be known in feet.
Care should be taken when using this calculation with dose rates taken clorr to the plant. Small errors in (2720P) 26.0
, .i glgf ' OYSTER CREEK RADIOLOGICAL CONTROLS Number
{
POLICY ANL PROCEDURE MANUAL 9300-ADH-4020.03
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Title Revisica No.
Oyster Creek Emergency Dose Calculation Manual 4' distance to the plant can lead'to i
large errors in projected ' dose rates. ;
This calculation may be used to perform a dose projection based on a ground level particulate release.
.The whole body doce rates calculated <
will be accurate but the child thyroid doses should be ignored.
7.1.3.2.2 Isocondenser Accident The isocondenser accident will ;
generate a source term based en the ,
core condition or t. reactor coolant sample, and the reactor pressure.
Ttis calculation assumes an entire ,
tube bundle ruptures ar.3 thus is a ;
worst case estimate only. ;
7.1.3.2.3 Aument Offgas Accident If a leak should develop in the Augmented Offgas (AOG) system this calculation can be used to develop a worst case source term. The coolant DEI is the only parameter needed.
The calculation assumes the entire AOG flow is being released to the atmosphere.
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Oyster creek Emergency Dose calculation Manual 4
- 1- e s 7.1.3.3 contingency calculations
. 7.1.3.3.1 Drywell !
The drywell contingency calculation is used to develop a source term ,
based on activity contained in the drywell. The calculation calculates [
i a source term for containment i venting, drywell leakage, or drywell failure.
If a dryvell air sample is available, it is used to determine the ,
activity. Otherwise, the CHRRMS monitor reading is used along with time after shutdown to calculate the drywell airborne activity.
After the drywell activity is calculated, the user is prompted for the release path. If containment venting is chosen, the vent line-up specified by the Emergency Operating l'rocedures is assumed.
1 If venting is not chosen, the user is asked if the containment ic intact.
This means that all penetrations and seals are closed and venting is not (2720P) pg,o p
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gf OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 93DO-ADM-4010.03
Title Revision No.
Oyster Creek Emergency Doce Calculation Manual 4 anticipated. Answering yes to this !
prompt leads to a calculation based
~
on normal drywell leakage. Drywell pressure is needed.
Finally, if neither of the above two options is chosen the user is asked-to enter a drywell leak rate. If the leak rate is not known, entering 0 to to this prompt will activste the leak rate calculation utility (7.1.5.5.1).
The two drywell leak rate scenarios require the statue of SBGTS and the stack ficw rate to be known. If the RAGEMS connection has been made, the RAGEMS computer will enter the stack flow rate.
p 7.1.3.3.2 Reactor Building l-The reactor building contingency l generates a cource term based on a l
known volume of reactor building.
l Reactor coolant concentration is l-based on either a reactor coolant sample or a core condition.
Concentration based'on core condition is the worst case for that core condition.
(2720P) 29.0 9
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@ f OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MA!;UAL Nufther 9300-ADM-4010.03 Title Revision No.
oyster Creek Emergency Dose Calculation Manual 4 The user is prompted for leak rate, how long the leak will last, stack flow, and the status of ssGTs." If the RAGEMS connection has been made, the RAGEMS computer will enter the stack flow rate.
7.1.3.3.3 Turbine Building The turbine building contingency y l
generates a source term based on a /
known volume of reactor coolant being released to the turbine building.
Reactor coolant concentration is based on either a reactor coolant sample or core condition.
l concentration based on core condition i is worst case for that core condition.
The user is prompted for leak rate, j
how long the leak will last, stack l
i flow rate, and if the turbine building vents have been isolated.
If the vents are not isolated. the l
- j. code asks for the total vent flow
.re e . This is the flow from all l
three turbine building. vents. If the j (2720P) 4
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glgf OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number 9300-ADM-4010.03 Title Revision No. ;
oyster Creek Emergency Dose calculation Manual 4 I
RAGEMS connection has been made, the RAGEMS computer will enter the stack flow rate and the turbine building i vent flow rate.
7.1.3.3.4 Fuel Handling The fuel handling contingency assumes the FSAR analysis release to determine a source term if spent fuel is damaged. As with all contingency calculations, this calculation gives a worst case source term. Required inputs are time after shutdown, stack i flow rate, and SBOTS status. If the RAGEMS c6 air #Mtion has been made, the RAGEMS ci9puter will enter the stack flow rate.
l l 7.1.4 Meteorology The RAC computer will call the met tower computer to obtain the current meteorological conditions. The meteorological l-input screen, (Figure 2), displays met data, chooses which parameters will be used, and allows the user to edit meteorological data.
Initially the user is allowed to edit only the parameters which are needed to perform a dose projection. For example, if an elevated source term exists, only the (2720P) 31.0
glgf l OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Numb 3r 9300-ADH-4010.03 Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 elevated data may be edited. If no source term exists, then no data may be edited.
After the needed data has been edited, the user ls prompted to determine if he wishes to edit the data which is not needed. Answering "Y" to this prompt allows the user to edit the other meteorological parameters.
When the meteorological input screen io printed, the sectors affected by both a ground level release and an elevated release are printed at the bottom. This information is on the printout only, not the video display.
E10URE 2 Ragems Auto Ventilation FMT Readings Utilities A Sensor D Sencor USE Units 33 Ft Wind Speed 13.2 0.0 Mph 150 Ft Wind Speed 27.6 0.0 Mph 3Rn Ft Wind Speed 29.4 0.0 29.4 Mph 33 Ft .i.id Divection 292.0 0.0 Degrees 150 Ft Wind Direction 292.0 0.0 Degrees 380 Ft Wind Direction 292.0 0.0 292 Degrees 150 Ft 33 Ft Delta T -0.4 0.0 Degrees F 380 Ft 33 Ft Delta T -1.4 0.0 -1.4 Degrees F Elevated Sector Affected ESE Graand Sector Affected ESE (2720P) 32.0
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@hMf CYSTER CREEK RADIOLOGICAL CONTRT.LS POLICY AND PROCEDURE MANUAL Humber 9300-ADM-4010.03 Title Revision No.
. Oyster Creek Emergency Dose Calculation Manual 4 7.1.5 Other Functions 7.1.5.1 RAGEMS Direct Connection Pressing the Alt-R " Hot Key" brings up'tho RAGEMS display. The first time the key is pressed the computer will dial and connect to the RAGEMS computer. To leave the RAGEMS display press the ESC key. The RAGEMS line will stay connected as long as the operator does not tell the computer to break the connection by pressirag Alt-H while in the RAGEMS display.
Subsequent returns to the RAGEMS display will show the most recent RAGEMS data. The display will be automatically updated every five minutes as the RAGEMS computer generates new data. Data is also updated even if the RAGEMS display is not on the screen.
As long as the RAGEMS connection is active, the computer will automatically enter RAGEMS data points any time the user is prompted for RAGEMS information. The RAGEMS choice on the " Hot Key" line is hi-lited when the RAGEMS connection is active to allow the user to know it's status from anywhere in the program.
j 7.1.5.2 Automatic Dose Projection The Alt-5 " Hot Key" will perform a dose projection l
with no input from the operator providing the (2720P) 33,o
{ 4 . - .
@hgf OYSTER CREEK RADI8 LOGICAL CONTR8LS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 RAGEMS connection is active. If the Alt-A,* Hot ,
Key" is pressed without the RAGEMS connection, the operator will receive a warning.
'i The automatic dose projection uses data from the-RAGEMS computer to determine release path, SBGTS state, source term, an release duration. Het data is obtained by calling the met tower. When an automatic dose projection is performed, the Auto t
" Hot Key" will be hi-lited. If 7.1.5.3 Ventilation A simplified ventilation diagram can be displayed on the screen by pressing the Alt-V " Hot Key". The diagram shows the release paths for monitored rel, eases at oyster Creek. ESC returns the user to the main program.
7.1.5.4 Field Monitoring Team Readings l
Alt-F activates the Field Monitoring Team (FMT) reading window where data from the FMT's is manually entered. As data is entered, the four most recent data points are retained by the computer for display on the final output screen, i
Four input fields are requiredt time, FMT ,
location, whole body dose rate, and child thyroid dose rate. Use the up and down arrow keys and the l
l enter key to move between input fields.- The left )
S (2720P) 34,o
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QQhM7 OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number 9300-ADM-4010.03 l
Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 '
i and right arrow keys and the backspace key are used to edit within a field. F10 enters the data l
as displayed on the screen. j If an error is discovered after data has been entered, enter " ERROR" in the time input field. I This will allow the user to delete one of the existing FMT readings. By positioning the cursor ,
at the reading to be deleted using the up and down arrow keys, then pressing Flo, the reading is
/f deleted from the computer memory.
The ESC key returns. the user to the main program.
7.1.5.5 Utility Functions Alt-U activates the utilities menu. Six functions-are available which are explained below. .
7.1.5.5.1 Leak Rate Calculation The leak rate calculation uses Bernoulli's Equation to calculate an approximate leak rate for air, steam, or water based on the leak size in square feet and the driving pressure.
If the calculation is for air, the air temperature is also needed. The result is in efm.
(2". 0P) 35,o
@hgf OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 ;
Title Revision No. l oyster Creek Emergency Dose calculation Manual 4
)
Change of state resulting from either-steam or water at elevated temperature ;
and pressure being released to !
atmospheric pressure may be calculated i
if the enthalpy of the fluid in Btu /lb !
is known. The code will then .
calculate both stgam and water leak rates in efm.
