ML20086B513

Rev 5 to Radiological Controls Policy & Procedure Manual 9300-ADM-4010.03, Oyster Creek Emergency Dose Calculation Manual

ML20086B513
Person / Time
Site:	Oyster Creek
Issue date:	07/16/1991
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20086B511	List: ML20086B509 ML20086B513
References
9300-ADM-4010.0, NUDOCS 9111200210
Download: ML20086B513 (93)

Text

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O Mf l OYSTER CREEK RADIOLOGICAL CONTROLS Number l POLICY AND PPCCEDURE MANUAL 9300-ADM-4010 03 Title.

Revision No.

Oyster Creek Emergency Dose Calculation Manual 5 Applicability / Scope Responr(ble office All GPUN Employees Bad Con 4300 This document is within QA Plan scope __L_.ye s No Effective Date Safety Reviews required _.2L yes _ No gjyg7gg) g7p7g Prior Revision . 4 . incorporated the This Revision 5 incorporates the following Temporary Changes: following "?lemporary Changes:

N/A N /.L List _of Effective Paces Lam Fevision Pace Reyision Paqe Revision Pace Eevision 1.0 5 20.0 5 39.0 5 58.0 E 2.0 5 21.0 5 40.0 5 59.0 5 3.0 4 22,0 5. 41.0 5 60.0 5 4.0 5 23.0 5 42,0 5 61.0 5 5.0 5 24.0 5- 43.0 5 62.0 5 6.0 4 25.0 5 44,0 5 63.0 a 7.0 4 26.0 5 45.0 5 64.0 5

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Oyster Creek Emergency Dose Calculation Manual 5 List of Effegt ive Pac 691 (continued)

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Oyster Creek Fmergerwy Cose Cal culation Manual ,

Ovater Qeek Erary ncy Doce calculaMon Manual f rDem section Table of Contenia Eang 1.0 Furpose.. ... ....... . . . ............................. .......... 7 2.0 Applicability / Scope................................ ..... .... .... 7 3.0 Definitions.. ..... ... .................... 4 .. .... .. .. .. .8 4.0 Policy............................................................. 18 5.0 Prerequisites.. .... ... . . ................................... . .19 6.0 Pr? cautions . ... ... . . .... ..... .. ... .... .. . .19 7.0 Procedure. ... ....... . .... ...... . . . , .19 7.1 Operation... ......... ........... ....... . ... . . ... .13 7.1.1 Computer Operat ion. . .............. .. . . . 19 7.1.2 Overview. . . ................ . .... .. .... ,,21 7.1.3 Sou rce Te ro Calculat ions . . . . . . . . . . . . ..... . . . ..,23 7.1.3.1 i

Monitored............. ..... ..... , . 23 7.1.3.1.1 Stack........ .... ..... . . . 23 7.1.3.1.2 Turbine Du11 ding.. .. . . . .25 i

7.1.3,2 Unmonitored Releases.... .. ..... . . ... 26 1

7.1.3.2.1 Field Monitoring Team Feading.. 26 7.1.3.2.2 Isocondenser Accident.... .. .27 7.1.3.2.3 Augmented Offgas Accident. .. 27 7.1.3.3 contingency Calculations. ... .... .. . .23

7.1.3.3.1 Drywel1.................. .. . 28 t

7.1.3.3.2 Reactor Building...... ..... . 29 I

l 7.1.3.3.3 Turbine Bailding......... . ... 30 )

l 7.1.3.3.4 Fuel Handlino... . .. .. 31 1

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OYSTER CREEK RADIOLOGICAL CONTROLS POIICY AND PROCEDUDE MANU7.I.

Number 93OO-ADM-4010.03 Title Revision No.

Oystar Creek Emergency Octio Calculation Manual 5 Ovster Croek _ E:mroe'ir.y Dose cakulatign_Jiyual III]CM)

L3J2 1 e of Content s Section })aae 7.1.4 Moteorology.......................................... 31 7.1.5 Other Functions............. ........................ 33 7.1.5.1 PCS Direct ConnectLon. .................. 33 >

7-1.5.2 Automatic Dose Projection............ ..... 33 7.1.5.3 Ventilation.. ....... . ..... ....... 34 7.1.5.3.1 Releano Path Analysis. ... .. 34 4

7.1.5.4 Field Monitoring Team Readings.. .... ..... 34 7.1.5.5 Utility Functions...... ............ .... 35 7.1.5.5.1 Leak Rate Calculat. ion. .35 1

7.1.5.5.2 Core Daenge Enti.mution. .. .... 36 7.1.5.5.3 i iold Iodine Measurement. . .... 36 4

'.l.5.5.4 Unit Conversiono.............. .37 s

7.1. 5. 5. 5 Semi-Infinite Cloud Approx..... 39 7.1.5.5.6 Calculator........ ........... 39 7.1.6 Belease Duration........ ............................ 40 7.1.7 Final Output................................ ....... 40 7.2 TheOrf.. ................................................... 43 7.2.1 Sourco Term.............. ........................... 43 7.2.1.1 Epectrum Determination..................... 43

~1 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

I k u ear OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number 9300-ADM-4010.03 Title Revision No.

Oyster Creek Emergency Dose Calculaticn Manual 5 01syer Cre Q Freccenev Dore Calglation Mgnual ( ER.Q31 l

Table of citr.teplyt l Seetten PASM 7.2.1.3.2 Iso Condenser Accident......... 54 7.2.1.3.3 Augmented Offgaa 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 Turba.ne Building.... . . . .61 7.2.1.4.4 Fuel Handling....... . .., . 62

, 7.2,2 Meteorology... . .......................... .. .. ... 63 7.2.2.1 Stability Class................... ....... .64 7.2.2.2 Windspeed...... .................... .. .. .65 7.2.2.3 Wind Direction................... ,,,.... . 65 7.2.3 Dose Projections.................................. .. 66 7.2.3.1 Release lloight............ ............... .66 7.2.3.2 Building Effect.............. ............. 66 7.2.3.3 Finite Model........................... ... 67 7.2.3.4 Semi-I nf in it e Mode l . . . . . . . . . . . . . . . . . . . .... 69 7.2.3.5 Maximum Calculation.................... ... 70 7.2.4 Other Function 6..................... ...... ...... .. 71 g#:"

7.2.4.1 PCS Direct Connection................... .. 71 1 7.2.4.2 Automatic Dose Projection........ ... ..... 73 7.2.4.3 Ventilation.. ........................... . 74 7.2.4.3.1 Release Path Analysis. . 74 ,3 f

7.2.4.4 Field Monitoring Team Readings... . . . 74 (2720P) 5.0

r d)] U ear OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number 93OO-ADM-4010.02 Title Revision No.

O f t:Er Creek Emergency Dona Calculation Manual 4 Ovster Cteek Er'erconev Dose CalculattnrL & nual (FDCM)

Table of Contento 1

section Pace 7.2.4.5 Utility Functioris........... ...... ....... 74 7.2.4.5.1 Leak Rate Calculation........ . 74 7.2.4.5.2 Core Damage Eatimation. . . . . . . . 77 7.2.4.5.3 Field Iodi.ne Moasurement....... 77 ,

7.2.4.5.4 Unit Conversions..... ...... .. 79 7.2.4.5.5 Semi-Infinite Cload Apprcx. . 80 7.2.4.5.6 Calculator............ ..... .. 81 80 References................. . ... ... ....... .. , ........ . . .81 Apper. dix A. Cloud Gamma Dor *. ........................ ...... ... ..A-1 l

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1 U ear OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL 4 Number 9300-ADM-4010.03 i

Title Revisicn No.

Oyster Cree- E: .ergency Occa Calcula*1cn Manual 4 1.0 PURPOSE The purpose of this manual is to provide a document that describes the assumptions and methodology used in the current Oyster Creek Radiological Assessment Computer Program (RACP). This includes calculating projected offsite doses from releaueo of radioactive material to the environment in accident conditions upon implementation of the Emergency Plan. As such, i

this document describes methods of projecting offsite doses during l

emergencies or for training purposes. Indt ations of these releases may resuit from Radiation Monitoring System (RMS) readings, onsite er of f site cample results, or contingency ca'.culation if RMS and sample resulta are not available. These dose projections are performed utilizing an IBM compatible computer and the current version of the RACP. The Radiological Assessment Coordinator, (RAC), and Environmental Assessment el Coordinator (EAC) are responsiblo for implementing the doue projection process.

2.0 APPL!CABILITl/ SCOPE i

1 The Emergency Dose calculation Manual, EDCM, is applicable to all qualified Emergency Plan personnel involved in the projection of offsite Js doses during an emergency. This manual providos the methods used in performance of dose projections during emergency situations where radioactive material has been or is predicted to be released to the i

environment.

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Oyster Cree' Imergency Doce Calculatien Manual 4 L

3.0 LEFINITIO2S 3.i B1GD!NG WAKE EFFECTS Effects on the dispersion of an atmospheric release occurring at, near, or below the top of a building (or any structure). Air flow 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 onsito concentrattens dramatically, while slightly reducing concentrations downwind for a short distance. Far downuind concentrations are y affected very little by building wake. Stack releases are high enough above the building so that building wake does not affect the plume significantly, i

3.2 CONTINGENCY CALCULAl!_02 A source term calculation perforced 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 - OCF A parameter calculated by the methods and models of internal dosimetry, which indicates the committed dose equivalent (to the whole body or an organ) per unit activity inhaled or ingested.

This parameter is epocific to the isotope and the doao pathway.

Dose conversion factors are commonly tabulated in units of mR/hr per curie inhaled or ingested or mR/hr per Ci/m in air or water.

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Oyster Creek Emergency Dose Calculation Manual 4 3.4 Opq5E EOUIVAl qr I-ill - del DOSE CQUIVALENT I-131 shall be that concentration of I-131 microcurios per gram which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid doue conversion facters used for this calculation shall be those listed in Table E-7 of Regulatory Guide 1.109, " Calculation of Annual Deses to Man from Routine Releases of Reactor Effluences for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix I".

3.5 ELEVATED RELEASE An airborne effluent plume which is well above any building wake

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effects so as to be essentially unantrained. Reg. Guide 1.145 cefines an elevated release point au being higher than two and one-half times the height of adjacent colid structures. The source of the plume may be elevated either by virtue of the physical height of the U' source above the ground elevation and buildingu cr by a ombination 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 61 stance to the ground concentration maxirum compared to ground releases. All main stack l release _ at Oyster Creek are elevated releases.

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l 4 3,6 ggflgi:1?gy AC;!on LFvEL - FAL y Predetermined eendations 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, requiro implementation of the Emergency Plan.

3.7 EMERGENCY DIPECTOR - Ep

'l Designated onsite individual having the responsibility and authority to implement the Emergency Plan, and who will conrdinate efforts to limit consequeneco of, and bring under control, the emergency.

3.B FMEPGENCY DOF? CALCULATION MANUAL - EDCM i-A controlled document describing the content, calculational methods, and use of the Radiological Assessment Computer 4[

Program (RACP).

3.9- EMERGENCY OPEPAR ONS FACILITY - EOF The Emergency Operations Facility serves as the primary location for managcment of the Corporation *s ov'erall emergoney response, rhis facility is equipped for and staffed by the Emergency Sapport U

organization to coordinate emergency response with off-site support agencies and to acsess the environmental impact of the emergency.

The EOF participates in accident assecsment and transmits appropriate data and recommended protectLve actions to Federal, State, and Local Agencies.

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3.10 [MERGENCY RESPONSE EnCILf?IES - EPf lW The primary locations for management of the Corporation *a overall emergency response. These faci!.ities are equipped for and staffed by the Emergency Support and Response Organizations to coordinate emergency response with offolto support agencies and assessment of the environmental impact of the emergency. The ERF participate in accident assessmont and transmit appropriate data and recommended protective actiona to Federal, State and Local agenciec.

3.1; ESERGENCY' PLANNING rnNr - EPZ A :one defined by a radial distance from the plant in which emeraency planning considerations are given. There are two EP2s.

The first in the Plume Exposure Pathway EP'4 and is located at approximately ten miles in radius around the site. In thia EP7.

emergency planning consideration la given in order o ensure that prompt and effective actions can be taken to protect the public and property in ;he event of an accident. The second EP* La called the Ingestion Exposurn Pathway EPZ and is located approximately 50 miles in radius around the site. Emergency planning considerations are given for the ingestien exposure pathway in this EPZ.

3.12 ENVIPONMENTAL ASSESSMENT COMMAND CENTEP ftACC1 The ETCC is located along side the EOF to provide a work area for the EACC staff. Under the direction cf the EAC, environmental data are collected and dose projections performed in support of the EOF,

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Oyster Creek EPercency Ocse Calculation Manual l 4 3.13 ENV!PONMFNTAL ASSESSMENT COOFDINAIOR O (EAC)

A rember of the emergency support organization, the EAC assumes responsibility for dose projections and offsite field monitoring Y

teams from the RA" when the EACC is activated. The EAC provides environmental data, calculations, and advice to the Group Leader R&EC.

3.14 E3IT VELOCITY AND PLUME RISE Atmospheric dispersion and ground ccncentrations are in part dependent on release height. Higher release heights will cause lower maximum concentrations at grcund level and will cause that maximum to oerur further downwind than would a lower release tf 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 much 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 m[1TF PLUME M$ DEL 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 dimensions of the plume, the radiation build-up factor, and the air attenuation of the gamma rays coming f rom the cloud. This model can estimate the dose to a receptor who is not submerged in the (2720P) 12.0

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radioactivo cloud. It is particularly useful in evaluatina donos from an elovated plume or when the recepto lo near t he uf fluent sc'u r ce .

< r 3.16 9AtL$pJbN PIMIC EOUATIpH An equation which takes input parainoters of plume height, a 'id lateral and vertical plume opread, and explicitly calculatos the l

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utraight lino Gaussian Plume Disporaion. The Gausolan Plume equation actually averagen enort term variationo t o produen a mean offective plumo, ao short term measurements of the piumu may not 1e duplicated by the Gaussian Plume Modol. /'

3.17 (a' QL@p,_IJTELFILEMI l

An airborne effloint plume which contacts the grciund onsent ially at the point of release eithes from a aourca actually located at the gro'ind clovation or from a sourco above ehn ground elevation which han signi.ficant butiding wake offects to causo the pluma to be _

entrain (d in the wake and driven to the ground elevation. Ground i level releases are trusted ditforently than elevated releases in t tia t the X/Q calculation r%nalts in significantly higher concentrations at the ground elevation near the releamo point.

