ML20079K224
| ML20079K224 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/31/1991 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13309A968 | List: |
| References | |
| PROC-910831, NUDOCS 9110210101 | |
| Download: ML20079K224 (86) | |
Text
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h wD e RECElvED CDM i AUG 311991 August 31, 1991 blIbIILE CO Y
SUBJECT:
. UNITS 2/3 0FFSITE 003E CALCULATION MANUAL Revision 24 Enclosed is Revision 24'to the Units 2/3 Offsite Dose Calculation-Manual (00CM). This revision added the componen' noling water, storage tank area, '
ano auxiliary building sumps as liquid ' s 2p points and updated default flow rates from the common plant vent stack ad:? . tonally, radiation monitor -
calibration constants wov uad='ed toa S .t recent surveillances and there was one editorial change tm typographical errors. None of the changes result in any modifications to either the plant configuration or operation. As such, there is.no impact on the accuracy or reliability of methods for determining effluent dose or:setpoint values, i A. complete list of the changes is attached to thi' letter and safety reviews have been performed for the ic110 wing changes: ,
- o batch release of the storage tank area sump via 2(3)RT-7821-o- 1 continuous release of the auxiliary building sump via 2(3)RT 7821 No positive fludings were found in any of the-safety evaluations.
No safety evaluations were performed for updating default flow rates.for releases- from the plant vent stack or radiation monitor calibration constants.
Both changes _ reflect results from routine surveillances.and t! such do not constitute a modification in methodology for determining activity released from the Site and subsequent dose to a met of the public.
.Per NRC Generic Letter 89 01, no safety' review was required or performed for the correction of' typographical error $.
E 9110210101 91101$
_PDR ADOCK 05000361 R PDR
Indicatcs typographical, sequential sectional and page number *ng, and format changes only - no safety review required.
1-2 In is'ote under batch release table, added Component Cooling Water Sump and h*orage Tank Area Sump.
1-2 'In Note dnder continuous release table, added Auxiliary Building Sump.
14 Amended "*" note to reflect auxiliary building sump at alternate ,
continuous relea:e point via 2(3)RT-7821 when the tureint plant sump is not available.
1 26 Updated liquid eff1 cent radiation monitor calibration constants table.
2 12 For Flow Rate, changed 83000 :fm/ fan to 82000 cfm/ fan and deleted 17500 cfm for laundry facility.
2-14 For Flow Rate, changed 3.917 x 10 7 cc/sec to 3.87 x 107 cc/sec and deleted cc/sec for laundry facility.
2-22 For Flow Rate,-for 2 f.n operation 7.83E7 cc/sec changed to 7.74E7 cc/sec and for 1 fan operation 3.92E7 cc/sec changed to 3.87E7 cc/sec.
2-23 For Flow Rate, changed 83000 cfm/ fan to 82000 cfm/ fan and deleted 17500 cfm for laundry facility.
4-6 For Action Statement c, changed Table 4-1 and Table 4-2 to Table 4-3 and Table 4-4 respectively.'
4-14 Figure 4-5 updated to reflect additio .a1 liquid release points.
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O' o 0FFSITE DOSE CALCUIATION MANUAL NUCLEAR GENERATION $1TE UNITS 2 AND 3
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V 0DCM-TABLE OF CONTENTS Raut r'
LIST'0F FIGURES ....................................................... IV a
....V-Vi
- i. L I ST OF T AB L E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ,
...... Vil INTRODUCTION ................................................-
1.01 LIQUID EFFLUENTS..................... ................... ....... 1-1
[ 1-1 1.1 Concentration...............................................
~
1.1.1 Specification....................................... 1-1
- 1.1.1.1, 1.1.1.2 Survel11ances.............................. 11 1.21 Dose........................................................1 l ~. 2.1 : Specification....................................... 1-5
- 11. 2.1.1 S urve ill ance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 - 5
'l.3 Li duid Waste Treatment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . 1-6 c .
1.3.1 =Sp1cification....................................... 1-6
-1.3.1.1, 1,3.1.2, 1.3.1.3 Surveillances..................... 1-6 1.4 Liquid Effluent Monitor Setpoints........................... 1-8 I '. 4.1 : Batch Release Setpoint Determination................ 1 1.4.2 ' Continuous Release Setpoint Determination........... 1-16 i
1.5 Dose Calcul ations for Liquid Effluents. . . . . . . . . . . . . . . . . . . . . . 1-;7 1.6 Repre sentative Sampl ing. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-30 2.0 GASEOUS EFFLUENTS. .............................................. 2-1 2.1 Dose Ratcc.................................................. 2-1 2.1.1 Specification......................................... 2 2.1.1.1, 2.1.1.2 Surveillances.............................. 2-1 2 . 2 Do s e - Nobl e G a s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 - 5 2.2.1 Specification..;...................... .............. 2-5 2 . 2.1.1 - S u rve i l l a nc e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.3 Dose Radiciodines, Radioactive Materials in Particulate F o rm a nd T r i t i um . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 - 6 2.3.1 Speci fi c ati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2- 6
- 2. 3.1.1 S u rve i 11 a nc e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 - 6 Revision 22 i 08-02-90
00CM TABLE OF CONTENTS (Contir s d) 2.4 Gaseous Radwaste Treatment.. ............................... 2-7 e
2 . 4 .1 S p e c i f i c a t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 7 2 . 4 .1.1 S u rv e il l a nc e . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-. .8 . . . . . . . . . . . 2 7 2.4.1.2, 2.4.1.3 Su rv e i11 anc e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2.5 T o t al 00 5 e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 9
) 2. 5.1 Speci f i cati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 9 U . S . I .1 S u rv e t 11 anc e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 9
{k 2.6 Gasenus Ef fluent Monitor Setpoints . . . . . . . . . . . . . . . . . . . . . . . . .
2- 11 2.6.1 P l a n t St a c k . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .2-15 . . . . . . . . . 2 - 11 2.5.2 Condenser Evacuation System.........................
r 2.6.3 Containment Purgu ... .............................. 2 18 I 2.6.4 W a s t e G a s He ad er . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 - 21 2.7 Gaseous Effluent Dose Ratt ................................. 2-26 2.7.1 N o bl e G a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 - 2 6
~ 2.7.2- Radiot odines and Particul ates . . . . . . . . . . . . . . . . . . . . . . 2-27 2.8 Ga seous Ef fluent Dose Cal cul ation . . . . . . . . . . . . . . . . . . . . . . . . . 2-29 2.8.1 N o bl e G a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 - 2 9 2.8.1.1 Historical Meteorology . . . . . . . . . . . . . . . . . . . 2-29 Concurrent Meteorology ................... 2-30 2.8.1.2 2.8.2 Rsdiciodines and Particul ates . . . . . . . . . . . . . . . . . . . . . . 2-31 2.8.2.1 Historical Meteorology . . . . . . . . . . . . . . . . . . . 2 31 2.8.2.2 Concurrent Meteorology ................... 2-33 ._ .
2.9 Tot al Do s e Cal cul ations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-81 2.9.1 Total Dose to Most Likely Member of the Public .... 2-81 ,
2.9.1.1 Annual Total Organ Dose . . . . . . . . . . . . . . . . . . 2-81 2.9.1.2 Annual Total Whole Body Dose . . . . . . . . . . . . . 2-82 2.9.1.3 Annual Total Thyroid Dose . . . . . . . . . . . . . . . . 2-83 3.t PROJf.CTED DOSES 3.1 Liquid Dose Projection ..................................... 3-1 3 . 7. Gaseous Dose Projection .................................... 3 1 4.0 EQUIPMENT ....................................................... 4-1 4.1 Radioactive Liquid Effluent Monitoring Instruinentation...... 4-1 1 4 .1.1 S p e c i f i c a t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 - 1 4 .1.1.1, a .1 1.2 Sur v ei11 anc e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4- 1 w
Revision 23 ii 02-28-91
l e e ODCM TABLE OF CONTENTS (Continued)
P.lat 4.2 Radioactive Gaseous Effluent Monitoring Instrumentation,.... 4-6 4-6 4.2.1 Specification.........................................
4 . 2 .1.1 Surv e il l an c e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 6 4.3 Operability of Radioactive Waste Equipment.................. 4 13 5.0 Radiologic al Environmental Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5-1 5.1 Monitoring Program..........................................
5-1 5.1.1 Specification...................................
5-2 5.1.1.1 Survet11ance....................................
5 11 5.2 Land Use Census.............................................
5 11 S.2.1 Specification...................................
5-11 5.2.1.1 Surveillance....................................
5.3 Interl aboratory Comparison Program. . . . . . . . . . . . . . . . . . . . . . . . . . 5-12 5-12 5.3.1 Specification...................................
5 12 5.3.1.1 Survet11ance....................................
5.4 Annual Radiological Environmental Operating Report.......... 5-13
- 5. 5 ' S ampi e Loc at i on s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 14 6.0 Administrative...................................................
6-1 6.1 Definitions.................................................
6-1 6.2 Administrative Control s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6 6.3 Major Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous)........... ............................ 6 8 6.4 Bases....................................................... 6-9 Revisiert 22 iii 08-02-90
- s
- , ,
00CM LIST OF FIGURES
[j,aure Title Paae SiteBou5daryforLiquidEffluents............................... 17
-12 2 2 ~ Si te Boundary f or Ga seous Ef fluents. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-10 45 SONGS-2 and 3 Radioactive Liquid Waste Treatment Systems......... 4-14 46 SONGS 2-and 3 Radioactive Gaseous Waste Treatment Systems......... 4 15 4 7 Sol i d Wa s te H andl i ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 16 i- . .
51; Radiological- Cnvironmental Monitoring Sample Locations........... - 5-23 t
.e Revision 22 iv 08 02 90
~*
a_ -
L L,
ODCM i
LIST OF TABLES
- Tabl e Title Pace 1-1
. Radioactive liquid Waste Sampling and Analysis Program.....
12 1-3 Liquid Effluent Radiation Monitors
- Calibration Constants ..................................... 1 26 1 Dose Commitment Factors j A , ...................... ........ 1 28 21 Radioactive Gaseous Waste Sampling and Analysis Program..... 2 2 23 -Gaseous Effluent' Radiation Monitor.
Calibration Constants ..................................... 2 25 2-4 Dose Factors for Noble Gas and Daughters . . . . . . . . . . . . . . . . . . 2 35 2-5 Dose Parameters i P k ....................................... 2-36 26 Controlling Location Factors .............................. 2-37 2 - 7 .- Dose Parameters 4R for Sector P............................. 2 2 Dose Parameters Rj --for Sector Q............................ 2-41 2 Dose' Parameters gR for Sector R............................ 2 50 2 Dose Parameters Rj for Sector A............................ 2 55 2-1L Dose Parameters gR for Sector B............................ 2 58 2-12 Dose Parameters gR for Sector C............................. 2-61 L 2-13' -Dose Parameters Rj for Sector D............................ 2-66 i2 14: Dose Parameters Ro for Sector E...........................'. 2 69
- o 2 15 Dose Parameters gR for Sectcr F............................ 2-72 2-16: 2-77 Dose' Parameters R[ for Sector:G............................
4-1: Radioactive Liquid Effluent Monitoring Instrumentation .... 4-2 42 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements..._............................... 4 4-3 : Radiosctive Gaseous Effluent Monitoring Instrun>entation.. . ..- 4-7 4-4 Radioactive Gaseous Effluent Monitoring Instrumentation
!- Surveill ance Requirements. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 y Revision 23 02-28 91
~..y.,
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--s:is,_' -,e +
-i
.v i e 00CM LIST-0F TABLES (Continued))
Title Paae
-T abl e- s 5 3' ,
51 Radiological Environmental Monitoring Program. . . . t. . . . . . . . . .
52= Reporting Levels for Radioactivity Concentrations in- ;;
Env i ronment al _ S ampl e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . c. . . . . . . . 5 ;7 58-Maximum Values for the-Lower Limits of Detection (LLD).....
. 5 3; 7
Radiologica1' Environmental Monitoring Sample! L ocations..... 515 544 '
5 21 55 l Plc Radiological Environmental Monitoring Locations........ ,
15 6- Sector and Direction Designation for Radiological;
- Environmental Munitoring Sample Location Map .............. 5 .
16 1? Ope r at i on al Mode s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 - 4 65
,6 2 Frequency Notatico...........................;..............
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vi Revision.21-02-15-90 l
-l'
= - - -
1HTRODUCT10fj The OFFSITE DOSE CALCULATION MANUAL (00CM) is a supporting document of the RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (NUREG 0472). The ODCM enumerates dose and concentration specifications, instrument requirements, as well as describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents. In order to meet release limitations it additionally calculates the liquid and gaseous effluent monitoring instrumentat'm alarm / trip setpoints. The environmental section contains a list of the sample locations for the radiological environmental monitoring program.
The ODCM will be maintained at the Site for use as a document of Specifications and acceptable methodologies and calculations to be used in implementing the Specifications. Changes in the calculational methods or parameters will be incorporated into the ODCM in ordcr to assure that the ODCM represents the present methodology.
vii
- - - - - - - - _ - - _ _ _ ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _
1.0 LIQUID .:FFLUENTS 1.1 COHt.ENTRATION SPECIFICATION 1.1.1 The concentration of radioactive material released from +5e site (see figure 12) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix 8, Taole II, column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved ar entrained noble concentration shall be limited to 2microcuries/mix 10 gases, the total activity.
APPLICAllljl11 At all times 80.I1081
- a. With the concentration of radioactivo material released from the site exceeding the above linits, imediately restore the cor, centration to within the above limits.
SURVEILLANCE REOUIREMENTS
.1 Radioactive liquid wastes shall be sampled and at alyzed according to the sampling and analysis program of Table 1-1
.2 The results of the radioactivity analytes shall be used in accordance with the methodology and parameters in Section 1.4 to assure that the concentrations at the point af release are maintained within the limits of Specification 1.1.1.
i 1-1 Revis' ion 22 08-02-90
-- - ----- - - _ _- __ _ _ _ _ "-----"--------_mm ___.___ _
- f. .
IMLL 12.1 RADIOACTIVE L10010 WASTE SAMPllNG AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Sahpling Analysis lype of Activity (LLD)
'tiquid Release Frecuency Freagnev Analysis -
(uti/mli"
_, T yne P P A. Batch Weste 5x10
r Releaseo Each Batch Each Batch Principa} Gama Emitters 1 131 lx10
M Dissolved and lx10
P OneBatch/M Entrained Gases (Gamma emitters)
M H3 1x10
P b
Each Batch Composite lx10',
Gross Alpha Sr 89, Sr 90 5x10**
P Q Each Batch Cbmposite b Fe-55 lx10**
1 Primary Plant Makeup Storage Tanks, Radwaste Primary Mll DATCH RELEASE PATHWAYS:
Tanks, Radwarte Secondary Tanks, Miscellaneous Waste Condensate Mnnitor Tanks, Blowdown Processing Sump, FFCPD sumps (high conductivity, low conductivity), 4 Component Coohng Water Sume Storage Tank Ana Sump.
B. Continuous D W Principa} Gamma 5x10
Releases'. Grab Sample Composite c Emitters 1-131 lx10**
M M Dissolved and lx10**
Grab SP.mple Entrained Gases (Gamma emitters)
H-3 lx10**
D M Grab Sample Composite C Gross Alpha lx10
D Q Grab Sample Composite Sr-89, Sr-90 5x10**
Fs-55 lx10 '
Elf CONTINUOUS RELEASE PATHPA: Turbine Plant Sump *, Blowdown Processing Sump,** A S/G Blowdown Bypass Line* , S/G Bi Exchanger, Auxiliary Building s ep.gwdown, Salt Water Discharge from CCW H 1-2 Revision 24 08-31-91
o x. TABLE 1 1- (Continued) 1 TABLE NOTAT10N'
- a. The LLD is the smallest concentration of radioactive material-in-a sample that; will-be detectad with 95% probability with 5% probability of_ falsely concluding-that a blank observation represents a "real' signal.
For a particular measurement (system (which may include radiochemical separation): 4.66 s r b
-LLO =
E . V e 2.22 x 10" . Y . exp ( Aat) . where:- LLD is the 'a priori" lower limit of detection as defined above (as microcurie _perunitmassorvolume), is the standard deviation of the background counting rate or of the sb counting rate of a blank sample as appropriate (as counts per mine te), E is the counting efficiency (as counts per transformation), Visthesamplesize(inunitsofmass-orvolume),
- 2.22 x-106 is the number of transformations per minute per microcurie, i Y is the fractional radiochemical yield (when applicable), j
~
A is the radioactive decay' constant for the particular radionuclide, and at is the elapsed time between midpoint-of sample collection and time of , counting (for plant effluents, not environmental samples). The value of sb used.in the calculation'of the LLD' for a particular measurement system shall be based on the actual observed variant.e of the background: counting rate or.of'the counting rate of the blank samples (as appropriate) rather than_on
' an unverified theoretically predicted variance.
In' calculating the LLD fer a radieruclide determined by gamma ray spectrometry.. the ba::kground should include the typical' contributions of other radionuclides normally present-in the samples. Typical values of E V, Y and at should be used in the calculatich.
-It should be reeWzed that the LLD is defined as an 1 oriori (before the fact) limit representing the capability of the measurement system and not as A ~
costeriori (after the fact) limit for a particular measurement.I "For a more complete discussion of the LLD, and other detection limits, see the following: (1) HASL Procedures Manual HASL-300 (revised annually). (2) Currie, L. A., " Limits for Quclitative Detection and Quantitative Determination - Application to Radiochemistry" Anal. Chem.- 40, 586-93 (1968). (3) Hartwell..J. K., " Detection Limits for Radioisotopic Couating Techniques," Atlantic Richfield Hanford Company Report ARH-2537 (June 22,1972). 1-3 Revision 21 02-15-90
s , TABLE 1-1 (Continuedl TABLE NOTATION
- b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the '.iquids released.
- c. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collectedictor continuously in to analysis, proportion to the rate of flow of the cffluent stream, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be ~ m entative of the effluent release.
- d. A batch release is the disch, v' liquid wastes of a discrete volume.
Prior to sampling for aralyses, , ach batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sampling.
- e. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from i volume of system that has an input flow during the continuous release,
- f. The principal gamma emitters for which the LLO specification applie:. ;
exclusively are the following radionuclides: Kn 54 ~" 59, Co-58, Co 60, D In-65, Mo 99, ts-134, Cs-137, Ce 141, and Ce-lO sist does not mean
.ed. Other peaks which that only these nuclides are to be detected an- c.bove nuclides, shall are measuranle and identifiable, together with also be identified and reported.
- Administrative controls shall ensure that only one continuous release point R is discharging through a discharge path at any given time. The normal continuous release point via 2(3)RT-7821 is the tue bine plant sump.
** The first sump volume of BPS ion exchanger regeneration process shall be treated as a batch release.
Sampling of this flow is not required if at least once per 31 days blowdown bypass isolation valve (52130lMU618 for Steam Generator 2E088, S21301MU619 for Steam Generator 2E089, 531301MU618 for Steam Generator 3E088 and
$3130lMU619 for Steam Generator 3E089) is verified locked shut.
1-4 Revision 24 08 31-91
o . 1.0 LIQUID EFFLUENTS (Continued) 1.2 Ddi[ SPECIFICATION 1.2.1 The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site (see figure 1 2) shall be limited:
- a. During any calendar quarter to less than or. equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and
- b. Daring any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
APPLICABILITY: At all times ACTION:
- a. With calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification 6.9.1, prepare ano submit to the Comission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce the releases and the proposed _ actions to be taken to assure that subsequent releases will be in compliance with Specification 1.2.1. .
SURVEILLANCE REOUIREMENTS
.1 Dose Calculation. Cumulative dose contributions from liquid effluents shall be determined in accordance with Section 1.5 at least once per 31 days.
1-5 Revisio'n 21 02-15 90
3 .- L1;0 TLIQUID EFFLUENTS (Continued) 1.3 L10VID WASTE TREATMENT SPECIFICAIION 1.3.1_ The liquid radwaste treatment system shall be OPERABLE. The
~ appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid eff'oent '
from the site (see Figure 1-2) when averaged over 31 days, would gxceed 0.06 mrem to the total- body or 0.2 mrem.to any organ. . APPLICABILITY: At all times ACTION: a.: With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any ' other report required by Technical Specification 6.9.1, prepare and submit to the Comission within 30 days pursuant to Technical Specification _6.9.2 a Special Report which includes the following information:
-1.-. Explanation of why liquid radwaste was being discharged without treatment, identification of the inoperable equipment or-subsystems and the reason for inoperability,
- 2. . -A: tion (s) taken to restore the inoperable equipment to CPEkABLE status,'and
- 3. fumary description of action (s) taken to prevent a recurrence.
SURVEILLANCE REQUIREMENTS
.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with Section 3.1.
.2 _ During-plant operation-(Mode 1-4), the appropriate portions of the
. liquid radwaste treatment system shall' be demonstrated OPERABLE by-
[f operating the liquid radwaste treatment system equipment for at least 15-minutes at least once per 92 days unless the-liquid radwaste system has been utilized to process radioactive liquid
. effluents during the previous 92 days.
.3- In plant shut-down (Mode 5, 6) the appropriate portions of the liquid:radwaste treatment system shall. be' demonstrated OPERABLE by operating the liquir' radwaste treatment sy:; tem equipment for at:
least 15-minutes prior to processing liquids unless the appropriate liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.
"Per reactor unit 1-6 Revision 2Z 08-02-90
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SITE BOUNDARY FOR LIOUID EFFLUENTS EjGURE1-2
REFERENCE:
TECHNICAL SPECIFICATIONS, FIGURE 5.1-4 1-7 Revision 21 02-15-90
e p 1.0 LIQUID EFFLUENIS (Continued) 1.4 Liquid Effluent Monitor Methods of Setpoint Calculation Liquid Radwaste Effluent Line Monitors provide alarm and automatic termination of relcase prior to exceeding the concentration limits specified in 10CFR20, Appendix 0 Table 11, Column 2 at the release point to the unrestricted area. To neet this specification and for the purpose of implementation of Specificatien 1.1.1,
. the alarm / trip setpoints for liquid ef fluent monitors and ficw measurement devices are set to assure that the following equation is satisfied:
5 HPC'If II'I) F+R where: HPC,ff = the effective effluent maximum concentration permissible limit (pCi/ml) at the release point to the unrestricted area for the radionuclide mixture being released. I N fi (1-2) I( ) 1-1 HFC j 1-8 Revision 21 02 15-90 l
1.0 LIQUID EFFLUENTS (Continued) 1.4 Liquid Effluent Monitor Methods of setpoint Calculation (Continued) where: th radionuclide as F, fractional concentration of the i obtained by sample analysis. N
= number of radionuclides identified in sample analysis.
th radionuclide (10CFR20, App 3 MPC, - HPC of the i Table 11, Column 2).
- the setpoint, in pCi/m1, representative of a C,
radionuclide concer.tration for the radiation monitor measuring the radioactivity in the waste effluent line prior to dilution and subsequent release. R = the permissible waste effluent flow rate at the radiatin monitor location, in volume per unit time in the same units as for F. F
= the dilution water flow in volume per unit time. The dilution watar flow (F) is 185,000 gpm per circ pump (4 total) and 17,000 spm per saltwater pump (2 total).
The design flowrate of each circulating water pump is 205,000 gpm. The value used in the oetermination of F takes into account f actors such as frictional losses, pump inefficiency, and tidal flow, and provides reasonable assurance that the radioactive release concentration is not underestimated. 1-9 Revision 21 02-15-90
a s l 1.0 LIQUID EFFLUENTS (Continued) 1.4 Liquid Effluent Monitor Methods of Setpoint Calculation (Continued) Administrative values are used to reduce each setpoint to account for the potential activity in other releases. These administrative values shall be periodically reviewed based on actual release data (including, for example, any saltwater discharge of the component cooling water heat exchanger) and revised as necessary. 1.4.1 Batch Release Setpoint Determination The waste flow (R) and monitor setpoint (c) are set to meet the condition of equation (1-1) for the effective MPC (HPC,ff) limit. The method by which this is
- accomplished is as follows:
STEP 1: The isotopic concentration for each batch tank (or sump) to be released is obtained from the sum of the measured concentrations in the tank (or sump) as determined by analysis. C -IC g + C, + C3+Ct+C, p (1-3) where: C = the total concentration in each batch tank. (uti/ml) I C,1 - the sum of the measured concentrations for each radionuclide, i, in the gama spectrum. (pCi/ml) C, p
- the Fe-55 concentration as determined in the previous quarterly composite sample. (uti/mi) 1-10 Revision 22 08 02-90 ,
i n- o 1.0 LIQUID EFFLUENTS (Continued) 1.4.1 Batch Release Setpoint Determination (Continued) C, the gross alpha concentration determined in the previous monthly composite sample. (uCi/ml) C, the Sr 89 and Sr 90 concentrations as determined in the previous quarterly composite sample. (pC1/ml) Cg the H 3 concentration as determined in the previous monthly composite sample. (uti/ml) STEP 2: The effective MPC (MPC,ff) for each batch tank (or sump) is determined using: 1 (1-4)
'II I ( 11LC) * ( iLC) + ( TLC) , (bn/_C) + (b) 1 (MPC g) (MPC,) (MPCt ) (MPC,) (MPCp ,)
MPC,g, MPC,, MPC t , - the.limiti..g concentrations of the MPCp ,, MPC, appropriate radionuclide from 10CFR20, Appendix B Table !!, Column 2. NOTE: For dissolved or entrained noble gases, the corcentration shall be limited to 2.0E-4 pC1/ml total activity. STEP 3: The radioactivity monitor setpoint C ,(pti/ml), may now be specified based on the values of C, I , F MPC,ff and R to provide compliance with the limits of 10CFR20, Appendix B Table 11, Column 2. The monitor setpoint (cpm) is taken from the applicable calibration constants given in Table 1-3 to correspond to the calculated monitor concentration limit Cr (pCi/ml). 1-11 Revision 21 02-15-90
a , 1.0 LlQUID EFFLUENTS (Continued) 1.4.1 Batch' Release Setpoint Determination (Continued) 1.4.1,1 RADWASTE DISCHARGE LINE HONITOR (2/3-7813) The value for C,, the concentration limit at the detector, is determined by using: , (RW) (F) (C' I) - (1 5) C m RC 33
- RC jp ,{
MPC MPC,ffg HPC eff2 effn where: n = number of tanks to be released. C,ff effective gam.1sotopic concentration at the monitor for the tank combination to be released (equal to IC Tg forsingletankreleases), i R3 (E ,4)g + R2 Ihi)2+..,FRn f1 )n 1 (1-6) Rg+R2 + ... + R n (I C,g)3, (I C,g)2, etc. - the total gama isotopic concentration of first tank, second tank, etc. (pti/ml).
%,, R2 , etc. - the efflaant flow rate from first tank, second tank, etc. Values of R for each tank are as follows:
Radwaste Primary Tanks R - 140 gpm/ pump (x no. of pumps to be run) Radwaste Secondary Tanks R - 140 gpm/ pump (x no. of pumps to be run) Primary Plant Makeup Tank R - 160 gpev' pump (x r.o. of pumps to be run) Condensate Monitor Tanks R = 100 gpm/ pump (x no. of pumps to be run) 1-12 Revision 21 02-15 90
1.0 LIQUID EFFLUENTS (Continued) 1.4,1.1 RADVASTE DISCHARGE LINE MONITOR (2/3 7813) (Continued) NOTE: Since the values of R are much smaller than F, the term (F + R) in equation (1-1) may be replaced by F. kPC,ffg, HPCeff2, etc. values of E ,ff % mah M M first tank, second tank, etc.
~
C , C , etc. - values of C, the total concentration, from 3 2 equation (1 3) for the'first tank,,second tank, etc. in pCi/ml. are RW 7813 and SG88 2' 3089 2, SG88 3' 30 89 3' 02 ' 03. T 2, T3 administrative values used for simultaneous releases from the Radwaste Effluent discharge and any or all of the four Steam Generators'as well as continuous discharges from the two Blowdown Processing Systems and the two Turbine Plant Sumps. The fractions RW 7813 and SG88 2' 3089 2' 3088 3'- 0 89-3, B2 ' 03 , T 2, T3 will be assigned such that (RW7813 + 3088-2 + 6089-2
- 3088-3 _
+ SG89 3 + O2+03+T 2 + T3 ) s 1,0.
1-13 Revision 21 02-15-90
.j v
- 1. 0 .. LIQUID EFFLUEKT5_ (Cor'inued) 1.4.1.1- RADWASTE DISCHARGE LINE MONITOR (2/3 70131- (Continued)
The 1,0 is- an administrathe value used to account for the potential activity released simultaneously from other release points. This assures that the total concentration from all release points to the plant discharge will not result in a release of concentrations exceeding the limits of to CFR 20, ,
- Appendix B. Table 11, Column 2 from the- site, NOTE: If C,1 C,ff, then no release is possiblo. To increase C ,, increase dilution flow F (by running more circulating water pumps-in the-applicable dis-
. charge structure), and/or decrease the effluent flow rates R , R , etc. (by throttling the combined flow 3 2 as measured on 2/3FI-7643,,2FIC-4055, 2FIC 4056,
.3FIC-4055 or 3FIC-4056:as appropriate) and recalculate C,using the new F. R and equation (1-5).
If there is no release associated with this monitor, the monitor setpoint should be established as close to background-as-practical to prevent spurious alarms and yet assure an alarm should an inadvertent . release occur. l-14 Revision 21 02-15-90
n . 1.0 LIQUID EFFLUENTS (Centinued) 1.4.1.2 UEUTRAtlIATION SUMP / FULL FLOW CONDENSATE POLISHER DEMINERAtIZ SUMP DISCHARGE LINJ MONITOR (batch) (2RT 7817. 3RT 7817) or C , the concentration limit at the The value for C2 3 Unit 2 or Unit 3 detector, is determined by using: C $ 2)Y)fvi (1 7) 2 < -(R)(C/MPC,ff) C I 3)I 71 (1 8) C3 ~< (R)(C/MPC,gg) where: g C, = the values of C, g and PPC,ff
, HPC,ff as defined in STEPS 1) and 2) for the Neutralization Sump /FFCPD Sumps.
Neutralization Sump R = 500 gpm FFCPD High Conductivity Sump R = 500 gpm FFCPD Low conductivity Sump R = 600 gpm C 2
= the instantaneous concintration at the detector (2RT-7817) in pCi/cc C
3
= the instantaneous concentration at the detector (3RT-7817) in uti/cc B2 and B3 are administrative values used to account for simultaneous releases from both SONGS 2 and SONGS 3 neutraliz: tion sumps. The fractions B2 ""d 03 (each normally set to 0.05) will be assigned such that (RW7g33 + SG88 2
+ SG89-2 + 3088-3 + 3089-3 + 02+03+T 2 + T3 ) s 1.0.
1-15 Revision 22 08-02-90 l
, 4 ~a-a. . . _ E.e--. ,m. W.(. 7.g u. s,. .
~
T .. . . . 1,0 L . LIQUID EFFLUENTS (Continued) l',4,1,2 : REUTRALIZATION $ UMP / FULL FLOW CONDENSATE POLISHER DEMINE SUMP DISCHARGE LINE MONITOR (batch) (2RT 7817, 3RT-7817) (Continued)
+ '
NOTE: If C2or'C3sICg, then no release is possible. To increase C or C3 , increase dilution flow F (by. 2 running more pumps), and/or decrease the effluent flow-rate R, (by throttling the flow as measured on 2F13722 or C using the new and3F13772).andrecalculateC2 3 F, R and equation (1 7) or (1 8). If:there'is no release associated with this monitor, the monitor setpoint should'be established as close-to background as' practical to prevent spurious alarms and yet assure an alarm
-should an inadvertent _ release occur, 1.4.2 Continuous Release Setpoint Determination l' The waste flow (R) and moniter setpoint (C ,) are set to meet the condition of equation (11) for the effective MPC (MPC,ff)
L limit. The method by which this is accomplished is as-follows: i 'h STER 1: The isotopic concentration for-the continuous releases are obtained for each release stream (steam generator blowdown, steam generator blowdom bypass, blowdown neutralization sump.and turbine plant sump) from the sum of the respective measured concentrations as , determined by analysis: C= , + C, + Ct+Cs+C, p (1 9)- 1 - 14, Revisio! 22 08-02-94 i L ._ , - . . __ . _ . _ . -, , . _ . , _ _ _ . _ . -
,a
3 1 4 : 1 1.0- -LIQUIDEFFLUENT5'(Continued) Continuous Release Setpoint Determination'(Continued) 1.4.2; where: C' - total concentration (pCi/ml)
= the total gamma activity (pCi/mi) associated wi'.h g
each radionuclide, i, in the weekly composite u. analysis for the release stream.
~the total measured gross alpha concentration (pC1/ml)
C, determined from the previous monthly composite analysis-for the release stream. C - the total Fe-55 concentration (pCi/mi) as cetermined Fe. in the previous quarterly composite sample for the
~
release stream. Cg - the total measured H 3 concentration (pci/ml) determined from the previous monthly composite analysis for the release stream. , a C, -- the total measured concentration (pCi/mi) of Sr-89
-and Sr 90 as determined from the previous quarterly composite analysis for the release stream.
STEP 2: Theeffar.tiveMPC(MPC,ff)foreu.hreleasestream(steam generatr,r blowdown, blowdown neutralization sump, or - turbine plant sump) is determined us) I (1-10) MPC - I ( 21/.s) , b/1) + (_aLC) + ( En/I) * (Cgj,q) 1 (MPC9 ) (MPC3 ) (MPC,) (MPC p ,) (MPCg ) 1-17 Revision'22 08 02-90
s , 1.0 LIQUID EFFU'I.NTS (Continued) 1.4.2 Continuous Rclease Setpoint Determination (Continued)
$1[P_J: The setpoint C , (uti/ml), for each continuous release radioactivity monitor may now be specifiec based on the respective values of C IC,g, F. MPC,gf. and R to prSvide comcliance with the limits of 10CFR20 Appendly B: Table 11. Column 2.