7.1.5.5.2 Core Damage Estimation ,
A rough core damage estimation is done of using the CHRRMS reading and time after shutdown. The result is in percent fuel melt. This calculation should only be used until a core ,
damage calculation using EPIP-33 can be performed. (
7 .1, . 5 . 5 . 3 Field Iodine Measurement l
l This function will convert gross field data to a committed child thyroid dose rate. The minimum data required ares gross silver zeolite cartridge' l
l reading in ep+ tross filter reading ,
in epm, background reading in epm, sample flow rate in liters / min, sample 1
(2720P)
- 36.0
glgf OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number 9300-ADM-4010.03 i
Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 time in minutes, and time after shutdown in hours. The FMT I designation and location should also I be entered.
The input data are entered as in all full screen editing functions as described in 7.1.1. The resulting committed child thyroid dose rate is in mrem per hour of exposure. The time, location, and committed child thyroid does rate are automatically transferred to the Field Monitoring u Team (FMT) data entry function (7.1.5.4) for display if the operator e accepts the data from within the FMT l data entry function. .
7.1.5.5.4 Unit Conversions A function is available which will convert units of measurement from one measuring system to another.
Conversions are available for units of Length, Area, Volume, Flow, Speed, Pressure, Temperature, Dose, Equivalent Dose, and Activity.
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@ M7 OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 On choosing the conversion function, another menu appears to allow the operator to choose which of the above measurements will be converted. The next menu allows the user to choose the units which the value is currently in, or put another way, the units to j be converted from. The final menu chooses the units to be converted to.
Once these choices have been made, enter the value to be converted using.
I the F10 key. The result is the value j in the new units.
For example, to convert 10 feet to !
meters, the conversion function is chosen from the utilities menu. On
! the second menu, units of length ara ,
! l I
chosen. Choose feet on the third i
menu, and meters on the fourth. Then-enter 10 into the input field with the
- l. F10 key and the result is 3.05 meters.
.l The ESC key is used to backstep i
through the menus.
l l
1 i 1 ;
i a
(2720P) 38.0 l l
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rz hClM7 OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number 9300-ADM-4010.03 Title Revision No. ;
Oyster Creek Emergency Dese Calculation Manual 4 7.1.5.5.5 Semi-Infinite Cloud Approximation ]
Approximate airborne concentration in uci/cc and MPC for iodine are calculated based on a gamma reading and the time after shutdown. The l
gamma reading MUST be due entirely to :
airborne activity, not direct shine.
7.1.5.5.6 Calculator A simple calculator is available which will add, subtract, multiply, and q divide is the final function on the utilities menu. The calculator uses Reverse Polish Notation logic. An example is the best way to explain.
To add 3.5 and 7.6 in the calculator function, enter 3.5 using the F10 key. Next enter 7.6 with F10 key._
Finally, enter "+" with the F10 key.
The result is 11.1. To then divide this number by 2, enter 2, then "/".
The result is 5.55. The-symbols for the math functions are listed below.
+ addition
- subtract
- multiplication
, / division
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U gM7 ' OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number-9300-ADM-4010.03L
. Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 7.1.6 Release Duration Depending on the type of release, the computer may generate a default release duration. In the absence of better inf)rmation, this value may'be used for_the release
~
duration. Before using the default, check with the-engineers, control room, TSC, and Parsippany or use your own judgement to determine if a better value is available.
If no default release duration exists in the computer, the_-
operator must provide an estimate for the release duration.
7.1.7 Final Ouput The final output gives total dose, dosa rate, and time to -
the PAG for both whole body and child thyroid exposures;for the site coundary, 2,5,'and 10 miles. The distance to the maximums is-also displayed for both whole body and child thyroid along with the dotal dose, dose rate, and time to PAG for the maximum.
The center section of the display shows the most recently entered meteorological data. Below that are the four most i' recent field monitoring team readings. The maximums and wind directions are hi-lited in yellow to-distinguish the most important information.
i
.(2*20P) -40.0 l 1
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, L u ~ . - , , 1 M@hM7' OYSTER CREEK RADIOLOGICALLCONTROLS Numb r POLICY AND PROCEDURE MANUkL' 9300-ADH-4010.03r r
Title 4 Revision No.'
Oyster Creek Emergency Dose calculation Manual' 4.
_ A hard copy is made of this display,(FAgure 3).which also
- includes the Emergency' Classification which is appropriate for the projected. doses. The logic used to calculated the classification ist.
Emergency- Maximum' Dose'(mrem)'within 10 miles- N. ..,
Classification Whole_B_odv' Thyroid None. O <= Dose < 10 0 <= Dose < 50 .-
Y; Alert 10 <= Dose < 50 50 <= Dose < 250 I '
Site Area Emecgen.cy 50 <= Dose <1000 -250 <= Dose <5000 General Emergency 1000 <= Dose 5000 <= Dose The classification is determined based on the most limiting of the maximum whole body dose ,and maximun. child thyroid I dose, ,
Finally, all inputs and aosumptions used in' obtaining the done projection are listed.. These may be uved after the fact to reconstruct how the dose projection wan done. 7 i
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l .
T l .
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g gp OYSTER CREEK RAD 8oLoGICAL CONTROLS POLICY AND PROCEDURE MANUAL Numb 0r 9300-ADM-4010.03 Title . Revision No.
oyster Creek Emergency Dose Calculation Manual 4 FIGURE 3 Ragoms Auto Ventilation FMT readings Utilities
-- TIME 20:24 WHOLE BODY CHILD THYROID Dese Rate Hours Dis. Chi /Q Dose Dose Rate Hours Dis. Doze mrem mrem /Hr to PAG Miles mRen mham/Hr to PAG Miles Sec/M*3. ---------- --------- ------
e--., ---- ..--
SB 1.61E-015 BKG BKG ' >99 SB 7.25E+002 1.04E+002 9.7 7.41E+; 1.06E+002 9.5 2.0 4.18E-007 3.94E+002 5.62E+001 88.9-30 2.69E-007 2.53E+002 3.61E+001 >99 5.0 2.90E+002 4.15Et001. 24.1 5.0 10.0 1.35E+002 1.94E+001 51.7 10.0 1.32E-007 1.23E+002 1.76E+001 >99 Max. Max.
Dose Dose 0.9 9.39E+002 1.34E+002 7.5 2.2 4.24E-007 3.99E+002 5.70E+001 .87.7 MET DATA Ground Wind Speed 13.2 mph Elevated Wind Speed 29.4 mph Ground Wind Dir (to) 112 degrees Elevated Wind Dir (to) 112 degreen Ground Stability Class -D
~
Elevated Stability Class D FIELD READINGS
( .- Time Location 4. WB Dose Rate CT Dose Rate 08:51 Lacey Rd and Rt 9 45 mrem /hr bkg mrem /hr 08:55 Lacey Rd and Parkway bkg mrem /hr bkg mrem /hr l
09:00 Lacey Rd and Eldg 12 access Rd 120 mrem /hr bkg mrem /hr l
09:1b Bayville Mcdonald's 53 mrem /hr 10 mrem /hr F1 Update All F2 Source Term F3 Met Data F4 Update Dose F9 Quit ,
EMERGENCY CLASSIFICATION SITE AREA EMERGENCY based on whole body dose 1
( ASSUMPTIONS / INPUTS USED Time = 20.:24 Date = 3/6/1990 Stack-release calculation Stack low range reading = 0 cps
-' Stack high range reading a 1.000E-013 Amps Stack high range reading = S.000E+000 uCi/cc Stack flow rate = 13'7 500 cfm l Time after shutdown = 0.00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> containment spray not considered Clad damage spectrum chosen
(.03 noble gases, .02 iodines w/ nartition factor of 1000)
SBGT not operating Release duration = 7.00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> (2720P) g
e-,
- s '
o ,
V g
~
g f- OYSTER CREEK RADIOLOGICAL CONTROLS Number.
- POLICY.AND= PROCEDURE MANUAL 9300-ADM-4010.03
' Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 ,
7.2 Theory
~
r 7.2.1 ~ Source Term The Source Term portion of the Oyster Creek RACP'is'used to '
a generate the quantity and radionuclide composition of the ']~ ;
radioactive material released (or aval:able for release) to-the environment. Releases are divxded into three'
. categories monitored, unmonitored, and contingency.
]
Monitored releases are from tha'two release-points monitored -T by the RAGEMS system. Unmonitored releases are potential release points which are not included in.the RAGEMS system.
contingency source terms attempt to generate a source term for-the "what if" cases. The source term module calculates release rates by isotope in uci/s.. .;
, 7.2.1.1 Spectrum Determination
~
Except in cases where an actual RAGEMS or coolant sample is available, a precalculated spectrum must l
be assumed. The assumed spectrum takes two l: different forms depending on the type of 1
, calculation being performed. If the source term t-is being determined for a monitored release point, l three spectra from Ref. 1 are used. Tnese spectra 1
represent assumed isotopic fractions for the 13 ;
isotopes assumed to be present in an effluent stream.
r -(2720P) 43.0
7 n: . , - - 1 lJ He' >
. U @ M f.. NfST2R CREEK RADIOLOGICAL CONTROLS Numb 3r 9300-ADM-4010.03 i
POLICY AN
D. PROCEDURE
KANUAL.
it
. Title' Revision No.
[g .,0yster Creek Emergency Dose; Calculation Manual 1 -4 These isotopes are KrB5 I131 KrB5m I132 Kr87 I133 ,
Kr88- I134 '
Kr133 I135 i
Xe133 1135- !