Grour.d level X/Q valuon becomo ossentially the same as elevated for larger distance downwind. All releanos at Oyoter creek, other than main stack, are ground level releason.

3.18 LOW POPUL C Ott ZOffE - LPt As defined in 10CFR100.3, *The area immediately surrounding the exclusion area which contains residente, the total number and

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doneity of which are 'tuch that there ic a reasonable probability

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that appropriate protectivo M*acuros could be taken in their behalf in the event of a serious accident."

3.19 EERIfi'IIVE ASUOfLQUlDnLt{U - PAQ Projected radioloalcal deco or dono cormnitment valuon to individuals of the general population and to emorgency workern that warrant protectivo a : tion bef ore or af ter a release of radioact.ve re a t e r i a l . Protectivo actions would be warranted provided tne reduction 11 individual doso expected to be achinved 1;y carrying out thu protectivo action to not o f f r30 t by excensive riska te individual catety in taking the protective action. The PAG at CCNGS is based on the Environmental Protection Agency low-level guidelinna of 1000 mR whole body or 5000 mR child thyroid. The PAG l

dr.es not incrude the dono that hau unavoidably occurred prior to the ovacuation.

3.20 EP.SIEC'TIVLAgl'QN PFCOM11ENDAHON - PAH Thoso actions recommended to the stato of New Jerooy to bo taken

, during or after an emergorcy situation that minimize er eliminato

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the rauiological hazart' to the health and nafety of tho general public, t

l 3,21 EAD1hTIQF MONITORgMLETEM - PMS N l

The oystem designed to detect, indicate, annunciate, and record the radiation level of effluent releaseu and radiation levola at i

i selected locations inside the plant to verify compliance with applicablo code of Federal Regulations (CFR) limitn. The RMS connicts of the following subsystems: area monitoring, atmospneric monitoring, and liquid monitoring.

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EN1LoiO2 LCM _MEfMl'EUI_C00EDIRhTOR - P AC l i

A tmmber of the initial response team of the emotgency renpanse otganization. Specific rerponsibilities apoigned to thu RAC include dirocting of f sito and onsito survey teams. The RAC to

=11eved of offatto radiological monitoring tesmo' renecnoibilitfen by the Environmental Ausetsment Coordinator (FAC). Tho P.AC performa deso projections, supplien cource term est imaten to the EAC and e..ourac a imely, accurato dono project ion ant il t h t. EAC y

aucunos recionulbility f or dono protection. The RAC'c matn tosponsibility is advioing the ED of any radiological concoruu.

Initially the croup Badiological controls supervisor aanumon u:e rolo of the RAC until rolleved by the Initial tw o pe n c e rmorgen~y Organi:ation RAC.

3.23 Ergt1Q.LegICAL E!!Of f.'EJJMtin SUPPQJiT i Individuale anoigned to aoniot the RAC in per f orming dono calculacions, cource term calculationn, and overall aaseurment and control et radiological hazards.

3.24 [SOEMS 1. P AG E Mfl._11 The RAGEMS I and Rt.',2MS II Systema monitor gaueoun effluent releases ' rom the main stack and the turbino building utack, respectively. They monitor pc.ruiculates, todinos, and neble gases.

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PFACTOR CO@/J{T SY11TJM - fRE N This system contains the nocessary piping and components to provide sufficient water flow to cool the reactor. This ayutem proviles for the transfer of energy from the reactor coro to the (2720N 15.0

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Revision ;Jo.

Ofstur Creek Rurger.cy Deco Calculation Manual 4 4 . _ .

turbino in the form t>f a pressurized steam, acts as a moderator for therms) fission, and providos a boundary to noparate flusion products from the atmosphere.

3.26 PJM]\1t!!P ATIOtt Release duration refers to the time interval during which

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radienuclides are released from the nueloar facility. Releanes may be monitored, unmonitorod, actual, or projected. The time interval uced to cotimate a releasu of unkncwn duration shou 1J roilect best ottimaten of the plant technical staff. in the abr.once of 7;t he r information, coven hours in used as the expected relenco durucion from the reactor building and one hour 10 usea its the expect ed releico duration from toe turbine building.

3.27 FILEAEE PAIE This term refers to the rato at whl e reaionucli. des are taleased to the environmont. !!ormally, it will be exprenaod in uC:e esc. _

3.28 SffM!iFI!!ITE PLl'MF MODEL Q

Deso assessment model which is based on the assumptirn that the dimensions of an effluent plumo are large compared to the distance that gamma rays can travel in air. The ground is considered to be an infinitely large flat plate and the receptor is located at. the origin of a hemispherical cloud of infinito radiuc. The radioactive cloud to limited to the space above the ground plane.

The semi-infinite plume model in limited to immnesion dono calculations.

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POLICY AND PRocrDURE MANUAL 9300-ADM-4010.03 Title Oyuter Creek En ergoney 71ose Calculatic o Manual lMovisionNo.

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l 3.29 ft9yECE TETUi The activity reluase rate, or concentration of an actua. release or potential release. 'the common units for the source term are C1, Ci/coc, and C1/ce, or multiplea thereof (e.g., uC1).

3.30 GIA!31LITY CLhgj A measure of the amount of mixing occurring between the plume and the atmosphere around the plutte. Conditions which create good mixing are unstable and conditionn which create poor mixing are etable. Pasquill stability clancification 10 a breakdown of the relative atmospheric stability into eight groups, denoted an A

> through G, from mest unstable to most stable. In the Pasquill stability clacsification system, stability in related to the change t

in temperature with height and the standard deviation of wind direction measurements. The more negative the change in temperature with increasing height, the more unstable the 4

atmosphere is. Standard deviation of wind direction (og) in not used in stability clano determination ir. the RACP.

3.31 IIc!!NICAL SUPPORT CJJIllLLIJ_C1 Emergency respcnse facility utilized by engineering personnel to provide engineering support for emergency operations. This le the location of the ED and tho RAC.

3.32 IfBRAIN FAQ10R - TF The terrain height above plant grade at distances from the release point. The terrain f actor accot.nts for increases in local ground

, level concentraticnt, due to terrain effects. The terrain factor is the terrain height. in meters at a given distance for each sector.

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()l QQ g OYSTER CREEK RADIOLOGICAL Cot 4TROLS Number POLICY AtlD PROCEDURE MANUAL 0300-ADM-4010.03 Title Revision Ho, Oyster Creek Imorgency Dose calculatjon Manual

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3.33 ;QQ_ - f " CH I o ve r 0" 1 The dispersion facter o' 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 in used to determine environmental atmospheric concentrations by multiplying the source term, represented by Q (in units of uC1/sec or CL/sec). Thus, the plume dispercion, X/0 (sec/ cubic meter) multiplied by the source term, Q (uci/coc) vaelds an environmental concentration, X (uci/m3). X/Q is a function of many parametera including wind speed, stability class, release point height, building size, and release velocity.

4.0 toLICr 1

This procedure is to serve as documentation for une of the oyster i

Creek Radiological Assessment Computer Program (RACP). Any change to the program shall first 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 chall consist of representatives from Rad Engineering, a

Emergency Planning, and Environmental Controls.

InTI8 Non-oubstantive changes to the computer program which have been voted on by the source term committee and documented

./

s in the minutes of the committee meeting may be implemented k3 without a revision to this procedure.

4.1 Three (3) non-controlled copies of this procedure will be sent to the Licensing Manager, oyster Creek.

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I" L ll U ea OYSTER CREEK RADIOLOGICAL CO!!TROLS l'OLICY AND PROCEDUBE MANUAL Number 9300-ADM-4010.03 l

Title Revision do.

Oyutor Creek Emergency Dabe Calculat wn Manual 5

..+. . - -

5.0 LEEEOU131 TEE 5.1 The following aro prerequisiten for projecting donou using the methods in the EDCH, and current version of the RACP.

5.1.1 Tho Emergency Plan is being implemented.

5.1.2 The RAC and/or EACC station are manned and functional.

6.0 PPICAVHQFji - Nono 7.0 NOCFQ12K This rection cf the EDCM is divided into two noctions, 7.1 operation and 7,2 Theory.

7.1 Operation This section will describe the operation of the RAC computer codo including which calculation to uso in different circumstances and what I

inputs are required for each calculation. The computer operator in urgod to road sections 7.1.1 and 7.1.2 before beginning any calculations.

7.1.1 Computer Operation

.The RAC computer codo is run on camputorn in the Emergency Control Centor (ECC), Tochttical Support Contor (TSC), and the Emergency Operations facility (EOF). The computer, printer, and auxiliary equipment are all turned on and off by a manter power switch located near the computer. In the control room this ,

switch is under tho dinplay monitor. In the TSC tho switch is mounted on the wall behind the computer. At the EOP the maetor switch is under the cabinet where the computer is kept. The RAC codo will automatically be loaded in the control room and EOF l when the competer is turned on. Type RA C " and hit the carriage return to load the program in the TSC.

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p= a m C k U ea OYSTER CREEK RADIOLOGICAL CO!JTROLS PottCY A!JD PROCEDURE MAfJUAL

!Jumtse r 93OO-ADM-4010.03 Title j kev i s ien fio.

Oyster Creek Emotgoney Dopo Calcul.ntion Manual '

$2hL3 PCE Auto Ventilation FMT Readingn Ut ilitiou j l

4 l

1 Offsite Doce Projuetion Program for Oyster Creek fluelear l' owe r S t a t i o n Revised February 28, 1941 l~

F1 Update All F2 Courco Torm F3 Mot Data F4 update Dose F9 Quit The initial screen will be displayed ( Fig'..t o 1) at the beginning of the program. The F1, F2, F3, F4, and F9 listed at the bottom of the scroon 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

" Hot F.ey s " . In this case the " Hot Foys" ato P, A, V, F, and [

U pressed in combination with the Alt key. For example, to access the AUTO function, hold down the Alt key and press 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

k)I U ear i i

"YS7 24 c'tfrx ^^ 2 'oo t c^' c t" 'S """ 'a r i

POLICY A!JD PROCEDURE MAfJUAL 9300-ADM-40lO.03 Ti t l es iht v i s i on flo .

Oyuter Cruek LW igenc JMe Calculatien .Unual S keys and "llot Keys

• which are active at the current position in the program are displayed on tho top and bottom lines. When in the menus, choices are made by either directly pressing the letter which is hi-11ted in red or moving the hi-lite bar using the up and down arrow keys to 1

the desired function, then pressing the Enter key. The ESC key will always back the user out of a function or calculatiin in the case of an error.

E'ull screen editing is used for all user input. Impat fields are hi-11ted in blue. If numerical values are being entered, the minimum and maximum values which may t9

' entered are displayed on either the top line er the bottom limo 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, presning the F10 key signifies the computer to accept the values displayed on the screen.

7.1.2 Overview After the code has been loadod, the operator should establish a connection with the Plant computer System f

(PCS). See section 7.1.S.1. This in done usina Alt-P.

1 Once the connection has been established, PCS data will automatically be entored into the computer, including i

t. i RAGEMS data. If the connection to the PCS la not available, the RAC computer will attempt to connect to the RA3 EMS computer. If neither connection is completed, the (2720Pi 21.0

I U ear OYSTER CREEK RADIOLOGICAL CO!1TROLS POLICY AND PROCEDUllE MANUAL

!J umi>o r 9300-ADM-4010.03 Yitle Rov i s ion !Jo.

Oyster Creek Emer'Jency Nno Calculativn Manual 5

__~

user will receive a warning mossago. l l The RACEMS system provides real tirno noble gas of fluont monitoring and releano point flow ratos. Stack high range and low range monitor readings, flow rato, T.B. high and low I range moniter readings, and T.D. vont flow rates are available from the PCS. Place conditions such as Poactor ,_

Level, Power, Drywoll ltydrogon, Containment Spray riow, Stand-by Can Demand, CliPRMS monitor and colected ARMS are alou available from the PCs. Any data points which are not good are asuigned a value of -1.0. Dono projections are brokun down int o three noctionat acurce term, meteorology, and dose calculation. tieteor ology chould automat.1cally be updated through contact with the met tower cottputer. Dopo calculatior.s are done with no input by the operator. The source term portion in where most of the inputs and operator deciolona are required.

When "F1 Updato All" or "F2 Source Torm" is pressed the source term menu will appear. Source term calculations fall int o three categoriost Monitored, Unmonitorod, and Contingency. Monitored releases uan thu RAGEMS monitors on the atack and turbino building vonta to develop a nource term for a release ao it occurs, j Unmonitored calculations are for releano pointo which are not monitored by RACEMS. An it.ocondannor failure and an l[

ADG accident rio the two specific accidento currently 1

1 (2720P) l 22.0

(4- kJ U ea YSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number 9300-ADM-4010.03 Title Devision No.

Oyster Creek Emergency Dose Calculation Manual 5 available under this option. Also, a downwind Field Team reading may be used to dovulop 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 it" calculation. Contingency calculations provide generic methods to develop a source term for "what if" situations. Calculations are available for events which may happen in the drywell, reactor building, turbine building and the refuel floor. The drywoll calculation includen drywsil venting, a worst case total reloaue of ' '

I drywell activity, and drywell leakage into the reactor building.

At several places in the code the user is prompted for the most recent DEI. This value can be obtained from chemistry or is posted on the white board just inside the control room door.

7.1.3 Sourco Term Calculations 7.1.3.1 Monitored 7.1.3.1.1 Stack The stack source term calculation develops a source term based on the RAGEMS I monitored readings or PASS sample. If a RAGEMS I PASS nample is available, the sample will bw used along with the stack flow rate to calculato tha source term.

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() QQ gf OYSTER CHEEK RAOIOLOGICAL CONTROL.S POLICY AND PROCEDURE MANUAL Number 9300-ADM-4010.03

_ - 4 -

Title j Revisien No.

Oyster Creek Emergency Doco Calculation Manual. l I

4 If no RACEMS ! PASS sample is available, the RAGEMS I monitoro aro used. Three values may be enteredt low range in eps, high range in ampa, and high rango in uCi/ce. The PCS I

will enter the high range valve in uCi/cc and the low range value in eps. If the ampo reading is availabla they should also be manually entered to develop a meaningful ocurco term.

