ML20237F962
| ML20237F962 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 02/27/1987 |
| From: | PACIFIC GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML17083B902 | List: |
| References | |
| CAP-A-8, NUDOCS 8709020048 | |
| Download: ML20237F962 (85) | |
Text
{{#Wiki_filter:l . l 1 I PACIFIC GAS AND FLECTRIC COMPANY NUE ER CAP A-8 REVISION 5 DEPARTENT OF NUCLEAR POWER GENERATION PAGE 1 0F 85 DIABLO CANYON POWER PLANT UNITS DCPP CHEMICAL ANALYSIS PROCEDURE TITLE: OFF-SITE DOSE CALCULATIONS FOR 1g-^* INFORMATION ONLY APPROVED: 76 b T PLANT PMNAGER p' NH7DATE EFFECTIVE DATE SCOPE [ This procedure describes the methodology for the following: Effluent T.S. Technical Specification Implements Type Surveillance Requirement Liquids 4.3.3.9.1 Determination of alarm / trip set- 10 CFR20, App.B. points for RE-18, RE-23. RE-3 Table II, Col. 2 and RE-16
' Gases 4.3.3.10 Determination of alarm / trip 10CFR20, App.B.
setpoints for RE-22, RE-14A, 14B Table II, Col. I and RE-27
.. Liquids 4.11.1.1.1 Pre-release analyses of effluents 10CFR20, App. B.
Table II, Col. 2 4.11.1.1.2 Post-release analysis of effluents Liquids 4.11.1.2 Dose calculations 10CFR50, App. I t Liquids 4.11.1.3.1 Dose projections 10CFR50. App 1. Gases 4.11.2.1.1 Dose rate calculations, Noble 10CFR20. App. B, Gases. Total Body and Skin Table II Col.1 P Gases 4.11.2.1.2 Dose rate calculations, IodT b , 10CFR20 App. B, i Particulate and "=dicN ctidas Table II, Col. 2 other than Noble Gases, , per organ, per age group , Gases 4.11.2.2 Noble Gas Air Dose Calculations 10CFR50. App. I 1 l Gases 4.11.2.3 lodines, Particulate, and Radio- 10CFR50, App. I ' nuclides other than Noble Gases Organ Dose Calculations per age group
, Gases 4.11.2.4.1 Noble Gases Iodines, 10CFR50, App. I Particulate, and Radionuclides other than Noble Gases, Dose Projection Liquids 4.11.4.1 Cumulative Dose from: Liquids, 40CFR190 and and Noble Gases lodines; Gases 6.9.1.6 Particulate; and Radionuclides other than Noble Gases per age group, per orcan ,
Direct 4.11.4.2 Direct Radiation Dose Rate and 40CFR190 Radiation Dose Calculations to unrestricted areas due to plant and high i radweste storage sky-shine. X006923a.08 II B709020048 870828 { l POR ADOCK 05000275 1 R . _ P@ _ .__--_- - _ _ _ O
e DIABLO CANYON POWER PLANT NUEER CAP A-8 REVISION 5 PAGE 2 0F 85 TITLE: OFF-SITE DOSE CALCULATIONS UNITS 1 AND 2 The calculational methodology for doses are based on models and data that make it unlikely to substantially underestimate the actual exposure of an individual through any of the appropriate pathways. Tables containing the values for the various parameters used in these expressions are also included. This procedure, and any changes thereto, requires PSRC review. TABLE OF CONTENTS Page
- 1. Liquid Radioactive Waste (LRW) Dose Calculations..................... 3 i
, 2. Liquid Radioactive Effluents Rad Monitors'.High Alarm Set Point (HASP) Calculations............. ................................... 5
- 3. Liquid Radioactive Effluents "31 Day-Dose" Projection Calculations.. 12
- 4. Gaseous (Noble Gas) Radioactive Release Rate Limit Calculations..... 13
- 5. Gaseous Radioactive Waste (GRW) Noble Gas Air and Tissue Dose Calculations........................................................ 15
- 6. GRW-Iodines, Particulate, and Tritium (I.P.T.) Release Rate Limit
[ Calculations........................................................ 20
- 7. GRW-I.P.T. Dose Calculations........................................ 22
- 8. GRW-Site Specific Candidate Dose Recipient Calculation Methodology.. 25
- 9. GRW "Real Time" Dose Calculation Contingency Levels................. 28
- 10. GRW-Process and Effluents Rad Monitors' HASP Calculations........... 29
- 11. GRW-Ef fluent s Dose Project ion Calcul at ions. . . . . . . . . . . . . . . . . . . . . . . . . . 33 I 12.
Direct Radiation Dose and Dose Rate Calculations From Site (Line-of-
- g. Sight and Sky Shine)................................................ 34 13 Onsite Dose to"" Members-of-the-Public" Calculations. .. .. . . .. . . . . .. . . 39
- 14. LRW-Dose factors (Table 1).......................................... 41&44
- 15. GRW-Nobl e Ga s Dose Factors (Tabl e 2) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43
- 16. GRW-I.P.T. Dose Factors (Tables 3A through 3P)...................... 44-59 17.- GRW-I.P.T. Critical-Organ-Super-Age-Group Def ault Dose Factors (Tables 4A & B)..................................................... 60-64 1
- 18. Historical " Running Five Year" Average GRW-Dose Meteorological l Dispersion Factors, Y/Q and li/Q (Tables SA & 58).................... 65&66 I a
X006923a.08 21
t DIABLO CANYON POWER PLANT NUEER CAP A-8 REVISION 5 PAGE 3 0F 85 TITLE: OFF-SITE. DOSE CALCULATIONS UNITS 1 AND 2
- 19. Site Locations for Candidate Dose and Dose Rate Recipients (Table 6). 67
- 20. LRW-System Diagram (Fig 1).......................................... 68
- 21. GRW-System Diagram (Fig 2).......................................... 69
- 22. Site Map (Fig 3).................................................... 70
- 23. Effective Flowrate Reduction AF, Due To Concurrent Liquid Re l e a s e s ( Ap pe nd i x 1 ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 71 {
- 24. Maximum Allowable Flowrate (MAF) 1.e. MPC, HASP, and "31 Day Dose .'
Projection" Limiting Flowrate (or Volume) Calculations (Appendix 1). 73 ?
- 25. Percent Release Rate Limit (PRRL) calculations for GRW Noble Gases
~ ) and IPT (Appendix 2)................................................ 76 l
- 26. R e f e r e nc e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 5 DISCUSSION This procedure is used in support of the portion of the Appendix A Technical
( Specifications that deals with routine radioactive liquid and gaseous releases to the unrestricted area. Limits are based on the dose comitment to a member of the general public related to the release of radiorsuclides through either , direct or indirect exposure (e.g. submersion in a cloud of radioactive Noble Gases, radionuclides deposited on the ground, direct radiation from radionuclides stored on site, inhalation of radionuclides or ingestion of radionuclides via a food pathway such as milk, meat, vegetable or fish, etc.). l PROCEDURE [ 1. Liquid Effluents
- a. Dose calculation (T.S. 3.11.1.2). p I
The dose contributions to the total boriy and each individual organ j (bone, liver, thyroid, kidney, lung and GI-LLI) of the maximum t exposed individual (adult) for, say, a radioactive liquid releases shall be calculated for all radionuclides I identified in those m liquid effluents released to urirestricted - l areas using the following expression: l m V D(d) D yg , j,l l I % Qj W l (j) il X006923a.08 31 1
DIABLO CANYON POWER PLANT NUMER CAP A-8 REVISION 5 PAGE 4 0F 85 TITLE: OFT-SITE._- DOSE CALCULATIONS UNITS 1 AND 2 where"Q = The cumulative dose to the total body or an organ t from the liquid effluents for the total time covering those m releases. Ajg u Composite dose parameter for the total body or an organ T of an adult for nuclide 1, for salt water site, in mrem /hr per pC1/ml (refer to Table 1). Vj = The volume of the jth release in gal. In the case of a batch release it is simply the volume in-the . batch tank released. For other releases this is *
, the flowrate used times the actual release time.
Cjj = The average concentration of radionuclides i in them: , liquid effluent passing thru RE-18, RE-3, RE-16 oV. RE-23 (or from any liquid stream entering the circulating water di) charge) as sampled and analyzed for in the j" release source, in t pCi/ml. 1
= Product of the near field average dilution and
. 300 mixing factor with 1/60 (hr/ min). The applicable factor for this mixing and near field dilution during any liquid release at DCPP's site specific discharge structure to any marine organism or dose point was selected as 1/5.8 F(j) = The total dilution water flowrate during the time of 'jth' release, in-spm. . ,
n(j) = # nuclides i in "jth" release
- b. Maximum Pennissible Concentration (MPC) calculation '
(T.S. 3.11.1.1.) 1)- The
' j th' MPC for the identified mixture of radionuclides in the batch of liquids is calculated as follows:
n I i Cj
=
MPC) Cj i i=1 MPC jj l
' Refer to the FSAR, Section 11.2.8, " Dilution Factors".
I X006923a.08 41 s
2 1 DIABLO CANYON POWER PLANT NUMER CAP A-8 REVISION- 5 PAGE 5 0F 85 TITLE: OFF-SITE DOSE CALCULATIONS tJNITS 1 AND 2 where: 1 MPCj = The unrestricted area total undiluted MPC for the
' j# particular mixture of identified radionuclides, in pC1/ml. z MPC,j
? = The MPC in unrestricted area water for radionuclides 1, in general, in pCi/ml (from 10CFR20, Appendix B, Table II, Column 2.). ,
, 2) The overall MPC for a combination of discharges (e.g.,
~ simultaneous discharge of a batch of liquid radwaste, discharge of steam generator blowdown, discharge of oily j water separator via the turbine building sump, and I discharge of condensate demineralized regenerate waste i also via the. turbine building sump) is calculated by ~
reapplication of the above equation using the total concentration for the pathway and its associated MPC: i n I ej Cj MPC overall
- ej Cj l I i j=1 MPCj I where:
r MPCoverall = The unrestricted area MPC for the current ! radionuclides mixture for concurrent j ; discharges, in pCi/ml.* - , ; Cj = The total activity concentration for the
, "jth" individual stream in pCi/ml. 4 MPCj = The total MPC for the "jth" individual individual mixture or stream determined as seen previously, in pC1/ml.
X006923a.08 51 a
J DIABLO CANYON POWER PLANT NUleER CAP A-8 REVISION 5 } PAGE 6 0F 85 1 TITLE: OFF-SITE DOSE CALCULATIONS UNITS l' AND 2 ej = The ratio of an individual discharge "jth" pathway flow rate to the sum total of.all individual undiluted pathway flow rates.
- c. High Alarm Set Point (HASP) Determinations (for Rad Monitors).
High Alarm Set Points are detemined from the expressions in this section. These expressions enable determination of the appropriate maximum alarm setpoint for each liquid effluent pathway (i.e., liquid radwaste system, steam generator blowdown and turbine building sump effluents) conservatively taking into
'- account not only existing and concurrent discharges, but also the .'
improbable discharge of an imaginary batch resembling the RCS.
. The High Alarm Set Points are designed such that the combined total C/MPC at the point of entry into the environment (ocean in this case) will never exceed unity. ,
Each of the independent liquid effluent pathways to the comon entry point to the environment (namely at "outfall"), are treated basically the same. There are four separate entities considered in the HASP determinations all of which introduce realistic i conservatism. First, there is the effect of concurrent releases from the other possible independent liquid effluent sources. This is manifested by the so-called " dilution flowrate reduction tem". AF, and is addressed for each separate monitor / release pathway in Appendix 1. Second using this along with the actual release per pre-releaseanalysig,(alrpadyinprogressorscheduled)thereis yielded the term, which is assembled so j j
" astoreducethe"1"(unity)ofthemax.allowedhatthe outfall (ocean). Third, this remainder, namely, 1-j , is then allotted to an imaginary release from the most conservative of possible sources, namely one that is scaled in the same isotopic mix proportions as a recent RCS sampling which has been decayed 24 hours (with exception that H3 is not scaled). Also, since all liquid effluent radiation monitors are only gross gama sensitive, then all i
X006923a.08 61 l i
$ 1 I
l l .
. 4 l
1 DIABLO CANYON POWER PLANT NUMER CAP A-8 i REVISION 5 i PAGE 7 0F 85 i TITLE: OFF-SITEt0SE CALCULATIONS ) UNITS 1 AND 2 ) i non-gansna concc,trations must be scaled according to their gamma counterparts 1. the same mix. Lastly, and very important, is the 1 fact that an a ncertainty factor (called "I&C uncertainty f actor") ' from the mon'cor's manufacturer specifications is conservatively applied to the final calculated HASP value. ! Below are the final expressions resulting from tFe deviations. First, some useful symbols and definitions that were used and are needed are as follows: ' Fc = Main or . Auxiliary seawater flow rate (in gpm). l F= fc + E fj, the total dilution water flow rate (in gpm). j In reality Fc is always FjandanyconcurrentsumofFj's,soh l for all practical engineering purposes (i.e., HASPS, pre-release I calculations, dose projections, etc.) one can approximate F :: F c henceforth. ! Liquid effluent flowrate of , jth,, source prior to { l Fj = dilution with Fc (in gpm). J Cj = Total radionuclides concentration in the liquid effluent of "jth" source proposed for release or actually in j j ! progress. Here Cj = I C4 where subscript "i' j i identifies the "ith" isotope per pre-release analysis l (all Cj's, jC 's are j in pCi/ml)
~
, l P MPCj = Unrestricted area total MPC for water in the "j"th effluent source (in pCi/ml). l I dC 3 i Here, MPCj = I jC i i WPCj OR l d fi h -1 dC j i NPCj={[I MPCj with 7 i= Cj 6Fj = The effective " dilution flowrate reduction term" due to other liquid discharges potentially occurring at the same time (see Appendix 1). X006923a.08 71 s
DIABLO CANYON POWER PLANT NUEER CAP A-8 REVISION 5 PAGE 8 0F 85 TITLE: OFF-SITE.. DOSE CALCULATIONS UNITS 1 AND 2 Subscript "j" refers to the "jth" release source and takes on values b. 1, 2, 3, 4, 5 whence, i b, denotes any one of the following batch tanks EDR(2), 3) FDR(2),CDT(2),WECT(2),SRRT(2),LHST(2). ! 1 1, denotes Unit l's steam generator blowdown tank 2, denotes Unit 2's steam generator blowdown tank 3 denotes the Oily Water Separator Reservoir . portion of the turbine building sump ' 4, denotes Unit l's Cond. Demin. Regen. Sys. Waste 7-Transfer Discharge 5, denotes Unit 2's Cond. Demin. Regen. Sys. Waste Transfer Discharge
- 1) Liquid Radwaste (LRW) system batch releases and the radiation monitor RE-18 (subscript "b" applies here).
h. C C
\
F-AF}- b b H3 1 y k3g ,\ F3 / MPCb MPCH3 . HASPi g(calc) = BKGDi g + (2) RCS 1 Cg I . 3 RCS ' ' C S H3 TPCg RO MPC Y Y r
- where = RCS ' [ RCSYi 'h ~1 MPC =
l{MPCj l Y ( ) p RCS -A j(1 day) RCS ' Ce i , (i = gamas only) 7 yi RCSC'- T RCS - A j (1 day) (see footnote
- below) 1 RCSC ' = I C1e l Y i / H3 l 1/8 t
" The RCS sample used for the set RCS Cj in this analysis is the one (from I either Unit 1 or 2 that is selected and tagged for this purpose by C&RP Engineer. The choice is based on it being most representative of the Current trcnc on RCS samples (isotopically) and being replete with the most isotopes i seen well above L.L,0. The values generated from this sample will prevail in all HASP calculations every 3 months unless otherwise dictated by the C&RP Engineer.
