ML20084T867
| ML20084T867 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/28/1991 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13309A943 | List: |
| References | |
| PROC-910228-01, NUDOCS 9103250324 | |
| Download: ML20084T867 (187) | |
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' ATTACHMENT A ODCM, Revision 23 i"
9103250324 910318 PDR ADOCK 05000361 R PDR
OFFSITE DOSE CALCULATION MANUAL NUCLEAR GENERATION SITE UNITS 2 AND 3 ODCM2- Revision 23 3081c-22. man 02-28-91
ODCM TABLE OF CONTENTS PJLat LIST OF FIGURES .............................................. ........ IV LIST OF TABLES ........................................ .......
... V-Vi
. . - V11 INTRODUCTION .............................. .............. .
.......... . I'l 1.0 LIQUID EFFLUENTS.....................................
.......... 1-1 l'.1 Concentration....................................
1-1 1.1.1 Specification....................................... 1-1 1.1.1.1, 1.1.1.2 Su rve i 11 an c e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.2 Dose........................................................ 1-5 1.2.1 Specificaticn....................................... 1-5 1.2.1.1 Survei11ance........................................ 1-5 1.3 Liquid Waste Treatment...................................... 1-6 1.3.1 Specification....................................... 1-6 1.3.1.1, 1.3.1.2, 1.3.1.3 Survei11 ances . . . . . . . . . . . . . . . . . . . . . 1 -6 1.4 Liquid Ef fluent Monitor Setpoints. . . . . . . . . . . . . . . . . . . . . . . . . . . 1-8
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1.4.1- Batch Release Setpoint Determination. . . . . . . . . . . . . . . . 1-10 1.4.2 Continuous Release Setpoint Determination. . . . . . . . . . . 1-16 1.5 rose Calcul ations for Liquid Effluents. . . . . . . . . . . . . . . . . . . . . . 1-27 1.6 Representative Sampling..................................... 1-30 2.0 GASEOUS EFFLUENTS................................................ 2-1 2.1 Dose Rate................................................... 2-1 2.1.1 Specification......................................... 2-1 2.1.1.1, 2.1.1.2 Survei11 ances . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1 2.2 Do s e - N o bl e G a s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-5 2.2.1 Specification........................................ 2-5
- 2. 2.1.1 Su rve i l l ance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-5 2.3 Dose - Radioiodines, Radioactive Materia 1L in Particulate F o nn a n d T r i t i um . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-6 2.3.1 Specification........................................ 2-6
- 2. 3.1.1 S urve il l ance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-6 Revision 22 1 08-02-90
1 OEM TABLE OF CONTENTS (Continued) Ent ' 2-7 2.4 Gaseous Radwaste Treatment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.1 Specification......................................... 27 2-7 2 . 4 .1.1 S u rve 111 an c e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.4.~1.2, 2.4.1.3 Survei11 ance s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-8 29 2.5 T o t al D o s e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.S.1 Specification......................................... 29 2-9
- 2. 5.1.1 S u rve i l l anc e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2.6 Gaseous Ef fl uent Monitor Setpoints . . . . . . . . . . . . . . . . . . . . . . . . . 2-11 l l 2 - 11 2.6.1 Pl ant St a c k . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-15 j 2.6.2 . Condenser Evacuation System......................... 2.6.3 Containment Purge .................................. 2-18 l 2.6.4 Waste Gas Header ................................... 2 21 i i 2.7 G. : ous : Ef fl uent Dose Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-26 .
- 2. 's .1 Noble Gases ........................................ 2-26 2.7.2 Radioiodines and Particulates . . . . . . . . . . . . . . . . . . . . . . 2-27
- =2.8 Gaseous Ef fluent Dose Cal cul ation . . . . . . . . . . . . . . . . . . . .=. . . . . . . 2-29 2-29 2.8.1 N o bl e G a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
2.8.1.1 Historical- Meteorology . . . . . . . . . . . . . . . . . . . 2-29 2.8.1.2 Concurrent Meteorology . . . . . . . . . . . . . . . . . . . 2-30 2.8.2 Radiciodines and Particulates ...................... 2-31 2.8.2.1. Historical Meteorology . . . . . . . . . . . . . . . . . . . 2 2.8.2.2 Concurrent Meteorol ogy . . . . . . . . . . . . . . . . . . . . . 2-33
- 2. 9 f Total Dose Cal cul ations - . .- . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-81 2.9.1 Total Dose to Most Likely kmber 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 3.0 ' PROJECTED DOSES-3.1 Liquid Dose Projection ...................................... 3-1
-3.2 Gaseous Dose Projection .................................... 3-1 4
4.0 EQUIPMENT.................................................. ..... 4-1 4.1 Radioactive Liquid Effluent Monitoring Instrumentation..., .. . 4-1 4.1.1 Speci fi cati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4- 1 4.1 '. l .1, - 4.1.1. 2 Su rvei11 ances . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 i Revision 23 l 11 02-28-91 L -
. _ . _~ ._ _ _ .- __ _ _ . . - . .._ _
i ODCM l TABLEOFC0KTENTS(Continued) , PJLSLR 4.2 Radioactive Gaseous Effluent Monitoring Instrumentation..... 4 6
- 4. 2.1 Speci fi c at i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46
- 4.2.1.1 Surveillance........................................ 46 4.3 Operability of Radioactive Waste Equipment.................. 4 13 5.0 Radiological Envi ronmental Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1 Monitoring Program.......................................... 5-1 5.1.1 Specification.......................=........... 5-1 5.1.1.1 Surveillance.................................... 52
_5.2 Land Use Census............................................. 5-11 5.2.1 ' Specification................................... 5 11 5.2.1.1 Survei11ance.................................... 5-11 5.3 Interl aboratory Compari son Program. . . . . . . . . . . . . . . . . . . . . . . . . . 5-12 5.3.1 Specification.........~.......................... 5 12 5.3.1.1 Surve111ance.................................... 5-12 5.4_ Annual Radiological Environmental Operating Report...... . .. . 513 , 5.5 S ampl e L o c a t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 - 14 S.0 Administrative................................................... 6-1 6 .1 - De f i n i t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1
- 6. 2 . Admi ni strati ve Control s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6 6.3 Major Changes!to Radioactive Waste Treatment Systems (Li quid and Gas eous) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-8 6.4 Bases....................................................... 6-9 l
Revision 22 iii 08-02-90
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ODCM LIST OF FIGURES-a t a riaure Title Paae 12 Site Boundary for Liquid Effl uents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-7 , 2-2 Site Boundary for Gaseous Effluents. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-10 4 5 - SONGS 2 and 3' Radioactive Liquid Waste Treatment Systems. . . . . .... 4-14
' 4-6 SONGS.2 and 3 Radioactive Gaseous Waste Treatment Systems........
4-15 47 Solid Waste Handling............................................. 4-16
- 51. Radiological Environmental Monitoring Sample Locations........... 5-23 Y
-l i .
1 q
. j-Revision 22 iv 08-02 / ., _au._s ~
_-- __ _~.
q 00CM LIST OF TABLES- , B Table Title Pace l l 1 l 1-1 Radioactive Liquid Waste Sampling and Analysis Program..... 1-2 !
)
1-3 Liquid. Effluent Radiation Monitors , Cal i bration Constants . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . 1-26 l 1-28 1-4 . Dose Commitment Factors j A , ............................... 2-1 Radioactive Gaseous Waste Sampling and Analysis Program..... 2 1 2-3' Gaseous Effluent Radiation Monitor Cal i bration Constants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 25
.2 -
Dom Factors for Noble Gas and Daughters . . . . . . . . . . . . . . . . . . 2-35 j 2-5 Dose Parameters Pik'"'"'""*""*"'' 2 Controlling l ocation Factors . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . 2-37
- 2-7 Dose Parameters Rj for Sector P. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-38 2-8' Dose Parameters R$ for Sector _ Q. . . . . . . . . . . . . . . . . . . . . . . . . . . 2-41 2-9 Dose Parameters R$ for Sector R. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 50 2 1 Dose Parameters Rj . for : Sector A. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-55 2 -Dose Parameters $R for Sector B............................ 2-58
-2412= Dose Parameters $R for Sector.C............................ 2-61
'2-13 Dose Parameters . Rj - for Sector D. . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-66 l 2 14 . -Dose Parameters jR for Sector E............................ 2-69
~2-15; Dose Parameters.'Rj fo r. Sect or i . . . . . . . . .- . . . . . . . . . . . . . . . . . . . . 2 -7 2 2416. DoseParameters;RjforSectorGa........................... 2-77
- 1. ' : Radioactive Liquid Effluent Monitoring Instrumentation .... 4-2
, 4-2 LRadioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements.................................. 4-4 o
i ~ 4. Radioactive Gaseous Effluent Monitoring Instrumentation..... 4 L ~4-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements.................................. 4-10 y Revision 23 02-28-91 L
DDCM LIST OF TABLES _ (Continued)) , c Table Title Paae
'5-l' : Radiological Environmental Monitoring Program. . . . . . . . . . . . . . 5-3 52 Reporting Levels for. Radioactivity Concentrations in Envi ronment al S ampl e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5- 7 5-3 Maximum Values for the Lower Limits of Detection (LLD)..... 58 5-4 Radiological Environmental Monitoring Sample Locations..... 5-15 5-5' Plc Radiological Environmental Monitoring locations........ 5-21 5-6 Sector _and Direction Designation for Radiological Environmental Monitoring Sample Locat ion Map . . . . . . . . . . . . . . 5-22 6-1 0pe rat i on al Mode s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-4
- 6-2 Frequency Notation......................................... 6-5 l-t t
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vi Revision 21 02-15-90 p L 1' . 9
l' ! INTRODUCTION L I The OFFSITE DOSE. CALCULATION MANUAL-(ODCM) is a supporting document of the f The ODCM L RADIOLOGICALEFFLUENTTECHNICALSPECIFICATIONS(NUREG0472). 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 instrumentation alarm / trip setpoints. The environmental section contains a list of the sample locations for the radiological environmental monitoring program, The OSCM 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 order to assure that the ODCM represents the n
present methodology. [ l-I- i L-L i I vii l I l
7::: v 1.0; LIQUID EFFLUENT $' 1.1 LONCENTRATION --
~
' SPECIFICATION 1.1.1 The concentration of rcdioactive material released from the site'(see Figure 1-2) shall be limited to the concentrations specified in 10 CFR Part 20. Appendix B, Table II, column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entraineo noble concentration shall be limited to 2 x 10 gases, the microcuries/ml 0 -
total activity. APPLICABILITY:- At all times ACTION: a.- With the concentration of radioactive material released from
- the site exceeding the above limits, immediately restore the concentration to within the above limits.
SURVEILLANCE REQUIREMENTS
.1 Radioactive liquid-wastes _ shall be sampled and analyzed according to the sampling and analysis program of Table 1-1.
.2 The results of the radioactivity ~ analyses shall be used in .
accordance with the methodology and parameters in Section 1.4 to: assure that the concentrations at the point of release are-maintained within the limits of Specification 1.1.1..
- =
L l :, l._ I' L l L
' l-1 '
Revision 22 08-02-90
_ TABLE 1-1 RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM , Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD) Tvoe Frecuency Frecuency Analysis (uti/ml)" A. Batch Wgste P P ReleaseQ Each Batch Each Batch Principa} Gamma 5x10 ' Emitters 1 131 1x10 ' P M Dissolved and lx10 ' One Batch /M Entrained Gases (Gama emitters) P M H3 1x10 ' Each Batch Composite b Gross Alpha , 1x10-' P Q Sr 89, St-90 5x10-' Each Batch Compositeb Fe-55 lx10
- E BATCH RELEASE PATHWAYS: Primary Plant Makeup Storage Tanks, Radwaste Primary Tanks, Radwaste Secondary Tanks, Miscellaneous Waste Condensate Monitor Tanks, Blowdown Processing Sump, FFCPD sumps (high conductivity, low conductivity).
D W Principa;, Gamma 5x10., B. Continuous Releasese,
- Grab Sample Composite c Emitters 1-131 1x10
- M M Dissolved and 1x10 '
Grab Sample Entrained Gases (Gama emittersl H-3 1x10-' D M Grab Sample CompositeC g g., D Q Grab Sample Compositec Sr-89, Sr 90 , 5x10-' Fe-55 1x10
- E CONTINUOUS RELEASE PATHWA((: Turbine Plant Sump, Blowdown Processing Sump,**
S/G Blowdown Bypass Line , S/G Blowdown, Salt Water Discharge from CCW Heat Exchanger. 1-2 Revision 22 08-02-90
TABLE 1-1 (Continuedl TABLE NOTATION , a The 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 *real" signal. For a particular measurement system (which may include radiochemical separation): 4.66 s LLD - b E . V . 2.22 x 10' . Y . 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 o'r volume), 2.22 x 106 is the number of transformations per minute per microcurie, 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 of counting (for plant effluents, not environmental samples). The value of sb used in the cniculation of the LLD for a particular measurement system snall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an ur. verified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background 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 calculation. It should be recognized that the LLD is defined as an a oriori limit representing the capability of the measurement system not asand(before a costeripd (after the fact) limit for a particular measurement.8 iFor 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 Quantitative Determination - Application to Radiochemistry" Anal . Chem. 40, 586-93 (1968). (3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanford Company Report ARH-2537 (June 22,1972). 1-3 Revision 21 02-15-90 1
TABLE 1-1 fContinued) 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 met 1od of-sampling ~employt:d results in a specimen which is representative of
- the liquids released.
l c.- To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samp1.is shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release. L
- d. A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each 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 a volume of system that has an input flow during the continuous release. ,
- f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, 00-60, Zn-65, Mo-99,'Cs-134, Cs-137, Ce-141, and Ce-144. This list does not maan l that only these nuclides are-to be detected and reported. Other peaks which
! bre measurable and identifiable, together with the above nuclides, shall also be identified and reported. l Administrative controls shall provide for composite sampling of the l continuous releases per note b vice note c until January 1,1983. L Continuous proportional sampling shall be in accordance with note c from , January 1,1983 and all times subsequent as required by Tabla 1-1. l L' The first sum) volume of BPS ion exchanger regeneration process shall be l treated as a aatch release. Sampling of this flow is not required if at least once per 31 days blowdown bypass isolation valve (S21301MU618 for Steam Generator 2E088, S21301MU619 L for Steam Generator 2E089, 531301MU618 for Steam Generator 3E088 and S3130lMU619 for Steam-Generator 3E089) is verified locked shut. 1-4 Revision 22 08-02-90
y Lico= LIQUIDEFFLUENTS'(Continued) , ., ..; l.2 DQS.E SPECIFICATION 1.2.1 The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor 1 unit, from the site (see Figure 1-2) shall be limited: ! l
- a. During any calendar cuarter to less than or equal to 1.5 mrem to the total body anc to less than or equal to 5 mrem to any l organ, and .