~ ?
Xel33m b
Xe135 l Xe135m-Alternately, for unmonitored rel: e se s and contingency calculations, expect 9d isotopic-4
. concentrations based cn.either the above spectrums, L e.g., isocondenser release or historical plant data, e.g. Augmented Off Gas (AOG) release,-are used. The clad damage-spectrum for these cases assumes.100% of j i
~
the full power clad inventory is released to the.
reactor coolant. Fuel melt assumes'100% core inventory of the 13 isotcpes is released to the i- !
If the computer operator knows the core condition, l]
he may directly choose the appropriate spectrum. If !
I not, he is pro'mpted by the code for plant parameters to determine the appropriate spectrum. Criteria for f i>
choosing opectra ares (2720P) 44.0 t 2 ,
J i_ - . j
M ,
- .; O
~E
[ Q7~
. OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Numbsr 9300-ADM-4010.03 Title Revision No.-
i ~
Oyster Creek Emergency Dose Calculation Manual 4 Fuel Melt Drywell hydrogen 20.5%. ~J CHRRMS 230,000 R/,hr Rx level < =<30" TAF for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ors i greater Clad Damage CHRRMS >1,000 and <30,000 R/hr t
Rx' level 3 30" TAF'for less than 1 hr. c I
-i Rx level 5 0" TAF Anticipated transient without scram
,1 (ATWS)' j control rod drop f
Fuel handling accident No Damage All other cases
. .j 7.2.1.2 Monitored 1
Two release points are monitored by the RAGEMS
, system. The main stack is' monitored by RAGEMS'I,
.i and the Turbine Building vents by RAGEMS II. .Both [
t systems consist of a high. range ion-chamber and low range scintillation detector which continually sample the effluent stream for noble gases. Flow, .;
indications are also available. For a more detailed description, see reference 2. tj 7.2.1.2.1 Stack j If a stack RAGEMS isotopic sample is '[
i l available, the. individual isotopic concentrations are multiplied by the u :
E (2720P) 45.0 l.. , j '
~. -- -
t V .
@ M7 ' OYSTER' CREEK RADIOLOGICAL CONTROLS' POLICY _AND PROCEDURE' MANUAL Numbor 9300-ADM-4010.03 l
Title _ _
Revision No.
Oyster Creek Emergency Dose, Calculation Manual 4 r
stack flow rate to develop a source !
term. The stack flow rate-is either .
available from the RAGEMS computer or l t
calculated using fan status and rated f
- flows. 4
[
In the absence of-a stack RAGEMS- ] '
p sample, the RAGEMS monitors are used l .
along with precalculated spectrums and: }
i-the stack flow rate. RAGEMS Af. '
-information is either input directly l
from the RAGEMS-computer as, discussed L in Section.7.2.4.1-or input manually l by the. computer operator.
Points available from the RAGEMS ri b -;
systems and normal' background levels where applicable, are
.i Stack Low Range <10 crs Stack High Range 1.0 E-13 Amps Stack'High Range .00676 uC1/cc Stack Flow Rate (cfm) 1 T.B. Low Range- <10 cpm ;
Feed Pump Room vent flow rate (cfm)
Operating Floor vent flow rate (cfm)
Lube Oil Bay vent flow rate (cfm) l'~
l.
(2720P) 46.0 1
- /[ s
- g"- l
[rj r )j Q@lgf OYSTER CREEK RADIOLOGICAL Cor3TROLS-POLICY AND PROCEDURE MANUAL-Number 9300-ADM-4010.03 Title Revision No.
Oyster Creek Emergency Dose Calculation Manual .4 Three different inputs from the RAGEMS I system are accepted by the computer. These-cre:
-
- Low range in cps from panels 1R and-;0F High range in amps,from panel 1R-High range in uCi/cc from the RAGEMS~ computer Gross effluent noble gas concentration is then' calculated as Cn = Ls/4.11ES (1)
If Cn > 0 or s 5 this value is used.
>.5 and either of I'f If Cn 5 0 or Cn the high range readouts are on. scale (above .01 uci/cc) then:
If the RAGEMS computer stack hi-range is on scale:
C n- =H us (2)
Otherwise if Hus is-not available Cn = H a/4.06E-10 (3)
Where Cn = total effluent n e gas concentration (uCi/c.
Le = RAGEMS I low range monitor reactivity (cps)
H us = RAGEMS I computer hi-range reading (uci/cc)
H, = High range reading (amps)
(2720P) 47.0 l
1 g gf OYSTER. CREEK-RADIOLOGICAL CONTRO2.S Numbst t K . POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title Revision No.
Oyster Creek Emergency Dose Calculation Manual- 4 ,
a 4.115ES = low range conversion factor eos f uCi/cc , ,. j 4.06E-10-= high range conversion factor amos' uCi/cc d
'After the appropriate spectrum-is chosen as described in 7.2.1.1, the -
spectrum is decayed .for time af ter ,
e l:
L shutdown. If the Standby Gas =
l Treatment System (SBGTS)-is operating, -
the isotopic. fraction-for the iodines are reduced by a factor"of 10 (90%
efficient). The: iodine fractions are.
y further reduced by a factor of 10 if I'
the release is from the Drywell and
-containment sprays are operating to L take credit for iodine washout I'
(Bef 3). The decayed, filtered, and p scrubbed isotopic fractions are then l'
renormalized to 1.0 to give a t
prediction of the isotopic spectrum at the time of-release.
i Isotopic source term is thens
~i Ci = Cg *El (4)
In (2720P) 48.0 s
^
s
+
g g f'. OYSTER CREEK RADIOLOGICAL CONTROLS' Numb:r'
, POLICY AND PROCEDURE MANUAL .9300-ADM-4010.03 ,
Title . Revision No.: ,
.0yster Creek Emergency Dose calculation Manual-4 where:-
[
CN = gross noble gas source term Ci =. concentration of isoto'pe i (uci/ce)
F1 = release. fraction of isotope-1. '
. s .:
8 4
En = E F1 = eum of noble gas fractions
.i=1 ,
1 i = 1 to 8 for' noble gas isotopes i ' 9 to 13 for iodine isotopos Because the RAGEMS sampling system ~
/f conta'ine iodine and particulate filters, the RAGEMS monitors detect only gross noble gas source term.
Equation l'our calculutes individual .
noble gas source terms by-multiplying gross noble gas source ~ term by the :
l assumed isotopic release fractions.
The iodine isotopsi are not measured by the RAGEMS system. Since only a noble gas gross concentration is t
calculated, an expected-lodine to c noble gas ratio is used. This b calcalated as:
. R.ng = E1 (5) 3g n ,
I, I'
l
, (2720P) 49,o
- .~ -
J t
$1-QQ Mf ' '
OYSTER CREEK RADIOLOGICAL CONTROLS ~
POLICY AND'PROCEDUR2 MANUAL Number,
'9300-ADM-4010.03 i
i s ,
Title. Revision No.
oyster Creek Emergency suse Calculation Manual- 4 4
Where Ring =. lodine to' noble gas ratio 113 Eg.= E F1 = sum of iodine fractions i=9 The gross lodine concentration would.
then be l Cy=CN *JRing' (6) 'f Where Cy = total iodine effluent- ,
concentration (uci/cc).
The isotopic lodine concentrations L
- are s ,
?
Ci = C3 *1L. (7)
E I
or Ci = Cy*
- 11 '(8) - .. ]
which reduces to equation (4)
Isotopic source term is' calculated.as:
Si = Ci
- FR
- 472 (9)- r where: ,
l FR = stack flow rate (cfm)
L 472 =' conversion factor 2211 i
E cfm ,
t l Si = release rate of isotope 11gG1' e
7.2.1.2.2 Turbine Building The turbine building has two release 1
points. The condenser bay exhausts to the i rain stack. The TB operating floor, feed pump room, and lube oil bay exhaust
- (2720P) 50.0
^ '
+
(/i hIj @ Mf OYSTER. CREEK RADIOLOGICAL' CONTROLS POLICY AND PROCEDURE MANUAL Numbar 9300-ADM-4010.03 Title _
Revision No.
Oyster Creek Emergency Lose Calculation Manual 4 through vents which are monitored by the RAGEMS system. The isotopic source term for the portion of the: rel'~ase' e which goes-
, to the main stack is. calculated'using,the 1 same method-and constants outlined in 7.2.1.2.1 with the exception that no SBGTS filtering or' containment spray washout exists.
9 Similar to the stack (7.2.1.2.1),- if af Turbine Building kAGEMS sample is available, source term is determined using the isotopic concentrations and.the total Turbine Building' vent flow rate.
Otherwise the RAGEMS II monitors are used' to develop a source term The RAGEMS-II system }1 .as the following points:which are available-via' the RAGEMS computer.
Turbine Building low range (cpm) Turbine Building high range (pci/cc) Feed Pump Room vent duct flow rate (cfm) (fp t )
(2720P2) 51.0
'd- +
i,. :v,_
Q M 7) OYSTER CREEK RADIOLOGTCAL CONTROLS Numbhr
, -POLICY AND PROCEdifrE MANUAL ~ 9300-ADM-4010.03 Title Revision No.
Oyster. creek Emergency Dose' Calculation Manual 4' Operating Floor vent duct.(TB stack) flow-1 rate (cfm) (Op vent) 1 Lube Oil Bay. vent duct flow' ra'teJ(cfm) '
U' (Lb vent) e Gloss effluent noble gas concentrations is l1 calculated as: 4 CN " L T/5.032E6 (10) j If CN >0 or $.5 this valve is used.