X006923a.08 81
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DIABLO CANYON POWER PLANT NUPEER CAP A-8 l REVISION 5 PAGE 9 Of 85 TITLE: OFF-SITE DOSE CALCULATIONS
- ~
UNITS 1 AND 2 S(subscript) indicates the isotopes, Sr 90/Y90, Sr 89 and any other non-gamma emitter (except H3). 18 RCS - y 3g = k I kj y fj' (kj's are supplied from CAP 0-19) i I Lastly, from HASP i g (calc) a usable high alarm set point is needed for the actual setting or comparing with what is already-physically on the instrument (rad monitor) itself. This is .' called projected HASP 3s and takes into account (as said earlier) e the 1&C uncertainty factor correction. It is given as:
- . (logio HASP 3 g(calc) - 0.3) proj. HASP3 s < 10 and must be entered on the release permit as called for in CAP A-5.
All of the above is performed automatically by the computer software per each pre-release analysis. The software also calculates a projerted reading of the radiation monitor vis-a.'vis the Cj and kj. Generally if the proj. HASPts is setting (from previous releases) greater then nothanaction theisexisting taken. That is, Operations and I&C do not have to change the HASP 3g on the monitor unless the projected reading calculation shows that, although less than proj. HASP i g, it is yet larger than the existing HASP 38 In this case the HASPja should be changed y upward to the proj. HASP 3s so the release can be legally
- discharged. On.the other hand should the proj. HASP3 be less than the existing HASP 38, then the release cannot be ischarged until the HASP 3s is . changed .to the proj. HASP 38 >
- 2) Steam generator blowdown tank liquid discharges and the radiation monitor RE-23 for both units (subscripts "1" and "2" apply here).
" F-aF 3 C C
, 3 ,
H3 8 y k23 f t MPC 3 MPCH3 . HASPy3(calc) = 2 BKGD23 + (3) RCS C 1 E 8+ 1 RCS ' B / H3 MPCg RCS C MPC Y Y I X006923a.08 91 l s
1 DIABLO CMYON POWER PLMT NUMER CAP A-8 REVISION 5 TITLE: OFF-SITE
- DOSE CALCULATIONS PAGE 10 0F 85 l
UNITS 1 MD 2 l AND (for Unit 2) C C
'f-af } _
, p 2 . H3 8 y k23 F
\ 2 / MPC 2 MPCH3 .
HASP 23(calc) = 2BKGDy3 + l RCS (4) j 1 C 1 I g. i l RCS C
' 8 / H3 Mg RCS MPC Y Y As in 1) a usable high alarm setpoint must be prepared from this final calculated value. Again this consists of applying the I&C instrument uncertainty factor. !
This-instrument correction f actor for RE-23, as ~ supplied by the manufacturer, is simply the following product: proj. 2(8) HASP 23 = 0.7 8 ( 8 } HASP 23(calc) This, of course, is entered on the release permit as l called for in CAP A-5. Also as in 1), these calculations are performed by the computer software per each pre-release analysis alo^g with a projected rad monitor reading (from the 3(8)Cj 's and 88 k1 's). And I
~
here as well, the same discipline as in 1) is followed, namely reset the HASP if the projected is lower than the existing, otherwise do nothing unless the existing > is below what the actual release may cause the rad monitof~to read, in which case reset it to the projected. 3} Oily water separator discharge and the radiation monitorRE-3(subscript"3"applieshere). F-AF},3 C 3 , C H3 k *g F y3 3 / MPC 3 MPCH3
- HASP 3 (calc) = BXGD3+
(5) RCS C 1 I p i RCS 8 H3 MPCg RCS C MPC Y Y X006923a.08 101 l
DIABLO CANYON PCMER PLANT NUM ER CAP A-8 REVISION 5 PAGE 11 0F 85 TITLE: OFF-SITE DOSE CALCULATIONS
.- UNITS 1 AND 2 Here, as in 1), a projected HASP 3 is formed as:
Proj. HASP 3 = 10 This is the I&C uncertainty f actor correction. This projected HASP is then entered as called for in CAP A-5 on release permlts. Also, the same discipline for resetting, as seen in 1) and 2) above, applies here for RE-3.
- 4) ~ Condensate demineralized regenerant system waste transfer. '
, discharges for Unit 1 and 2 and. radiation monitors RE-16 for both ; units (subscripts "4" and "5" apply here).
RCS ~ 3 , C, , C H3~ h y k16 , CF-of f4 MPC 4 MPCH3 .
~
8 HASP 16(calc) = 28KGD16 + (6) RCS 1 I C
- g. 1 RC$ ' 8 H3 MPCg RCS C MPC Y Y AND
* ~
y 3 C 5 C H3
~
y k16 , F-AF f 5 / M} ~ W MPCH3 , 8 HASP 16(calc) = 28KGD16 + (I) RCS RCS 8 H RCS C MPC
. Y Y Here, as above, one performs the I&C uncertainty factor correction to yield a projected HASP and then enters this on the release form per CAP A-5 along with the same discipline on resetting as for RE-18, 3, and 23.
X006923a.08 111
- - _ - _ - - - - - - - - - - - _ _ _ _ _ _ - . - _ _ . - - - - - - - _ _ - - - - - l
DIABLO CANYON POWER PLANT NUPEER CAP A-8 REVISION 5 PAGE 12 0F 85 TITLE: OFF-SITE ~ DOSE CALCULATIONS UNITS 1 AND 2
- d. Dose Projection (T.S. 4.11.1.3.1 and T.S. 4.11.1.3.3)
Dose projections for the categories of calculated total body exposure and organ exposure are recorded at least once per 31 days. The period over which projections are made is 31 days. The calculations are also made prior to each release to satisfy T.S. 4.11.1.3.3 The purpose of this is to determine if appropriate treatment of liquid radioactive materials in relation to maintaining releases "as low as , reasonably achievable", is necessary. Projections will in any case be recorded on the last working day of each month with attention to the Technical Specification frequency requirement contained in Section 4.11.1.3.1. The projected dose is calculated by application of equation (8) below.~ The following guidance of default flowrates is provided, where appropriate when using equation (8). i i
- 1) Maximum Rated Flowrates (for default use) i a) Chemical Drain Tanks (26 gpm).
b) LaundryWasteTanks(13gpm). c) Floor Drain Receiver Tanks (35 gpm). d) Waste Concentrator Condensate Tanks (60 gpm). e) Equipment Drain Receiver Tanks (36 gpm). t f) Steam Generator Blowdown, both-units, (150 gpm). g) Spent Regenerant Receiver Tanks (70 gpm). h) Oily Water Separator (Turbine Building Sump) (100 gpm).
- 1) Condensate Demin. Regen. Sys. Waste Transfer Discharge Line, Unit 1. (Max 240 gpm).
j) Condensate Demin. Regen. Sys. Waste Transfer Discharge Line, Unit 2, (Max 240 gpm). X006923a.08 121 s
)
DIADLO CANYON POWER PLANT NUEER CAP A-8 REVISION 5 PAGE 13 0F 85 TITLE: OFF-SITE DOSE CALCULATIONS 1
- ~
UNITS 1 AND 2 Using the form of equation (1), define ; j (0.1.2)d t E Dose to organ "T" by proposed 'jth' release from either I both units in comon "(0)", unit "(1)" or unit "(2)" using pre-release sample analysis for C y ; along with rated s flowrate for pump in stream of 'jtn* release (namely Fj), and i maximum time, or Vj = Fj Atj (max) Atj)(max) envisioned Vj = maximum for release capacity period (with of tank for i That is, {
'jth' release. . j
. 1 J' . n(j) f (0.1,2) t i* id 300 i=1 g
HeretheF(j)dependson}hg, F (j) at the time of the j circ.waterflowratetobeused e discharge j With Dy defined as the total dose to organ t covering all the "m" (postho,3,$easesoccuringinthepreviousmonthof"T"daysand re t defined as the total dose delivered to organ t by all releases o(0,1,2)d ccurring for the "t" days of the present month, one has the definition of the 31 day { dose projection as: 31 day pm j' (0,1,2)D, + (0,1,2)d , + (0,1,2)dz (0.1.2)Dr= 31 (8) T + t
- 2. Gaseous Effluents
?
In view of the more instantaneous impact of gaseous releases, a variety of calculational disciplines is necessitated. Each calculational method p (herein described in detail) is dedicated wholly to a specific Technical 4 Specification or purpose and consequently must be totally comprehensive
~ toward that goal even though some of the equations and their constituents appear repeated or very similar.
~
- a. Noble gases (exists as a unique pathway dose and applies equally to all age groups when tissue doses are calculated).
- 1) Release rate limit of Noble Gases (Tech. Spec. 3.11.2.1.). This discipline is primarily used in determining gaseous effluent rad monitor high alarm setpoints and pre-batch release decision criteria. The release rate limit for the noble gases is determined in accordance with the following expressions:
X006923a.08 131
DIABLO CANf0N POWER PLANT NUEER CAP A-8 REVISION 5 TITLE: OFF-SITE TOSE CALCULATIONS PAGE 14 Of 85 UNITS 1 AND 2 n . I (Kj) (X/Qj) (Qi) 3 500 mrem /yr (9) 1=1 , n . I (L i + 1.1M 1) (X/Q) (Qj) 23000 mrem /yr (10) i=1 e where; e i Kj = The total body dose factor due to gamma emissions for each identified noble gas radionuclides, in mrem /yr per pC1/m 3 (from Table 2). Lj = The skin dose factor due to beta emissions for each identified noble gas radionuclides, in mrem /yr per pCi/m8 (from Table 2). ( Mt = The air dose factor due to gamma emissions for each l identified 5 noble gas radionuclides, in mrad /yr per pC1/m (from Table 2). Unit conversions constant of 1.1 mrem / mrad converts air dose to skin dose. (X/Q)= The " controlling"I historical five year running average8meteorological diffusion dispersing factor, in sec/m . This is almost always the highest ", amongst the past five year running averages of hourly X/Q's for the candidate dose recipient locations in any land sector area-at or beyond the unrestricted area boundary (See Table 6). It is based on the five years > of data just previous to the current year but always updated each calendar year (by dropping the fif th year back and adding the current year's data - See Table 5A). X/Q's used here are from the Gaussian plume model
. (Reg. Guide 1.111), in sy m#
1 See the explanation on controlling in section 2.c. i x006923a.08 141 i
DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 5 TITLE: OFF-SITE DOSE CALCULATIONS PAGE 15 0F 85
~ -
UNITS 1 AND 2 Qj = The release rate u refionuclide 1, in gaseous effluents from all re wase points at the site, in pCi/sec. This is generated from radiochemical analyses and effluent rad monitor scaling data plus flow rates (plant vent, etc.). See discussion following Qj below.
- 2) Air dose in unrestricted areas due to noble gases (T.S. 3.11.2.2 and T.S. 3.11.2.4).
The air dose in unrestricted areas due to noble gases released in' gaseous effluents shall be calculated in accordance with the following expressions: Day = 3.17E-8 I n Mi l(X/Q)Qj) (11) h i=1 n _ Da8 = 3.17E-B I Nj [(X/Q)Qjj (12) i=1 where: Day = The set of air doses due to gama emissions for all identified noble gas radionuclides, in mrad, calculated for each of the site boundary center-of-sector locations (land sector) or any T "other candidate hypothetical individual. dose
' recipient in the unrestricted area during time at. .
Da8 The set of air doses due to beta emissions for all identified noble gas radionuclides, in arad, calculated for each of the site boundary center-of-sector locations (land sector), or any other candidate hypothetical individual dose recipient in the unrestricted area during time At. ; 3.17E-8 = The reciprocal of the number of seconds in a \ year. X006923a.06 151 i
1 DIABLO CANYON POWER PLANT I NUMER CAP A-8 l REVISION 5 ' TITLE: OFF-SITE-DOSE CALCULATIONS PAGE 16 0F 85 4 UNITS 1 AND 2
=
(X/Q) The " set" of real time hourly average X/Q's for each of the site boundary center-of-sector ! (land) locations or any other candidate hypothetical individual dose recipient location in the unrestricted area (See Table 6). The I first contingency level values to use in the event of Met Tower Data collection failure are the set of X/Q's generated for 2.a.1) above preferably from Table SA. X/Q's used here are 4 1 from the Gaussian plume model (Reg. Guide e 1.111), in s_g m8 Nj = The air dose factor due to beta emission for each identified noble gas radionuclides, in mead /yr per pC1/m 8 (from Table 2). h Atthisjunctionitswelltopointout,thatasidefhom satisfying the Tech. Spec. 3.11.2.2, the gamma air dose of 2.a.2) I will always provide for all noble gases a suitably conservative (approximately + 5%) surrogate to the whole body external tissue dose to individuals. Furthermore, with the exception of the extremely short half-lived noble gases of Kr-88 and Xe-135M. (which in all probability will never dominate the isotopic constituency of any release), indirectly, the beta air dose of 2a.2),with its Tech. Spec. 4.11.2.2 never exceeded, will also ' (vis-a-vis Tech. Spec. 4.11.2.1.1), ensure a safe surrogate for the skin dose to individuals. At all candidate dose recipient I - locations which are not recognized by the annual land use census
~
as being locations for real individuals (residences, farms, etc.) but Nhere individuals could hypothetically exist (e.g., site boundary), then the gamma and beta air dose calculations can P serve as surrogates to the external whole body and skin tissue doses. 3) External tissue dose to real individuals in unrestricted areas due to noble gases (Tech. Spec. 4.11.4.1 and 6.9.1.6). The whole body and skin doses to real individuals in unrestricted areas due to noble gases released in gaseous effluents shall be calculated in accordance with the following expressions: X006923a.08 161 q' ,
v ,,
', c y \
- t 1 ,N> '),
, e !
# /
! DIABLOCANYONPOWERPLAq NUNCd/ < O P A-8 !
REVISsON 5 j
,5 ? . . .
c PAGE 17 UF 85
/ i VITLE: OFF-SITU DDSE CALCULATICU '
' t >"
[s s p-3 , , r [ UNITS 1 AND 2 l i j ,. - ' 1
-M - -
M j
. . 1
(- _I [
, 'j
.n< '
/_
, t -
Dub .s 3.17E-8 I Kt 1(X/Q)Qil (lla) i=1
/ . ,
.. i t, < - )
n '.
'6 ) .. .
Dst . 3.17E-8 E (Li + 1.Ji43 ) f(X/Q)Qi), (12a)
<,J 11 *
[
.thereq Theset51extenalwholebodykissuedoses
/ ; = '
Dwb
- i -
from ell identifitd noble gas radionuclides in mrem. I calculated io'r ech 6f the candidate real" individual
~, <
~
dose recipients i'n the unrestricted areas during period
, . ' At. ,
, ,! b l =
- l Dsk ' The set of uternal skin doses from all I
.(dentified noble gas radionucl ues, in mrem, calculated i for each of the candidate rea*O individual dose iecipients in the unrestricted area during period At.
J (X/Q) = The set of real time hourly avt,'rage X/Q's for each of the candidate real intividual doce recipient
; , ilocations in the unrestricted Area (e.g., residences, i
f arms, etc. based c's G.c annual land use census). (See i Table 6.) The first contir<gency level values to use in .!