- b. During any enlendar 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 i limits, in lieu of any other report required by Technical
l Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a , Special Report +hich identifies the cause(s) for exceeding the limit (s) ano defines the corrective actions taken to j!
-reduce the releases and the proposed actions to be taken to-
. assure that subsequent releases.will be in compliance with- :
Specification 1.2.1.- . 1
~ SURVEILLANCE REQUIREMENTS i
.1 Dose Calculation. : Cumulative dose contributions from liquid i
= eifluents shall be determined in accordance with _Section 1.5 at !
least once-per 31 days, j
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l' p i i 1-5 Revision 21 02-15-90
1.0 1.10010 EFFLUENTS (Continued) 1.3 L10010 WASTE TREATMENT , SPECIFICATION 1.3,1 The liquid radwaste treatment system shall be OPERABLE. The a)propriate portions o' the system shall be used to reduce tie radioactive materials in liquid wastes arior to their discharge when the projected doses due to tie liquid effluent 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. APPLICABillTh At all times ACT10Ni
- 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 Commission within 30 days pursuant to Technical Specification 6.9.2 a Special Report which includes the following information:
- 1. Explanation of why liotid radwaste was being discharged without tre* % '., iaentification of the inoperable equipmen+ or subsy. ems and the reason for inopertoility,
- 2. Actirn(s) taken to restpre the inoperable equipment to OPEPABLE status, and
- 3. Sumary description of action (s) taken to prevent a recurrence.
SEyflLLANCE RE0VIREMENTS
.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 14), the appropriate portions of the liquid radwaste trLatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equi) ment for at least 15-minutes at least once per 92 days unless tie 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 liquid radwsste treatment ';; tem eruipment 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 22 08 02-90
SAN Qu0fRC WUCLCAR CCWCRATING ITAfl0N Umfl 1 tt3
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. ss SITE BOUNDARY FOR LIOUID EFFLUENTS FIGURE 1-2
REFERENCE:
TECHNICAL SPECIFICATIONS, FIGURE 5.1-4 17 Revision 21 02 15 90
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l 1.0 LIQUID EFFLUENTS (Continued) I 1.4 Liquid Effluent Monitor Methods of Setpoint Calculation' l Liquid Radwaste Effluent Line Monitors provide alarm and automatic termination of release prior to exceeding the concentration limits specified in 10CFR20, Appendix B, Table !!, Column 2 at the release point to the unrestricted area. To meet this specification and for the purpose of implementation of Specification 1.1.1, the alarm / trip setpoints for liquid effluent monitors and flow mansurement devices are set to assure that the following equation is sathhed: 5 MPC,ff (3,3) where: MPC,ff a the effective effluent maximum concentration permissible limit (uti/ml) at the release point to the unrestricted area for the radionuclide mixture being released, 1 N It (1-2) I( ) 11 HPC g 1-8 Revision 21 02-15 90 )
1.0 LIQUID EFFLUENTS (Continued) 1.4 Liquid Effluent Monitor Methods of Setpoint Calculation (Continued) where: F - fractional concentration of the ith radionuclide as i obtained by sample analysis. N .
= number of radionuclides identified in sample analysis.
th radionuclide (10CFR20, App B. MPC = MPC of the i I Table 11, Column 2). C, - the setpoint, in pCi/mi, representative of a radionuclide concentration 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 radiation 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 water flow (F) is 185,000 gpm per circ pump (4 total) and 17,000 gpm per saltwater pump (2 2cial). The design flowrate of each circulating water pump is 205,000 gpm. The value used in the determination of F takes.into account factors 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 4 02-15 90
^
1.0 L10010 EFFLUDrT5- (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)andrevisedasnecessary. 1.4.1 Batch Release Setpoint Determination The waste flow (R) and monitor setpoint (c) are set to meettheconditionofequation(11)fortheeffective MPC (MPC,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 = I C,9 + C, + C, + Ct+C, p (13) where: C = the total concentration in each batch tank. (pCi/ml) E C,1 = the sum of the measured concentrations for each
- radionuclide, i, in the ganna spectrum. (pC1/ml)
L C,p - the Fe 55 concentration as determined in the previous quarterly composite sample. (uti/ml) 1-10 -Revision 22 08-02-90 l l-
~ ~ '='~ .
l . R LIQUID EFFLUENTS (Continued) ? 1.4.1 Batch Release Setpoint Determination (Continued) ,
- ., , C, a the gross alpha concentration determined in the previous monthly composite sample. (pCi/ml)
C,
= the Sr 89 and Sr 90 concentrations as determined in the previous quarterly composite sample. (pCi/ml)
C - the H 3 concentration as determined in the previous t monthly composite sample. (ptt/ml) STEP 2: The effective MPC (MPC,77) for each batch tank (or sump) is determined using: 1 1 (1-4)
'If E
(h) + (h) + (h)(MPC + )(N)(MPC,)
+ (bf_t/1 (MPC ,
1 (MPC 4) (MPC,) t p MPC,g, MPC,, MPC t , = the limiting concentrations of the MPC p ,, MPC, appropriate radionuclide from 10CFR20, Appendix B, Table II, Column 2. NOTE: For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 pti/mi total activity. SIfL1: TheradioactivitymonitorsetpointC,(pCi/ml), may now be specified based on the values of C, I g, 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 i from the applicable calibration constants given , in Table 1-3 to correspond to the calculated monitor concentration limit C, (pci/ml). 1 11 Revision 21 02-15 90
1.0- Ll'CIO EFFLUDITS (Continued) 1.4.1 Batch Release Setpoint Determination (Continued) 1.4.1.1 RADWASTE DISCHARGE LINE MONITOR (2/3-7813) The value for C,, the concontration limit at the detector, is determined by using: (RW) fF) fC,7f) (1-5) C m RC RC pp RC nn 33 4 + MPC,ff3+ ~MPC MPC eff2 effn where: n number of tanks to be released. C,ff effective gamma isotopic concentration at the monitor for the tank combinatiori to be released (oqual to E C,9 forsingletankreleases). I(fyil+R2(fyi)2+...+R I n Ifyi n I (16) R3+R2+...+R n 1 (I C,j)3, (I C,j)2, etc. - the total gamma isotopic concentration of first tank, second tank, etc. (pti/ml). R3 , R2 , etc. the effluent flow rate from first tank, second tank, etc. Values of R for each I tank are as follows: Radwaste Primary Tanks R=140 gps / pump (xno.of.pumpstoberun) Radwaste Secondary Tanks R-140gp# pump (xno.-ofpumpstoberun) Primary Plant Makeup Tank R - 160 gp# pump (x no. of pumps to be run) Condensate Monitor Tanks R 100 gp# pump (x no. of pumps to be run) 1-12 Revision 21 02-15-90
1.0
' )
LICIDEFFLUElfTS (Continued) 1.4.1.1 RADWASTE 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 1,2 may be replaced by T. MPC,ff3, MPCeff2, etc. = values of MPC,77 fromequation(1-4)for first tank, second tank, et';. C , C2 , etc. = values of C, the total co'icentration, from - 3 equation (1 3) for the first tank, second tank,etc.inpCi/ml. are RW 7813 and SG88 2' 0089 2' 0088 3' 00 89 3, B2 ' 0 3, T 2., T3 administrative values used for'st.nultaneous 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 and SG88-2' 0089 2' 0088 3, SG89 3, B2 ' 03 , T 2,.T3 7813 will be' assigned such that RW7813 + 0088-2 + 3089 2 + 0088 3
+ SG89-3 + B2+B3 4 T2 + T3 s 1.0.
I 1-13 Revision 21 02-15 90
1.0 LIQUID EFFLUENTS (Continued) 1.4.1.1 RADWASTE DISCHARGE LINE MONITOR (2/3 78111 (Continued) , l l The 1.0 is an administrative value used to account for the l potential activity released simultaneously from other release i points. This assures that the total concentration from all 'l release points to the plant discharge will not result in a release of concentrations exceeding the limits of 10 CFR 20 l Appendix B, Table !!, Column 2 from the site. NOTE: If C ,s C,yf, then no release is possible. To increase C,, increase dilution flow F (by running f more circulating water pumps in the applicable dis- ) charge structure), and/or decretse the effluent flow rates Rj , R , etc. (by throttling the combined flow 2 as measured on 2/3F1-7643, 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 r.onitor, 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 14 Revision 21 02 15 90 l
1.0 LIQUID EFFLUENTS (Continued) 1.4.1.2 NEUTRAL 11AT10N SUMP / FULL FLOW CO@ENSATE POLISHER DEMINERAll2ER (FFCP SUMP DISCHARGE LINE MONITOR 1 batch) (?RT-7817, 3RT-7817) The value for C or C , the concentration limit at the 2 3 Unit 2 or Unit 3 detector, is determined by using: C2 5 (2}(} 1i {l'7) (R)(C/MPC,f f) (B)(F)K 3 M C3 1 1 (R)(C/MPC,77) where: C EC,g, MPC,ff the values of C, 20,g and HPC,ff as defined in STEPS 1) and 2) for the Neutralization Sump /FFCPD Sumps. Heutralization Sump R - 500 gpm FFCPD High Conductivity Sump k 500'gpm FFCPD Low Conductivity Sump R = 600 gpm C 2
- the instantaneous concentration at the detector (2RT-7817)inpCi/cc C
3
- the instantaneous concentration at the detector (3RT7617)inpCi/cc B2 and B3 are administrative values used to account for simultaneous releases from both SONGS 2 and SONGS 3 neutralization sumps. The fractions 8 and 2 B3 (each normally set to 0.05) will be assigned such that RW7813 + 8088-2
+ SG89 2 + S088 3 + S089 3 + 02+03+T2+T3 s 1.0.
1-15 Revision 22 08-02 g0
n , 1 1.0 L10010 EFFLUENTS (Continued) 1
-1.4.1.2 NEUTRALIZATION SUMP / FULL FLOW CONDENSATE POLISHER DEMINERAL17ER (FFCPD)
-SUMP DISCHARGE LINE MONITOR (batch) (2RT-7817. 3RT-7817) (Continued)
.- l NOTE: If C2 or C3s C,$, then no release is possible. To increase C 2 r C , increase dilution flow F (by 3 running more pumps), and/or decrease the effluent flow ; rate R, (by throttling the flow as measured on 2FI 3722 I and 3fl 3772), and recalculate C2 or C3using the new 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 The waste flow (R) and monitor setpoint (C,) are set to neet the condition of equation ~(11) for the effective MPC (MPC,ff) limit. The method by which this is accomplished is as follows: STEP 1: The isotopic concentration for the continuous releases are obtained for each release stream (steam generator blowdown, steam generator blowdown bypass, blowdown - neutralization sump and turbine plant sump) from the sum of the respective measured concentrations as detemined by analysis: C= 4 + C, + Ct + C,_+ Cp , (19) 1-16 Revision 22 08 02-90
l
-100 LIQUID CFFLUDfTS (Continued) .
1.4.2 ContinuousReleaseSetpointDetermination(Continued) , where:- C = total concentration (pCi/ml) ; 1 j = the total gamma activity (pCi/ml) associated with l each radionuclide, i, in the weekly composite analysis for the release stream. C, = the total measured gross alpha concentration (uti/ml) determined from the previous monthly composite analysis for the release stream. C,p
- the total Fe 55 concentration (pci/ml) as determined in the previous quarterly composite sample for the release stream.
C - the total measured H 3 concentration (pCi/ml) determined t from the previously monthly composite analysis for the release stream. C, = the total measured concentration (pci/ml) of Sr-89 and Sr 90 as determined from the previous quarterly composite analysis for the release stream. STEP 2: The effective MPC (NPC,7f) for each release stream (Steam generator blowdown, blowdown neutralization sump, or turbine plant sump) is determined using: I (1-10)
=
MPC'II E( ) , (hd) , ( ) C ggg) (Cgj_g) 1 ( PCg ) (MPC) s ( PC,) , ((MPC p ,) t (MPC) 1-17 Revision 22 08-02 90
,._%. ,e
1.0 Ll~,,21D EFFLUENTS (Continued) c 1.4.2 Continuous Release Setpoint Determination (Continued)
~ ' '
' STEP _3: The setpoint, C, (uti/ml), for each continuous release radioactivity monitor may now be specified based on the respective values of C, ECg , F, HPC,77, and R to provide compliance with the limits of 10CFR20 Appendix 8. Table !!, Column 2. The monitor setpoint (cpm)istakenfromtheapplicablecalibrationconstants ;
given in Table 13 to correspond to the calculated monitor limit C, (pci/ml). t l 1 18 Revision 21 02-15-90
Y 1.0 LIQUID EFFLUENTS (Lontinued) 1.4.2.1 hfUTRALIZATION SUMP DISCHARGE LINE MONITORS ' (2RT-7817. 31T-7817) The valua for C or C , the concentration limit at the 2 3 Unit 2 or Unit 3 detector is determined by using: (B)(F)EC j (1-11) 2 C2 I i (R)(C/MPC,ff) (112) C3 $ (B)(F)EC74 3 1 (R)(C/MPC,ff) where: C, g, HPC,ff = the values of C, E C,4 and MPC,ff as defined in STEPS 1 and 2 for the Steam Generator blowdown / BPS neutra-lization sump. R= The effluent flow rate at the radiation monitor as defined in STEP 2 (maximumof500gpm). C 2- the instantaneous concentration at the Unit 2 detector (2RT-7817)inpCi/cc C 3= the instantaneous concentration at the Unit 3 detector _(3RT-7817)inpC1/cc B2 and 83,are administrative values used to account for simultaneous releases from both SONGS 2 and SONGS 3 neutralization sumps. The fractions B 2 and B 3 will be assigned such that RW7813 + 8088-2 + 8089 2 + 3088 3 + 3089-3
+ B2+03+T 2 + T3 s 1.0 1 19 Revision 22 08 02-90
1.0 LIQUID EFFLUENTS (Continued) 1.4.2.1 tiEUTRAL17ATION SUtiP DISCHARGE LINE M3NITOR (2RT-7817. 3RT-78171 (Continued) ( l l NOTE: If C 2or C3 s I C,3 then no release is possible. To increase C or C3 , increase dilution flow F (by 2 running more circulating water putnps), and/or decrease the effluent flow rate R. (by throttling the flow as measuredon2F13722and3F13772),andrbcalculate C or C using the new F, R and equation (1 11) or 2 3 (112). 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 cecar-l 1-20 Revision 21 f 02-15-90
300 LIQUID EFFLUENTS (Continued) 1.4.2,2 STEAM GTNERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT 6733. 2RT-6739. 3RT 6753. 3RT-67591
- The value for C59 2' 053 2, C59-3 or C53-3, the concentration limit at the Unit 2 or Unit 3 detectors, is determined by using:
( 88 2 W)fC,g (l,l3) Cp5 (R)(C/MPC,ff) C 89 2 MfC,4 (l,l4) 53 2 5
. (R)(C/MPC,ff)
(SG883)(F)rC,g (R)(C/MPC,77) C 53 3 5 (* } (R)(C/MPC,ff) where: l C, E C,4, MPC,ff = values of C, E C,4 and MPC,ff (as defined in STEPS 1 and 2 above) l for the steam generator blowdown bypass. R = the maximum blowdown bypass effluent flowrate .i per steam generator, 200 gpm. C = the instantaneous concentration at the Unit 2 detector l 59 2 (2RT-6759)inpCi/ml , C 53 2
= the instantaneous concentration at the Unit 2 detector (2RT-6753)inpCi/ml C $9,3 - the instantaneous concentration at the Unit 3 detector (3RT-6759)inpCi/ml C
53 3
= the instantaneous concentration at the Unit 3 detector 1 (3RT-6753)inpCi/ml 1-21 Revision 21 -t 02-15-90 N _
+
1,0 L10il!D EFFLUDifs (Continued) 1,4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS 12RT 6753. 2RT 6759. 3RT-6753. 3RT 6759) (Continued) are RW and SG88 2' 3089 2' S088 3' S089 3' 02 ' 03, T 2, T3 7813 administrative values used for simultaneous releases from the l 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' S088 3' 30 89 3' 02 ' 03 , 7 2 T3 will be assigned such that RW7813 + S088 2 + S089 2 + S088 3
+ SG gg,3 82+03+T2+T3 s 1.0.