L If C N50 or CN >.5.and the RAGEMS II hi.gh range monitor is on scale (above 0.01 0
pCi/cc) then CN = Hut (11) l l
}
t; where: i e
CN = t tal effluent n,oble; gas
., concentration ggi L
cc L '!
LT = RAGEMS II low range monitor (epm) s n .
Hut = RAGEMSLII~high range-monitor ;
L
( Ci/cc) l 5.032E6 = low range conversion factor ,
l (cpm /pci/cc).
- j. .
Total flow is the sum of the three vent flows FR = Fp vent + Op vent + Lb vent l or a default value of 47,000 cfm.is used.
! Once the gross noble gas source term and I-flow . _a have been calculated, the h
(2720P2) 52.0 l
t a- -
- . OYSTER C K RADIOLOGICAL' CONTROLS .Numbar (r;() j%g g f-
. POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 l-Title < Revision No.
Oystgr' Creek Emergency Dose Calculation Manual 4 isotopic release rates are calculated using equations (4) and (9).of 7.2.1.2.1.
~ '
7.2.1.3 'Unmonitored Three methods of-developing a source term during an unmonitored' release are contained in-the-code. The most general is through the use of a downwind gamma reading to develop a source term. Accident-specific source term can be generated for on isocondenser failure and an AOG line break. The calculations are overly conservative because of the nature of an unmonitored. release and should be treated as such.' -
' 7 .1 '.1. 3 .1 Field Monitoring Team Reading This calculation uses a downwind -
centerline gamma reading and the time after shutdown to develop an isotopic source term. The calculation assumes a clad damage spectrum since this.is used'in the majority.of the severe FSAR accident analyses.
The spectrum is decayed for time after shutdown,-then renormalized to 1.0. Next, an assumed gross release rate of 1 yCi/cc and flow rate of 1000 cfm arr.insed to perform a dose projection at the downwind distance where the gamma dose rate was taken. This spectrum is:
Sia = 1.0
- Fi
- 1000
- 472 (2720P2) 53.0
s .- ,
Nyder orSrzR CRr R RxDrotoozcit ConrRots POLICY AND PROCEDURE MANUAL.
==mder 9300-ADM-4010.03 Title- Revision No.
oyster Creek Emergency Dose Calculation Mauusi 4 where Sia = assumed isotopic source term.
(pCi/s) 1.0 = assumed gross release concentration (pci/cc)-
Fi' = isotopic fraction of isotope-1 1000 = assumed flow rate (cfm)-
472- = conversion factor (cc/s/cfm).
Using the'resulting calculated dose rate, the source term is than calculated as:
Si =
Sia
- DRc/DRm where S i- = -19etopic source term (pci/s)
)'
DRc = calculated dose rate using assumed isotopic source. term--
DRm = measured dose rate 7.2.1.3.2 Idocondenser Accident At Oyster Creek-two isolation condensers are-used as part of the Emergency Core Cocling System. These isocondensers are shell and tube hees exchangers with steam from the reactor flowing through tubes, giving up energy to water on the shell side, condensing, and returning to the reactor. As' the shell side sator warms, it eventually begins to boil and releases.
i-steam.to the atmosphere. In the event of 1
(2720P2) 54.0 wa-
_ ~ . . . .. . . . .
U --
i\ ,
(4j (j] g gf OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL
. Numb 3r 9300-ADM-4010.03' Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4
.. a tube leak or rupture, a-direct path' exists for reactor coolant-to be released to the-atmosphere.
A single isocondenser consists of two U-shaped tube bundles, each:with 36 tubes. Bacause it is not practical 1to-determine the number.of tubes which are leaking, this calculation assumes an
' entire tube bundle to have ruptured.
Coolant leak rate is calculated:
LRc =
165000 * (Pr/2.5) 1/2 * .016/60.
where:
'LRc == coolant leak rate (cfm) 165000= rated flow rate through tube bundle at 2.5 lb pressure drop (lb/hr)
Pr = reactor pressure'(PSIA)
=
2.5. = : pressure for rated flow (PSIA) 0.16 =. specific volume of water 3
(ft /lb) 60 =
minutes (cr hour The coolant concentration is obtained either from a reactor coolant sample if i
one is available or precalculated spectra as described in 7.1.1.1. If the precalculated no. damage spectrum is used,
., which represents the normal coolant (2720P2) 55.0
Ihi NIj @ Mf OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Humb3r-9300-ADM-4010.03 Title ~
Revision No.
Oystericreek Emergency Dose Calculation Manual' 4 concentrations, it is adjusted-to current conditions by ratioing the actual DEI to-that assumed for the spectium.'
d The resulting' coolant isotopic o concentraticns-are then multiplied by the calculated leak rate;to give an isotopic source term in C1/s.
7.2.1.3.3 Augmented offgas A3cident The Augmented Offgas (AOG) system is used.
to hold up and filter the ef fluent -f rom the air ejectors before it is released via the stack to the atmosphere. -This.
,- calculation assumes a normal AOG isotopic.
spectrum a9 developed in' Reference-4.
The release spectrum'can be modified to match current conditions by the.use_of a current' DEI. This.value is ratioed to the DEI of the assumed normal coolant to modify the assumed release concentrations. 'A standard AOG flow rate of 122 cfm is useds 7.2.1.4 Contingency Calculations Contingency calculations attempt to develop a source term for the "what if" cases before a release actually begins. Four contingency calculations are available.
J (2720P2) 56.0 y.
i?
i-
.h g.7 . OYSTER CREUK= RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL-Nambr.r 9300 '.DM-4010.03 v
s Title Revision No. >
- Oyster Creek Emergency Dose Calculation Manual 4-2 Because these are contingency calculations and -)I 7
assumptions must be made, it must be stressed-that the calculations are worst case-for a gived ac'cident.,
7.2.1.4.1 lDrywell ,
The drywell contingency calculation is' used to. develop a- source ternt for an t .
actual or hypothetical accident in the 4 drywell. A drywell' isotopic air sample ~Is ,
sicher'directlytinput by.the operatar or; j calculated based on the Containment High' A Range Radiations-Monitoring.Syster (CHRRMS). If the CHRRMS is used, gross concentration is calculated:
1- +
ly) = DRc
- 813
- 1E6/8.8E9' l
t where:
Cp = gross containment airborne concentration ( C1/cc) 813 = gross activity'(C1) per R/hr_in containment, see Reference 5' ,
'1E6 = conversion (pci/C1) 8.8E9 = free air volume of drywell and torus (cc) Reference 9 DR C = CHRRMS monitor reading (R/hr) .
The CHRRMS reading is then used to. choose
' ,l an isotopic spectrum as outlired in 7.2.1.1. After the spectrum is decayed 4
for, time after shutdown and renormalized, (2720P2) 57.0 .>
t 4
g , .,
- w.
( ,- . :p
[.
s.
+
- ; ~
i e g'., g.,
ky3 gf OYSTER CREEK RADIOLOGICAL CONTROLS Number 9300-ADM-4010.03 POLICY AND PROCEDURE MANUAL Title Revision No.
- , Oyster Creek Emergency Dose' Calculation Manual 4
'1 drynell isotopic concentration can be 7
calculated .
~ '
Cg=Cp p
- fL .
s
.where: .
C D1 =: concentration of isotope 1 in the;
-drywell1 fi = decayed and renormalized isotopic fraction of isotope i After the isotopic concentrations are .
1 either entered or calculated as outlined. ',
above, the rel1ase rate from the dryvell' ,
is needed. This calculation addresses three release paths. The first is >
d~
containment venting...The Emergency {
Operating, Procedures:-(EOP's) specify a venting lineup through the SBGTS. Worst !
cat e, this would give a flow rate of 2600 cfm from the drywell to the main stack' .
Isotopic source terms are then St=Cpt.* 2600
- 472
- FFi .
where S
t
= isotopic release rete (yci/S)-
2600 = maximum flow rate through SBGTS (cfm) 472 =
conversion factor.((cc/s) / cfm) r FFi = filtration factor 1.0 for noble gases, 0.1 for iodines p
(2720P2). 58.0 7
t
Y * '
V
@lg7 . OYSTER' CREEK RADIOLOGICAL CONTROLS' Number
POLICY AND PROCEDURE MANUAL. 9300-ADM-4010.03' ,
. Title Revision No. -$
Oyster Creek Emergency Dose Calculation Manual L4 l The second release calculation which can be calculated is the release due to normal s r
i drywell lerkage. The drywe'll leakage'is. ,5 s
calculated es a function of drywell_- 4 r
pressure as DL = .632 * '(P/35)h-r472 D
- where DL = drywell leakage (cc/s) .
.632 = . Tech Spec drywell leakage at.
35 psi (cfm) 35 = Tech Spec drywell pressure-(psi)
P D
= Drywell pressure (psi)
This value, when multiplied by the drywell-isotopic concentrations, yields an : '
isotopic source term.
The third release calculation allows the-user to directly enter a drywell leak rate (DL) due to drywell failure.' The two
)
methods of determining drywell leak rate i assume the leak is directly from the- 3 drywell to either SBGTS.or the stack. No credit is .aken for holdup or dilution in d the reactor building. If stand-by gas is on the iodine release rates are reduced by a factor of 10.
(2720P2) 59.0
i.,g
~
(rj gij g gf OYSTER CREEK RADIOLOGICAL CollTROLS POLICY AND PROCEDURE MANUAL IIoter -L 9300-ADM-4010.03' Title .