The monitor setpoint (cpm) is taken from thi applicable calibration constants given in Table 1-3 t' ; . respond to the calculated monitor limit C, (sci /ml). 1 18 Revision'21 02 15 90
&.7, l-L l,
1.0 LIQUID EFFLUENTS . (Continuv.'
' l.4.2.1 NEU"RAllZATIQUUMPDistHARGEtlNEMONITORS f2R"-78 L7. 3RT 7817)
The value for C or C3 , the concentration ilmit at the 2 Unit 2 or Unit 3_ detector is determined by usingt (1 11) (8)(F)rC1^g 2 Cs g , j (R)(C/MPC,gg) i (112) 1 (B)(F)rc,, 3
.C3 s 1 (R)(C/MPC,ff) where:
l C. . "?C,gg . the values of C, r C,4 and MPC,gf as defined in STEPS.) and 2 for-the
- Steam Generator blowdown / BPS neutra -
11 ration sump. t R- The effluent flow rate at the radiation monitor as defined in STEP 2 (maxteusof500gpa). C2= the instantar.cous concentration at the Unit 2 detector (2RT 1817) in pCi/cc (- the instantaneous concentration at the C3+ Unit 3 detector (3RT-7817)inpCi/cc B2 and B3 are administrative values used to account for q imultaneous releases frbi both SONGS 2 and SONGS 3 ne,'ralization sumps. Th6 fractions B 2 and B3 will be assigned such that.(RW7813 + 5088 2 + 5089 2 + 3088 3 + 3089 3
- +B2+03+T j + T3 ) i 1.0 1-19 Revision'22 08 02 90.
L
1.0 LIQUID EFFLUEMIS (Continued) 1.4.2.1 !GIf)1]IA11ClLiW1 nIstHARcE LINE MONITOR (2RT 7817. 3F1 78171 (Continued) NOTE: If C2 or C 3 5yC,,,thennore.leaseispossible. To increase C 2 0 ,3 increase dilution flow F (by runningmorecirculatingwaterpumps),and/ordecrease the effluent flow rate R (b/ throttling the flow as measured on 2F13722 and 3F13772), and recalculate using the new F. R and equation (1 11) or C2 cr C3 (112). If there is no release associated with this monitor, the monitor setpoint should be established as close to background as practical to trevent spurious altras and yet assure an alarm shouid an inadvertent release occur. E \t . N 1 20 Revision 21 02-15 90
1.0 LlQUlb EFFLUENTS (Continued) 1.4.2.2 iTEAM CINERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2R1 6753, 2RT 6759. 3RT 6753._3RT 6759) or C $3,3, the concentration The value for C50 2' C53 2' C59 3 limit at the Unit 2 or Unit 3 detectors, is detemined by using: C 88 2 ( 7 (ll3) H*2 5 (R)(C/MPC,77) (50892)(F)yC.,4 { ,}4) c 53 *I 3 (K)M/MPC,gg) ($ 88*3}(} 71 (1 15) C 59 3 1 (R)(C/$PC,ff) g IS0893)(F)yC71 (116) 53 3 5 (R)(C/MPC,gg) where: C, I C,g, MPC,gg - values of C I C,4 and MPC,ff (as defined in STEPS 1 and 2 above) for the steam generator blowdown bypass. R = the maximum blowdown bypass effluent flowrate per steam generator, 200 gpm. C = the instantaneous concentration at the Unit 2 detector 59 2 (2RT6759)inpCf/mi C = the instantaneous con:entration at the Unit 2 detettor 53 2 (2RT 6753) in pCi/ml C 59 3
= the instantaneous concentration at the Unit 3 detector L
(3RT 6759) in pCi/mi C 53 3
= the instantaneous concentration at the Unit 3 detector (3RT-C753) in pC1/mi 1 21 Revision 21 02-15 90
l 1.0 LIQUID EFFLULNTS (Ct;ntinued) 11,tAMGENERAYORBLOW2GNBYPASSDLSCHARGELINEMONITORS l 1.4.2.2 H},16753. 2Rb6759. 3RT 6753. 3R" 67591 (Continued) RW7gg., and SG88 2' 5089 2, SGgg,3, SG gg,3, B2 ' 03 . T 2, 13 an administrative values used for simultaneous releases from the Radwaste Eftluent discharge and any or all of the four Steam Generators as well as continuous disch:rges from the two Blowdown s Processing Systems and the two Turbine Plant Sumps. The fractions RW7813 and SG88 2, SG89 2' 3088 3' 30 89 3' 82 ' 03 ' I 2, 73 will be assigned such that (RW7813 + 5088 2 + 8089 2 + 3088 3 -
+ SG 89 3 82 + B. + T 2*I)$1.0. 3 The 1.0-is an administrative value used to account for the potential activity released simultaneously from other release
- points. This assures that the total concentration from all release points to the plant discharge will not result in a release of concentrations exceeding the limits of 10 CFR 20, Appendix B. Table !!, Column 2 from the site.
NOTE: If C59 2, C53 2 C59 3, or C$3,3 s y C,g (for the respective steam generator), then no release is possible. , To increase C59 2, C53 2, C$9,3 or C53 3, inenas's dilution flow F (by running more circulating water pumps), and/or decrease the affluent flow rate R (by throttling the flow as measured on 2FIC 4055, 2FIC 4056, 3FIC4055,3FIC4056or2/3F17643,asappropriate)and recalculate C53 2, C53 2, C59,3 or C$3,3 using the new values of F, R and equation (1-13), (1 14), (115) or (116). 1 22 Revision 21 02-15 90 l
..# -. . _ _ _ _ _ - . _ _ . , _ , . _ . _ , , ~ . . _ . - - - , _ . . _ , _ . . - . ~ . _ . _ - , , _ . . . - - _ . _ , . , _ . , , _ _ .
- r 1.0 11Q010 EFFLUENTS (Continued) 1.4.2.2 111A3_1[NERATOR.1LOVDOWN BYPASS Ol} CHARGE LINE MONITOR $
H PT 6753, 2RT 6759. 3RT 6753. 3RT 67591 (Continued) If there is no release associated with this monitor, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet assure an alarn shou ~:d an inadvertent release occur. 1.4.2.3 TURBINE PLlJ4T SUMP @NITORS f fRT-787L 3RT-78211 The value t'or2C or C3 (the concentration limit at the Unit 2 or Onit 3 wetector) is detsrmined by using (T (1-17) C g $ _ 2)(F)tC1g (R)(C/MPC,gg) l (T)(F)rt,g (1 18) l 3 i C ! 3 s (R)(C/MPC,gg) i where: C, g, MPC,gy - values of C. g arid HPC,ff (as defined in STEPS 1 and 2 above) for the turbine plant sump l R -50gpypump(xno.sumppumpstoberun) C 2 the instantaneous concentration at the Unit 2 detector (2RT-7821) in pCi/ml. the instantaneous concer,tration at the Unit 3
- f. C3 detector (3RT-7821) in C1/ml.
1 23 Revision 21 02 15 90
'~
p-'-'s + - *T T
M =. ; , V , . 1.0 LIQUID EFFLUENTS (Continued) 1.4.2.3 TURBINE PLANT _ SUMP MONITQ M RT 7821. 3RT 78211 (Continued) T2 and T3are administrative values used to account for simultaneous releases from both SONGS 2 and SONGS 3 turbine plant sumps. The fractions T2and T3 will be assigned such that(RW7333 + SG88 2
- 30092*$ Bf,+3 * $ 89 3 2*03*T2 ,
+T)i1.0,3 NOTE:- If C2 or C3s C,4(fortherespectivesump),then l
- no release is possibic. To increase C2 or C3, increase the dilution flow F (by running more circulating water t
- pumps)andrecalculsteC2 or C3using the new value l ofFandequation(117)or(1-18). :
Use of a temporary dis:harpe path from the Turbine Plant Sump is 3 allowed providing the. radiation monitor, 78ci, in service a. J the r normal discharge path B " sed concurrently. Temporary pumps facilitate faster dist eben draining the condenser.to the " outfall via this pithway. The following conditions shall be met 3; t
- a. The release permit shall account for the entire volume of water discharged from the lurbine Plant Sump.
' b. The alam setpoint for the monitor shall be adjusted to take into account the entire discharge flow through both the nomal and temporary paths.
- c. Procedures shall require the immediate termination of the i discharge via the temporary path if the monitor on the normal
( ~ path alarms. 7 s. 1-24 Revision 21 02 15 90 N
--- ,, 4 - 3 -..de, -
.-,,---q%~re-,. --
- m E ws w-,, y-, .,v-.v,-,, e. . re w -- i-vvww wy -=v, 3v,- .
v-vnyw,,-*'-- m y - --- v --v - r' w y r + - r n '- S'-"
1.0 LIQUID EFFLUENTS (Continued) 1.4.2.3 TURBINE PLANT SUMP MONITORS (2RT 7Q21. 3RT 7821) (Coatinued) If there is no release associated with this monitor, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet assure an alarm should an inadvertent release occur. t l 25 Revision 22 08 02 90
--.= g- -- eee' --e ---.cpme. gr,
l Table 1 3 Liquid Effluent Radittion Monitor Calibration Constants (pC1/cc/ cpm) Co*60 RAf133 Ct 137
-MONITOR 2RT 6753- 1.80E 8 1 010 8 f I
2.14E R 1.99E 8 2RT 6759-2.14E 8 1.96E 8 < 3RT 6753 : I 3RT 6759- 1.79E 8 1.94E 8 __
- 2.12E 9 3.59E*9- 5.20E.9 ft ;
2/3RT7813 ;
-2RT 7817 2.43E 9 3.40E 9 4.89E 9 2RT 7821 2.14E 9. 3.63E 9- 5.21E 9 ,
'3RT-7817 2.33E 9 3.22E 9 4.73E 9 3RT-7821' 2.13E 9 3.64E 9 5.20E 9 I
4 l t c : I"I This table provides typical (120%)' calibration constants for the liquid ; effluent radiation monitors. , 1 26 Reviston 24 08 31 91
~ - ' .. , , . .. # L m~ , ,, ~,;L ,. ., ' _..,.._m,,,.... ._ ..~_. ., ,..,. ----,.__, ,. _ . ,... _ _ .. ... ,_ _ _ _ , _ . _,,m... _.._,_._.;-,,_Z1.,
l I 1.0 LIQUlb EFFLUENTS (Continued) 1.5 Dose calculation for Liquid Effluents The liquia releases considered in the following dose calculations are described in Section 1.4. The dose comitment to an individual f rom raditactive materials in liquid effluents released to unrestricted areas are calculated for the purpose of implementing Specification 1.2.1 using the following expression. I(Ag, E(at) Cg ) Fj )) (1 19) D, where: the site t elated adult ingestion dose comitment A,q factor to the total body or an orgar, r, for each identified principal gama and beta emitter, i, from Table 1 4 in mrem /hr per pCi/ml.
- the average concentration of radionuclide, i, in the C) g undiluted liqcid effluent during time period, at)in(pC1/ml).
D, = the dose comitment to the total body or an organ, e, from the liquid effluent for the time period, Atj,inmrem F)
- the near fleid average dilution f actor for Cg) during the time period, at). This factor is the ratio of the maximum undiluted liquid waste flow during time period, at3 , to the average flow from the site discharge structure to unrestricted receiving waters, or taximum 'tiouid radienctive waste flow discharge structure exit flow at j =
the length if the jth time period over which Cg3 and Fj are averaged for all liquid releases, in hours. . 1 27 Revision 23 l 02 28 91
~ . . . . .. . ..
6 . IABLE 1 4 005E COMMITMENT FACTOR 5*, AI ' (nrem/hrperpCi/ml) Radio- Total Liver Body Thyroid Kiriney Lung GI LLI Nur.lide Bone 2.82E 1 2.82E 1 2.82E 1 2.82E 1 2.82E 1 2.82E 1 H3 4.57E 1 4.57E-! N 24 4.57E 1 4.57E 1 4.57E 1 4.57E 1 4.57E 1 5.58E+0 3.34F+0 1.23E40 7.40E40 1.40E+3 Cr 51 7.06E+3 1.J5E+3 2.10E+3 2.16E+4 Mn St 1.78E+2 3.1;E+1 2.26E42 5.57E+3 Mn 56 8.23E+3 1.97E44 2.03E+4 Fe 55 5.llE+4 3.53E+4 6.32E+5
.'e 59 8.06E+4 1.90E45 7.27t+4 5.30E+4 2.36E42 3.59E+3 Co 57 1.42E42 1.35E+3 1.22E44 Co.56 6.03E+2 3.82E+3 3.25E+4 Co 60 1.73E+3 1.01E+2 5.40E+2 1.83E+4 Cu 64 2.14E42 1.61E+5 5.13E45 2.32E45 3.43E45 3.23E+5 Zn 65 9.39E 2 7.37E 7 Br 84 Rb ES 1.79E+0 9.49E,.1 2.47E 11 1.43E+2 8.00E+2 Sr 89 4.-99E43 Sr 90 1,23E+5 3.01E+4 3.55E+3 Sr 91 9.18E+1 3.71E+0 4.37E+2 Sr 92 3.48E+1 1.51E40 6.90E+2 Y 90 6.06E+0 1.63E 1 6.42E+4 Y 91m 5.73E 2 2.22E 3 1.68E 1 Y 92 5.32E 1 1.56E 2 9.32E+3 Zr 95 1.59E+1 5.llE+0 3.46E+0 8.02E+0 1.62E+4 Ir 97 6.81E 1 1.78E 1 8.13E 2 2.68E 1 5.51E+4 Hb 95 1.84E+0 1.03E+0 5.51E 1 1.01E+0 6.22E43 Nb 95m 1.34E+0 1.03E+0 5.51E 1 1.01E40 6.22E+3 Nb 97 1.55E 2 3.91E 3 1.43E 3 4.56E 3 1.44E+1 M: 99 1.28E+2 2.43E+1 2.89E+2 2.96E+2 Tc 99m 1.30E-2 3.66E 2 4.66E-1 5.56E 1 1.79E 2 2.17E+1 Ru 103 1.07E+2 4.60E+1 4.07E+2 -
1.25E+4 Ru 106 1.F9E+3 2.01E+2 3.06E+3 1.03E+5 Ag llom 1.42E+3 1.32E+3 7.82E+2 2.59E+3 5.37E+5 Sn 113 2.26E+5 Sn 117m 2.26E45 Sb 124 2.76E+2 5.22E+0 1.09E+2 6.70E-1 2.15E42 7.84E+3 Sb 125 1.77E+2 1.97E+0 4.20E+1 1.7aE 1 1.36E+2 1.94E+3 Te-129m 9.31E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 4.69E+3 Te 132 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 6.24E+3 1 131 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E42 8.23E+1 1 132 1.06E+1- 2.85E+1 9.96E+0 9.96E+2 4.54E+1 5.35E+0 1 133 7.45E+1 1.30E+2 3.95E+1 1.90E+4 2,26E+2 1.16E+2 1-134 5.56E+0 1.51E+1 5.40E+0 2.62E+2 2.40E+1 1.32E 2 1 135 2.32E+1 6.08E+1 2.24E+1 4.01E+3 9.75E+1 6.87E+1 NOTE: Where no value is 91ven, no data are available.
- Source: Reg. riuide 1.109, Table E ll, Table A 1 USNRC NUREG 0172, Table 4
- Methodology: USNRC NUREG 0133, Section 4.3.1 1-28 Revision 23 02 28 91 L
I
r 4: TABLE 1 4 l DOSE COMMITMENT FACT 0kS* Ag' (mrem /hr per pC1/ml) l Radio. Total G1 LL1 Thyroid Kidney Lung
. Liver Body Nuclide Bone t
1.75E+3 2.85E+2- i 1.33L:4 5.27E+3 : C5 134 6.84E+3 1.63E+4 2.1GE+2 3.21E+2 2.04E+3 1.57E+3 Cs 136 7.16E+2 2.83E+3- 1.35E+3 2.32E+2 7.85E+3 4.07:+3 Cs 137 8.77E+3 1.20E+4- 8.70E 1 5.12E 5 5.94E+0 8.81E+0 Cs 138 6.07E+0 1.20E+1 3.17E 3. .1.39E+1 5.59E 3 2.30E 1 5.23E 3 Ca 139 -7.85E+0 7.02E 1 1.18E+0 3.38E+3 Ba 140 1.64E+3 2.06E+0 1.08E+2 5.83E+4 La 140 1.571+0 7.94E 1 2.10E 1 0.86E+3 2.32E+0 2.63E 1 1.08E+0 Ce 141' 3.43E+0. 1.67E+4 4.46E+2 4.94E 2 1.97E 1 Ce 143- 6.04E 1 4.43E+1 6.04E+4 Ce 144 1.79E42 7.47E+1 9.59E+0 2.68E+0 2.20E+4 Nd.147 -3.96E+0 4.5WE+0 2.74E 1 ' 2.51E+3: . W 187 ~9.16E+0~ 7.66E+0 2.68E+0 1.08E 2 7.11E+2 } Np 239 3.53E 2 3.47E 3 1.91E 3 1 NOTE: Where no value is given, no data are available.
- Source - Reg. Guide 1.109. Table E-11, Table A 1 USNRC NUREG 0172. Table 4
*Methodologys ' USNRC NUr.EG 0133, Section 4.3.1 l
- l l.
l ; l i- , 1 29 Revision 23 02 28 91 i
- . . . . . . . - . _ . - _ _ . . ..:-...-.....-. .- - . - - - ~ . - , _ - . - _ - . . . . _ . . . , . . . . ~ . . . . - . . . .
e . 1.0 LIQUID EFFLUf.NTS (Continued) 1.6 Representative $ntapling Prior to sampling of a batch release, each batch shall be thoroughly mixed to assure representative sampling. The methodology for mixing and sampling is described in 50123 111 5.11.23, " Units 2/3 Liquid Effluent Release Permit
- and 501231115.2.23, " Units 2/3 Liquid Effluent sample Collection".
9 1 300le. man- 3 30 Revision 21 02 15 90 i __ _ . . . . . _ . . _ . . _ . _ _ _. ~ _ _ _
}. ,
I l P 2.0 SA$E005 EFFLUENTS
- 2.i DOSE RATE )
$PECffIEATION 2.1.1 The dose rate in unrestri 'sd areas due to radioactive l materialsreleasedingastrJeffluentsfromthesite(see Figure 2 2) shall be limited to the following: !
- 4. For noble gases: Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the l skin, and t
- b. For all radiciodines, tritium and for all radioactive 4
naterials in particulate form with half lives greater thM ! i i-' 11 days: Less than or equal to 1500 mrem /yr to any organ, f APPLICABIL11Q At all times ; AC110Ni % e a.- With dose rate (s)_excueding the above limits, immediately ? ' decreasethereleaseratetowithin_theabovelimit(s). SURVf1LLANCE RE00fREMENTS [
?
.1 The dose rate due to noble gasas in gaseous effluents shall be
! determined to be within the abcVe limits in accordance with Section 2.7.
.2 The dose rate due to radiciodines, tritium and -adioactive materials in particulate fom with half lives greater than 8 days in gaseous effluents shell be detemined to be within i l
the move limits in accordance with-Section 2.7 by obtaining j rep.*esentative samples and performing anal,yses in accordance with the sampling and analysis progra9 specified in Table 2-1. i I ( f i
.l h
t y t i~ 21 Revision 21 ! l 02 15 90 [ ) 6 m , ar- - - we n,, -,,,,,ww,,--,,,,e,--e +w,en-,,-e,w er m ,,, m ,a e,n--,z..--we.--,e.-w.-mern,,,,.m,--,,.--+.w-,,,,,ne--m,-----e,.ww-w+nn,,,r,- n+
TABLE P 1 RADIDACTIVE GA5EOUS WASTE SAMPllNG AND ANALYSIS PPjjif g l i l Minimum Type of Lower Limit Gaseous of Detection Release Sampling Analysis Activity Frequency Analysis (pCi/ml)a Type Frequency P Batch P Principal Gama Emitters 9 lx10** Waste Gas Each Tank Each Tank Decay Tank Grab Sample Each Batchi Principal Gama Emitter 19 $x10*' incine.ated Each Batchi Oilh Grab Sample -
*
- Principal Gama Emitters.9 lx10**
Continuous
*
- Tritium lx10*'
Wd 1.}3g ly30.n Continuous f Charcoal l x10* " Sampler Sample 1 133 + Wd Continuousf Particulate Principal Gama Emitters 9 lx10 * ' Sampler Sample (1131andOthers) H Continuousf Composite Gross Alpha lx10*88 Sampler Particulate Sample Q Continuousf Composite Sr 89 and Sr 90 l x10* ' Sampler Particulate
- Sample Cor.tinuousf Noble Gas Noble Gases lx10**
Monitor Monitor Gross Beta or Gama
- Sampling frequencies for noble gases and tritium are: ,
CONTINUOUS PATHWAYS: Containment Purge - 42' : Each Purgeb ,c Containment Purge 8' : Monthly Grab b Condenser Air Ejector : HonthlyGragb Plant Vent Stack : b'eekly Grab i' 22 Revision 12 08 02-90
6 TABLE 2-1 (Continued) TABLE NOTATION
- a. The LLD is the smallost concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation): 4.66 s b LLD = E V e 2,22 x 10' Y . exp ( Aat) where: LLO is the 'a priori' lower limit of detection as defined above (as microcurie per unit n ss or solume), is the standard deviation of the background counting rate or of the sb counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per transformation), V is the sample size (in units of mass or volume), ' 2.22 x 106 is the number of transformations per minute pee microcerte, Y is the fractional radiochemical yield (when applicable), a is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and time td counting (for plant effluents, not environmental samples). The value of sb used in the calculation of the LLO for a particular measurement system shall be based on the act';al observet: variance of the background counting rate or of the counting rate of the blank sampics (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLO for a radionuclide determined by gama ray spectrometry, the background should inciddu the typical contributions of other radionuclides normally present in the samples. Typicui values of E, V, Y and at should be used in the calculation. It shouid be recognized that the LLO is defined as an a priori (before the fact) limit representing the capability of the measurement system and not as a costeriori (after the fatt) limit for a particular measurement.*
*For a more coEplete discussion of the LLO, and other detection limits, see the following:
.(1) HASL Procedures (2) Currie, Manual, L. A., " Limits tiTSL 300Detection frr Qualitative (revised annually)d an Quantitctive 0; termination -
Application to Radiochemistry" Anal. Chem. 40, E.86 93 (1968). (3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Company Report ARH 2537 (June 22, 1972). , 23 Revision 21 02 15 90
TABLE 2 1 (Continutun TAELE NOTAT!0N
- b. Malyses shall also be performed followint shutdown, startup, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a 1 nour ,
i period. This_ requirement does not apply if t (1) analysis shows that the DOSE l EQUIVALENT l 131 concentration in the reactor coolant has not 19 creased more than a f actor of 31 and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
- c. Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded.
- d. Samples shall be changed at least once per 7 days and analyses shall be !
completed within 48 hours after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours for at least 7 days following each ,hutdown, startup, or a THERMAL POWER change exceeding.15 percent of RATED THERMAL POWER in 1 hour and analyses shall- be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. The latter requiretent does not apply if t (1) analysis shows that the DOSE EQU! VALENT l-131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) tht noble gas monitor shows that effluent activity has not increased more than a factor of 3. ,
- e. Tritium grab samples shall be taken at least one per 7 days from the venttiation exhaust from the spent fuel pool area, whenever spent fuel is in ,
l the spent fuel pool.
- f. The ratio of the sample flow rate tt the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 2.1, 2.2, 2.3.
- g. The principal ganna emitters for which the LLD specification applies exclusively are the following radionuclides: .Kr 87, Kr 88, Xe 133, Xe 133m, Xe 135, and Xe 138 for gaseous emisStons and Mn 54 Fe 5g, Co 58, Co.60, Zn 65, Ho 99, Cs-134 Ce 141 and Ce 144 for particulate emissions. This list does not mean _that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with ths above nuclidas, shall also be identified and reported,
- h. Incinerated oil may be discharged at points other than the plant vent stack.
- Release shall be accounted for based on pre-release grab sample data,
- i. Samples for incinerated oli releases shall be collected from representative samples of filtered oil in liquid form.
Y l 24 Revision 22 08 02 90 l L b ,
2.0 GA$E003 EFFLUENTS (Continued) 2.2 DOSE - NOBLE CASES SPECIFICATION 2.2.1 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site (see Figure 2 2) shall be limited to the following:
- a. During any calendar varter: Less than or equal to 5 mrad for gama radiation and less than or equal to 10 mrad for beta radiation and.
During any calendar year: 1.ess than or equal to 10 mrad for b. gama radiation and less than or equal to 20 mrad for beta radiation. LPJ"." ABILITY; .it all times ACTIO9:
- a. Wit. calculated air dose from radioactive noble gases in geseous ef fluent > exceeding any of the above limits, in lieu of any other report required by Technical Specification 6.$.), preptre and submi' % the Comission within 30 days, pursuant to Technical $4cification 6.9.2, a Special Report which identifie! the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with Specifica-tion 2.2.1.
SURVEILLANCE RE001REMENTS
.1 Dese Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section 2.8 at least once per 31 days.
25 Revision 21 02 15 90
- ~ - - - - _ _ _ - - _ _ _ - - - _ _ _ _ _ _ _ _ _ _
2.0 EtSE005 EFFLUENTS (Continued) 2.3 DOSE RADIO!ODINES. RADIDACTIVE MATERIALS IN PARTICULATE FORM AND T RITlUM SPEClflCATIQS 2.3.1 The dose to an individual from tritium, radiciodines and radioactive materials in particJ1ste fort, with half lives greater than 8 days in gasious effluents released, from asch reactor unit, from tne site (see Figure 2 2) shall be lh.ited to the following:
- n. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,
- b. During any calendar year: Less than or equal to 15 mrem to any organ,
- c. 'tess than 0.1% of the liTits of 2.3.1 (a) and (b) as a result of burning contaminated oil.
APPLICABILJ.lyl At all times ACTION:
- a. With the calculated dosi m the release of tritium, radiolodines, and radioac a materials in particulate form, with half "!ves greater that, 3 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the Consission wittin 30 days pursuant to Technical Specification 6.9.2 a Special Report which identifies the cause(s) for exceeding the liinit and defines the corrective actions taken to reduce releates and the proposed actions to be taken to atsure that subsMuent releases will be in compliance with Specification 2.3.1.
SURVEltLANCE REOUIREMENTS
.) D21t_C11Glitions Cum 114tive dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Sectior 2.8 at least orce per 31 days.
26 Revision 21
- 02 15 90 t
2.0 GASE0US d FLUENis (Continued) 2.4 GASEOUS RADVASTE TREATMENT SPECIFICATION 2.4.1 The GASEOUS RA0 WASTE TREATMENI SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be operable. The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases from the site (see Figure e 2 2), when averaged over 31 days, would exceed 0.2 mrad for gama radiation and 0.4 mrad for beta radiation. The appropriate portions of the VENTILATION EXMAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous tffluent releases from the .ite (see Figure 2 2) when averaged over 31 days would exceed 0.3 mrem to any organ.* APPLICABILITY: At all times ACTIONL
- a. With gaseous waste being discharged without treatnent and in excess of the above limits, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the Comission within 30 days, pursuant to Technical Specification 6.9 2, a Special Report which includes the following information:
- 1. Explanation of why gaseous radwaste was being discharged without treatment, identification of the inoperable equipment or subsystems and the reason for inoperability, -
- 2. Action (s) taken to restore tht. inoperable equipment to OPERALLE status, and
- 3. Sumary description of action (y taken to prevent a recurrence.
SURVEILLANCE REOUIREMENTS
.1 Doses due to gaseous releases from the site shall be projected it least once per 31 days, in accordance with Sectior. 3.2.
"These doses are per reactor unit.
2-7 Revision 22 ' 08 02 90
[ [ # , 2.0 GASE005 EFFLUENTS (Coritinued) 2.4 A&SEOUS RADWASTE TREATMENT (Continued)
$URVE1LLANCE REQUIREMENTS (Continued) ,
.2 ,, lant operation (Modes 14), the applicable portions of J DurinkSEOUSRADWASTETREATMENTSYSTEMandVENTILA110NEXH the G '
TREATMENT SYSTEM shall be demonstrated OPERA 8LE by operating , the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION. EXHAUST TREATHENT SYSTEM equipment for at least 15=
' minutes, at least once :)er 92 days unless the appropriate ,
i' system has been utilized to process radioactive gaseous effluents during the previous 92 dsys,
- r. 4
.3- In plant shut down (Mode-5, 6) the applicable portions of the- ,
GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall- be demonstrated OPERA 8LE by operating the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15 minutes prior to processing gases unless the appropriate ' i
. gaseous radwaste system has been utilized to process radioactive gaseous effluents during the previous 92 days.
. i l
r p .- P T 2-8 Revision 22 ' 08 02 90 - i e e 2,.., s - -,,v-c..~,, -c,-.w-m~,1 ,, -r------,_%y.r%,emE . pmhv.mm,,,,,r-,_, ,, co -- 7,,1,-w,_,,-r,,%.,,,,-,,y,wr-y-.+-,.myww-w.,,y,,-
2.0 CASE 0V$ EFFLUENTS (Continued) 2.5 TOTAL DOSE SPECIFICATION 2.5.1 The dose or dose comitment to any member of the 5 public, due to releast's of radioactivit/ and radiation, from uranium f"el cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive montt, APPLICABillTY: At all times ACTION:
- a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 1.2.1.4, 1.2.1.b. 2.2.1.a. 2.2.1.b. 2.3.1.a. or 2.3.1.b in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory ,
Comission, Washington, D.C. 20555, within 30 days, which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 2.5.1. This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the public from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report. If the estimated dose exceeds the limits of Specification 2.5.1, and(s) if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of paragraph !!N 11(b). Submittal of the report is consideret. a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR Part 20, as addressed elsewhere in this ODCM. SURVEILLANCE RE0VIR(M[HLi
.1 Dese Calculations Cumulative dose contributions from liquid i and gaseous effluents shall be determined in accordance with surveillance 1.2.1.1, 2.2.1.1, and 2.3.1.1.
l 29 Revision 21 02 15 90 1 L
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x_ - i w/ SITE C' Y FOR EASEBLS EFFLUENTS FIGURE Z-2 REFER [ LICE: IECHNICAL SPECIFICATIONS, FIGURE 5.1-3 Revision 21 2 11, 02-15-90 I- _>
2.0 GASEOUS EFFlVD(I) (Continued) 2.6 Methods of Caltulation for GastQus Effluent Monitor Seignin11 Administrative values are useo to reduce each setpoint to account for the potential activity in other releases. These administrative values shall be periodically reviewed based on actual release data and revised as required. 2.6.) PLANT VENT STA,06 2/3RT 7808, 2RT 7865 1, 3RT 7865 1 2.6.1.1 2/3RT 7808 Plant Vent Stack Monitor For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor.
. Total Body The concentration at the detector corresponding to a 500 mrem /yr total body dose rate at the exclusion area boundary is detemined by:
C (0.38)(2120 h,,e)(500mrevyr)(10m'/cc) (2 1) det = (Flow rite, cfm) (X/Q, soc /m')(I (Kg , ' mrem /vr) ( lj_ )) i pCi/m' C tot wheret C - the instantaneous concentration at the detector, det pCi/cc 0.38 = an administrative value used to account for potential activity from other gaseous release pathways 2 11 Revision 22
- l 08 02 90 L
I 2,0 Bl1005EFFLUERTS (Continued) 2.6.1 FLANT VENT STAtt . 2/3R17808, 2RT 78651, )RT 78651 (Continued) th Kg a the total body dose conversion f actor for the i gama emitting noble gas, mrem /yr per uti/ms , from Table 2 4 Cg a concentration of the ith nc:21e gas, as detenened by '.smple analysis, pCi/cc
= total concentration of noble gases, as determined Cg ,g by sample analysis (pC1/cc) = ECg i
Flow Rate - the plant vent flow rate, cfm f
= 82.000 cf# fan (x no. uf fans to be run) 2120 = conversion constant, cfm per m*/sec 500 mrem /yr a total body dose rate limit, as specified by specification 2.1.1.a X/Q = historical annual average dispersion factor, sec/m*
- 4.8E 6 sec/mi ikill The concentration at the detector corresponding to a 3000 mrem /yr skin dose rate at the exclusion area boundary is determined by:
c (0.38)(2120,.C[e , ) (3000 n. rem /yr) (10 m*/cc) (2 2) det = [ Flow rate, cfm) (X/Q, sec/m*)[Ill.g i +g 1.lH pC1 , atq/n.t)( C li )) tot 2 12 Revision 24 08 31-91
a * . 2.0 GA5[005 EFFLUENTS (Cortinued) 1.6.1 PLANT VENT STACK 2/3RT 7808, 2RT 7865 1, 3RT 7865 1 (Continued) wherer th noble Lg
= skin Dose Conversion Factor for the i gas, mrem /yrperpCl/m*,fromTable24 th noble Hj = air Dose Convrtsion Factor for the i f gas, mreWyr per pCi/me, from Table 2 4 1.1 = conversion factor to convert gama air dose to l skin dose ,
3000mreWyr - skin dose rate limit, as specified by
- Specification 2.1.1.a
' Other values in equation (2 2) are defined in equation (21)-
from equations (2 1) or The ses11er of the values.of Cdet (2 2) is to be used in the determination of the maximum permissiblemonitor_alarmsetpoint(cpm),asfollows: The maximum persistible alars setpoint (cpm) is determined using the calibration constant for 2/3RT 7808 given in Table 2 3. The maximum permissible alara setpoint is the value
'cpo' corresponding to the concentration, Cdet(thesmaller value from equation (2 1) or (2 2)). The calibration constant used is based on Kr 85 or on Xe.133, whichever yields a lower detection tfficiency (the largest value in terms of pCi/cc/ cpm). ;
The alarm setpoint will be maintained at a value not greater , than the maximum permissible alarm setpoint. l- . 2 13 Revision 21
, 02 15 90
i 2.0 $61[g) EFFLUENTS (Continuet')
-2.6.1 figlVENT STAG . 2/3RT.7300, 2RT 78651, 3RT.78651 (Continued)- :
If _ there is no release associated with this monitor, the monitor ! t setpoint should be established as close as practidal to ! background to prevent spurious alarms and yet assure an alarn should inadvertent release occur. l 2.6.1.2 2RT 7865 1 and 3RT.7865 1 Wide Ranoe Gas Monitors Themaximumreleaserate(uti/sec)forWideRangeGas Monitors is determined by converting the concentration at- l l the detector._Cdet(pCi/cc)toanequivalentrelease ' rateinpti/sec,asfollows: A,,, (23) i
, Igdetuti/ccHf{owrate.ec/seci wheret +
A = the maximum permissible release rate, pCi/sec ( max C det
=
the smaller of the values of Cdet obtained fromequations(21)or(22). ! Flow Rate -- flow rate,-cc/sec-
' - (3.87 x 10' cc/sec per fan) (number of faus) 2 = a factor to compensate for the split flow between Unit 2 and Unit 3 plant vent stacks 1
The release rate setpoint will not be set gre'ater than the maximum release rate detemined above, when this monitor is being used to meet the requirements of Specification 2.2.1.. i le l-- 2 14 Revision 24 08 31 91
- u. -- - . . - , . . - . . . , . . . . - , - . - .. ..-.- . ,,, - ,- ...- ,-.---- -- -.-.-.,,. - ~_
2.0 AMIOUS EFFLUENT 5 (Continued) PLANT VENT STACK 2/3RT 7800, 2RT 78651, 3RT 78651 (Continued) 2.6.1 If there is no release associeted with this monitor, the monitor setpoint should be established as close as practical to background to prevent spurious riarms and yet assure an alarm . should an inadvertent release occur. 2RT 7818, 2RT 7870 1, 3RT 7818 or , 2.6.2 (Q!iDENSER EVACUATION SYSTEM 3RT .7870-1
- ?..