The 1.0 is an administrative value used to account for the ' i 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 8. Table II, Column 2 from the site. l l NOTE: If C59 2, C53 2, C59 3, or C53 3 &fC,9(forthe I respective steam generator), then no release is possible. To increase C59 2, C53 2, C59,3 or C$3,3, increase dilution flow F (by running more circulating water pumps), and/or decrease the effluent flow rate R (by throttling the flow as measured on 2FIC 4055, 2FIC-4056, 3FIC4055,3FIC-4056or2/3FI7643,asappropriate)and recalculate C59 2, C53 2, C$9,3 or C $3,3 using the new values of F, P .ad :quation (1-13), (1-14), (1-15) or (116). 1-22 Revision 21 02-15 90
1.0 LlQUID EFFLUENTS (Continued) 1.4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS
. l?RT 6753. 2RT-6759. 3RT 6753. 3RT 67591 (Continued)
If there is no release associated with this monitor, the monitor setpoint shoulo be establisned as close to background as practical to prevent spurious alarms and yet assure an alarm should an inadvertent release occur. 1.4.2.3 TURBINE PLANT S'hlP MONITORS (2RT 7821. 3RT 78211 The value for 2C or C3(theconcentrationlimitatthe Unit 2 or Unit 3 detector) is determined by using: (12 )(F)tc (117) Cg$ i, ' 4 (R)(C/MPC,ff) (T)(F) ,g 0 18) 3 (R)(C/MPC,97) where: C, 4, HPC,ff = values of C, g and MPC,gf (asdefinedinSTEPS1and2above) for the turbine plant sump R = 50 gpm/ pump (x no, sump pumps to be run) C 2
= the instantaneous concentration at the Unit 2 detector (2RT7821)inpCi/ml.
C3 = the instantaneous concentration at the Unit 3 detector (3RT7BM' inpCi/ml. 1-23 Revision 21 02 15 90
f l 1.0 LIQUID EFFLUDfT5 (Continuad) 1.4.2.3 TURBINEPLANTSUMPMONITORS(2RT-7821.3RT-7821)(Continued) are administrative values used to account for T2 "" ' T3 simultaneous releases from both SONGS 2 and SONGS 3 turbine plant sumps. The fractions T2 and 13will be assigned such that RW7333 + SG88 2 + 3089 2 + S088 3 +02*03+T2 S089 3
, + T3 s 1.0.
NOTE: If C2 or C 3 s I C,4 (for the respective sump), then no release is possible. To increase C2 or C3 , incnase the dilution flow F (by running more circulating water pumps) and recalculate C2 or C3 using the new value of F and equation (1 17) or (1 18). Use of a temporary discharge path from the Turbine Plant Sump is allowed providing the radiation monitor, 7821, in service and the normal discharge path is used concurrently. Temporary pumps facilitate faster discharge when draining the condenser to the outfall via this pathway. The following conditions shall be met:
- a. The release pemit shall account for the entire volume of water discharged from the Turbine Plant Sump.
- b. The alarm setpoint for the monitor shall be adjusted to take into account the entire discharge flow through both the normal i
and temporary paths.
- c. Procedures shall require the immediate temination of the
! discharge via the temporary path if the monitor on the normal path alarms. 1 24 Revision 21 02 15 90
s 100 LIQU!D EFFLUDifs (Continued) 1.4.2.3 TURBINE PLANT SUMP MONITORS NRT 7821. 3RT 7821) (Continued) , If there is no release associated with this monitor, the j
. monitor.setpoint should be established as close to background < as practical to prevent spurious alarms and yet assure an 4
alarm should an inadvertent release occur. 1 I l ! f - 4 1 L 4 L f d 1 25 Revision 22 08-02-90
Table 1-3 Liquid Effluent Radiation Monitor Calibration constants (uci/cc/ cpm) MONITOR Co-60 Ba-133 Cs-137 2RT 6753 1.80E-8 1.91E 8 2RT 6759 2.14E 8 1.99E-8 3RT-6753 1.79E 8 1.91E 8 3RT-6759 1.94E-8 1.94E-8 2.10E-9 3.54E-9 5.17E-9 2/3RT-7813 2RT 7817 2.12E-9 3.64E 9 5.25E-9 2RT-7821 2.10E-9 3.58E-9 5.21E-9 3RT-7817 2.13E.9 3.63E-9 5.26E-9 3RT 7821 2.11E-9 3.60E 9 5.19E-9 ("I 'This table provides typical (i 20%) calibration constants for the liquid effluent radiation monitors. 1-26 Revision 22 08 02-90
l l 1.0 LIQUID EFFLUINTS (Continued) 1.5 Dose Calculation f'or Liquid Effluents The linuid releas'es considered in the following dose calculations are describd in Section 1.4. The dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areat are calculated for the purpose of implementing Specification 1.2.1 using the foleing expression. D, = r[Ag , I(at) C g3F3)) (119) where: A, g
- the site related adult ingestion dose commitment factor to the total body or an organ, r, for each identified principal gamma and beta cmitter, i, from Table 14 in nrem/hr per pCi/ml.
j - the average concentration of radionuclide, i, in the C) undiluted liquid effluent during time period, 6tj in(pCi/ml). D, - the dose comitment to the total body or an organ, r, from the liquid effluent for the time period. At), in mrem F 3 the near field average dilution factor for Cg) during the timeperiod,At). This factor is the ratio of the maximum undiluted liquid waste flow during time period, at), to the average flow from the site discharge structure to unrestricted receiving waters, or maximum liauid radioactive waste flow discharge structure exit flow at j - the length of the jth time period over which Cg3 and F 3 re a averaged for all liquid releases, in hours. 1 27 Revision 23 02-28 91
TABLE 1-4 I DOSE COMMITHENT FACTOR $*, Aj' (crem/hr per pCi/ml) Radio- Total Thyroid Kidney Lung GI-LLI Nuclide Bone Liver Body 2.82E 1 2.82E 1 2.82E 1 2.82E 1 H3 2.82E-1 2.82E 1 4.57E-1 4.57E-1 4.57E-1 4.57E 1 4.57E 1 N 24 4.57E-1 4.57E 1 1.40E+3 5.58E+0 3.34E40 1.23E+0 7.40E+0 Cr-51 2.10E+3 2.16E+4 Mn.54 7.06E+3 1.35E+3 2.26E+2 5.67E+3 Mn 56 1.78E+2 3.15E+1 1.97E+4 2.03E+4 Fe-55 5.11E+4 3.53E+4 8.23E+3 5.30E+4 6.32E+5 Fe 59 8.06E+4 1.90E+5 7.27E+4 3.59E+3 Co-57 1.42E+2 2.36E+2 1.22E+4 Co-58 6.03E+2 1.35E+3 3.25E+4 Co-60 1.73E+3 3.82E+3 5.40E+2 1.83E+4 Cu-64 2.14E+2 1.01E+2 3.43E+5 3.23E+5 Zn 65 1.61E+5 5.13E+5 2.32E+5 9.39E-2 7.37E 7 Br 84 2.47E-11 Rb 88 1.79E+0 9.49E-1 8.00E+2 Sr 89 4.99E+3 1.43E+2 3.01E+4 3.55E+3 Sr 90 1.23E+5 4.37E+2 Sr-91 9.18E+1 3.71Ev0 1.51E+0 6.90E+2 SP-92 3.48E+1 6.42E+4 Y 90 6.06E+0 1.63E.1 2.22E 3 1.6BE-1 Y-91m 5.73E-2 9.32E+3 Y-92 5.32E-1 1.56E 2 3.46E+0 8.02E+0 1.62E+4 2r-95 1.59E+1 5.11E+0 5.51E+4 Zr-97 8.81E-1 1.78E-1 8.13E-2 7.68E-1 5.51E 1 1.01E+0 6.22E+3 Hb 95 1.84E+0 1.03E+0 1.03E+0 5.51E-1 1.01E+0 6.22E+3 Hb-95m 1.84E+0 3.91E-3 1.43E-3 4.56E-3 1.44E+1 Nb 97 1.55E-2 1.28E+2 2.43E+1 2.89E+2 2.96E+2 Mo 99 3.66E-2 4.66E-1 5.56E-1 1.79E-2 2.17E+1 Tc-99m 1.30E-2 4.60E+1 4.07E+2 1.25E+4 Ru-103 1.07E+2 1.59E+3 2.01E+2 3.06E+3 1.03E+5 Ru-106 Ag-110m 1.42E+3 1.32E+3 7.82E+2 2.59F.+3 5.37E+5 Sn 113 2.26E+5 Sn 117m 2.26E+5 lb Sb-124 2.76E+2 5.22E+0 1.09E+2 6.70E-1 2.15E+2 7.84E+3 Sb 125 1.77E+2 1.97E+0 4.20E+1 1.79E-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 5.35E+2 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 i.45E+1 1.30E+2 3.95E+1 1.90E+4 2.26E+2 1.16E+2 I-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 given, no data are available.
- Source: Reg. Guide 1.109, Table E-11, Table A 1 USNRC NUREG-0172 Table 4 @
- Methodology: USNRC NUREG-0133, Section 4.3.1 1-28 Revision 23 02-28 91
o TABLE 1-4 DOSE COMMITMENT FACTOR $*, Ab (mrenVhr per pCi/ml) i Radio- Total Nuclide Bpne Liver Body Thyroid Kidney Lung GI-LLI 6.84E+? 1.63E+4 1.33E+4 5.27E43 1.75E+3 2.85E+2 Cs-134 Cs 136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21E+2 l Cs 137 8.77E+3 1.20E+4 7.85E+3 4.07E+3 1.35E+3 2.32E+2 8.81E+0 8.70E 1 5.12E 5 Cs 138 Ba-139 6.07E+0 1.20E+1 5.59E 3 5.94E+0 2.30E-1 5.23E-3 3.17E 3 1.39E+1 h-,l 7.85E+0 Ba-140 1.64E+3 2.06E+0 1.08E+2- 7.02E-1 1.18E+0 3.38E+3 La-140 1.57E+0 7.94E 1 2.10E-1 5.83E+4 Ce 141 3.43E+0 2.32E+0 2.63E-1 1.08E+0 8.86E+3 Ce-143 6.04E-1 4.46E+2 4.94E-2 1.97E-1 1.67E+4 Ce 144 1.79E+2 .7.47E+1 9.59E+0 4.43E+1 6.04E+4
- 2 Nd 147 3.96E+0 4.58E40 2.74E-1 2.68E+0 2.20E+4 W -187 9.16E+0 7.66E+0 2.68E+0 2.51E+3 Np-239 3.53E 2 3.47E-3 1.91E 3 1.08E-2 7.11E+2 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 b
"
- Methodology: USNRC NUREG 0133, Section 4.3.1 V- y i
l l 1-29 Revision 23 02-28 91
)
Ic0- . LIQUID DFLL'TW5 (Continued) _. 1.6 Representative sampling .
..t "~~
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 501231115.11.23, ' Units 2/3 Liquid Effluent Release Permit" and 50123 III-5.2.23, ' Units 2/3 Liquid Effluent Sample Collection. A' 1 i t 1 L , I 3081c. man 1 30 Revision 21: 02-15 90
, ._ _ . . . , ._. ___ _ __..,_. .._.. _...__.~._. _.
l 2.0 EASE 005 EFFLUENTS j 2.1 DOSE RATE f I SPECIFICATION \ 2.1.1 The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents from the site (see Figure 2-2) shall be limited to the following:
- a. For noble gases: Less than or equal to 500 urem/yr to the total body and less than or equal to 3000 mrem /yr to the skin, and
- b. For all radiciodines, tritium and for all radioactive materials in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.
APPLICABillTY: At all times ACTION:
- a. With dose rate (s) exceeding the above limits, immediately decrease the *elease rate to within the above limit (s).
SURVEILLANCE RE0VIREMENTS
.) The dose rate due to noble gases in gaseous effluents shall b'e determined to be within the above limits in accordance with Section 2.7.