Revision No.
Oyster Creek Emergency Dose Calculation Manual' 4 7.2.1.4.2 Reactor Building The reactor building contingency calculates a release rate EasedLon a volume of coolant released to the reactor building. Coolant concentrationfis'either:
manually input or; assumed based.on the entered spectrum as outlined in 7.2.1.1' with the "No Damage" spectrum corrected for current DEI. Isotopic source term is then calculated as:
St=Cy* (LR*LT*3785/5.04E10)*2600*FF t*472:
if SBGTS is on and St=Ct * (LR*LT*3785/5.04E10)*65000*472-if SBGTS is off' wherce S = isotopic release rate (pci/s) t Ct = isotopic coolant concentration (pCi/cc)
LR = leak rate (gpm)
LT =
leak. time (minutes) 3785 = conversion factor (cc/ gal) 5.04E10= volume of reactor building (cc)
Reference 9 2600 = SBGTS flow (cfm) 65000 = reactor building fan flow (cfm)
FF t = filtration factor; 1.0 for noble gases, 0.1 for lodines 472 =
conversionfactor(CC[e)
- . (2720P2) 60.0
h[ "
. .i m- ,
.1, -
S'.
@ M7 . OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE: MANUAL Number-9300-ADM-4010.03
=
. i. . . Title Revision No.
' Oyster Creek Emer,gency Dose Calculation Manual 4 7.2.1.4.3 Turbine Building 4.._ The turbine building contingency-ac calculates a source term bssed on a volume f of' coolant' released to.the, turbine- '!
r ,
building. Because the turbine building '
has both elevated (main stack) and ground.
't level (TB vents) release points, both l' elevated and ground level source ' terms are [
devel'oped.
Reactor coolant concentration is either' ,a manually input or assumed based on the if';
h' entered spectrum as' outlined in 5.2.1.1' with t.;e "No. Damage" spectrum corrected
.for current DEI. Elevated source term is:
4 S,3 = C i*(LR*LT*3785/1.0 Ell)*86000*472 .
where -l S
t
= isotopic release rate (pCi/s).
Ct a isotopic coolant concentration I (pCi/cc) ,
r
~
IR = leak rate (gpm) '
LT =
leak time (minutes)
, 3785 =- conversion factor (cc/ gal) j-
?
1.0E11= volume of turbine building (cc)
Reference 9 86000 = turbine building fan flow (cfm)-
i 472 =
conversion factor (cc/s / cfm) <
I
-(2720P2 ? 61.0 1 e r 4
tw;
{ zo g gf OYSTER CREEK RADIOLOGICAL CONTROLS Number.
9300-ADM-4010.03 POLICY-AND PROCEDURE MANUAL Title .
Revision No..
Oyster Creek Emergency Dose Calculation Manual 4- ,
and the ground level source term, if.the k s
vents are not isolated is: ,
=
Sg L g*(LR*LT*3785/1.0E11)*FTB*472 where: ,
i FTB = total' turbine' building vent flow. !
(cfm) .
= Operating Floor vent flow + Pump Room vent flow + Lube 011 Bay vent- 't
, flow 5.2.1.4.4 Fuel Handling ,
The fuel handling accident contingency t ,
develops a source term for a fuel handling: ,
accident.- This calculation assumes a fuel j~
1
!= bundle is dropped onto the core with damage. s
-resulting to 124 fuel rods (FSAR-ll -
analysis). One hundred' percent of the gap-I
' activity contained in the rods is released l
to the refuel floor. At T=0 the gap 1
activity contained in 124 fuel rods by T
l isotope is -
E Kr 85 38.9 C1 Kr 85m- 1670 Ci Kr 87 3260 Ci Kr 88- 4750 Ci ,
Xe 133 11900 C1 Xe 133m 418 Ci Xe 135 2370'Ci j Xe 135m 3450 C1 I 131 3960 Ci I 132 5570 Ci I 133 7890 C1 3 I 134 8820 Ci I 135 6960 Ci These values were calculated using total gap activity from Reference 3 and (2720P2) 62.0
- 1- - - -- --- --- - -
gigt s m. -
6
'L g gf _ - OYSTER ' CREEA RADIO 2.OGICAL CONTROLS ' Number .
POLICY AND PROCEDURE. MANUAL 9300-ADH-4010.03 Title Revision No.
Oyster-Creek Emergency' Dose Calculation Manual 43 .
multiplying by 124/34720 to represent the fraction of fuel pins damaged.
These activities are first decayedLfor the-
~
time after-shutdown, then considered to be .
I released to the refuel floor atmosphere. ;
, i Release rates are calculacedt. !
S g = R g*1.0E6/2.0E10*1270*472*FFt-l-
l' if SBGTS is' running, or l-St = Ry*1.0E6/2.0E10*31700*472*
lL L
if SBGTS is not running where:
Rt =- decayed amount of isotope 1 release-(C1) l- 1.0E6 = conversion (pci/C1) 2.0E10= refuel floor volume (ce)
, 1270 = maximum flow rate from' refuel.
'l floor with SBGTS on-(cfm)
=> filtration factor 1.0.for noble gases, 0.'1 for lodines.
31700 = maximum' flow rate from refuel .!
floor with reactor building fan on (cfm) {
S t
= isotopic release rate-(yci/s) -
472 =
conversionfactor(eefe) f FF t = filtration factor 1.0 for noble gases 0.1 for lodines 7.2.2 Meteorology .
t Normally, meteorological parameters are obtained through a direct ;
- connection, via modem, with the Forked River met tower. If the conn.ection cannot be completed, or the operator wishes to i (2720P2) 63.0
(if NI) Q @f OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL' Number 9300-ADM-4010.03 Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 manually enter meteorological parameters, full screen editing allows both elevated (380 ft) and ground level (33 ft) parameters to be input. The code initially' allows only thos'e p'arameters which are necessary to perform a dose projection based on the source term to be entered. For example, if only an elevated source term exists, only the elevated parameters may be edited.
If no source term above background exits, initially no editing' will be allowed.
After'the needed parameters are entered, the computer asks the operator if he wishes to edit the' values which will be displayed Lf on the meteorology section of the final output, but not needed for the calculations.
7.2.2.1 Stability Class The difference in temperature between two helghts (AT).
is used as a measure of the atmospheric stability.
Based on the AT, one of the Pasquill-Gif ford stability classes is chosen. Specific criteria are as follows:
Stability Class Delta T Delta T-(380-33ft) (150-33ft)
Elevated Ground A < -3.61 < -1.22 B -3.61 to -3.24 -1.22 to -1.10' C -3.23 to -2.86 -1.09 to -0.97 D -2.85 to -0.96 -0.96 to -0.33 E -0.95 to 2.84 -0.32 to 0.95 o
F 2.85 to 7.58 0.96 to 2.55 G >7.59 >2.56 AT is in degrees Fahrenheit.
.(2720P2) 64.0
}-- ' y L ,
- [
gf-- OYSTER CREEK RADIOLOGICAL CONTROLS Number .
POLICY AMD PROCEDURE MANUAL- 9300-ADM-4010.03' 1 Title- Revision No. .
Oyster Creek Emergency Dose Calculation Manual 4 7.2.2.2 'Windspeed
- Although elevated wind speed is input by the operator or.the met tower computer, the elevated'wi'dn speed is adjusted for the height of the stack using the equation WSg = WSE Ihhhtl)P ,
i where:
WS g = adjusted wind speed (mph)
WS = entered wind speed (mph)
E 368.1 = physical stack height (ft) ,
380 = height of elevated sensors (ft) p = 0.25 if A, B, or C stability 0.33 if D stability-0.50 if E, F, or G stability The lowest adjusted wind speed allowed is 0.5 mph. >
7.2.2.3 Wind Direction L Both elevated and. ground level wind. direction are entered in degrees 'from'. Wind direction 'to' is calculated by adding 180* if'the wind directioncis less L than 180* or subtracting 180* if the wind direction is greater than 380*. The sector the wind is blowing into is based on the following ranges. .
(
Sector Degrees Sector Degrees Sector Degrees N 350-11 SE 125-146 W 260-281 NNE 12-34 SSE 147-169 WNW 282-304 NE 35-56 S 170-191 NW 305-326 ENE 57-79 SSW 192-214 NNW 327-349 E 80-101 SW 215-237 ESE 102-124 WSW 238-259 (2720P2) 65.0
( -
I glgf - OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 .
Title . Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 7.2.3 Dose *Projectior.s Two separate models are used by the RAC code tG calculate whole
~
body and child thyroid dose rates. Whole body dose rates =are calculated using a finite' gamma model which calculates dose rates from both an overhead cloud and immersion.- Child thyroid dose rates are calculated using a semi-infinite cloud model.
7.2.3.1 Release Height At Oyster Creek the only elevated release point is the main stack. All-other release points are considered ground level with a-release height of O. Elevated release height ist HR = 112.2 + Pr+Tg i where:
Hp = effective release. height (meters) 112.2 = physical stack height (meters)
P " P l ume rise calculated using the Briggs Plume R
Rise Equations (Ref. 13) j Tg = terrain factor based on downwind distance and wind direction (meters) 7.2.3.2 Building Wake Effect 1
For ground level releases a building wake effect is calculated which is used as a virtual source distance.
The distance simulates the building wake effect of the reactor building. The virtual distances for each of the seven stability classes are 209, 209, 209, 284, ,
483, 734, and 1219 meters, respectively. The virtual distance is added to the actual downwind distance before the dose projection is performed.