2.6.2.1 2RT 7819 and 3RT 7.818 Condenser Airliglar Monitors ' For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas moatters is based on the gas-eous effluent flow rate and the meteorological dispersion factor. The concentration at the detector corresponding to a total body dose rate of 500 mrem /yr at the exclusion area boundary
-is determined by using:
Total Body (0.1)(0,5)(2120 *h,,e)(500
, mrem /yr)(10**m'/cc) (24)
C det = (Flow rate, cfa) (X/Q sec/m*)(E (K g , aren/vr) ( Jg. )) i pct /m' C tot The concentration at the detector corresponding to a t 2000 mres/yr skin dose rate at the exclusion area boundary is determined by using: M1 C m set (24a) t- det )( }) (Flow rate, cfe) (X/Q, sec/ms)[I(Lg + 1.1Mg , 2-15 Revision 21 02 i5 90 i
. + , ,. - - , _ , - . , , ,.4,.,_,.-,,.. . , , . ~, .. .,.n- -, , , , ..,.,,,..~,..-~----,..n. .,
t,
?o yi3EOUS EFFLUEKIS (Continued)
',p 0.6.2 [QNDENSER EVACUATION SYSTEM - 2RT 7818, 2RT 78701, 3RT-7818 or 3RT-7870 1 (Continued) e where:
.f U 0.1 is an administrative value used to account for potential activity from other gaseous release pathways, 3 , ad 0 5 is an adminktrative value used to account fer releases from botn SONGS 2 and SONGS 3 condenser air "' ejectors simultaneously. Other parameters are specified h in 2.6.1.1, above. fy;g fromequatio,s(2-4)or
- The smaller of the values Cdot (2 4a) is to be used in determining the maximum permissible l'
mehitor alarm setpoint (cpy, as follows: The maximum pemissiole alam setting (cp) is cetermined by using the calibration constant for the correspondir.g tendenser Fvacuation Sy. tem Monitur givn in Taule 2-3. 'he maximum permissible alarm setpoint is the crm value corresponding to the concentration, Cdet, !maller value fram equation (2 4) or (2 4a)). I! J calibration mstant usert is based on Kr-85 or on Xe-133, whicherer yields a icwsr detection.*fficiet.cy (higher value in terms of pCi/cc/ cpm). The alarm setpoint will not be set greater than the , maximum pemis:ible alarm setting determined above. 2-16 Revision 21 02-15 90
o
- a. .,; ;
2.0- GAlt005'EFFLUDff5-(Continued)
~
CONDENSER EVACUATION SYSTEM . 2RT 7M0 2RT-7870el, 3RT 7818 or.
'2.6.2- 3RT 78tv.1 (Continued) ,
If there.is no release associated with this monitor.- the unitor setpoint should be established as close as y l practical to background to prevent spurious .iarms yet assura an alarm should an inadWrtent release occur. . 2RT-78701 and 3RT 78701 Wide Range Gas Monitors 2.6.2.2 E-)
- Themaximumreleaserate(gCi/sec)forWideRangeGasMonitor
'is-detemined by ccnverting the concentration at- the detector, C det (pCi/cc), to an equivaler.t release rate -in-pct /sec.
A max
- IUdet, pCi/u) (flow rate,. cc/sec) <
-where:
A a the maximum pemissible release rate, pCi/sec
. max ,
Cg ,g - the smaller value of Cdet, as obtained from
-equations (2-4);and-(2-4a) flow rate - flow "ne of the condenser air' ejector, cc/sec
' = 4.719EScc/sec'(conservativelyassumeda - esign flow rate)
If there:is no release ~ associated with this monitor, the monitor setpoint should be establishec; as close as practical-to background to prevent spurious alarms yet assure an-alarm shc.uld an inadvertent release occur. 2 Revision-21
- 02 15 90 J
4
-*4erwa+ .
t'c---- 3_-ng -- y q MW g- g r- p q-yyTr 1 -- 2.0 SA_SE005 EFFLUD(Li (Conti tued) 2.6.3 CONTAINh?.NJ IESI - 2RT.7828, 3RT-7828, 2RT 7865, 3RT-7865 For the purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based en the gaseous effluent flow rate and the meteorological oispersion f ac*.or , , The concentiation at the detector corresponding to e total . body dose rete of 500 mrem /yr at the exclusion boundary is determined ty using: Total _ Body C (0.38)(P)(2120 ,f[,c)(500 mrem /yr)(10"m'/cc) (2-6)
'C det2 -(Flow rate, cfm['(h/Q, sec/m')(I (Kg , mrem /vr) ( _Gi ))
i pC1/m C tot C (0.38)(P.)(2120 ,@ ,c ) ( 500 mreWyr) ( # / /cc) - (2 7) det3 -(Flow rate, cfm) (X/Q, sec/m')[I (Kg , mrem /vr) ( lt_ )) - 1 pC1/m' C tot The concentration at the detector corresponding to a
*I 3000 mrem /yr skin dose rate at the exclusion area boundary is determined by using:
ikill e C (0.38)(P3)(2120 , k ) (39tio mrem /yr) (10 m*/cc) (26a) dtt2 -(Flow rate, cfm) (X/Q, sec/ms)[I(L g + li1Mg , mrem /vr)( Jg_ )) ^ i pCi/m' C tot C (. )(P)(2120 ,5,f[,e)(3000rrem/yr)(10"m*/cc) (2-7a) det3 -(Flow rate, cfm) (X/4, sec/m')[I(L g + 1.1Mg , mrem /vv)( J g_ )) i pC1/m' C tot 2-18 Revision 22 08 02-90
b , . ll 2.0 GASEOUS EFELUEKJS (Continued) 2RT 7828, 3RT-7828, 2RT 7865, 3RT-7865 2.6.3 CONTAINENT PURGE (Continued) where: ' C The instantaiieous concentration of the Unit 2 detector det2 in pCi/cc. C det3 - The instantaneous concentration of the Unit 3 detector in pCi/cc. s 0.38 is an administrative values used to account for potential activity from other gaseous release pathways. Pa and P are administrative values used to account for simultaneous purges of both SONGS 2 and SONGS 3. The fractions Pa and Pe will be assigned such that P + P 5 1.C. Flow rate v. the obssrved maximur flowrate in cfm fron the unit specific monitor 7828. Default values will be the following conservative mer.sured ficus:
- 50,000 cfm full purge
= 0,000 cfm mini-purge (The above values replace the smaller design flowrates.)
Other parameters are as specified in 2.6.1.1 above. The smaller of the values of maximum permissible Cdet2 from equation (2-6) or (2-64) and Cdet3 from equations (2-7) or (2-7a) is to be used in determining the maximum permissible monitor alarm setpoints. 2-19 Revision 22 00-02-90
.i, '
1 2.0 M5E00! EFFLUENTS -(Continued) 2RT 7828, 3RT 7828, ;R1-7865,_3RT TA5 2.6 3 - CONTAINMENT PURGE (Continued) 2.6.3.1 Maximum Permissible Alarm Settina (RT-7865) The maximum per'issible alarm setting for the Wide Range Gas Monitor expiessed as a maximum release rate (pCi/sec) is determined by converting tb concentration at the detector, C det (pti/cc),to an equivalent release rate in pCi/sec. A,,,=(Cdet, p 1/cc) (flow rate, cc/sec) where:
= the maximum permissible rOtase rate (pCi/ce' A,,x
-C = the smaller value of Cdet, as obtained from det equation (2 6, 2 6a) for Unit 2~or (2 7, 2 7a) for Unit 3.
flow rate - flow rate, cc/sec
= 1.416E6 cc/sec for mini-purge
= 2.360E7_cc/sec'for main purge.
.2 Maximum Permissible Alarm Settina (RT-7828)
The maximum permhsible alars setting' for RT-7828 is in uti/cc and-is the smaller of the values of Cdet2 (pCi/cc) from ep atiane (2-6) and (2-6a). If there is no release associated wit.: this monitor, the o7f monitor setpoint should be estabitsbed as close as practical to backgre nd to prevent spurious alarms yet assure an alarm should an inadvertent releare occur. 2-;0 Revision 22 ' 08-02-90 l
.~ _ ~_ _ ._ .
t
" j';j .
,oc ..,
.1 l
2.0= ' GASEOUS EFFLUENTS ' (Contin'.eu )
- . WASTEGASHEADER'-3RT-7865,2/3RT-78087 l
'2,6.4 l
for the' purpose of-Specification 2.1.1, the;alars'setpoint k _ level forinoble gas monitors is based an the 91seous effluent
'fiow rate 'and the meteorological dispersion factor. Since-the 7 waste gas hwier discharges- to the plant vent stack,'either
'3RT-7865 r 2/3RT-7808 may be used to monitor waste gas header y
releases.- The concentration at the detector corresponding to a total body
-dose rate of 500 mrem /yr or a skin dose rate of 3000 mrem /yr at 7 the exclusion = area boundary is determined by using equations:(2-1)-
or (2 2)Lwith; sample concentration (Cg ) and (Ctot) being obtained
~from the waste gas decay tank to be released.--
-The smaller of the values of maximum permissible concentration .
(Cdet);from. equation (2-1)or'(2-2)istobeusedin determining the maximum permissible monitor alarm setpoint. 4 2/3RT-7808 2' The maximum permissible alarm setting (cp.t.) is determined 4 1 - s by using the calibration' constant for plant vent stack' . monitor 7808 given in Table 2-3.J The maximum' permissible -
.setpoint is the cpm value corresponding to the concentra-g
- tion Cdet, (smaller value from equation (2-1) or -(2-2)).
^l
< ~
- - - 7
_ i: i '
- 2-21 Revisien 21 02-15-90
. __. _ . c_.. . - . , _ _ . , . _. _ _ _--s,.._ , ,
'i
=, -
. . .g V
2.0- A&$1005 EFFLUENTS (Continued) 2.6.4 - WASTE GAS HEADER - 3RT 7865, 2/3RT 7808 (Continued) i 3RT 7865
' The' maximum permissible alarm setting is expressed as a maximum release rate (pCi/sec) and is determined by.
converting;the concentration at-the detector, Cdet, to an equivalent release rate. in utt/see by equation (2 8). s A . ,_Ltdet' "ti/ce) Ifl wrate. ec/seci (2 8) .t where:
'A a the maximam permissibla 791 ease rate, pCi/sec det C - the smaller value of Cdet, as obtair.ed from det.
equation-(21) or (2 2), flowrate flowrate, cc/sec
- 7.74E7 cc/sec for 2 fan operation or
--3.87E7 cc/sec for 1 fan operation 2 = correction'for-3 7865 viewing only 1/2 the total Plant Vent Stack Flow, w
.l' A release fror, the waste gas header _is r.ot possible if:
(2-9)
)
p (fC)(g
)>Cdet
= 2 -i". Revision 24 08-31-91
-. . :..-. - - . . . _ - . , ~.. . . .. - ~ . - . , . - ... -
. ; .- ,7 ,
~2;0 '- GASE0US EFFLUEjgj (Continued) 2.6.4 WASTE GAS HEADER 3RT-7865 -2/3RT-7808 (Continued) 2.6.4.1'(Continued) .
Where: EC total concentration in waste gas holdup. tank 4 i to be released f- waste gas header effluent flow- rate, cfm , , F- plant vent stack flowrate in efm (166,000 cfm for 2 fan operation; 82,000 for 1 fan operation) Cdet - smallet . f the value; of Cdet from equation (2-1) or(2-2)withCg being obtained fror. the waste gas holdup tank to be released- ' If a release.is not possible, adjust the waste gas header. flow by determining the maximum permissible a-*e gas header effluent flow rate corresponding to the Vent Stack Hanitor setpoint in accordance with.the following:
-f < (0.9) $det)(F) --(2-10)-
E C, where: waste gas header effluent flow rate (cfm)
~
f - - F- plant vent stack flow rate (cfs) used in equation'(2-1)or(2-2)- 2-23 Revision'24 08-31-91
~
.,, , . . . ~ .- - - - . -
_v 5 ,< v, -: .;- W; '
- 2.0' SMIQVilfFLUENtf!(Continued)
? <
12.6i4L WMTE GAS HEADER : 3RT 7865, 2/,1RT 7808 (Continued)
~2.6.4.12 - (Cmtinued)
~
from.
.Cdd = the' smaller of the value of Cdet e equation (2 1) or (2-2) 4 I C, = total gamma activity (gCi/cc) of the waste
> 1 3
"* . gas holdup tank to be released, is determined.
from the pre release sample-analysis.
+' .
The 0.9 is an a'dministrative value to account for the potential activity from other releases in the same release pathway. 1 i
~
s; s >p
+4 l?
?u-r3 2-24 Revision *21 02-15-90' [
's ;
i L Y* a - - . . . . . . , _,.,,.,n. _ .,,
Table 23(*) Gaseous Effluent Radiation Monitor Celibration Constants (pCi/cc/ cpm) MONITOR _ Kr-85 _Xe-133 3.90E 8 4.62E 8 2/3RT 7808C 4 27E-8 6. -8 2RT-7818A _ 2RT-7818B 7.31E 5 3.73E 8 5.09E-B 3RT 7818A 2.21E-5 3RT-7818B 9.31E-5 (a)This table provides typical (220%) calibration constants for the gaseous effluent radiation monitors. 2-25 Revisio6 21 02-15-90
2.0 GASE00$ EFFLUENTS (Continued) 2.7 Gaseous Effluent 00se Rate The methodology used for the purpose of implementation of Specification 2.1.1 fcr the dose rate above background to an individual in an unrestricted area is calculated by using the following expressions: 2.7.1 FOR NOBLE GASES:
"* Ki IX/0) (211) bTB i i
(2-12) bs "* ILi + l*lH i) IXIO) i.- j _. where: b - total body dose rate in unrestricted areas due TB to radioactive materials released in gaseous effluents, in mrem /yr bs = skin dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, in mrem /yr Kj - the total body dose factor due to ganna emissions for each identified noble gas radionuclide, i, in mrem /yr per pCi/m' from Table 2-4, 2-26 Revision *21 02-15-90 l l
. _ _ - - _ - - _ _ _ - _ . __ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - ^ - - - ^ - - + _ - - - - _ , _ _ _ _ _ _ _ _
2.0 GA5E005 EFFLUENTS (Continued) 2.7.1 TOR NOBLE CASES: (Continued) Lj skin dose factor due to the beta emissions for each identified noble gas radionuclide, i, in rem /yr per pCi/m* from Table 2 4 Mg - the air dose factor due to gamma emissions for l each identified noble gas radionuclide, 1, in mrad /yr por pC(/m' from Table 2-4. (r.onversion constant of 1.1 mrem / mrad converts air dose to skin dose.) hg - the measured or calculated release rate of radionuclide, 1, for either cont;nuous or batch gaseous effluents,. in pC1/sec 1
'0G 5 - 4.8E-6 sec/m'. The maximum annual average atmospheric dispersion factor for any sector or distance at or beyond the enrestricted area boundary.
2.7.2 FOR ALL RADI0IODINESm TRITIUM AND FOR ALL_ RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVE 3 GREATER THAN EIGHT 0411: (2-13) o
=
I [I (Pik N) k 1] where: l b, - organ dose rate in unrestricted areas due to radioactive materbls released in gaseous effluents, in mram/yr 2-27 Revisiorf 22 08-02-90 k
~ . .
- 2. 0. GASE00 LEFFLUENIl (Continued)'
2.),2 fgLALL ' RAD 101001NES. TRIT 10Kf_tiRERJLL RADIOACTIVE MATERI ALS _IN PAIQICULATE FORM WITlGAtf LIVELOREATER THAN LIGHT DAYS: (Continued) hj a the measured or calculated release rate of radionuclide, i, for either continuous or batch gaseous effluents, inpCi/sec P - the dose parameter for radionuclide, i, for ik pathway, k, from Table 2 5 for the inhalation pathway in mrom/yr per pCi/ms. The dose factors are based on the critical indivical organ and the child age group.
. Vg - the highest calculated annual average dispersion parameter for estimating the dose to an individual at or beyond the unrestricted area boundary for pathway k.
- (X7Q),4.8E-6sec/msfortheinhalationpathway.
The location is tha unrestricted area in the NW sector. W ), 4.3E-8 m'? or the food and ground (!. f plane. pathways. The location is the tarestricted area in the E sector. 2-28 Revision *22 08-02-90
~ .. .
. +
2.0- GASEOUS EFFLUENT $ (Continued) 2.8 gjtscous Efflyent Dose calculatign 2.8.1 DOSE FROM NOBl1 GASES IN GA,51005 EFFLUENTS The ghseous releases considered in the following dose calculations are describeo in Section 2.6. The air dose in unrestricted areas due to noble gases released in gaseous effluents is cciculated using the following expressions: 2.b.t.1 [or historical meteorp193f: 0 - 3.17x10" I M g[ IT/QT Qg] (2-14) 7 i
- 3.17x10" I N g[ ]T[QT Qg) (2-15) 0, where:
- the total 9ama air dose from gaseous 0,
effluents, in mrad
- the total beta air dose from gaseous 0,
effluents, in mrad ; t 3.17x10" - (inversesecondsperyear) H, - the air dose factor due to gamma emissions for each idei.tified noble gcs radionuclide, i, tr.
.nrad/yr per pCi/m* from l'able 2-4 Ng - the air dose due to beta emissions for each identified noble gas radionuclide, i, in mrad /yr per pCi/m* from Tabli 2-4 2-29 Revision'22 08-02-90
2.0- GASEOUSEFFLUENTS-(Continued)
=2.8;l;l For historical meteorclogy:- (f:ntinued)'
TINI - 4.8t-s sec/m'. - The maximum annuai average-- atmospheric dispersion factor for any sector oi-distance at or beyond the unrestricted area bouadary, t
-Qj
= the amount of noble gas radionuclide, i, released in gaseous effluents it, C1.
2.8.1.2 For meteoroloav congurrent with release: NOTE: Consistent with the methodology provided in Regulatory Guide 1.109 and-the'following equations,- RRRGS (Radioactive Release , Report Generating System)-software is used to-perform the actual calculations.
-I .
1.14x10EM(E(Atf(X/Q)3,Q43)] (216); D,,. g
= 1.14x10 Hg[I (At3 (X/Q)), Qg3)] .(217)
D,j where:
- the total gama air dose from gaseous D,,
effluents in sector- f, in mrad , Df,_
.- the total beta air dose from gaseous ' effluents in sector 6. in mead 1.14x10 -inversehours/ year-G P
the air dose factor doe to gama emissions-c
, Mg for each idert.lfied ncble gas radionucilde, 1, in mrad /yr per pCi/m' from Table 2-4.
l 2-30 Revisiod22 08-02-90 L
- - 9 e e
1 l 2.0 .GAguUS EFFLUENT 1 (Continued) l 2.8.1.2 For mettgroloav concurrent with release: (Continued) Ng - the air dose factor due to beta emissions for each identified noble gas radionuclide, i, in mrtd/yr per pCi/m' from Talele 2 4. th time period over
= the length of the at) which (X/Q)), and Q4 ) are averaged for gaseous releases in hours
= the atmospheric dispersion factor for (X/Q)),
at exclusion Soundary location time period 6tj in sector a determined by concurrent reatecrology,insec/m' the average release rate of radionuclide, hjj = i, in gaseous effluents during time period, at), in pCi/sec 2.8.2 DOSE FROM TRITIUM. RA01010*)1NES AND RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES t GREATER THAN 8 DAYS IN GASEOUS EFFLUENTS The dose to an individual from tritium, radiciodines , and radioactive materials in particulate form with half lives greater than eight days in gaseous effluents released to unrestricted areas is calculated using the following expressions: . 2.8.2.1 For historical meteoroloav: D, - 3.17x10I [(IR ikNk) 01 ] (2-18) i k 2-31 Revision' 21 02-15-90
L GASEOUS EFFLUG H (Continued) 2.0 2.8.2.1 For historical meteoroloay: (Centinued) where: D - the total projected dose from gaseous o effluents to an individual, in mrem Qg
- the amount of each radionuclide, i, (tritium,radiciodine, radioactive material in particulate form with half lives greater than eight days), relessed in gaseous effluents in pCi RN - the sum of all pathways k for radionuclide, ik k i, of the R , gW product in mrem /yr per - Ci/sec. The IkR k Nk value for each '
radionuclide,1, is given in Table 2-6 The given is the maximum I RikNk for aH k locations and is based on the most restrictive age groups. R - the dose factor for each identified ik radionuclide, i, for pathway k (for the inhalation pathway in mrem /yr per pC1/m* and for the food and ground plane pathways in m* mrem /yr per 6 *i/sec) at the controlling location. The Rik s for each controlling location for each age group are given in Tables 2-7 thru 2-16. Data in these tables are derived using the NRC code, PARTS. (See " Submittal of 1990 00CM Oose Parameters for EONGS 1, 2, and 3" from E. S. Medling to P. H. Penseyres, dated 1/29/91). 2-32 Revision 23 02-28-91 l
2.0 GASE00$_ EFFLUENTS (Continued) 2.8.2.1 For historical meteoroloov: (Continued) W - the annual average dispersion parameter for k estimating the dose to an individual at the controlling location for pathway k.
- IT/lJ for the inhalation pathway in sec/ms.
The TT/l{J for each controlling location is given in Tables 2-7 thru 2-16.
- TD76Jforthefoodandgroundplanepathways in m" . The TD76J for each controlling location are given in Tables 2-7 thru 2-16.
4
- 2.8.2.2 Eqr_matenroloov concurrent with releues:
NOTE: Consistent with the methodoiogy provided in Regulatory Guide 1.109 and the following equations, RRRGS (Radioactive Release Report Generating System) software is used to perform the actual. calculations. D, - 1.14 x 10" ((atj ) (Rikt) (Wjks) ( ij)] (2-19) where: D,
- the total annual dose from gaseous effluents to an individual in sector # in mrem.
At j - the length of the j th period over which Wjke and Qg) are averagad for gaseous released in hours hjj - the average release rate of radionuclide, i, in 9aseous effluents during time per Jo at) in pCi/sec 2-33 Revision'22 08-22-90
... , - . .- _ . _ . . - - . _ . .. - . . . ~ . _
i f _% m = .: -j t
- 2. 0 -. : CASE 005 EFFlUIHLi -(Continued) 2.8.2.2 For meteoroloav. concurrent with releases: . (Continued)
.the dose factor for each identified radionuclide i,
-R -l ik#
for pathway k for sector # (for the . inhalation - ; pathway in mrem /yr per gCi/m* and for the food- j and ground plane pathways in m' mrem /yr per-4 pCi/sec)atthecontrollinglocation.'Alistingof R for the controlling locations in each landward , ik sector for each group is given in Tables 2-7 thru 2-16. The # is determined by the concurrent-meteorology. . L _W jks = the dispersion parameter for the _ti::n period 3at h :: for each pathway k for calculating the dose to an individual at the controlling location in sector # using concurrent meteorological conditions, ;
- (X/Q) for the inhalation pathway in sic #
l- 4
--(0/Q) for the food and ground plane-pathways in m**
~
P is i-l' 34 Revision 21 02-15-90 L l' p
--- - - +- , _ _ . .
.u . L., ; ., - , , . , , . , . ~ + ._ , , , , . .
TABLE 2._4 DOSE-FACTORS FOR NOBLE-GASES AND DAUGHTERS **- Beta Air Dose l (Total Body Dose: Skin Dose- Gamma Air Dose Factor K Factor L j factor M-g Factor N ) (mrem /y (mrad /yr (mrad /yrg ! Radio- (mrem /yr perpci/m*) perpC1/m*)_ perpCi/m*) perpct/m*) J Huclide I m 1.46E+3 1.23E+3 1.97E+3-Kr-85m 1.17E+3* 1.34E+3 1.72E+1 1.95E+3 Kr 1.61E+1 9.73E+3 6.17E+3 1.03E+4 Xr-87 5.92E+3 I 2.37E+i 1.52E+4 2.93E+3-Kr 88- 1.47E+4 4.76E+2 1.56E+2 1.llE+3 Xe-131m 9.15E+1 9.94E+2 3.27E+2 1.48E+3 . Xes133m 2.51E+2 3.06E+2 3.53E+2 1.05E+3 Xe 133 -2.94E+2 7.11E+2 3.36E+3 7.39E+2-Xe-135m 3.12E+3 1.86E+3 1.92E+3 2.46E+3
- Xe-135- -1.81E+3 Xe-138 8.83E+3 4.13E+3 9.21E+3 - 4. 7 5E+3 --
2.69E+3 9.30E+3 3.28E+3 Ar-41 8.84E+3
*l.17E+3 - 1.17 x 10'
** Source: USNRC Reg ' Guide 1.109. Table B-1 2
2-35 Revision'21 02-15*90
L TABLE 2-5 DOSE PARAMETER P j ,g* , CHILD AGE GROUP CRITICfL ORGAN Inhalation Pathway inhalation (mrem Pathway)
/yr per Ci/m Radionuclide (mrem /yr per pCi/m ) Radienuclide 1.1E+3 ! -131 1.6E+7 H-3 ,
1.7E+4 1 -132 1.9L+5 Cr 51 1.6E+6 I -133 3.8E<6 Mn 54 5.1E+5 1 -134 5.1E+4 ,- Co-57 1.1E+6 I -135 7.9E+5 Co-58 7.1E+6 Cs-134 1.0E+6 Co 60 2.2E+6 rs-136 1.7E+5 / St-89 1.0E+8 Cs-137 9.1E+5
- Sr-90 Zr 95 2.2E+6 Ba-140 1.7E+6 Nb-95 6.1E+5 Ce-141 5.4E+5 Ru-103 6.6E+5 C0-144 1.2E+7 Te-129m 1.8E+6 i
- Source: USNRC NUREG-0133, Secticn 5.P.1.1 2-36 Revision 23 02-28-91
< 1 '.
s 7
-t TABLE 2-6 I
CON' ROLLING LOCATION FACTORS i -
'I RikNk k
~ Radionuclide- . mrem /yr per Ci/sec H -3 9.62b4
, Cr-51 3.25E 2 Mn 34 6.52E+0 1.66E+0 l Co 57' .
, -. Co 12.33E+0
- Co 60 8.56E+1- ,
Sr 4.34E+1- 1 Sr 90 1.82E+3
/.
\' Zr-95 2.90E+0-Nb-95 6.81E+0-Ru 103; 1.08Ed.
Te-129m: 5."J2E+0
~
Cs-134 -3.36E+1
-Cs-136 6.81E-1 Cs-137 3.67E+1 Ba-140- 1.56E+0
- Ce-141 .5.74E-I Ce-144 1.68E+1
- 1.19E+1 3 I -131
'I ~132 1.45E-1 +' s I= 133 ~2.82E+0 I -134 3.94E-2 I- 135 5.94E-1 UN ID 3.59E+0
- Footnote: These values te ha used in manual cz,1culations are the maximum IR k ik kW for al's iocations based on the most restrictive -age group.
.2-37 Revision 23 02-28-91 Y we -e-. - e r m u -
=, um--, ..~.~r rv +t- s=v*--T*w-' +-**v*e 7 v - N e - ^' * -" t 4 '*=*5-(
TABLE 2 ) l 005E: PARAMETER Rj FOR SECTOR P Pathway Surf-Beach Distance - 0.4 miles X/Q-- 1.8E 6 sec/m' 0/0 8.2E-9 m , Infant Child Teen Adult Inhala- Food & Inhal a- food &. Inhala- Food &- Inhala- Food & Radio - tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H~-3 -1.2E+1 0- 5 lE+1 8.7E+1 0' 1.8E+2 2.2E+4 8.4E+2- 1.1E+5 9.9E+2 3.2E+5-Cr-51 1.6E+4' 6.6E+6 8.0E+4 3.2E+7 9.6E+4 9.5E+7 Mn 54 0- 5.3E+3 1.6E+6 '2.4E+4 7.9E+6 2.5E+4 2.3E+7 Co 57-1.2E+4 1.8E+6 5.4E+4- 8.7E+6- 6.4E+4 2.6E+7 00 58 Co 60 0- 7.3E+4 1.0E+8 3.5E+5 4.9E+8 4.lE+5 1.5E+9 Sr 0- 2.2E+4 1.0E+2 9.7E+4 4.9E+7 9.6E+4 1.5E+3 3r 1.lE+6 0- 4.tE+6 6.8E+6 - 2.3E+4 1.2E+6 1.lE+5 5.8E+6 1.2E+5 1.7E+7 Zr 95 Hb 0- 0- 6.4E+3 6.6E+5 3.0!+4 3.lE+6 3.5E+4 9.4E+6 Ru-103 6.9E+3 -5.2E+5 3.2E+4 2.5E+6 3.5E+4 7.4E+6 Te 129m- 0' 1.8E+4- 9.4E+4 8.0E44 t4.5E+5 7.9E+4' 1.3E+6 Cs-134 ' 0-
- 1 1.lE+4- 3.3E+7 4.5E44 -1.6r+8 5.8E+4- 4.7E+8 Cs-136. ' 0-
- 1.8E+3 7.2E+5 7.8E+3 3.4E+6 1.0E+4 1.0E+7 Cs 137 0- 9.4E+? 4.9E+7 3.4E+4- 2.4E+8 -4.3E+4 7.lE+8 Ba- t-) .o. .o. 1.8E+4 9.9E+4 8.2E+4 4.7E+5 8.7E+4 1.4E+6
- Ce i ',1 0- 5.7E+3 6.6E+4 2.5E+4- 3.lE+5 2.5E+4 9.4E+5 Ce-144- - 1.2E+5 - 3.3E+5 5.4E+5 1.6E+6 5.3E+5 4.8E+6 1--131 0- -1.7E+5 8.3E+4' 5.9E+5 3.9E+5 8.2E+5 1.2E+6 1 -132 0- 2.0E+3 5.9E+3 6.lE+3 2.8E+4 7.8E+3 8.5E+4 I -133- 4.0E+4 1.2E+4 1.2E+5 5.6E+4 1.5E+5 1.7E+5
-1;-134 0- 5.3E+2 - 2.2E+3 1.6E+3 1.0E+4 2.0E+3 3.lE+4
'2.5E+4 5.8E+4 3.lE+4 1.,7 E+5 1 1351 8.2E+3 1.2E+4-5.9E+4 5.1E+7
~
UN 10 1. 0 E+ 4 -- 3.6E+6 5.0E+4 1 7E+7
- Inhalation Pathway, units - !"