.2 The dose rate due to radioiodines, tritium and radioactive materials in particulate form with half lives greater than c days in gaseous effluents shall be determined to be within the above limits in accordance with Section 2.7 by obtaining representative samples and performina analyses in accordance with 't.he sampling and analysis progna specified in Table 21.
2-1 Revision 21 , 02-15-90
, TABLE 2 1 MD10 ACTIVE GASEOUS WASTE SAMPilNG AND ANALYSIS PROGRAM Minimum Type of Lower Limit Gascous Sampling Analysis Activity of Detection Release (pCi/ml)a . Type Frequency Frequsney Analysis Batch P P Each Tank Principal Gama Emitters 9 1x10**
Waste Gas Each Tank Decay Tank Grab Sample Each Batchi Each Batchi Principal Gama Emitters 9 5x10*' Incinerated Oilh Grab Sample
*
- Principal Gama Emitters 9 1x10**
Continuous
*
- Tritium 1x10**
Wd 1-131 1x10*** Continuousf Charcoal Sampler Sample 1-133 1x10*** Wd Continuousf Particulate Principal Gama Emitters 9 1x10 88 Sampler Sample (1 131 and Others) M Continuousf Composite Gross Alpha 1x10*** Sampler Particulate Sample Q Continuousf Composite Sr 89 and Sr 90 1x10 82 Sampler Particulate Sample Continuousf Noble Gas Noble Gases 1x10** 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 Grabb Condenser Air Ejector : Monthly Grabb Plant Vent Stack : Weekly GrabD e i x 2-2 Revision 22 08-02 90
TABLE 2 1 (Continued) 7ABLE NOTATION
- a. The LLD is the smallsst 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. l For a particular measurement system (which may include radiochemical senration):
4.66 s LLD . b E e V e 2.22 x 10' Y e exp ( Aot) 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 cour.ts 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 per microcurie, 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 coll'ection and time of counting (for plant effluents, not environmental samples). The value of sb used in the calculation of the LLD for a particular r..easurement system shall be bastd on the actual observed variance of the backgroand countihv rateorofthecountingrateoftheblanksamples(asappropriate)ratherthanon an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background should include the typical contributions of et.her radicnuclides normally present in the samples. Typical values of E, V, Y and at should be used in the calculation. It should be recognized that the LLD is defined as an a oriori limitrepresentingthecapabilityofthemeasurementsystemand(before not as a
- l. nosteriori (after the fact) limit for a particular measurement.*
L
*For a more complete discussion of the LLD, and other detection limits, see the
! following: l (1) RASL Currie,Procedures Manual, L. A., " Limits HASL-300 for Qualitative (revisedan Detection annually)d Quantitative Determinat (2) Application to Radiochemistry" Anal. Chem. 40, 586 g3 (1968). (3) Hartwell, J. K., " Detection Limits for Radioisotopic Counting Techniques," Atlantic RichfieldHanfordCompanyReportARH-2537(June 22,1972). 2-3 Revision 21 02-15 90 ,
TABLE 2-1 (Continued) I. I TABLE NOTAT128 '
- b. Analy;es shall also be performed following shutdown, startup, or a THEPJRL POWER change exceeding 15 percent of the RATED THERMAL POWER within a 1-hour period. This requirecent does not apply if: (1) analysis shows that the DOSE EQUIVALENT l 131 concentration in the reactor coolant has not increased more than a fWor of 3; 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 floodef..
- 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 st le.ast once per 24 hours for at least 7 days following each shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in I 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 requirement does not apply if: (1) and ysis shows that the DOSE EQUIVALENT l 131 concentration in the reactor coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 2.
- e. Tritium grab samples shall be taken at least one per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool,
- f. The ratio of the sample flow rate to 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 gamma 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 emissions and Hn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-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 measur able and identifiable, together with the above nuclides, 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.
- 1. Samples for incinerated oil releases shall be collected from representative samples of filtered oil in liquid form.
2-4 Revision 22 08-02-90
2.0; GA5E0USEFFLUENTS:'(Continued) J 2.2 DOSE - NOBLE GASES ,
- 3. SPECIFICATION 2.2.1 The air dose due to noble gases released-in gaseous effluents, from each reactor unit, from the site (see Figure l
$,-2) shall be limited to the following: .
'lI
- a. During any calendar quarter: Less than or equal to 5 mrad ;
for gamma radiation and less than or equal to 10 mrad for l beta radiation and, l 1
- b. During any calendar year: Less than or equal tc '10 mrad for l ganna radiation and less than or equal to 20 mrad for beta radiation.-
APPLICABILITY: At all times ACTION:
-aL With calculated air dose from radioactive noble gases in- i gaseous effluents exceeding any of.the above limits, in lieu
.of any other report required.by. Technical Specification -
6.9.1, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special. Report-
;which. identifies the cause(s) for exceeding the limit (s) and defines the corrective actions .teken to reduce releasos and the proposed-corrective actions to be taken to assure that subsequent releases will be in compliance with Specifica-
. tion 2.2.1. ,
SURVEILL'ANCE REQUIREMENTS
.1 Dose Calculations Cumulative dose contributions for the current cc.lendar quarter and current calendar year shall be determined in
,accordance with Section 2.8 at least once per 31 days.
2-5 Revision 21 02-15-90
v ,
- 2.0- SA$E00$-EFFLUENTSJ (Continued)?
2.3 D)SE'- RADIQ1QD.lNES. RADI0 ACTIVE MATERIALS IN PARTICULATE FORM AND T tITIUM- , SPECIFICATION: 2.3.1 The dose'to an individual from tritium, radiotodines and radioactive materials in particulate form _ with half lives ' greater than 8 days in gaseous effluents released, from each ; reactor unit, from the site (see Figure 2-2)-shall be limited ! to the following: , e.- During any calendar quarter: Less than or equal to 7.5 mrem
- to kny organ and,
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
- c. Less than 0.1% of the limits of 2.3.1 (a) and (b) as a result i, of burning contaminated oil, APPLICABILITY: At ali times h
ACTION: e
-a. With the calculated dose from the release of tritium..'
b radiciodines, and radioactive materials in particulate form,. with half lives greater than 8 days, ir gaseous #1uents t exceeding any of the above limits, in lieu of any other re)ert required.by Technical Specification 6.9.1, prepare and su)mit to the Commission.within 30 days pursuant to Technical L, , Specification .6.9.2 a- Special Report whicia identifies the-
- cause(s) for exceeding the 1imit and defines the corrective- <
actions taken to reduce releases:and the proposed actions to l be taken to assure.that subsequent releases will be in compliance with' Cpecification 2.3.1. ; SURVEILLANCE REQUIREMENTS o
.1 Done calculations Cumulative dose contributions for the current L calendar quarter and current calendar.-year shall be determined in ;
L accordance with Section 2.8 at least once per 31 days. l L t
- 4-t 2-6 Revision 21 02-1.L90
. _ _ . , ~ . .
2.0 GASEOUS EFFLUENTS (Eontinued) 2.4 GASEOUS RADWASTE TREATMENT , SPECIFICATION-2.4.1 The GASEOUS RADWASTE TREATMENT 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 rekases from the site (see Figure 2-2), when avera e0 over 31 days, would exceed 0.2 mrad for gamma radiat on and 0.4 mrad for beta radiation.
.The appropriate 'ortions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 2-2) when averaged over 31 days would exceed 0.3 mrem to any organ.*
APPLICABILITY: At all times ACTION:
- a. With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of :tny other report required by Technical Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Technical S)ecification 6.9.2, a Special Report which includes tie 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 the boperable equipment to OPERABLE status, and
- 3. Summarydescriptionofaction(s)takentoprevent a recurrence.
SURVEILLANCE REOUIREMENTS
.1 Doses due to gaseous releases from the site shal l be projected at least once per 31 days, in accordance with Si: tion 3.2.
~
"These doses are per reactor unit.
2-7 Revision 22 08-02-90
200 SASE005 EFFLUENTS (Continued) 2.4 GASEOUS RADWASTE TREATMENT- (Continued)
. - , - SURVEILLANCE RE0VIREMENTS (Continued)
.2 During plant operation (Modes 1-4), the applicable portions of i
the GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXRAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXRAUST TREATMENT SYSTEM equipment for at least IS minutes,- at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.
.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 OPERABLE by operating the GASEOUS RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXRAb,' TREATMENT SYSTEM equipment for at least IS minutes prior to e.*ocessing gases unless the appropriate gaseous,radwaste system has been utilized to process radioactive gaseous effluents during the previous 92 days.
l l l l f 2-8 Revision 22 08-02-90
2.0 GASEOUS EFFLU3TS (Continued) L 2.5 TOTAL DOSE
- SPECIFICAT103 2.5.1 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel 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 months. APPLICABILITY: 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.a.
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) ccvered by this report. Iftheestimateddose(s) exceeds the limits of Specification 2.5.1, and if the release condition resulting in viointion 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 190.11(b). Submittal of the report is considered 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 REOUIREMENTS
.1 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with surveillance 1.2.1.1, 2.2.1.1,'and 2.3.1.1.
2-9 Revision 21 02-15-90
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REFERENCE:
TECHNICAL SPECIFICATIONS, FIGURE 5.1-3 2-10 Revision 21 02-15-90
._ -- c -. -. -
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1 230 GASE0US EFFLUENTS (Continued) 2.6_ Methods of Calculation for Gaseous Effluent Monitor Setooints 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 and revised as required. 2.6.1 PLANT VENT STACK - 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, t
.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 mre#yr total body dose rate at the exclusion area boundary is determined by: C (0.38)(2120 h,,c)(500mre#yr)(10"m'/cc) (2-1) det = (Flow rate, cfs) (X/Q, sec/m')[E (Kj , mrem /vr) ( Gj ,)) i C1/m' C tot where: C = the instantaneous concentration at the detector, det pC1/cc 0.38 - an administrative value used to account for potential activity from other gaseous release pathways t i 2-11 Revision 22 08-02-90
200 GASE0US EFFLUENTS (Continued)
- 2. 6.1. PLANT VENT STACK - 2/3RT 7808, 2RT-7865 1, 3RT-7865 1 (Continued)
' ~ ~ ~
Kj = the total body dose conversion factor for the ith gamma emitting noble gas, mrem /yr per pC1/m*, from Table 2-4
- concentration of the ith noble gas, as determined C,
by sample analysis, pCi/cc C - total concentration of noble gases, as determined tot by semple analysis, (pCi/cc) = ECg i Flow Rate = ~ the plant vent flow rate, cfm
= 83,000cfm/ fan (xno.offanstoberun)
+ 17,500 cfm (laundry facility) 2120 - cenversionconstant,cfmperm8/sec 500 mrem /yr = total body dose rate limit, as specified by Specification 2.1.1.a X/Q = historical annual average dispersion factor, sec/ms
= 4.8E-6 sec/mi ikin The concentration at the detector corresponding-to a 3000 mrcm/yr skin ' dose rate at the exclusion area boundary is determined by:
(0.38)(2120 ,. )(3000 mrem /yr)(10m'/cc) e (2-2)
, (Flow rato, cfm) (X/Q, sec/m*)[E(L g + 1.1Mg , mrem /vr)( _Gj ))
i pCi/m' C tot 2-12 Revision 22 08 02-90
2.0 GASE0US EFFLUENTS (Continued) PLANT VENT STACK - 2/3RT 7 BOB, 2RT-7865-1, 3RT-7865-1 d (Continue.)
- 2. 6.1 :
where: Lg - skin Dose Conversion Factor for the ith noble gas, mrem /yr per pCi/m*, from Table 2-4 Mg - air Dose Conversion factor for the ith noble gas, mrem /yrperpCi/ms, from Table 2-4 1.1 = conversion factor to convert gamma air dose to skin dose 3000 mrem /yr = skin dose rate limit, as specified by Specification 2.1.1.a
.0ther values in equation (2-2) are defined in equation (2-1).
from equations (2-1) or The smaller of the values of Cdet (2-2) is to be used in the determination of the maximum permissible monitor alam setpoint (cpm), as follows: The maximum permissible alarm setpoint (cpm) is . determined using the calibration constant for 2/3RT-7808 given in Table 2-3. The maximum pemissible alarm setpoint is the valua
" cpm" corresponding to the concentration, Cdet (the smaller 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 efficiency (the largest value in tems of pCi/cc/ cpm).
The alarm setpoint will be maintained at a value not greater - than the maximum permissible alam setpoint. 2-13 Revision 21 02-15-90
%3 . . . . . . . . . . . . . . . . . . .. .. . . . ..
2.0 - GASEOUS EFFLUEHTS (Continued) 2.6.1 PLANT VENT STACK - 2/3RT-7808, 2RT-7865-1, 3RT-78651 (Continued)
; _,, If there is no release associated with this monitor,.the monitor setpoint should be established as close as practical to background to prevent spurious alar.u and yet assure an alarm ,
should inadvertent release occur. 2.6.1.2 2RT-7865 1 and 3RT-7865-1 Wide Ranoe Gas Monitors The maximum release rate (pCi/sec) for Wide Range Gas Monitors is determined by converting the concentration at the detector, Cdet (pCi/cc) to an equivalent release rate in pC1/sec, as follows: A . IGdct. uti/ccif flowrate. cc/sec) (2-3) max where: A = the maximum pemissible release rate, pCi/sec max C det
= the smaller of the values of C det obtained from equations (2-1) or (2-2).