The pr,yr an contains logic to chooso

( between the valuco if more than one is entered. The s*.ack flow rate will be untered by the PCS if available. If the atack flow rate is not available, entoring "0 to this prompt will causo a fan flow table which prompts the user for fan status to appear.

SDGTS filtration encJid only be used if Stand-by Gas is running and the reactor building fans aro isolated.

Standby Gas status will be entered by the PCS. The code can take credit for the iodine washout which would occur if the airborno activity is in the I

(2720P) 24.0 1

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i r kJ } U ear o'rsTrn enEEx n^o2o'oo2 CAL co"TPo'S N""'er POLICY AND PROCEDURE MANUAL N00;ADM

• 4 0l O : 0 3 )

Title Feviulen Ho, Oyst er Creek Emergency Oore Calculat tun Manual 5

= ---

..-a- _ , ,

containment ni the containment uprays are on. Choone these two options only if the release la from the drywell.

Again, these two cption.s will be

• i indicated by the PCS. l l

Finally, the computer will ask for the core condition. If the usar known the current coro condition it can bo entered directly. Otherwiue, the user choosos the "flot Soro" option and is prompted for plant conditiens to determine the core condition. The required plant paramete.s will be displayed sla the PCS connection, if applicablu. Tho user may use the displayed values or enter different values.

7.1.3.1.2 Turbine Building Because the turbine building has releaan pointe monitored by both the RAGEMS I and RAGEMS II systems, both are used for this calculation. If i

RAGEMS PASS wamples are available, they are veed along with the stack and turbine building vents flow rates to (2720P) 25.0

I' dJl U ear oY3 ca c"Etx ^^o 2o'oo 2 c^' co Tao's POLICY A!JD PROCEDURE MAtiUAL

'i" mt r 9300-ADM-4010.03

_k _ . _ . . _ _ _ _ __-_

Title j Huvision fJo.

Oyuter Creek Emerger.cy Doao Calculatten Manual '

develop the pourco term. 80 aware that the olevated and ground levoi wind directions may be different. In i

tho absence of PASS samples, the RAGEMS monitors are used to develop l

the source term. If on-line, the PCS j 1

will enter the utack high rango and I low rango readingu, the stack flow 1 l

rate, the turhi.o building high and low range readingo, and the turbino buildine vont readingn and tirc after i

shutdown. If the unor han the high range reading in amps, it should be manually or.terod. The computer will pick which of *.ho monitor readings to uso.

If no RAGEMS PA3s sample results have been entored, the computer will prompt the user for the core condition. If the core condition is known, it nhould be entered directly, Otherwise, the codo teill proinpt the operation for plant conditions frce whici.'it will choose the core condition.

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dll " U ear OYS1 ER CREEK RADIOLOGICAI. CO!JTROLS POLICY A!4D PROCEDURE mat 4UAL tiumber 9300-ADM-4010.03

_ a __ _

Title Revinion tJo.

Dyst er Creek Dnergency Done Calculat . cn Manua l  !

._ 4 1__.-

7.1.3.2 Unmonitored Feleases 7.1.3.2.1 Mold Honitoring Team Reading A downwind field monitoring team reading may be used to develop a saures term for a ground levul release. The reading must be a plated g(ndaw reading taken at the plumo centerline. The diAtance to the site must be known in feet, Care should be taken when using this calculation with dono raton taken close to the plant.

small errors in distance to the plant can lead to large erroru in projected dooo rates. This calculation may be used to perf orm a close project ion baoud on a grcund levol particulato release. Tho wholo body doou rates calculated will be accurate but the child thyroid dosed should be ignored.

' . l . 3 . .> . 2 Isocondenser Accident Thu isocondencer accident will generato a source term based on the core condition or a roactor coolant cample, and the reactor pressure.

This calculation assumen an entiro (2720P) 27.0

/~ h) QQ gf CYSTER CREEK liADIOLOGICAL CO!4TROLS l!Jumber POLICY AtJD PROCEDURE MAf1UAL 9300-ADM-4010.03 Title 5viston ti e ,

oyster Creek Emergency Dese calculatu n Manual 5 tubo bundle ruptures and thuo ia a worrt came ostimate only, 7.1.3.2.3 Augmented effgas Accident U If a leak should develop in thu Augmented Offgau (ADG) oystem this calculation can be used to develop a worst caso cource torm. The coolant DEI is the caly paramoter needed. The calculation arsumos the ent ire ADG flow is being released to tho a t nio s ph e re .

I 7.1.3.3 contingency Calculations 7.1.3.3.1 Drywell The drywell contingency calculation tu uced to develop a source term based on activity containod in the drywoll.

The calculation determinos a sourco $

term f or containn.ent venting, drywell leakage, or drywell failure.

It a drywell air samplo is available, it in uuod to determine the activity.

Otherwise, the CHRRMS monitor roam,ng la used along with time after shutdown to calculate the drywell airborne activity.

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1

k)l U ear OYSTER CREEK RADIOLOGIC %L CONTROLS POLICY AND PROCEDURE HANUAL Number 9300-ADH-4010.03

. - - - - . 4 -

Title Revision Uc, Oyster Creek Fmergency Dono Caiculation Manual 5

- +

Af ter tho drywell activity in calculated, the user in prompted for the release path. If contalnment venting is choson, thu vent line-up spocified by the Emergency Operating Proceduren is assumed. A second I option allows the uno to calculato a worst caso release of all activity in the drywell.

NOTE Thio calculation in intended to answer the question of the PAR Logic Diagram which asks if there is sufficient activity in the dryvell to exceed the PACS, if roloaued. A reloano duration of ono hour must be assumed for this calculation If neither of the above optiono aro l

chocen, the user is asked if the containment is intact. This means that all penetrations and coalo are cloaod and venting in not anticipated.

Answering yes to this prompt leads to a calculation based on normal drywell loakage. Drywell prassure is needed.

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C (I QQ Qf OYST1.R CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 f - _.__. __.

4-Title  ; Povimien No.

Oyster Creek E::ergency 00ae Calculstion Manual { 5 i

- _ _ _ _ _ _ ~ _ _

Finally, if none of the abova threo options are chopon the urer is anked to enter a drywell leak rate. If the leak rate is not known, entering 0 to to this protnpt will activate the leak rato calculation utility (7.1.5.5.1). The two drywell leak rate acontrios require the statuo of SBCTS and the stack flow r a r. o to be known. Both will be ontored I

by the PCS.

7.1.3.3.2 Poactor Building The reactor building contingency generater a pource term bemed on a known volume of roactor building.

Reactor coolant concentration to baned on either a reactor coolant sample er a core condition. Concentration based on coro condition is the worst case for that core condition. The unor is prompted for leak rate, how long the leak will last, stack flow, and the status of SDGTS. If the RAGEMS connection has been mado, the RAGEMS i

, computer will enter the atack flow t

rate.

(2720P) 30.0 t

l l _ _

()j QQ Qf OYSTER CREEK RADIOLOGICAL CONTROLS l Number POLICf AND PROCEDUFF MANUAL l 93CO-ADM-3010.03 l

Title Reviaion No.

OyFter Creek Enerqency Doso Calculatten Manual S ,

1 7.1.3.3.3 Turbino Lutiding The turbine building contingency generates a source term based on a known volume of reactor coolant being i

released to the turbine building.  !

Reactor ccolant concentration iu based on either a reactor coolant sample or coro ecndition.

Concentration based on coro conditicn j

ic worst case for that core condition.

The user is prompted for leak rate, how long the leak will las:, atack flow rate, and if the turbine building vento have been isolated. If the ,snts are not isolated, the code asks for the '

total vont flow rate. Thio is the flow from all three turbine building vents.

The PCS computer will enter the stack I flow rate and the turb;no building vent flow rato.

7.1.3.3.4 Fuel llandling The fuol handling contingency assumes the FSAR analynis releano to determine a source term if spent fuoi it damaged. As with all contingency (2720P) 31.0

d U ear orsten catex x^nrotocrCAL CouTnots POLICY AND PROCEDURE MANUAL numoer 9300-ADM-4:,10.03

_______j__._. _ . . . _ _ -

Oyst< Crook : tergency Dose C.alculaticn N nual  ! 5 i

calculations, this calculation gives a worst case source term. Required inputs are time after shutdown, stack flow rate, and SUGTS status. The PCS g{

will enter the stack flow rate.

7.1.4 M1:teorology The RAC computer will call the mot tower computer to obtain the current motocrological condit ions. The meteorological input screen, (Figure 2), displayn raet data, choosou which parameters will be used, and allows the user to edit meteorological data.

Initially the usor to allowed to edit only the parameters which are needed to perform a dono projection. for exatiple, if an elevated nource term exists, only the elevatea data may be editad. If rio source term exista, then no data may be editc.

After the required data have been edited, the user in prompted to determine if he wishes to edit thn data which is l not needed. Answering "Y" to this prompt allows the user to edit the other meteorological parameters. When the i

meteorological input screen is printed, the sectoro affected

?*

by both a ground level release and an elevated release are i printed at the bottom. This information la on the printout l

l only, not the video display.

l (2720P) 32.0

1 1

I OO M  ! OYSTER CREEK RADIOLOGICAL CONTROLS Number l POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title l Revision Na. I Oyster Creek Emergency Dono calculatica Manual 5 FIGUPE 2  !

Ilmut 11:32:35 l Date: 02/28/199: j i

A Sensor D Sensor USE Units 33 Ft Wind Speed 7.6 7.9 Mph 150 Ft Wind Speed 9.9 MISSING Mph 380 Ft Wind Speed 11.6 11.7 12 Mph 33 Ft Wind Directio.1 239.0 239.0 Degrees 150 Ft Wind Direction 244.0 MISSING Degrees 380 Ft Wind Direction 239.0 239.0 239 Degrees 150 Ft - 33 Ft D.e l t a T -1.1 MISSING Degroos F  !

380 Ft - 33 Ft Delta T -3.2 -3.2 -3.2 Degrees F Elevated Sector Affected ENE Ground Sector Affected ENE 7.1.5 Other Functions 7.1.5.1 PCS Dircct connection Pressing the Alt-P " Hot Key" brings up the PCS display. The first time the key is pressed the computer will dial and connect to the Plant C mputer System. The user will be prompted for his location. Enter this using *le F10 key. To leave the PCS display press the , key. The PCS line will stay connected as long as the operator (2720P) 33.0

1 1

I k U $Qf OYSTF.R CREEK RADIOLOGICAL CONTROLS thambe r POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title Cycter Creek Emetgency Dooo ca l cu l a t. i o n M a n u a '.

l Rovialon No.

i

.- . __ .i coes not tell t.he computer to break the connection by prossing Alt-il while in the PCS display.

Subsequent returns to the PCS display will show ,

the most recent PCS data. The display will be automatically updated every 15 seconds as the PCS relays new data. Data is also updated even if the PCS dioplay is not on the screen.

As long as the PCS connection lo activo, the computer will automatically enter PCS data pointo any time the user la prompted for RAGEMS 4

information included in the PCS data set. Had PCS e data is ansigned a value of -1.0. The PCS choice on the "llot Key" line in hi-lited when the PCS connection is active to allow the unor to know it a status from anywhere in the program. If the

~

computer does not connect with the PCS, it will i

attempt to connect to the RAGEMS computer. If a connection la completed with the RAGEMS computer, stack high rango and flow, and turbine stack high rango, low range, and vent flows will be available. In this case, "RAGEMS" will be reverse hi-lited on the top line.

)

7.1.5.2 Automatic Dose Projection The Alt-A " Hot Key" will perform a doao projection with no input from the operator providing the PCS ' )

(2720P) 34.0

l kJ U ear ovstra entox n^nto'oo2c^L cor:to's e'OLICY AND PROCEDURE MANUAL

' dumber 9300-ADM-40lO.03 Title hevision ilo.

cyster creek Emergency Dose calculation Manual 5 i

or RACEMS connecticn is activo. If the Alt-A "llot Koy" la pressed without a computer connection, the l5 operator will receive a warning.

The automatic dove projection uses data from the POS or RAGEMS computer to determino release path, coro damage, source term, and releare duration. -

Mot data one is obtained by calling the met

,, tower. When an automatic doce projection 5. 0 performed, the Auto "flot Key" will tie hi-lit ed.

7.1. 5. 3 Ventilation A simplified ve.itilation diagram can be dinplayed on the acreen by pressing the Alt-V "llo t Key". The diagram shows the release patha for monitored releases at ayatesr Creek. ESC returns the user to the main program.

7.1.5.3.1 Releaso Path Analysis '

Pressing the F1 key while on the i

ventilation screen will perfocm a relwase path analyolo. If the RAC ,

computur is connected to the PCS, tho analysis may be done with no input i

from the operator. Otherwise, the operator will be prompted for varioua ,

RMS parameters.

12720P) 35.0

L ll U ear orsita catex R^o2otootc^' ct'"T"o'S POLICY AND PROCEDURE MANUAL Numbar .

9300-ADM-4010.03 Title Revision No.

Oyster creak Emergency Cose calcularton Manu.sl E The output of this analynia is both to I

the screen and the printer.

I Recommendations are inuladed on ways to verify the analysis. ,

gyy .

This 2.nalyste is neant to be used *

• as at aid only. It is in no way *

• mear t to replace nound engineering *

• judgement. +

7.1.5.4 Field Monitorio ; Tet.m Road 1.nga Alt ~F activatos the Field Monitoring Team (FMT) reading window where dec.a f r om t .' . => FMT*o are

(

manually entered. An data are entered, the four most recent data points are retained by the computer for display on the final output screen. _

Four input fields are required: time, FMT location, whole body dose rate, and child thyroid doce rato. Une the up and down arrow keys and the enter key to move between input fields. The left and right arrow keyu and the backspace key are unod to edit within a field. TlO entern the data as displayed on the screen.

If an error is discovered after data has been en:ered, enter " ERROR

• in the time input field.

This will allow the user to delete one of the

(

existing FMT readings. By positior.ing the cursor (2720P) 300

. ; s . . ., e W ..

s

~

Nuder orstra entex a^o2o'oarex' courno's POLICY AND PPOCEDURE MANUAL au d <

9300-ADM-4010.03 Title Revisicn No.