Food & Ground Pathuay, units A " j l l I l 2-38 Revision 23 02 28-H r '* ' ' ' - , , , . , , . ,
TABLE 2 7 DOSE FARAMETER Rt FOR SECTOR P Page 2 of 3 Pathway = Pt. Loran Military Hsng Distance - 2.7 miles X/Q - 1.2E-7 sec/m' 0/Q - 3.6E-10 m-* Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhal a- Food a Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide Pathway 0- 1.lE+3 1.3E+3 1.3E+3 0-H -3 6.5E+2 4.7E+6 1.7E+4 4.7E+6 2.lE+4 4.7E46 1.4E+4 4.7E+6 Cr 51 1.3E+4 1.4E+6 1.4E+9 1.4E+9 1.6E+6 1.4E+9 2.0E+G 1.4E+9 Mn 54 1.0E+6 3.4E+8 5.lE+5 3.4E+8 5.9E+5 3.4E+8 3.7E+5 Co-57 3.8E+5 3.4E4 9.3E+5 3.8E+8 3.8E+8 1.lE+6 3.8E+8 1.3E+6 3.8E+6 Co 58 7.8E45 6.0E+6 2.2E+10 4.5E+6 2.2E+10 7.lE+6 2.2E+10 8.7E+6- 2.2E+10 Co 60 2.2E+4 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4 E+6 Sr-89 2.0E+6 Sr-90 4.lE+7 1.0E+8 1.lE+8 9.9E+7 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Zr 95 1.8E+6 5.0E+5 1.4E+8 Nb 95 4.8E+5 1.4E+8 6.1 E4 5 1.4E+8 7.5E+5 1.4E+8 1.1E+8 6.6E+5 1.1E+8 -7.8E*5 1.lE+8 5.0E+5 1.lE+8 Ru-103 5.5E+5 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 E Te-129m 1.7E+6 2.0E+7 Cs-134 6.8E+9 1.0E+6 6.8E+9 1.1E+6 6.8E+9 8.5E+5 6.8E+9 7.0E+5 Cs-136 1.5E+8 1.7E+5 1.5E+8 1.9E+5 1.5Et8 1.5E+5 1.5E48 1.3E+5 Cs-137 6.1E+5 1.0E+10 9.1E+5 1.0E+10 8.5E+5 1.0E+10 6.2E+5 1.0E+10 Ba 140 1.6E+6 2.lE+7 1.7E+6 2.1E+7 2.0E+ 6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 1 -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.lE+4 4.5E+5 4.'E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6d .+5 2.5E+6- 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 InhalationPathway, units-yff Food & Ground Pathway, units - (m mremhr) pCi/sec 2 "d9 Revision 23 02-28-91
t 2 . IABLE 2-7 DOSE PARAMETER R$ FOR SECTOR P Page 3 of 3 Pathway former Nixon' Estate (no garden) Distance - 2.8 miles X/Q - 1.2E 7 sec/m D/0 - 3.4E 10 m*' Infant Child Teen Adult Inhal a- - Food & Inhala. Food & Inhala-- Food & Inhala- Food & Radio- tion Ground- tion Ground- tion Ground tion Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide
~ '1.1E+3 1 3E+3 0- 1.3E+3 0-H -3 '6.5E+2 4.7E+6 Cr-51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.lE+4 4.7E+6 1.4E+4 1.6E+6 1.4E+9 2.0E+6 1.4E+9- 1.4E+6 :1.4E+9 Mn-54 'l.0E+6 '1.4E+9 3.8E+5- 3.4E+8 5.1E+5 3.4E+8 5.9E+5 3.4E+8 3.7C45 3.4E48 Co 57' 3.8E+8 1.lE+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co 58 7.8E+5 2.0E+10 7.lE+6 2.2E+10 6.7E+6 2.2E+10 C . 0E+ 6 2.2E+10 Co 60 4.5E+6-2.2E+6 2.2E+4 2. 4 E+6 0.2E+4 1.4E+6 2.2E+4 Sr-89 2.0E+6 2.2E+4 0-Sr 4.lE+7 1.0E+8 1.lE+8 9.9E+7 2.2E+6 '2.5E+8 2.7E+6 2.5E+8 1.8E+6. 2.5E+8 Zr 95 1.8E+6 2.5E+8 1.4E+8 Hb-95 4.8E+5 1.4E+8 6.lE+5 -1.4E+b 7.5E+5 1.4E+8 5.0E+5 Ru-103- 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.lE+8 5.0E+5 1.lE+8 2.0E+7 1.8E+6 2.0Ev7 2.0E+6- 2.0E+7 1.2E+6 2.0E+7
- - Te-129m- 1 ~.7 E+6 -
'Cs-134 7.0E45- -6.8E+9 1.0E+6 - 6.6E+9 1. l E+ 6 - 6.8E+9 8.5E+5 6.8E+9-lCs-136 1.3E+5 1.538 1.7E+5 1.5E+8 1.9E+5- 1.5E+8 1.5E+5 1.5E+8 Cs-137 6.1E+5 1.0E+10 9.1E+5 1.0E+10 8.5E+5 1.0E+10 6.2E+5 1.0E+10 Ba-140' 1.6E+G- .2.lE+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.lE+7 Ce 141 5.2E+5- 1.4E+7. 5.4E+5 1.4E+7 6.lE+5 1.4E+7 .3.6E+5 1.4E+7 Ce-144 9.8E+6- 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6- 7.0E+7 I 131- 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1AE+7 1.7E+7 1.2E+7 1.7E+7 1 -132 :1.7E+5- 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.lE+5 1.2E+6 1 -133 -3.6E+6- 2.4E+6 3.8E+6- 2.4E+6 2.9E+6- 2.4E+6 2.2E+6 2.4E+6 I.-134. 4.5E+4 4.5E+5- 5.1E44 -4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I 135 :7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5- 2.5f+6 UN-ID - 6.5E+5- 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8- 8.6E+5 7.5E+8 w
InhalationPathway, units-]jY im* m/vr) food & Ground Pathway . units 2-40 Revision 23 02-28-91
. o L
! IM LE 2-8 DOSE PARAMETER Rj FOR SECTOR Q Page 1 of 9 Distance - 1.1 miles I I Pathway Enlisted Bch Trailers X/Q - 9.3E-7 sec/m' D/Q - 4.6E 9 m Child Teen Adult infant inhala- ' Food & Inhala- Food & Inhala- Food & Inhala- Food & tion Ground tion Ground tion Ground tion Ground Radio- Pataway Pathway Pathway Pathway Pathway Fathway Pathway Pathway Nuclide 0- 0- 6.3E+2 H3 0-0- 7.2E+3 2 . 3 T- -6 Cr 51 0- 7.0E+5 6.9/+8 0-Mn 54 1.
- i+ 8 0- -0 0- 1.8E+5 Co 57 4.6E+5 1.N E+8 Co 58 U. 0- 0-0- 0- 3.0E+6 1. E+10 Co 60 0- 0- 7.0E+5 1.ti+4 0- 0- 0- 0-Sr 89 5.0E+7 -a-Sr-90 0- 0- 8.8E+5 1. M. . L Zr-95 2.5E+5 6.8E+7 0- 0-Nb 95 2.5E+5 5.4E+7 Ru-103 0- 0- 0- 0- 5.8E+5 9.8E+6 Te-129m 0- 4.2E+5 3.4E+9 Cs-134 Cs-136 0- 0- 0- 7.3E+4 7.5E+7 0- 3.lE+5 5.lE+9 Cs-137 6,4 E+ 5 1.0E+7 Ba 140 Ce-141 0- 1.8E+5 6.8E46 6- 3.9E+6 3.5E+7 re 144 8.6E+6 1 -131 0- 0- $ 6.0E+6 5.7E+4 6.2E+5 1 -132 1 -133 -u- 1.lE46 1.2E+6 1.5E+4 2.2E+3 I -134 1 -135 2.2E+5 1.3E+6 UN 10 4.3E+5 3.7E48 "T'*/ r Inhalation Pathway, units C1/m!
2 Food & Ground Pathway, units *' M
'* "C1/sec p 2-41 Revision 23 02-28-91
i
)
TABLE 2-8 l DOSE PARAMETER Rj FOR SECTOR Q Page 2 of 9 Pathwsy San Onofre Mobil Homes D stance = 1.3 miles X/Q = 7.4E 7 sec/m* 0/0 3.6E 9_m " Infant Child Teen Adult . Inhala- Food & Inhala- food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.lE+3 1.3E+3 1.3E+3 Cr 51 1.3E+4 4.7E+6 1.7E+4 4.7E46 2.lE+4 4.7E+6 1.4E+4 4.7E+6 Mn-54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Co 57 3.8E+5 3.4E+8 5.lE+5 3.4E+8 5.9E+5 3.4E+8 3.7E+5 3.4E+8 Co-58 7.8E+5 3.8E+8 1.lE+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co 60 4.5E+6 2.2E+10 7.lE+6 2.2E+10 8.7E+6 2.2E+10 6.0Et6 2.2E+10 Sr-89 2.0E+6 2.2E+4 2.2E+6 P.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 4.1E+7 1.0E+8 1.1E 8 9.9E+7 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7L,6 2.5E+8 1.8E+6 2.5E4B Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.FE+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.lE+8 7.0E+5 1.1E+8 5.0E+5 1.1E+8 Te-129m 1.7E+6 -2.0E+7 1.8E+6 2.0E+1 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 7.0E+5 6.8E+9 1.0E+6 6.8E+9 1.lE+6 6.8E+9 8.5E+5 6.8E+9 Cs-136 1.3E+5 1.5E+8 1.;E+f 1.5E+9 1.9E+5 1.5E+8 1.5E+5 1. 5 E+ 8 Cs-137 6.1E+5 1.0E+10 9.lE+5 1.0E+10 8.$E+5 1.0E+10 6.2E+5 1.0E+10 Ba 140' l.6E+6 2.1E+7 1.7E+6 2.1E+7 2 0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7- 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7-1 -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6- 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I -135 7.0F+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-10 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5- 7.5E+8 r r Inhalation Pathway, units "C I* I Food & Ground Pathway. units j""'V"I l . f 2-42 Revision 23 i- 02-28-91
TABLE 2-8 DOSE PARAMETER Rj FOR SECTOR Q Page 3 of 9 Pathway Dittance - 0.6 miles State Park 0{fice Trailer D/Q - 1.2E 8 m ' X/Q - 2.2E 6 sec/m Infant Child Teen Adult Food & Inhala- Food & Inhala- Food &!!nhala- Food & Inhala-tion Ground tion Ground tion Ground tion Groend Radio- Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide 0- 5.8E+1 0-H -3 -0 2,lE+5 0- 0- 6.6E+2 Cr-51 0- 0 Mn-54 0- 0- 6.4E+4 6.3E+7 C0-57 0- 1.7E+4 -1.6E+7 Co 58 0- 4.2E+4 1.7E+7 Co 60 -U- 2.7E+5 9.8E+8 0- 6.4E+4 9.9E+2 Sr 89 0-Sr 90 0- 0 4.5E+6 Zr-95 0- 8.lE+4 1.1E+7 0- 2.3E+4 6.2E+6 Nh-95 0- 2.3E+4 5.0E+6 Ru-103 0-Te-129m 5.3E+4 9.0E+5 Cs-134 0- 3.9E+4 3.lE+8 6.7F+3 6.9E+6 Cs-136 Cs-137 0- 2.8E+4 4.7E+8 Ba-140 0- 0- 5.8E+4 9.4E+5 Ce-141 0- 1.7E+4 6.2E+5 Ce-144 0- 0- 3.6E+5 3.2E+6 I -131 0- 5.4E+5 7.9E+5 1 -132 5.26,3 5.7E+4 I -133 9.8E+4 1 lE+5 I -134 0- 1.4E+3 2.1E+4 I.-135- 2.0E+4 1.2E+5 UN-ID 3.9E+4 3.dE+7 Inhalation Pathway, units "**#
"C1/m!"
g 2 Food & Ground Pathway, units = (m )(mrem /vri gCi/sec l l 2-43 Revision 23 02-28-91 L l
TABLE 2-6 DOSE PARAMETER Ri FOR SECTOR Q Page 4 of 9 Pathway - Surf. Beach Guard Shack' Oistance - 0.7 miles X/Q = 1.8E-06 sec/m' 0/Q = 9.9E 09 m** Infant Child Teen Adult Inhala. Food & Inhala- Food & Inhela- l Food & Inhala- Food &
- Radio- tion Ground tion Ground tion ! Ground tion Ground Pathway Pathway l Pathway Pathway pathway Pathway Pathway Nuclide Pathway 0- 0- 0- 0- 7.2E+1 H -3 8.2E+2 2.7E+5 Cr-51 0- .
Mn-54 0- 0- 0- 8.0E+4 7.9E+7 0- 0 0- 2.lE+4 2.0E+7-Co-57 Co 58 -0 5.3E+4 2.2E+7 Co-60 0 0- 3.4E+5 1.2E+9 Sr 89 8.0E+4 1.2E+3 0- 5.7E+6 0-
- Er-90 Zr-95 -0 1.0E+5 1.4E+7 Nb-95 0- 0- 2.9E+4 7.8E+6 Ru 103 -0 2.9E+4 6.2E+6 1.lE+6
-0 0- 6.6E44 Te-129m Cs-134 0- -0 4.8E+4 3.9E+8 Cs-136 0- 8.4E+3 8.6E+6 Cs-137 3.5E+4 5.9E+8 Ba-140 7.3E+4 1.2E+6 Ce-141 0- 0- 2.lE+4 7.8E+5 Ce-144 4.4E+5 4.0E+6 L I -131 6.8E+5 9.8E+5 1 -132 0- 6.5E+3 7.1E+4
! -133 -0 1.2E+5 1.4E+5
. I -134 -0 0- 1.7E+3 2.6C+4 I -135 0- 2.6E+4 1.4E+5 UN-ID -0 4.9E+4 4.3E+7 ( 4 Inhalation Pathway, units "I'"(!I j ' I* Food & Ground Pathway, units f*j"(([YPI j I 2-44 Revision'23 - 02-28-91 4
,, . . . - --.. _ . . , . , , , . , , . , _ . . .. _. ,. _-m -
1 TABLE 2-8 DOSE PARAMETER Rj FOR SECT 0it Q Pa9e 5 of 9 Pathway - Enlisted Beach Check-in Distance - 1.4 miles X/Q = 6.8E-7 sec/m* D/Q - 3.2E-9 m-' Infant Child Teen Adult Food & Inhal a- Food & Inhala- Food & Inhala- Food & Inhala- Ground tion Ground Radio- tion Ground tion Grounc tion Pathway Pathway Pathway Pathway Pathway I Nuclide Pathway Pathway Pathway 0- 0- 2.9E+2 0-H -3 1.lE+6 0- 0- 3.3E+3 Cr-51 -0 0- 3.2E+8 3.2E+5 Mn 54 0- 8.4E+4 7.8E+7 0-Co 57 2.lE+5 8.7E+7 0-Co-58 1.4E+6 4.9E+9 Co 60 3.2E+5 4.9E+3
-0 Sr 89 0- 2.3E+7 0-Sr-90 4.0E+5 5.7E+7 Zr 95 0- -u- 0- 1.2E+5 3.1E+7 Nb-95 0- 0- 1.2E+5 2.5E+7 Ru+103 0- 4.5E+6 0- 2.6E+5
- Te-129m 1.9E+5 1.6E+9 Cs-134 0-3.3E+4 3.4E+7 Cs-136- U-2.3E+9 Cs-137 0- 1.4E+5 2.9E+5 4.7E46 Ba-140 0- 8.3E+4 3.lE+6 Ce-141 Ce-144 1.8E+6 1.6E+7 0- 0- 2.7E+6 3.9E46 I -131 2,6E+4 I -132 0- 0- 2.8E+5 4.9E+5 5.6E+5 I -133 I -134 6.8E+3 1.0E+5 1 135- 1.0E+5 5.8E+5 UN ID 2.0E+5 1.7E+B Inhalation Pathway, units "'g" ?"
" V"I Food & Ground Pathway, units = j l
2-45 Revision 23 02-28-91
1 .. TABLE 2-8. :
- DOSE PARAMETER Rj FOR SECTOR Q Pathway== Sheep ~(Meat)-. Distance -1,6 mile;*
X/Q 5.6E-7 sec/m' 0/0 - 2.6E P m* i
~
-Infant Child- Teen Adult Inhala- ' food-&- Inhala- Food & Inhala I food & Inhala- Food &
Radio- tion : Ground tion -Ground tion Ground- tionL Ground Pathway: Pathway Pathway Pathway Path',say . Pathway Pathway- Pathway Nuclide H -3 - - 0- - 0- 1.5E+0 1.2E+0 7.0E+0 2.1E40 ' 1.0E+2 7.9E+1 2;6E+4 Cr-51 - 0- - 0- 5.1 E+ '. 0- - 0- 7.8F+2 1.4E+3 7.7E+3 7.6E+6 Mn-54 00 57 - 0 4.?E+3 0- 8.1E+3 -2.0E+3 1.9E+6. .
-0 0- r.7E+3 0- 2.0E+4- 5.1E+3 2.1E+6 Co-58 - e Co-60 -0 - 0- 3.7E+4 0- 7.3E+4 3.3E+4 1.2E+8 Sr-89 0- -
0- 5.0E+4 2.6E44 7.7E+3 3.1E+4 Sr 90 0- - 0- 1.0E4 6 0- 8.1E+5 5.5E+5 1.3E+6 ,
-Ir-95 : 0- -- c. - 6.3E+4 0- 1.1E+5 9.7E+3- 1.6E+6 Nbi95- -
0- 2.4E+5 0- 4.5E+5 2.8E+3 1.6E+6
.Au-103 -
0- 4.2E+5 7.6E+5- 2.8E+3 1.9E+6 T e-129m -0 0- - 0- 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Cs-134- - 0- 1.4E+5 1.2E+5 4.7E+3- 3.8E+7 Cs-136. 0- - 0- 5.1E+3 - 0- 4.3E+3 8.1E+2 8.3E+5-
- Cr-137 0- - 0. 1.3E+5 9.5E+4 3.4E+3- 5.7E+7 Ba-140 - 0- -
0- 5.1E+3 - 0- 4.3E+3- 7.0E+3 1.2E+5 ':\' Ce-141- - - 0- 1.5E+3 ,0-- 2.4E+3 -2.0E+3- 7.9E+4 Ce-144 - 0-- 1.8E+4 . 3.0E+4 4.3E+4 4.3E+5 I; 131 -C- - - 0- 6.6E+5 - 0- 4.4E+5 6.6E+4: 7.0E+5 1 -132 6.3E+2 6.8E+3 1 -133L - 1.6E-2 - - 0- 8.7E-3 1.2E+4 1.3E+4. I:-134 0- - 1.6E+2 2.5E+3 I -135 - 1.1E-18 - 0. 6.4E-19 2.5E+3 -1.4E+4 UN !D . 0 1.1E+5 - 0- 9.5E+4 4.8E+3 -4.2E+6 InhalationPathway, units =]j*!" Food & Ground Pathway, units I*3 II""'"#VII - pCi/sec 2-46 Revision 23 02-28-91
-r g y g- ~ < - - , t., ,.-, g ,,. ,t v - r r- v re- eus-ar we--s"u m**7-+et-i-'<w'- m - w o w-' e w
- 4 e e e-r -ei-+-===+n--- *-de w-***=wm -w ww e w + e e-* em **~~-"**-ewe-e**
TABLE 2 8 DOSE PARAMETER Rj FOR SECTOR Q Page 7 of 9 Pathway S. C. Res W Garden Distance - 4.1 miles 1.2E-07 sec/rn' 0/0 4.lE-10 m-* X/Q Infant Child Teen Adult Food & Inhala- Food & Inhal a- Food & Inhala- Food & Inhala- Ground tion Ground Radio- tion Ground tion Ground tion Pathway Pathway pathway Pathway Pathway Nuclide Pathway Pathway Pathway 3.8E+3 1.3E+3 ?.4E+3 1.3E+3 1.9E+3 H -3 6 V+2 1.lE+3 9.4E+6 2.lE+4 1.'iF+7 1.4E+4 1.1E+7 Cr 51 iL4 4.7E+6 1.7E+4 2.0E+9 2.0E+6 2.2L+9 1.4E+6 2.2E+9. Hn-54 1, ; .46 1.4E+9 1.6E+6 5.6E+8 5.9E+5 6.3E+8 3.7E+5 5.8E+8 Co-57 3.8E+5 3.4E+8 5.1E+5 7.lE+8 1.3E+6 8.9E+8 9.3E+5 8.5E+8 Co 58 7.8E+5 3.8E+8 1.lE+6 2.3E+10 8.7E+6 2.4E+10 6.0E+6 2.4E+10 l Co-60 4.5E+6 2.2E+10 7.1E+6 3.lE+10 2.4E+6 1.2E+10 1.4E+6 7.2E+9 Sr-89 2.0E+6 2.2E+4 2.2E+6 1.3E+12 1.1E+8 7.7E+11 9.9E+7 5.8E+11 Sr 90 4.lE+7 1.0E+8 1.8E+6 1.2E+9 2.5E+8 2.2E+6 1.0E+9 2.7E+6 1.3E+9 : Zr-95 1.8E+6 7.5E+5 4.9E+8 5.0E+5 4.5E+8 l No 95 ' 4.8Et5 , 1.4E48 6.lE+5 3.8E+8 ' 6.6E+5 4.4E+8 7.8E+5 5.6E+8 5.0E+5 4.9E+8 Ru 103 5.5E+5 ).1E+8 9.7E+8 1.8E+6 2.4E+9 2.0E+6 1.4E+9 1.2E+6
- Te-129m 1.7E+6 2.0E+7 6,8E+9 1.0E+6 3.!E+10 1.lE+6 2.2E+10 8.5E+5 1.6E+10 Cs-134 7,0E+5 1.7E+5 2.4Ev8 1.9E+5 2.1E+8 1.5E+5 1.9E+8 i Cs-136 1.3E+5 1.5E+8
-1,0E+10 9.1E+5 3.4E+10 8.5E+5 2.3E+10 6.2E+5 1.8E+10 Cs-137 6.1E+5 7.4E+7 2.1E+7 1.7E+6 1.3E+8 2.0E+6 8.8E+7 1.3E+6 l Ba-140 1.6E+6 3.6E+5 3.3E+8 Ce-141 5.2E+5 1 4E+7 5.4E+5 3.4E+8 6.1E+5 4.2E+8 1.2E+7 9.3E+9 1.3E+7 1.2E+10 7.8E+6 9.0E+9 Ce-144 9.8E+6 7.0E+7 1.6E+7 4.1E+9 1.5E+7 2.lE+9 1.2E+7 1.4E+9 1 -131 1.5E+7 1.7E+7 1.9E+5 1.2E+6 1.5E+5 l_2E+6 1.1E+5 1.2E+6 I -13? 1.7E+5 1-2E+6 2.2E46 2.4E+6 1 -In 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 4.SE+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5
-I -134 4.5E+4 4.5E+5 5.1E+4 2.5E+6 I -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 7.5E+8 1.0E+6 3.3E+9 1.2E+6 2.4E+9 8.6E+5 1.8E+9 UN-ID 6.5E+5 Inhalation Pathway, units - !"
Food & Ground Pathway, units - (m r r) j 2-47 Revision 23 02-28 91
TABLE 2-8 5 .-DOSE PARAMETER Rj- FOR SECTOR Q Page_8-of 9 Pathway - San Clemente Ranchl(No Residents) Distance - 2.2 miles L D/Q - 1.4E-9 m .- X/Q _3.3E-7 sec/m* Infant- _ Child- Teen ' Adult u -. Food L- Inhala- Food & Inhala- Food &~ Inhala. Food &- Inhala-Radio-- tion: Ground tion Ground tion Ground tion: Ground l_ Pathway Pathway Pathway Pathway - Pathway Nuclide! Pathway Pathway Pathway 40- 0- 3.8E+3: 0- 2.4E+3 - 1.9E+3- -i D 'H E3 6.7E+6 Cr 5) -0 . 4.8E+6 7.4E+6 6.1E+8 0-- 8.3E+8 8.0E+8- l Mn 54 - 2.4E+8 Co-57 - -2.2E+8 2.9E+8
-0. 0. 3.3E+8 . 5.1E+8 0-- 4.7E+8' Co-58 2.7E+9-Co-60 0- 2.0E+9- 3.0E49
- 3.1E+10 -1.2E+10 7.2E+9 Sr-89 5,8E+11 Sr 90. -0 0- 1.3E+12 7.7E+11 ij 7.8E+8 - 1.1E+9 0- - 9.1E+8 4 4 , Ir-95-- 3.5E+8 - 3.lE+8
~
Nb 95- 0- 2.4E+8 - 0- 3.3E+8 4.5E+8- -0 ' 3.8E+8-Ru-303 3
- 2.3E+9 1.4E+9 9.5E+8 Te-129m-2.4E+10 1.5E+10 - 9.2E+9:
Cs-134' ' Cs-136 1 -0 - -9.0E+7 - 5.7E+7- 0- 3.6E+7
- Cs-137 2.3E+10 1.3E+10 7.8E+9-Ba-140 1.1E+8 6.8E+7 - 5.3E+7 Ce-141 3.3E+8 4.1E+8 0- 3.2E+8- ,
Ce-144 9.2E+9 :1.2E+10 9.0E+9 . . I -131 -4,1E+9 2.1E+9 1.4E+9 1 h 1 -132 - 6.0E-36 2.6E-36 1.7E-36
.1--133' 0- 4.0E-11 1.7E-11 ' 11.1E-11
- I -134 - 6.1E-37 ~0-
- 2.7E-37 1.7E-37 I -135 - 7.0E-35 3.1E 35 1.9E-35 i UNcID' : 0- 2.5E+9 ' -0 1.7E+9- 1 1E+9-a v
T S Inhalation Pathway,Junits = ""'1/m!" pC t I*3 I I *"'"'# V"I Food _& Ground = Pathway, units pCi/sec 2-48 Revision 23 02-28-91 5 9 1 4 w --,9r,n-,,--.-- - - - - - ,-,--w+...,--, ,a
TABLE 2-8
, DOSE PARAMETER Ri FOR SECTOR Q Page 9 of 9 Pathway San Clemente Ranch Adm. Offices Distance - 2.5 miles X/Q 2.7E-7 sec/(m') D/Q - 1.lE-9 m
infant Child Teen Adult Food i inhala- Food & Inhal a- Food & Inhala- Food & Inhala- Ground tion Ground Radio, tion Ground tion Ground tion Pathway Pathway Pathway Pathway Pathway Nuclide Pathway Pathway Pathway 0- 0- 4.3E+2 1.9E+3 H -3 0- 4.9E+3 8.3E+6 Cr-51 0- 0- 0- -0 4.8E+5 1.3E+9 Hn 54 0-
-r- -d- 1.3E+5 3.6E+8 Co-57 3.2E+5 '6.0E+8 Co-58 0- 0- 2.0E+6 1.0E+10 Co-60 0- 0-
-0 4.8E+5 7.2E+9 Sr-89 0- 3.4E+7 5.8E11 Sr-90 -0 0- 6.1E+5 9.9E+8 Zr 95 0- 1.7E+5 3.6E48 Nb-95 0- 0-
- 1.7E+5 4.2E+8 Ru-103 4.0E+5 9.6E+8 Te-129m Cs-134 2.9E+5 1.2E+10 Cs-136 0- 5.0E+4 8.7E+7 Cs-137 2.lE+5 1.lE+10 Ba-140 0- -0 4.4E+5 6.0E+7 Ce-141 1.2E+5 3.2E+8 Ce-144 0- ! 2.7E+6 9.0E+9 1 -131 0- I 0- 4.lE+6 1.4E+9 1 -132 3.9E+4 4.2E+5 1 -133 0, 7.4E+5 8.4E+5 1 -134 1.0E+4 1.5E+5 1 -135 -
1.5E+5 8.6E+5 UN-ID - 3.0E+5 1.3E+9 Inhalation Pathway, units "C1/m!r p I*a I I *"*/"I Food & Ground Pathway, units pC1/sec 2-49 Revision 23 02-28-91 l l
o . TABLE 2-9 j DOSE PARAMETER Ri FOR SECTOR R Pa9e 1 of.5 j P&thway = San Onofre Mobile Homes Distance 1.2 miles q 0/Q - 3. 2 E- 9 n,' ' X/Q - 5.3E-7 sec/m' Infant Child Teen Adult , Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground ; Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Patht y Pathway l 1 1.1E+3 1.3E+3 0- 1.3E+3 t H -3 F FE+2 4.7E+6 4.7E+6 1.7E+4 4.7E+6 2.1E+4 4.7E+6 1.4E+4 Cr-51 1.3E+4 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E+6 1.4E+9 Mn 54 1.0E+6 5.1E+5 3.4E+8 5.9E+5 3.4E+8 3.7E+5 3.4E+8 - Co-57 3.8E+5 3.4E+8 1.1E+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Co-58 7.8E+5 3.8E+8 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6. 0E+6 2.2E410 Co 60 4.EE+6 2.0E+6 -2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-89 i 1.0E+8 0- 1.1E+8 0- 9.9E+7 Sr-90 4.1E+7 2.5E+8 2.5E+8 1.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+ 6 Zr-95 1.BE4 6 4.bE+5' 1.4E48 6.1E+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8
- - Nb-95 Ru-103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.1E+8 5.0E+5 ! 1.1E+8
Te-129m- 1.7E+6 2.0E+7 1.8E+6 2.0E47 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 7.0E+5 6.8E+9 1.0E+f 6.8E+9 1.1E+6 6.8E+9 8.5E+5 6.3E+9 . Cs-136 1.3E+b 1.5E+8 1.7E+S 1.5E+8 1.9E+5 1.5E+8 1.5E+5 1.5E+8 Cs 137 6.1E+E 1.0E+10 9.1E+5 1.0E+10 8.5E+5 1.0E+10 6.2E+5 1.0E+10 Ba-140 1.6E4 6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6 2.1E+7 Ce-141 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.4E+7 3.6E+5 1.4E+7 , Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 1 -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1 7E+7 1.2E+7 1.7E+7 L -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I -134 4.5E+4 4.5E+5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 j 1 -135 7.0E+5' 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 Inhalation Pathway, units - yj*(Y" Food & Ground Pathway, units im r r) j 2-50 Revision 23 ' 02-28-91
. . 8.
IABLE 2-9 DOSE PARAMETER Rj FOR SECTOR _ R 4 l Page 2 of 5_ ; I Pathway = San Clemente, Ranch (No Residents') Distance = 2.3 miles > X/Q < 2.0E-71 sec/m D/0 = 1.0E 9 m *- Infant Child Teen . Adult Inhala- Food & Inhala. Food-& Inhala- Food & Inhala- Food &- tion- Ground tion Ground tion Ground. tion Ground Radio-- Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide. , C- 3.8E+3 - 2.4E+3 1.9E+3 H 3. 0- 6.7E+6 0- 4.8E+6 0- 7.4E+6 , Cr 51 8.3E+8 0-- 8.0E+8 Mn-54 6.1E+8 -0 0-- 2.2E+8 0- - 2.9E+8- 2.4 E+8 Co.57 - 0
- 3.3E+8 S.1E+8 ' 4.7E+8 Co-58 -0* 2.7E+9 Co 60; 0- -0 2.0E+9 3.0E+9 '
3.1E+10 1.2E+10 0: 7.2E+9-Sr 89 0- 5.8E+11
- 5 r 90 -- -0 . 1.3E+12 0- 7.7E+11
' 0- 7.8E+8 1.1E+9 9.1E+8
-Zr -
3.1E+8 Nb 95 - 2.4E+8 3.5E+8 3.3E+8 4.5E+8 0- 3.8E+8 - Ru-103 9.5E+8 A
-Te-129m -0 -0 : 2.3E+9 0- 1.4E+9 :
-Cs-134 - 2.4E+10 1.5E+10 - 9.2E+9
-Cs-136' ' 9.0E+7 5.7E+7 0= 3.6E+7 Cs-137 0- -0 2.2E+10 1.3E+10 - 7.8E+9
.Ba-140 1.1E+8 6.8E+7- 5.3E+7 3.3E+8 4.1E+8 ~0-
- 3.2E+8
'Ce 141.
Ce 144 0- 9.2E+9 1.2E+10 9.0E,9 I -131 -0 ' 4.1E+9 2.1E+9 1.4E+9 , I 132 6.0E-36 2.6E-36 1.7E-36 I -133 L4.0E-11 1.7E-11 1.1E-11 I -134 6.1E-37 2.7E-37 0- 1.7E-37 I--135 ' 7.0E-35 3.1E-35 - 1.9E-35 2'.5E+9 1.7E+9- 1.1E+9 l UN ID . d
"'*/
Inhalation Pathway, units = "Ci/m?" p LFood'&-Ground Pathway, units I*3 I'**#Y"I pC1/sec 2-51 Revision 23 02-28-91 . r 4 - ,- .,sw..--.~,d....~ <4
,~~..+4&v,,, ..+-s .e . .,y.rg %-- .-4 .-x--, ,w w~, ,-.m ---r,~, ,.+mv y--c,,,--c-,.v.y --
IABLE 2-9 005E PARAMETER Rj FOR SECTOR R Page'3 of 5 Pathway - SC Ranch Packing Distance - 2.6 miles X/Q - 1.7E-07 sec/m* D/Q - 8.2E-10 m** Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Ground tion Ground jtion Ground Radio- tion Ground tion Pathway Pathway Pathway' Pathway Patnway Nuclide Pathway Pathway Pathway l i J
-0 0- 7.4E+2 1.9E+3 H -3 8.4E+3 9.5E+6 Cr-51 -0 8.2E+5 1.6E+9 i Mn 54 !
-0 2.2E+5 4.4E+8 Co-57 0- -0 5.4E+5 6.9E+8 Co-58 0-0- 3.5E+6 1.5E+10 Co 60 0- '
Sr-89 0- 8.2E+5 7.2E+9 0- 5.8E+7 5.8E+11 Sr-90 -0 1.lE+9 i Zr-95 0- 1.0E+6 0- 2.9E+5 3.9E+8 Nb-95 4.4E+8 Ru-103 -0 2.9E+5 0- 0- 6.BE+5 9.6E+8
-Te-129m 1.3E+10 0- 4.9E+5 Cs-134 1.2E+8 Cs-136 0- -0 8.5E+4 Cs-137 3.6E45 1.4E+10 0- 7.4E+5 6.5E+7 Ba-140 Ce-141 2.1E+5 3.3E+8 4.5E+6 9.0E+9 Ce-144' 1 -131 7.0E+6 1.4E+9 I -132 6.7E+4 7.2E+5 1 -133 0- 1.3E+6 1.4E+6 I -134 1.7E+4 2.6E+5 I -135 2.6E+5 1.5E+6 UN-ID 5.0E+5 1.5E+9 i
Inhalation Pathway, units *'
*C1/m!"
g m m /vr) $ Food & Ground Pathway, units - pC1/sec 2-52 Revision 23 02 28-91
I IAllLE 1-2 OOSE PARAMETER Rg FOR SECTOR R
. Pa9e 4 of 5 Pathway - Sheep Heat Distance = 0.9 miles X/Q = 8.3E-7 sec/m' 0/Q - 5.2E 9 m
- Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Grcund tion Ground tion Ground tion Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide Pathway 0- 1.5E+0 1.2E+0 7.0E+0 2.lE+0 H3 1.0E+2 7.9E+1 2.6E+4 Cr 51 0- 0- 5.lE+1
-0 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Hn-54 1.9E+6 4.7E+3 8.lE+3 2.0E+3 Co 57 5.lE+3 2.lE+6 Co 5B -0 9.7E+3 2.0E+4 0- 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Co-60 3.1E+4 5.0E+4 2.6E+4 7.7E+3 Sr 89 1.3E+6 1.0E+6 8.1E+5 5.5E+5 Sr-90 0-1.6E+6 2r-95 0- 6.3E+4 1 lE+5 9.7E+3 2.4E+5 4.5E+5 '2.8E+3 1.6E+6 Nb.95 -0 0- 4.2E+5 7.6E+5 2.8E+3 1.9E+6 Ru-103 0-6.0E+5 4,5E+5 6.4E+3 7.6E+5 Te 129m 0- 1.4 E+ 5 0- 1.2E+5 4.7E+3 3.8E+7 Cs-134 Cs 136 5.1E+3 4.3E+3 3.lE+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 ha-140 -0 0- 5.1E+3 4.3 E >3 7.0E+3 1.2E+5 Ce 141 0- 0- 1.5E+3 0- 2.4E+3 2.0E+3 7.9E+4 Ce-144 0- 1.8E+4 3.0E+4 4.3E+4 4.3E+5 1 -131 0- 6.6E+5 4.4E+5 6.6E+4 7.0E+5 1 -132 0- 6.3E+2 6.BE+3 1 -133 -0 1.6E-2 8.7E-3 1.2E+4 1.3E+4 1 -134 '
0- 1.6E+2 2.5E+3 1 -135 -0 0- 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN 10 1.1E+5 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units mrem /yr pC1/m food & Ground Pathway, units I*'II'""**/YPI pC1/sec 2-53 Revision' 23 02-28-91
y . _ _ . . . . ~ . . . _ _ _ . _ _ p ;
- . e
' TABLE 2-9 r
DOSE PARAMETER Rj FOR SECTOR R Page 5 of 5 -! 1 Pathway =DeerCor,sumeg Distanca - 2.2 miles 4 l X/Q yl.8E-7 sec/m D/Q - 8.8E-10 m** Infant Child Teen -Adult Inhala- Food & Inhala- Food & Inhala- Focd & Inhala. Food & Radio- tion- Ground tion Ground tion Ground- tion Ground i Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide H -3 - 0- 0- 2.8E+1- 2.3E+1 3.5E+1 3.9E+1 1, Cr 0- 5.0E+4 1.0E+5 3.9E+2 0- 0- 7.7E+5- -0_ l.4E+6 3.8E+4 3.2E+5l, 4.1+7
-Mn-54 0- .