' the event of
- t Tower Data collection failure are the !
set of 17Q7 generated for 2.a.1) above, preferably r from Table SA. X/Q's used here are from the Gaussian ! r ---plume model (Reg. Guide 1.111). It is noteworthy here to also mentim that the X/Q's calcule.ted here are for real individusis as opposed-to those hypothetical y individssis of P.a.2) and include all off-center-line j (from plus* or wind direction) contributions using y 12cy as the consideration cut-off criteria.in sec m8 t I I l l X006923a.08 171 , k
DIABLO CANYON POWER PLANT NUE ER CAP A-8 REVISION 5 PAGE 18 0F 85 TITLE: OFF-SITE DOSE CALCULATIONS UNITS 1 AND 2 i i Qj = The average release of noble gas radionuclides in pCi over time period At. This entity is a product of a ~ release rate 61 and a release time, At. Normally At = 1 hour (or less) so as to be compatible with the , computer's hour-by-hour "real time" dose calculation which depen (s on a matching hourly average X/Q from the Het Data. Qt comes from the product of a release vent's concentration, C1 , and flowrate F (plant vent and/or steam generator blowdown tank vent) infomation , during At. Cj results from a detailed grab sample . j
. isotopic analysis as scaled by ratios of the attendant
- I effluent rad monitor's gross readings.for the periods '
I
~
At that occur out of sequence or in between the grab , sampling times. j Should the plant vent grab samples indicate less than h LLO or the rad monitors fall to register detection whef - aknownbatchreleaseit.inprogress(e.g., containment purge or G.D.T. release), however short At, then if a more measurable end reliable C,1 (directly sampled from I the batch sourcc) can be made and scaled by batch-to-vent flowrate ratios to give the appropriate Cj, then it should be pursued. Should the release's at be less than 1 hour and within the hourly clock time that X/Q represents, then the X/Q for that hour will l prevail for At's period. Any At greater than 1 hour or with any other span (< 1 hr.) that overlaps the regular hourly clock time that X/Q represents (wherein X/Q changes but Cj is constant), then separate fractioning r of the At should occur to yield the correspondingly j a different Qj that coincides with the X/Q changes. P
- b. Radiciodines, radioactive materials in particulate form and radionuclides other than noble gases.
4 l X006923a.08 181 1
. DIABLO CANYON POWER PLANT NUMEP. CAP A-8 REVISION 5 PAGE 19 0F 85 TITLE: OFF-SITE DOSE CALCULATIONS 1 AND 2 UNITS l
In contrast to the calculational methodology just seen in 2.a. for the external doses (and dose rates) from noble gases, the methods utilized here are quite different and more complex with the exception of the
" ground plane" deposition pathway dose, which is also an external dose and similar to the noble gases (but considers only the whole body and not the skin). Doses (and dose rates) other than " ground plane",
delivered here are strictly internal and are segregated according to i intake pathway as well as age group. ' Furthermore, while noble gases i (and " ground. plane" iodines, particulate, and tritium - I.P.T.)- ! essentially dose only the two organs, namely whole body and skin, here. I seven ma a-namely? bone, jor radiation sensitive liver, total body,organs of kidney, thyroid, the bodylung are and considered, GI-LLI
- tract. The internal intake pathways are four (aside from the external
- - ground plane mentioned) in number, with one being inhalation, which is X/Q (diffusion dispersing factor) dependent and the.other three being food ingestion pathways, which are D/Q (deposition dispersing factor) dependent (asisgroundplane). The three food ingestion pathways in
- this case are, namely:
foliage-to-cow-to-milk-to-human; foliage-to-animal-to-meat-to-human; , and vegetable-to-human. ' Finally, the four age groups considered here are respectively: infant, child, teen and adult (see Reg. Guide 1.109 and NUREG 0133). The infant is subjected to only the inhalation, cow-milk and ground ! plane pathways by the assumption of not being old enough to consume l meats and vegetables. i for each of the radionuclides, intake pathways, age groups, and organs ( affected, their dose (and dose rate) factors are given in Tables 3A through 3P, and are to be used in the equations which follow below. s P
~
X006923a.08 191 i
DIABLO CANYON POWER PLMT NUEER CAP A-8 REVISION 5 PAGE 20 0F 85 TITLE: OFF-SITE DOSE CALCULATIONS UNITS 1 MD 2 , To add to the complexity and in deference to the hour-by-hour "real ! time" pace set by the noble gas chronology of dose archiving, the real ' time matching X/Q's and 0/Q's used here must be recalled, in
" flash-back" f ashion, from temporary storage by the computer. This is necessary since at the present time, and until an upgrading on the I gaseous effluent iodine and particulate rad monitoring system occurs, l the existing effluent rad monitors, are not being used to scale with i their ratio of readings the in between hour-by-hour periods for knowledge on isotopic concentrations in the release quantities (as.is provided from the noble gas grab sampling and analysis). Tritium a 1 analysis plus gama isotopic analyses on iodine.ane particulate are l
- normally conducted on a week-to-week basis and dtily (at best) from spot grab sampling or composite sampling. Consequently, the Cj's l which generate the j'sandTj'susedintheexpressionsbelow,must ,
be fractionated or pro-rated according to the At's when F (vent flowrate), or X/Q, (or 0/Q) change. Certainly the Strontium's (Sr-90 " h and Sr-89) mandate this with their quarterly composite sampling and analysis period. Additionally, this f acilitates dose projection requirements and their calculations. Since a " previous" period's l pre-releaseanalysisforsomespecificDj'scanbesubstitutedwith the current X/Q's (or D/Q's) and later purged with the aid of the stored knowledge on these X/Q's (or D/Q's) until the post-release analysis data becomes available.
- 1) Release rate limit (T.S. 3.11.2.1).
This discipline is primarily used in determining rad monitor high alarm setpoints and batch pre-release decision criteria. The 7
- release rate limit for all radioiodines and radioactive materials u in particulate form and radionuclides other than noble gases is determined in accordance with the following expression:
n (p)(o) I i=1(a)Pj [E Qj] ,<1500 mrem /yr (13) X006923a.08 201 i
DIABLO CANYON POWER PLANT NUEER CAP A-8 REVISION 5 TITLE: OFF-SITE DOSE CALCULATIONS PAGE 21 0F 85 UNITS 1 AND 2 where: (p) (o) P = The dose factor for gaseous (a) j radionuclides (trailing subscript "1") other than noble gases. The dose factors are based on organ (trailing superscript "(o)", age group (leading subscript "(a)") and pathway (leading superscript "(p)"). For the inhalation inh (o) _ pathway, P ; the units are
., (a) j in { mrem /yr per pCi/m8 ). For the ground gp plane pathway, Pj; the cow-milk ~
cm (o) pathway, P ; the meat-animal I (a) t ma (o) { pathway . P ; and vegetable pathway (a) j l I y (o) P ; the units are in lm -mrem8
/yr (a) t I
" per pC1/m*]. Refer to Tables 3A through 3N and Table 3P. 4 i
U = The " controlling : historical five year running average meteorological dispersion factor for the : candidate dose recipient locations in any land !
. sector at or beyond.the unrestricted area boundary. )
9=X/Q[yjfortheinhalationpathway. (refer to Table SA.) I
' See the explanation on controlling in 2.c. which follows. '
i X006923a.08 211
1 l 1 DIABLO CANYON POWER PLANT NUMER CAP A-8 REVISION 5 TITLE: OFF-SITC DOSE CALCULATIONS PAGE 22 0F 85 UNITS 1 AND 2
\
l U = DM (m*8) for any food and ground j plane pathway (refer to Table 58.) (See also definition in 2.b.2) below) The same 1 ic for obtaining this average (both X/Q and / 15 that is explained in 2.a.1)'s definition on the X/Q for noble gases there. m Remember the X/Q values used here, in 2a.1), and seen in Table 5A come from the five year running average of hour-by-hour X/Q's archived for each of the candidate 6). For dose recipient all X/Q's generating locations the average X/Q (See at Tableh I real individual dose recipient location (e.g.,
- residence, farm,etc.),includedarethe i off-center-line contributions mentioned in 2.a.3). j
=
Qi See definition under 2.a.1).
- 2) Doses in the unrestricted are due to radiciodines, radioactive materials in particulate fom and radioactive materials other l than noble gases (T.S. 3.11.2.3, T.S. 3.11.2.4, T.S. 4.11.4.1, j and T.S. 6.9.1.6). i 1
i The dose to an individual from radiciodines, radioactive t
- materials in particulate form and radioactive materials other '
~ than noble gases shall be calculated.in accordance with the following expression:
(p)(o) n (p).(o) ) D = 3.17E-8 I R W Qi (14) (a) i=1 (a) g ' l : l l l X006923a.08 221
DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 5 PAGE 23 0F 85 j TITLE: OFF-SITE DOSE CALCULATIONS l UNITS 1 AND 2 I
]
)
where: (p) (o)
= The dose factor for each identified gaseous (a)Ri radionuclides (trailing subscript "i")
1 L other than noble gases. The dose factors i' here are identical to the "Pj" dose factors given in the definition 2.b.1). That is (p) (o) (p) (o) . P E R i (a) I (a) I . m
, except for the " ground plane" pathway, / . where .
9PPj / 9PRj . Refer to Tables 3A through 1
~
3N and Table 30. The units here are Imrem/yr per pCi/m 81 or Im2 mrem /yr per pCi/sec) W = The " set" of "real time" hourly average dispersion factors for all of the candidate dose recipient locations in the unrestricted area. W .
= X/Q [sec/m8 ] diffusion dispersion
! factor for the inhalation pathway (Refer to definition in 2.a.2) and i 2.a.3), also see 2.b.1) above).
~
l
.{
l W = D/Q [m-81. deposition dispersion l factor for any food and ground plane P pathway. l l i l l l X006923a.08 231 l
DIABLO CANYON POWER PLANT NUEER CAP A-8 REVISION 5 TITLE: OFF-SITE DOSE CALCULATIONS PAGE 24 0F 85 UNITS 1 AND 2 , 1 The D/Q values are extracted from Fig. 6. Reg. Guide 1.111 for each candidate dose recipient location's downwind distance from the plant. The only other variables for dependency in this are wind direction and location's arc length normal to the plant's direction. For site boundary and other hypothetical or virtual individual locations this latter is simply the sector's (22)*) arc length at its particular distance. For real individual locations (e.g., ' residences and f arms) the arc length is, arbitrarily chosen as, 1) times the max property width normal to the plant's direction. This arc also determines the cut off for the 9 frequency distribution of wind directions to that particular l l 1 7 real-individual dose recipient location. ! Qj = The average release of radionuclides, radioactive airborne h - particulate, and gaseous radionuclides other than noble ~ gases in the gaseous effluents (in pCij over time period at. ; This entity is structured similarly to the definition in 2.a.2) and 2.a.3). The principle exception being, as I explained above in 2.b., is that, unlike for the noble ' (' gases, these radionuclides releases do not use the attendant rad monitor ratio of readings (i.e. real time to sample time) to scale the Cj values for periods of At in between sampling and analysis. As explained above at 2.b., this makes for a preferred lengthy prorating or fractionation on the Cj's, which are assumed constant over the much shorter hour-by-hour At's or the At's when F (vent flowrate) or W (dispersion factor) is subject to a change. The week-to-week, or month-to-month, or quarter-to-quarter (in r case of the strontiums) composite analyses mandate this. 6 (p) (o) (a)D = The set of internal doses (plus the lone external dose from , the " ground plane" pathway) per pathway, per age group, per principal organ (of that age group) from all identified non-noble gas airborne radionuclides, in mrem, calculated
- for each of the candidate individual (real, hypothetical, or virtual - See 2.c. below) dose recipients in the unrestricted area during period At.
X006923a.08 241 i
~ ~ ~ ' ' ' ' ' '
' ' '~~ '
- ' ~ ' ' ' ' '~
i DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 5 PAGE 25 0F 85 TITLE: OFF-SITE DOSE CALCULATIONS UNITS 1 AND 2 ' I
- c. Gaseous effluents' candidate dose recipients (and locations).
Much reference in 2.a. and 2.b. above, was made to the so called
" candidate dose recipient" locations. These are particular site specific geographical locations in land areas of the unrestricted area between (or at) the site boundary and a 5 mile circular perimeter ,
l around the plant site. Particular to these locations are positions l where a maximum exposed individual might in all probability exist ' without benefit of licensee control. These are labeled candidate dose recipients simply because of the higher probability and the fact that a I the random wind with its meteorological dispersion makes the final *- ' en decision on who, when, and how much gets dosed. For obvious reasons, L the site boundary provides part of this set of locations. However, the Annual Land Use Census dictates the ultimate locations. Here an extensive survey, locates the residences, farms and other institution where real individuals may exist along with information on their
- l occupation f actors, property dimensions, and potential pathways for l l doses. .
1 Conveniently the areas for these locations are divided into the 22j' land sectors between site boundary and the 5 mile outer limit. Finally, reasonableness or common sense probability with implicit guiding by NUREG 0543 tempers the final selection of " candidates". For example, the individual that wanders to the site boundary daily from a nearby town only to inhale and be externally exposed is unlikely to also drink the milk from the imaginary cows at 5 miles. , Similarly the child living at 4j miles in the N sector while inhaling j and simultaneously ingesting cattle meat on his property probably does i g, not eat vegetables grown on the farm in the ESE sector, and so on. l ' From the land use census, only the closest-to-the-plant residence per sector was selected. Since information as to the ages of the t { residents (or their visiting rela ives) was not garnered, then ; conservatively all age groups must be assumed to live year-round at l the residences. i Furthe'rmore, specific to the site the following is assumed to exist: 1 l
\
l l X006923a.08 251 s
DIABLO CANYON POWER PLANT NUM ER CAP A-8 REVISJON 5 TITLE: OFF-SITl; 00SE CALCULATIONS PAGE 26 0F 85 UNITS 1 AND 2
- 1) Meat cattle for marketing are assumed to be able to graze right up to site boundary in all land sectors. This generates the newly defined " degraded" hierarchy of dose recipients called the
" virtual" individual. Degraded in the sense that the only, but most probable, dose received is via the meat ingestion pathway (for all age groups except infants).
- 2) The vegetable farm in the ESE sector while possessing virtual individuals of the type defined in 2.c.4), above, (but for vegetables in place of meat), do indeed have real individuals.
These are migrant farm workers who in all probability spend 12 g e hours per work day there with their entire family and more than 1 L likely take home vegetables grown there and cattle meat from there. For this reason, this is treated conservatively as a real l individual residence for all age groups possessing meat animals and a vegetable garden.
^
- 3) While each residence is assumed to have its meat animals or vegetable gardens confined within their property boundary the one l exception is the residence in the NNW sector at lj miles where I its meat animals can graze right up to the site boundary in both the N and NNW sectors.
- 4) At the site boundary another form of " degraded" hierarcny of dose recipients is now defined, namely the " hypothetical" individual.
Degraded here in the sense that the land use census does not recognize this individual as a bonafide real individual residing there with property to enclose meat animals, vegetable gardens, and such. Reasonableness assumes however that this type of 7' individual could wander daily to the site boundary and receive the external doses from the nobles along with ground plane external doses from the non-nobles and only the inhalation 1 internal dose from the non-nobles (applies to all age groups). > Here the gr.mma air and beta air doses serve as a surrogate to the noble external doses.