Flow Rate - flow rate, cc/sec
= (3.917 x 10' cc/sec per fan) (number of fans-to be run) + 8.259 x 10' cc/sec (laundry facility) 2 'a factor to compensate for the split flow between Unit 2 and Unit 3 plant vent stacks The release rate setpoint will not be set greater than the .
maximum release rate detemined above, when this monitor is being used to meet the requirements of Specification 2... 11 2-14 Revision 21 02-15-90
TABLE 2-12 DOSE PARAMETER R FOR SECTOR C Page 3 of'5 '
' ~
Pathway - Sewage Facility Distance - 2.2 miles' l X/Q = 1.2E-7 sec/m' 0/Q - 1.2E-9 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 H -3 0- 2.9E+2 Cr 51 3.3E+3 1.lE+6 Mn 54 3.2E+5 3.2E+8 Co-57 8.4E+4 7.8E+7
-Co-58 2.lE+5 8.7E+7 Co-60 1.4E+6 4.9E+9 Sr-89 -0 3.2E+5 4.9E+3 Sr-90 2.3E+7 Zr-95 4.0E+5 5.7E+7 Nb-95 0- 1.2E+5 3.lE+7 Ru-103 1.2E+5 2.5E+7 lb Te-129m 0- 2.6E+5 4.5E+6 Cs-134 1.9E+5 1.6E+9 Cs-136 0- -0 3.3E+4 3.4E+7 Cs 137 1.4E+5 2.3E+9 Ba-140 2.9E+5 4.7E+6 Ce-141 8.3E+4 3.1E+6 Ce-144 1.8E+6 1.6E+7 I -131 2.7E+6 3.9E+6 I -132- 2.6E+4 2.8E+5 lb I -133 4.9E+5 5.6E+5 I -134 6.8E+3 1.0E+5 lb I -135 1.0E+5 5.8E+5 UN-ID 2.0E+5 1.7E+8 Inhalation Pathway, units
"}f("
y Food & Ground Pathway, units I" " "FI 7 2-63 Revision 23 l 02-28-91
- w. -
TABLE 2-12 DOSE PARAMETER Rg FOR SECTOR C l Page 4 of'5 j Pathway Sheep (Meat)' Distance - 0.2 miles X/Q = 6.5E-6 sec/m D/Q = 5.3E-8 m ' Infant Child Teen Adult Food & Inhala- Food & Inhala- Food & Inhala- Food & Inhala-Radio- tion Ground tion Ground tion Ground tion Ground Pathway Pathway Pathway Pathway Pathway Nuclide Pathway Pathway Pathway 1.5E+0 1.2E+0 7.0E+0 2.1E+0 H -3 0- 5.1E+1 1.0E+2 7.9E+1 2.6E+4 Cr-51 7.6E+6 7.8E+2 1.4E+3 7.7E+3 Mn 54 1.9E+6 4.7E+3 8.1E+3 2.0E+3 Co-57 2.1E+6 9.7E+3 2.0E+4 5.1E+3 Co-58 3.3E+4 1.2E+8 Co-60 3.7E+4 7.3E+4 5.0E+4 2.6E+4 7.7E+3 3.1E+4 Sr-89 1.3E+6 1.0E+6 8.1E+5 5.5E+5 Sr-90 1.6E+6 6.3E+4 1.1E+5 9.7E+3 Zr-95 2.8E+3 1.6E+6 Nb-95 2.4E+5 4.5E+5 Ru-103 4.2E+5 7.6E+3 2.8E+3 1.9E+6 lb 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Te-129m 1.4E+5 1.2E+5 4.7E+3 3.8E+7 Cs-134 Cs-136 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 5.1E+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 4.3C+4 4.3E+5 I -131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 I -132 F.3E+2 6.8E+3 [h 1 -133 1.6E-2 8.7E 3 1.2E+4 1.3E+4 I -134 1.6E+2 2.5E+3 p I -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units " F , Food & Ground Pathway, units - (m )(mrem /vr) uti/sec 1 2-64 Revision 23 l 02-28-91
TABLE 2-12 DOSE PARAMETER Rg FOR SECTOR C Page 5 of 5 1 l 1.0 miles Distance Pathway - Deer Consumer D/Q = 5.1E 9 m** X/Q = 3.4E-7 sec/m* Child Teen Adult Infant Food & Inhala- Food & Inhal a- Food & Inhala- Food & Inhala- Ground tion Ground tion Ground tion Ground tion Radio- Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide 2.8E+1 2.3E+1 3.5E+1 3.9E+1 H -3 3.2E+5 5.0E+4 1.0E4 5 3.9E+2 Cr-51 3.8E+4 4.1E+7 Mn-54 7.7E+5 1.4E+6 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-57 4.7E+7 9.6E+6 1.9E+7 2.5E+4 Co-58 7.2E+8 3.6E+7 7.2E+7 1.6E+5 Co-60 3.1E+7 4.9E+7 2.6E+7 3.8E+4 Sr-89 1.2E+9 1.0E+9 8.0E+8 2.7E+6 Sr-90 4.8E+4 2.0E+8 Zr-95 6.2E+7 1.lE+8 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 lb 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Te-129m 3.4E+8 1.4E+8 1.2E+8 2.3E+4 Cs-134 9.5E+6 5.lE+6 4.2E+6 4.0E+3 Cs-136 4.0E+8 1.3E+8 9.3E+7 1.7E+4 Cs-137 7.4E+6 5.0E+6 4.2E+6 3.5E+4 Ba-140 4.2E+6 1.5E+6 2.4E+6 9.9E+3 Ce-141 Ce-144 1.8E+7 2.9E+7 2.lE+5 4.9E+7 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -131 3.4E+4 (b I -132 3 lE+3 1.6E+1 8.6E+0 5.9E+4 6.7E+4 1 -133 I -134 8.2E+2 1.2E+4 IA 1.1E-15 6.3E-16 1.2E+4 6.9E+4 I -135 1.4E+8 UN-ID 1.1E+8 9.4E+7 2.4E+4 Inhalation Pathway, units = !" , I" " vr) Food & Ground Pathway, units jc 2-65 Revision 23 ) 02-28-91
TABM 2013 i FOR SECTOR 0 l DOSE PARAMETER R$ Page 1 of 3 Pathway Camp San Ono[re Distance 2.0 miles ' X/Q 6.6E-8 sec/m D/Q - 6.4E 10 m-Child Teen Adult Infant Food & Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Ground tion Ground Radio- tion Ground tion Ground tion Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide Pathway 0- 0- 0- 1.3E+3 0- , H3 0- 4.7E+6 0- 1.4E+4 Cr 51 - 0.- 0- 1.4E+6 1.4E+9 Mn 54 0- 3.7E+5 3.4E+8 Co 57 0- 9.3E+5 3.BE+8 0- 0-Co 58 0- 6.0E+6 2.2E+10 Co-60 0- 1.4E+6 2.2E+4 g Sr 89 9.9E+7 Sr-90 0-1.8E+6 2.5E+8 Zr 95 5.0E+5 1.4E+8 Hb 95 Ru-103 5.0E+ 5 1.lE+8 l^ Te 129m 0- 1.2E+6 2.0E+7 8.5E+5 6.8E+9 Cs-134 1.5E+8 Cs-136 0- 0- 1.5E+5 Cs-137 -0 5.2E+5 1.0E+10 0- 1.3E+6 2.lE+7 Ba-140 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 1.lE+5 1.2E+6 IA 1 -132 I -133 2.2E+6 2.4E+6 1 -134 3.0E+4 4.5E+5 [A 1 -135 4.5E+5 2.5E+6 UN-ID- 8.6E+5 7.5E+8 Inhalation Pathway, units = ""'1/m!" pC Food & Ground Pathway, units = im )Imrem/vr) pC1/sec 2-66 Revision 23 l 02-28-91 l
. . . ~ .. - . . - . ~ . - . - - - . - . .- - _ -.- . . - _ _ - - - - . . . - _ -
TABLE 2-13 DOSE PARAMETER Rj FOR SECTOR D Page 2 of 3
..~ (
Pathway Sheep (Meat)' Distance - 0.2 miles X/Q = 6.3E-6 sec/m 0/Q = 6.6E 8 m ' ; 1 Infant Child Teen Adult l Inhala- Food & Inhal a- - Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground- tion Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide Pathway .I 1
)
1.5E+0 1.2E+0 7.0E+0 2.1E+0 H~-3 5.lE+1 1.0E+2 7.9E+1 -2.6E+4 Cr 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Mn-54 4.7E+3 8.lE+3 2.0E+3 1.9E+6 Co-57
.Co 58 - 9.7E+3 2.0E+4 5.lE+3 2.1E+6 i Co-60 3.7E+4 7.3E+4 3.3E+4 1. h.+6 Sr-89 -0 . 5.0E+4 2.6E+4 7.7E+3 3.lE+4 Sr-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.1E+5 9.7E+3- 1.6E+6 Nb -0 . 2.4E+5 4.5E+5 2.8E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5- 2.8E+3 1.9E+6 lh-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 5.lE+3 4.3E+3 8.1E+2 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 Co-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
- I -132- 6.3E+2 6.8E+3 Ik IL-133 1.6E 8.7E-3-' 1.2E+4 1.3E+4 1.-134 - - - l.6E+2 -2.5E+3 lA I -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4
-UN-ID_ 1.1E+5 -9.5E+4 4.8E+3 -4.2E+6~
Inhalation _ Pathway, units "]j f . Food & Ground Pathway, units I" " 7 2-67 Revision 23 02-28-91
TABLE 2-13 DOSE PARAMETER R FOR SECTOR D 9
. Page 3 of 3 i
. Pathway = Deer Consumer Distance 1.0 n.iles J l
X/Q 3.3E-7 sec/m' 0/Q - 3.3E 9 m ' Infant Child ~.een Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & l Radio- tion Ground tion Ground tion Ground- tion Ground Pathway Pathway Pathway Pathway Pathway Nuclide Pathway ' Pathway Pathway 2.8E+1 2.3E+1 3.5E+1 3.9E+1 H -3 5.0E+4 1.0E+5 3.9E+2 3.2E+5
-Cr-51 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Mn 54
-0 4.6E+6 8.0E+6 1.0E4 3 2.3E+7 Co 57' --
4.7E+7 Co-58 9.6E+6 1.9E+7 2.5E+4 Co-60 3.6E+7 0- 7.2E+7 1.6E+5 7.2E48 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.lE47 1.0E+9 8.0E+8 2.)E+6 1.2E+9 < Sr-90 Zr-95 6.2E+7 1.lE+8 4.8E+4 2.0E+8 Nb 95 2.3E+8 -0 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 [h Te-129m- - 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.lE+6 4.2E+6 4.0E+3 9.5E+6 O Cs-137 l'.3E+8 9.3E+7 1.7E+4 4.0E+8 D Ba-140 5.0E+6 4.2E+6 3.EE+4 7.4E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6
'Ce-144 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 lb-I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 1 -134 8.2E+2 1.2E+4 Ih .
I -135 1.lE 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 = % , Food & Ground Pathway, units I*3 II""**/VPI pC1/sec 2-68 Revision 23 02-28-91
o TABLE 2-14 1 DOSE PARAMETER R g FOR SECTOR E Page 1 of 3 Pathway Camp Horno Distance 4.0 miles ' X/0 6.6E-8 soc /m' 0/Q = 6.4E-10 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 H -3 1.3E+3 Cr-51 0- 1.4E+4 4.7E+6 Mn-54 0- 1.4E+6 1.4E+9 00 57 0- 3.7E+5 3.4E+8 Co 58 0- 9.3E+5 3.8E+8 C0-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 p' Sr-90 9.9E+7 Zr-95 1.8E+6 2.5E+8 Nb-95 5.0E+5 1.4E+8 Ru 103 5.0E+5 1.1E+8 IA Te-129m - 1.2E+6 2.0E+7 Cs-134 8.5E+5 6.8E+9 Cs-136 1.5E+5 1.5E+8 Cs-137 6.2E+5 1.0E+10 Ba-140 1.3E+6 2.1E+7 Ce 141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 1 -132 0- 1.lE+5 1.2E+6 IA I 133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 lA I--135 4.5E+5 2.5E+6 UN-10 8.6E+5 7.5E+8
"'*#V" Inhalation Pathway, units = "C1/m* p 2
Food & Ground Pathway, units - (m )(nrem/vr) pCi/sec 2-69 Revision 23 02-28-91
TABLE 2-14
. DOSE PARAMETER Rg FOR SECTOR E Pathway Sheep (Meat)' Distance - 0.3 miles X/Q=4.5E6sec/m D/Q = 5.9E 8 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 Nuclide Pathway H -3 1.5E+0 1.2E+0 7.0E+0 2.lE+0
.0- 5.lE+1 1.0E+2 7.9E+1 2.6E+4 Cr-51 7.8E+2 0- 1.4E+3 7.7E+3 7.6E+6 Mn-54 4.7E+3 8.lE+3 2.0E+3 1.9E+6 Co-57 C0-58 9.7E+3 2.0E+4 5.1E+3 2.lE+6 Co-60 -0 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Sr-89 5.0E+4 2.6E+4 7.7E+3 3.lE+4 Sr-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 2r-95 6.3E+4 1.lE+5 9.7E+3 1.6E+6 Nb-95 '2.4E+5 4.5E+5 T. 8E+3 1.6E+6 Ru-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 lk l -- Te 129m 6.0E+5 4.5E+5 .6.4E+3 7.6E+5 Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 l 4.3E+3 8.lE+2 8.3E+5 Cs-136 5.lE+3 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
.I -132 6.3E+2 6.8E+3 lb I -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 I -134 1.6E+? 2.5E+3 lA i
I -135 1.lE-18 6.4E-19 2.5E+3 1.4E+4 ! UN-ID 1.lE+5 9.5E+4 4.BE+3 4.2E+6 l l l l Inhalation Pathway, units ' " y Food & Ground Pathway, units - (m')(mrem /vri pC1/sec 2-70 Revision 23 02-28-91
~
2.0 ,rgg!S a EFFLUDfTS (Continued) 2.6.1 PLANT VENT STACK - 2/3RT-7808, 2RT-7865 1, 3RT-7865-1 (Continued) If there is no release associated with this monitor, the monitor setpoint should be established as close as practini to background to prevent spurious alarms and yet assure an alarm should an inadvertent release occur. 2.6.2 CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-1, 3RT 7818 or 3RT-7870 1 2.6.2.1 2B1-1818 and 3RT-7818 Condenser Air Eiector Monitors For the purpose of implementation of Specification 2.1.1, the alana setpoint level for noble gas monitors 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'
.C ( II
- I see)I Y)5 / ) (2-4) det - (Flow rate, cfm) (X/Q, sec/ms)[r (K ,j mrem /vr) ( __qj ))
i pC1/m' C tot The concentration at the detector corresponding to a 3000 mrenVyr skin do e rate at the exclusion area boundary is determined by using: Skin C Sec ( * #)I " /C ) (2-4a) det . (Flow rate, cfm) (X/Q, sec/ms)[I(L 4 + 1.1Mg , mrem /vr)( _qj,_)) i pCi/m* C tot 2-15 Revision 21 02-15-90
2.0 GASEOUS EFFlygl{L$ (Continued)' 2.6.2 CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-1, 3RT 7818 or 3RT-7870-1 (Continued) where: O.1 is an administrative value used to account for potential activity from other gaseous release pathways. 0.5 is an administrative value used to account for releases from both SONGS'2 and SONGS 3 condenser air ejector. simultaneously. Other parameters are specified in 2.6.1.1, above. fr m equations (2-4) or The smaller of the values Cdet (2-4a) is to be used in determining the maximum permissible monitor alarm setpoint (cpm), as follows: The maximum permissible alarm setting (cpm) is determined by using the calibration constant for the corresponding Condenser Evacuation System Monitor given in Table 2-3. The maximum permissible alarm setpoint is the epm value corresponding to the concentration, Cdet, [ smaller value from equation I.2-4)or-(2-4a)). The calibration constant used is based on Kr-85 or on Xe-133, whichever yields a lower detection efficiency (higher value in terms of pti/cc/ cpm). The alarm setpoint will not be set greater than the maximum pennissible alarm setting determined above. 2-16 Revision 21 02-15-90
. . . x < . . . ..