Co 57 0- 4.6E+6 8.0E+6 1.0E+4 2.3E+7 0- 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co 58-- 0 0- 0- 3.6E+7 7.2E+7 1.6E+5 7.2E+8 :
'Co 60 Sr-89 0- 4.9E+7 2.6E+7 3.8E+4 3.lE+7 Sr 90 0- 0- 1.0E+9 -0 _ 0.0E+8 2.7E+6 1.2E+9 0- 6.2E+7 1.lE+8 4.8E+4- 2.0E+8 Zr-95 2.3E+8 4.5E+8 1.4E+4. 8.2E+8 Nb 95-Ru 103: 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te 129m - 0- 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Cs-134- 1.4E+8 1.2E+8- 2.3E+4 3.4E+8 .
Cs-136 ! 5.1E+6 4.2E+6 4.0E+3 9.5E+6 Cs 137 0- 1.3E+8 9.3 E+7 1.7E+4 4.0E+8 l Ba 140 - 5.0E+6 -4.2E+6 3.5E+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3' -4.2E+6 Ce-144 0- - 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.lE+3 3.4E+4-- I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4. 1 -134 -0 -C- 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID - 1.1E+8 9.4E+7 2.4E+4- 1.4E+8-L
-\.
Inhalation Pathway, units _
"g'j*(!"
Food & G"ound Pathway, units I*'II*"'*#VPI gCi/sec t 2-54 Revision 23 02-28 91
+.= a
. TABLE 2-10 ,
DOSE PARAMETER R FOR 5ECTOR A 9 . Page 1 of 3 l. Pathway Camp San Mateo Distance - 3.6 miles * -; X/Q _7,lE 8 sec/m' - 0/Q - 4.lE 10 m* - j Infant- Child -Teen Adult Food & Inhala. Food & Inhala- Food & Inhala. Food & inhala. Ground Radio- tion Ground tion Ground tion Ground tion' Pathway Fathway Pathway Pathway Pathway Nuclide Pathway Pathway pathway
-0 0- 1.3E+3 0 H -3 0- - -
4.7E+6 '
-0 - 0- 1.4E+4 Cr-51 1.4E+6_ 1.4E+9 ;
0- - 0- -0 ~ Mn 54 3.7E+5- 3.4E+8-0- Co 57 9.3E+5 3.8E+8-Co 58- - 0- 0- 6.0E+6- 2.3E+10 Cc-60 - 1.4E+6 2.2E+4 Sr-89 0- :
-0 9.9E+7 Sr-90 -0 . -0
-0 . 1.8E+6 2.5E+8 Zr-95 -- 0- 0- 0- 5.0E+5 1.4E+8 Nb 95 5.0E+5 1.lE+8 Ru 103 0- .
1.2E+6- 2.0E+7 Te-129m 0- - - 8.5E+5 6.8E+9
-Cs-134 Cs-136' -04 0- - 0-- 1.5E+5 1.5E+8-Cs-137 ' a0 - 0- 0- 6.2E+5 1.0E+10 0- 0- 1.3E+6 2.1E+7 Ba-140 -
Ce-141 3.6E+5- -1.4E+7-Ce-144 1 0- 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7-
- 1.lE+5- 1.2E+6 1 -132 - - . 2.2E+6 2.4E+6 133 .
-I -134 3.0E+4- 4.5E+5 I--135 4.5E+5 2.5E+6 UN ID - 0-- - 8.6E+5 7.5E+8: ;
b Inhalation Pathway, units =pCi/m! "I'*# " 7 r 2 Food & Ground Pathway, units'- (m ifmrem/vr) pC1/sec 2-55 Revision' 23 02-28-91 N 7
--r a.,ew,-..-,r,- ,,-mv,~ ,.,,y- v - ww m te- , e - i,-v vv w w e v %w e re ww-e ev - w' w w wem sw evee w eww ,w-g *= w ev~+ t --*~-t wo e T -r 9 " wre - - w w g- r ~' me-w w " y "* m g
. e 18Mll:10 OOSE PARAMETER R g FOR SECTOR A Page 2 of 3 Pathway Sheep (Meat)'
Distar.*e - 0.2 miles D/0 5.2E-8 m** X/Q = 6,7E-6 sec/m Child Teen Adult Infant Inhalt- ' Food & Inhala- Food & Inhala- Fooi & Inhala I -Food & tion Ground tion Ground tion Cround tion Ground Radio- Pathway Pathway Pathway Pathway Pathway Nuclide Pathway Pathway Pathway 1.5E+0 0- 1.2E+0 7 .0 E+0 2.lE+0 H3 7.9E+1 2.6E+4 i 0- 0- 0- 5.1E+1 1.0E+2 Cr-51 1.4E+3 7.7E+3 7.6E+6 Mn-54 7.8E+2 1.9E+6 4.7E+3 8.lE+3 2.0E+3 Co 57 5.lE+3 2.lE+6 0- 0- 9.7E+3 2.0E+4 Co-58 7.3E+4 3.3E+4 1.2E+8 Co 60 3.7E+4 3.1E+4 2.6E+4 7.7E+3 Sr 89 -0 5.0E+4 1.3E+6 0- 1.0E+6 0- 8.lE+5 5.5E+5 Sr-90 0- 9.7E+3 1.6E46 6.3E+4 1.lE+5 Zr-95 0- 2.8E+3 1.6E+6 0 0- 0- 2.4E+5 4.5E+5 Nb 95 7.6E+5 2.8E+3 1 9E+6 Ru-103 4.2E+5 7.6E+5 0- 6.0E+5 4.5E+5 6.4E+3 Te-129m 0- 4.7E+3 3.8E+7 Cs-134 0- 1.4E+5 1.2E+5 4.3E+3 8.lE+2 8.3E+5 Cs-136 5.1E+3 9.5E+4 3.4E+3 5.7E+7 Cs-137 1.3E+5 1.2E+5 5.lE+3 4.3E+3 7.0E+3 Ba-140 2.0E+3 7.9E+4 Ce-141 0- 1.5E+3 2.4E+3 3.0E+4 4.3E+4 4.3E+5 Ce-144 0- 1.8E+4 7.0E+5 0- 6.6E+5 4.4Ev5 6.6E+4 I -131 6.EE+3 6.3E+2 I -132 8.7E 3 1.2E+4 1.3E+4 I -133 0- 1.6E-2 1.6E+2 2.5E+3 I -134 - 0.- 1.4E+4 I -135 1.1E-18 6.4E-19 2.5E+3 f
- 1. lE+ 5 9.5E+4 4.8E+3 4.2E+6 UN-ID Inhalation Pt.thway, units mremy uCl/m I* ""M Food & Ground Pathway, units uti/sec 2-56 Revision 23 02-28-91
. . 1 IMLE_2-10 :
005E PARAMETER R FOR SECTOR A 9 Page 3 of 3-Pathway - Deer Consumer Distance - 2.2 miles X/Q = 1.9E-7 sec/m* D/Q 1.4E 9 m , Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food i Inhala- Food a Radio-- tion Ground tion Ground tion Ground tion Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide 2.8E+1 0- 2.3E+1 3.5E+1 3.9E+1 H -3 3.2E+5 0- 0- 5.0E+4 1.0E+5 3.9E+2 Cr-51 3.8E+4 4.lE+7 Hn-54 7.7E+5 1.4E+6 0- 4.6E46 8.0E+6 1.0E+4 2.3E+7
~
Co-57 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co 5S 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Co-60 4.9E+7 2.6E+7 3.8E+^ 3.lE+7 Sr-89= 1.0E6 0- 8.0E+8 2.7E+6 1.2E+9 Sr 90-6.2Et7 1.1E+8 4.8E+4 2.0E+8 Zr-95 1.4E+4- E.2E+8 Nb-95 0- 2.3E+8 0- 4.5E+8 Ru 103 0- 4.2E+8 0- 7.5E+8 1.4E+4 1.3E49 Te-129m 0- 5.9E+8 - 4.5E+8 3.2E+4 6.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs 136 0- 5.1E+6 4.2E+6 4.0E+3 -9.5F+6 Cs-137- 0- 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140 5.0E+6 4.2E+6 3.5E+4 7.4E+6 C0-141 0- 1.5E+G 2.4E+6- 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.lE+5 4.9E+7 I -131 6.5E+8 4.3E+B 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 1 -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 0- 1.1E 15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = } I* H*"'*/VII Food & Ground Pathway, units pC1/sec 4 l 2-57 Revision 23 02-28-91 1' i-l.
e .- -..- -..-- - - . - . - - - ~ - t TABLE'2-11 y F 005E PARAMETER R F0F, SECTOR 8 l j : Page 1 of 3 ; Pathway:= Sheep (Meat)' Distance = 0.2 miles X/Q = 6.1E 6 sec/m D/Q = 5.3E 8_m*' ; Infant Child- Teen' Adult i Inhala- Food & Inhala. Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion --Ground tion Ground Nuclide Pathway _ Pathway Pathway Pathway Pathway Pathway Pathway Pathway , H -3 1.5E+0 1~.2E+0 7.0E4 0 2.1E+0 ; Cr 51 30- 0- 0- 5.1E+1 .0- 1. 0 E+ 2 7 . 9 E+ 1 -- 0.6E+4 i Mn 54 0 7.8E+2- 1.4E+3 7.7E+3 - 7.6F+6 Co 57 0- 4.7E+3 8.1E+3 2.0E+3 1.9E+6 Co-58 0- 0-- 9.7E+3 2.0E+4 - 5.1E+3 2.1E+6 Co 60 3.7E+4 7.3E+4 3.3E+4 1.2E+B Sr-89 :-0-- 5.0E4 4 2.6E+4 7.7E+3- 3.12+4
= Sr 90 : -0 . - 1.0E+6 8.1E+5 5.5E+5 1.3E+6 Zr 95 : -0J 6.3E+4- 1.1E+5- 9.7E+3 1.6E+6
-Nb 95 -0 0- 2.4E+5 - 4.5E+5 2.8E+3 1.6E+6:
Ru 103- 4.2E+5 0- 7.6E+5 2,8E+3 1.9E+6 ,
.Te-129m ~0-
- 6.0E+5 -4.5E+5 -6.4E+3 7.6E+5-
-Cs-134 . - 0- 1,4E+5 1.2E+5 4.7E+3 3.8E+7 Cs-136- 0- 0 5.1E+3 ;4.3F+3 8.1E+2: 8.3E4 5 Cs-137 - 0- -0 0- 1.3E+5 9.5E+4 3.4E+2 5.7E+7 Ba-140l - '5 1E+2 4.3E+3. 7.0E+3 :1.2E+5 Ce 141' 1.5E+3 -2.4E+3- 2.0E+3- 7.9E+4-
~Ce-144 -0 ' 0 -0 1.8E+4 3.0E+4' 4.3E+4 4.3E+5 1 -131 6.6E+5 4.4E+5 -6.6E+4 7.0E+5 '
I -132 : -0 1 6.3E+2 6.8E+3
- I -133 . -1.6E-2 8.7E 1.2E+4- 1.3E+4 I -134 .
- 1.6E+2 2.5E+3.
I -135, 1.1E-18 6.4E-19 2.5E+3 1.4E+4 , UN ID 1.1E+5 .-0-- 9.5E+4 4.8E+3 4.2E+6 s
-Inhalation Pathway, units- EEIEllE .
pCi/m Food & Ground Pathway, units.= ik 'fmrem/vr) pui/sec
^ "
2-58 Revision 23 > 02-28-91 _,. .m.- - . . ._m_ . - . , _ _ _ . ~ . _ , _ _ . . . . _ . _ _ _ - . _ . , , - . . . _ . _ . _ _ . - . - , - _ , -
l mu.2.u DOSE PARAMETER R4 FOR SECTOR B Page 2 of 3 IPathway=DeerConsumer Distance 1.1 miles X/Q - 3.4E 7 sec/m' 0/Q - 2.4E-9 m-' infant Child Teen Adult inhala- Food 1 Inhala- Foor k Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide Pathway 0- 2.8E+1 2.3E+1 3.5E+1 3.9E+1 H.3 3.9E42 3.2E+5 0- 0- 0- 5.0E+4 0- 1.0E+5 Cr 51 3.8E+4 4.1E+7 Mn 54 7.7Et5 1.4E+6 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co 57 0- -0 4.7E+7 9.6E+6 0- 1.9E+7 2.5E+4 Co 58 0-7.2E+8 Co 60 3.6E+7 7.2E+7 1.6E+5
-0 4.9E+7 2.6E47 3.CE+4 3.lE+7 Sr 89 1.2E+9 Ir 90 1.0E+9 8.0E+8 2.7E+6 6.2E+7 1.lE+8 4.8E+4 2.0E+8 Zr-95 0- 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Nb 95 1.4E+4 1.3E+9 Ru 103 0- 4.2E+8 -0 7.5E+8 0- 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Te-129n; -0 0- 1.4E4 8 1.2E+8 2.3E+4 3.4E44 Cs-134 C-5.1E+6 4.2E+6 4.0E+3 9.5E+6 Cs-136 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Cs 137 5.0E+6 4.2E+6 3.5E+4 7.4E+6 Ba 140 0- 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce 141 -
Ce-144 1.8E+7 2.9E+7 2.1E+5 4.9E'7 1 -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 1 -132 3.1E+3 3.4E+4 1 -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 , I -134 8.2E+2 1.2E+4 1 -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 inhalation Pathway, units
*"*i/m pC f
*# f 2
Food & Ground Pathway, units - (m Hmrem/vr! pCi/sec 2-59 Revision' 23 02-28-91 1 l
a . 161LE 2-11 00' E PARAMETER Rg FOR SECTOR B Page 3 of 3 1 Distance - 2.1 miles Pathway . Sanitary I.andfill' X/Q = 1.4E-7 sec/m' 0/Q - 1.2E 9 m ' Infant I Child Teen -Adult ; Inhala - Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio-- tion Ground tion Ground tion Ground tion Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway s Nuclide Pathway H -3 2.9E+2 . , Cr-51 -0 0- 3.3E+3 1.1E+6
.Mn 54- 3.2E+5. 3.2E+8 ,
0- 0- 0 - 8.4E+4- .7 BE+7 Co-57 Co 58 0- = 0- 0- 0- 2.1E+5 8.7E+7-Co-60 0 -0 0- -1.4E+6 4.9E+9 Sr 0- 0- 3.2E+5 4.9E+3-Sr-90 0- 0- 0- 2.3E+7 > Zr-95 - 0- 4.0E+5 5.7E+7 Nb 95-. 1.2E+5 3.1E+7 Ru-103 0- 1.2E+5- 2.5E+7 , Te-129m 0- C'- - 2.6E+5 4.5E+6 Cs-134 . 0- -C - - 1.9E+5- .I.6E+9 Cs-136: 0- 3.3E+4- 3.4E+7 Cs-137 0- - 1.4E+5 2.3E+9 Ba-140 0- -0 . 0- 2.9E+5 4.7E+6 Ce 141- 0- 8.3E+4 3.1E+6 m Ce-144 ' 0- .1.8E+6' 1.6E+7= f I -131- - 2.7E+6 3.9E+6
-I -132 0- 2.6E+4~ 2.8E+5 1 -133 - 0- 4.9E+5 5.6E+5 1 -1341 6.8E+3 1.0E+5
.I -135~ 0- -
0- 1.0E+5 -5.8E+5
-UN-ID -0 .. 2.0E+5 .1.7E+8 p
- l Inhalation Pathway, units l
"Ci/m!"
p p '" II""'*/V"I Food'&-Ground Pt.thway, units pCi/sec L l '. 2-60 Revision 23 02-28-91 y
. . ~ . . . _ - - , -. . - - --
1 e .- TABLE 2-171 i: DOSE PARAMETER R g FOR SECTOR C Page 1 of 5 Pathway Camp-San Onofre Distance - 2.6 miles X/Q = 9.2E-8 sec/m' D/Q - 8.4E-10 m ' I Child Teen Adult 1 Infant - ! Food & Inhala- Food & Inhala- Food & Inhala- Food & l Inhala- Ground tion Ground tion Ground tion Ground tion Radio- Pathway Pathway Pathway Pathway Pathway Nuclide Pathway Dathway Pathway 1.3E+3 H .3 0- 1.4E+4 4.7E+6 0- i Cr 51 1.4E+6 1.4E+9 Mn-54 0- 0- 0- 3.7E+5 3.4E+8 Co-57 -0 3.8E+8 0- -0 9.3E+5 Co 58 6.0E+6 2.2E+10 Cn-60 1.4E+6 2.2E+4 St-84 0- 0- 9.9E+7 Sr 9) 0- 1.8E+6 2.5E+8 Zr-E5 0- 0- 5.0E+5 1.4E+8 Nb-95 0- 0-0- 0- 5.0E+5 1.1E+8 Ru-103 . 0- 1.2E+6 2.0E+7 Te-129m 8.5E+5 6.8E+9 Cs-134 0- 0-0- 1.5E+5 1.5E+8 i Cs-136 6.2E+5 1.0E+10 Cs-137 0- 0- 0- Sa-140 1.3E+6 2.1E+7 4-Ce-141 3.6E+5 1.4E+7 Ce.144 7.8E+6- 7.0E+7 0- 1.2E+7 1.7E+7 I -131 0-1 -132 0- 0- 1.lE+5 1.2E+6 I -133 0- 2.2E+6 2.4E+6 I -134 0- 3.0E+4 4.5E+5 I -135 0- 4.5E+5 2.5E+6
'UN-ID- 8.6E+5 7.5E+8 Inhalation Pathway, units mrem /yr uti/m 3
Food & Ground Pathway, units - (m Mmrem/vr1 pC1/sec 2-61 Revision 23 02-28-91
TABLE 2-12 i 5 DOSE PARAMETER R FOR SECTOR C 9 Pagr. ? of 5 l Pathway - Camp San Onofre fr. Stn Distance = 2.3 miles X/Q = 1.lE-7 sec/m - C/Q - 1.lE-9 m ' Infant Child Teen Adult Inhala. Foodk Inhala- Food & Inhala- food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Pathway _ Pathway Pathway Pathway Pathway Pathway Pathway Pathay Nuclide 0- 5.2E+2 0-H3 0- Cr-51 - 5.9E+3 1.9 E46 Hn 54 0- 5.8E+5 5.7E+8
- -0 0- 0- 0- 1.5E+5 1.4E48 Co-57 Co-58 0 3.8E+5 1.6E+8 Co 60 0- 0- -0 2.5E+6 8.8E+9 Sr 89 0- 5.8E45 8.9E+3 0- 4.lE+7 Sr-SO Zr-95 -0 0- 7.3E+5 1.0E+8 Nb 95 0- 2.lE45 5.6E+7 Ru 103 0- 0- 2.lE+5 4.5E+7 Te 129m 4.8E+5 8.lE+6 Cs-134 0- 3.5E+5 2.8E+9 Cs 136 1
-0 0- 0- - 6.0E+4 6.2E+7 Cs-137 -0+ 2.6E+5 4.2E+9-Ba-140 +0- - 5.2E+5 8.4E+6 Ce 141 . 1.5E+5 5.6E+6 Ce-144 3.2E+6 2.9E+7 I -131 T- 4.9E+6 7.1E+6 I -132 4.7E+4 5.1E+5 I -133 0- - 8.8E+5 1.0E+6 1 -134 1.2E+4 1.8E+5 I -135 '
1.8E+5 1.0E+6 UN-ID -3.6E+5 3.lE+8 1 InhalationPathway, units-]j!" Fnod & Ground Pathway, units I*2 ' * " *#Yd pCi/sec 2-62 Revision 23 02-28-91
~
o s TABLE 2-12 FOR SECTOR C OOSE PARAMETER R9 Page 3 of 5 Pathway Sewage Facility Distance - 2.2 miles D/0 - 1.2E 9 m ' . X/Q = 1.2E-7 sec/m' l Child Teen Adult Infant food & Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Ground tion Ground Radio- tion Ground tion Ground tion l Pathway Pathway Pathway Pathway Pathway Nuclide Pathway Pathway Pathway l 2.9E+2 0-H -3 0- 0- 3.3 E43 1.lE+6 Cr-51 -0 3.2E+8 0- 0- 0- 3.2E+5 Hn-54 0-0- 8.4E+4 7.8E+7 Co 57 -0 2.lE+5 8.7E+7
-0 Co 58 0- 1.4E+6 4.9E+9 Co 60 3.2E+5 4.9E+3 Sr-89 2.3E+7 0-0- 0- 0-Sr-90 4.0E+5 5.7E+7 Zr-95 1.2E+5 3.lE+7 Hb-95 '
1.2E+5 2.5E+7 Rucl03 2.6E+5 4.5E+6 0- ' Te-129m 1.9E+5 1.6E+9 Cs-134 -0 0- 3.3E+4 3.4E+7 Cs-136 1.4E+5- 2.3E+9 Cs-137 0 2.9E+5 4.7E+6 Ba-140 8.3E+4 3.1E+6 Ce-141 Ce-144 -t - 1.8E+6 1.6E+7 I -131 2./E+6 3.9E+6 I -132~ 0- 2.6E+4 2.8E+5 I -133 4.9E+5 5.6E+5
! -134 6.8E+3 1.0E+5 1.0E+5 5.8E+5 I -135 UN-ID. 2.0E+5 1.7E+8 Inhalation Pathway, units mrem /yr pC1/m Hmrem/vr)
Food & Ground Pathway, units - gCi/sec 2-63 Revision' 23 02-28-91
. +
IAhll i DOSE MRMUE' d FOR j SECTOR C Page 4 of 5 Pathway - Sheep (Meat)' Distance 0.2 mi',es' X/Q - 6.5E 6 sec/m D/Q - 5.3E-0 m-I Infant Child een Adult inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Grounc tion Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide 1.5E+0 1.2E+0 7.0E+0 2. lE< C H -3 2.6Ed Cr-51 0- 5.lE+1 1.0E+2 7.9E+1 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Hn 54 0- 4.7E+3 8.lE+3 2.0E+3 1.9E+6 Co-57 0- 0- 9.7E+3 2.0E+4 5.lE+3 2.lE+6 Co 58 7,3E+4 3.7 E+4 3.3E+4 1. 2 E+ B Co-60 5.0E+4 2.6E+4 7.7E+3 3.1E+4 Sr-89 0- 1,0E+6 8.1E+5 5.5E+5 1.3E+6 Sr-90 9.7E+3 1.6E+6 Zr-95 6.3E+4 1.1E+5 2.4E+5 4.5E+5 2.8E+3 1.6E+6 Nb-95
-C- 4.2E+5 7.6E+5 2.0E+3 1.9E+6 Ru 103 0 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Te-129m 1.4E+5 1.2E45 4.7E+3 3.8E+7 Cs-134 Cs-136 -0 5.1E+3 4.3E+3 8.1E+3 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba-140 5 lE+3 4.3E+3 7.0E+3 1.2E+5 Ce 141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 Ce-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 1 -131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 1 -132 6.3E+2 6.8E+3 1 -133 0- 1.6E-2 8.7E-3 1.2E+4 1.3E+4 I -134 1.6E+2 2.5E+3 1 -135 1.lE-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.lE+5 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units - yr Food & Ground Pathway, units I" ""M pCi/sec 2-64 Revision'23 02-28-91
IAllL2:12 1
* , DOSE PARAMETER R FOR SECTOR C 9 'Page 5 of 5-P.athway=DeerConsumeg Distance = 1.0 miles
- 3 3 - 3.4E 7-sec/m 0/Q = 5.1E 9 m- .
Infant Child Teen Adult
~
Inhala- Food &= Inhala- Food 1- Inhala- Food & Inhaia- Food & Radio- tioni Ground tion Ground tion- . Ground tion Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide H -3 - 0- 0- 0- 2.8E+1 - 2.3E+1 3.5E+1 3.9E+1 0- 0- 5.0E+4 - 1.0E+5 3.9E+2 3.2E+5 ,
- Cr 51 -
4.1E+7 Mn 54 - 0- 0- 7.7E+S 1.4E+6 3.8E+4 0- 4.6E+6 8.0E+6 1.0E+4 -2.3E+7 Co 57 - 0 0- 9.6E+6 0- 1.9E+7 2.5E+4 '4.7E+7 . Co-58 ' Co 60- -0 3. 6 E+ 7 7.2E+7 1.6E+5 7.2E+8 0- - 0.- 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-89
- Sr-90 0- 1.0E+9 8.0E+8 2.7E+6 1.2E+9
' 0- 0- 6.2E+7 0- 1.1E+8 4.8E+4 2.0E+8-Zr Nb 95 - 0- 0- 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 0- 4. 2E+8 7.5E+8 1.4E+4 1.3E+9 Te-129m 0- -0 5.9E+8 4.5E+8 3 2E+4 -6.4E+8 Cs-134 -
0- 1.4E+8 1.2E+8 2.3E+4 -3.4E+8-
-Cs-136 . 5.1E+6 4.2E+6 4.0E+3 -9.5E+6 Cs-137 -
0- 0- 1.3E48 9.3E+7 1.7E+4 '4.0E+8 Ba-140 0- -0 5.0E+6 4.2E+6 3.5E+4 7.4E+6!
.Ce-141 1.5E+6 2.4E46' 9.9E+3' 4.2E+6-Ce-144 1.8E+7 2.9E+7 2.1E+5- 4.9E+7 '
I -131 0- 6.5E+8 4.3E+8 3.3E+5 5.9E+8-I -132 3 1E+3 3.4E+4 I -133 - 1.6E+1 8.6E+0 5.9E+4 6.7 E+4 I -134 8.2E+2 1.2E+4-
.I -135-- 0-- 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-10 - -
0- 1.1E+8 9.4E+7 2.4E+4- 1.4E+8 i Inhalation Pathway, units = y*Ch
- Food &~ Ground Pathway, units = #* *F'*#VPI 2-65 Revisich 23 02-28-91 d . y ---
r - , + , . , . ,y.n ----g. . _ - ,_-.....rm ..,,,.-.....r..,~.i,-r -- , - , - , ..
b CI.'
- TABLE 2-13 DOSE PARAMETER Rj FOR SECTOR D Page 1 of 3 Pathway-CampSanOno[re Distance - 2.8 miles '
X/Q = 6.6E 8 sec/m D/Q = 6.4E 10 m- - -i 1 Teen Adult ) Infant ' Child Food &- Inhala- Food & Inhala- rood & Inhala- Food & Inhala-Ground tion f Ground tion Cround Radio tion Ground tion Pathway Pathway Pathway Pathway. Pathway R Nuclide Pathway Pathway Pathway 0- 0- 1.3E+3 0-- H -3 0- 1.4E+4 4.7E+6 Cr-51 -0 0-0- 0- 1.4E+6 1.4E+9 Hn 54 3.7E+5- 3.4E+8 Co-57 0- 0- -0 0- 0 9.3E+5 3.8E+8 Co-58 -0 6.0E+6 2.2E+10 Co-60 - i 1.4E+6 2.2E+4 <- Sr 9.9E+7. 0-Sr . 0- 1.8E+6 ' 2.5E+8 Zr Hb 95 0. 0- 0- 5.0E+5 1.4E+8 Ru-103 -- 5.0E+5 1.1E+8 - 1.2E+6 2.0Et? Te-129m -- Cs-134 J. 0-- 8.5E+5 6.8E+9 Cs-136- 0- -0 ' 0- 1.5E+5 1.5E+8 Cs-137- . 6.2E+5 -1.0E+10 0- 1.3 E+6 2.lE+7 Ba-140-Ce-141- .-0-- 0- 3.6E+5: 1.4E+7-Ce-144 7.8E+6 7.0E+7 1 -131 0- 1.2E+7 1.7E+7 ? I -132- - 1.1E+5 1.2E+6 I -133 2.2E+6 2.4E+6 I -134 0- 3.0E+4 4.5E+5 I -135 0- 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 t i i P^ l. I' Inhalation Pathway, units E '*#T" uCi/m Food & Ground Pathway, units I"2 II*"'*#V"I pC1/sec 2-66 Revision 23 02-28-91
TABLE 2-13 DOSE PARAMETER R g FOR SEC10R D Pa9e 2 of 3 Pathway - Sheep (Meat)' Dista nce - 0.2 miles
- X/Q - 6.3E 6 sec/m 0/Q = 6.6E 8 m-Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhal a- Food & Inhala- Food &
tion Ground tion Ground tion Ground tion Ground Radio- Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pothway Nuclide 1.5E+0 0- 1.2E+0 7.0E+0 2.lE+0 H -3 0- 2.6E+4 7.9E+1 0- 1.0E+2 Cr-51 5.lE+1 0- 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Mn-54 0- 1.9E+6 4.7E+3 8.1E+3 2.0E+3 Co-57 5.1E+3 2.lE+6 Co 58 0- 9.7E+3 2.0E+4 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Co 60 0- 5.0E+4 2.6E+4 7.7E+3 3.1E+4 Sr 89 Sr-90 0- 0- 1.0E+6 8.lE+5 5.5E+5 1.3E+6 6.3E+4 1.lE+5 9.7E+3 1.6E+6 Ir-95 0- 2.4E+5 .0- 4.5E+5 2.8E+3 1.6E+6 Nb 95 0- 4.2E+5 , 7.6E+5 2.8E+3 1.9E+6 Ru-103 6.4E+3 7.6E+5 6.0E+5 ~ 4.5E+5 4 Te-129m 1.4E+5 1.2E+5 4.7E+3 3.8E+7 Cs-134 8.3E+5 Cs 136 5.lE+3 4.3E+3 8.1E+2 Cs 137 1.3E+5 I 9.5E+4 3.4E+3 5.7E+7 5.1E+3 4.3E+3 7.0E+3 1.2E+5 Ba-140 C- 1.5E+3 2.4E+3 2.0E+3 7.9E+4 Ce-141 Ce-144 1.8E+4 3.0E+4 4.3E+4 4.3E+5 1 -131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 1 -132 6.3E+2 6.8E+3 1 -133 1.6E-2 8.7E 3 1.2E+4 1.3E+4 1 -134 1.6E+2 2.5E+3 1 -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8Ev3 4.2E+6 Inhalation Pathway, units grem/vr uti/m* I* " " /Y"I Food & Ground Pathway, units pC1/sec 2-67 Revistor. 23 02-28-91
TABLE 2-13 00SE PARAMETER Rg FOR SECTOR D Page 3 of 3 1 Pathway - Deer Consumer Distance - 1.0 miles 0/Q 3.3E-9 m
- X/Q = 3.3E 7 sec/m' Infant Child Teen Adult Inhala- food & Inhala- Food & Inhal a- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide 0- 0- 2.8E+1 0- 2.3E+1 3.5E+1 3.9E+1 H -3 3.2E+5 0- 5.0E+4 0- 1.0E+5 3.9E+2 Cr 51 4.1E+7
-c 0 0- 7.7E+5 0- 1.4E+6 3.8E+4 Mn 54
-Os 4.6E+6 8.0E+6 1.0E+3 2.3E+7 Co-57
- 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co 58 -0 -0 0- 3.6E+7 0- 7.2E+7 1.6E+5 7.2E+8 Co 60 3.1E+7 0- 4.9E+7 2.6Et7 3.8E+4 Sr-89
-0 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Sr-90 0- 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Zr-95 8.2E+8 Nb-9E 0- 0- 2.3E+8 4.5E+8 1.4E+4
-0 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Ru-103 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Te-129m 0- 1.4E+8 1.2E+8 2.3E+4 3.4E48 Cs 134 Cs-136 5.1E+6 4.2E+6 4.0E+3 -9.5E+6 Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0E+8 Ba-140
- 5.0F+6 4.2E+6 3.5E+4 7.4E+6 Ce-141 1.5Et6 2.4E+6 9.9E+3 4.2E+6 Ce-144 0- 1.8E+7 2.9E+7 2.1E+5 4.9E+7 I.-131 ~0- 6.5E+8 4.3E+8 3.3E+5 5.9E+8
- 1 -132 3.1E+3 3.4E+4 I -133 ~0- 1.6E+1 0- 8.6E+0 S.9E+4 6.7E+4 I -134 0- 8.2E+2 1.2E+4 I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.1E+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = ]j*
Food & Ground Pathway, units I* Yd f 2-68 Revision 23 02-28-91
IAlllE 214 00$E PARAMETER Rg FOR $ECTOR E P a r' ' I of 3 Pathway . Camp Horno Distance = 4.0 miles D/0 6.4E 10 m
- X/Q = 6.6E 8 sec/m' Child Teen Adult Infant Food & Inhala. Fcod & Inhala- food &
Inhala- food & Inhala-tion Ground tion Ground tion Ground Radio- tien i Ground Pathway Pathway Pathway Pathway Pathway Nuclide l Pathway Pathway Pathway ( 0 0- 0- 1.3E43 0 H3 0- 0- 0 0- 0- 1.4E44 4.7E46 Cr 51 0- 9 0- 0 0- C. 0- 1.4E46 1.4E+9 Mn 54 0- 0- 0-0- 0- 0- 3.7E45 3.4E4B Co 57 0- tv 0-0- 0- 0 9.3E+5 3.8E+8 Co 50 0 0 0 0- 0- 0- 0- 6.0E46 2.2E+10 co ce 0 0 0- 1.4E+6 2.2E+4 Sr 89 0- 0- 0 0* 0- 0 O' 9.9[+7 0 Sr 90 0- -0 0- 0 l 0 0 0- '0- 1.8t+6 2.5E48 Zr 95 0- 0- 5.0E45 1.4E48 Nb 95 0- 0- 0- 0-0 0- 0- 0 5.0E+5 1.lE4B Ru 103 0+ 0- 2.0E+7 0- 0- 0- 0- 1.2E+6
- Te-129m 0 0- 6.BE+9 0 0- 0- 0- 8.5E45 Cs 134 0- 0- 1.5E+8 0- 0- 0 0- 1.5E+5 Cs 136 0 1.0E+10 Cs 137 0- 0- 0- 0- 6.2E+5 0 0- 0 0- 1.3E46 2.lE+7 Ba 140 0- 0 1.4E+7 0- 0- 0- 0- 0- 3.6E45 Ce 141 0-0- u- 0- 0- 7.8E46 7.0E+7 Ce 144 0-0- 0- 0- 0- 0- 1.2E47 1.7E+7 1 -131 0-0- 0- 0- 1.1E+5 1.2E46 1 -132 0-1 133 0 0- 0 0- 0- 2.2E46 2.4E+6 0- 0- 0- 3.0E4 4 4.bE+5 1 134 v- 0
-0. 4.5E45 2.5E+6 1 13J. - 0- 0 0- 0-0- 8.6E< 5 1.5C+8
,Wlb 0-- 0- 0 r
*# YF Inhalation Pathway, units = *Ci/ms p I* **/ Y d food & Ground Pathway, units pC1/sec 2-69 peytston 23 02 28 91 I
a . TABLE 2-11 005E PARAMETER R9 FOR SECTOR E Page 2 of 3 Pathway Sheep (Heat)' Distance = 0.3 miles X/Q = 4.5E 6 sec/m D/Q = 5.9E 8 m ' Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala. Food & Inhala- food & I Ground tion Ground tion Ground Radio. tien Ground tion Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide Pathway 1.5E+0 0- 1.2E+0 7.0E+0 2.lE+0 H3 0- 0 0 0- 1.0E+2 7.9E+1 2.6E44 l Cr 51 0 0 0 5.lE+1 I 0- 0- 7.8E+2 0- 1.4E+3 7.7E+3 7.6E46 Hn 54 0- l Co 57 C 0- 4.7E+3 0- 8.lE+3 2.0E+3 1.9E+6 !