~
l I 1 l l X006923a.08 261
R DIABLO CANYON POWER PLANT NUEER CAP A-8 REVISION 5 PAGE 27 0F 85 TITLE: OFF-SITE DOSE CALCULATIONS
.- UNITS 1 AND 2
- 5) Thus far the land use census indicates no milk cows within the 5 mile perimeter. However, the utility has conservatively assumed .
imaginary milk cows can exist at or beyond 5 miles in all land sectors for which the milk can be marketed for consumption. This then generates the third virtual individual as in 2.c.1) or 2.c.2), above, but constrained this time to only the cow-milk ) ingestion pathway for all age groups (generally the infant { predominates). 1
- 6) Finally for all categories of individual dose recipients described above in 2.c.1) through 2.c.5), for their respective f locations, an occupational factor of one "1" is assumed with 7 exception of the real. individuals (all age groups) at the vegetable f arm in the ESE sector, namely in 2.c.2), and only in the case of the noble gas, ground plane and inhalation pathways (non-noble) there. Inthatexception,fortheexternalnoblegeh (whole body and skin) dose along with the non-noble ground plane
- and internal non-noble . inhalation pathway doses there, a one half (0.5)occupancyfactorisassumed.
[ In usage of the equations of 2.a. and more notably 2.b., when I computing an individual's dose (or dose rate), it only makes sense to ) ultimately sum up over the individual's (any age group) dose ' pathways, { l where pemitted, at each of the candidate dose recipient locations. i It is this summing for a max over these different pathways of doses (i.e., for each age group's organs, etc.) at each location, whether during only a At, daily, weekly, quarterly or annually, that eventually determines the so called controlling candidate (with max dose) and hence " controlling" location in that time period (e.g., site g boundary nobles-in NW sector; or nobles plus non-nobles for the real l a child at residence in E sector because of bone dose; or virtual-cow-milk-infant at 5 miles in NNW sector because of thyroid oose;etc.). For reason that the meteorological conditions may change over or in between any At, but most certainly between any week, month or quarter, then these summations of dose (or dose rate) entities dictate that any of the candidate dose recipient locations can at sometime, (certainly, some month or some quarter) be the " controlling" (max dosed) location. Table 8 indicates the existing land-use-census-based selection'of candidate dose recipient locations i and is subject to change anytime but is usually determined annually. l 1 i i X006923a.08 271 s
]1 DIABLO CMYON POWER PLMT NUMBER CAP A-8 REVISION 5 PAGE 28 Of 85 TITLE: Off-SITE DOSE CALCULATIONS UNITS 1 MD 2
- d. Gaseous ef fluents contingency levels for "real-time" calculation of doses (and dose rates).
Normally the dose (and dose rate) information for all candidate dose recipients shall be calcul6ted hour-by-hour, twenty-four hours per day, 365 days per year using the equations of 2.a. and 2.b. on the data gathered from the radiochemical analyses, rad monitors and met tower's computer and all perfomed on the HP 1000. In the event of temporary unavailability of certain systems feeding this " train", certain " default" plans of calculation operation must be pursued. Most important of these concerns the met tower and HP-1000. 9 7
- 1) Met tower data ("real-time" hourly averages) - Unavailability.
Here the computer software is instructed to use the historical l i average met data from Tables 5. h j
- 2) HP-1003 - Unavailability I Here the HP 9845 computer is instructed to take over with the use
( of the data from Tables 4A and 48. Since the factors for use in 3 the equations of 2.a. (Table 2) are never the complexity of those used in 2.b., Tables 4A and 48 represent the conservative i degeneration of the dose factors of Tables 3A to 3P into the single' columns of a " super" age group " critical" organ factor per pathway per nuclide. These were selected out of Tables 3A to 3P as being the maximum factor out of the age groups and in turn amongst the organs for each pathway and nuclide, r 3) Het Tower data and-HP-1000 - Unavailability Here contir.gency level 2.d.1) and 2.d.2) are jointly pursued. p i I X006923a.08 281 l 1 1
DIABLO CANYON POWER PLANT NUMER CAP A-8 REVISION 5 ) PAGE '29 0F 85 TITLE: 1)FF-SITE TOSE CALCULATIONS UNITS 1 AND 2 i l
- 4) HP 1000 and HP 9845 - unavailability Calculations by hand where possible .will be conducted on the most significant nuclides reported from radiochemical analyses along with'the use of met data from Tables SA and 5B, and dose factors from Table 2 and Tables 4A and 48. Use of forms 69-10387 and 69-10388 from CAP A-6 will be used in such situations (See i CAP A-6). l
- e. Gaseous effluents, alam setpoint determinations ,
i
- 1) Plant vent noble gas monitor, RE-14A and RE-148 The channel which high alarm corresponds-to is to be pemissible the maximum set no higher dosethan a count rate at the rate b
" controlling" locations, usually the boundary of the restricted ~
area (site boundary), which is 500 mrem /yr (250 mrem /yr-2 plant' operator) for total body exposure and 3000 mrem /yr (1500 mrem /yr-2 plant operator) for skin exposure. Each unit constitutes a release source, and_each is therefore aliotted one-half the limiting condition for annual dose. 8 To calculate the high alam set' point, it is necessary to I establish the release rate limit, and then working " backwards", calculate the corresponding max concentration in the plant vent. Once this concentration is known, the corresponding count rate can be calculated using the channel sensitivity value or kj values relating count rate to isotopic activity concentration. [ First, the release rate limit is detemined using equations (9) i and (10), the more restrictive release rate (of the two) being l used for establishing the alarm point. Then calculate the p concentrations corresponding to the limiting release rate using the expression
- Maxf1 ,,
MaxC i= U2F pv (15) 8 The fraction one-half is selected for convenience. Each unit's release may be proportioned differently as long as the site dose max limitations are met. X006923a.08 291 s
OfABLO CANYON POWER PLANT NUEER CAP A-8
. REVISION 5 TITLE: OFF-SIT,E.00SE CALCULATIONS PAGE 30 0F 85 UNITS 1 AND 2 l
where: MaxCi= the max allowable concentration of radionuclides 1, in pCi/mi F py = the flow rate in the plant vent in ft /8 min. 472 = a conversion constant, ml/sec per ft 3/ min. For normal operation, the value used for F 220,000 f t 3/ min (two auxiliary building ex5y can be as high as aust fans and two fuela e handling building exhaust fans in operation) or one half that ' v?lue. The unadjusted high alarm set point is then determined as follows: %- High Alarm Set Point (HASP in cpm) < kRE14 CT + Bkg cpm (16) where: kpgl4 = the pressurt;-drop-corrected
- gross channel sensitivity to typical mixtures, in cpm per l pCi/ml (I kj C 1/CT) l Max CT= the total max allowable concentration of Max noble gas activity, in pCi/ml (I Cj) g-i u
per equation (9) or (10). l P
- Oue to the friction pressure head loss in the long sampling tube plus the drop across the filter paper of the plant vent particulate monitor, (RE-28) in tandem with RE-14, there exists a density reduction in RE-14's measuring chamber. This reduced radioactivity concentration as sampled from the plant vent must necessarily impose a correction to RE-14's reading so as to yield an accurate measure (by RE-14) of what's being released by the plant vent. This pressure drop (between RE-14's chamber and the outside atmosphere is gauged at the chamber and is called AP. The corrected k value for Patm - AP RE-14 is then kRE14 = -
kRE14 (uncorrected). P atm X006923a.08 301 s i
- l DIABLO CANYON POWER PLANT NUMER- CAP A-8 REVISION 5 PAGE 31 0F 85 TITLE: Off-SITE DOSE CALCULATIONS UNITS 1 AND 2 This entity is expounded upon again in Appendix 2.
Now this final calculated value must have applied to it the so-called I&C uncertainty factor adjustment to compensate for. the statistical bounce and drift of the actual radiation monitor. This is called the projected HASPg4 and is given as 10(I 910 MSP34 - 0.3) as per afg. specs. This then is what is actually set on the monitor.
- 2) Gas decay tank monitor RE-22 9 e
- ,, The high alarm setpoint for RE-22 is determined in similar fashion as for RE-14A and RE-148 except for the pressure correction. The desired condition is to have RE-22 alam (and g thereby trip the release isolation valve (RCV-17) at a release .
rate which is no higher than that required to cause alem of i RE-14A and B given the added concentration of radioactivity from l the gas decay tank to that already in the plant vent. First, detemine the release rate limit on the basis of the "f 's", resulting from the projected release of gas decay tanks, be ng added to the nomal plant vent noble gas activity concentration, using equations (9) and (10). This net result must now be converted to the corresponding concentration in the undiluted pathway by multiplying by the ratio of the plant vent flow rate to the gas decay tank release flow rate (nomally, approximately 31 scfm). This represents the. limiting. Y concentration passing through RE-22, and the high alarm setpoint
' is detemined as similarly prescribed above for RE-14. This entity is also expounded upon again in Appendix 2.
There is no pressure correction here (as with RE-14) since the sampling line is short and there is no filter in between, however the same I&C uncertainty factor correction is applied as with
, RE-14. This then is what's set on the monitor.
~
'r s
l 1 X006923a.08 311 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ . _ _ . . t
DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 5 PAGE 32 0F 85 4 TITLE: OFF-SITE DOSE CALCULATIONS UNITS 1 AND 2
- 3) Steam generator blowdown tank vent monitor, RE-27 The site boundary dose contribution for releases from this i independent pathway during normal operation are expected to be a very small fraction of the dose contribution resulting from releases via the plant vent. For purposes of establishing the high alarm setpoint on RI-27, use as a basis release rates such that the dose contribution ~from this pathway will not exceed one percent of the maximum limits on dose rates due to noble gases, that is, 5 mrem / year to the total body and 30 mrem / year to the skin. For two-unit operation, one-half of these values should be allotted to each unit. 9 L first, determine the release rate limit for typical mixtures.
using equations (9) and (10), but with. the reduced doses I' described above. Next, calculate the corresponding activity l! r* concentration which flows through RE-27. Note that a ~ concentrating effect of gaseous activity occurs in the blowdown tank vent because virtually all of the gaseous activity is carried out by only about one-third of the water mass which had entered the blowdown tank. Use the following expression to j determine the activity concentration flowing through RE-27: Qt
=
Ct (17) # (R)wi where: I r = w Ct the total activity concentration in RE-27, in pCi/ gram Qt = the activity release rate, in pCi/sec I
=
W1 the total steam generator blowdown flow rate
, f rom all steam generators, in grams /sec l R =
the fraction of the blowdown which flashes to (R = 0.32, for most of the time, assuming that the inlet temperature is - 490*F). i l i X006923a.08 321 ; r i
i i 1 DIABLO CANYON POWER PLANT NUM ER CAP A-8 I REVISION 5 PAGE 33 Of 85 TITLE: Off-SITE 10SE CALCULATIONS UNITS 1 AND 2 The high alarm setpoint is established using a similar relationship as described above for RE-14 and RE-22. As with RE-22 there is no pressure correction, however, there is the II.C uncertainty and it is given a little differently as:. ; proj. HASPn { monitor. The =value 0.7 HASPn(for used Ccalc). This t should notthen is what exceed is uCi/ 0.015 set on gram, the considered as dose equivalent I-131, because this is the implied , concentration in the blowdown tank vent when the secondary coolant is at its technical specification limit of 0.10 p/Ci/ gram. 1 dose equivalent I-131. 9 { f. Gaseous effluents dose projections (T.S. 3.11.2.4) Dose projections for the categories of calculated air dose due to I noble gases to the controlling. location and calculated dose to the controlling individual due to.radiciodines, radioactive materials in ~ h particulate form and radionuclides other than noble gases are made at least once per 31 days. Projections will normally be made on the last working day of each month, with attention to the technical ( specification frequency requirement contained in section 4.11.2.4.1. The projected doses are calculated by application of equation (11), (lla), (12), (12a), or (14), as appropriate, using estimated releases from expected releases from Gas Decay Tanks, Containment Purges, and j building ventilation exhaust. j i The projected doses, whether from GOT, containment venting (or purging), and plant vent continuous releases, could contain interim r portions of the calculations (performed by the computer's "real time"
' software package) based on pre-batch release data or a previous periods composite analyses'-data. And, in almost every instance, a scaling is involved by the ratio of 31 days to the number of days in I the current quarter added to the previous quarter all sultiplied by the sum of last quarter's max dose to the max doses accrued and calculated to date thus far this quarter. At any rate, this always ends ug stored in the instantaneous running archive of doses (by computer). These " interim" dose calculations after use for projection l purposes must eventually be purged and replaced with " correct" dose !
portions based on actual days involved i.e. update or post-release- , analysis data on batches, and concurrent data from the composites. l X006923a.08 331 i
DIABLO CMYON POWER PLANT NUMBER CAP-A-8 REVISION 5 PAGE 34 0F 85 TITLE: OFF-SITE DOSE CALCULATIONS UNITS 1 AND 2 '
- 3. Direct Radiation (T.S. 4.11.4.2) !
Direct radiation from the plant site to the unrestricted area is composed of two principal components, namely line-of-site (or primary) radiation and ) sky-shine (or secondary scattered) radiation. For significant distances 1 the latter component becomes quite dominant. i At Diablo Canyon Power Plant, being a P.W.R., turbine building shine (in cetrut to B.W.R.'s) is all but non-existent. Likewise the containment i structures being so thickly shielded, never become the major sources for direct radiation. The most likely candidates for any measurable source of f direct radiation to the unrestricted area are the cask liners and drums e holding the radioactively hot spent resins; filter beds; evaporator sludges; etc., which are slurried with concrete and compacted for high radwaste storage. The high radwaste storage bunkers themselves, although h heavily shielded, for storing these casks, drums, etc., do represent the - only continuc,us low level source of direct radiation. The most probable time for concern in calculating doses or dose rates due to direct radiation is during the preparation and transportation (to the bunkers from the Auxiliary building) of the casks, drums, beds, etc. of radwaste. Two basic assumptions are made in the following expressions used for calculating dose rates and the doses. One, is that, since the nearest unrestricted area (i.e. closest site boundary) location is 800 meters (or greater) away, and the bunker rooms, cask liners, and drums are < 10' or 15' in dimension, then all sources will be assumed point sources. This allows at least two significant figure confidence on dose and dose rate calculations. Secondly the " sky-shine" or scattered radiation is assumed spherical rather than hemispherical about the source. That is the ground is conservatively assumed to be a perfect mirror to the radiation. In that j 3
, which follows the so-called " build-up" factor, B, accounts for the !
sky-shine contribution whereas the I e -F /r term accounts for the line-of-sight contribution. 8 l i X006923a.08 341 s i ______________--_-_--_a
1 i
)
DIABLO CMYON POWER PLMT NUEER CAP A-8 REVISION 5 PAGE 35 0F 85 TITLE: OFF-SIIE 10SE CALCULATIONS j UNITS 1 MD 2 ] (
- a. Dose rate calculations (air dose rate only). l
- 1) When isotopic concentrations of unshielded directly exposed sources are known.
l
- -u r i b(R/hr)=156 I Ci I Ej i 3 p' Bje i Oj !
l 7 i j di aj (18)
~
% l
)
, where* i
~
~
r = distance from source (i.e. open cask, open drum or exposed source) on site to point of interest for i calculatingdoseratesinunrestrictedarea,inmetersh I Cj = number of curies of isotope "i" in source. ! Ejj = gamma energy, in Mev, of j gama decay scheme in the ith isotope h* dj pure number of gamma decays in j th decay scheme per disintegration of the ith isotope fI i 156 = units compatibility constant I p' = existing total gamma attenuation coefficient 0j for air, in meters -2
- a function of Ejj L p' =
existing total gamma absorption coefficient aj . for air, in meters -2 with (Note: Wa
- Da Dair p Ca
- Ophoto elect + Ocompt. abs + Opair prod)
_ - a function of Ejj 1+rpy{1+ sj\ N Bjj = (Ref 7) (19) D a u Sj = existing compton scatteringcoefficient for air in meters a function of Ejj X006923a.08 351
1 DI ABLO CMYON POWER PLMT NUMER CAP A-8 REVISION 5 PAGE 36 0F 85 TITLE: OFF-SITE DOSE CALCULATIONS
, UNITS 1 MD 2 l
l l po = p's + p's (20) T l p' (any subscript) = p (any subscript) (21) [ P = existing press. (atm, mmHg, etc.) T = existing temp. (*R, *K) Po,To= S.T.P. (i.e. 760 m, 273*K etc.) , ! i
, From the curves in Ref. 7 and Ref. 8 the following expressions j were empirica My curve fitted (any subscript). j pa(m-2) = 0.001e [1.34-0.105(in(10E)-1.57) 2 l j (22) 95(m-8) = 0.001e [3.10-0.089(En(10E)+1.89) 2 ] (23) l i
NOTE: (22) and (23) are accurate within 2 10% for j 0.1Mev<E<2.5 Mev. I
- 2) CT the When isotopic concentration, concentrations is known areeffective along with an not known buttotal I (,gama) )
l (external to the source) per disintegration also known, equation- l (18) becomes: b(R/hr)= 156 2 Cr(curies)f(Mev)ud(T)B(I)e (24) r (m) l I en ! 1 pd(I) where: B = 1 + ru (l) 1+ (25) , W$(I) . Here equations (20), (21), (22) and (23) are repeated for I here. X006923a.08 361
. DIABLO CMYON POWER PLMT NUEER CAP A-8 REVISION 5 PAGE 37 0F 85 (
TITLE: Off-SITE DOSE CALCULATIONS UNITS 1 MD 2
- 3) When no isotopic or total concentrations are known, but rather I (gama external) is known plus a up-close survey meter reading (at some closs distanceo r ), i.e., 6(r o) in R/hr, is known. Such is the case for an enclosed source (already in cask, drum, or storage bunker) behind shielding with an effective E (known) in Mev.