2.0 GASEOUS EFFLUENTS (Continued) 2.6.2 CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870 1, 3RT 7818 or ' 3RT-7870-1 (Continued) l IfthereisnoreleaseassociatedwIththismonitor, the monitor setpoint should be established as close as practical to background to prevent sourious alarms yet assure an alarm should an inadvertent release occur. 2.6.2.2 2RT-7870-1 and 3RT-7870 1 Wide Ranoe Gas Monitors The maximum release rate (pCi/sec) for Wide Range Gas Monitor is determined by converting the concentration at the detector, C det (pCi/cc), to an equivalent release rate in pCi/sec. bax-(Cdet, pCi/cc) (flow rate, cc/sec) where: bax = the maximum permissible release rate, pCi/sec Cdet - the smaller value of Cdet, as obtained from equations (2-4) and (2-4a) flow rate = flow rate of the condenser air ejector, cc/sec
- 4.719ES cc/sec (conservatively assumed as design flow rate)
If there is no releasc associated with this monitor, the
. monitor setpoint should be established as close as practical to background to prevent spurious alarms yet assure an alarm should an inadvertent release occur.
2-17 Revision 21 02-15-90
= ~~~* _ _ _ _ _ _ _ - _ _ _ _ _
2.0- GASE0US EFFLMDEI (Continued) I 2.6.3 GfTAINMENT W i - 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 on the gaseous effluent flow rate and the meteorological dispersion factor.
, The concentration at the detector corresponding to a total b0dy dose rate of 500 mrem /yr at the exclusion boundary is determined by using:
Total Body C (0.38)(P)(2120 ,h[,c)(500 mrem /yr)(10"m*/cc) (2-6) det2 -(Flow rate, cfm) (X/Q, sec/m*)[r (K g , mrem /vr) ( lj_ )) i pC1/m* C tot C (0.38)(P )(2120 jf,7[,e)(500mre#yr)(10"m*/cc) (2-7) det3 -(Flow rate,_cfm) (X/Q, sec/m*)[I (K g , mrem /vr) ( lj_ )) i pCi/m* C tot The concentration at the detector ccrresponding to a 3000 mrem /yr skin dose rate at the exclusion area boundary is determined-by using: Ekin C M / ec ( W)I "/ ) (2-6a) det2 -(Flow rate, cfm) (X/Q, sec/m*)[I(L i 4 + 1.1M pC1 g
, g/mr)( 33_
C }) tot C
- m / ec ) @ 00 mre# y d (10" m'/cc) (2-7a) det3 -(Flow rate, cfm) (X/Q, sec/m')[I(L g + 1.1M g , mrem /vr)( lj_ ))
i pCi/m* C tot 1 2-18 Revision 22 08-02-90
- ! 2.0; SASEuuS EFFLUENTS (Continued):
2;6.31 CONTAINMENT PURGE - 2RT-7828, 3RT,7828, 2RT-7865, 3RT-7865~ ,
.( Continued). ,
[ '< where: , C 4 det2 = The instantaneous concentration of the Unit 2 detector inpCi/cc. ' C det3 - The. instantaneous concentration of the Unit 3-detect
~
in pCi/cc.- 0.38 is an-administrative. values used to account for potential- , activity.from other gaseous' release pathways.
. P and P are administrative values used to account for Y simultaneous purges.of both SONGS 2 and SONGS 3. The fractions'P and Ps will be assigned such that.
# ' ~
~P + P s 1.0.
Flow l rate' . the observed maximum flowrate in cfm from the unit specific monitor 7828. Default values will be the following conservative measured flows:
=; 50,000 cfm full purge
= 3,000 cfm mini-purge.
[~ .
+
(The above values replace thv. smaller design , flowrites.) - n ~ 1 Other parameters are as specified in 2.6.1.l above. The smaller of the valuesiof maximum permissible Cdet2 II'" ' equation (2-6)or(2-64)andCdet3 fromequations(2-7) l' or-(2-7a) is to be used in determining the maximum permissible monitor alarm setpoints. 19 Revision 22 3 08-02-90 I
.s. #+Aw e r 4 90 h
- euyaedFer* -- r --
2.0 J. 2005 EFFLUENTS '(Continued) 2.6.3 CONTAINMENT PURGE - 2RT 7828, 3RT-7828, 2RT-7865, 3RT-7865 (Contit.ued) 2.6.3.1 Maximum P,ermissible Alarm Settina (RT-7865) The maximum permissible alarm setting for the Wide Range Gas Monitor expressed as a maximum release rate (pCi/sec) is determined by converting the concentration at the detector, C det (pti/cc),to an equivalent release rate in pCi/sec. A,,x = (Cdet, Ci/cc) (flow rate, cc/sec) ; where: A
= the maximum permissiblo release rate (pCi/cc) .
max C = the smaller value of Cdet, as obtained from det equation (2-6,2-6a)forUnit2or(2-7,2-7a) for Unit 3. flow rate - flow rate, cc/sec
-1.416E6cc/secformini-purge 4
= 2.360E7 cc/sec for main purge.
t
.2. Maximum Permissible Alarm Settino (RT-7828)
LThe maximum permissible alarm setting for RT-7828 is in-
- pCi/cc and is the smaller of the values of Cdet2(pci/cc) fromequations(2-6)-and.(2-6a).
If there.is no release associated with this monitor, the. monitor setpoint should be established as close es practical to background to prevent spurious alarms yet-assure an alarm i should an inadvertent release occur. e 2-20 Revision 22 08-02-90 l
' GASEOUS EFFLUENTS (Continued) 2.0 2.6.4 WASTE GAS HEADER - 3RT-7865, 2/3RT-7808 For the purpose of Specification 2.1.1, the :larm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor. Since the ,
waste gas header discharges to the plant vent stack, either 3RT-7865 or 2/3RT-7808 may be used to monitor waste gas header releases. The concentration at the detector corresponding to a total body dose rate of 500 arem/yt or a skin dose rate of 3000 mrem /yr at the exclusion area boundary is determined by using equations (2-1) or (2-2) with suple concentration (C g) 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) is to be used in determining the maximum permissible monitor alarm setpoint. 2/3RT-7808 The maximum permissible alarm setting (cpm) is determined by using the calibration constant for plant vent stack mor.itor 7808 given in Table 2-3. The maximum permissible setpoint is the cpm value corresponding to the concentra-tion Cdet, (smaller.value from equation (2-1) or (2-2)). 2-21 Revision 21 I 02-15-90
2.0_ GASEOUS EFFLUENTS (Continued) 2.6.4 WASTE GAS HEADER - 3RT-7865, 2/3RT-7808 (Continued) 3RT-7865 The maximum permissible alarm setting is expressed as a maximum release rate (pci/sec) and is determined by c converting the concentration at the detector, Cdet, to an equivalent release rate in pCi/see by equation (2-8). 4 ,x - M et. uti/ce) (flowrate. 2 cc/seci (2-8) F where: A = the maximum permissible release rate, pCi/sec det
-C det
= the smaller value cf Cdet, as obtained from equation (2-1) or (2-2),
flowrate -- flowrate, cc/sec
= 7.83E7 cc/sec for 2 fan operation or
= 3.92E7 cc/sec or 1 fan operation 2 = correction 't;r 3-7865 viewing only 1/2 the total Pleat Vent Stack Flow.
.1 A release from the waste gas header is not possible if:
(2-9) (fi){ f)>Cdet 2-22 Revision 21 02-15-90
I 20 GASE0US EFFLUENTS (Continued) 2.6.4 WASTE GAS HEADER - 3RT-7865, 2/3RT-7808 (Continued) , 2.6.4.1 (Continued) where: total concentration in waste gas holdup tank IC4= 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; 83,000 for 1 fan operation)
+ 17,500 cfm (laundry facility) from equation (2-1)
Cdet = smaller of the values of Cdet being obtained from the waste gas holdup or (?-2) with C4 tank to be released if a release is not possible, adjust the waste gas header flow by determining the maximum permissible waste gas header effluent flow rate corresponding to the Vent Stack Monitor setpoint in accordance with the following: f 4 (0.9)(Cdet)(F) (2-10) I C, i where: f = waste gas header effluent flow rate (cfm) F= plant vent stack flow rate (cfm) used in equation (2-1)or(2-2) 2-23 Revision 21 , 02-15-90 l
2;i. $AK005 EFFLUDf75 -(Continued) 2.6.4 WASTE. GAS HEADER - 3RT 7865, 2/3RT 7808 (Continued) , 2.6.4.1 (Continued) IF0" Cdet = the sm611er of the value of Cdet equation (2-1)or(22) , total gamma activity (pCi/cc) of the waste EC9= i gas holdup tank to be released, as determined from the pre release sample analysis. The 0.9 is an administrative value to account for the potential l activity frem other releases in the same release pathway. i 4 9 l p i 2 24 Revision 21 02-15 90 i ( . 2 - __
Table 2 3(*) Gasecus Effluent Radiation Monitor Calibration constants (pCi/cc/ cpm) MONITOR Kr 85 Te 133 2/3RT7808C 3.90E 8 4.62E 8 2RT 781AA 4.27E 8 6.63E 8 2RT 7818B 7.31E.5 2.07E 5 3RT 7818A 3.73E 8 5.09E 8 3RT 78188 9.31E 5 2.21E 5 I (a)This table provides typical (120%) calibration constants for the l passous effluent radiation monitors. . i 2 25 Revision 21 02-15 90 L
I 2.0 $ASE00$..EFFLUDif$ (Continued) 2.7 anseous Efn uent Dese Rate , The methodology used for the purpose of implementation of Specification 2.1.1 for the dose rate above background ) I to an individual in an unrestricted area is calculated i by using the following expressions: 2.7.1 FOR NOBLE CASES: D (211) ; T8 " E, _El IEIN 01_ , D, =I (Lg+ 1.lM )g TX7@ Qg_ (212) j_ wheret l , l-b.TB
- total body dose rate in unrestricted area; fue to radioactive materials released in gaseous effluents, in are#yr i
b, = skin dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, in arc #yr Kg = the total- body dose factor due to gamma
- omissions for each identified noble gas radionuclide,i,inare#yrperpCi/m' from Table 2 4.
t 2 26 Revision 21 02-15-90
. -. . , -- =_= - - .. . . .
2.0 GA$E005 EFFLUENTS (Cchtinued) 2.7.1 FOR NOBL LG.MFJ (Continued)
= skin d)se factor due to the beta emissions for 14 each identified noble gas radionuclide,1, in mrem /yr per pCi/m' from Table 2 4 Hj = the air dose factor due to gamma emissions for each identified noble gas radionuclide, i, in mrad /yr per pCi/m' from Table 2 4.
(conversion constant of 1.1 mre# mrad converts airdosetoskindose.) hg - the measured or calculated release rate of radionuclide, i, for either continuous or batch gaseous effluents, in pti/sec TXTOT = 4.8E-6 sec/m'. The maximum annual average atmospheric dispersion factor for any sector or distance at or beyond the unrestricted area boundary. 2.7.2 [pR ALL RAD 101DDINES. TRITIUM AND FOR ALL RADIDACTIVE MATERI ALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN ElGHT DAYS: {I[(P ik N)k (2-13) o i) where: b, = organ dose rate in unrestricted areas due to radioactive materials released in gaseous effluents, in mre#yr : 2-27 Revision 22 08-02-90
2.0 MSE005 EFFLUENS (Continued) 2.7.2 FOR ALL RAD 1010Y NES. "RITIUM AND FOR ALL RAD 10ACT)yE , MATER lALS IN PA rlCULA"E FORM WITH HALF LIVES GREATER THAN EIGHT DAYS (Continued) hj = the measured or calculated release rate of radionuclide, i, for either continuous or batch gaseous effluents, inpCi/sec t P = the dose parameter for radionuclide, i, for ik pathway, k, from Table 2 5 for the inhalation pathway in r. rem /yr pet pCi/ms. The dose factors are based on the critie.a1 individual. organ and the child age group. W = the highest calculated annual average k dispersion parameter for estimating the dose to an individual at or beyond the unrestricted area boundary for pathway k.
= (X,7Q),4.8E6sec/m*fortheinhalationpathway.
The location is the unrestricted area in the W sector.