- 0. 0- 0- 9.7E+3 0- 2.0E+4 5.lE+3 2.lE46 Co 58 1.?E+8 l 0- 0- 0- 3.7E+4 7.3E+4 3.3E+4 Co 60 3.lE+4 0- 0- 0- 5.0E+4 0- 2.6E+4 7.7E+3 Sr 89 5.5E+5 1.3E46 Sr-90 0- 0- 0- 1.0E+6 0- 8.1E+5 0- 6.3E+4 0- 1.lE+5 9.7E+3 1.6E+6 Zr 95 0-0- 2.4E+5 0- 4.5E+5 2.8E43 1.6E+6 Nb 95 0-
-0 4.2E+5 7.6E+5 2.8E+3 1.9E46 Ru 103 0- 0- 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Te 129m 0-0- 0- 1.4E+5 0- 1.2E+5 4.7E+3 3.8E+7 Cs 134 0-0- 0- 5.lE+3 0- 4.3E+3 8.lE+2 8.3E+5 Cs 136 0-0' 0- 1.3E+5 -0 9.5E+4 3.4E+3 5.7E+7 Cs-137 0-0- 0- 5.1E+3 4.3E+3 7.0E+3 1.2E+5 Ba-140 0- 0- 1.5E+3 0- 2.4E+3 2.0E+3 7.9E+4 C6-141 0 0- 0- 1.8E+4 3.0E44 4.3E+4 4.3E+5 Ce 144 131 0- 0- 6.6E+5 0- 4.4E+5 6.6E+4 7.0E+5 1
1 -132 0, 0- 0- 0- 6.3E+2 6.8E+3 0- 1.6E-2 0- 8.7E-3 1.2E+4 1.3E+4 , 1 -133
- I -134 0 0- 0- 0- -0 0- 1.6E+2 2.5E+3 1 -335 +0- 0- 1.1E-18 6.4E-19 2.5E+3 1.4E+4 -
UN 10 1 lE+5 0- 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units - " I ""'Y"I Food & Ground Pathway, units 2 70 Revision 23 1 02 28-91 L
I IABLLL11 DOSE PARAMETER Rg FOR SECTOR E Ptge 3 of 3 Pathway Deer Consumet. Distance 1.2 miles D/0 8.3E 9 m ' X/Q = 3.7E 7 sec/m' Infant Child Teen Adult Food & Inhala- food & Inhala- food & Inhala- food & inhala- Ground tion Radio. tion Ground tion Ground tion Ground Pathway Pathway Pathway Pathway Pathway Nuclide Pathway Pathway Pathway 0- 2.8E+1 0- 2.3E+1 3.5E+1 3.9E+1 H3 0- 0-5.0E+4 0- 1.0E+5 3.9E+2 3.2E+5 Cr 51 0- 0- 0-0- 7.7E+5 0- 1.4E+6 3.8E+4 4.!E+7 Hn 54 0 0-4.6E+6 0- 8.0E+6 1.0E+4 2.3E+7 Co 57 0 0 9.6E46 0- 1.9E+7 2.5E+4 4.7E+7 Co 58 0- -0 0- 3.6E+7 0 7.2Et7 1.6E+5 7.2E+8 Co 60 0- 0-0- 0- 4.9E+7 -0 2.6E+7 3.8E+4 3.lE+7 Sr 89 0- 1.2E+9 1.0E+9 -0 8.0E+8 2.7E+6 Sr 90 0 4.8E+4 2.0E+8 0- 0- 6.2E+7 0- 1.lE+8 Zr 95 1.4E+4 8.2E+0 Hb 95 0- 0- 0- 2.3E+8 0- 4. 3E+ 8 0- 4.2E+8 0- 7.5E+8 1.4E+4 1.3E+9 < Ru-103 .0 0-0- 5.9E+8 0- 4.5E+8 3.2E+4 6.4E+8 Te 129m 0 0-0- t.4E+8 0- 1.2E+8 2.3E+4 3.4E+8 Cs 134 0- 5.lEt6 0 4.2E+6 4.0E+3 9.5E46 Cs 136 0-
- 0. . 1.3E+8 0. 9.3E+7 1.7E+4 4.0E+8 Cs 137 0-0- 0- 5.0E+6 0- 4.2E+6 3.5E+4 7.4E+6 Ba-140 0-0- 0- 0- 1.5F36 0- 2.4E+6 9.9E+3 4.2E46
% Ce 141 0- 1.BE+7 2.9E+7 2.lE+5 4.9E47 Ce-144 -0 0- 0- 0- 6.5E+8 -0 4.3E+8 3.3E+5 5.9E+8 1 131 1 -132 0- 0- 0 0- 3.lE+3 3.aE+4 1 -133 0- 1.6E+1 0- 8.6E+0 5.9E44 6.7E+4 1 -134 -0 0- 40- 0- 8.2E+2 1.2E+4 1 135 0- 1.1E 15 6.3E 16 1.2E+4 6.9E+4 UM-ID 0- 0- 1.lE+8 0- 9.4E+7 2.4E+4 1.4E+8 InhalationPathway, units ="C]/
Food & Ground Pathway, units a -@ pC1/sec Hmrem/vrl l 2 71 Revision 23 02 28 91
.__..________._m.._.___.___.m.-_.__ ~ _ - . _
o s TABLE 2 15 DOSE PARAMETER Rg FOR SECT 0k Page 1 of 5
~
Pathway Olstance 0.8 miles
$an Onofre S} ate Park Guard Shack 0/Q = 7 lE 9 m 8 X/Q = 8.1E 7 sec/m -
Infant Child Tsen Adult eenn U.# Inhala. Food & Inhala- food 6 inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Pathway Pathway Pathway . Pathway Pathway Pathway Pathway Pathway Nuclide 0 0- 7.2E+1 0 H3 0- 0 0 0- -0 0- 0- 0- S.2E+2 2.7E+5 Cr 51 0-0- 0- 0- 0 0- 0- 8.0E+4 7.9E+7 i Mn.54 0: 0- 0- 0 0 0 2.lE+4 2.0E4 7 Co 57 "> 0- 0- 0- . 0- 0- 5.3E+4 2.2E+7 Co 58 0-0- 0 0- 0- 3.4E+5 1.2E+9
-Co 60 0
$r 89 0- 0- 0 0- 8.0E+ 4 1.2E+3 ,
- 0-0- 0- 0- 0- 0 5.7E+6
^ Sr 90 1.4E+7. - Zr 95 0- 0- 0- 0- 0- 1.0E+5 4
- 0- 0- 0- 0 0- 2.9E+4 7.8E46 :
Nb 95 ' 0 -0 0- 0- 2.9E+4 6.2E46 Ru 103 ?
- Te-129m 0- 0- 0 0 0- 6.6E+4 1.lE46 0- 0- 0 9- C- 4.8E+4 3.9E+8 .j Cs 134 0- i 0- 0 .0 0 0- 0 6.4E+3 8.6E46
-Cs 136 "
k . 0- 0- 0 0- 0- 0- 3.5E+4 5.9E+8 Cs 137 Ba 140 0- 0 0 0- 0- ?.3E44 1.2E+6
- Ce 141 -0 0- 0- 0- 0- 0- 2.lE+4 7.8E4 5 Ce 144- -0 0- 0- 0 0- 0- 4.41+5 4.0E+6 I 0- 6.0E+ 5 9.8E+5
- I 101 0- u- 0- 0-0 0- 0- 0- 6,$E+3 7.lE+4 i d
'l 132 0- 0 '
I 133 0 0- 0- 0- 0- 1.2E+5 1.4E+5 r
- 0- i.7E+3 2.GE+4
. 1 -134 0- 0 0- -0 1 135 0- . 0-- 0- 0- 2.6E+4 1.4E+5-F 4,9E+4 UN 10 0- 0- 0- 0- 0- 4.3E+1 i Inhalation Pathway, units E l R L pC1/ ins Food & Gror.nd Pathway, units h d inrem/vtl i - pC1/sec i 1 i 2 72 Revision'23 ; 02-28 91 l l? L e
. . . - . - - . . . - . . . - - . = . , . - , .- - . . . - . - - .a.-.-_.-
e
- IAi!LLL*.i DOSE PARAMETERy R FOR L O M F Page 2 of 5 Pathway . Beach Concession Distance = 0.9 miles D/Q = 6.0E 9 m
- X/Q = 6.9E 7 sec/mi Child Teen Adult Infant l
Inhala. Food & Inhala- foob inhala- Food & Inhala- Food & Ground tion Ground tan Ground tion Ground Radio. tion Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide 0- 0- 0 0- 1.2E+2 g3 0 0- 4.4E45 0 0- 0- 0 1.3E+3 Cr.$1 0- 0- 1.3E+0 0 0- 0- 1.3E+5 Hn 54 0 0 0- 0- 0- 3.5E+4 3.2E+7 co 57 0- 0- 0 0- 0 -0 0- *0* 'O' 8*7E+4 3 EE+7 Co 58 0- 5.6E+5 2.0E49 0- 0 -0 0- 0-Co 60 0- 1.3E+5 2. 0 E+ 3 St 89 0- 0- 0- 0- 0 0- 0- 0- 0- 9.3E+6 0-Sr 90 0- 0- 2.4E+7 0- 0 0- 0- 1.7E+5 Zr 95 0- 0-0- -0 0- 0- 4.7E+4 1.3E+7 Nb 95 0- 4.7E+4 1.0E+7 Ru 103 0- 0 0- 0- 0-0- 0- 0- 0- 1.lE45 1.8E46 - Te 129m 0- 7.9E+4 6.4E+8 0- 0 0 0- 0-Cs 134 0 0- 1.4E+4 1.4E+7 Cs-136 0- 0- -0 0- 0- 0- 5.BE44 9.6E4B Cs 137 0- -0 1.9E+6
-0 -0 0- 0- 0- 1.2E+5 Ba 140 0- 1.3E+6 0- 0- 0- 0- 3.4E44 Ce 141 0- 6.5E+6 0- 0 0 0- 0- -0 7.3E+5 Ce 144 0- 0- 0- 0- 0- 0- 1.!E+6 1 6E46 1 131 0- 1.lE+4 1.2E45 I -132 0- 0- 0- 0- ,
0- 0- 0- 0- 0- 2.0E45 2.3E+5 1 133 0-0- 0- 0 0- 2.8E+3 4.2E+4 1 134 0-2.4E+5 I 135 0- 0- 0 0- 4.2E+4 UN+1D 0- 0 8.lE+4 7.0E47 t e 4 b Inhalation P4thway, units y jj' food & Ground Pathway, units Im'H mtf.m/Yr} pC1/stc 2-73 Revision' 23 02-28 91 _ _ _ , . ~ . _ . . . - . - _ _ , _ - , . .. ._ _ . -
m - - . - - - - - - - _ _ _ _ l . . lAXLhil 005E PARAMETER Rg FOR SECTOP F Page 3 of 5 Pathway Border Patrol Checkpt. Distance 1.8 miles X/Q = 2.4E-7 sec/m . D/Q = 1.8E 9 m
- Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Fr.od & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide Pathway 0- 0- 0- 0- 3.6E+2 H3 0 0-0- 4.1E+3 1.3E46 Cr 51 3- 0- 0- 0- 0-0- 0- 0- 0- 4.0E+5 3.9E+8 Hn 54 0- 0-0- -0 0- 1.1E+5 9.8E+7 Co 57 -0 0-0- 0- -0 0- 0- 2.6E+5 1.1E48 Co 58 0- 6.1E+9 0- 0- 0- 0- 1.7E+6 Co-60 0- 6.2E+3 0- 0- 0- 0- 4.0E+5 Sr 89 0- Sr 90 0- 0- 0- 0- 2.8E+7 0- 0- 0- 0- 5.0E+5 7.2E+7 Zr 95 3.9E+7 Nb 95 0- 0- 0- 0- 0- 1.4E+5 0- 0- 0- 0- 0- 1.4E+5 3.1E+7 Ru-103 Te 129m 0- 0- 0- 0- 3.3E45 5.6E+6 0- 0- 0- 2.4E+5 1.9E+9 Cs-134 0- 0- 0- 0- 4. 2 E+ 4 4.3E+7 Cs 136 0-0- 0- 1.8E+5 2.9E+9 Cs 137 0-0- 0- G- 0- 3.6E+5 5.9E+6 B2-140 0- 0- 0- 0- 1.0E+5 3.9E46 Ce 141 0- u- 0 0- 2.2E+6 2.0E+7 Ce 144 0- 0- 0- 3.4E+6 4.9E+6 I 131 0- 0-3.5E+5 1 132 0- 0- 0- 3.3E+4 I -133 0- 0- 0- 0- 0- 0- 6.18:+5 7.0E45 0- 0- 0- 0- 0- 0- 8.5E+3 1.3E+5 1 -134 I -135 -0 0- 0- - 1.3E+5 7.2E+5 UN 10 0- 0- 2.5E+5 2.1E+8 i
/
Inhalation Pathway, units - gu $"l/m7 Food & Ground Pathway, units . MM pCi/ser, 2-74 Revision 23 02-28-91 l _ heh'
( IABLE 2-13 OOSE PARAMETER R g FOR SECTOR F Pa9e 4 of 5 Pathway Sheep (Meat)' Distance = 0.5 miles' X/Q = 1.9E 6 sec/m 0/Q = 1.7E 8 m-Infant Child Teen Adult Inhala- Food & Inhala- food & Inhala- food & Inhala- Food 5 Radio- tion Ground tion Ground tion Ground tion Ground Pathway Pat' ay Pathway Pathway Pathway Pathway Pathway Nuclide Pathway 0- 1.5E+0 0- 1.2E+0 7.0E+0 2.1E+0 H3 0- 0-1.0E+2 7.9E+1 2.6E+4 Cr 51 0- 0- 5.1E+1 " 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Hn 54 0- 1.9E+6 0- 0- 4.7E+3 8.1E< 3 2.0E+3 Co 57 0- 2.1E+6 9.7E+3 0- 2.0E+4 5.1E+3 Co 58 0- e0-3.7Ev4 0- 7.3E+4 3.3E+4 1.2E48 Co 60 7.7E+3 3.1E+4 0- 5.0E+4 0- 2.6E+4 Sr 89 0 8.1E+5 5.5E+5 1.3E46 Sr 90 0- 1.0E+6 0-0- 6.3E+4 0- 1.1E45 9.7E+3 1.6E+6 Zr 95 0-1.6E+6 Hb 95 0- 0 0- 2.4E+5 4.5E+5 2.8E43 4.2E45 7.6E+5 0.8E+3 1.9E+6 Ru 103 7.6E+5
-0 6.0E+ 5 0- 4.5E+5 6.8E+3
- Te 129m 0- 1.4E+5 1.2E+5 4.7E+3 3.8E+7 Cs 134 8.3E+5 Cs 136 0- 5.1E+3 0- 4.3E+3 8.1E+2 0- 1.3E+5 0- 9.5E+4 3.4E+3 5.7E+7 Cs 137 0-0- 5.1E+3 4.3E+3 7.0E+3 1.2E+5 Ba 140 Ce-141 0- 0- 1.5E+3 2.4E+3 2.0E+3 7.9E+4 Ce-144 1.8E41 3.0E+4 4.3E+4 4.3E+5 1 -131 6.6E+5 0- 4.4E+5 6.6E+4 7.0E+5 I -132 0- 0- 0- 6.3E+2 f.8E+3 1 -133 0- 1.6E-2 8.7E-3 1.2E+4 1.3E+#
1 -134 0- 0- 0- 1.6E+2 2.5E+3 ,
! -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-10 1.1E+5 0- 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units = ]j"h" Food & Ground Pathway, ut.its Im'iferem/vri gCl/see r
2.75 Revision 23 02 28 91 L _ _ _ _ _ _ _ _ _
IABLE 2-16 DOSE PARAMETER R j FOR SECTOR F Pa9e 5 of 5 - t
! Pathway Distance - 1.4 miles Deer Consume [ D/0 = 2.3E 9 m '
X/Q = 3.0E 7 sec/m Infant Child Teen Adult l Inhala- Food & Inhala- Food & Inhala. Food & Inhala- Food & tion Ground tion Ground tion Ground tion Ground Radio- Pathway Pathway Pathway Nuclide Pathway Pathway Pathway Pathway Pathway 2.8E+1 0- 2.3E+1 3.5E+1 3.9E+1 H -3 0 0- 0 5.0E+4 0- 1.0E+5 3.9E+2 3.2E+5 Cr-51 0 0 3.8E+4 4.1E+7 0- 0- 0- 7.7E+5 0 1.4E+6 Hn 54 2.3E 7 0- 0- 0- 4.6E+6 0- 8.0E+6 1.0E+4 i Co 57 4.7E+7. -l 0- 0- 0 9.6E+6 0- 1.9E+7 2.5E+4 Co 58 7.2E+8 j 0- 0- 0 3.6E47 0- 7.2E+1- 1.6E+5 Co 60 3.1E+7 Sr 89 -0 0- 0- 4.9E+7 0- 2.6E+7- 3.8E+4-0- 0- 0 1.0E+9 0 8.0E+8 2.7E+6 1.2E+9 i Sr 90- 4.8E44 2.0E+8 i
-Zr 95 . 0- --0 -
04 6.2E+7. 0- 1.1E+8 0- 2.3E+8 0- 4.5E+8 .1.4E+4 8.2E+8 Nb-95 0- 1.3E+9 0- 4.2E+8- 0- 7.5E+8 1.4E+4 Ru 103. 0 3.2E+4 6.4 E+8 Te 129m j 0 -0 5.9E+8 40- 4.5E+8 1.4E+8 0- 1.2E+8 2.3E+4 3.4E+8 Cs 134 i 0- 0-4.2E+6 4.0E+3 9.5E+6 Cs 136 0- 0- 0 5.1E+6 0 0 1.3E+8 0- 9.3E+7 1.7E44- 4.0E+0 - Cs-137 0-0- 40 5.0E+6 0 4.2E+6 3.5E+4 7.4E46
-Ba 140' 0' 0- 0- 1.5E+6 0 2.4E46 9.9E+3 4.2E+6 Ce 141 - 0..
0- 0- 0- 1.8E+7 0- 2.9E+7 2.1E+5 4.9E+7 Ce 144 0 6.5E+8 0- 4.3E+r 3.3E+5 5.9E+8 1 -131 0'
- 0. 0- 0- ' 3.1 E+3 3.4E+4 r I'-132 0- 0. C-5.9E+( 6.7E+4 !
! 133 0 0- 1.6t+1 0 8.6E44 0- 0 0- 0- 0 . 8.2E+2 1.2E+4
~I -134 0 I 135- 0 0 0- 1.1E 15 0- 6.3E.16 1.2E+4 6.9E+4 ;
UN ID '0-
- 0- -1,1E+8 0- 9.4E+7 2.4E+4 1.4 E48 -
I Inhalation Pathway, units - C
-Eocd & Ground-Pathway, units I" ""*
- P1 C1/sec 2 76 Revist d 23 r 02 28 91
. _ . . , ,u_ . . . . _ - _ . . , , . - _..,___-.._~m...,,.m..,, . ,. .
s TABLE 2 16 DOSE PARAMETER Pg FDP. SECTOR G Page 1 of 4 Pathway =SanOnofreS}ateBeachCampground Distance = 0.8 miles' X/Q
- 7.7E 7 sec/m . D/Q = 3.9E 9 m-infant Child Teen Adult inhala- Food & Inhala- Food & Inhala. Food & Inhala. Food &
Radio- tion Ground tion Ground tion Ground tion Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide H3 8.0E+1 0- 1.4E+2 0- 1.6E+2 0- 1.6E+2 0 5.7E45 2.!E+3 5.7E+5 2.6E+3 5.7E+5 1.8E+3 5.7E45 - Cr 51 1.6E+3 1.2E+5 1.7E+8 1.9E,5 1.7E+8 2.4E+5 1.7E+8 1.7E+5 1.7E*8 Hn 54 4.2E+7 6.3E+4 4.2E+7 7.2E+4 4.2E+7 4.6E+4 4.2E+7 Co 57 4.7E+4 4.7E+7 1.4E+5 4.7E+7 1.7E+5 4.7E+7 1.1E+5 4.7E+7 Co 58 9.6E44 2.7E+9 8.7E+5 2.7E+9 1.lE+6 2.7E+9 7.4E+5 2.7E+9 Co 60 5.6E45 2.7E+3 2.7E+5 2.7E+3 3.0E+5 2.7E+3 1.7E45 2.7E43 Sr 89 2.5E45 0-Sr 90 5.0E+6 0- 1.2E+7 0- 1.3E+7 0- 1.2E+7 3.1E+7 2.8E+5 3.lE+7 3.3E+5 3.lE47 2.2Ee5 3.1E+7 Zr 95 2.2E+5
-1.7E+7 7,6E+4 1.7E+7 9.3f+4 1.7E+7 6.2E44 1.7E+7 Hb 95 5. 9i.+ 4 1.3E+7 8.2E+4 1.3E+7 9.7E+4 1.3E+7 6.2E+4 1.3E+7 Ru 103 6.8E+4 - Te 129m 2.1C+5 2.4E+6 2.2E+5 2.4E+6 2.4E+5 2.4E46 1.4E+5 2.4E+6 Ct 134 8.7E+4 8.4E48 1.3E+5 8.4E+8 1.4E+5 8.4E+8 1.0E+ 5 8.4E48 Cs-136 1.7E+4 1.9E+7 2.1E+4 1.9E+7 2.4E+4 1.3E+7 1.8E+4 1.9E+7 Ct, 137 7.5E+4 1.3E49 1.lE+5 1.3E+9 1.0E+5 1.3E+9 7.7E+4 1.3E+9 Ba 140 2.0E+5 2.5E+6 2. l E+ 5 2.5E+6 2.5E+5 2.5E+6 1.6E+5 2.5E46 Ce 141 6.4 E+4 1 7E+6 6.7E+4 1. 7 E+ 6 7.6E+4 1.7E+6 4.5E44 1.7E46 1.5E+6 8.6E+6 1.6E+6 8.6E+6 9.6F+5 8,6E+6 Ce-144 1.2E+6 8.6E+6 1 131 1.8E+6 E.lE+6 2.0E+6 2.1E+6 1.8E+6 2.1E+6 1. 5C+ 6 2.!E+6 1 132 2.1E+4 1.5E+5 2.4E+4 1.5E+5 1.9E+4 1.5E+5 1.4E+4 1.5E+5 1 133 4.4E+5 3.0E+5 4.7E+5 3.0E+5 3.(E+5 3.0E+5 2.7E+5 3.0E+ 5 I -134 5.5E+3 5.5E+4 6.3E+3 5.5E+4 4.9E+3 5.5E+4 3.7E+3 5.5E44 i 135 8.6E+4 3.1E45 9.8E+4 3.1E+5 7.7E+4 3.lE+5 5.5E+4 3.1E45 UN !D 8.0E+4 9.2E+7 1.2E+5 9.2E+7 1.5E+5 9.2E47 1.lE+5 9.2E+7 l-f l
Inhalation Pathway, units - fc / l Food & Ground Pathway, units ho r r) l p p 1 2 77 Revision' 23 02 28 91
t
. i TABl.E 2-16 DOSE PARAMETER Rg FOR SECTOR G Page 2 of 4 Pathway Hwy Patrol Wgigh Statten Distance 2.0 miles ,
D/0 8.5E 10 m-X/Q 2.0E 7 sec/m Child Teen Adult Infant Food & Inhala. Food & Inhala- Food & Inhala. Food &- Inhala. tion Ground Radio- tion Ground tion Ground tion Ground Pathway Pathway Pathway Pathuf Pathway Nuclide Pathway Pathway Pathway 0 0- 0- 2.9E+P 0-H3 0- 0 0-0 0- 0- 3.3E+3 1.lE+6 Cr 51 0- 0 3.2E+8 0 0 0- 0- -3.2E+5 Hn 54 0- 0 8.4E+4 7.8E+7 0- 0- 0- 0+ Co 57 0- 0 0- 2.lE+5 8.7E+7 Co 58 -0 0- 0- 0- 0 0 0- 1.4E+6 4.9E+9 Co 60 0- 0- -0 0 4.9E+3 0 0- 0- 3.2E+5 Sr 89 0- 0 0 0- 2.3E+7 0 0- 0- 0- 0 0-Sr 90 0- 4.0E+5 5.7E+7 tr 95 0- *0- 0 0- 0 0- 0- 1.2E+5 3.lE+7 Nb 95 0- 0 ' 0- 0 1.5E+7 0- 0- 0 1.2E+5 Ru 103 0- 0- 4.5E+6 0- 0- 0 0- 2.6E45
. le 129m 0 1.9E+5 1.6E+9 0- 0- 0- 0- 0 Cs 134 3.3E+4 3.4E+7 Cs-116 0- 0- 0- 0 0-0 0 1.4E+5 2.3E+9 Cs 137- 0- 0 4.7E+6 0- 0 0 0- 2.9E+5 Ba 140 0 3.3E+4 3.lt+6 0- 0- 0- 0 0 0-Ce 141 1.6E+1 0 0- -0 0- 0- 0- 1.8E+6 Ce-144 3.9E+6 1 -131 0- 0- 0 0- 0- 2.7E+6 0 0- 2.6E+4 2.8E+5 1 132 0- 0-0- 0 0- 0- 4.9E+5 5.6E4 5 1 133 0- 0-0- 0- 0- 0- 6.8E+3 1.0E+5 1 134 0. 0 5.8E+5 0- 0- 0- 0- 0- 0- 1.0E+5 I .115 0- 2.0E+5 1.7E+8 UN ID 0- 0- 0- 0-IrhtlationPathway, units =gj
#I Food & Ground Pathway, units -
2 78 Revision' 23 02-20 91
i I i
-IAB1E 2-16 1
1 00$E PARAMETER Rg FOR SECTOR G y Pathway = Sheep (Meat)' Distance a 2.7 miles D/Q 4.8E 10 m ' - X/Q = 1.2E 7 sec/m : Infant Child Teen Adult l Inhala- food & Inhala- Food & Inhala- Food & Inhala- Food & Ground tion Ground tion Ground tion Ground Radio- tion Pathway Pathway Pathway Nuclide Pathway Pathway Pathway Pathway Pathway i 0- 1.5E+0 0- 1.2E+0 7.0E+0 2.1E+0 H -3 0-0- 5.1E+1 0- 1.0E+2 7.9E+1 2.6E+4 Cr 51 0- -0 ' 0- 7.8E+2 0- 1.4E+3 7.7E+3 7.6E+6 Mn-54 0- 0-0- 4.7E+3 0- 8.1E43 2.0E+3 1.9E+6 Co 57- 0- 0 2.1E46 0 9.7E+3 0- 2.0E+4 5.1E+3 Co 58 0- 0 3.3E+4 1.2E48 Co 60 0- 3.7E+4 0- 7.3E+4
-0 5.0E+4 0- 2.6E+4 7.7E43 3.1E+4 fr 89 -0+ 0 0: .8.1E+5 5.5E+5 1.3E46
$r 90- 0 0 0- 1.0E+6 0 6.3E+4 0- 1.1E+5 9.7E+3 1.6E+6 Zr 95 -0 0-0- 2.4E+5 0- 4.5E+5 2.8E+3 1.6E+6 Nb 95 -0 0- 1 0- 4.2E+5 0 7.6E+5 2.BE+3 1.9E+6 Ru 103 0- 0-6.0E+5 0 4.5E+5 6.4E+3 7.6C+5 Te 129m 0 0- 0 .
1.4E+5 1.2E+5 4.7E+3 3.8E+7 - Cs 134 c.. 0-
-0 5.1E+3 -0 4.3E+3 8.1E+2 8.3E+5 ;
Cs 136 0- 0-0- 0- 1.3E+5 0- 9.5E+4 3.4E+3 5.7E+7 Cs 137 C ' 0 0- 5.1E+3 0- 4.3E+3 7.0E+3 1.2E+5 Ba-140 0 0' 0- 1.5E+3 0- 2.4E43 2.0E+3 7.9E+4 Ce 141 0- 1.8E+4 3.0E+4 4.3E4 4 4.3E+5 Ce 144 I 131 0 0- 0- 6.6E+5 4.4E+5 6.6E+4 17.0E+5 I 132 0- 0- 0- -0 6.3E+2 6.8E+3 : I 133 0- 0- 1.6E-2 8.7E 3 1.2E+4 1.3E+4 i 0- 0- 0- 1.GE42 2.5E+3
! 134 0 1 -135 -0 0+ 1.1E 18 0- 6.4E 19 -2.5E+3 1.4E+4 UN ID' 0- 1.1E+5 0- 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units E 8 pC1/m*
Food & Ground Pathway, units IE U ""#V"I pC1/sec 2-79 Revision 23 02 28-91 _ ._ . _ _ _ .. , _ _ _ . . _ . . _ _ . , _ . . ~ . _ , _ . . . . . . _ _ . _ _ . _ _ _ . _ . _ _ , _
i . TABLE 2-16 DOSE PARAMETER Rg FOR SECTOR G Page 4 of 4 , Pathway a Deer Consumer Distance = 3.3 miles '. : X/Q - 8.8E 8 sec/m' D/Q = 3.2E 10 m-Child Teen Adult infant Food L Inhala- Food & Inhala- Food & Inhala. Food & Inhala- Ground tion Ground Radio- tion Grouno tion Ground tion Pathway Pathway Pathway Pathway Pathway Nuclide Pathway Pathwly Pathway - i 0- 2.8E+1 0- 2.3E+1 3.5E+1 3.9E+1 H3 0 0-0- 1.0E+ 5 3.9E+2 3.2E+5 Cr 51 0- 0- 0- 5.0E+4 0- 7.7E+5 1.4E+6 3.8E+4 4.1E+7 En 54 0- 0 1.0E+4 2.3E+7 0 -0 0- 4.6E+6 -0 8.0E+6 Co 57 1.9E+7 2.5E+4 4.7E+7 Co 58 0- 0- 0 9.6E+6 0-0- 3.6E+7 0- 7.2E+7 1.6E+5 7.2E+8 Co 60 0- 3.8E+4 3.1E+7 Sr C9 0- 0 0- 4.9E+7 2.6E+7 0- 1.0E+9 b.0E48 2.7E+6 1.2E+9
-Sr 90 0- 0 4.8E+4 2.0E+8 6.2E+7 0- 1.lE+8 Zr 95 0 4.5E+8 1.4E44 8.2E+8 Nb 95 0- 2.3E+8 0-0- 4.2E+8 0- 7.5E+8 1.4E+4 1.3E+9 Ru 103 -0 -0 ~
0- 5.9E+8 0- 4.5E48 3.2E+4 6.6E+8 Te 129m 0- 0-1.4E+8 1.2E+8 2.3E44 3.4E+8 Cs 134 0- 0-0- 0- 5 lE+6 0- 4.2E+6 4.0E+3 9.5E+6 Cs-136 0-0- 0- 1.3E+8 0- 9.3E+7 1.7E+4 4.0E+8 Cs 137 7.4E46 0- 5.0E+6 0- 4.2E46 3.5E+4
\ Ba-140 Ce 141 0-0-
0-0- -0 1.5E+6 2.4E+6 9.9E+3 4.2E+6 0- 0- 1.8E+7 2.9E+7 2.lE+5 4.9E+7 Ce 144 0- 0- 0- 6.5E+8 4.3E+8 3.3E+5 5.9E48 1 -131 3.4E+4 1 132 0- 0- 0- 0- 0- 3.1E+3 0- 1.6E+1 8.6E40 5.9E+4 6.7E44 1 -133 I 134 0- 0- 0- 0- 0- 8.2E+2 1.2E+4 0- 0- 1.lE-15 6.3E-16 1.2E+4 6.9E+4 I -135 1.4E+8 UN ID 0- 0- 1.1E+8 0- 9.4E+7 2.4E+4 Inhalation Pathway, units = } Food & Ground Pathway, units fm r vrl j l 2-80 Revision 23 02 28 91
2.9 TOTAL 00$E CALCULATIONS 2.9.1 Total Dose to Most Likely Member of the Public The total annual dose or total dose comitment to any member of the public, due to releases of radioactivity and to radiation, from tranium fuel cycle sources within 5 miles of the Site is calculated using the following expressions. This methodology is used to meet the dose limitations of 40 CFR 190 per twelve consecutive months. The transportation of radioactive material is excluded from the dose calculations. The Annual Total Dose is determined monthly for maximum organ (gas & liquid),wholebody(gas & liquid)and thyroid (gas & liquid) to verify that the Site total (Units 1, 2 and 3) is less than or equal to 25 mrem, 25 mrem and 75 mreu respectively.