Oys er Creek Emergency Dose Calculation Manual 5 at the reading to be deleted using the up and down+ '

arrow keys, then pressing Flo, the reading is

. ,e n, .4y,7 3 deleted from the computer memory. ^

., jj%

'The Erc-key'raturns the user to the main pedia T N W "

s an o _. y - 4 W9mmTfr$Mf*ru ms .

.....<,a ..r u. m +<a wM ,-

,a 8 a

ud [.

7.1.5.5:,,.Utt313y Functione=;, 3 4

,, g, , Qj- Q

, ;r; L Nl Win $%SifWOD' ora lU ,3, h

't-

'l Alt-Usactivateatthejutilities

.n  ?

[ _'f ' Q : $ Q Q .;f Q:;.

(Six'monu. fun onsy N h F&,

.] .) -

-are available which are explainoc below.

. t

'N01> [L

• N. .,o.,

.O VNp*,g mi'y.j ,n*9.L 7.1.5.5.1 Leak Rato Calculation > /-

p3 ),-

The leak rato calculation usos Bernouill'c Equation to calculate an approximate leak rate for air, steam, k or water based on the leak size in c

square feet and the driving pressure.

If the esiculation is for air, the air

~

tercquerature is also needed. The result in in efm. Change of stato resulting-from either steam or water at elevated temperature and pressure being released to atmospheric pressure may be calculated if the enthalpy of=

the fluid in Dtu/lb le known. The : . qg ; '

. e

,, 2 code will then calculate both '

steamIyi d,yM't . ,

,4 I y

_ ~ .

"V $dp ;

yd;%f3fiy'N[

~

~

h ;;i.b, ,M n i ,N M ,

gand' water!1eakrate'sincfJ .l 3q w h IUj k [ ,'y h / h

,/e., -a wnp' a[ n.3.1 k m w* k5 g h +[ h , m{ Y [ h h h ( h N d $ J'w~v ~.p. . m[ u M v N "'l j w.

W-g ,37.0

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l gg g OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADH-4010.03 Title Revision No.

Oyster Creek Emergency Dose calculation Manual 5 7.1.5.5.2 Core Damage Estlanation A rough core damage estimation is done 7 using the CHRRMS reading and time after shutdown. The result is in

. m 3,~

.m. ., .

. o %. . =m C j T' . g ; a ,,percent. fuel-melt. This calculation._.#,, f.&

7, _2  : > , :[nv ;$a&"[.,Q.,e,p x py i

i <,;

. ,j., , .wp c w r. s f k(d @ Ndh[ ' 4 ' fNd!.$niyb'.useduniil'aic'o' .[ $

e

, r

.f '

d a*'r @ $W 'e-

damage calculation using EPIP-337?

n@lyyQd J M%..,( .,A[MG '~,4 can g, ,

~

be performed.

7.1.5.5.3 Field Iodine Measurement This function will convert gross field data to a committed child thyroid done rato. The minianum data required ares gross silver zoolite cartridge reading in epm, gross filter reading in epm, background reading in erm,

, sample flow rato in liters / min, sample time in minutes, and timo after shutdown in hours. The FMT designation and location should also be entered.. ,

,1 The. input data are entered as in all n.

,, . . _ _. 4 N. gu ;p g, .,3 ,; full screen editing functions as

,_3 4-*'.,.*.,-

+

s 2 . Q j. s14t:@ L s a s

.q.igQ 3&[=,g,jy [ ..[ *

, J ..

r r

}fi"l f ; g j; N. M,,,X x +;Q;oy k h#qh<f/@ described in i7.1.1. gThe res

~

. ~ r: A wk/Wici;;; gnu, 2[, $' i Ijki @hW@dhcS connai@tted(child thyroid-dos e (rate t

is k .96i~ ' :j',d' -'

1;pr;;g ( 1} g h h

,7 }fs%dA l

^jehpc emper.hourdofexposure;g.{

gkqfff .f 4[ Mf ' s Thec (f fff ig.

dhN /_hkm h5 1,M '

yp k_kiI}h.hNb, NNhgk. 4 hlM Yh t m ,7> pON,,,I (2720P) 'W ? -

r m> 3e %r yy

~

v w_. 3 -

I'~ L U BM 1*! STER CREEK ItADIOLOGICAL COliTROLS Number POLICY AND PROCEDURE MANUAL 9300-hDM-4010.03 Title Revision No.

Oyster Crook Emergency Dose calculation Manual 5 t itue, location, and comitted child thyroid dose rate are e.utt.matically i traanferred to the riuldtHonitoring* '

Team (FMT), data entry function ' r (7.i'.b.4)'for Jicplay'if,the.jperator. , ,

,i,,j l

a . .t \

,. ac, cep,tu o the data , f rom ' w.ithi.nithofFMTG

-W -

-)

j, *=b ,. j, c ' , r t.p }

data entry function. *' +

t 7.1.5.5.4 Unit conversions A function to available which will convert units of nicacuremont from one measuring nyatom to another.

( conversions are availablo for units of Longth, Area, Voluma, Flow Spood, Pressure, Temperature, Dono, Equivalent Done, and Activity.

On choosing the convorolon function, another menu appears to allow the operator to chooso'which of the abovo measurements will be converted. The-next menu allows the unor to choooo tho units which the value is currently,.

s.

o -

-in,' or put.another way, tho; units to' i, ',

(

y W, m . . . - > - . .

s -

f

{

4 xbetconverted o.,

from.7The o

final menu- '

,9

,I. i -

y ?

.? fi l ' . . .,.  ?

o, - x , -'l ? choose,n!the,unito -!tof be, convorted'.<- , to.w 5 -s-i s . ,

y , ,< .= ,

=a. , '

, j

• S y, ,y .-

g_ ,

s +

3 V, eb; L 'O Mbl:OUN/f-d o 1 ~ Cp<

4/ v!'s JW

-t

,.3-

.., , a -, s.

c; .

o,: 1 %",

' g .s.

u; T Q Oncejthese

- j r j. gu r '

,,+ ~-

','i' t.. +

~..

' f ;;. e f

w;.q i , " 7]-4 2 ']-pph'np;m/c:hoicesxhavebeenimadoD 4

p

. , . 4 4 p, 1 w}, .

og;b q,t g , ' !'

3- g 's ; -- [

3 .'b.  ; .

s . .

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o kl l U ea OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDORE MANUAL Nurrber 9300-ADM-4010.03 c ,

( '

Titla Revision No.

Oyster Creek Emergency Dose Calculation Manual 5 enter the value to be e,'nverted using the F10 key. The result in the value in the new units.

For examplo, to convert 10 feet to rneters , the conversion function 19 "

m l 4

. gg'_ so c, , $

s

& , ..t . 4 , chosen from the utilities menu. 'Ons <

= l,' --

L .;

the second nenu, units of longth are -  !

1 chosen. Choose feet on the third i i

menu, and metere on the fourth. Thea enter 10 into the input field with the F10 key and the recult is 3.05 meters.

( The ESC key is used to backntep through the rnenus.

7.1.5.5.5 Semi-Infinite Cloud Approximation Approximate total airborne t-concentration in uCi/cc and MPC for iodine are calculated based on a gamma reading, approximate cloud radius, and the time after shutdown. The gamma reading MUST be due entirely to airborno activity, not direct shine.

7.1.5.5.6 Calculator i 1

j 4

.!;, .,'#,g .

1

.A niroplejcalculator which will addi [Q 1 3

~< ' . > . ,

,'  : 'i .s

..4 } ' },.

,(!

, ,, . , , . . . . . , . ;-~.,. .

a M:' 7.$' .y1. -i,*

e ..,4isubtractR

, .. p ,

multiply,land divide.is;the .,' sag

. . . y _ . , .

~

. . , , ,J,; .,ib h h ? , ', .? ^;'h ; i '

'4  ;;jE ? l l(h !'N JU .;,,, : ;e c y Y Y. ', s$ L f: ". '\f . .

I. \ '

t

? pi.)., d;j l

,s Q( + &, 1 -

,J

,u,,

finalifunctionjonithe utilities, menu.+ /,.?, " ;M J-

.h +

l i ,. .w ~.'

r (;4@g:~ w 4W s

• > '*c' " *

. *4

[

f^ $ ;f ' i.f 9, I f j f }; f i hk I?

I}h J

,.y ,>4l .

t r!. ; , , 7 ,( ~_}

-(2720P) .'50.0

_ _ _ .~ ___ . _ . _ _

=

U ear OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE HANUAL Number 9300-ADM-4010.03 Title Revision No.

Oyster Creek Emergency Dose Calculation Manual 5 Tne calculatnr uses " Reverse Polish ,

Notation * (RP4' logic. An example is a che best way to explain.

To add 3.5 and 7.6 in the calculator

.- function, enter 3.5 using the P10

=

key. Next enter 7.6 with F10 key.

Finally enter "+" with the F10 key.

s The resuA*. is 11.1. To then divido this number by 2, enter 2, then "/".

The result is 5.55. The symbols for

'E the math functions are listed below.

( + addition

- subtract

• multiplication

/ e ision i 7.1.6 Release f, a' 1 Dependir. c., che type of release, tha computer may generate a default release duration. In the absence of better un inf ormation, this value may 've used f or the releasa 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.

EE-If no default release duration exists in the comnuter, the operator must provide an estimate for the release duration.

(2720P) 41.0

. _ _ _ ___ . _ . . _ _ _ _ _ - . - - . - . - - - - - - - - - - - - - - - - - - - - " - ~ ^ " - - ^ - - - - -

I'- LJ l Udear orSTen carex ^^rto'ootc^L co"Tno'S " umber POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title Revision No.

Oyster Creek Emergency P se calculation Manuel 5 7.1.7 Final Ouput The final output gives total done, dose rate, and time to the PAG for both whole body and child thyroid exposures for the site boundary, 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 rato, and time to PAG for the maxim .

The center section of the display shows the most recently entered meteorological data. Below that are the four most recent field monitoring team readings. The maximums and wind directions are hi-lited in yellow to distinguish the most

( important information.

. A hard copy is made of this display (Figure 3) which also I

inu,'.udes the Emergency Classification which is appropriate for the projected doses. The logic used to calculated the clansification is:

saergency Maximum Dose (mrem) within 10 miles classification Whole Body Thyroid None O <= Dose < 10 0 <= Dose < 50 Alert 10 <= Dose < 50 50 <= Dose < 250 Site Area Emergency 50 <= Dose <1000 250 <= Dose <S000 General Emergency 1000 <= Dose 5000 <= Dose l

The classification is determined based on the most limiting of i

the maximum whole body doce and maximum child thyroid doso.

.- ina lly , all inputs and assumptions used in obtaining the dose l projection are listed. These may be used af ter the fact to l

reconstruct how the do.e projection was done.

(2720P) 42.0 l

kJ } U ear OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number 9300-ADM-4010.03 Title Revision No.

Oyster Creek Emergency Dose Calculatica Manual 5 ELE RE 3 PCS Auto Ventilatinn FMT read!ngs Ucilities tr- --TIME 11:32 - -

m WHOLE BODY I CHILD THYROID l Dis. Dose Dose Rate Hours Dis. Chi /Q Dose Dose Rate Hours Miles mrem mrem /Hr to PAG Miles Sec/M'3 mrem mRom/Hr to PAG

.j SB 6.16E+00 8.80E-01 >99 SB 6.05E-10 BKG BKG >99 2.0 3.15E+00 4.51E-01 >99 2.0 8.94E-07 5.78E-01 8.26E-02 >99 5.0 7.54E-01 1.08E-01 >99 5.0 2.10E-07 1.3SE-01 1.93E-02 >99 i 10.0 2.67E-01 3.02E-02 >99 10.0 6.25E-08 3.99E-02 6.70E-03 >99 l Max. Max. '

Dose Dose 0.6 7.77E+00 1.11E+00 >99 1.0 1.62E-06 1.05E+00 1.50E-01 s99 '

MET DATA l Ground Wind Speed 7.6 mph Elevaced Wind Speed 11.6 mph lGround GroundWind Dir (from) Elevated Wind Dir (from) 239 degrees 239 degrees y

! Stability Class C Elevated Stability Class C h

( FIELD READINGS -h j Time Location WB Dose Rate CT Dose Rate  ?

) mrem /'.1r mrem /hr mRom/ hr mrem /hr l

( mrem /hr mrem /hr 4

{ mrem /hr mrem /h1 F1 Update All F2 Source Term F3 Met Data F4 Update Doce F9 Quit EMERGENCY CLASSIFICATION NO CLASSIFICATION based on done projections ASSUMPTIONS / INPUTS USED Time = 11:32 Date = 2/28/1991 Stuck release calculation Stack low ranga reading = 10000 cps Stack high range reading = 1.000E-10 Amps Stack high range reading = 4.000E-01 uCi/cc '

Stack flow rate = 140000 cfm Time after shutdown = 2.00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Containment spray not considered Clad damage spectrum chosen

(.03 noble gases, .02 lodines V/ partition factor of 1000)

SBGT operating helease duration = 7.00 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> Assumed gross elevated release rates:

1.61E+06 uCi/s Noble Gas, 1.81E+02 uCi/s Iodine Assumed gross ground release rates:

0.00E+00 uCi/s Noble Gas, 0.00E+0C UCi/s Iodine (2720P) 43,g

f ()j g g{ OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUA1 93OO-ADM-4010.03 Title Revision No.

Oyster Creek E.aergency Done Calculation Manual 5 7.2 Theory 7.2.1 Sourc7 Term The Sourco Term pot Lion of the Oyster Croek RACp is used to generate the quantity and radionuclide composition of the radioactive mat erial released (or available for raicane) to the environment. R31 eases are divided into three categories monitored, unmonitored, sud contingoney.

Monitored releauce are from the two release points monitored s

by the RAGEMS system. Unmonitored rr.ieases are pctential release points which are not included in the RAGEMS syntem.

Contingency source terms attempt to generate a ocurce term A

for the "what if" cases. The ocurce term module calculates release ratoa by isotope in uC1/s.

m 7.2.1.1 Spectrum Determination Except in cases where an actual RAGEMS or coolant sample is available, a precalculated spectrum must be ascumed. The assumed spectrum takes two different forms depending on the type of calculation being performed. If the source term is being determined for a monitored release point, three spectra irom Ref. 1 are used. These spectra represent assumed isotopic fractions for the 14 isotopes assumed to be present in an effluent stream.