(Note: rnr o), then: b(R/hr) =f To \*0(r)o 8(Ge-D o(I)" e 1 (26)'
\r ) \
(NOTE: The buildup factor, 8(ro ) times the h attenuation, e-p'ro , for r (<10 o meter) - 1) where: equations (20), (21), (22), (23) and (25) are (- used here also. ) ( 4) Examples: Example 1. 1 = Cs-137 T = 289* K (16*C or 66*F) j=1 P = 1 atm Et j = 0.662 Mev r = 800 meters F U = 0.9 Ci = 2 curies
.di .
. B calculates to = 13.45 whereas:
e"Ycalculatesto 0.000522 Then: 6 = 7.3E-9 R/hr 1 l X006923a.08 371 s
DIABLO CANYON POWER PLANT MumER CAP A-8 REVISION 5 TITLE: OFF-SITE 1)0SE CALCULATIONS PAGE 38 Of 85 UNITS 1 AND 2 - Example 2. T = 0.662 (Nev) T = 289' P = 1 atm r = 800 meters r o = 1 meter b(r)=2.0R/hr o 8 calculates to = 13.45 and again , e'Y ~ calculates to 0 D00522 Thus: 6=2.19E-8R/hr
- b. Dose Calculation (air dose only). Here we simply calculate the dose rate by equations (18), (24), or (26) and multiply by the recorded time. At. ~
D(R) = b(R/hr)At(hr) (27)
- 1) Continuous At = 1 yr = 365 days = 8760 hrs
- 2) When processing and moving radwaste for storage in the high radwaste storage area, the radwaste foreman's records for this processing and moving time is used for At. Equation (27) is applied and the dose archived and sumed to previeus such doses.
r -
~3)
Example: 2 curies of Cs-137 are lying on ground directly exposed for continuously direct radiation to site boundary 800 meters away. neglecting decay. . 0 ='6.4E-5 Rads = 0.064 stads 0.064 mrems annually
- 4. Uranium fuel Cycle Cumulative Dose (T.S. 3.11.4)
The cumulative dose off-site to any member of the public due to radioactive releases is determined by suming the calculated doces from the following as appropriate. -
- a. Liquids,usingequation(1). Usually this is not added to b, c, or d below.
- b. Noble gases, using equations (11) and (12) or (lla) and (12a).
X006923a.08 381 i
DIABLO CANYON POWER PLANT NUE ER CAP A-8 REVISION 5 PAGE 39 0F 85 1 TITLE: OFF-SITE DOSE CALCULATIONS UNITS 1 AMD 2
- c. Iodines and particulate, and radionuclides other than noble gases, using equation (14).
- d. Directradiationfrom3.usingequation(27).
- 5. On-site dose calculations to any member of the public due to (their) activity inside the site boundary (T.S. 6.9.1.6).
1 Although the main body of this procedure is dedicated primarily to off-site dose calculations, with the demarcation between off-site and on-site being the site boundary, in some instances the methodology , used for off-site can be used for on-site calculations. However, e - there are limitations to the expressions used and these will be a delineated in that which follows.
~
Particular to this site are situations where on occasions some membeb of the public are allowed within the site boundary but only in the
- owner controlled area up to the protected area boundary. Although this area is considered under license control, because of situations ,
usually so transient, film badging, TLDs, dosimeters and such are not-( felt necessary. Nonetheless, dose calculations will be made according l i to this section to satisfy this licensee control. The most prevalent or frequent members of the public are: tour participants to the simulator (training building) or bio-lab, policemen to the shooting range (most frequent); ranch hands driving cattle through from adjacent properties; and American Indians visiting ancient onsite burial grounds (closest to plant). Doses due to liquid releases are j too improbable, hence not calculcted for here. However, doses due to gaseous releases and direct radiation are considered. Of course, of E prime concern are the time and distances involved. There are
- limitations on these distances used, however. For gaseous releases the doses are calculated using equations (lla), (12a) and (14) with the Rj's in (14) confined to the inhalation and ground plane pathways.,
and furthermore excluding the infant age group. The major distance ' limitation here is where the X/Q and D/Q dispersion factors breakdown mathematically. These values are obtained by extrapolating linearly backwa values,rds the logarithms (dispersion of the most factor versus proximate distance) site other and some boundary (S.B.) known location (loc.) to the appropriate distance onsite. That is: log IX/Q (or D/Q]onsite: log [X/Q (or D/Q]S*B*-log [X/Q(orD/Q]1oc* log (dist.S.B.) - log (dist. loc.) llog (dist.onsite)-log (dist.S.B.]
+1ogIX/Q(orD/Q)]S.B.
X006923a.08 391 i
l { DI ABLO CANYON POWER PLANT NUEER CAP A-8 I REVISION 5 PAGE 40 0F 85 TITLE: OFF-SITE DOSr. CALCULATIONS UNITS 1 AND 2 1 Considering Reg. Guide 1.111's figure bounds and DCPP's site specific
" building wake" correction factors, the distance litaitations for which the mathematical expressions can be expected to be reasonably reliable are for distances greater than (>) 200 meters.
Likewise for direct radiation, the doses are calculated using equations (18) through (27). Here the storage of solid radwastes is assumed a point source although finite source dimensions of approximately 15' to 20' do certainly exist. For field point dose calculations less than (<) 100 meters away, an error would start i showing up in those equations. l = Consequently 200 meters away-from the plant's (both units) centroid . and the storage bunkers is arbitrarily selected as the closest l
- perimeter for which onsite doses will be calculated with reasonable !
a reliability using the 00CP equations. , { Fortunately, the types of the members-of-the-public onsite described { I above, at worst, barely approach that 200 meter limit. Below is a j table describing the type of onsite member-of-the-public expected at DCPP, the sectors and closest distances in which they may visit and finally their average expected visitation times (based on Security Dept,information). SECTOR CLOSEST P0lNT AVERAGE EXPECTED ONSITE MEMBER OF 0F APPRCACH VISITATION OF THE PUBLIC VISITATION TO PLAN 1_ TIME PER YEAR _ (1) Police at SE 700m 208 hours shooting range 7 (2) Tour Participants
~
(a) Simulator Bldg S (SE) 310m 4 hours (b) Bio Lab SSE(SE) 460m 6 hours (c) Ov'erlook E 210m 1 hours (3) American Indians NW 200m 96 hours at burial grounds NNW 200m 96 hours , (4) Ranch hands driving NW 250m I hour cattle around site NNW 350m I hour N 320m I hour NNE 450m I hour NE 630m I hour X006923a.08 401 s s
( DIABLO CANYON POWER PLANT NUIEER 1AP A-8 REVISION 5 TITLE: Off-SITE 00SE CALCULATIONS PAGE 41 0F 85
" I UN1TS 1 AND 2 I TABLE 1 CONPOSITE DOSE FACTOR, Ajy, FOR ADULTS, SALTWATER SITE
{ (mrem / hour per pC1/ml)
't:
NUCLIOE T. BODY THYROIO K10NEY LUNG GI-LLI 80NE LIVER H 3 2.82E-01 2.82E-01 2.82E-01 2.82E-01 2.82E-01 NO DATA 2.82E-01 Be 7 6.52E+01 NO DATA NO DATA NO DATA 2.61E+02 2.61E+01 NO DATA C 14 2.90E 03 2.90E 03 2.90E 03 2.90E 03 2.90E 03 1*45E 04 2.90E 03 Na 24 F 37 - 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 .' 3.35f D5 50 DITI WO DITI WO DITI T.18I D6 T.37I 57 T.D4I D6- >
- Cr 51
;- 5.58E 00 3.34E 00 1.23E 00 7.40E 00 1.40E 03 NO DATA NO DATA Mn 54 1.35E 03 NO DATA 2.10E 03 NO DATA 2.16E 04 NO DATA Wn 53 -
- - 1.06E 03 i 3.T5r D1 WO 0ITI -
7.76f D2 WO DITI T.37E D3 WO DITI T.78I D2% Fe 55 8.23E 03 NO DATA NO DATA ! Fe 59 1.97E 04 2.03E 04 5.11E 04 3.53E 04
- l 7.27E 04 NO DATA NO DATA 5.30E 04 6.32E 05 8.06E 04 1.90E 05 Co 57 !
2.3EE 02 NO DATA NO DATA NO DATA 3.59E 03 NO DATA l.42E 02 l fo 58 T.lST D3 Ho DITI WO 0ITI Wo 0XTI T.72r 54 WO 0XII 3.D3r 52-Co 60 3.82E 03 NO DATA NO DAT A NO DATA i 3.25E 04 NO DATA 1.73E 03 Ni 63 1.67E 03 NO DATA NO- DATA NO- DATA 7.18E 02 4.96E 04 Wi 63 - 1.44E 03 j T.70T D1 WO DITI WO DITI WO DITI 3.35T D2 7.52r D2 7.32I D1-Cu 64 1.01E 02 NO DATA 5.40E 02 NO DATA 1.83E 04 NO DATA 2.14E 02 Zn 05 2.32E 05 NO DATA 3.43E 05 NO DATA Yn 65 - i.16T D1 WO 0ITI
- 3.23E 05 1.61E 05 5.13E 05 {
1.76T D2 WO DITI I.ISI D1 3.13T D2 3.I6I D2 As 76 3.94E 03 NO DATA 7.86E 03 NO DATA ~ 7.86E 06 NO DATA 4.71E 03 Br 82 4.07E 00 NO DATA NO DATA NO DATA 4.66E 00 NO DATA Br 83 00 DATA F.25E-02 NO DATA .NO DATA NO DATA 1.04E-01 NO DATA NO DATA Br 84 9.40E-02 NO DATA NO DATA NO DATA t 7.38E-07 NO DATA NO- DATA Er 83 -
' 7.E6T-D3 WO DITI WO DITI WO DITI T.30E-T8 Wo 0ITI WO 0XII -
Rb 86 2.91E DE NO DATA . NO DATA .NO DATA
~
1.23E 02 NO DATA 6.24E 02 Rb 88 9.49E-01 NO DATA NO DATA NO- DATA 2.47E-11 NO DATA 1.79E 00 lb 83 - - 3.14I~D1 WO DITI WO DITI WO DITI - I.I9f-T4 WO DITI T.T9T DO
- I Sr 89 1.43E 02 NO DATA NO DATA NO DATA Sr- 90 8.00E 02 4.99E 03 NO DATA 3.01E 04 NO DATA NO DATA NO DATA 3.55E 03 1.23E 05 NO DATA IR 9T - 3.71E DO WO DITI WO 0ITI Wo 0XTI -
i 3.17E D2 I.T8T D1 WO DITI - Sr 92 ! 1.51E 00 NO DATA NO DATA NO DATA 6.90E 02 3.48E 01 NO DATA Y 90 1.25E-01 NO DATA NO DATA NO DATA Y 9TM-
- - 6.42E 04 6.06E 00 NO DATA 7.72T-33 WO DITI WO DITI Wo DITI -
T.38E-31 I.73f-D2 WO DITI - Y 91 2.37E 00 NO DATA NO DATA NO DATA Y 92 4.89E 04 8.88E 01 NO DATA 1.56E-02 NO DAT A NO DATA NO DATA 9.32E 03 5.32E-01 NO DATA Y 93 - - - i.36f-D2 WO DITI WO DITI WO DITI 3.35T D4 T.39f DO WO DITI - 2r 95 3.46E 00 NO DATA B.02E 00 NO DATA ! Zr 97 8.13E-02 NO DATA 1.62E 04 1.59E 01 5.11E 00
- - 2.68E-01 NO DATA 5.51E 04 8.81E-01 1.78E-01 1 Rb 93 - I.lar 52 WO DITI 7.36E D2 WO DITI No 99 T.31E D6 3.17E D2 7.19E D2-2.43E 01 NO DATA 2.89E 02 NO DATA 2.96E 02 NO DATA 1.28E 02 Ic_99_M, _ 4. 66E_-91_ N0_D AT A _ 5. 56E-91_1 79E-22_ 2.17E p1_1. 30E-p2_ 3. 66E-02_
X006923a.08 411 s
DIABLO CANYON POWER PLANT NUEER CAP A-8 REVISION 5 PAGE 42 0F 85 TITLE: OFF-SITI 00SE CALCULATIONS - UNITS 1 AND 2 I 1 TA8LE 1 - (Continued) I t NUCLIDE T. 80DY THYROID KIDNEY LUNG GI-LLI 80NE LIVER Tc101 1.88E-01 NO DATA 3.46E-01 9.81E-03 5.77E-14 1.33E-02 1.92E-02 Rul03 4.60E 01 NO DATA 4.07E 02 NO DATA 1.25E 04 1.07E 02 NO DATA Rul05 3.51E 00 NO DATA 1.15E 02 NO DATA- 5.44E 03 8.89E 00 NO DATA rut 03 - 7.51T 52 WO DITI 3.56T 53 WO DITI T.53I US T.39I 53 WO DITI - Ag110M 8.45E 02 NO DATA 2.80E 03 NO DATA 5,80E 05 1.54E 03 1.42E 03 Sn113 4.28E 03 1.82E 03 NO DATA NO DATA 3.10E 05 7.66E 04 2.83E 03 (4115 6.12E 02 NO DATA 1.13E 04 NO DATA 9.39E 06 NO DATA 1.56E 04
- Sn117M 2.02E 04 NO DATA NO DATA NO DATA . 2.26E 05 NO DATA NO DATA i)
?