(2720P2) 66.0
q s.
h Qf OYSTER CREEK RADIOLOGICAL: CONTROLS POLICY AND PROCEDURE MANUAL Numb 3r 9300-ADM-4010.03- ,
Title Revision No.
Oyster. Creek-Emergency Dose Calculation Manual 4 ui ,
7.2.3.3 Finite Model The OCNGS RACP model calculates external whole body
(
gamma dose rate using a finite model f6r both ground; and elevated releases. The finite gamma dose. algorithm ,
is licensed from Dr. John Hamawi of Entech. Engineering.
\
through Pickard, Lowe, & Garrick, Inc. (Dr. Hamawi was the author of the dose integral routine listed in Appendix F of Reg. Guide 1.109). -The dose is computed by multiplying the dose rate by the expected dutstion of release.
The finite gamma dose algorithm in the OCNGS RAC modell has the same structure as Pickard, Lowe & Garrick's "IDAS finite gamma dose algorithm. The basis for the algorithm is-a three dimensional array of finite gamma factors. These finite gamma factors are pre-computed three dimensional numerical integrations which' appear l in the theory of the finite cloud model and represent l
the spatial distribution of the radioactive material in i the finite plume. These factors depend upon the plume dimensions at the downwind distance of interest, the l- plume elevations, and the average gamma energy of the nuclide mix in the cloud. They are sometimes referred to as " gamma X/Q" in the literature although.they are not derived from typ'ical X/Q calculations. The finite gamma factors in the array correspond to 28 downwind (2720P2) 67.0
,' a,
=m s , .
, i II @ g7 OYSTER' CREEK RADIOLOGICAL CONTROLS Numb 3r; POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title ,
. Revision No.
oyster Creek Emergency Dose Calculation Manual 4
c{
i distances, 6 heights above ground,' and 6 energy groups. Specifically, the downwind distances are 400, 500, 600, 700, 800,.900, 1000, 1250,~1500,1750,-
2000, 2250, 2500, 3000, 3500, 4000, 4500,;5000, 5500, .
6000, 6500,'7000, 7500, 8000, 9000, 10000, 15000, and 20000 meters. The-6 heights above ground-are 0, 50, 100,-150, 250, and 500 meters. The six energy groups ares 0.032, 0.081, 0.25,.0.25, 0.53, and 1.0 MeV. The abundances of the noble gases for_tho six energy groups were taken from MIDAS.
For effective release heights other than the 6 fixed
~
heights,-the finite gamma factors are extrapolated to that height. For downwind distances other than the 28 fixed downwind distances, the finite gamms factor of t
the nearest fixed distance is assigned to that distance, i.e., no horizontal interpolation is done, as ,
l is consistent with MIDAS.
The OCNGS RAC model explicitly includes the -
1' l contribution of I-131, I-132, I-33, I-134, and I-135 to l-the external whole body gamma dose. This method of 1
handling the contribution from the radioiodines is more accurate than the' method used in MIDAS. Th's abundances ,.
of the radioiodines were taken from the Radioactive Decay Data Tables, D.C. Kocher, ligl. All radionuclides are decayed during plume travel.
(2720P2) 68.0
4
+
s :%
h g[ OYSTER CREEK RADIOLOGICAL CONTROLS POLICY M;D PROCEDURE MANUAL Numb;r-9300-ADM-4010.03-I Title Revision:No. (
Oyster Creek Emergency Dose Calculation Manual <
s A more detailed discussion of the finite model is !
contained in Appendix A.
7.2.3.4 Semi-Infinite Model The OCNGS RAC model calculates the thyroid dose rate due to inhalation of I-131, I-132, I-133, I-134, and I-135. The thyroid dose rate is proportional to X/Q.
The constant of' proportionality is the product of the.
l child inhalation dose factors. The program uses the child breathing rate of 0.42 m3/hr (from Table E-5, Reg. Guide 1.109) and the child inhalation dose factors from Table E-9, Reg. Guide 1.109 to compute the dose rate conversion factors. The dose is computed ~by-
. multiplying the dose rate by the expected duration of L
the release.
The radioiodines are decayed during plume travel time.
The decay constants for I-131 through I-135'are from=
i
'the Radioloolcal Health Handbook, Reference'6. The ;
child thyroid dose rate at distance d is thent-DR(d) =((d) *i=1 [ Si
- DF i where:
DR(d) = child thyroid dose rete at distance d X (mrem /hr)
QId) =
chi over Q at distance d (s/m3)
S t
= release rate of isotope 1 (Ci/s)
DF 1 = dose factor for isotope i (2720P2) 69.0
di :
g{ OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND-PROCEDURE MANUAL 9300-ADH-4010.03 ,
i
Title:
Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 a specific dose factors are Il31 1.84E9 (mrem #"/hr)
I132
~
2.21E7 ~ '
I1?' 4.38E8 I13i- 5.76E6-I13L 9.0E7 The basis for the X/Q calculation is the Gaussian diffusion equation and al10 x 7 array of sigma y's and sigma z's for 7 stability classes and at 10 fixed downwind distances. For distances other than the fixed downwind distances, the sigma y's and sigma z's are linearly interpolated before X/Q is computed for that.
distance. The ten fixed distances ares 200, 500, 1000, 2000, 3000, 6000, 10000, 30000, 50000, and'80000. LJ l
meters. X/Q is calculated as:
- 1 -HR '
X(d) EXP Q WSg *.45*o y*og __ 20 g #__
where:
1 WS 3 = adjusted wind speed for the release height (mph) .;
.45 = conversion factor oy = lateral plume spread (m) o, = vertical plume spread (m) .
HR = effective release height (m)-
7.2.3.5 Maximum Calculation Maximum whole body dose rate is calculated by.
i performing both ground level and elevated dose projections, if appropriate, at the site boundary, 400, 500, 600, 700, 800, 900, 1000, 1250, 1500, 1750, 2000, (2720P2) 70.0 4
At )
II x.
h gf OYSTER CREEK RADIOLOGICAL CONTROLS
- POLICY AND PROCEDURE MANUAL' NumbOr 9300-ADM-4010.03 Title .
Revision No. i Oyster Creek Emergency. Dose Calculation Manual 4 2250, 2500, 3000, 3218, 3500, 4000, 4500, 5000, 5500,
}
6000, 6500, 7000, 7500, 8000, 8045, 9000,.10000, 15000, 16090, and 20000 meters. The-ground live 1*and elevated'
. values for each distance are then added-and compared to' find the highest value.
~
Maximum child thyroid dose-rate is calculated in the-same way except.that dose rates are calculated at the J .:
site boundary, 400, 600, 800, 1000, 1200, 1400, 1600, i
1800, 2000, 2500, 3000, 3218, 3500, 4000,'4500, 5000, 5500, 6000, 6500, 7000, 7500, 8000, 8500, 9000, 10000,-
11000, 12000, 13000, 14000, 15000, 16000, and 16090 meters.
7.2.4 Other Functions.
1' Several other functions exist, which although not required for I, dose projections, add considerably more power and user friendliness to the code. These functions are activated by." Hot l Keys" which can be used at any place in the code. Combinations of pull down menus and pop up windows.are used to simplify the '
l machine / user interface.
7.2.4.1 RAGEMS Direct Connection i
The RAGEMS computer is a DEC PDP-11 which is physically located in the computer room beside the Control Room.
e From the computer room, a chemistry technician.can i activate a display which is updated every 5 minute (2720P2) 71.0
+
l
=
,+
L g g{ ' OYSTER CREEK RADIOLOGICAL CONTROLS Numb;r POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 i ,
Title. .
Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 Data points on this display which are used for done
. projections are:
RAGEMS I (stack) High Range Reading CyCi/cc)
Stack Flow Rate (cfm)
RAGEMS II (TB) Low Range Reading,(cpm)
RAGEMS II (TB) High Range Reading (yci/cc)'
Feed Pump Room Vent Flow Rate (cfm)
Operating Floor Vent Flow Rate'(cfm) !
Lube Oil Bay Vent Flow Rate (cfm)- 'I Because of staffing problems, the physical location'of the computer, and communications problems there has _,
~
been difficulty in obtaining RAGEMS data for dose-projections, especially of the TSC and EACC. To
'l alleviate this problem, a direct connection via modem is available between a computer running the RAC code and the RAGEMS computer. The RAC computer initiates- -
the call which is automatically answered by the RAGEMS i
computer. The RAC computer then gives the appropriate j
'l account name, password, and commands to the RAGEMS I computer to establish a communications link.
The RAC computer then monitors the RAGEMS connection J I
and updates the above 7 data points as they are sent t l
from the RAGEMS computer. This communication takes I place in'the background and is invisible to the user.
The communication between the two computers continues l
'until the operator hangs up from the RAGEMS computer. !
J E
i (2720P2) 72.0 i i
L j
..l
I
- 1 -!
m 1-r h gf OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Numb;r -
9300-ADH-4010.03
- . Title Revision-No.
Oyster Creek Emergency Dose Calculation Manual 4 While there is-a connection with the RAGEMS computer, the RAC code will display the RAGEMS data points and
, 'also enter them into calculations. Th'i operator may-override the automatically entered values for i: calculational purposes, but may not change the actual 8
'RAGEMS data.
7.2.4.2 Automatic Dose Projection ,
With the direct _ connection made to the:RAGEMS computer, i
a dose projection based on the RAGEMS data can be-made with no operator input.
- The computer looks at the RAGEMS data to determine where a monitored release is coming from. If either o'f=
the Turbine Building monitors is above background,-the release is considered to be from the Turbine Building.