I (272CP) 44.0

l I

(f kJ l U ear OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number 9300-ADM-4010.03 Title Revision No.

Oyster Creek Emergency Doso Calculation Manual 5

_._4 These isotopen are:

Kr85 I131 Kr85m I132 Kr87 1133 Kr88 I134 Kr133 I135 Xe131m I135 . .-

Xo133 Xe133m Xel35 Xc138

'f

( Alternately, for unmonitored releason and contingency calculations, expected isotopte concentrations based on either the above spectrums, e.g., isocondenser release or .

historical plant data, e.g. Augmented off Gao (AOG) release, are used. The clad damage spectrum for theco cases assumes 100s of the full power clad inventory is releaned to the reactor coolant. Fuel molt assumes 100% core inventory of the 14 isotopos in released to the reactor g coolant.

If the computer operator known the core condition, he may directly choose the appropriato spectrum.

l If not, he is prompted by the code for plant (2720P) 45.0

I'~ kJ } U ea OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANt!AL Number 9300-ADM-4010.03 Title Revision No.

Oyster Creek Ettergency Doae calculation Manual L parameters to determine tho appropriate spectrum.

Criteria for choosing spectra are Fuel Malt Drywell hydrogen 20.51 CHRRMS >30,000 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 /> or greater Clad Damage CHRRMS >1,000 and <30,000 R/hr Rx level $ 30" TAF for less than 1 hr.

Rx lovel < 0" TAF Anticipated transient without scram (ATWS)

( Control rod drop Fuel handling accident No Damage All other cases 7.2.1.2 Monitored Two release points are monitored by the RAGEMS system. The main stack is monitored by RAGEMS I, and the Turbine Building vents by RAGEMS II. Both aystems 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, aeo reference 2.

7.2.1.2.1 Stack

( If a stack RAGEMS isotopic sample is available, the individual inotopic (2720P) 46.0

l (t" k i l U ear OYSTER CREEK RADIOLOGICAL CONTROLS Mumber POLICY AND PROCEDURF HAHUAL 9300-ADM-4010.03 Title Revision No.

Oyster Creek Emergency Dcoe Calculat-ion Manual 5 i

_ _ . _ _ _ \

concent rations are multiplied by the stack fAow rate to develop a ocurce term. The stack flow rate is either available from the RAGEMS computer or calculated using fan status and rated flows.

In the absence of a stack RAGEMS sample, the RAGEMS monitors are used along with precalculated spectrums and the atack flow rate. RAGEMS information is either input directly

{

from the RAGEMS computer as discucsed in Section 7.2.4.1 or input manually by the computer operator.

Pointo available from the RACEMS systems and normal background levels where applicable, are:

Stack Low Range <10 cps Stack High Range 1.0 E-13 Amps Stack High Range .00646 uCi/cc l3 Stack Flow Rate (cfm)

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)

(2720P) 47.0

T k U ear OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL Number 9300-ADM-4010.00 Title Revision No.

Oyster Creek Emergency Dose Calculation Manual 5 Three different inputa from the RAGEMS I system are accepted by the computer. These are:

Low range in cps from panels 1R and 10F High range in amps from panel IR High range in uCi/cc from the RAGEMS computer Gross effluent noble gas concentr ation is then calculated as:

Cn = Ls/4.IlES (1)

If Cn > 0 or 5 5 this v11ue is used.

If Cn 5 0 or C n >.5 and either of

[

the high range readouts are on scale (above .01 uC1/cc) then:

If the RAGEMS computer stack hi-range is on scale:

n =H us C (2)

Otherwise if Hus is not available Cn

• N a/4.06E-lO (3)

Where Cn = total effluent noble gas concentration (uci/cc)

La = RAGEMS I low range monitor reactivity (eps)

H us = RAGEMS I computer hi-range reading (uci/cc)

Ha = High range reading (amps)

2720P) 18.0

a kl U ea OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE KANUAL Number 9300-ADM-4010.03 Title. Revision No.

Oyster Creek Emergency Dose Calculation Manual 5 4.115ES = low range conversion factor ces uCi/cc 4.06E-10 = high range conversion factor Amng_

uCi/cc After the appropriate spectrum to chosen as described in 7.2.1.1, the spectrum is decayed for time after shutdown. If the Standby Gas Treatment System (SBCTS) is operating, the isotopic fraction ror the lodines are ; v m r .- . af a factor of 10 (90s

( efficient). The iodine fractions are further reduced by a factor of 10 if the release is from the Drywell and containment sprays are operating to take credit for iodine washout (Ref 3). The decayed, filtered, and scrubbed isotopic fractions are then renormalized to 1.0 to give a prediction of the isotopic spectrum at the time of release.

Isotopic source term is then:

CL = CN *El (4)

In l

(2 /20P) 49,o

[4- t2 1 Nuclear orsTra casex a^ototocrcut cournot.s POLICY AND PROCEDURE MANUAL nemeer 9300-ADH+4010.03

.--- ,.. _ .~,

-k- .-_.;

Title evin;on no, Oyster Creek Emergency Doso Calculaticn Manuat 5 whore:

Cy = gross noble gas sourc6 term Ci = concentration of isotopo i (uci/cc)

FL = release traction or isotope i t

9 }

In = E FL = sum of ncble ore frActionc .

i=1 D ia 1 to 9 for esole gae isotopen i = 10 te 14 for iodino isotopes Because the RACEMS sampling system contains iodine sad particulato filters, the RAGEMS monitora detect I

only gross noble gao source term.

Equation four calculates individual noblo gas source terms by multiplying gross noble gas source term by the assumed isotopic roloaso fractiono.

The lodine isotoped are not measured by the RAGEMS system. Since only a noble gas gross concentration is calculated, an expected iodine to noble gas ratio is used. This calculated as:

Ring = E, (5)

+

'ng I

(2720P) 50.0

[T ()j y ggf OYSTER CREEK RADIOLOGICAL CONTROLS I Number POLICY Arid PROCEDURE MANUAL 9300-ADM-4010.03 Title Revision No.

Oyster Creek Emergency Dose Calculation Manual 5 Where Ring = iodine to noblo gas ratio 14 .

Et = E F1 = sum of iodine fractions i=10 Ihe gross iodine concentration would then be

, Cy =C N

• Ring (6)

Where Cy = total iodine effluent concentration (uct/cc)

The isotopic iodino concentrations are:

Ci ~C 1

• LL (7, E

I or Ci =C y *E =

11 (8)

[

' 7 I E N I which reduces to equation (4)

Isotopic source term is calculated as:

Si = Ci

• FR

• 472 (9) where FR = stack flow rate (cfm) 472 = conversion factor ec/s cfm si = release rate of isotope i p,C1 s

7.2.1.2.2 Turbine Building The turbine building has two release points. The condenser bay exhausts to the rain stack. The TB operating floor, feed pump room, and luhe oil bay exhaust (2720P) 51.0

k UC ear orSTeit carex R^ntotocIcAL coNTito's Number POLICY AND PaoCEDUltE MANUAL 9300-ADM-4010.03 Title lluv i c i on No .

Oyster Crook Emergancy D030 Calculatton Manual ';

through vents which are monitored by the RAGEMS system. Tho isctopic ocurco to. 1 for the portion of the release which goes to the main stack is calculated using the aere m9thod and con?taats outlined in 7.2.1.2.1 with the exception that no SBGTS filtering or containment spray wanhout exists.

Similar to the atack (7.2.1.2.1), if a Turbine Building RAGEMS sample in avaLlable, source term is determined using the isotopic concentrations and the total Turbino Building vont flow rato.

Otherwiue the RAGEMS II monitors are used to develop a source term.

The RAGEMS Il nystem providen the following points which are available via the RAGEMS computer.

Turbine Building low rango (cpm) Turbino Building high range (pcl/cc) Feed Pump Room vent duct flow rato (cfm) (fp vent)

I (2720P2) 52.0

k O M OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY i.ND PROJEDURE MANUAL 9300-ADM-4010.03 Title Reviolon th.

Oyster Creek Emergency Dose Calculation Manual 5 Operating F'loor vent duct ( Til stack) flow rate (cfm) (Op vent)

Lube 011 Day vent duct flow rate (cfm)

(Lb vont) cross offluent noble gas concentrations is calculated ae C (10) 3 = L T/5.032E6 If C g >0 or $ 5 this valve in used.

If Cg <0 or C3 >.5 and the RAGEMS II high range monitor is or, scale (above 0.01 pCi/cc) then C g = liut (11) where:

Cp = total effluent noble gas concentratic, gpi CC L =-

RAGEMS II low range monitor 7

(cpm) liu t a RAGEMS II high range monitor (yC1/cc) 5.032E6 = low rango conversion factor (cpm /pC1/ce).

Total flow is the sum of the three vont flows FR = Pp vent + Op vent + Lb vent or a default value of 47,000 cfm is used.

Once the gross noble gaa ocurce term and f flow rate have been calculated, the (2720P2) 53.0

e b U M OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 93OO-ADM-4010.03

n. 1' Title Revicion No.

Oyster Creek Emergency Done 2*1culation Manual $

isotopic release rates are calculated 4 4

using equationa (4) and (9) e.f 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 codo. The most general 10 through the use of a downwind gamma reading to levelop a scurce term. Accident-specific cource term 74n be genetatet for an inocondenner failure and an AOG lino treak. 'I e calculations are overly conservative because of t'ao nature of an unmonitored release and chould no treated as auch.

7.1.1.3.1 Field Monitoring Team Reading This calculation uses a downwind centerline gamma reading and the timo after shutdown to develop an ic' topic ,

source term. The calculation assumes a clad damage spectrum since thic is unod in the majority of the severo FSAR accident analycos.

The spectrum is decayed for timo after shutdown, then renormalized to 1.0. Next, an assumed gross release rate of 1 pC1/cc and flow rate of 1000 cfm are used to perform a dono projection at the downwind distance where the gamma dose rate was taken. Thio spectrum 10:

Sia = 1.0

• Fi

• 1000

• 472 (2720P2) 54.0

k UC $M OYSTER CREEK RADIOLOGICAL CONTROLS Humber POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title Reviaion tio.

Oyster Creek Emergency Dose calculation Manual 5 d_ ___

where:

Sia = assumed isotopic source term (pC1/s) 1.0 = assumed gross release concentration (pci/cc)

Fi =

isotopic fraction of isotope i 1000 =

assumed flow rate (cfm) 472 =

conversion factor (cc/a/cfm)

Uning the resulting calculated dose rate, the source term is then calculated an:

Si =

Sia

• DRc/DRm where Si a isotopic cource term (pCi/c)

DRc =

calculated dose rato using assumed isotopic acurce term DRm =

measured dose rate 7.2.1.3.2 Isocondenser Accident At Oyster Creek two isolation condensers are used as part of the Emergency Core cooling System. These isocondensera are shell and tube heat exchangern with steam from the reactor flowing through tuhea, giving up energy to water on the shell olde, condensing, and returning to the reactor. As the shell side water warms, it eventually begins to boil and releases steam to the atmosphere. In the event of (2720P2) 55.0

U0 N[ OYSTER CF. .K .aDIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-40lO.03 Title Revision No.

Oyster creek Emergency Dose calculation Manual 5 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. Because it is not practical to determine the number of tubos which are leaking, this calculation assumes an entire tube bundle to have ruptured.

Coolant leak rate is calculated:

LRc = 165000 *

(Pr/2.5) 1/ *

.016/60 I

where:

LRc =

coolant leak rate (cfm) 165000= rated flow rate through tube bundle at 2.5 lb pressura drop (lb/hr)

Pr a reactor pressure (PSIA) 2.5 a pressure for rated flow (PSIA) 0.16 = upecific volume of water 3

(ft /lb) 60 = minutes per hour The coolant concentration is obtained either from a reactor coolant sample if one is available or precalculated spectra as described in 7.1.1.1. If the precalculated no. damage spectrum is used, which repranents the normal coolant (2720P2) 56.0 l

UC M[ OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title Revision No.

Oyster Creek Emergency Dose Calculation Manual 5 concentrations, it is adjusted to current conditions by ratioing the actual DEI to that assumed for the spectrum.

The resulting coolant isotopic concentrations are then multiplied by the calculated leak rate to give an isotopic source term in pCi/s.

7.2.1.3.3 Augmented Offgas Accident The Augmented Offgas (AOG) system is used to hold up and filter the effluent from the air ejectors before it is released via the stack to the atmosphere. This calculation assumes a normal AOG isotopic spectrum as developed in Reference 4.

The release spectrum can bo 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 ADG flow rate of 122 cfm is used.

7.2.1.4 Contingency Calculations l contingency calculations attempt to develop a source term for the "what if" cases before a release actually begins. Four contingency calculations are available.

l I

(2720P2) 57.0

1 l

l l

l

[u. O M[ OYSTER CREEK RAOIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 93OO-ADM-4010.03 Title -

Re*cinion No.

Oyster Creek Emergoney Doso Calculation Manual 5 Because these are contingency calculations and assumptions must be mado, it must be stressed that the calculations are vorot case for a given accident.

7.2.1.4.1 Drywoll The drywell contingency calculation is used to develop a source term for an actual or hypothotical accident in the drywell. A drywell isotopic air nample io either directly input by the operator or calculated based on the Containment High Range Ra:iiations Monitoring System (CHRRMS). If the CHRRMS is used, gross concentration is calculated:

Cy = DR c

• dl3

• LEG /8.8E9 where:

C = gr as containment airborne D

concentration (pci/cc) 813 =

gross activity (C1) per R/hr in containment, neo Reference 5 1E6 =

conversion (pci/C1) 8.8E9 = free air volume of drywell and torus (cc) Reference 9 DR g =

CHRRMS monitor reading (R/hr)

The CHRRMS reading is then used to choose an isotopic spectrum ao outlined in 7.2.1.1. After the opoetrum to decayed for time after ahutdown and renormalized.

(2720P;) 58.0

k IO N OYSTER CREEr, RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title Revision No.