.1 Annual Total Organ Dose (f0T(organ))
12 2/3 g D. (organ) - t I D (OG) + 0 (OL) + D ,(OG) (2 20) TOT 11 j1 j1 ji j1 ; j - Units 1, 2 and 3 1 months : - 12**
- NOTE:N D'(OG)-t,forbone J1
**All to be sumed over the most recent 12 months, where:
n (2 21) 0 (OG) - K I C)Rik k; g N i - each isotope in ji - t al specific organ category year uci K = 3.1688E-2 sec Ci 2 81 Revision 21 02-15-90 i
2.9 TOTAL 005E CALCU!ATIONS (Continued) 2.9.1 Total Dose to Mest Likely Member of the Pua11e (Continued) n = number of isotopes in the specified organ category C gj = total particulate gas curies released for the month IR4g Wk = controlling location factors from ODCH Tables 2-6, Units 1 and 2/3 D (OL) = liquid organ dose for the specified organ in mrem for the j1 month. (Reference 00CH Units 2/3 (1 19). Unit 1 (1 13)) N D'(00)=fNote:H'bonecontribution=as ji 0) organ dose form tritiu
.2 Annual Total Whole Body Dose .--- DTOT E 12 2/3 -
+ 0(Direct);
D (WB) =~-r I D (WBL) + D N
,(OG) + 0.9 0 (7) (222)
- TOT 1 1- j=1 j1 j1 ji
.= Units 1, 2 and 3
= months 1 12*
*To be summed over the most recent 12 months, where:
D (WBL) = liquid whole body organ dose in orem for the whole month, ji (Reference ODCM Units 2/3 (1 19), Unit 1 ODCM (1 13)1
' DN '(OG) = gas organ dose from tritium in arse for the month.
L j1 (from-(221)) 0 = gama air dose in mrad fc* the month.
- J1(y). 0.9 converts mrad to mrem.
(ReferenceODCMUnits2/3(214), Unit 1ODCM(210)] h n 4 l D (Direct) = z max (D(beach)q) 2: i=1 O(bkgd)q
.0342 (223) l- j=1 n.
i - for all TLDs per quarter j = for Quarters 1-4 2-87 Revision 21 02 15 90
s . 2.9 TOTAL DOSE CALCULATIONS (Continued) 2.9.1.2 6anual Total _Whole Pody Dose D T01 331 (Contfnued)
- Direct Radiation The direct radiation levels are evaluated most recently Jsing cadmium covered TLDs. The TLDs are placed at 59 locations around the site. The average dose from TL0s 5 to 50 miles from the site is used as background. These sites are subject to change.
The background is subtracted from the highest reading plant surrounding area TLD. This value is the direct dose but must be prorated by the occupancy factor
- Example; beach time of 300_ hour.1, or 8 hours for landward occupancy, yr yr D
.3 Annual Total Thyroid Dose TOT (THYROID) 12 2/3 - -
D(THYROID)- I E (0 (OG) + 0 (OL) ; (2 24) TOT 1-1 j-1 j1 ji
.j - Units 1, 2 and 3 1 - months 1 - 12*
*To be sumed over the most recent 12 months, where:
D (OG) - thyroid organ dose from gaseous iodine for the month j1 in mrem. (from221) D J1(OL)liquid thyroid organ dose for the month in mrem.(Refe 2-83 Revision 21 02-15-90 l f
e 3.0 PROJECTED DOSES 3.1 1.iquid Dose Projection J The rnethodology used for projecting a liquid dose over 31 days ( for Specification 1.3.1 is as follows:
- 1. Determine the monthly total body and organ doses resulting from releases during the previous twelve months.
- 2. Projected dose - Previous 12 months' dose divided by 12 for the total body and each organ.
3.2 Gaseous Dese Projection The methodology used for projecting a gaseous dose over 31 days for Specification 2.4.1 is as follows:
- 1. Detarmine the monthly gama, beta and crgan dose resulting from releases during the previous twelve months.
- 2. Projected dose = Previous 12 months' dose divided by 12 for the gama, beta and organ doses. -
31 Revi'sion 22 08 02 90
i 4.0 E00lPMENT 4.1 RADI0 ACTIVE L10VID EFFlVENT MQilIORING INSTRUMENTATION
$1ECIFICATIQS 4.1.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 41 shall be OPERABLE with their alarWtrip setpoints set to ensure that the limits of Specification 1.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with Section 1.4.
APPLICABillTY: At all times ACTION:
- a. With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 4-1. Exert best efforts to return the
- instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument (s) remain inoperable for greater than 30 days, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.
- c. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE and either the appropriate ACTION items in Table 4-1 not taken or the necessary rurveillances not performed at the specified frequent;y prescribed in Table 4-2, an INVESTIGATIVE REPORT shall be prepared which identifies the cause(s) for the event and definas the corrective actions to be taken to proclude recurrence of the event.
SURVEILLAN(E REOUIREMENTS
.1 Each radioactive liquid effluent mor.itoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK.
SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4-2.
.2 At least once per 4 hours, all pumps required to be providing dilution to meet the site radioactive effluent concentration limits of Specification 1.1.1 shall be determined to be operating and providing dilution to the discharge strecture.
4-1 Rev'ision 23 02-28 91 )
TABLE 4-1 . RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS OPERABLE A _CTION INSTRUMENT *
- 1. GROSS RADI0 ACTIVITY MONITORS PROVIDING rdRM TERMlHATION OF RELEASE 1 28
- 4. Liquid Radwaste Effluent Line - 2/3 RT-7813 j-Steam Generator Blowdown (Neutt:11zation Sump), 29 ;
- b. 1 full Flow Condensate Polisher Eftluent Line - 2(3)RT-7817 I 1 30
- c. Turbine Plant Sumps Effluent Line - 2(3)RT-7821 Steam Generator (ECBS) Blowdown Effluent 29
- d. 1 Line - Z(3)RT6759 29
- e. Steam Generator (E089) Blowdown Effluent 1 Line - 2(3)RT6753
- 2. FLOW RATE MEASURENENT DEVICES 31 I
- a. Ligald Radwaste Eifluent tire
- b. Steam Generator Blowdown (Neutralization Sump), 1 31 Full Flow Condensate Polisher Effluent Line 31 1
- c. Steam Generator (LOB 8) Blowdowr, Bypass Effluent Line I 31
- d. Steam Generator (E089) Blowdown Bypass Effluent Line 1
Revision 22
^ 4-2 08-02-90 1
i i L - - - -
l s JJjM41 (Continued ; TABtr NOTATION i
- Monitor Recorders are not required for the Operability of the monitor.
e providing the inoperable recorder does not cause the monitor to become ! inoperahse (1.o,, feedback signal . As long as the monitor has indicction, ; alarmcapellity(ifapplicable),)properresponse(baseduponsurvelliance requirements) and isolation function (if appitcable), the loss of the recoider does not rtnder the monitor inoperable. ACTION 28 - With the number of channels OPERABLE less than required by the ' Minimum Channels OPERABLE requirements, effluent releases may tontinue provided that prior to initiating a release: : a, At least two independent samples are analyzed in accordance with $pecification 1.1.1 and b.. At least two technically qualified nmbers of- the Facility Staff inde endently verify the release rate calculation and discharge ine lying: Otherwise, suspenc' release of radioactive affluents via this pathway. !
- - ACTION 29 - With the number of channels OPERABLE less than required by the Minimum Channels ONRABLE recuirement, effluent releases via this pathway may continh providet grab samples are analyzed for gross !
l radjonctivity (beta or gamma) at a limit of detection of 'at least 10* microcuries/ gram:
- a. At least once per 8 hours when the specific activity of the
- secondary coolant is-greater than 0.01 microcuries/ gram DOSE EQUIVALENT l 1311 .
- b. At least once per 24 hours when the specific activity of the secondary coohnt is less than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT 1-1311 or
- c. Lock closed valve HV 3773 and divert flow to T-064 for processing as liquid radwaste.
ACTION 30 - With the number of channels OPERABLE less-than required by the Minimum-Channels OPERABLE recuirement, effluent releases via this . pathway may continue providec that,- at least once per 12 hours, grab samples are collected and analyzed within 4 hours of collection time for gross rapicacttvity (beta or gamma) at a limit of detection of ' at least 10' .microcuries/ml or lock closed valve S22U19 MUO77 or S22U19 MUO78 and divert flow to the radwaste sump for processing as liquid radwaste. ACTION 31.- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves ma.y be used to estimate flow. 4-3 Rev'ision 22 08 02 90
$ " w <igt-6o tw ~ ,.g.i- ,y, -k.pii,,r4,e<,gg.g ir=e+=saag+-p9 h -w wyr p,g-g i e, w.9r, e. - e.c4em 9 .- .uy9-qw4gg. ppg--ryg.,y gg . Leg 699 g.m. 4.y-g-geag sgw gp ym..y.-ygy.g+.g.gs up , < y 9 3 g 9 y. ywgy-
~
TABLE 4-2 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRLMNTATION SURVEILLANCE REQUIREMMIS OfwiEL CHANNEL SOURCE CHANNELS FUNCTIONAL O!ECK __ CALIBRATIO3 TEST INSTRUMENT ** OiECK _
'l. GROSS BETA OR GA!9tA RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTCetATIC TERMINATION l OF RELEASE
- a. Liquid Radwaste Effluents Line -
2/3 RT-7813 D F R(2) Q(1)
- b. Steam Generator Blowdcwn (Neutralization S ep),
Full Flow Condensate Polisher Effluent Line - 2(3)RT-7817 D M R(2) O(1)
- c. Turbine Plant Sump Effluent Line -
D if R(2) Q(1) 2(3)RT-7821
- d. Steam Generator (E088) Blowdown Bypass Effluent Line - 2(3)RT-6759 0 M R(2) Q(1)
- e. Steam Generator (E089) Blowdown Bypass D M R(2) Q(1)
Line - 2(3)RT6753
- 2. FLCW RATE MEASUREMENT DEVICES
- a. Liquid Radwaste Effluent Line D(3) N.A R Q
- b. Steam Generator Blowdown (Neutralizaticn Sump),
0(3) N.A R Q Full Flow Condensate Polisher Effluent Line
- c. Steam Generator (E088) Blowdown Bypass D(3) N.A R Q Effluent Line
- d. Steam Generatcr (E089) Blowdown Bypass O(3) N.A R Q
. Effluent Line 4-4 Revision 22 08-02-90
+
JJBLE A 2 (Continuedi TABLE NOTAT10f]
" Honitor Re: orders are not required for the Operability of the monitor, providint the inoperable recorder does not cause the monitor to become inoperabie(i.e.,feedbacksignal). As long as the monitor has indication, alarm capability (if applicable), proper response (based Lpon surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable.
(1) The CHANNEL FUNCTIONAL TEST shall also denonstrate verification of effluent path isolation closure and Control Room alarm annunciation if any of the following conditions exist:*
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downsca'1 failure.
(2) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Sta.ndards or using standards that have been obtained from sup)11ers that participate
- in measurement assurance activities with NBS. liese standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration shall be used.
(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made. Y
*lf the instrument controls are not in the operate mode, procedures shall require that the channel be declared inoperable.
4-5 Revision 22 08 02 90
(.
\
4.0 E0VIPMIR 4.2 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
$_P1(JFICATION 4.2.) The radioactive gaseous effluent monitoring instrumentation channels shown in Table 4 3 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 2.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined 'n accordance with ODCH.
APPLICAEllm At all times ACTION:
- a. With a radioactive gaseous effluent monitoring instrumer,tation channel alarm / trip setpoint itss conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affectec channel or declare the channel inoperable,
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 4-3. Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally.
if the inoperable instrument (s) remain inoperable for greater than 30 days, explain in the next Semiannual Radioac',ive Effluent Release Report why the inoperability was net corrected in a timely manner.
- c. With iess than tSe minimum number of radioactive gas eous effluent monitoring instrumentation channels OPERABl! and either the appropriate ACTION ttems in Table 4-3 not taken or the necessary surveillances not performed at the specified frequency prescribed in Table 4-4, an INVESTIGATIVE REPORT shall be prepared which identifies the cause(s) for the event and defines th? cs rective actions to be taken to preclude recurrence of the#evint.
SURVEllLANCE RE0VIREMENT,f 7
.1 Each radioactive,ga aous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK.
SOURCE CHECK, CHANNEL CAllBRATION and CHANNEL FUNCTIOMAL TEST operations at the frequencies shown in Table 4 4. 4-6 Re0ision 23 02-28-91
-m . _mm___m_______-m-___._.__.__.______.-____.______._-_-___.____m_.___.m________._.__________.__.______ma
TABLE 4-3 , RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS APP 11CARItiTY ACTION OPERABLE INSTRUMENT ***
- 1. WASTE GAS HOLDUP SYSTEM
- a. . Noble Gas Activity Monitor -
Providing Alam and Automatic
- 35 Termination of Release - I 2/3 RT-7808, 2 RT-7865-1 or 3 RT-7865-1
- 36 4
- b. Process Flow Rate Monitoring Device 1
- 2. CONDENSER EVACUATION SYSTEM
** 37
- a. Noble Gas Activity Moallor - 2(3;CI-7818 ce 2(3)RT-7870-1 1
** 40
- b. Iodine Sampler I
** 40
- c. Particulate Sampler I
** 36
- d. Associated S --4 F?~n Measuring Device 1
** 36
- e. Process Flow Rate Monitoring Device 1(1)
- 3. PLANT VENT STACK
- 37
- a. Noble Gas Activity Monitor - 2/3 RT-7808, 2RT-7865-1 1 or 3RT-7865-1
- 40 Iodine Sampler I
- b. I
- 40
- c. Particulate Sampler
- 36
- d. Associated Sample flow Measuring Device I
- 36
- e. Process Flow Rate Monitoring De<1ce I(2)
- 4. CONTAINMENT FURGE SYSTEM
- a. Noble Gas Activity Monitor - Providing Alarm and Automatic
- 38 1
. Termination of Release - 2(3)RT-7828, or 2(3)RT-7865-1
- 40 1
- b. Iodine Sampler + 40 1
- c. Particulate Sampler
- 36 Process flow Rate Monitoring Device I
- d. I
- 36
- e. Associated Sample Flow Measuring Device 4-7 Revision 22 03-02-90
- - _ _ _ . . - - .- _ . - -.~.-, .. - - . - ~.-
3 o-VABLE 4-3 1rentinued) TABLEJ01AT10N j
- At all times.
** MODES 14 with any main steam isolation valve and/or any main steam ,
Isolating bypass valve not fully closed. ,
*** Monitor Recorders are not required for the Operability of the monitor, t
providing the inoperable recorder does not cause the monitor to become + inoperable (i.e., feedback si nal). As long as-the monitor has indication, alarm capability if applicable), proper response (based upon surveillance requirements) an isolation functior, (if ap)11 cable), the' i loss of the recorder does not render the monitor inopera)1e. ! (1) 2(3)RT 7818 is not equipped to monitor process flow. If another means of continuously monitoring process flow is not available, then comply with . ACTION 36.
.(2) 2/3 RT 7808 is not equipped to monitor process flow. If 2RT-7865 or .
3RT 7865 is not available to continuously monitor plant vent stack flow, a en comply with ACTION 36.- ACTION 35 - With the number of channels OPERABLE less than required by tho , Minimum Channels OPERABLE requirement, the contents of the tank (s)
- may be released to the anvironment provided that prior to initiating the release:
- a. A*, least two independent samples of the tank's contents are analyzed, and.
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; ,
Othetvise, suspend releases of radioactive effluents via this , p athway. -- ACTION 36 - With the number of channels OPERABLE less than required by the , Minimus Channels OPERABLE recuirement, effluent releases via this pathway may contitiue providet the flow rate is estimated at least once per 6 hours. System design characteristics may be used to - estimate flow. ACTION 37 - With-the number of channeir; OPERABLE less- than required by the Minimum Channels OPERABLE requirement, effluent releases via this , pathway may continue provided grab samples are taken at least once per 12 hours ano these samples are analyzed for gross activity within'24 hours. ACTION 38 With the numbe, of channels OPERABLE less than required by the Minimum Channt,1s OPERABLE requirement, innediately suspend PURGING of radioactiva effluents via this pathway. ACTION 39.- Remaining in Technical Specifications. 48 Revision 22-08 02 90
.--._.,2_.. u__ . . . ~ . _ ._._.u.._ . _ . . _ _ _ . _ . . _ _ . . _ . . , _ . . _ _ .
e TABLE 4-3 1Continuedj, TABLE NOTATION ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement effluent releases via the effected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 2-1. i L 1 4-9 Revision 22 08 02 90
I TABLE 4-4 . RADI0 ACTIVE GASEOUS EFFl.UENT NIN1JORIN9 INSTRUMENTATION SURVEILLANCE FEQ CHNiNEL MODE FOR W!!IDI FUNCT10NAL SURVEILLMitE CHANNEL SOURCE DIANNELS IS REQUIRED TEST _ CHECK GICK_ CAEISRATION INSTRUMENT ***
- 1. WASTE GAS HOLDUP SYSTEM
- a. Noble Gas Activity Monitor -
Providing Alarm and Automatic Termination of Release -
- 2/3 RT-7808, 2RT-7865-1, Q(1)
P P R(3) 3RT-7865-1 *
- b. Process Flow Rate Monitoring Q P N.A R Device
- 2. CONDENSER EVACUATIOii SYSTEM
- a. Noble Gas Activity Monitor - Q(2)
++
2(3)RT-7818,2(3)RT-7870-1 D M R(3) ** N.A N.A N.A ** Iodine Saicpler W N.A b .. W N.A N.A
- c. Particulate Sampler
++
- d. Assectated Sample Flow R Q D N.A Measuring Device
++
- e. Process Flow Rate Monitoring R Q D N.A Device (2(3)RT-7870-1)
Revision 22
- 4-10 08-02-90
TABLE 4-4 (Continued) . RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE FOR idHICH SOURCE CHANNEL FUNCTIONAL SURVEILLANCE.' CHANNEL CALIBRATION _ TEST IS REQUIRED-INSTRUMENT... CHECK- CHECK
- 3. . PLANT VENT STACK
- a. Noble Gas Activity Monitor - D M R(3) Q(2) 2/3 RT-7806. 2RT-7865-1, 3RT-7865-1
- b.- lodine Sampler W N.A N.A N.A Particulate Sampler N.A N.A N.A
- c. W
- d. Associated Sample Flow *
-Measuring Device D N.A R Q
- e. Process Flow Rate Monitoring
- Device D M.A R Q l
! 4. CONTMtMENT PURGE SYSTEM l . ! a. Noble Gas Activity Monitor -- i Providing Alarm and Automatic j Termination of Release -
- i 2(3}RT-7828,2(3)RT-27865-1 D P(4) R(3) Q(1)
- Iodine Sampler. W N.A N.A N.A i b. N.A *
- c. Particulate Sampler -W N.A N.A
- d. Process Flow Rate Monitoring
- Device D N.A- R Q l Associated Sample Flow :
- e.
- Measuring Device D N.A R Q
+ e 4-11 Revision 22 08-02-90
. - . _ , _ . . - ..m . . , , , , .- _. . ..- , , , ,. . _ _ , . , . . . - - , . . - _ . _ - , _ _ _
, _ . - , . _ . ~ . , _ . , _ . . . - _ . . _
c ( , I D.ELLi-4 feontinuedi TABLE NOTATION
- At all times.
** Modes 14 with any main steam isolation valve and/or any main steam isolating bypass valve not fully closed.
"* Nsitor Recorders are not required for the Operability of the monitor, pro M ing the inoperable recorder does not t.acse the monitor to become ineptsble (i.e., feedback signal). As 1cng as the monitor has indication, alarm tapability (if applicible), proper response (based upon surveillance requirements) and isolation function (tf apslicable), the loss of the recorder does not render the .onitor inoperasie.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation closure snd control room alarm annunciation if any of the following conditions exist:$
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downstale failure.
(2) The CHANNEL TUNCTIONAL TESi shall also demonstrate that control room alarn annunciation occurs if any of the following conditions exist:#
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
(3) The initial CHANNEL CALIBRATION shall be performed using one or mere of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from sup>11ers that participate in measurement assurance activities with NBS. T1ese standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration shall be usG. (4) Prior to each release and at let.st once per month.
~
ITf the instrument controls are not set in the operate mode, procedures shall call for declaring the channel inoperable. 4-12 Revision 22 08 02-90
e \ L 4,3 OPERABILITY OF RADIDACTIVE UA$TE EQUlPHENT-The flow d;agrams defining the treatment paths and the components of the radioactive liquid, gaseous and solid wuste mLnagement systems are shown in figures 4-5 thru 4 7. s s t 4-13 Rev'ision 21 02-15-90
----.-_._._.____.---_-__--------_-_a--- - . _ - - - - - _ - - - - - - . _ _ - - - - - - - - - - - - - __.
FIGURE 4-5 s')NGS 213 RADI0 ACTIVE LIQUID WASTE TREATHENT SYSTEMS l CCW Sump Hain Storage Tank Area Sump Condenser (Batch) ; (Patch) A i Aux Building l Turbine y 4 Sump + Plant Sump 3 lRT7821 - (Continuous) (Continuous) l --.
, y Neutralization
> BPS 4 Sump y- RT 7817 .+
(Batch / Cont) l I
~)
HCS LCS (Batch) ; (Batch} sh 6
.,1 FFCPD RT 6753 +
S/3 E089 1 *
.9/G E088 g RT 6759 CCW HX SAMPLED Saltwater 2 (Continuout) -.
Radwaste Primary Tanks Radwaste Secondary Tanks -- Prict,ry Hakeup Tanks ?/3 RT 7813
- Condensate Monitor Tanks l --
(Batch) . - - Radiation Monitor Intake NOTE: Monitor pathways are unit specific unless indicated to be common to Units 2 and 3. Outfall V l Pacific Ocean 4-14
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. 5.0 RA010L001 CAL ENVIRONMENTAL MONITORING 5.1 tenitorino P.ront::m iPJCIFICAT10N 5.1.1 The radiological anvironmental monitoring program shall be conducted as specified in Table 51. The requirements are applicable at all times.
aEELICABILITY: At all times AG1031
- a. Should the radiological environmental monitoring program not be conducted as specified in Table 5-1, in lieu of any other report required by Technical Specification (s) 6.9.1, prepare and submit to the Cearnission, in the Annual RaJiological Opereting Report (see Section 5.4), a-description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
- b. Should the level of radicactivity in an environmental sampling medium exceed the reporting levels of Table 5-2
-hen averaged over ar;f calendar quarter, in lieu of any Aher report required by Technical Specification (s) 6.9.1, prepare and submit to thn Consnission, tiithin 30 days froni the end cf the affected calendar quarter a Report pursuant to Technical Specification (s) 6.9.1.13. When more than one of the radionuclides in Table 5-1 are detected in the sampling medium, this report shall be submitted if:
GDy ntration fil + concentration (2) + , . 1 1.0 limit level (1) limit level (2)
- c. When radionuclides other than these in Table 5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limitsofSpecification(s) 1.2.1, 2.2.1 or 2.3.1, as appropriate. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition sha'll be reported and described in the Annual Radio 1cgical Environmental Operating Report (see Section 5.4).
- d. With fresh leafy vegetable samples or fleshy vegetable samples unavailable from one or more of the sample locations required by Table 5-1, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the comission within 30 days, pursuant to Technical Specifications 6.9.2, a Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples. 1 The locations from which samples were unavailable may then be deleted from those required by Table 5-1, provided the locations from which the replacement sampics were obtained are added to the environmental monitoring program as replacement locations.
5-1 Revision 22 08-02-90
, , .m
l .' 5.0- RADIOLOGICAL ENVIRONMEhTAL HONITORING -(Continued) i. l SURVEILLANCE RE00lREtiDill .
.1 The radiological environmental monitoring samples shall be collected pursuant to Table 51 from the locations given in Tables 5 4 and 5 5 and Figure 51 and shall be analyzed pursuarit >
to the requirements of Tables 5-1 and 5 3. f n l 5-2 Revision 22 08-02-90 1 I l
- _ _ - _____________-___ ___. __ _ l
, . ,,t ~_
TABLE 5-1
~
RADIOLOGICALENVIRONMENTAL MONITbRING FROGRAM - Number of Samples Sampling and l l Exposure Pathway a S11ection Freauencya Type and Frecut.ncy of Analyses I andler Sample and Samole locations Continuous operation Radiciodine cartridge. Analyze
- 1. Mt!20RNE Samples from at least of sampler at least once per 7 days for I-131.
Radio!odine 5 locations Pai ticulate sampler. Analyze for . l 3 samples frers offsite with samole collection gross beta radioactivity 1 24 hours ! and as required Ly dort Particulates locations (in different Perfom sectors) of the highest Icading. but at folicwing filtgr change. analysis on each calculated ann a1 average once per 7 days.jeast gama isotopic l sample when gross beta activity is ground level D/Q. > 10 times the yearly enan of control l samples. Perform gacca isotopic I sample from the vicinity analysis on composite (by location) of a comunity having the - sample at least once per 92 days. the h!ghest calculated annual average grcund-I 1evel D/Q. l l 1 sample from a control loca-l tion 15-30 km (10-20 miles) l distant and'in the leastt pre-j valent wind directien l At least ont.c per Gassna dose. At least once per 92 days.
- 2. DIRECT At least 30 locations includ- 92 days.
RADIAlION 8 ing an inner ring af stations l in the general 4res of the l site boundary and an outer ring approximately in the 4 i to S mile range from the site l with a station in each sector of each rir.g. The balance of the stations are in special interest areas such as popula-I tion centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations. l - l l Revision 21 5-3 02-15-90 < _ - _ _ --__ - m
- TABLE 5-1~[(Continued).
.. t RADIOLOGICAL ENVIR0ptENTAt. MONITORING PROGRAM ' Exposure Pathway Nteber of Samples .$aspling and
[q)1estion Frecuenty a- lyp! Land Freauency of Analyses and/or Sawle and" Sample locationsa-
- 3. WATERBORNE
- a. Ocean 4 locations. At least once per: Ganuma' isotopic : analysis of each -
i month and compositedf.l monthly! sample'. ' Tritium analysisJ ' quarterly of composite sample at least once a per 92 days.. .
- b. Drinking 2-locations Monthly at each
' Gamma isotopic and tritium location. analyses of each sample.
- i. .
i c. Sediment 4 locations O..least once per- Gamma isotopic analysis of each from 184 days. . sample. Shoreline
- d. Ocean 5 locations At least~ once per Gansna isotopic analysis of each Bottoa 184 days. sample. ,;
Sediments i E b 54 Revision 22 08-02 .
. . .- . . . , .. . c. ,. .
. ... ... ~ . . - - - .
7 . . . . . _ . _ . . , . ~ . - . _ . . . _ ~ ~ _ . _ . _. _ 7 _ , , . . . . . . - . . . . . _ . . .
> ,; 5 -
- TABLE 5-1 [(Conticued)
RADIOLOGICAL ENYIRGIGIENTAL NONITORING PROGRAM Exposure Pathway 1 Number of Samples :Sampilng and and Sample locationsa Collection Freovency a :Tvae and Freuuency of Analyses - - and/or Samole i
- 4. INGESTION Gamma' isotopic analysis on '
- a. Honmigratory. -3 locations One sample lin season, or at least once per . ~e dible portions..
Marine ~ . Animals . 184 days if not seasonal. One . sample
- of each of the follow- I ing species: '
- 1. Fish-2 adult species ~
.such.as perch or.
sheephead.
- 2. Crustacean-such as
- crab or lobster.
- 3. Mollusks-such as- .
limpets, seahares or ; t class. t 2 locations, Represer.tative Gamma isotopic enalysis on edible'. i
- b. Local Crops portions semiannually and 1-131 .;
- vegetables, normally 1 leafy and'1 fleshy analysis for leafy crops. ,
^
collected at harvest- ' time. At least 2
. vegetables collected semiannually from -
l each location. . t Revislod 21- ; 5-5 02-15-90 7
. , y -. 4 1 'a v - , . .
- a . . . _ _2<v.- --<<-m = __ a2--&-__-m-r-__
~ ...y.~. .- .. -, ~ . . - -. -.. - -
;a /-i y.
TABLE S-l' (tontinued)-
-- r 18BLE' NOTATION'
~
- a. Sample locations are. indicated on Figure 5-1.
- b. Gamma isotopic analysis means.the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. -
- c. The purpose ofL this sample is to 'obtain background informatien. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted. .
- d. Canisters 'for the collection of radiolodine in air are subject to channeling. These devices -should be carefully:
checked before operation in the field or several should be mounted in series to prevent loss of todine,
- c. Regulatory Guide 4.13 provides minimum acceptable performance criteria for thermoluminescence dosimetry (TLD) systems used for environmental monitoring. One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously say be used in place of, or in addition to, integrating dosimeters.
For the purpose of this table, a thermoluminescent dosimeter may be considered to be one phosphor' and two or more phosphors in a packet may b'e considered as two or more dosimeters. Film badges :should not be used for measuring - direct radiation.
- f. Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g., hourly) relative. to the compositing period (e.g., monthly).
i 5-6 Revision 22 02-90 F e er ^- e-- - thi - - * - -- -
_ TABLE 5-2 . REPORTING. LEVELS FOR RADIDACTIVITY CONCENTPJLTIONS IN ENVIRONMENTAL SARPLES Reporting Levels Airborne Particulate local Crops Water or Gases Marine Animals (ptt/m*) (pC1/Kg, wet), (pCl/Kg, wet) Analysis (pci/1) H-3 2 x 10*(a) 1 x 10' 3 x 10* Mn-54 4 x 10' 1 x 10* Fe-59 l 1 x 10' 3 x 10' Co-58 l 3 x 10' I x 10' Co-60 l 3 x 10 2 2 x 10' Zn-65 Zr-Nb-95 4 x 10* 0.9 1 x 10' I-131 2 10 1 x 10' 1 x 10' Cs-134 30 20 2 x 10' 2 x 20' Cs-137 50 Ba-i.a- 140 2 x 10' (a) For drinking water samples. This is 40 CFR Part 141 value. Revision 21 5-7 02-15-90
. . , ,. ~ - , . . . . . . . _ . _ ,. . _ . _ . . . . . - . . . . . . . . - _ . - - _ . . - . _ . . . . . . - _ _
JELE 5-3 y. MAXINUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLDJ.a.c.- , i Airborne Particuhte - Water or Gases Marine Animals .. Local Crops Sedimenti Analysis (pCi/1) -(pCi/m*)' (pC1/Kg. wet) .
..(pCi/Kg, wet) (pCi/kg, dry) .
gross beta 4 1 x 10 ' H-3 2000 Hn 15 '130 Fe-59 30 260 Co-58, 60 15 .130 Zn-65 30 260 1 Zr-95 30 l Nb-95' 15 , 1b 7 x 10~' 60 I-131 5 x 10 ' 130- 60 150 < Cs-134 15 6 x:10-* 150 80 180
-Cs-137 18 Ba-140 60' ,
La-140 15 5-8 Revision 21 - 02-15-90 4
* - , - , . - -- 5 + * +- a ~ , y
C ? TABLE 5 3 (Continutdl TABLE NOTATION , a.- 1The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "re'1" . signal.
- For- a particular- measurement- tystem (which may include radiochemical
. separation):
4.66 s LLD = b E V . 2.22 x 10' ._Y e exp (-Aat)
- where:
LLD is the "a priori" lower limit.of- detection as defined above (as microcurie per unit mass or volume), sb is the standard deviation of the background counting rate or of the counting rate of. a_ blank sample as appropriate _(as counts per , minute), E is the counting efficiency (as counts per transformation), V is the sample size (in units of mass or volume),
'2.22'x.10* is the number of transformations per minute per microritie.
Y is t' fractional radiochemical yield (when applicable), L A is the radioactive decay constant for the particular radionaclide, and: At is the elapsed time' between midpoint of sample collection or . .end of the collection period anditime of counting (for < environmental samples, not plant effluents ). - The value of sb used in the calculation 'of the-LLD for a detection system - Jshall be based on the actual-observed variance of the~ background counting C rate or of the counting rate of the blank samples (as appropriate) rather
- than on an unverified theoretically predicted variance. In calculating,the LLD for a radionuclide determined by gama-ray Spectrometry, the background shall include the-typical contributions of. other radionuclides normally present in the samples (e.g.. potassium-40 in milk samples). Typical values of E V,Y and at shall be used in the calculations.
E v 59 Revision 22 4 08 02-90 1
. , -- .,_ = . - - , - .
TABLE-5-3 (Continggd1 IABLE NOTATION It should be recognized that the LLD is defined as_ an A priori (before the fact) limit-representingthecapabilityofthemeasurementsystemandnotas a posterioti (after_ the fact) limit for a particular measurement.*
- b. LLD for drinking water.
- c. Other peaks which are measurable and identifiable, together with the radionuclides in Table 5 3, shall be identified and reported.
*For a more complete discussion of the LLD, and other detection limits, see the following:
(1) HASL Procedures Manual, HASL-300 (revised annually). (2) Currie, L.-A., " Limits for Qualitative Detection and Quentitative Determination - Application to Radiochemistry" &nal. Chem. 40, 585 93 (1968). (3) Hartwell, J. K., " Detection timits for Radioisotopic counting Techniques," Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972). N , N 5-10 Revision 21 02-15-90 ,
5.0 RADIOLOGICAL ENVIRONNENTAL MON!TORING (Continued) f 5.2 LAR USE CENSUS . SPECIFICATION 5.2.1 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden
- of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles, for elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the 1,and use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles.
APPLICABILITY: At all times MllQ!il
- a. With a land use census identifying a location (s) which yields a calculated dose or dose comitment greater than the values currently being calculated in Technical Specification 2.3.1, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the Comission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the newlocation(s).