Otherwise the release is from the Reactor Building.
L The computer assumes a clad damage spectrum and 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> l
time after shutdown.
A source term is then calculated as outlined in 7.2.1.2.1 if the release is from the Reactor Building. ,
No credit is taken for containment sprays. SBGTS is {
assumed to be running if the total stack flow is less than 150000 cfm. The release duration is assumed to be seven hours.
If the release is determined to be from the Turbine Building a source term is calculated as outlined in 7.2.1.2.2 and the release duration.is assumed'to be one hour.
(2720P2) 73.0
.g , -
- i ,
QQ f; OYSTER CREEK RADIOLOGICAL CONTROLS Numbnr ;
-POLICY *AND PROCEDURE MANUAL 9300-ADM-4010.03 Title . . . Revision No. ,
Oyster Creek Emergency' Dose Calculation Manual 4 .
- 7.2.4.3 Ventilation '
i A graphic depiction.of the monitored release paths is available. The diagram is very simplified', showing vent paths, Reactor Building and Turbine Building fans, and stand-by gas.
'7.2.4.4 Field Monitoring Team Readings Time, location, whole body dose rate, and child thyroid' dose rate from field monitoring teams may be entered for display on the final output. No calculations are performed.
7.2.4.5 Utility Functions ,
7.2.4.5.1 Leak Rate Calculation A leak rate based on the-driving pressure-and size of the leak-can be calculated.
l Bernoulli's equation.
I P y + hydg + dv1 2=P + . h2 dg + dv 2 s is used, t l
where l_ P,1 P2 "' Pressure in state 1 and 2 I l (Psig) h,h2=
y height above reference plane (ft) d = density (lbm/ft3) g = gravitational constant (32.2 ft/s')
V,V2=
3 velocitios (ft/s)
(2720P2) 74.0
. . .=
hglg[ OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND-PROCEDURE MANUAL 9300-ADM-4010.03 Title Revision-No.
Oyster Creek Emergency Dose Calculation Manual 4 Assuming:
h g=h 2 , P 2 =0, and V y =0 then:
P1= dV 2
or the potential energy in the form'of.
pressure is squal to the kinetic energy of ,
.the moving fluid. Solving for the velocity of the fluid and multiplying by the leak area:
LR+A*(Py *144/d*2*32.2)b*60 where:
LR =
leak rate (cfm) 144 =
conversion factor (in2 /ft2) 32.2 =
conversion factor ( % )
60 =
conversion factor (s/ min) >
1 A = , leak area'(ft2) 1 The densities used in this equation are 2.23 lbm/ft for steam 46.4 lbm/ft for water 3
8.07E -2*(7hhh7)*(Pl+1 .7) lbm/ft for air where:
T = air temperature (*F)
An assumption is made in Eernoulli's equation that the fluid is incompressible.
Although this will lead to some error when used for steam or air, it will provide a good leak rate approximation. ,
(2720P2) 75.0
~L . -+-
3:
_ h Mf OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number-
'9300-ADH-4010.03 z es-Title Revision No.. "
Oyster Creek Emergency Dose Calculation Manual 4' Tha above calculation does not account for the change of state which will take place ,
when the approximately 520*F Water or~ steam' is released to atmospheric pressure. IF the .
operator.knows the enthalpy of the-fluid,<
the code will correct for change of state and give the ree- ..nq leak rate of both steam and water. To determine these,-first the quality is calculated:
X= (ghikf) where X = quality-h = enthalpy of fluid (Btu /lb) hf = saturated liquid enthalpy at 1 atmosphere (Btu /lb) <
hg. = saturated vapor enthalpy at 1 atmosphere (Btu /lb)
The water leak rate is then Lw =
d*LR*(1-X)*.Ol6747
-and the steam leak rate is s
Le = d*LR*X*26.799 where:
Lw =
water leak rate (cfm)
Le =
steam leak rate (cfm)
.016747= specific volume of water at 1 atmosphere (ft3/lbm) ,
26.799 = specific volume of steam at 1 atmosphere (ft3/lbm)
(2720P2) 76.0
@lgf ' OYSTER CREEKiRADIOLOGICAL CONTR07.,S Number POLICY AN
D. PROCEDURE
MANUAL 9300-ADM-4010.03 ,
' Title Revision No.
Oyster Creek Emergency Dose Calculation Manual 4 7.2.4.5.2 Core Damage Estimation
'The percentage of' fuel melt is estimated t
using the CHRRMS reading. Emdrgency Plan Procedure 9473-IMP-1300.33 Reference 7, ,
contains graphs which relate CHRRMS reading to percent noble gas released and percent e ,
. noble gas released to percent core melt.
Curve fitting to these graphs gives:
D = C
- CR wheret D = % core damage C = conversion factor ',
, 3.021E-4 if TAS < 1.0 hr 4.982E-4 if 1.0-< = TAS < 2.0 hr-6.749E-4-if 2.0 < = TAS < 4.0 hr 1.018E-3'if 4.0 < = TAS < 8.0 hr 1.676E-3 if 8.0 < = TAS < 24 hr 3.796E-3 if 24 < = TAS < 72 hr 7.604E-3 if TAS > = 72 hr TAS = Time After Shutdown (hr) i y CR = CHRRMS reading (R/hr) l l 7.2.4.5.3 Field Iodine Measurements The. Oyster Creek Field Monitoring Teams l~ (FMT's) use a RADECO air sampler with a silver zeolite cartridge and paper filter te draw air samples to determine child tyroid committed dose. The cartridge and filter are counted with an E-140 with a HP-270 (2720P2) 77.0
.s ,
g 7 OYSTER CREEK RADIOLOGICAL CONTROLS Numb 3r POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03-Title Revision No.
+ Oyster Creek Emergency Dose Calculation Manual' 4'.
probe.- FMT's report gross filter count rate, gross cartidge count rate, background count rate, sampler flow thte; 'and sample-time to the EAC or RAC, as appropriate.
Using these values gross airborne iodine concent' ration is calculated:
1 C=l(z-B)/.0039+(F-B)/.10l/(f*St*1000*2.22E6) j i
i where: '
C = airborne iodine concentration- <
(yci/cc)'
Z- = silver zeolite cartridge reading (epm) '
B = background reading (cpm)
F' = filter paper reading (cpm) l
.0039= counting efficiency for silver zeolite cartridge
.10' = counting efficiency for filter 1 5
paper
- =
f sample flow rate (liter / min)
St = sample time (min) 2.22E6= conversion factor (dpm/yC1) 1000 = conversion factor (cc/ liter) +
Child thyroid committed dose rate is then found by multiplying this concentration by l-a dose factor for the expected lodine 1
I (2720P2) 78.0 1
i
is '
-i 4'
..h gf OYSTER CREEK RADIOLOGICAL CONTROLS.
POLICY AND PROCEDURE MANUAL Numb r 9300-ADM-4010.03.
Title _ .
Revision No. 1 oyster Creek Emergency. Dose Calculation Manual '4 spectrum., At power this spectrum is O expected to be I-131' 11.9s-I-132 .Pu. S t :
I-133 z3.8%'
I-134 26.6%
I-135 21.04 l These values are first decayed for time-after shutdown, then renormalized. The dose factor is then:
5 "
i DF = I fl Dfi f i=1 .,
where: '
DF = dose factor for iodine spectrum .
{ mrem /hr)
MG1/Cc ,
Fi = decayed and renormalized fraction of isotope i 1
DFi = dose factor for isotope i (mgemfhr) see Reference 5.2.3.4 7.2.4.5.4 Unit Conversions A unit conversion function is included to facilitate calculations. The utility will l convert' units of length, area, volume, flow, speed, pressure, temperature, dose, equivalent dose, and activity between different measurement systems. In all-cases except temperature conversion, the entered value is multiplied by a conversion factor to obtain a value in the new units.
('2720P2 ) 79.0
1 o' ,
g gg' OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL, Numb 2r
-9300-ADM-4010.03 Title Revision No.'
Oyster Creek Emergency Dose Calculation Manual 4
. s I
Temperature conversions use the'following ]
relationships:
F=$C+32 ~ ~
R = F+459 K = C+273 where F = degrees Fahrenheit C = degrees Celsius j R = degrees Rankin
[
K = degrees Kelvin
!=
l < 7.2.4.'5.5 Semi-Infinite Cloud Approximation i
A semi-infinite cloud approximation can'be used to approximate total airborne
-concentration and total iodine MPC.- Total i
airborne concentration is calculated ass-l C = &*Ea y, where C = approximate airborne concentration (pci/ce) ;
Ea = average gamma energy (MeV) 1-l 9.OES=- numerical conversion factor l DR = gamma dose rate (mR/hr)
- Ea is determined as a function of time l
l-l after shutdown. Ea varies from .54 MeV at l
TAS = 0 to .772 at times greater than one
, hour.
l l MPC is calculated l
MPC = .188 * .00119
- C / 9.OE9 (2720P2) 80.0
7 .,
N NE' OYSTER CREEK RADIOLOGICAL CONTROLS- Numb;r 9300-ADM-4010.03
~ POLICY-AND PROCEDURE MANUAL-h' Title- Revision No.
Oyster Creek Emergency Dose Calculation Manual 4, where:
.118 = conversion between total iodine and DEI for this spectrum
.00119= fraction of release which4 is iodine 9.0E9 = 1 MPC for I-131 7.2.4.5.6 Calculator A calculator utility is available which uses Reverse Polish Notation (RPN) logic to perform addition, subtraction, .)
l multiplication, and division.