Oyster Creek Emergency Doso Calculation Manual 5 drywell isotopic concentration can be calculated:

CDi =C D

• II where C =

c ncentration of isotope i in the Di drywell fi =

decayed and renormalized lootopic fraction of lootope i After the isotopic concentrations are either entered or calculated as outlined above, the release rate from the drywell is needed. This calculation addresses four release paths. The first in f ;-

( containment venting. The Emergency Operating Procedures (EOP'o) upecify a venting lineup through the SBGTS, Worst case, this would give a flow rate of 2600 cfm from the drywell to the main stack.

Isotopic source termu are then:

Sg=CDL

• 2600

• 472

• FFi

where

S =

isotopic release reto (pCL/S) t 2600 = maximum flow rate through SBGTS (cfm) 472 =

conversion factor ((cc/s) / cfm)

FFi =

filtration factor 1.0 for noble gases, 0.1 for lodines l '

I (2720P2) 59.0 I

b UO Mf OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title _

Revision No.

Oyster Creek Emergency Doce Calculation Manual 5 The second release calculation is a worst came analysis which assumes that all the activity in the drywell is released. A drywell and torus volume of 2.8 E G cubic feet is assumed to he released over a period of one hour. This leads to a flow rate of:

5' F= 2.8 E 5/60

• 472 where P is the flow rate is cc/s. '

This value, multiplied by the drywell isotopic concentrations gives an isotopic

{

source term. A release duration of ono hour must be used.

The third release calculation which can be calculated is the release due to normal drywell leakage. The drywell leakage is calculated as a function of drywell pressure as:

DL = .632 * (PD /35)b

• 472 wherer DL =

drywell leakage (cc/s)

.632 =

Tech Spec drywell leakage at 35 psi (cfm) 35 =

Tech Spec drywell pressure (psi)

P =

Drywell pressure (psi)

D (2720P2) 60.0

b M M[ OYSTER CREEK RADIOLC..ICAL CONTROLS Number POLICY AND PRfIEDURE MANUAL 9300-ADM-4010.03 1 _

Title Revision tio.

Oynter Ct.eek Emergency Down Calculation Manual 5

.,3 , , _

This value, when multiplied by the drywell isotopic concentrations, yloids an isotopie source term.

The fourth release calculation allcwo the .

l user to directly entor a drywell leak rate (DL) due to drywell failure. The two methods of determining drywell leak rate assume the leak 10 directly from the drywell to either SDGTS or the o t. a c k No credit is taken for holdup or dilution in the reactor building. If otand-by gas is on the iodine release rates are reduced by a factor of 10.

7.2.1.4.2 Reactor Building The reactor building contingency calculates a release rate based on a volume of coolant released to the reactor building. Coolarit concentration is either manually input or assumed based on the entered spectrum an outlined in 7.2.1.1 with the "No Damage" opectrum corrected for current DEI. Isotopic nource term is 1

\

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ND M[ OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND l'ROCEDURE MANUAL 9300-ADH-4010.03 Eitle Revision Uc.

Oyster Creek Emergency Dose Calculation Manual 5 then calculated as:

S a t Ct* (LR*LT*3705/5.04E10)*2600*FFi*472 if SBGTS in on and St=ci (LR*LT*3705/5.04E10)*65000*472 if SBGTS is off where S

t

isotopic roloaso a n's e (pci/s) ct

isotopic coolant concentration (pci/cc LR =

leak rate (gpm)

LT =

leak timo (minutes) 3785 =

conversion fact.or (ce/ gal)

-! 5.04E10= volumo of reactor building (ce) Ref et e 2600 =

SBGTS flow (cfm) 65000 =

reactor building fan flow (cfm)

FF =

filtration factort 1.0 for noble gacim t

for iodines 22.LH 472 =

conversion factor (cg,)

7.2.1.4.3 Turbino Building The turbine building cont ingency calculates a source term barad on a volume z of coolant released to the turbine building. Becauue the turbine building has both elevated (main atack) and ground level (TB vento) release points, both (2720P2) 62.0

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Oh M OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title Revision No.

Oyster Creek Emergen:y Doce calculation Manual 5 elevated and ground level source terms are developed. Reactor coolant concentration

.Le either manually input or assumed based i on the entered spectrum as outlined in 5.2.1.1 with the "No Damago" spectre >

corrected for current DEI. Elevated source term is

).

S t a Ct*(LRaLT=3785/1 OEll)*86000*472 whare:

S = isotopic release rato (pCi/c) #

t Cg = isotopic coolant concentratio1

( Ci/ce) y I LR = leak rate (gpm)

LT =

icak time (minutes) 3785 = conversion factor (cc/ gal) 1.0 Ell = volume of turbine building (cc)

Referenca 9 1

86000 = turbine building f an flow (cfm) 472 =

converaton factor (cc/s / cfm) and the ground level source term, if the vents are not isolated is:

S t

=

Lg*(LR*LT*37S5/1.OEll)*F TD 2 where:

F =

total turbine building ~ vent flow TD (cfm)

=

Operating Floor vent flow + Pump Room vent flow + Lube Oil Bay vent flow (2720P2) 63.0 i

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l

, Oh M O'. STER CREEK RADIOLOGICAL CONTROLS I Number POI-ICY AND PROCEDURC MANUAL 9300-ADM-4010.03 Title Revision 11 0 Oyster Creek Emergency Dosa calculation Manual 5 5.2.1.4.4 Fuel llandling The fuel handling accident contingency develops a source term for a fuel handling accident. This calculation assumos a fuel bundle la dropped onto the core with damage repulting to 124 fuel roda (FSAR analyois). One hundred percent of the gap activity contained in the reds is released to the refuel floor. At T=0 the gap ,

activity contained in 124 fuel rode by

isotope is Kr 85 38.9 Ci Kr 85m 1670 Ci Kr 67 3280 Ci Kr 88 4750 Ci lf Xe 131m 699 Ci Xe 133 11900 C1 Xe 133m 418 C1 ~

Xe 135 2370 Ci Xe 138 11900 Ci l 5~

I 131 3960 C1 I 132 5570 Ci I 133 7890 Ci I 134 8820 Ci I 135 6960 Ci These values were calculated using total t

gap activity from Referenca 3 and multiplying by 124/34720 to represent the fraction of fuel pins damaged. These activities are first decayed for the time after shutdown, then considered to be releaned to the refuel floor atmosphero.

1 (2720P2; 64.0 e ____ . _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ ___ __

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UC M OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Title Reviolon No.

Oystet Creek Emergency Dose Calculaticn Manual 5 Release rateu are calculated:

5t=Rg*l.0E6/2.OE10*1270*472*fF, if SBGTS is running, ci st = R =1.0E6/2.0E10*31700a472*

y if SBGTS is not running where Rg = decayed amount of isotope i u

release (C1) 1.OE6 = conversion (pCL/Ci) 2.0E10n refuel floor volume (ce) 1270 = maximum flow rate from refuel floor with SBGTS on (cfm)

filtratien factor 1.7 for noble j gases, 0.1 for iodines 31700 = maximum flow rate from refuol floor with reactor building f an on (cfm) st = iootopic release rate (pCL/a) 472

conversion factor ( $ )

FF y = filtration factor 1.0 for noble gasen 0.1 for iodines 7.2.2 Meteorology Normally, meteorological parametern are obtained through s direct connection, via modem, with the Forked River met tower. If the connection cannot be completed, or the operator wiches to 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 those parameters i

.a (2720P2) 65.0

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k U M[ OYSTER CREEK RADIOLOGICAL CONTROLS Humber POLICY AND PROCEDUR1' MANUAL 9300-ADM-4010.03 Title Revision No.

Cyater Crook Emergency sDose Caler' . on Manual 5 which are noceauary to perform a dopo projection based on the source term to be entered. For example, if only an elevated source term exista, only the elevated paran.otore may be edited.

If no sourco term above background exitu, initial.ly no editing will be allowed.

Af t.or the needed patamotors are ontored, the computer asks the operator if he wishou to edit the values which will be displayed on the meteorology nection of the f inal out put, but not needed for the calculations.

7.2.2.1 Stability Claus The difference in temperature between two heighta (AT)

, ( is used as a measure of the atmoaphoric st abilit y.

Based on the AT, one of the Panqui'.l-Gifford stability l

clasnes is chosen. Specific criteria are as follows:

Stability Class Delta T Celta T _

(380-33ft) (150-33ft)

Elevated Ground A < -3. 61 < -1.22 B -3.61 to -3.24 -1. 22 to - l .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 F 2.85 to 7.58 0.96 to 2.55 G >7.59 >2.56 AT is in degreen Fahrenheit, i

d (2720P2) 66.0 l

UC Mf OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Tit'le 11evision No.

Oyster Creek Emergency Dose Calculation Manual 5 7.2.2.2 Windepeed Although elevated wind speed is input by the operator or the met tower computer, the elevated wind spood is adjuoted for the h sight of the atack using the equation WSg = WSg (jff'1)P where WS g = adpasted wind speed (mph)

WS = enterad wind s[eed (mph)

E 368.1 = physical stack height (ft) 380 = height of elevated sensors (ft) p = 0.25 if A, 8, or C ntability 0.33 if D stability 0.50 if E, F, or G stability The icwest adjusted wind upeed allowed is 0.5 mph.

7.2.2.3 Wind Direction Both elevated and ground level wind direction aro er.tered in degrees 'from'. Wind direction 'to' is calculated by adding 180' if the wind directica is less than 180* or subtracting 1808 if the wind direction is greater than 180'. The sector the wind is blowing into is based on the following ranges.

Sector Degrees Sr., tor Degrees Sector Degrees N -350-11 SE 125-146 W 260-281 NME 12-34 SSE 147-165 WNW 282-304 i NE 35-56 S 170-191 NW 305-326 l ENE 57-79 SSW 192-214 NHW 327-349 I E 80-101 SW 215-237 ESE 102-124 WSW 238-259 (2720P2) 67.0

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- 1 Uh N OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE KANUAL 9300-ADM-4010.03 Title Reviojon No.

Ovster Creek Emergency Dona Calculation Manual 5 4 -

7.2.3 Dose Projections Two separate models are used by the RAC code to calculate whole nody and child thyroid dose rates. Whole body done rates are calculated using a finite gamma model which calculates doce rates frem both an overhead cloud and immersion. Child thyroid done rates are calculated using a semi-infinite cloud model.

7.2.3.1 Release Height At Oyster Creek the only elevated rolesse point is the main atack. All cther releaan points are connidered ground level with a release height of O. Elevated releane height is:

j Hg= 112.2 + Pr + T f where:

Hg = effective release height (meters) 112.2 = physical utack height (meters)

Pg = plume rise calculated using the Briggs Plume Rise Equationn (Ref. 13)

Tg = terrain factor Laced on downwind distance and wind direction (meters) 7.2.3.2 Duilding Wake Effect For ground level releasen a building wake effect la calculated which is used 40 a virtual source distance.

The distance simulates the building wake effect of the reactor building. The virtual distances for each of the seven stability clauses are 209, 209, 209, 284, 483, 734, and 1219 meters, renpoetively. The virtual

distance to added to the actual downwind distance betore the dose projection is performed.

i I

i l

(272002) 68.0 l I

i I

1

(T h y $g OYSTER CREEK FADIO14MICAL CO!4TROLS IJutnbe r POLICY At4D PROCEDllPE MA!4UAh 9300-ADM-4010.03 TLtle Rovi sion fJo.

Oyoter Creek Emergoney Doon calculation Manual 5 7.2.3.3 Finite Modol The OCtJGS RACP model celt;ulaton external whole body gangna dose rate using a finito rnodel for both ground 4.nd elevated reloaeon. The finite garruum dose algorithm is licensed f rom Dr. John Hamawl of Entoch Engineering through Pickard, Lowe, & GarricN, Inr. (Dr. Hataawi was the author of the dono integral routino listed in Appondix F of Reg. Guido 1.109). The doou is computed by roultiplying the doro rate by the expected duration of releano.

, The firite gamma dono algorithm in the octJGs RAC model T

( has tbo name st ructure an Pickard, Lowo & Garrick's MIDAS finite garuna doon algorithm. Thu basis for the algorithm is a three dimenolonal array of finite gamma factors. Thoso finite gamma factors are pre-computed three dimenolonal numerical integrations which appear in the theory of the finito cloud model and repropont the spatial distribution of the radioactive material in the finite plume. These f actoro depend upon the plurre dimensions at the downwind distance of intercet, tho

\

plume elevations, and the average gamma energy of the nuclido mix in the cloud. They are 3cmotimes referred h to as agamma X/Q* in the literature although they aro i

not derived from typical X/Q calculations. The finite

( gamma factors in,the array correspond to 28 downwind (2720P2) 69.0

I UO M OYSTER CREEK RADIOLOGICAL Cot 4TROLS POLICY AND PROCEDURE mat 10AL IJumbe r 4300-ADX-4010.03 Title hovinion !;e.

Oyst er Creek tmergeticy Deso Calculatico Manual 5 distancos, 6 heights above ground, and 6 unorgy groupn. Spoeifically, the downw!-d distancou aron 400, 500, 600, 700, 800, 900, 1000, 1250, 1500,1750, 2000, 2250, 2500, 3000, 2,500, 4000, 4500, 5000, 5500, g

6000, 6500, 7000, 7500, 8000, 9000, 10000, 15000, and 20000 meters. The 6 heightn above ground are: 0, 50, 100, 150, 250, and 500 meters. The six energy groupr are: 0.032, 0.081, 0.15, 0.25, 0.53, and 1.0 Mev. The abundineco of the noblo g a ce ti for the air otiorgy gro. ipa woro taken frum MIDAS or calculated uuing the same ,

b methodo used by PL&G.

( For effectivo release heights other than the 6 fixed heights, the finite gamma factors are extrapolated to that height. For downw'ad distances other than the 20 fj.xed downwind distances, the finite gamma factor of the nearest fixed distance is assigned to that distance, i.e., no horizontal interpolation in done, a t.

is consistent with MIDAS.