- b. With s land use census identifying a location (s) which yields a calculated dose or dose comitment via the same exposure pathway 20 percent greater than at a location from which samples are currently being obtained in accordance with Section S.1, in lieu of any other report required by Technical Specification 6.0.1, prepare and submit to the Comission within 30 days, pursuant to Technical Specification 6.9.2, a Special Re aort which identifies the new location. The new location siall be added to the radiological environmental mcnitoring program within 30 days. The sampling location, excluding the control station location, having the lowest calculated daes or dose comitment via the same exposure pathway may be deleted from this monitoring program after October 31 of the year
'in which this land use census was conducted.
SURVEILLANCE REOUIREMENTS
.1 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.
- Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.
5-11 Revision 22 , 08-02-90 (
- 44. . . . . . . _ _ , a1 . - - -
. ._m. . . = . . , . . e e.m. . -_oa #t , . . .s. m + 2 - .. -- ,a~s . . . . # . , . .w . . .
3 4
- 5.0j RADIOLOGICAL ENVIRONMENTAL NONITORING (Continued).
l 5.3 11NTERLABORATORY COMPAR!$0N PROGRAM SPECIFICATION' , 5.3.1 Analyses-shall.be performed on radioactive materials supplied as partzof an Interlaboratory Comparison Program. 1 '
.which has been approved by the Commission.
- APPllCABitITti At all times- ,
a ACTION:
- a. With analyses not being performed as required'a'bove, l
report the corrective actions taken to prevent a recurrence-to= the Commission in the Annual Radiclogical .- . Environmental Operating-Report, SURVEILLANCE REOU1REMENTS
.1- A suunary of the results obtained as part of the above required Interlaboratory Comparison Program and in' accordance with Section 5.4.1 of this documentLshall be included in the Annual ,
Radiological Environmental Operating Report (see Section 5.4). x.
.' ~
i i. L L 4 p L ..
' 5-12 Revision 22 08-02-90
l 7.: -550 RADIOLOGICAL. ENVIRONMENTAL MONITORING.'(Continued) 5.4' LN.NUAL RADIOLOGICAL INVIRONMENTALJf18&llHG REPORT *- 5.4.lc ;The unnual radiological environmental operating reportst 4
- shall include- summaries, interpretations, and an.analysisE
- of trends of the results of the radiological environmental surveillance activities for the report period,Lincluding a
- comparison with preoperational studies, operational:
- controls (as appropriato) and previous; environmental surveillance-reports and an assessment of? the observed
-impacts of the. plant' operation on the environment.- The reports shall also-include the results of land use censuses required by Section 5.2. If-harmful effects or evidence of trrevenible camage are detected by the monitoring, the report shall provide aninx1ysis of the problem.and a planned course of action to alleviata the problem.- .
The annual radislogical environn.ntal operating' reports
-shall inckde summarized and tabulateo results in the-format of Rigulatory Guide 4.E. December 1975 of all radiological environmer.31 sampics taken during the report period. In tne avent that some results are not available for incleston with the report, the report shall be suknitted noting and explaining the_ reasons for the missing results. The nitsing data shall be submitted as soon as possible in a supnitmentary report.
The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances:and directions from the mid-point of reacter Units 2 and 3; and the results of-licensee-participattun'in the Interlaboratory Compartson Program, required by Section 5.3. I
- Aisingle_ submittal may be made for a multiple unit station, combining those sections that are connon to all units at the station.
5-13 Revision 21 02-15-90
}
u .
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.5 SAMPLE LOCATIONS The R' adiological Environmental Monitoring Sample Locations are identified in Figure 5-1. These sample locations are described in Tables 5 4 and 5 5 and indic. ate the distance in miles and the direction, determined from degrees true north, from the center of the Units 2 and 3 building complex. Table 5-6 gives the sector and direction designation for the Radiological Environmental Monitoring Sample Location on Map, Figure 5-1. 5-14 Revision 21 02-15-90
_ ___ . ._ .__ _ ~ _ _ _ _ _ _ _ .
- f Page'l of 6-TABLE S 4 g RADIOLOGICAL ENVIRORMENTAL MONITORING SAMPLE LOCATIONS ;
DISTANCE * '
-Iniles) DIRECTION
- TYPEOFSAMPLE}ANDSAMPLINGLOCATION***
Direct Radiation-City of San Clemente.(Former SOG&E Offices) 5.6 NW 1-Camo San Mateo (MCB, Camp Pendleton) 3.5 N
-- 2 Camp San Onofre (MCB, Camp Pendleton) 2.6 NE 3
Camp-Herno_(MCB,LampPendleton) 4.5 E
.: 4 Camp t.as Pulgas (MCB, Camp Pendleton) 8.5 E ,
5 3.0 ESE 6 11d Route 101:(East-Southeast)
-0.5 .ENE 7 Old Route-101L(East-Northeast).
1.5 -NW 8- Nancommissioned Officers' Beach Club ' 9: _Basilone Road /1-5 Freeway Offramp 2.0 NW 10 : Bluff--(AdjacenttoPIC#1) 0.7 WNW
'll Former Visitors' Center 0.3** NW-
.SouthLEdge of Switchyard .0.2** - E-4 11 2 13L Southeast Site boundary (Bluff) 0.4** lSE L14 , Huntington Beach Generating Station 37.0- NW.
15 So;theast Site Boundary (Office Building) 0.2** SE [ 116 ' East' Southeast Site Boundary 0.4** ESE 17- Tiinsit: Dose-18' Tri, sit Dose 119 - San Clemente Hit 11 ands -5.0 NNW-20~ h t."Clemente' Pier; :5.3 NW Concordia Elementary . School - San Clemente- -3;5- NW 4 21 22 Former U.S. Coast Guard Station - San Mateo Pcint: 2.7 WNW 23 5an Clementi General Hospital. 8' 2. - NW L
- P.4 San Clemente High School 6.0 NW. .
7* p
- Distance (miles) and Directio.. (sector) are measured relt.tive to Units 2 ar,d
--3 midpoint. _ Direction-is' determined from degrees true north.
** - Distances-are within the Units 2- and 3 Site Boundary -(0.4 mile in' all sectors) and not required by Technical Specification. -
L L
*** MCB Marine Corps Base' PIC Pressurized Ion Chamber p .
5-15 Revision 23
'02-28 91 p -
. - .~w-.- - . , , ,
Page 2 of 6 IABLE 5 4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- TYPE OF SAMPLE AND SAMPLING !OCATION m (miles) DIRECTION
- DirnetRadiation(Continued) 25 Convalescent Home - San Clemente 8.0 NW 26 Dana Hills High School 11.0 NW 27 U.S. Post Office - Dana Point 10.6 NW 28 Doheny Fire Station - Capistrano Beach 9.5 NW 29 San Juar, Capistrano Fire Station 10.8 NW 30 Laguna Beach Fire Station 17.5 NW 31 Aurora 'Sark-Mission Viejo 18.7 NNW 32 Santa Ana Police Department 32.0 NW 33 Camp Talega (MCB, Camp Pendleton) 5.7 N 34 Stn Onofre School (MCB, Camp Pendleton) 1.9 NW 35 Range 312 (MCB, Camp Pendleton) 4.7 JNE 36 Range 208C(MCB,CampPendleton) 4.2 NE 37 Laguna Niguel Fire Station 14.2 NW 38 San Onofre State Beach Park 3.3 SE 39 Basilone Road Trailer Park (MCB, Camp Pendleton) 1.4 NNW 40 SCE Training Center - Mesa (Adjacent to PIC #3) 0.7 NNW 41 Old Route 101 --East 0.4 E 42 Horno Canyon (MCB, Camp Pendleton) 4.7 E 43 Edison Range (MCB, Camp Pendleton) 10.6 SE 44 Fallbrook Fire Station 18.0 E 45 Interstate 5 Weigh Station 2.0 ESE 46 San Onofre State Beach Park 1.0 SE 47 Camp Las Flores (MCB, Camp Pendleton) 8.6 SE 48- Mainside (MCB, Camp Pendleton) 15.0 ESE Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
** Distances are w thin the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.
*** MCB Marine Corps Base PIC - Pressurized Ion Chamber i
5-16 Revision 21 02-15-90
. . A '
Page 3 of.6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- TYPE OF SAMPLE AND SAMPLING LOCATION *** fmiles) DIRECTION
- Direct Radiation (Continued) '
49 Camp Chappo (MCB, Camp Pendleton) 12.8 ESE 50 Oceanside Fire Station 15.5 SE Carlsbad Fire Station 18.6 SE 51 52 Vista Fire Station 21.0 ESE-San Diego County Operations Center 45.0 SE 53 54 Escondido Fire Station 32.0 ESE 55 San Onofre State Beach (Unit 1 West Southwest) 0.2** WSW 56- San-OnofreStateBeach(Unit 1, Southwest) 0.1** SW 0.l** SSW. 57' San Onofre State Beach (Unit 2) 0.l** S 58- San Onofre State Beach (Unit 3) 59 - SONGS Meteorological Tower 0.3** WNW 60 Transit control Storage Area - 61- Mesa-EastBoundary(AdjacenttoPICf4) 0.7 N 62 MCB--CampPendleton(AdjacenttoPICf5). 0.6 NNE 63- MCB - Camp Pendleton (Adjacent to PIC f6) 0.6 NE 64 MCB - Camp Pendleton (Adjacent to PIC #7) 0.5 ENE 65 MCB - Camp Pendleton (Adjacent to PIC #8). 0.7- E 66; San Onofre State Beach (Adjacent to PIC #9) 0.6 ESE- - 67 Former SONGS Evaporation Pond (Adjacent to Plc F2) 0.6 NW ' '68 - Range 210C(MCB,CampPendleton) 4.3 ENE 99 Transit Dose - - 1 Distance-(miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is detemined from degrees true north. Distances are within the Units 2 and 3 Site Boundary (0.4 mile _in all sectors) and not required by Technical Stacification.
*** MCB - Marine Corps Base PIC - Pressurized Ion Chamber 5-17 Revision 21 02-15-90 I
- Page 4 of 6 IMLE 5-4 RADIOLOGICAL ENYlRONMENTAL HONITORING SAMPLE LOCATIONS DIS 1ANCE*
TYPE OF SAMPLE AND SAMPLING LOCATION , (miles) DIREC110N* Airborne 1 City of San Clemente (City Hall) 5.5 NW 2 Camp San Onofre (Camp Pendleton) 1.8 NE 3 Huntington Beach Generating Station 37.0 NW 5 Units 2 and 3 Switchyard 0.13** NNE 6 SONGS Meteorological Tower 0.3** WNW 9 State Beach Park 0.6 ESE 10 Bluff 0.7 WNW 11 Mesa EOF 0.7 HNW 0.6 Fumer SONGS Evaporation Pond hW 12 13 Marine Corps Base (Camp Pendleton East) 0.7 E f Soil Samples 1 Camp San Onofre 2.5 NE 2 Old Route 101 - East Southeast 3.0 ESE 3 Basilone Road /I-5 Freeway Offramp 2.0 NW 4 Huntington Beach Generating Station 37.0 NW 5 Former Visitor's Center 0.2** NNW Ocean Water A Station Discharge Outfall - Unit 1 0.5 SSW E Outfall - Unit 2 0.7 SW C Outfall - Unit 3 0.7 SW D Newport Beach 30.0 NW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
** Distances are within the Units 2 and 3 Site boundary (0.4 mile in all sectors) and not required by Technical Specification.
5-18 Revision 21 02-15-90 t 1
l r_ l
- Page 5 of 6 TAD'.E 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION
- Drinking Water 1 Tri Cities Municipal Water District Reservoir 8.7 NW 2 San Clemente Golf Course Well 3.5 NNW 37.0 tid -
3 Huntington Beach ShorelineSediment(BeachSand) 1 San Onofre State Beach (0.6 mile Southeast) 0.6 SE 2 San Onofre Surfing Beach 0.9 NW 3 San Onofre State Beach (3.1 miles Southeast) 3.1 SE 4 Newport Beach (North End) 30.0 NW local Crops 1 San Mateo Canyon (San Clemente Ranch) 2.6 NW 2 Southeast cf Oceanside 22.0 SE Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north. 5-19 Revision 23 02-28-91
~Page 6 of 6 rah 0LO61 CAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE *
-TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION *
.Non-Migratory Marine Animals A Unit 1 Outfall 0.9- WSW B Units 2 and 3 Outfall 1.7 SSW C Newport Beach 18.2 NW 7
Kelp A -San Onofre Kelp Bed- 1.5 S B . San Mateo Xelp Bed 3.8 WNW , C- Barn Kelp Bed 6.3 SSE D Newport Beach 15.6 NW Ocean Botton Sediments A . Unit 1 Outfall (0.5 mile West) 0.6 W~ LB Unit-1 Outfall (0.6 mile _ West) 0.8- SSW-C Unit 2 Outfall. 1. 6 -- SW D Unit 3 Outfall -1.2 SSW E Newport Beach 18.2 NW
- Distance (miles)!and Direction (sector) are measured relative to Units 2 and-
-3 midpoint. Direction-is determined from degrees true north.
5-20 Revision 23 02-28 91
.- ~ .- . . . . - . . . .. ~ ,
;s
PIC - RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS Theta DISTANCE
- PRESSURIZED 10N CHAMBERS (
Dearees)* Meters ,
miles DIRECTION / SECTOR
- St -San Onofre Beach 298' 1070 0.7 WNW P S2. SONGS Former Evap. Pnd 313' 890 0.6 NW Q S3. Japanese Mesa 340' 1150- 0.7 NNW: R S4 MCB - Camp' Pendleton 3' 1120 0.7 N A SS MCB - Camp Pendleton 19' 10$0 0.6- NNE B-46' 940 0.6 NE C' 56 MCB - Camp Pendleton 57 MCB - Camp Pendleton 70' 870 0.5 ENE D 0.7 1120 E E-S8 MCB - Camp Pendleton - 9B*
59 San Onofre State Beach 121' 940 0.6 ESE F o , l 1 J i Distance.(meters / miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Theta direction is determined from degrees true north. l ! I ... y 5-21 Revision 21 02-15 .
l
*
- TABLE 5-6 SECTOR AND DIRECTION DESIGMATION FOR RADIOLOGICAL ENVIRONMENTAL MONITORlHG SAMPLE LOCATION M/P DEGREES TRUE NORTH NOMENCLATURE FROM SONGS 2 AND 3 M10 P0lHT Sector Center Sector 22.5' Line Sector *. Direction 1,imit limit.
A N 348.75 0 & 360 11.25 B NNE 11.25 22.5 33.75 C NE 33.75 45.0 56.25 78.75 0 ENE 56.25 67.5 E E 78.75 90.0 101.25 F ESE 101.25 112.0 123.75 G SE 123.75 135.0 146.25 H SSE 146.25 157.0 168.75 180.0 19'. '.5 J S 168.75 SSW 191.25 2L2.6 S3.75 K 236,25 L SW 213.75 225.0 258.75 M WSW 235.25 247.5 281.15 N W 258.75 270.0 303.75 P WNW 281.25 292.5 315.0 326.25 Q NW 303.75 326,25 337.5 348.75 R NNW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true North. 3081c-22. man , 5-22 Revision 21 , 02-15 90
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6.0 60H11011B Q 1 l 6.1 Diffl)1101t1 1he defined terms of this section appear in capitalized type and are applicable through these Specificattoos. MllD3 6.1.1 ACTION shall be that part of a specification which prescribes remedial measures reoutred under designated conditions. CHANNEL CAllllBal10B 6.1.2 A CHANNEL CAllBRATION shall be tFe adjustment, es necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. Thr CHANNEL CAllBRATION shall encompass the er. tire channel, including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CAllBRATION tcay be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. ChehMELIHEG 6.3.3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This dctermination shall include, where possible, comparison of the channel Indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. CHANNEL FUNCTIONAL TEST 6.1.4 A CHANNEL FUNCTIONAL TEST shall be:
- a. Analog char.nels - the injection of a simulated signal into channel as close to the sensor as practicable to verify OPERABILITY, including alarm and/or trip functions.
- b. Bistable channels - the injection of a simulated signal into the sensor to verify OPERABILITY, including alarm and/or trip functions.
- c. Olgital computer channels the exercising of the digital computer hardware using diagnostic programs and the injection of simulated process data into the channel to verify OPERABillTY.
61 Revision 21 02-15 90 l
~
6.0 @MINISVRdUl[ (Continued) DOSE EQUIVALENT 1.lu 5.1.5 DOSE EQUlVALENT l 131 shall be that corcentration of 1131 (microcuries/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1 131, 1 132, 1-133, 1 134, and 1-135 actually present. The throid dose conversion factors used for this calculation shall be those ilsted in Table 111 of 11D.14844
'Calcelation of Distanen Factors for Power and Test Reactor Sites."
[EIWil(CY NOTAT1Q3 6.1.6 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 6.2. GASEOUS RADWAITE TREATMENT SYJIf3 6.1.7 A GASE00$ RADWASTE TREATHENT SYSTEM is any system designed and installed to reduce raoioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. INVESTIGATIVE R QB1 6.1.8 The group responsible for the missed ACTION or surveillance shall perform an evaluation which covers the root cause(s), corrective action, and recommendations to preclude recurrence of the event. Copies of the resulting report shall be provided to Effluent Engineering and the Unit Superintendent with the original sent to COM-SONGS for retention. MEMBERS OF THE PUBLIC 6.1.9 HEMBER(S) 0F THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant. This category shall include nonemployees of the licensee who are pennitted to use portions of the site for recreational, occupational, or purposes not associated with plant functions. This . category shall not include non employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter an area thtt is controlled by the licenses for purposes ol' protection of individuals from exposure to radiation and radioactive materials. I 6-2 Revision 23 02-28 91
.---,c . - - - -- --
6.0 ADMINISTRATIVE (Continued) QE[RaE E OPERABillTY 6.1.10 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are recuired for the system, subsystem, train, component or cevice to perform its function (s) are also capable of performing their rotated support function (s). EMRGE PURGING 6.1.11 PURGE or FURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the ccnfinement. EllL69UNDARY 6.1.12 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee. EQLIDIELCATION 6.1.13 S0t101FICAT10N shall be the conversion of radioactive wastes from 11guld systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free standiig). EQURCE CHECK 6.1.14 A SOURCE CHECK shall be the qualitative assestnant of channel responst when the channel sensor is exposed to a radioactive source. IBERMAL POWER 6.1.15 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. VENTING 6.1.16 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that reolacement air or gas is not provided or required during VEliT3NG. Vent, used, in system names, does not imply a VENTING process. 6-3 Revision 23 02 28 91 4
IMLLh1 l emnonten REACTIVITY % OF RATED AVERAfC COOLANT t OPERATION MQE (QHDITION. K,7f IHL(y',,,ffy,[fL* ,,,,,,T I MP m.AJM( .
- 1. POWER OPEPATION 2 0.99 > 5% 2 350'r
- 2. STARTUP 1 0.99 s 5% 1 350'T
.$. HOT STANDBY < 0.99 0 2 350'F
< 0.99 0 350'F> T,yg>200'F
- 4. B0T SHUTOOWN
- 5. COLD SHUTDOWN < 0.99 0 s 200'r
- 6. REFUEllNGa* 1 0.95 0 s'140'T l'icluding decay heat.
** Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
64 Revision 21 02-15-90
13Mll i:2. U1011LNCYNOTA712!i l
@lAUPli G101!D101
$ At 1 erst once per 12 f.ours D At least once per 24 houts W At least once per 7 days M At least once per 31 days Q
At letst once per 92 days SA At least once por 184 days R At least once per 18 months
- S/U Prior to each reactor startup P Completed prior to each release N.A. Not applicable Refueling Not to exceto 24 months Interval
*A month is defined as a 31. day period.
e 65 Revision 22 08 02 90
l 6.2 ADMlHISTRATIVE CONTROM i i l SEMIANNVAL RADIOACTIVE EffLVEtll.LHIA5E REPQRL* 6.2.1 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January I and July 1 of each year. The period of the first report shall begin with the date of initial criticality. 6.2.2 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Heasuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light Water Cooled Nuclear Power Plar,ts, " Revision 1. June 1974, with data summarized on a quarterly basis following thn format of Aopendix B therecf. The radioactive effluent release report to be sutnitted 60 days after January 1 each year shall include an annual summary of hourly meteoroldgical data collected over the previous year. This annJal SUM 4ry may bei either in the form of a'n hour by hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distribucions of wind speed, wind direction, and atmospheric stability. This sans report shall include an assessment of the radiation doses due to the rAdioective liquid and gasacus effluents teleases from the unit or station during the previous calendar year. This same report shall also include an asussment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their actfvities inside the SITE BOUNDARY (Figure 1-2 and 2 2) during the report period. All assur:ptions used in making those assessments (i.e., specific activity, exposure time and lecation) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by samplir.g frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be perfomed in accordance with the OFFSITE DOSE CALCULSfl0N MANUAL (00CH). 6-6 Revision 22 08 02 90
6.0 ADMINISI.%Ilyi (Continued) 6.2 6DMIPISTRATIVE CO,81RQL1 (Continued) 6.2.2 (Continued) The radioactive effluent release report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed HEMBER OF THE PliBLIC from reactor releases and other nearby uranium fuel cycle sources (including doses frein primary afflunot patnways end direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, invironmental Radiation AcceptableProtection methods for Standards calculating the for Nuclear Power Operation. dose contribution from liquid and gaseous effluents are i given in Regulatory Guide 1.109, Rev.1. ! The radioactive effluents release shall include the following information for each type of solid waste shipped offsite during the report period:
- a. Container volume,
- b. Total curie quantity (specify whether determined i by measurement or estimate),
- c. Principal radionuclides (specify whether
- detemined by measurement or estimate),
- d. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),
- e. Type of container (e.g., LSA, Type A. Type 3 LargeQuantity),and f.
Solidification Agent (e.g., cement, urea formaldehyde). The radioactive effluent release reports shall include unplanned rnleases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis. , The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period. The submittal
- A single submittaT may be made for a multiple unit station.
should combine those sections that are comon to all units at the Station; however, for units with separate radwaste sy;tems, the submittal shall specify the releases of radioactive material from each unit. . 67 Revision 22 08-02-90
- 6. 0' @MINISTRATIY1 _(Continued) 1 6.3 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATHENT SYSVEMS (Liquid, &
- Gaseous)
Licensee initiated major changes to the radioactive waste systems (liquid & gaseous):
- 1. Shal! be reported to the Comission in the Monthly Operating l Report for the period in which the evaluation was performed !
pursuant to Technical Specification 6.5.2. The discussion of each - change shall contain:
- a. A sumary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.591 ;
- b. Sufficient detailed inforntion to totally support the reason for the change without benefit of tdditional or .
supplemental information;
- c. - A detailed description of the equipment, components and ,
processes involved and the interfaces with other plant systemst .
- d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous
- effluents that differ from those previously predicted in i the-license application and amendments thereto;
- e. An evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area
- and to the general population that differ from those previously estimated in the license application and amendments thereto;
- f. A comparison of the predicted releases of radioactive materials. in liquid and gaseous effluents to the actual release for the period prior to when the changes are to be -
madet An estimate of the exposure to plant operating personnel as I 9 , a result of the change; and
- h. Documentation of the fact that the change was reviewed and found acceptable pursuant to Technical Specification 6.5.2.
- 2. Shall become effective upon review and acceptance purtuant to Technical Specification 6.5.2.
6-8 Revision 22 08 02 90 D v'Eir.. .-.r.. < # .-e ....-,v._,.. -,-r.w vr _ < - . , m.r, . . . - . .,,,.-e, y,..w.- v-ey , , . - - , y - - . , .,y., ,,m. - ,- , .. ,vy,-.y
6.0 ADMIN 151 RAT 1Yi (Continued) 6.4 Mill HOU10 EFFLUENTS r.0NCEN1 RAT 10N (1.1) 6.4.1 This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site will be less than the concentration levels specified in 10 CFR Part 20 Appendix B Table 11, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section ll.A design objectives of Appendix 1.10 CFR 50, to an individual, and (2) the limits of 10 CFR 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe 135 is the controlling radioisotope and its HPC in air (submersion) was converted to an ecuivalent concentration in water using the nothods describec in International Commission on Radiological Protection (ICRP) Publication 2. , QMI (1.2) 6.4.2 This specification is provided to implement the require-ments of Section ll.A, III.A and IV.A of Appendix I,10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix 1. The ACTION statements provide the required operating flext-bility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept
'as low as is reasonably achievable.' The dose calcu-lations in the ODCM implement the requirements in Section
!!!.A of Ap)endix ! that conformance with the guides of Appendix 1 >e shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCH for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1,"
l Revision 1, October 1977 and Regulatory Guide 1.113,
' Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for_ the Purpose of Implementing Appendix I," April 1977.
L This specification applies to the relaase of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units l sharing that system. 69 Revision 21 02 15-90
L6.01 AD % %5.1A glg -(Continued)' 14 FfML$ (Coatinued). Uh010 WMTEil@llifJil (1.3) j 6.4.3 The OPERABil.lTY of the liquid isdwaste treatment system ; enuire that this systsm will be available for use whenever ! IWuid4ftluents require treatment prior to release to the ! environment. The requirement that the appropriate portions ! of this. system be uted whan specified provides assurance f tnat the releases of radioactive materials in liquid
~
effluents will be kept "as low as is reasonkbly ; achievable." This saecification implements the . t requirements of 10 C:R Part 50.26a, General Design Crittrion 60 of Appendix. A.to 10 CFR Part 50 and the design objectivt given in Section 11.0 of Appendix ! to 10 CFR Part % The specified limits governing the use of appropriate portions of the liquid radwaste treatment , system were. specified as a suitable fraction of the dose desig'n objectives set forth in Section II.A of Appeadix 1, 10 CFR Part 50 for liquid effluents.- , DA5fa$ trnt)tnis ] v DQS.U@H (2.1)' . 6.4.4 This specification is provided to ensure that the desn at i any time at the site boundary from gaseous affluents from all units on tha site will be within the annual dose limits , i of 10 CFR Part 20 for unrestricted areas.. The annual dose limits are the doses assuciated with the concentrations of 10 CFR Part 20, Appendix 5,- Table II, Column 1. These limits provide reasonable assurance that radioactive , material discharged in gaseous effluents will not result in ; the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual .
. average concentrations' exceeding the limits specified in Appendix B,-Table II of 10 CFR Part 20.(10 CFR Part . ;
20.106(b)). For. individuals who may at times be within the the occupancy of the-. individual will be- .l siteboundaryIowtocompensatefor:anyincreaseinthe sufficiently atmospheric diffusion factor above that for the site' boundary. The specified release rate limits restrict, at all times.. the corresponding gamma and beta dose ratos above background:to an individual at or beyond.the site- ! boundary to less than or equal to 500 mreWyear to the !
-total body or to less than or equal to 3000 mrom/ year to' the skin.- These release rate limits also restrict, at all. l times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal -,
to1500mram/ year. ; This specification applies-to the release of gaseous i effluents from all reactors at the site.- For units with shared radwaste treatment systems, the gaseous effluents from the shared system are proportioned among the units . L sharing that system. , I g 6 10 Revision 21 L: 02 15490 l I
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6.0 ADjilR157RATIVE (Continued) 6.4 ft1ES (Contiruti) QQiL_RRE GASES (2,2) 6.4.5 This specification is provided to irt.plement the requirements of Sections II,b, Ill.A and IV.A of Appendix 1. ,3 CFR Part 50. The Limiting Cendition for Operation impkments the guides set forth in Section !!.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix ! to assure that the releases of radioactivo material in gaseous effluents will be kept 'as low as is reasonably achievable." The Surveillancr' Requirements implement the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix 1 be shown by calculational procedures besed on models and data such that the actual exposure of an individual through appropri.te patt. ways is unlikely to be substantially underestin.ated. The dose calculations established in the ODCH for l calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109,
' Calculation of Annual Doses to Man from Routine Relea:es of Reactor Effluents for the Purpose of Evaluating - Compliance with 10 CFR Part 50, Appendix 1,* Revision 1, Octrber 1977 and Regulatory Guide 1.111, 'Hethods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors," Revision 1 July 1977. For d3dividuals who may it times be within the site boundary, r A occupancy of the individual will he sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. For PEMBERS Of TliE FUBLIC who traverse the SITE BOUNDARY via highay I 5, the residency time shall be corsidered negligible and hent.s the dose '0'. The ODCH equations prcvided for determining the air doses at the SITE HOUNDARY are based upo1 the historical average atmospheric conditions.
DQ3E - RADlulDQlES, RA010ACHEI MIIRIALS INJARTICM1, ATE FORM AyQ . IRilMi(2.3) 6.4.6 This specification is provided to implement the requirements of Sections !!.C. III.A and IV.A of Appendix 1, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section !!.C of ( Appendiy 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive maternis in gaseous effluents will be kept 'as low as is reasonably L achievable." The ODCM calcule.ttonal methods specified in the Surveillance Require'.rients in.plennt the requirements in Section Ill.A of Appendix ! that conformance with the ) guides of Appendix 1 be shown by calculational procedures I 6 11 Revision 22 l 08-02 90 I l
V "
6.0 AMilH1,$Jf61Y1 (Continued) 6.4 133fji (Continued) based on models and data, such that the actual exposure of no individual through appropriate pathways is unlikely to be substantially underestimated. The ODCH calculational methods for calculating the doses due to the actual release ratis of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Conpliance with 10 CFR Part 50, Appendix 1,* Revision 1, October 19i7 and Regulatory Guide 1.111 ' Methods for Estimating Atmospheric Transport and Dispersion of Geseous Effluents in Routine Releeses from 1.ight Water Cooled Reactors," Revision 1. July 1977. These equations also pro,.de for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radiciodines, radioactive materials in particulate form and tritium are 4cpendent on the existing radionuclide pathways to stan, in the unreWicted area. 1he pathways which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man,
- 3) deposition onto grassy areas where milk animals and meat
- producing animals graze with consum> tion of the milk and meat by man, and 4) deposition on tie ground with subsequent exposure of man.
GASEOUS RADWASTE TREATMENT (2.4) 6.4.7 The OPERABILITY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriato portions of these systems be rted, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept 'as low as is reasonably achievable.' This specification implements the requirements of 10 CFR Ptirt 50.36a, Ger,erci Design Criterien 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.0 of Appendix ! to 10 C?R Part 50 The specified limits governing the use of approwinte porticns of the systems were specified as a suita>1e fraction of the dose design objectives set forth in 3ections II.B and II.C of Appendix 1,10 CFR Part 50, for gaseous effluents. l l l 6 12 Revision 21 , 02-15 90 l l-
l i 6.0 EDMINISTRaTIVE (Continued) 6.4 jLQLi (Continued) i TOTAL DQif. (2.5) 6.4.8 This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and submittal of a Special Report whenever the calculated dosos from plant radioactive eifluents exceed twice the design objectivo doses of Appendix 1. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for 12 consecu';ive months to wlWn the 40 CFR 190 limits. For the purposes of the Specia'. Re sort, it mty be assumed that the doso comitment to the mem>er nf the public from other uranium fuel cycle sources fs negligible, with the exception that doso contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the Special Re) ort with a request for a variance in accordance wit) the provisions of 40 CFR 190.11, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected. Aa individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation which is part of the nuclear fuel cycle. MDIDACTIVE LIOUID EFQUENT INSTRUMENTATION (4.1) 6.4.9 The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm / trip setpoints for those instruments shall be calculated in accordance with the precedures in tho 00CH to ensure that the alarm / trip will occur artor to exceeding the limits of 10 CFR Part 20. The OPERAllt.!TV and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. i i . 6 13 Revision 21 02-15-90 t i
- )
- P 6.0 @jilH11LM1 (Continued) 6] ffjli (Continued)
M010 ACTIVE GASEOUS NFLUENT INST @HENTATIQH (4.2) 6.4.10 The i"idioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments . thall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CfR Part 20. Thir. Instrumentttion also includes provisions for monitoring and contro11th0 the concentrations of potentially explosive gas mixtures in the waste gas holdup system. Tho OPEitABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. HONITOR1Rq I1 M (5.1) 6.4.11 The radiological monitoring program required by this , specification provides measurements of radiation end of radioactive materials in those exposure pathways and for those radionuclides, which Icad to thi highest potential
- radiatien exposures of individuals re.;ulting from the station operation. This monitoring program thereby supplements the radiologict) effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levcis of radiation are not higher than erpected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be effective for at least the first three years of convaercial operation.
Following tl.is period, progrem changes may bo initiated based on operational experience. The detection capabilitias required by Table E 1 are state-of-the art for routine environnental measurements in industrial laboratories. It should oe recognized that the LLD is defined as an A Dr.icr.1 (before.tho het) limit representing the capability of a measurement system ind not as A Rosteriori (after the fact) linit for a particular measurement. /snalyst.s shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample. sizes, the presence of interfering nuclide'. or other uncontrollable circumstances may render these LUs unachievable. in such cases, tne contributing factors will be identified and described in the Annual Radiological Environmental Operating Reprt.
. l 6-14 Revision 22 08 02 90 I
l
' * - , I 6.0 ADMINISTR4LLVI (continued)-
6.4 j!MfJi (Continued) LANDUSECENSUS(5.2)
-6.4.12 This specification is provided to ensure that changes in the use of UNRESTRIC1ED AREAS are identified and that modifications to the monitoring program are ma:ie if required by the results of this census. The best survey infomation from the door to-door, aerial or consulting with local agricultural authorities shall be used. This census satisfios the requirements of Section IV.B.3 of Appendix ! to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposuri pathways via leafy vegetablos-wili be identified and munitored since a garden of this size is the minimum required to produce the quantity (26 P
kg/ year) of leafy vegetables assumed in Regulatory Gu4de 1.109 for consumption by a child. To determine this ' minimum garden size, the following assumptions were used,
- 1) that 20Y. of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield cf 2 kg/ square meter, i INTERLABORATORYCOMPARSONPROGRAM(5.3) %
- 6.4.13 The requirement for participation in an Interlaboratory. f Comparison Piogram is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are !
perfomed as part of the quality assurance program for r environmental sonitoring in order to demonstrate that the . results are reasonably valid, f k i L L 6-15 Revision 22 08 02-90 d
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