- (D7Q),4.3E8m**forthefoodandground plane pathways. The location is the -
unrestricted area in the E sector. L, . l 2-28 Revision 22 08-02 90
.m . , _ , - , , , . __, - - _ , , , . --w.--, m. . ---, .- - , -
2.0 GASEOUS EFFLUENTS (Continued) i 2.8 Egeous Effluent Dose Calculatan , 2.8.1 DOSE FROM NOBLE GASES IN GASEOUS EFFLUENTS The gaseous releases considered in the following dose , calculations are described in Section 2.6. The air dose in unrestricted areas due to noble gases released in gaseous effluents is calculated using the following expressions: 2.8.1.1 [gy historical meteoroloav:
= 3.17x10** E jM ( M Qg) (2 14)
D, D = 3.17x10 I N [g IT/QT Qg) (2-15) p where:
. D,
= the total gamma air dose from gaseous effluents, in mrad D = the total beta air dose from gaseous j
effluents, in mrad 3.17x10 = (inversesecondsperyear) Mg - the air dose factor due to gama emissions for each identified noble gas radionuclide,1, in mrad /yr per pC1/m' from Table 2-4 , Ng - the air dose due to beta emissions for each identified noble gas radionuclide, i, in arad/yr per pCi/m' from Table 2-4 2-29 Revision 22 08 02 90
200 M SE00$ EFFLUENT $ (Continued) 2.8.1.1 For historical meteoroloov: (Continued) TVQT = 4.SE6sec/m'. The maximum annual average atmospheric dispersior. factor for any sector or ; distance at or beyond the unrestricted area l boundary. 1 Qj
= the amount of noble gas radionuclide,1, l l
released in gaseous effluents in pC1. 1 2.8.1.2 For meteoroloav conctrrent with release: ) l NOTE: Consistent with the methodology provided in Regulatory ! Guide 1.109 and the fol hwing equations, RRRGS (Radioactive Release l I Report Gen'erating System) software is used to perform the actual calculations. i
. l D,, =1.14x10**rM[I(Atj j (X/Q)), Qgj)) (2-16)
D, g = 1.14x10r N 4 [I (6tj (X/Q)), Qjj)) (2-17) where: D,, - the total gamma air dose from gaseous effluents in sector e, in mrad , D, j
- the total beta air dose from grseous effluents in sector #, in mrad 1.14x10 =inversehours/ year 1
Mg = the air dose factor due to gamma emissions for each identified noble gas radionuclide, i, in arad/yr per pCi/m' from T:. ale 2-4. I 2-30 Revision 22 08-02-90 L
2.0 SASE005 EFFLUENTS (Continued) 2.8.1.2 For meteoroloav_ concurrent with release: (Continued) N4 . the air dose factor due to beta emissions , for each identified noble gas radionucith, i, in mrad /yr per pCi/m' from Table 2 4. th time period over At j = the length of the which (X/Q)3, and Qg) are averaged for gaseous releases in hours
= the atmospheric dispersion factor for (X/Q)),
time period Atj at exclusion boundary location in sector a determined by concurrent meteorology, in sec/m' 0 - the averege release rate of radionuclide, 93 i, in gaseous effluents during time period, Atj , in pCi/sec 2.8.2 DOSE FROM TRITIUM. RAD 1010 DINES AND RADIDACTIVE MATERI AL S IN PARTICULATE FORM WITH HALF LIVES GREATERTHAN 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, = 3.17x10E[( ikk)Ol W i (218) 2 31 Revision 21 02.15 90
8.0 EASE 005 U FLUENTI (Continued) i I (Continued) 2.8.2.1 For historical meteoroloovt where:
- the total prohected dose from gaseous D,
effluents to an individual, in mrem
- the amount of each radionuclide, i, Qg (tritium,radiciodine, radioactive material in particulate form with half lives greater than eight days), released in gaseous effluents in pCi IR ikWk - the sum of all pathways k for radionuclide, 1, of the R ,g W product in mrem /yr per pCi/sec. The I RikNk value for each radionuclide, i, is given in Table 2-6.
The given is the maximum I RikNk for all k locations and is based on the most restrictive age groups. R ik
- the dose factor for each identified radionuclide, i, for pathway k (for the inhalation pathway in mre#yr per pCi/m' and for the food and ground plane pathways in m' - mre#yr per pC1/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 ODCM g Dose Parameters for SONGS 1, 2, and 3' from E.S.MedlingtoP.H.Penseyres, dated 1/29/91).
2-32 Revision 23 1 02-28-91
2.0 M5E005 EFFLUENTS (Continued) 2.8.2.1 For historical meteorology: (Cont lnued)
~~
W - the annual average dispersion parameter for k estimating the dose to an individual at the controlling location for pathway k.
- TI7QT for the inhalation pathway in sec/ms .
The TX76J for each controlling location is given in Tables 2 7 thru 216.
- TD7QT for the food and ground plane pathways in m" . TheTD7QTforeachcontrolling location are given in Tables 2 7 thru 2 16.
2.8.2.2 f_qt.gteorolooy concurrent with releases: 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. , 1mn . D, 1.14 x 10" I I I ((At)) (Rik#) (Njke) (Olj)] (2-19) where: D, the total annual dose from gaseous effluents to an individual in sector # in mrem. the length of the j th period over which Wjke At j and Qg) are averaged for gaseous released in hours Qjj = the average release rate of radionuclide,1, in gaseous effluents during time period Atj inpCi/see 2-33
- Revision 22 08 22-90
l 200 RASE 005 EFFLUENTS (Continued)
' 2.8.2.2 - For meteoroloav concurrent with relettes: (Continuvj Rike = the dose factor for each identified radioni lide 1, for pathway k for sector # (for the inhalatcm pathway in are#yr per pCi/m' and for the food and ground plane pathways in m' are# yr per pC1/sec) at the controlling location. A listing of R ik or f the controlling locations in each landward )
- sector for each group is given in' Tables 2-7-thru !
1 2 16. The # is determined by the concurrent i meteorology. ; l Wjke = the dispersion parameter for the time period Atj for each pathway k for calculating the dose to an individual at the controlling. location in sector # l using concurrent meteorological conditions. i
= (X/Q) for the inhalation pathway in sec/m'
= (D/Q) for the food and ground plane pathways in m**
3 I. . . l p 2-34 Revision 21 02-15 90 7_
TABLE 2-4 00$E FACTORS F6R NOBLE EASES AND DAUGU ER$** W
-Total Body Dose Skin Dose Gamma Air Dose Beta Air Dose Factor K g Factor L 9 Factor M g Factor N g (mreWyr (mreWyr (mrad /yr (mrad /yr Radio- perpC1/m')
Nuclide perpCi/m') perpC1/m') perpCi/m') kr 85m 1.17E+3* 1.46E43 1.23E+3 1.97E+3 1.34E+3 1.72E+1 1.95E+3 Kr 85 1.61E+1 Kr-87 5.92E+3 9.73E+3 6.17E+3 1.03E+4 ) Kr 88 1.47E+4 2.37E+3 1.52E+4 2.93E43 f Xe-131m 9.15E+1 4.76E+2 1.56E+2 1.11E+3 Xe-133m 2,51E+2 9.94E+2 3.27E+2 1.48E+3 Xe-133 2.94E+2 3.06E+2 3.53E+2 1.05E+3 Xe-135m 3.12E+3 7.llE+2 3.36E43 7.39E+2 Xe-135 1.81E+3. 1.86E+3 1.92E+3 2.46E+3 Xe 138 8.83E+3 4.13E+3 9.21E+3 4.75E+3 l Ar 41 8.84E+3 2.69E+3 9.30E+3 3.28E(3 I
*1.17E+3 1.17 x 10'
- ** Source: USNRC Reg. Guide 1.109, Table B 1 2-35 Revision 21 02-15-90
TABLE 2 5 DOSE PARAMETER P ik* CHILD AGE GROUP CRITICAL ORGAN . Inhalation Pathway Inhalation Pathway (mrem /yrperpCi/m) Radionuclide (mrem /yr per pCi/m ) Radionuclide 1 -131 1.6E+7 H-3 1.1E+3 1.7E+4 1 132 1.9E+5 Cr-51 1.6E+6 1 -133 3.8E+6 Mn 54 5.1E+5 1 134 5.1E+4 C0 57 Co 58 1,1E+6 1 -135 7.9E+5 C0-60 7.1E+6 Cs 134 1.0E+6 Sr-89 2.2E+6 Cs 136 1.7t+5 Sr 90 1.0E+8 Cs-137 9.1E+5 Zr 95 2.?E+6 Ba-140 1.7E+6 Nb 95 6.1E+5 Ce 141 5.4E+5 Ru 103 6.6E+5 Ce 144 1.2E+7 lb Te 129m 1.8E+6
- Source: USNRC NUREG-0133, Section 5.2.1.1 2 36 Revision 23 I 02-28 91
TABLE 2 6 l CONTROLLING LOCATION FACTOR 5 , IR ikNk Raeionuclide mres/yr per pCi/sec l
,I H -3 9.62E-4 l Cr-51 3.25E-2 j Mn-54 6.52E+0 1 Co 57 1.66E+0 -
l Co 58 2.33E+0 co 60 8.56E+1 . Sr 89 4.34E+1 l Sr 90 1.82E+3 J i Zr 95 2.90E+0 Nb 95 6.81E+0 Ru-103 1.08E+1 i Te-129m 5.32E+0 l Cs-134 3.36E+1 : l Cs-136 6.81E-1 Cs 137 3.67E+1 8a 140 1.56E+0 Ce 141 5.74E 1 Ce-144 1.68E+1 I -131 1.19E+1 l I -132 'I.45E-1 j I -133 2.82E+0 . I -134 3.94E 2 l I 135 5.94E 1 UN-ID 3.59E+0 i i l I l Footnote: ~ These values to be used in manual calculations are the maximum ERW ik kfor all locations based on the most restrictive age group. k 2-37 Revision 23 02 28 91
TABLE 2 7 DOSE PARAMETER Rt FOR SECTOR P Page 1 of 3 4 Pathway Surf Beach Distance 0.4 miles' D/Q 8.2E 9 m* X/Q = 1.8E-6 sec/m' Infant' Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala. I Food & tion Ground tion Ground tion Ground tion Ground Radio- Pathway Pathway Pathway Nuclide Pathway Pathway Pathway Pathway Pathway 5.lE+1 0- 8.7E+1 0-H3 0- 1.2E+1 1.1E+5 9.9E+2 3.2E+5 Cr 51 0- 0- 1.8E+2 2.2E+4 8.4E+2 1.6E+4 6.6E+6 8.0E+4 3.2E+7 9.6E+4 9.5E+7 Mn 54 0- 0 0- 5.3E+3 1.6E+6 2.4E+4 7.9E+6 2.5E+4 2.3E+7 Co-57 0-0- 1.2E+4 1.8E+6 5.4E+4 8.7E+6 6.4E+4 2.5E+7 Co 58 0- 1.5E+9 0- 7.3E+4 1.0E+8 3.5E+5 4.9E+8 4.1E+5 00-60 0- 2.2E+4 1.0E+2 9.7E+4 4.9E+2 9.6E+4 1.5E+3 Sr-89 0-1.1E+6 0- 4.4E+6 6.8E+6 Sr 90 1.7E+7 0- 2.3E+4 1.2E+6 1.1E+5 5.8E+6 1.2E+5 Zr 95 3.5E+4 9.4E+6 Nb 95 0- 6.4E+3 6.6E+5 3.0E+4 3.1E4 5 5.2E+5 3.2E+4 2.5E+6 3.5E+4 7.4E+6 (h Ru 103 0- 6.9E+3 0- 1.8E+4 9.4E+4 8.0E+4 4.5E+5 7.9E+4 1.3E+6 Te 129m 4 Cs 134 0- 1.1E+4 3.3E+7 4.5E+4 1.6E+8 5.8E+4 4.7E+8 3.4E+6 1.0E+4 1.0E+7 Cs 136 Cs 137 0-0- 0-1.8E+3 9.4E+3 7.2E+5 4.9E+7 7.8E+3 3.4E+4 2.4E+8 4.3E+4 7.1E+8 k Ba 140
- 0- '
1.8E+4 9.9E+4 8.2E+4 4.7E+5 8.7E+4 1.4E+6 Ce-141 5.7E+3 6.6E+4 2.5E+4 3.1E+5 2.5E+4 9.4E+5 Ce 144 0- 1.2E+5 3.3E+5 5.4E+5 1.6E+6 5.3E+5 4.GE+6 i I 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 6.1E+3 2.8E+4 7.8E+3 8.5E+4 lb I 133 4.0E+4 1.2E+4 1.2E+5 5.6E+4 1.5E+5 1.7E+5 I -134 5.3E+2 2.2E+3 1.6E+3 1.0E+4- 2.0E+3 3.1E+4 lg 1 135 8.2E+3 1.2E+4 2.5E+4 5.8E+4 3.lE+4 1.7E+5 UN !D 1.0E+4 3.6E+6 5.0E+4 1.7E+7 5.9E+4 5.1E+7 Inhalation Pathway, units "}j#,7 y Food & Ground Pathway, units l' ""'#VN C1/sec l 2-38 Revision 23 02-28 91 4
l TABLE 2-7 DOSE PARAMETER Rj FOR SECTOR P Pa9e 2 of 3 Pathway Pt. Loran Mijitary Hsng Distance = 3.6E 2.7 miles ' X/Q 1.2E 7 sec/m D/Q 10 m* i Infant Child Teen Adult , Inhal a- - 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 i H3 6.5E+2 1.1E+3 1.3E+3 0- 1.3E+3- 0 Cr 51- 1.3E+4 4.7E+6 1.7E+4 4.7E+6 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 1.4 E4 6 1.4E+9 Co 57 3.8E+5 3.4E+8 5.1E+5 3.4E+8 5.9E+ 5 3.4E+8 3.7E+5 3.4E+8 00 58 7.8E+5 3.8E+8 1.lE+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+6 Co-60 4.5E+6 2.2E+10 7.lE+6- 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr-89 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-90 '4 lE+7 1.0E+8 0- 1.1E+8 0- 9.9E+7 - L .Zr 95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb 95 4.8E+5 1.4E+8 6.lE+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.1E48 6.6E+5 1.1E+6 7.8E+5 1.1E+B 5.0E+5 1.1E+8 Te 129m 1.7E+6 2.0E+7- 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 8.5E+5 2.0E+7 6.8E+9 g Cs-134 7.0E+5 6.8E+9 1.0E+6 '6.8E+9- 1.1E+6 6.8E+9 ' Cs-136 1.3E+5 1.5E+8 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.lE+5 1.0E+10 8.5E+5 1.0E+10 6.2E+5 1.0E+10 2.lE+7-
-Ba 140
- 1.6E46 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.1E+7 1.3E+6
.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 Co 144 4.8E+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 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.lE+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 4.0E+4 4.5E+5 3.0E+4 4.5E+5 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 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 l Inhalation Pathway, units = yj",#7 L
-Food & Ground Pathway, units = '"
~
" VPI l:
2 39 Revision 23 02-28-91
._ , _ ~ _ _ _ _ _ . - -_ _ _ , _ _ _ _ _ _ _ . _ _ _ _ . . _ . _ _ . . _ . .