Sb122 5.98E 00 2.70E-01 NO DATA 1.07E 01 6.72E 03 1.07E 01 5.37E-01 ;l Sb124 1.09E 02 6.70E-01 NO DATA
- 2.15E 02 7.84E 03 2.76E 02 5.22E 00 IeT25 - i.70T 51 T.79T-51 50 DITI 2.91E 01 6.52E 01 8.82E 02 NOT.36T DATA52 T.14T 53 T.77T 52 T.97T 50 L ,
Te125M 8.66E 02 2.17E 02 1.86E 01 - Te127H 6.68E 01 1.40E 02 2.23E 03 NO DATA - 1.84E 03 5.48E 02 1.96E 02 TeT27 - T.33T 50 E.EOT 50 3.33T 51 WO DITI ' 7.53r 52 I.90T 50 3.IOT 50 Te129M 1.47E 02 3.20E 02 3.89E 03 NO DATA 4.692 03 9.31E 02 3.47E 02 . Te129 6.19E-01 1.95E 00 1.07E 01 NO DATA - 1.92E 00 2.54E 00 9.55E-01 TeT3TM- T.71T 51 T.58T 52 I.14T 52 WO DITI I.IOT 53 T.iOT 52 I.ISI 31- j Te131 5.03E-01 1.31E 00 6.,99E 00 NO DATA 2.26E-01 1.59E 00 6.66E-01 Te132 1.24E 02 1.46E 02 1.27E 03 NO DATA 6.24E 03 2.04E 02 1.32E 02 I T T35 -- i.31T 51 V.ill 53 T.32T 52 WO DITI T.51T 52 1.ist 51 T.17T 52 I 131 1.79E 02 1.02E 05 5.35E 02 NO DATA. 8.23E 01 2.18E 02 3.12E 02 3 1 132 9.96E 00 9.96E 02 4.54E 01 NO DATA 5.35E 00 1.06E 01 2.85E 01-
- J T T33 - 3.ist 51 I.IOT 54 7.Y6T 52 WO DITI T.T67 52 7.15T 51 T.30T 52' I 134 5.40E 00 2.62E 02 2.40E 01 NO DATA 1.32E-02 5.56E 00 1.51E 01 1 135 2.24E 01 4.01E 03 9.75E 01 NO DATA 6.87E 01 2.32E 01 6.08E 01 y IsT33 - ~~ I.33T 54 WO DITI - 3.777 53 T.75T 53 7.35Y 52 3.34T 53-' T.Bar 54
- Cs136 2.04E 03 NO DATA 1.57E 03 2.16E 02 3.21E 02 7.16E 02 2.83E 03 Cs137 7.85E 03 NO DATA. 4.07E 03 1.35E 03 2.32E 02 8.77E 03 1.20E 04 IsT3E - I.V4r 50 WO DITI I.Ill 50 E.70T-51 3.12T-55 1.57T 50 T.YoY 51'-
- Ce139 3.81E 02 NO DATA NO DATA NO DATA 3.25E 03 NO DATA NO DATA l,!
Sa139 2.30E-01 NO DATA 5.23E-03 3.17E-03 1.39E 01 7.85E 00 5.59E-03 i 8a140 1.08E 02 NO DATA 7.02E-01 1.18E 00 3.38E 03 1.64E 03 2.06E 00 bat 4T - T.797-51 WO DITI T Y.38T-53 T.I37-53 T.IOT-59 3.32T 50 Y.387-53 4 Ba142 1.08E-01 NO DATA 1.50E-03 1.00E-03 2.43E-18 1.72E 00 1.77E-03 2 La140 2.10E-01 NO DATA
-~
NO DATA NO DATA 5.83E 04 1.57E 00 7.94E-01 IaT47 - 9.T37-33 WO DITI WO DITI WO-DITI Y.38T 52 I.567 52I.37T Cel41 2.63E-01 NO DATA 1.08E 00 NO DATA 8.86E 03 3.43E 00 2.32E 00 Cel43 4.94E-02 NO DATA
- 1.97E-01 NO DATA
- 1.67E 04 6.04E-01 4.46E 02 -
TeT41 - V.39T 50 WO DITI I.13T 51 WO DITI -' I.547 54 T.79T 52 7.17T 51- ! Pr143 2.87E-01 NO DATA 1.34E 00 NO DATA 2.54E 04 5.79E 00 2.32E 00 Pr144 9.64E-04 NO DATA
- 4.44E-03 NO D ATA
- 2.73E-09 1.90E-02 1.87E-03 4 WdT47 - 7.74T 51 WO DITI 7.38T 50 WO DITI Y.70T 54- 1.I6T 50 1.387 50-W187 2.68E 00 NO DATA NO DATA NO DATA 2.51E 03 9.16E 00 7.66E 00 hp239 _ _1911-93_ 30_ DATA _198{-22_ 30_DAT3 _ M1[ 22_ M3{-p2, 3.47E-03_ j X006923a.08 421 I
s
( 4 1 { DiPato
' CANYON P05ER PLANT NUEER CAP A-8 1 1
REVISION 5 .j PAGE 43 0F 85 ti LYTLE: Off-SITE.00SE CALCULATIONS
~
UNITS 1 AND 2 s{ s q n E N b u O m
- s. - Nmmem mmmmNmemm
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ym > COe e e e e e o e o e e o e e Ne
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*=e 4U M e b CCCOCCCCCQCCOCC
+ ++++++++++++++ **
a E e6 ** W W W W W L.J W W w W W W W W w 1 w E I" m m N N N m m @ N m @ N*=s===C I
>= EW L mNNMmN@mNmmmmNM I g* e um e e e e e e o e o e e e e e e Q CO %y m e==m W M a m m M M M m m m m i D C O I 4 U
'e I g C C w 1
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>= C 6 Q e E
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++++++++++++ >
0 i 1 E @ == 8WWWWWwwwWWWWWW E i Q OJ bh 8 @ W M N m @ @ T @ m @ N m Ch we j 6 C i T M Ps M Q N N m C e=e 4D N was @
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, UNITS 1 AND 2 TABLE 30 DOSE PARAMETERS 8, Ri FOR RADIO!0 DINES, RADIOACTIVE PARTICULATE AND ANY RADIONUCLIDES OTHER THAN NOBLE GAS, G' E005 EFFLUENTS, ANY AGE GROUP, GROUND PLANE PATHWAY (m2 arem/yr per pC1/sec)
RADIONUCLIDES R (GROUND)
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- 1. H-3 0.000E+00 l
- 2. C-14 0.000E+00 ,
- 3. CR-51 4.668E+06 em 4. MN-54 1.342E+09
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- 8. ZN-65 7.501E+08
- 9. R8-86 9.005E+06
- 10. SR-89 2.230E+04
- 11. SR-90/Y90 4.482E+05
- 12. Y-91 1.183E+06 l )
- 13. ZR-95 2.493E+08
- 14. N8-95 1.366E+08
- 15. RU-103 1.087E+08
- 16. RU-106 4.200E+08
- 17. AG-110M 3.482E+09
- 18. CD-115/115M 4.500E+06
- 19. 58-124. 5.949E+08
- 20. 58-125 2.286E+09
- 21. TE-129M 2.001E+07
- 22. 1-131 1.722E+07
- 23. 1-133 2.474E+06
- 24. CS-134 6.833E+09 ,
- 25. CS-136 1.491E+08
- 26. CS-137 1.030E+09
- 27. BA-140
. 2.054E+07
- 28. CE-141 1.360E+07
- 29. CE-144 6.958 E+07
- 30. ND-147 8.481E+06 8
Values for the dose parameters for all pathways are calculated by the PGandE " Tech. Spec." Code and based on Reg. Guide 1.109 or NUREG 0133. X006923a.08 581 i
l OIABLO CANYON POWER PLANT kUMBER CAP A-8 REVISION 5 TITLE: OFF-SITE DOSE CALCULATION PAGE 59 0F 85 i l UNITS 1 AND 2 TABLE 3P 3 00SE PARAMETERS , Pi FOR RA010100!NES, RADI0 ACTIVE PARTICULARS, AND ANY RADIONUCLIOE OTHER THAN N0blE GAS, GASEOUS EFFLUENTS, ANY AGE GROUP, GROUND PLANE PATHWAY (m8 arem/yr per pCi/sec) RADIONUCLIDES P (GROUND)
- 1. H-3 0.000E+00
- 2. C-14 0.000E+00 '
** 3. CR-51 6.667E+06 ;- 4. NN-54 1.098E+09 !
- 5. FE-59 3.922E+08 1
- 6. CO-58 5.272E+08 j$)-
- 7. CO-60 4.400E+09 *
- 8. 2N-65 6.894E+08
- 9. RB-86 1.286E+07
- 10. SR-89 3.160E+04 -
- 11. SR-90/Y90 6.403E+03 l 12. Y-91 1.669E+06 s
i
- 13. ZR-95 3.487E+08
- 14. NB-95 1.956E+08 )
- 15. RU-103 1.551E+08
- 16. RU-106 2.992E+08
- 17. AG-110 3.143E+09 1
- 18. CD-115/115M 6.300E+06
- 19. 58-124 8.374E+08
- 20. 58-125 7.552E+08 y 21. TE-129M 2.856E+07
- 22. 1-131 2.460E+07
- 23. 1-133 3.502E+06
- 24. CS-134 2.813E+09 '
- 25. CS-136 2.129E+08
- 26. CS-137 1.147E+09
_ 27. BA-140 . 2.934E+07
- 28. CE-141 1.942E+07 4
- 29. CE-144 5.855E+07
- 30. NO-147 1.212E+07 3
Values for the dose parameters for all pathways are calculated by the PGandE " Tech. Spec." Cod) and based on Reg. Guide 1.109 or MUREG 0133. X006923a.08 591 i
DIABLO CANVON POWER PLANT NuteER CAP A4 REVISIDW 5 PAGE 60 0F 85 TITLE: OFF-SITE'00SE CALCULATION UNITS 1 AND 2 TABLE 4A 1 DOSE PARAMETERS 8 Ti OR'6 , { FOR RADIOI0 DINES, RADIOACTIVE PARTICULATE. AND l ANY NON-NOBLE GASES { SUPER AGE GROUP. CRITICAL ORGAN INHALATION COW-MILK-INGESTION PATHWAYS INHALATION MILK RADIONUCLIDES (MREM /YR PER pCi/M8 ) 8 (M , MREM /YR PER pC1/SEC)' g , H 38 1.3E+03 (teen total body) 2.4E+038 (inf.totalbody) < 1 C 148 3.6E+04 (child bone) 3.2E+068 (inf. bone) Cr 51 Mn 54 2.1E+04 (teen lung) 2.0E+06 (
")
7.5E+06 (teen GI-LLI) 3.1E+07(inf. liver) h 4 Fe 59 1.5E+06 (
") 3.4E+08 ( " "
) l Co 58 1.3E+06 (
") 9.1E+07 (teen GI-LLI)
Co 60 8.7E+06(
") 2.9E+08 (
)
(' Zn 65 1.2E+06 (
") 1.7E+10 (inf. liver)
Rb 86 2.0E+05(childliver) 2.1E+10 ( "
)
Sr 89 2.4E+06 (teen lung) 1.1E+10 (inf. bone) Sr 90/Y90 Y91M/Y91 1.1E+08 (teen bone) 2.9E+06(teenlung) 1.0E+11 ( " ") 5.5E+06 (teen GI-LLI) Zr 95 2.7E+06 (
") 1.0E+06 (
)
Nb 95M/95 7.5E+05(
") 2.9E+08( " "
) !
g- Ru 103 7.8E+05 (
") 1.3E+05(
) !
Ru 106/Rh106M 1.6E+07(
") 1.5E+06(
) i Ag 110M 6.8E+06 (
") 2.1E+10 (' " "
) ,
8 Values for tie dose parameters for all pathways are calculated by the PGandE
" Tech. Spec." Code based on Reg. Guide 1.109 or NUREG 0133.
8 for tritium and carbon-14, the units of the dose parameters are eres/yr per 9C1/9 for all pathways, and they must be multiplied by X/Q. X006923a.08 601 i
DIABLO CANYON POWER PLMT NUMER CAP A-8 REVISION 5 TITLE: OFF-SIT.E40SE CALCULAT10N PAGE 61 0F 85 UNITS 1 - AND 2 I TABLE 4A (cont'd) 8 DOSE PARAMETERS , K OR K. FOR RADIO!ODINES, RADIOACTIVE PARTICULATE, AND ANY NON-NOBLE GASES SUPER AGE GROUP. CRITICAL ORGAN ! INHALATION COW-MitK-INGESTION. PATHWAYS INHALATION MILK RADIONUCL]DE (MREN/YR PER pCi/Ms) (ga, MREM /YR PER pCi/SEC) '
- Cd 115/Cd 115M/ )
1 In 115M 2.8E+06(teenlung/GI-LLI) Sb 124 3.9E+06 (teen lung) 6.9E+07 (teen GI-LLI) i Sb 125 2.7E+06 (
")
7.8E+08 ( 2.2E+08 (
)
)
K l l Te 129M Cs 134 2.0E+06 (
") 1.3E+09 (inf. kidney) 1.1E+06 (teen liver) 5.4E+10 (inf. liver) j
( Cs 136 1.9E+05(
) 5.5E+09 ( " "
)
; Cs 137 l
' 9.1E+05 (child bone) 4.9E+10 (," "
)
Ba 140 2.0E+06 (teen lung) 2.3E+08 (inf. bone) Ce 141 6.1E+05(
") 1.5E+07 (teen GI-LLI) f )
Ce 144 1.3E+07(
") 1.3E+08 (
) )
Nd 147 Unidentified 3.7E+05(
") 6.9E+05 (
) .
1.1E+08 1.0E+11 I 131 1.6E+07(childthyroid) r 1 133 " " 5.2E+11 (inf. thyroid) 3.8E+06( ) 4.8E+09 ( " "
)
I e l 8 Values for the dose parameters for all pathways are calculated by the PGandE
" Tech. Spec." Code based on Reg. Guide 1.109 or NUREG 0133.
8 For tritium and carbon-14, the units of the dose parameters are ares /yr per uti/m s for all pathways, and they must be multiplied by X/Q. X006923a.08 611
DI A8LO CANYON PO'.'ER PLANT NUMER CAP A-8 REVISION 5 PAGE 62 0F 85 TITLE: OFF-SITE DOSE CALCULATION
.- UNITS 1 AND 2 TABLE 4A (cont'd) !