The OCNGS RAC model explicitly includes the contribution of I-131, I-132, I-133, I-134, and I-l35 [

to the external whole body gamma doue. This :nethod of hand 11.nq the contribution from the radiciodinos in mora accurate than the muchod used in MIDAS. The abundances of the radiciodines were taken from tho J1alicactlyn

.ecay p_ Data TabA s, pAtapjler, RF11 All radionuclidos are decayed during plume tt avel. l (2720P2) 70.0

.- - .-~ _ . . - . -. . . . _ . _ _ - . - _ . . . _ _ _ _

1 k UO M OYSTER CREFE RAPlOLOGICAL CO!4THOLS 14 umber f

Poi.1CY AND PM)CEDURE MAtiUAL 9300-ADM-4010.03 1 1

. - - . -- .- . - , . - - - . l Titic Revision 140. 1 Oyr. tor Creek Energency Dooo Calculat ion M.nnual 5 j

]

A more detailed dir.cuusion of the finite model in  !

l contalrod in Appendix A.

7.2.3.4 Semi-Infinite Moool The OCNGS RAC model calculates the thyrcid dnou rato duo to inhalation of I-131, 1-132, 1-133, 1-134, and 1-135. The thyroid dose rato is proportional to X/Q.

The conotant of proportionality 10 the product of the child inhalation dc actors. The program usen thi chi 2d braathing rato of 0.42 m3/).r (from Table E-5, Reg. Guide 1.10'4) and the child inhalation doce factora from Table E-9, Reg. Guido 1.10r> to computa the dopo

( rato conversion factors. The done is coroputed by multJrlying the dose rate by the expected duration of the r o'l e a n e .

The radiciodinen are decayed during plume travel time.

The decay constas.to for I-131 through I-135 are from the BadiologjgaLfealth.lfandbong, Reforcnce 6. The child thyroid done rate at distanco d in then:

DR(d) =h(d)

• i=1 f Si

• DF I whero DR(d) = chlid thyroid dose rato at distance d (nRom/hr) hid) =

chi over Q at distance d (e/m3)

=

S j release rate of isotope 1 (ci/c)

DP g = done factor for isotope 1

(

(2720P2). 71.0

1

. k hh Of OYSTER CitEEK ltADIOLod1 CAL COf4TitoLS 14unibe r POLICY Af4D l'ROCEDURE MAtJUAL 9300-ADM-4010,0)

Title HovisionJo.

oyotar Creek En ergency Dutio Calculat ton Manual f, apocitie doou facttro aret 1131 1. die 9 (aj'[!/'ML)

I132 2.21I7 1133 4.3 BIB 1134 5.76t6 1135 9.0E7 The baels for the X/Q calculation is the Laussian diffusion equation.

X/Q is calculated aus

= 1 X, ( ,3 ) EXb -~I@w-Q US 3* .45acy *u r.

- 2"z -

whetet W5 3 = adjutated wind upuod for tho role.are height (mph)

.4S = convorolon factor oy = lateral plumo opread (m) og a vertical plumo opread (m)

!!R = offective releane height (m)

Tho lateral plume spread, Ty in calculated using the f

l following equations from referonco 8.14.

i l

• X

• tan (.017453293 * (C1 - di Ty - 465.11628

• Inx);

where x = downwind distan00, (Km)

C1, di = coolfLeionts baued on otability class au given bolow Stability Clana ci di A 24.1670 2.5334 l C 18.3330 1.8096 C 12.5000 1.0857 (2720P2) 72.0

UC $M OYSTER CREEK RADIOLOGICAL CONTROLS !Jumbe r POLICY AND PROCEDtinE MANUAL 93OO-ADH-401C.03 Title BevAolon 11o.

Oyster Creek Ernergency Dose Calculation Manual 5 Stability Class Ci di D 8.J330 0.72302 E 6.2500 0.54287 F 4.1667 0.36191 G 4.1667 0.36191 For G stability, the calculated value is egaal to the F stability value from the above equation. This value in then multiplied by .6667 to obtain Ty for G stability (reference 8.13). f 0

The vertical plume spread, Tg is calculated using the ,

following equation from reference 8.14.

Ta = A y a X The coefficiento, A gand bi, are functions of stability class and downwind dLotance. Because the coefficients are more complex than those for Ty, they will not be listed here. The interested user 10 referred to reference 8.14.

7.2.3.5 Maximum Calculation Maximum whole body dose rate is calculated by performing both ground level and olovated done projections, if appropriate, at the site boundary, 400, 500, 600, 700, 800, 900, 1000, 1250, Ir00, 1750, 2000, 2250, 2500, 3000, 3218, 3500, 4000, 4500, 5000, 5500, 6000, 6500, 7000, 7500, 8000, 8045, 9000, 10000, 15000,

(

(2720P2) .0

U M[ OYSTER CREEK RADIOLOGICAL CONTROLS Number POLICY AND PROCEDURE MANUAL 9300-ADM-4010.03 Titic Revision No.

Oyster Creek Emergency Doso Calculation Manual 5 16090, and 20000 meters. The ground level and elevated values for each distance are then added and compared to find the highest value.

Haa msm child thyroid doue rate lu calculated in the saui:e wa, -- ~

that dose ratos are calculated at the s.".e toundo /, 400, 600, 800, 1000, 1200, 1400, 1600, 1800, 20JO, 2500, 3000, 3218, 35Co, 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 Several other functions exist, which although not required for

[

dose projections, add conoiderably more power and user friendlinens to the code. These functions are activated by " Hot Keys" which can be used at any place in the code. Combinationu of pull down menus and pop up windows are used to simplify the machine / user interface.

7.2.4.1 PCS Direct Connection The Plant Computer System is physically located on the first floor of the Site Emergency Building (FEb). A direct feed was established from the PCS to a personal computer, also located in the SEB. This personal J computer has four available lines which are called, via l

i modem, to obtain plant data. RAGEMS and RMS data are also included.

(2720P2) 74.0 l

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U $8f OYSTER CREEK RADIOLOGICAL CotiTROLS tiumbe r l'OLICY AtlD l'itoCEDURE MAtJUAL 9300-ADH-4010.03 Title Revisien llo.

Oyster Creek Emergency Dono Calculat ion Manual $

Soveral paramotors are also calculated by the PC baood on inputa from the PCS. Time after shutdown, lowest reactor water lovel, and how long the reactor levol was no ~30" aru examples of theue. The PC operates continually, alwayu ready to relay data from the PCS to a RAC computer, tiew data is tranomitted every 15 seconds.

When the PCS flat key is pur,hed, the RAC computer firct

'l looks to veo if a modem la available. If not, the monnage "flo modem for PCS connection" will be dioplayed within fivo seconda. Otherwise the RAC computer will i dial and connect to the PC in the SEH. After the user i

logu on with his location, data tranomission begins.

Up to four RAC computorn may be connected to thu SED computer at the same time.

If the computer in the SEB doou not answer, the RAC computer will attempt to call the RAGEMS computer. If the RAGEMS computer anuwers, a Logon and Password will be sont and when accepted, the RAC computer will s

receivo data directly from the RAGEMS computer. If this caso only RAGEMS I high rango and otack ilow, and RAGEMS II high and low rango and vent flows will be available to the codo. RAGEMS data is updated every f ive rainutes.

(2720P2) 75.0

, UC $$f OYSTEft CHEEK RADIOLOGICAL CONTHOLS fiumber 9300-ADM-4010.03 POLICY AtJD ?HOCEDURE MANUAL Title novintur. No.

Oysit e r Croek Energency Dono Calculat icn Manual 5 Finally, if nc> connection is mado to the l'CS or RAGEMS computorn, thu une is warnod that no connuttAon was I

available.

• 1 . . 4.2 Automatic Doou Projectiori With the direct connection mado to the PCS computor, a dose projection based on the PCs date an bo mado with no operator input.

The computer looks at tlm PCS data to determine where a j 1

i monitored releano in coming from as described in 7.2.4.3.1. The computer then determinou a core damago spectrum an outlined in 7.2.1.1.

A cource term in then calculated an outittied in 7.2.1.2.1 if the releaGo 10 from the Hoactor Building. The reluano duration is assumed to be oeven hours.

Il the roloaou is determined to be from the Turbino Building a sourco term is calculated as outltnod in 7.2.1.2.2 and the release duration la accumed to bo one hour.

( 7.2.4.3 Ventilation A graphic depiction of the monitored releano patha is available. Tho diagram is very simplified, showing I vent paths, Reactor Building and Turbine Building fano, and stand-by gae.

t (2720P2) 76.0

[ U $g OYSTER CREEK RADIOLOGICAL CO!lTNULS dumtie r POLICY At3D PROCEDURE HAtJUAL 9300-ADH-401C.03 y_._________ __ . -

Titlo flu v i s i on 110.

Oyster creek Erwrgency Dow calculation Manual L 7.2 4.3.1 Releano Path Analynia To detocmino the release pat ha, airborno dCliVilles Calculated from RMS readings and appropriato dilution factora are compared to RAGEMS readingo. Airborno concentrations are calculated from th? CllRRMS and monitcru A-4, C-6 and C-9/10 by assuming their reailings to be duo to a nomi-infinito cloud of Xe-133. The concentraticon are then diluted by asuumed flow raton f or t he Rx 111dg fans, SHGTS, Turbine Bldg vents, and j Condensor Bay fans, and compared to the concentrat. ion measured by the RAGEMS nyutoms. A calculated concontration greator than .1 of the concentration moacured by RAGEMS at the roloaco points in conoidered a good match, s

7.2.4.4 Field Monitoring Team Roadings Time, location, whole body dono rato, and child thyroid done rate from field monitoring teamn may be entered for dipplay on the final output. 11 0 calculations are performed.

7.2.4.5 Utility Functiono 7.2.4.5.1 Leak Rato Calculation

( A leak rato based on the driving preocure and size of the leak can t>o calculated.

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MC Mf OYSTER CREEK RADIOLOGICAL CO!4Th0LS 14 umber POLICY At4D PROCEDURE MA!4UAL 9300-ADM-4010.03 Title Rev i o ion .!Jo ,

Oystor Creek Emerge vy Dono Calculation Manual S Bernoulli's equation.

P + h dg + \dv 2=P2+hdg*

3 y g 2 \dv 7 2 is used.

where p, g P2= prosaure in ctato 1 and 2 (psig) h,g h; = height above reference plano (ft) d = doncity (Ibm /ft )

=

9 g r av i t a t iorg a l conntant (32.2 ft/s')

V, 3 V2= vel cition (ft/s)

Assuming

( h=h' 3 2 P =0, 2

and V 3 =0 then:

P 3

dV 2 or the potential enorgy in the form of prosaure is equal to tho kinetic energy of the moving fluid. Solving for the velocity of the fluid and multiplying by tbo leak area LR+A*(Pl *144/d*2*32.2)b*C0 whore LR

leak rate (cfm) 144 =

conversion factor (in2 /ft2) 32.2 =

conversionfactor({hyf((}

60 =

convornion factor (s/ min)

A =

leak area (ft2)

(2720P2) 78.0

[ U Mf OYSTER CREEK RADIOLOGICAL CONTROLi; Humber POLICY AND PROCEDURE MANUAL 93OO-ADM-4010.03 Title Revision No.

oyster Creek Emergency Done calculation Manual 5 Tht consition used in thin equation are 2.23 lbm/ft for steam 46.4 lbm/ft for water 3

8.07E"2*(7 % )*( @ y Al) lbm/ft for air where T = air temperature ('F)

An assumption 10 made in Burnoulli's equatian that tho fluid is incomprescible.

Although this will lead to come error when used for steam or air, it will provido a good leak rato approximation.

( The 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 known the enthalpy of tho fluid, the code will correct for change of state and give the resulting leak rate of both oteam and water. To determine thene, first the quality is calculated:

X= (ggEh{}

whores X = quality

, h = enthalpy of fluid (Btu /lb) hf = saturated liquid enthalpy at I atmosphere (Htu/lb)

(2720P2) 79.0

NO M[ OYSTEl4 CREEK RADIOLOGICAL CONTitoLS Number POLICY AND l'ROCEDURE MANUAL 9300-ADM-4010.03 Title Revision 110.

Oys.ter Creek Emergency Dose calculation Manual 5

} - __

hg =

naturated vapor enthalpy at I atmosphore (Htu/lb)

Tho water leak rate lu then Lw =

d*LR*(1-X)*.016747 and the steam leak rato is j 1

Ln a d*LR*X*26.799 Wharol Lw =

Water leak rate (Cfm)

La =

nteam leak rate (cfm)

.016747= opecific volumo of watur at I atmoophoro (ft3/lbm) 26.799 = spocific volume of steam at I atmosphere (ft3/lbm)

( 7.2.4.S.2 Core Damago Estimation The percontage of fuel molt la outimated using the CllRRP.S reading. Emurgoney Plan Procedure 9473-IMP-1300.33 Reference 7, contains graphs which relate Ci!RRMS reading to percent noble gas releaned and porcent noble gas released to percent core rnelt.

Curve fitting to those grapha given:

D=C* CR where D = \ coro damage C = conversion factor 3.021E-4 if TAs < 1.0 hr 4.982E-4 if 1.0 < = TAS < 2.0 hr (2720P2) s. v . O

[ h] UC Mf OYSTER CREEK RADIOLOGICAL CONTROLS POLICY AND PROCEDURE MANUAL

!!umbe r 9300-ADM-/.010.03 Title Revinien !;o.

Oyster Creek Emergency Dose calculation Manual 5 6.749E-4 if 2.0 < = TAS < 4.0 hr 1.018E-3 if 4.0 < = 1AS < 8.0 hr 1.676E-3 if 0.0 < = TAS < 24 hr 3.796E-3 if 24 < = TAS < 72 hr 7.604E-3 if TAS > = 72 hr TAS = Time After Shutdown (hrf CR = CllRRMS reading (R/hr) 7.2.4.S.3 Field Iodine Moacurementa The Oyotor Creek Field M:nitoring Teams (FMT's) uun a RADECO air camplar with a silver zoolito cartridge and paper filter to

! draw air samples to determino child tyroid committed doso. The cartridge and filter are counted with an E-140 with a HP-270 probe. FMT' n report gross filter count rate, gross cartidge count rate, background count rate, cairpler flow rate, and camplo a

time to the EAC or RAC, as appropriate.

Using those values groes airborno iodine concentration in calculated:

C=l(Z-B)/.0039+(F-D)/.10 l/(f*St*1000*2.22E6) where C = airborne lodine concentration (pci/cc)

Z = nilver toolito cartridge reading

( c pm)

(2720P2) 81.0

b U NI OYSTER CREEK RADIOLOGICAL CONTROLS Numbur POLICY AND PROCEDURE HA!JUAL 9300-ADM-4010.03 Title _ _ .

llovision flo.