8.0 REFERENCES
8.1 Calculation 9340-89-005, Revision O.
-l l
8.2 . Specification OCIS-402180-003, Revision O. j
.Y 8.3 McKenna, T.J. and Glitler,.J.G., " Source Term Estimation During' Severe Nuclear Power Plant Accidents", Nuclear Plant Journal, .
s 1
November-December 1988, pp 83-85, 98. l 8.4- Calculation 9430-88-007,- Revision 0.
8.5- Calculation C-1302-661-5350-11. j l
8.6 Radiolocical Health Handbook, U.S. Department of Health, Education, .!
and Welfare, 1970.
8.7 Emergency Plan. Implementing Procedure, 9473-IMP-1300.33. j r
8.8 Slade, David H., Meteoroloov and Atomic Enerov,. United States Atomic ;
Energy Commission, July 1968. f l
8.9 0.C.N.G.S. Plant Operations Manual. !
(2720P2) 81.0
a, U@ M7 OYSTER CREEK RADIOLOGICAL CONTROLS.
POLICY AND PROCEDURE MANUAL Numb 3r 9300-ADM-4010.03 -
Title Revision'No.
Oyster Creek Emergency Dose Calculation Manual 4 8.10 -O.C.N.O.S. Updated Final Safety Analysis Report. .
8.11 U.S. NRC Reg. Guide 1.145.
8.12. U.S. NRC Reg. Guide 1.109.
8.13 Plume Rise, Briggs, G.A., (TID-25075), United States Atomic Energy >
commission, Office of Information Services, 1967, 1974.
f O
I 1
(2720P2) 82.0
9300-NPI-4010.03, Rev. 4 APPENDIX A
~
CLOUD GAMMA DOSE: THEORY For clouds with dimensions that are small compared to the range of the gamma radiation, a.
calculation of the gamma dose at a given point must take into account the radia' ion, received from various parts of the plume. The complexities of geometry, absorptione and buildup make complete solution difficult and require the use of specialintegrals.
In terms of the reference system given'in Fig.1, the equation for the gamma dose can be written:
0.1616
- a y 90 (9x /90 ) (Il+U)2 (1) 7 (x,y,0)
- g Y 'r where L a * ** 2 I+2 I=l " } eXP -(*~ -exP --
dr dt (2a) 4{Ti pel
- 0
- 0 2 ay , , 2 og L r and
} exP -(*~ I" +
I= # dr dt l
2 -exP (2b) .!
l- 4(Ti peg a n.9 , 2 og , 2 ag ,
The symbols are defined in Table 1. Eqs. (1), (2a) and (2b) above correspond to Eqs. (7.41),
(7.41a) and (7.41b) in Reference (8]. Values of 1 1 and I2 are determined from numerical s
integrations.
i s
El-1
e 9:
9300'ADM-4010.03, Rev..4 j
APPENDIX A FIGURE 1 i Coordinate System for Cloud Gamma-Dose Calculations t
(mI +r I-2 mr cos'()
RELEASE. CLOUO . VOLUME ELEMENT OF CLOUD,(n,y.I)
PolNT- . CENTER _ (Lt.0,h)
_ [2, r sin' $ d(r dr)-
( 0. 0. n)s u ;
e sin' + 1 o
l z .
l- m r s
- p I""O'0I "
(0,0,0)s :-
m8-( x,-Ot)a,y,2 + h8 y 4 Yi
'I RECEPTOR ( ui .yi .O )# ,
[
i i
l El-2
r -
ns '*
9300-ADM-4010.03, Rev.'4i c
6' TABLE 1 DEFINITION OF SYMBOLS j
,D(x,y,0) . Gamma-ray dose [ rads) as a function of downwind distance z and l
crosswind distance y .j y Total absorption coefficient for air (m~1). (pa= p + #s' "I 8 is#sthe
- scattering absorption coefficient) -
q p Energy absorption coefficient for air (m-l) _
a k (p-p3)/p,(dimensionless)
E Average gamma energy emitted at each disintegration (Mev/ dis) i Q- 0
- Initial source strength { curies)
Qx/Q 0 Fraction of original source material which was not removed by radioactive decay (dimensionless] .
1 ,' I Integrals used in the solution of the equations from gamma-ray dose 1 2 from a cloud (s/m) ii Average wind speed (m/s) m,r Distances used to describe the three-dimensional geometry for cloud gamma-dose calculations (m) (see Fig.1) jl og Standard deviation of plume width [m); ay = V oy g o t Time [s]
El-3
______________________--_1
u 9300-AtH-4010,03', Rev. 4
.o - - ,
APPENDIX A CLOUD GAMMA DOSE: APPLICATION OF THEORY Numerically evaluating the integrals 11 and I 2in Eq. (1) takes many hours of computer time.
Obviously, this time is not available during a radiological emergency. Therefore, these integrals need to be pre--computed. This section describes how this was done.
Eq. (1) can be rearranged as'follows:
Qo (Qx /Qo) 0.1616pp <
yD(x,y,0) " -
a 7(I + kI )12[
l The expression in braces contains not only the integrals 11 and 21, but also the factors y, p '
a E y, and k. We will call the expression in braces the gamma factor, and denote it by F:
7 -
yF s 0.1616 y#aE 7 (I l + kI2)- (3) k Eq. (1) can therefore be written as:
D= Qo (Qx /90) 4 F (la) 7 _
Gamma factors were computed and stored in arrays as a function of the following variables:
downwind distance, crosswind distance, height above ground, stability class and gamma
( ' energy group. A total of 381,024 gamma factors were computed:
1 (42 downwind) X (36 crosswind) X (6 heights) X (7 stability classes)
X (6 energy groups) = 381,024 Table 2 lists the downwind distances, crosswind distances, heights, stability classes, and energy groups.
El-4
~ - -
(
- e. # ,
'y 9300-ADM-4010.03, Rev. 4 APPEtOIX A TABLE 2 i
Variables for Array of Gamma Factors .
Downwind Stability Energy Index Distance Height Class Group -
(m) -
(m) (Mev) - .
1: -50 0 A 0.032
-2. 100- 30- B' 4 0.081 3 150 60 0 0.150 4- 200- 100 D- 0.250 5 250 150. E 0.530 6 300 300 F' 1.000 ,
7 350 G 8 400 9 500 10 600 11 700 i 12 800 13- 900 14 1000 15 1250 16 1500 17 1750 18 2000 19 2250 20- -2500 21 3000 22 3500 23 4000 24 4500 25 5000 .i 26 5500 27 6000 28 6500
- l. 29 '7000 l 30 7500 L 31 8000 L 32 9000 ;
10000 i 33 l 34 15000 '
35 20000 36 25000
, 37 30000 38 40000 l 39 50000 40 60000 41 70000 42 80000 El-5
t 9300-ADM-4010.03, Rev. 4 ;
3.-
-APPH OIX A
- Table 2 shows that the gamma factor is a function of both space and gamma energy. The dependence of the gamma factor on space is,given by its dependence on the downwind distance, crosswind distance, height and stability class. The stability class is a spatial variable because it-determines the width and height of the cloud, as given by yo and og ,
respectively. 1 l
- The gamma factor is also a function of the energy of the gamma rays, E . The gamma factor, y
7F, is a function of the gamma ray energy because is a function of energy (1) , and isa non-linear term in the integrals It and I 2, as seen in Eqs. (2a) and (2b). This non-linear dependence ofy F on E necessitates partitioning F by energy group.
y y A particular radionuclide may emit gamma rays with a broad range of energies -in some cases a range spanning as much as three orders of magnitude. A single value of E may not N y
accurately represent the contribution of these rays to the whole body dose. Instead of a single value of H y, the spectrum of gamma ray energies is better represented by several values of E y, especially in view of the non-linearity of F. Table 3 lists the six valuei of E that were y y used to represent the full range of gamma energies. Values of , a, and k for each Ey are also shown.
Although radionuclides emit gamma rays across a broad spectrum of energies, the distribution of this energy varies markedly with radionuclide. Some radionuclides may emit many low energy gamma rays and only a few high energy rays. Others may emit a lot of medium energy rays and only a few high and low energy rays. Infinite combinations are possible, and the distribution of the intensity of this energy uniquely characterizes each radionuclide.
El-6 7
y; -
9300-ADM-4010.03,1 Rev.'4-f APPENDIX A TABLE 3 :
The Dependence of p, ,, and k on Ey P Vg k E.7 . . ,
(Mev) (m-I) (m~1) -
0.032 4.000E-02 1.500E-02 1.667E+00 :
0.081 2.200E-02 3.200E-03 5.875E+00 !
1,734E-02 l 0.150 3.268E-03 4.307E+00 0.250 1.455E-02 3.623E-03 '3.014E+00 0 530' 1.093E-02 3.836E-03 1.850E+00 1.000 8.203E-03 3.609E-03 1.273E+00 L
p The intensity of the gamma rays for each of the six energy levels is called the abundance. The i'
abundance is denoted by a. Thus the total gamma dose for a radionuclideis the sum of the
' the gamma factors for each energy group weighted by the abundance for each energy group:
D= Qo (Qx /90) ,7F'j ag (1b)-
,y g ,
s=1 The only other term in Eq. (Ib) which needs to be computed is the ratio Q x /Q0, which is given by:
i-Q
= exp[-A(6t + )) (4)
, where 6t = holdup time of radionuclide A = decay constant for radionuclide El-7 l
,