DOSE PARAMETERS 8, % OR K. FOR RAD 10100!NES, RADIOACTIVE PARTICULATE, AND ANY NON-NOBLE GASES j SUPER AGE GROUP. CRITICAL ORGAN FARM-ANIMAL-MEAT-INGESTION. VEGETABLE-INGESTION PATHWAYS ANIMAL (MEAT) VEG RADIONUCLIDES (M 8, MREM /YR PER pC1/SEC) (M8, MREM /YR PER pCi/SEC) H 3 8 3.2E+028 (adult total body) 4.0E+038 (child tot body),' { C 148 5. 3E45 8 (childbone) 3.5E+068 (child bone) j Cr 51 1.6E+06 (adult GI-LLI)
~ 1.2E+07 (adult GI-LLI)
Mn 54 2.2E+07 (
) 9.4E+08 (
)
Fe 59 1.8E+09 (
) 9.8E+08 (teen GI-LLI)
Co 58 3.1E+08 (
) 6.1E+08 (adult Gt-LLI) )
Co 60 1.1E+09 (
) ' 3.2E+09 (teen F.1-LLI)
Zn 65 1.0E+09 (adult liver) 2.7E+09 (chi'd liver) Rb 86 5.4E+C8 (child liver) " " 4.6E+08 ( )
\ Sr 89 4.2E+08 (child bone) 3.6E+10 (child bone)
Sr 90/Y90 1.0E+10 (adult bone) 1.4E+12 (
)
Y91M/Y91 5.3E+08 (adult GI-LLI) 3.2E+09 (teen GI-LLI) 2r 95 1.6E+09 (
) 1.2E+09 ( " "
)
Nb 95M/95 6.8E+09 ( ) 4.7E+08 (adult GI-LLI) Ru 103 1.1E+10 (
)
5.7E+08 (teen GI-LLI) Ru 106/Rh106M 1.5E+11 ( ) 1.5E+10 ( " "
* )
Ag 110M 2.1E+09 (
) "
4.4E+09 ( " ) 9 8 Values for th'e dose parameters for all pathways are calculated by the PGandE
" Tech. Spec." Code based on Reg. Guide 1.109 or NUREG 0133. ,
I a for tritium and carbon-14, the units of the dose parameters are arem/yr pa.- pCi/m8 for all pathways, and they must be multiplied by X/Q. X006923a.08 621 1 1
~
DIABLO CANYON POWER PLMT NUMER CAP A-8 REV3SiON 5-TITLE: OFF-SITE-90SE CALCULATION PAGE 63 0F 85
-UNITS 1 AND 2 TABLE 4A (cont'd)
DOSE PARAMETERS 8. Ti OR Tj. FOR RADI0 IODINES, RADI0 ACTIVE PARTICULATE. AND-ANY NON-NOBLE GASE3 SUPER AGE GROUP CRITICAL ORGAN FARM. ANIMAL. ; MEAT-INGESTION. VEGETABLE-INGESTION PATHWAYS ANIMAL (MEAT) VEG RADIONUCLIDES (M8. MREN/YR PER pC1/SEC) (M8, MREN/YR PER pCi/SEC) e e Cd 115/Cd 115M/ L In 115M 5.4E+07(adultGI-LLI) 2.5E+09 (teen GI-LLI) Sb 124 Sb 125 4.7E+08 ( 1.7E+08 (
)
)
3.0E+09 ( " 1.6E+09 ( " "
)
)
h Te 129M 5.4E+09 (
) 2.9E+09 (child kidney)
Cs 134 1.2E+09 (adult liver) 2.6E+10 (child-liver) Cs 136 4.5E+07 (
) 2.2E+08 (
)
Cs 137 1.1E+09 (child bone) 2.5E+10 (child bone) Ba 140 5.7E+07 (adult GI-LLI) 2.8E+08 (
)
Ce 141 3.2E+07 (
) 5.3E+08 (teen GI-LLI)
Ce 144 3.9E+08 (
) 1.3E+10 ( " "
)
Nd 147 3.9E+07(
) 1.9E+08 (adult GI-LLI)
Unidentified 1.5E+11- 1.4E+12 1 131 2.7E+09 (child thyroid) 2.4E+10 (child thyroid)
! 133
{ 6.7E+01( " "
) 4.1E+08 (
)
e 8' Values for the dose parameters for all pathways are calculated by the PGandE
" Tech. Spec." Code based on Reg. Guide 1.109 or NUREG 0133.
8 For tritium and carbon-14, the units of the dose parameters are arem/yr per 8 pCi/m 83 for all pathways, and they must be multiplied by X/Q. X006923a.08 63I I i I
DIABLO CANYON POWER PLMT NUseER CAP A-8 REVISION 5
~
PAGE 64 Of 85 TITLE: Off-SITE 00SE CALCULATION UNITS 1 AND' 2 TABLE 48 1 DOSE PARAMETERS , % AND K , FOR RADIO!0 DINES. RADIOACTIVE PARTICULATE. AND ANY RADI0 ACTIVE NON-NOBLE GASEOUS EFFLUENTS SUPER AGE GROUP. CRITICAL ORGAN GROUND PLANE PATHWAY f k 8 RAD 10NUCL10E Ili ( M . UCl/SEC MREM /YR )- . qg M . MREM /YR ) UC1/SEC ,
- H 3 0 0
- - C 14 0 0 Cr 51 4.7E6 6.7E6 j$)-
Mn 54 1.3E9 1.1E9 Fe 59 2.8E8 3.0E8 to 58 3.8E8 5.3E8 Co 60 2.1E10 4.4E9 Zn 65 7.5E8 6.9E8 Rb 86 9.0E6 1.3E7 l Sr 89 2.2E4 3.2E4 Sr 90/Y90 4.5E5 6.4E5 Y 91 1.2E6 1.7E6 Zr 95 2.5E8 3.5E8 Hb 95 1.4E8 2.0E8 RU 103 1.1E8 1.6E8 RU 106/Rh106M 4.2E8 3.0E8 Ag 110M 3.5E9 3.1E9
. Cd 115/115M 4.5E6 6.3E6
'. Sb 124 6.0E8 8.4E8 Sb 125 2.3E9 7.6E8 Te 129M 2.0E7 2.9E7 e Cs 134 6.8E9 2.8E9 Cs 136 1.5E8 2.1E8 Cs 137 , 1.0E9 1.1E9 Ba 140 2.1E7 2.9E7 Ce 141 1.4E7 1.9E7 Ce 144 7.0E7 5.9E7 Nd 147 8.5E6 1.2E7 1 131 1.7E7 2.5E7 1 133 2.5E6 3.5E6 1
' Values for the dose parameters for all pathways are calculated by the PGandE " Tech. Spec." Code based on Reg. Guide 1.109 or NUREG 0133.
X006923a.08 641 i
DIABLO CANYOM POWER PLMT NUteER CAP A-8 REVISION 5 TITLE: OfF-SITETOSE CALCULATION PAGE 65 0F 85 LMITS 1 MD 2 e0
- e e O O
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i DIABLO CANYON POWER PLANT NUEER CAP A-8 REVISION 5 PAGE 66 0F 85 TITLE: OFF-SIT.E -GOSE CALCULATION UNITS 1 AND 2 e
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DIABLO CANYON POWER FLAMT NUE ER CAP A-8 REVISION 5 PAGE 67 0F 85 TITLE: OFF-SITE-DOSE CALCULATION
. UNITS 1 AND 2 TABLE 6 LOCATIONS FOR CANDIDATE DOSE (Rj) AND DOSE RATE (Pj) RECIPIENTS N
siiu ce ,
.5=u - m a ! m E a . 1 In u u.e u.i . si i n ,m iu i
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- eirtesi 1Mi.ieweis essesee to anip the tettie-emet.entesi pathmey.De Aise et these hysetAetttei itsettens. lAtindiviestis Appetheticei emessed inst.lsessite eniy the ispnele een ste.itenehsI e 38s. uftete heat end etia ete rete tdtlie enSegise the male gu geens oir f W esposed to the mees esse end sete str dose serve as the fecm. Sesc. servogste.
8eesteence instions seassia reelladivie.els usite som simitanosusir he asessed te not only asele gas estoie tesy (ens stin) , msesesas enrii dosemeilrates. u ese rates, but else to imeietten. gmund piene leet) eatest one sessiste vegetenie savasar assu, as 8ttre 90 estee'Tielitei dispersion mee steet 1/Q and D/Q are 6ted est just to the distence se me annuintas secter, sut eine to see resteense utom lesetien.
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=i.wai. outrecleient and .0,etaieenir uwention insicoctnom, .e etnie == (eas
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l l DIABLO CANYON POWER PLMy t NUEER CAP A-8 j REVISION 5 j PAGE 68 0F 85 TITLE: OFF-SITE-DOSE CALCULATION UNITS 1 MD 2
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DIABLO CANYON POWER PLANT NUE ER CAP A-8 REVISION 5 PAGE 70 0F 85 TITLE: OFF-SITCDOSE CALCULATIONS UNITS 1 AND 2 FIGURE 3 SECTOR MAP SHOWING RECEPTOR LOCATIONS
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DIABLO CMYON POWER PLMT NUEER CAP A-8 REVISION 5 { TITLE: OFF-SITE DOSE CALCULATIONS PAGE 71 0F 85 UNITS 1 MD 2 i APPENDIX 1 ' l Here the constituents, AF, to the Liquid Effluent "idiation monitor high alarm set point expressions as disp 10ed in 1.c. are expounded upon in more detail. Fromderived. were these, it is relatively effortless to see how equations (2) through (7)
- 1. RE-18 (Subscript "b")
The afb term is assembled from the other sources, as. afb = 5 CjFj . L j=1 jfb The C&RP Engineer will specify the AF ,made 4;p of choices on b. C) and Fj. The choices are as foi ows: I ( a. If there is a discharge already in progress from any (or all) of the other potential sources (jfb), then use the actual values of C) and Fj. N b. If there is a planned discharge from any of the other potential sources (j/b "b" discharge and whereinpre-r)eleaseanalysisdataalsoprovidesawhich C might occu this value and the maximum d . then use, default value of Fj. X006923a.08 711 i
DIABLO CMYON POWER Pl. ANT NUEER CAP A-8 REVISION 5
,l PAGE 72 0F 85 '\'6 TITLE: OFF-SITE-COSE CALCULATIONS n
UNITS I MD 2 APPDDIX 1 (Continued)
- c. In tha absence of any pre-release data, yet there is possibility of a discharge from these other sources (j/b) occurring during batch "b's" discharge, then select a max conservative value of the j
, C from a recent history of y
8 \( ( ( such values also the maximum default alue of Fj.
- d. Withtheassurancethatno"jth"dischahgawilloccurduringthe a,
batch "h's" discharge, then select / C) = 0 for that Ej h othe "jth" potential source.
- 2. RE-23(Subscript"1"forUnit1-Subscript"2"forUnit2)
, As in 1. (above), assemble the AFn2) term as:
C3 F3 \ AF = I j =b .3.4.5.2 (1) ( j j j/l(2) \ MPCj/ Again as in I., the C&RP Engineer will specify the AFM2) makeup of the following choices orf C) and Fj: g j s a ., If there is a discharge fres'n'any (or a.11) of the other potenti I sources already in progress, tften use the actual values O C .- 7 , and Fj in these discharges j p 6. For the d' n M
.i b
C'C contribution, the C&RP Engineer can select from a b recent history (within 2 weeks) of such values the maximum (hence most conservative) along with Fj = max default value.
, i i
X006923a.08 721
DIABLO CMYON POWER PLANT NUEER CAP A-8 REVISION 5 PAGE 73 0F 85 i TITLE: OFF-SITE DOSE CALCULATIONS UNITS 1 MD 2 i l APPENDIX 1 (Continued)
- b. If there is a proposed "jth" discharge (jpb) which may coincide or 1 overlap with this di charge and for which a pre-release analysis gives the values of , then use 3
these values along with the max' default Fj. For theCb and F3 contributions, use the same as instructed in 2.a. above. N
, c. . If there are no discharges from the "jth" sources (jpb) and no pre-release data on j/b, then enter "0" for these C
contributions to the AF u r). For the b and Fb - contributions, use the same as instruc % ted in 2.a. and/or 2.b. above. (
- 3. RE-3 (Subscript "3")
As in 2. above, the AF 3 is generated by exactly the same instructions with the exception of merely permuting the subscript "3" with the subscripts "1" (or "2"), namely: AF3=I j Fj j= .1.2.4.5 MPCj
?: 4. RE-16 (Subscript."4" for Urrit 1 ~ Subscript *5" for Unit 2)
As in 2. above, .the AFd5) are generated by exactly the same instructions . j as in 2. with the except1bn of merely permuting the subscripts "4(5)" with the subscripts "l(2)", namely:
. . AF4 (5) " g [C3 F%
3 j =b .1.2.3.5.(4)I MPC ' jf4(5) k j/
- 5. Allowable flowrates and/or Batch Volumes as a Liquid Radwaste Release Limiting Criteria
- a. M.P.C. or Maximum Allowable Flowrate (MAF) Limiting - T.S.
3/4.11.1.1(10CFR20) X006923a.08 731 i
l DIABLO CANYCM POWER PLANT NUM ER CAP A-8 l REVISION 5 l PAGE 74 0F 85 TITLE: OFF-SITE DOSE CALCULATIONS l
.- UNITS 1 AND 2 1 i
Appendix 1 (Continued) l l MAF p , F(j) - AFj l Cj/MPCj NOTE: because F contains Fc I and Fj, one can either the rated flowrate for the pump in stream of f" use'Fj re =leaseFj , or simply F :: Fe(j) since Fc >> f This also applies to b. and c. below. j, in any case. f
- b. H. A.S.P. Limiting Flowrate (i.e., " turning" the proceke's rain body equation (2) through (7) "inside out") ,
.- l i dHASPcalc(existing) dBkgd RCS ,RCSCw, HASP 1 Cn + 1 , ;
Fj = (F-afj)4 TlT,a 7 6 j g3 MPIg RCSMPC' MPCH3 i Y kj Cy Y
< l (IC910A ctual HASP +0.3) j=1*2 Note:j=b 3 HASP (existing) = 10 and HASP (exisi.ing) = Actual HA9 L
calc calc 0.7 RCS Also the bracketed "[ ]" term as well as Cg3/MPCH3 is a slowly varying constant and at most calculated quarterly Here, as seen in 1.c. of the procedure's main body, one has i i 2i(1 day) ) RCS RCSf ' S-1 l dereRCFri Y i . RCSCe MPC y E l I Y i (i"Y s only) . ( 1/MPCj)l RCSi C RCS RCS . '41(1 day) , (8 usually = Sr 89 and Sr 90/Y90) and e
~
i p H3
'i p 8 ,
- c. "31-Day-Dose Projection Limiting ,
Volume - T.S. 3./4.11.1.3. 31DDPy V 'j g 0.2 mrem,( pw.b.) t MAX j " --< or - d (from 1.d. of procedure) ' (c.1.2)d,ri 31 0.06 mrem,( = w.b.j(T+t) (0.1.2- Pg) (0.1.2) g Note: V) = F'j Atj(max) , where F'j is the rated flowrate of "jth" release pump and 4tj(max) = maximum time proposed for release, or alternately V) E maximum capacity of tank for proposed "jth" release X005923a.08 741 ,
q DIABLO CMYON POWER PLANT NUMER CAP A-8 REVISION 5 TITLE: OFF-SITE DOSE CALCULATIONS PAGE 75 0F 85 )
.- l UNITS 1 AND 2 I
APPEhDIX 2
- 1. HOBLE GASES i Two important entities are generated for triggering the effluents engineer and the attendant rad monitor's valving automatics to allow or disallow a radioactive gaseous batch release. Concerned here are the only two gaseous batch release sources, the Gas Decay Tanks and the Containment {
i Purge ( or venting), which efflux through the plant vent. The expressions ! controlling these decision entities are found in the main body of this i procedure through equations (9)-and (10).: Equation (9) is preferentially ! selected over equation (10) .since, almost without exception, the whole , e, body dose rate calculation always seems to predominate over the skin dose rate calculation (i.e., with regard to the most conservative dose rate i i limitation). Although the Technical specification assigns a 500 mrem /yr ! (whole body dose rate) overall limitation to both units, the Calculation b ' here will conservatively assign a 250 arem/yr limit per Unit in this - i procedure's equation (9). ( These key entities are the percent release rate limit (P.R.R.L.) and attendant rad monitor high alarm set point (H.A.S.P). Although the local , i attendant rad monitors for ncble gas releases from the gas decay tanks and containment are respectively RE-22 and RE-12 the final attendant effluent rad monitor is RE-14A and RE-148. Consequently for each batch release from either containment or gas decay tank whether a g ojected HASF for RE-12 or RE-22 is calculated, a projected HASP for RE-14A and RE-14B must ! also always be calculated. Lastly, since the prc:edure partitions 99% of all gaseous releases to the plant vent and 1% to the steam generator
- blowdown tank vent (at least with regard to dose ratec) then equation 19)'s usage will have a 0.99 multiplication factor.