Oyuter Creek En.ergency Dose Calculation Manual 5 D =

background reading (cpm)

F =

filter paper reading (cpm)

.0039= counting ef ficiern y for silver scolite cartridgo

.10 -

counting officiency Ior f11 tor paper f =

can:ple flow rate (11 tor / min)

St = sample timo (min) 2.22E6= conversion factor (dpm/pci) 1000 = conversion f act or (cc/ liter)

Child thyroid committod dono rato is then found by multiplying thin concentration by

( a dose factor for the expected lodine spectrum. At power t his opoetrum in expected to bei I-131 11.9%

I-132 16.th I-133 23.14 I-134 26.6%

I-135 21.0L Those values are first decayed for timo after shutdown, then renormalized. The dose factor is thon 5

DF=E fi Dfi i=1 where DF =

done factor for lodino spectrum

( Epom/h pUl7cc )

t Fi =

decayed and renormalized fraction of isotopo 1 (2720P2) f12 . 0

, _ ~ . _ _ _ _ _ _- _. _ _ _ - _ . .

k U Mf OYSTER CREEK RADIOLOGICAL CONTROLS tiumt>o r i POLICY AND PROCEDUR1-; MANUAL 9300-ADH-4010.03 Titio Hovision No. l Oyster Creek En ergency Dopo Calculation Manual 5 l

DFi a dooo factor for footopo 1

( 000 Referenco 5.2.3.4 7.2.4.5.4 UnitConve{rsionsp"gJ'[hI)

A unit conversion function is included to facilitato calculations. The utility will convert unitu of longth, area, vo l u.ao ,

flow, preed, pressure, temperaturn, doso, equivalent dopo, and activity 1)otween different meaaurement nyotemc. In all cases except temperaturo convorolon, the entered value in multiplied by a conversion factor to obtain a value in the now unita.

(

Temperaturo conversions uno the following relationshipo:

9 F = 5C+32 R= F&459 K = C+273 where:

F = degroen Fahrenheit c = degrees Calsius R = degrees Rankin K = degrono Kolvin 7.2.4.5.5 semi-Infinito cloud Approximation A comi-infinito cloud approximation can be used to approximate total airborno concentration and total iodine MPC. The

[

{ entered doce rate is first corrected to a (2720P2) 83.0

[ k UO M OYSTEH CHEFF HADIOLOGICAL CONTI4OLS Numt>er l'OLICY AND PHOCEDURE MANUA1. 9300-ADM-4010.03 i Title novision No. i Oyst er Creek Emergency Daue calculaticn Manaal L semi-infinite dono rate by polving Dj - uxDR for DRs.

I 1

where D f a moacured finite dose rato 1

u= linear absortion coefficient j I for gamma raya in air (m"I) x = optimated radius at finito cloud (maters)

DRo = nomi-infinito doon rato (mR/hr)

Tot al airtiorno concentration lo calculated I

nos i

l u

i

= 9%

• E a lI where C = approximate airborno concentration (4 i/cc)

En =

averago gamma energy (HeV) 9.0ES= numerical conversion factor Ea la determined as a function of time after chutdown. Ea varies from .54 MeV at TAS = 0 to .172 at times groator than one hour.

MPC is calculated MPC = .388 * .00119

• C / 9.0E9 t /

l \

\

l t

(2720P2) 84.0

k Uh h[ OYSTER CREET RADIOLOGICAL CONTROLS fiuml>e r POLICY A!JD PROCEDURE mat 40AL 9300-ADM-4010.03 l

.- - \

Title Reviuton tio. ,

oyster Crook Emergency Dopo Calculatton Manual 5 l

wheros

.118 = conversion between total todine and DEI for this rpectrum

.00119= fraction of reloano which la lodine 9.0E9 = 1 HPC for I-131 7.2.4.5.6 Calculator A calculator utility la available which uurs "Roverso Polish tiotation* ( RP!1) logic to perform addition, subtractlon, multiplication, and division.

8.0 fif7Eligt!GE 8.1 Calculation 9340-89-005, Revision O.

11 . 2 Specification OCIS-402180-003, Revision O.

8.3 McKenna, T.J. and Glitler, J.G., "Sourco Term Estimation During Severo tJuclear Power Plant Accidento", [JysJffit,flp_rtt_droul[1gJ,,

!!cvember-December 1988, pp 83-85, 90.

8,4 Calculation 9430-88-007, Reviolon 0, 8.5 Calculation C-1302-661-5350-11, 8.6 liptd i ol ogica l floa lt h__Ilanfit22gh , U . S . Department of !!oalth, Education, and Wolfaro, 1970.

8.7 Energency Plan Implementing Procodore, 9473-1MP-1300.33.

8.8 slado, David 11., htagrglegyr and AtorthEnergy, United stateo Atomic Energy Commionion, July 1968.

8.9 0. C . fl . G . S . Plant Operations Manual.

(2720P2) 85.0

. - - - . . . . - .- - - _ = - - . . ~ . - - - _ . - . . - . . . - . .- -

I Nh M[ *'YSTER CREEK RADIOLOGICAL CONTROLS Number POLICY Af4D l'HOCEDURE MANUAL 9300-ADM-4010,03 Title Rovinion No.

Oyster Ctcuk En:orgr'ncy Dose Calculist ion Manual b 0.10 0.c.N.G.C. Updated Final Safoty Analyola Repor*,.

8.11 U.S. NRC Rog. Guido 1,145.

0.12 U.S. NRC Reg. Guido 1.109.

8.13 11umn Bjan, Driggs, G.A., (TID-25075), United Statas Atomic Energy Committolon, Of fico of Information services, 1967, 1974.

8.14 Industrial Source con: plex (ISC) Dispersion Model Uner's Guido, y volume I.

I p

l (272002) 86.0

_ . . _ . _ _ _ _ .....__.-_...._.__,___._.m . . . . - - _ . - - . . _ _ _ . _ _ . _ . _ _ . _ . _ _ . _

t 9

9300-ADM-4010 93, Ik:v. 4  ;

APPENDIX A CLOUD G AMM A NOSE: TilEOltY For clouds with dimensions that are small compartd to the range of the ganuna radiation, a calculation :.f the r,amma dose at a Si ven point must take into account the radiation received '

from varion.; parts of the plume. The complexitter, of geometry, absorption, and buildup make complete solution difficult and require the use of special integrals.

f:

1 In terms of the reference system given in Fig.1, the equation for the gamma dose can be written:

0.1610' D a H7 9 0-(9 x/9 )0 (Il + kI )2 - "

? (x,y,0)

• g

~~~

II) where

'u

_ - *** 2-

_(m-r{" ,exp ,(m+r I= eXP #r) gxp '

t . dr dt (2a) 4 @ #al # 0*0 2 ag' , 2 a; ,

f and '

._- r = ,* 2 u it exp (-gr) 2

],' _ . - (m-r

, =

-exp b- -

dr dt (2b) 4fTr a l*0*O 2 ag , ,

2a* y The symbols are defined in Table 1. Eqs. (1), (2a) and (2b) above correspond to Eqs. (7.41),

(7.41a) and (7.41b) in lleference (81. Values of 13 and 12 are determined from numerical 1

integrations.

')

l i

s El-1

...a -

,_ __o

9300-N41-4010.03, Rev 4 NTII:DIh A l'lGUllE 1 Coordinate System for Cloud Gamma-Dose Calculations (m 2 ,,2-2 mr cos ()'/I RELEASE CLOU0 NOLUME ELEMENT OF CLOUD (a,y,1)

POINT CENTER (Ut,0.h)- f

( 0,0, h i s G f

/t.b (2 e r sin 4 d 4 r dr)

\

!Y 14

/

o ..-

y/, r sin 4 t

m r s a h (0,0,0) s -  :

\

1. ( =i.0,0 )

m t-( m,- 01)I+ y,2 + h2

< r.

RECEPTOR ( si ,ys .O l e i

6 I-l i-

~

I

\

El-2 a- --r-e w >= v g-e W fM--g w yimy- e* e.-,-' - 9 g. =

. . . . . __ _ . . . - _ __._ _ _ _ ._ _ _ _ _ _ -- _ _ _ _ _ _ __.. -. _ m _ _ _ .. . _ _ _ . . _ _ . . - -

9300-ALE-4010.03, Rev. 4 APPENDIX A  !

TAllLE 1 DEFINITION OF SYM13OLS 7D(x,y,0) Gunma-ray d(ise [ rads] as a function of downwind distance : and C: >sswir i distance y y 3 4/ Q r>)tption coefdcient for air [m~I]. (y = ap + #s, where3 y is the i sznering absorption coefficient) l

-v I!nmgphwrption coefficient for air [mI) 3 {

3 k- (ppq'z/ 3 [dimensionless)

Ey - Average gamma energy emitted at each disintegration [Mev/ dis]

Qg Initial source strength (curies] l t

Qx/Qp - Fraction of original source material which was not removed by radioactive decay (dimensionless}

- 1 ,1 Integrals used in the solution of the equations from gamma-ray dose 3 2 from a cloud [s/m]_

- ii Average wind speed [m/s] ,

m,r Distances used to describe the three-<limensional geometry for cloud ,

gamma-dose calculations Jmj (see Fig.1) c ag Standard deviation of plume width [m); a3 = /_ a a y 7 t Time [s] -;

El - I

,.,,---s--r,.., .v w . ,,.,_,e,-.m.+,,,,-,v,-

, ~ , . , . _ , . . , , ~ , + , . - , - - , . , - , , . ,~,v...~-.---,-..,..#.,~,r.....m. ,.w,--,-,~,~ ,,,v. .-.m.,-...- .

l 9 300-NN-4010.03, Rev. 4 APP 10;DDL A CLOUD G AMM A DOSE Al'i'LIC ATION Ol' TilEOlW Numerically evaluating the integrals 1) and I.,in l'q. (1) takes many hours of computer time Obviously, this time is not available during a radiological emergency. Tht refore, the3e integrals need to be pre-computed. This section describes how this was done.

Eq. (1) can be rearranged as follows:

D(x,y,0) "0 Qgx(90/9 )l0.1616

/ I 4;'a l k(I g + ki )f The expression in braces contains not only the integrals 31 and 1, 7 but also the factors n. ;;a' E_,, and k We will call the expression in braces the gamma factor, and denote it by ,12 7

F z 0.1616 y ay Ey(1-i

+ kl.,)..

(3) 'f

. Eq. (1) can therefore be written as:

D= Qo (Qx/Qo) F (la) 7 g 7 P

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 totalof 381,024 gamma factors were computed:

(42 downwind) X (36 ctosswind) 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

• 1 9300-NN-4010.03, Rey, 4 l

, APPI1 DIX A l l

TADLE2 l Variables for Array of Gamma l'a tors  !

t 4

Downwind Stability Energy  ;

index Distance licight Class Group '

_ t (m) (m) (Mev) 1 50 0 A 0.03" 2 100 30 13 0.081 i 3 159 60 C- 0.150 i 4 200 100 D 0.250 i 5 250 150- E 0.530 6 300 300 F 1.000 l 7 350 G  !

8 400 0 500

+

10 600 11- 700 12 800  ;

13 000 14 1000 t) ' !'

15 1250 I 16 1500 i

17 1750 '

I-18 2000 10 2250 20 2500 i 21 3600 1 22 3500 23 4000 ,

21 4500 25 5000 26 5500 27- 6000 i 28 6500

-20 7000 i 30 7500 -i 31 8000 '

32 0000 <

33 .10000 '

i

~

34 15000 35 20000 36 25000 37 30000

• 38 40000-

=30 50000 L -

.40 00000.  :

i -41 70000 '

l 42. 80000

=(

L El-5 J

c_ .___....-._._._..m.___~_.___.____._..

i

- P 9300-N1M-4010.03, Rev. 4 j

- , I APPINDIX 3 Table 2 shows that the gamma factor is a function of both space and gatuma energy. The depet.dence 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 v). and o.,, l respectively, i

• I The gamma factor is clso a function of the energy of the gamma rays, E . The gamma factor,  ;

7

,P,is a function of the gamma ray energy because is a function of energy [1] , and p is a non-linear term in the integrals 31 and 1, 2 as r m in Eqs. (2a) and (2b). This non-linear i

dependence of .7P on E,7 necessitates partitioning ,yF by energy group.

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 I ,

accurately represent the contribution of these rays to the whole boay doae. Instead of a single i value of E , the spectrum of gamma ray ' nergies e is better represented by several vahies of -

7 E 7, especially in view of the non-linearity7of F. Table 3 lists the six values of E, that were ,

used to represent the full range of gamma energies. Values of p, 3, and k for each E are also  ;

shown.

- Although - radionuclides emit gamma rays across a broad spectruru of energies, the -

c. i distribution of this energy varies markedly with radienuclide. Some radionuclides may. emit many low energy gamma rays and ordy a few high energy rays. Others may emit a lot of ^ .

medium cncrgy 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.

'(

i

'El-6

i

!/

9300-ADM-4010,03, Rev. 4 APPL?OIX A

( TAnlE3 i'

The Dependence of v, ap , and k on E, Ey H k l'a ,

(Mcv) -(m-I) (m'I) 0.032 4.000E-02 1.500E-02 1.067E+00 '

O.081 2.200FA2 3.200E-03 5.875E+00 0.150 1J34E-02 3 268E-03 4.307E+00 0.250 1.455E-02 3.023E-03 3.014E+00 .

0.530 1.003E-02 3.830E43 1.850E+00 1.000 8.203E-03 3.009E-03 1.273E+00 e

The intensity of the gamma rays for cach of the six energy levels is called the abundance. The 'l l abundance is denoted by a. Thus the total gamma dose for a radionuclide is the sum of the

[ the gamma factors for each energy group weighted by the abundance for each energy group:

1 x

y Dn Qo (Q /Qo) h, ggP o (Ib) 1:1 The only other term in Eq. (Ib) which needs to be computed is the ratio Q /Q , which is x O  ;

given by:

Q -

= exp(-A(6t + (4) where 6t = holdup time of radionuclide A = decay constant for radionuclide 1 5 x El-? l __ - l- . .- - . - - - - - - - - ~ - ~ ~ - - ~ - ~ ~ ~ " " ' ' " "}}