} Now the analytics implementing all of this is as follows; X006923a,08 751
DIABLO CANYON POWER PLANT NumER CAP A-8 REVISION 5 PAGE 76 0F 85 TITLE: OFF-SITE DOSE CALCULATIONS
~
UNITS 1 AND 2
- a. % Release Rate Limit (P.R.R.L.) and High Alam Set Point (H. A.S.P._)
Def's the batch flow rate F*, which adds to the existing plant vent flow rate (F,,). This can be from either the containment (F*=Fet.usually 55000cfm) or from the gas decay tank.s (F*=Fqor, usually 31 cfm). This means that during a batch release (whether from contairunent or gas decay tank) the new plant vent flow rate will be F,, + F*. Now looking at some other definitions needed, one has the set C'(NG) i and their total Cj(NG) where, C'(NG) is the concentration of noble gas isotope 3
"i" (in pCi/cc)or.in (containment gasthedecayplant ventwith tank), justCyp(rior NG)..=toI discharge Ci(NG) Theof C,th,e batch, s come ,
from the last known samole analysis as scaled by RE-14 ratios. ? Additionally there is the set Cg(NG) and its total, Cr*(NG) = Cl(NG), ~ which define isotopic noble gas concentrations (and total) in{the hatch about to be released (i.e., containment or gas decay terk). The C i's com from the batch's pre-release sample analysis. Companion to these are the relative isotopic fractions, namely b fi = C'/Ct andf5=C/Ch (1) i Now during the discharge the new plant vent concentration, Cj(NG), will be the following sum, with the batch addition dilution scaled (cy flowrate ratics) 1.e.: pv \ . [ f* b C i Ci +I iC1 (pCi/cc) (2) I i=Ypv+f*/ (fpv+f*) Similarly from this set (equation 2) the new plant vent total concentration r of noble gases is CT (NG) = ICj, and the relative isotopic fractions: . FyC}+F*Cl p fj(NG) = Cj/CT" e a. fyCT p + F*CT This is easily seen, since CT* \ (fpvCh+F*Ch) (Fpy + F*/ 1 1 l X006923a.08 761
D!ABLO CANYON POWER PLANT NUE ER CAP A-8 REVISION 5 PAGE 77 0F 85 TITLE: OFF-SITE DOSE CALCULATIONS UNITS 1 AND 2 At this point one calls equation (9) from the main body of this procedure and rearranges it in view of the earlier (above) constraints and equation (3) . along with the fact that. Qi (pC1/sec) = 472 F (cfs) Cg(pC1/cc), namely: 0.99 X 250 mrem /yr WCT ("6) " 472 (fpy + F*)(X/Q)C/L MAX I "1 ft (NG) {4) where: Kj is the noble gas "i" whole body dose factor and i
* (X/Q)C is the caximum historical "five year" running average "contro/L MAXlling location's" (usually-sector-center-line-at-site boundary) meteorological diffusion dispersion f actor - See Tables 2 and 5A of this procedure. ,
, NOTE: One can see that since Cg (NG) = CT (NG) fj(NG)
I and the fact that Fpy and F* as well as (X/Q) are independent of 1, then they can be factcred out from under the "I" sign, ( I Obviously from equation (4), MAXC T (NG) sets the limit on what can be released for cl1 the relative isotopic mixes involved with this particular batch release. From this it is an easy matter to express simple, percent for what is actually released (assuming all the fj's, fj's and fj's hold fixed). g Forthis,usingaknowledgeofCh,Ch,CT and equation (4), one has: Ch(NG) CT(NG) P.R.R.L.* = x 100 = x 100 < 100% (5)* W "(NG) C W CT(MG) or finally. P.R.R.L.* = 191(FpyC}+F*C{}(X/Q)C/LMAX IKi fi (NG) (6) 1 X006923a.08 771 i
DIABLO CANYON POWER PLANT NUPEER CAP A-8 REVISION 5 PAGE 78 0F 85
- sTLE: OFF-SIT.E. DOSE CALCULATIONS UNITS 1 AND 2 I
A note of clarification is in order. By examination of equation (6), the P.R.R.L.* is the percent that CT (NG) represents out of a potential limit MAX CT
' (MG), which this discharge can impose as it is added to an already existing and radiologically restrained effluent stream. To see that those are, indeed, release rates being compared, one only has to mitiply both numerator and denominator of the R.H.S. of (5) by
- MAX-472f, to get QT / QT -
Now for the H.A.S.P. one simply has e
-- MAX a H.A.S.P.RE22 (or RE12) = Bk9RE22 (or RE12) + kRE22 (or RE12) CT(NG) where:
kRE22 (or RE12)
- I fi (NG) kj (RE22 or RE12),
MAX = MAX l and CT (NG) = CT (NG) CT (NG)/C T (NG) in addition j e { to using equation (1) and CAP D-19 values for kj (RE22 or RE12) Likewise: MAX l HASPRE14 = Bk9RE14 + kRE14 CT(NG) j Using equation (3) and again CAP D-19 values for kj(RE14) kRE14
- I f1 (NG) kj (RE14) i .
Finally from these calculated ?alues of the HASP (RE22. RE12, or RE14), a usable high alarm set point is needed for the actual setting or comparing with what is already physically on the instrument (rad monitor) itself. This is called projected HASP and take into account the I&C uncertainty factor correction. It is given as: p-oj. HASP < 10(ID9 10 HASP (calc)-0.3) and must be entered on the release permit as called for in this procedure. This applies to RE22, RE12. RE14A and 148. X006923a.08 781 i
- j
DIABLO CANYON POWER PLANT kJeER CAP A-8 REYISION 5 TITLE: Off-SITE DOSE CALCULATIONS PAGE 79 Of 85 UNITS 1 AND 2 All of the above is performed automatically by the computer software per each pre-release analysis. The software also calculates a projected reading of the radiation monitor 88 vis-a 'vis the Ct (or C 1) and 88 kj (or kj, or 8'k t). Generally if the proj. HASP is greater than the existing setting (from previous releases) then no action is taken. That is. Operations and I&C do not have to change the HASP on the monitor unless the projected reading calculation shows that, although less than proj. HASP, it is yet larger than the existing HASP. 'In this case the HASP should be changed upward to the proj. HASP so the release can be legally discharged. On the other *
, -hand should the proj. HASP be less than the existing NASP, then the ; release cannot be discharged until the HASP is changed to the proj. HASP.
- 2. 10 DINES, PARTICULATE AND TRITIUM As with noble gases in section 1. of Appendix 2 we are concerned with a h
(, similar entity, in the so called P.R.R.L. except it is being applied only to containment. It is assumed that the only significant nuclides for the gas decay tank are the noble gases. Also only the P.R.R.L. will be developed but no H.A.S.P., this is because there is no iodine rad monitor. on containment nor does the plant vent iodine monitor possess any automatics to isolate containment. Equation (13) from the main body of this procedure is the controlling expression here, which comes directly unde r T.S. (L.C.O. ) 3.11.2.1.b. Although the Technical Specifications assigns a 1500 m-em/yr dose to any organ limitation to be applied to the ! site's both arem/yr limitunits, per the unit.calculation here will conservatively assign 750 Also to simplify the calculation and at the same
" time maintain conservatism, the formulae will use the so-called super-age group / critical-organ dose rate factors Fj, found in table 4 of this l
procedure. This in effect selects the highest dose rate factor across the seven (7) major organs amongst the four (4) principle age groups, all for
- each radionuclides (1.P.T.).
)
l l IJ X006923a.08 791 . I
l DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 5 PAGE 80 0F 85 TITLE: OFF-SITE DOSE CALCULATIONS
-- UNITS 1 AND 2 Similarly, as with noble gases in 1. above, one defines Fct as the contaiment purge (or vent) flow rate (usually 55000 cfm), and Fp y as the i plant vent flow rate prior to containment purge.
Also C'(I.P.T.) j is the concentration of the radioparticulate isotope, or pCi containment purge. Thp Cj co/cc) radioiodine or tritium (in,'s found me from theinlast theplant plant vent vent just prior to sample analysis. Similarly Cj (I.P.T.) is that same I.P.T. isotope found in ; containment before the purge and comes from the pre-release analysis for I.P.T.'s in containment As described above: , 8 a a a , Ci (IPT) , , ,, Cg(IPT) , fj{IPT) =
- with CT (IPT) = I Cj(IPT) and fj(IPT) = ,, ' with CT (IPT) = I* b T)
Ch(IPT) i CT (IPT) i l Also Ci (IPT) = ( ) Ck + ( )CkwithC(IPT)=IT Ct (IPT) Fy+fct p I pv + fct i and fj(IPT) = Cj(IPT)/C T(IPT) From this one also sees that 1 l CT (IPT) = 'FpyCT (IPT) + Fet Ch(IPT) (fpv + fct) '
" ~
I C{(IPT) Ch(IPT)
'.' and * (Fpy + Fct) . I CT (IPT) _
FpyCT(IPT)+Fct CT (IPT) , At this point, one recalls equation (13) from the main body of this procedure and rearre.nges 1t in view of the above constraints and the definition of Fj(IPT) along with the fact that 6j(pCi/sec) = 472 F(cfm)Cg(pC1/cc): l l X006923a.08 801 i ______________w
R i DIABLO CANYON POWER PLANT NUEER CAP A-8 i REVISION 5 l TITLE: OfF-SITFDOSE CALCULATIONS l UNITS 1 AND 2 O b S
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DIABLO CANYON POWER PLANT NUMER CAP A-8 REVISION 5 PAGE 82 0F 85 TITLE: OFF-SITE _DCSE CALCULATIONS UNITS 1 AND 2 From the 3 leading candidates for " controllers location" above, choose MX mx smallest C (IPT) and call it (MIN)C T(IPT) T MAX . . Then CT (IPT) = CTIIPT) T CT (IPT) (MIN)C (IPT) CT (IPT) and (P.R.R.L.)IPT " ggw a X100%
"CT (IPT) , ~
D. i 1 l l X006923a.08 821 i
DIABLO CANYON POWER PLANT NUMER CAP A-8 REVISION 5 PAGE 83 0F 85 TITLE: OFF-SITE-DOSE CALCULATIONS _ UNITS 1 AND 2 1 inh p cap gpp a,v,gp , amp vp . gpp H3 1.3E3 2.4E3 0 4.32E3 Cr 51 2.1E4 7.5E6 6.7E6 1.70E7 Mn 54 2.0E6 3.1E7 1.1E9 1.51E9 Fe 59 1.5E6 3.4E8 3.9E8 2.98E9 Co 58 1.3E6 9.1E7 5.3E8 1.19E9 Co 60 8.7E6 2.9E8 4.4E9 6.50E9
- Zn 65 1.2E6 1.7E10 6.9E8 4.05E9 l
~
Rb 86 2.0E5 2.1E10 1.3E7 1.00E9 j Sr 89 2.4E6 1.1E10 3.2E4 3.64E10 i SR 90/Y 90 Y91m/Y91 1.1E8 2.9E6 1.0E11 5.5E6 6.4E3 1.7E6 1.41E12 3.73E9 h Zr 95 2.7E6 1.0E6 3.5E8 2.98E9 ( Hb 95M/Nb 95 7.5E5 2.9E8 2.0E8 7.37E9 ( Ru 103 7.8E5 1.3E5 1.6E6 1.16E10 Ru 106/Rh 106m 1.6E7 1.5E6 3.0E8 1.65E11 Ag 110m 6.8E6 2.1E10 3.1E9 8.05E9 Cd 115m/Cd115/ In115m 2.8E6 6.9E7 6.3E6 3.56E9 I Sb 124 3.9E6 7.8E8 8.4E8 3.89E9 Sb 125 2.7E6 2.2E8
]
, 7.6E8 2.15E9 g Te 129M 2.0E6 1.3E9 2.9E7 8.32E9
- Cs 134 1.1E6. 5.4E10 , ..2.8E9 2 86E10 !
Cs 136 1.9E5 5.5E9 2.1E8 3.70E8 , Cs 137 9.1E5 4.9E10 1.1E9 2.67E10 Ba 140 2.0E6 2.E38 2.9E7 3.52E8 Ce 141 6.1ES 1.5E7 1.9E7 5.72E8 Ce 144 1,.3 E 7 1.3E8 5.9E7 1.35E10 Nd 147 3.7ES 6.9ES 1.2E7 2.35E8 UnId 1.1E8 1.0E11 3.1E9 1.55E12 I-131 1.6E7 5.2E11 2.5E7 2.67E10 I-133 3.8E6 4.BE9 3.5E6 4.12E8 X006923a.08 831 t
r a DIABLO CMYON POWER PLMT NU43ER CAP A-8 RfVISION 5 PAGE 84 Of 85 TITLE: Off-SITE DOSE CALCULATIONS UNITS 1 AND 2 Ecuation (7). (8) and (9) in view of 'the values for Pj's and current met data from taeles 5A and 58 simplify to the following:
=
I esc 58T(IPT) (f pv + fct)l0.0031(g3 + 38.4fg131 + 9.06f1133 + Z (2.39C-6 I""Fp + 0.925f-8 9PPP )fp) (10) or e T(IPT) (f pv ' Ict)l0.00282fn3 + 97.4f j g31 + 2.5 fg133 + I (2.84E 7 I""Pp + 3.48E-9 a.v.gopp )fpg gg) P ( or
**C SMID T(;r7) (Fp, + Fet) 10.000462fn3 + 151f g331 + 1.40f g333 + ? ;-10 IC"Ep fpl (12)
O In view of the foregoing expressions and equations (10). (11) and (12) one finally has. j
? - I ct Ci(IPT)ll0.0032fg3 + M.4ft131+9.06f!133+Z(2.39E-6 " hep +0.925E-89PPp)fpl (13) 58(p,g,g,L,) p =100lF,Ch(IPT)+fp P
or 1 ~ I VF(p,g,g,t,)p=100[F,Cf(IPT)+fp ctC (IPT)l{CF00282fg3+97.af3 331+2.51f g133+I(2.84E-7 ""Ep+ 3.481-98 J*9PPp)fpl (14) p or
$NID(p,g,g,t,) p =100lF,;i(IPT)+Fp ct CT(IPT)llo.000462fn3 + 151fg131+1.40f3133+2.91E-10EC"Ep fel (15)
P X006923a.08 851 s
4 DIABLO CANYON POWER PLANT MUEER CAP A-8
' REVISION 5 PAGE 85 0F B5 TITLE: OFF-SITE DOSE CALCULATIONS
- ~
UNITS 1 AND 2 { l 1 REFERENCES
- 1. " Draft Radiological Technical Specifications for PWR's," NUREG No. 0472, May 1978.
- 2. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix L I, " Regulatory Guide 1.109 Rev.1, October 1977. '
- 3. " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG No. 0133, October 1978. .
- 4. " Age-Specific Radiation Dose Commitment Factors for a one-year Chronic
[ Intake," NUREG No. 0172, November 1977. l S. " Methods for Demonstrating LWR Compliance with the EPA Uranium fuel Cycleb Standard 40 CFR Part 190," NUREG No. 9543, January 1980. ~
- 6. " Methods for Estimating Atmospheric Trangert and Dispersion of Gaseous
( Effluents in Routine Releases from Light-Water-Cooled Reactors", Regulatory Guide,1.111, Rev.1. July,1977.
- 7. "The Atomic Nucleus" R.D. Evans, McGraw-Hill, 1955.
- 8. " Radiological Health Handbook", U.S. Dept. Health, Education and Welf are, !
P.H.S., 8RH, 1970. ! I 1 - 1 1 l X006923a.08 861 4
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