TABLE 2-7 DOSE PARAMETER Rt FOR SECTOR P Pathway Former Nixon Estate (no garden) Distance 2.8 miles ' D/Q 3.4E-10 m* X/Qw 1.2E-7 sec/m' Child Teen Adult Infant Food & Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Ground tion Ground Radio- tion Ground tion Ground tion Pathway Pathway Pathway Pathway Pathway Nuclide Pathway Pathway Pathway 1.3E+3 0- 1.3E+3 H -3. 6.5E+2 1.lE+3 4.7E+6 1.7E+4 4.7E+6 2.lE+4 4.7E+6 1.4E+4 Cr-51 1.3E+4 4.7E+6 1.4E+9 1.6E+6 1.4E+9 2.0E+6 1.4 E+ 9 1.4E+6 Mn 54 1.0E+6 1.4E+9 3.4E+8 5.1E+5 3.4E+8 5.9E+5 3.4E+8 3.7E+5 Co 57 3.8E+5 3.4E+8 3.8E+8 1.1E+6 3.BE+8 1.3E+6 3.8E+8 9.3E+5 Co-58 7.8E+5 3.8E+8 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Co-60 4.5E+6 2.2E+10 7.1E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr 89 2.0E+6 2.2E+4 2.2E+6 1.1E+8 0- 9.9E+7 0-Sr-90 4.lE+7 1.0E+8 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 Zr 95 1.8E+6 2.5E+8 5.0E+5 1.4E+8 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+5 1.4E+8 Nb 95 5.0E+5 1.1E+8 # Ru-103 -5.5E+5 1.1E+8 6.6E+5 1.lE+8 7.8E+5 1.1E+8 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Te 129m 1.7E+6 2.0E+7 1 lE+6 6.8E+9 8.5E+5 6.8E+9 Cs-134-Cs 136 7.0E+5 1.3E+5 6.8E+9 1.5E+8 1.0E+6 1.7E+5 6.8E+9 1.5E+8 1.9E+5 1.5E+8 1.5E+5 1.5E+8 1.0E+10 h 6.1E+5' 1.0E+1.0 9.lE+5 1.0E+10 8.5E+5 1.0E+10 6.2E+5 Cs 137 1.6E+6 2.lE+7 l.7E+6 2.lE+7 2.0E+6 2.lE+7 1.3EtG 2.lE+7 Ba-140- i 1.4E+7 5.4E+5 1.4E+7 6.1E+5 1.dEt7 3.6E+5 1.4E+7 Co-141 5.2E+5 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 Ce 144 9.8E+6 1.6E+7 1.7E+7 1.5E+7 I.7E+7 1.2E+7 1.7E+7 I -131 1.5E+7 1.7E+7 1.2E+6 lA I -132 1.7E+5 1.2E+6 .l.9E+5 1.2E+6 1.5E+5 1.2E+6 1.1E+5 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
'5.lE+4' 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 (A I -134 4.5E+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 2.5E+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 s
e u Ir.halation Pathway, units "[j",#7 y Food & Ground Pathway, units I"'II"P**/VPI pC1/sec 2-40 Revision 23 02-28-91
TABLE 2-8 DOSE PARANETER Rj FOR SECTOR Q Page 1 of 9 Pathway Enlisted Beh Trailers Distance = 4.6E-9 1.1 miles' m* D/0 X/Q = 9.3E 7 sec/m' Child Teen Adult Infant Food &' Inhala- Food & Inhal a- Food & Inhala- Food & Inhala. tion Ground tion Ground tion Ground tion Ground Radio- Pathway Pathway Pathway Nuclide Pathway Pathway Pathway Pathway Pathway 6.3E+2 0-
-H -3 0-2.3E+6 0 0- 0- 0- 7.2E+3 Cr-51 6.9E+8 Mn 54 0- 0- 0- 7.0E+5
-0 0- 0- 0- 1.8E+5 1.7E+8 Co-57 0-Co-58 0- 0- 4.6E+5 1.9E+8 Co 60 -0.. 0- 0- 3.0E+6 1.1E+10 0- 0- 7.0E45 1.lE+4 Sr-89 Sr-90 0- 5.0E+7 Zr-95 0- 8.8E+5 1.3E+8 Nb-95 0- 2.5E+5 6.8E+7 k Ru-103 0- 2.5E+5 5.4E+7 ,
-0 0- 5.8E+5 9.8E+6
.Te 129m 0- 4.2E+5 3.4E+9 Cs-134 0-Cs-136 0. 0- 7.3E+4 7.5E+7 ,
0- 3.1E+5 5.lE+9 Cs-137
-C- - 0- 0- 0- 6.4E+5 1.0E+7 Ba-140 0- 1.8E+5 6.8E+6 Ce-141 3.9E+6 3.5E+7 Ce 144 I -131 -0 . 0- 6.0E+6 8.6E+6 5.7E+4 6.2E+5 I -132
.I -133 0- 0- 1.lE+6 1.2E+6 ,
I -134 0- 0- 1.5E+4 2.2E+5 I'-135. 0- 2.2E+5 1.3E+6 UN-ID 0- 4.3E+5 3.7E+8 r Inhalation fathway, units =y"]j',#7 Food & Ground Pathway, units = U""'*#VN I"t pCi/sec 2 41 Revision 23 l 02 28 91 . u _,_- -- _,_. -
l i TABLE 2-1 DOSE PARAMETER Rj FOR SECTOR Q Page 2 of 9 Pathway San Onofre Mobil Homes Distance = 1.3 miles' X/Q = 7.4E 7 sec/m* D/Q = 3.6E 9 m*
)
Infant Child Teen Adult I 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 , s 1.lE+3 1.3E+3 0- 1.3E+3 -0 H -3 6.5E+2-1.4E+4 4.7E46 Cr-51 1.3E+4- ~4.7E+6 1.7E+4 4.7E+6 2.lE+4 4.7E+6 1.6E+6 1.4E+9 2.0E46 1.4E+9 1.4E+6 1.4E+9 Mn 54 1.0E+6 1.4E+9 3.4E+8 5.1E+5 3.4E+8 5.9E+5 3.4E+8 3.7E+5 3.4E+8 Co-57 3.8E+5 3.8E+8 1.1E+6 3.8E+8 1.3 E+ 6 3.8E+8 9.3E45 3.8E+8 Co 58 7.8E+5 2.2E+10 7.1E+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E410 % Co 60 4.5E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr 89 2.0E+6 0-Sr-90 4.lE+7 0- 1.0E+8 0- 1.1E+8 0- 9.9E+7 2.5E+8 2.2F+6 2.5E+8 2.7E+6 2.5E+8 1.8E46 2.5E+8 Zr-95 .1.8E+6 1.4E+8 Nb 95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7. 5E+ 5 1.4E+8 5.0E45 Ru-103 5.5E+5 1.lE+8 6.6E+5 1.lE+8 7.8E+5 1 !E+8 5.0E45 'l.lE48 lh Te-129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 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 134_ Cs-136- 1.3E+5 1.5E48- 1.7E+5 1.5E+8 1.9E+5 1.5E+8 1.5E45 1.5E+8 Cs 137- 6.lE+5' l.0E+10 9.1E+5 1.0E+10 8.5E+5 1.0E+10 6.2E45 1.0E+10
-Ba-140 1.6E+6 2.1E+7 1.7E+6 _2.lE+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 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 1.5E45 1.2E+6 1.lE+5 1.2E+6 iA 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 1 -134' 4.5E+4 4. 5E+ 5 5.lE+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 lh 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 y= "]f !"
Food & Ground Pathway, units I" " V"I j 2-42 Revision 23 02 28-91 l ': I L- _ _ _ , , , , _
- ~_ _ _ . . _ _ _ _ _ . . . _ . _ _ _ _ , _ _
TABLE 2-8 DOSE PARAMETER Rj FOR SECTOR Q l Page 3 of 9 Distance 0.6 miles Pathway State Park 0[fice Trailer D/Q - 1.2E-8 m-' X/Q=2.7E-6sec/m Child Teen Adult Infant Food & Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Ground Ground tion Ground tion Ground tion Radio- tion Pathway Pathway Pathway Pathway Pathway Nuclide Pathway Pathway Pathway 0- 5.8E+1 H3 2.1E+5 0- :- 6.6E+2 Cr 51 6.4E+4 6.3E+7 Mn 54 0- 1.7E+4 1.6E+7 Co 57 0- 0- 0- 4.2E+4 1.7E+7 Co-58 0- 0- 0-0- 2.7E+5 9.BE+8 Co 60 0- 9.9E+2 0- 6.4E+4 Sr 89 4.5E+6 Sr 90 0- 8.1E+4 1.1E+7 Zr 95 0- 0-0- 0- 2.3E+4 6.2E+6 Nb 95 0-5.0E+6 lb 0- 0- 0- 2.3E+4 Ru-103 9.0E+5 0- 5.3E+4 Te 129m 3.1E+8 3.9E+4 Cs 134 Cs 136 0-0- 0-6.7E+3 2.8E+4 6.9E+6 4.7E+8 h Cs-137 0- 0-0- 0- 5.8E+4 9.4E+5 Ba 140 6.2E+5 Ce 141 1.7E+4 3.6E+5 3.2E+6 Ce 144 7.9E+5 I 131 0- 5.4E+5 0- 5.2E+3 5.7E+4 th I 132 0- 0- 9.8E+4 1.lE+5 I -133 2.1E+4 I -134 -0 0- 1.4E+3 th I -135 2.0E+4 1.2E+5 0- 3.9E+4 3.4E+7 UN ID Inhalation Pathway, units - Yr Food & Ground Pathway, units I"'IISP'*#VII pC1/sec 2-43 Revision 23 1 02-28-91
TABLE 2-8 DOSE PAPMETER Rj FOR SECTOR Q Page 4 of 9 l Pathway Surf. Beach Guard Shack Distance 0.7 miles X/Q = 1.8E-06 sec/m' 0/Q = 9.9E-09 m-' Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground
- ion Ground tion Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide Pathway H3 0- 7.2E+1 0- l Cr-51 0- 0- 0- 8.2E+2 2.7E+5 l Mn 54 8.0E+4 7.9E+7 Co-57 0- 0- 0- 0- 0- 2.lE+4 2.0E+7 2.2E+7 Co-58 5.3E+4 Co 60 0 0- 3.4E+5 1.2E+9 Sr-89 0 0- 8.0E+4 1.2E+3 Sr-90 0- -0 0- 0 5.7E+6 Zr-95 -0 0 1.0E+5 1.4E+7 i Nb 95 2.9r+4 7.BE+6 Ru-103 0- 0' 2.9E+4 6.2E+6 lb Te 129m 0- 6.6E+4 1.lE+6 Cs-134 0- 0- 0- 4.8E+4 3.9E+8 n i Cs-136 8.4E+3 8.6E+6 5 i Cs-137 ,
3.5E+4 5.9E+8 l Ba-140 0- 7.3E+4 1.2E+6 Ce 141 0- 2.1E+4 7.8E+5 Ce-144 4.4E+5 4.0E+6 I -131 6.8E+5 9.8E+5 1 -132 -0 0- 5.5E+3 7.lE+4 lh I -133 1.2E+5 1.4E+5 1 -134 1.7E+3 2.6E+4 16 ' I -135 0- 2.6E+4 1.4E+5 UN ID 0- 4.9E+4 4.3E+7 Inhalation Pathway, units
"]fhr y
9 Food & Ground Pathway, units Im Hmrem M ) pC1/sec 2-44 Revision 23 02 28-91 t
- m. . . _ . _ _ . . . ._ - _ - - _ _ _ _ _ _ _ _ _ ___
l IABLE 2-8 J DDSE PARAMETER Rj FOR SECTOR Q Distance - 1.4 miles h thway Enlisted Beach Check-In D/0 3.2E-9 m X/Q - 6.8E-7 sec/m' Infant Child Teen Adult Food & Inhala- Food & Inhala- Food & Inhala- Food & inhala. Ground tion Ground Rtdio- tion Ground tion Ground tien Pathway Pathway Pathway Pathway Pathway Nutlide Pathway Pathway Pathway 4 2.9E+2 H3 0- 0-0- 3.3E+3 1.1E+6 Cr 51 0- 0- 0- 0-0- 0- 0- 3.2E+5 3.2E+8 Mn 54 0- 7.8E+7 0- -0 0- 0- 8.4E+4 Co 57 8.7E+7 i Co 58 0- 2.1E+5 0- 0- 1.4E+6 4.9E+9 00 60 0 4.9E+3 0- 0- 3.2E+5 Sr 69 Sr 90 -0 -0 0- 2.3E+7 0- 4.0E+5 S 7E+7 Zr 95 3.1E+7 Nb-95 -0 0- 1.?E+5 Ru-103 0- 0- 1.2E+5 2.5E+7 lE Te 129m 0- 2.6E+5 4.5E+6 Cs 134 0- 1.9E+5 1.6E49 Cs 136 0-0- 3.3E+4 1.4E+5 3.4E+7 2.3E+9 Cs 137 ! 4.7E+6 4 Ba 140 0- -0 2.9E+5 0- 0- 8.3E+4 3.1E+6 Ce 141 , Ce 144 0- 0- 1.8E+6 1.6E+7 I 131 0- 0 0- 2.7E+6 3.9E+6 1 -132 0- 2.6E+4 2.8E+5 lb 0- 0- 4.9E+5 5.6E+5 I 133 0-1.0E+5 I 134 0- 0- 0- 6.8E+3 16 . I -135 0- -0 1.0E+5 5.8E+5 i UN ID 2.0E+5 1.7E+8 l 1 L
- Inhalation Pathway, units yj*[!"
Food & Ground Pathway, units IP'II""**#V"I pCi/sec r 2 45 Revision 23 02-28 91
1 TABLE 2 8
)
DOSE PARAMETER Rj FOR SECTOR Q Page 6 of 9
~
Pathway - Sheep (Meat)' Distance = 1.6 miles' X/Q = 5.6E-7 sec/m D/Q = 2.6E-9 m-Child Teen Adult Infant Food & Inhala- Food & - Inhala. Food & Inhala- Food & Inhala-Ground tion Ground tion Ground tion Ground Radio- tion Pathway Pathway Pathway Nuclide Pathway Pathway Pathway Pathway Pathway 1.5:+0 0- 1.2E+0 7.0E+0 2.1E+0 H -3 -0 0-1.0E+2 7.9E+1 2.6E+4 Cr-51 0- 5.1E+1 7.6E+6 7.8E+2 1.4E+3 7.7E+3 Mn 54 0- 0 2.0E+3 1.9E+6 0- 0- 0- 4.7E+3 0- 8.1E+3 Co 57 5.1E+3 2.1E+6 0- 9.7E+3 0- 2.0E+4 Co 58- 3.3E+4 1.2E+8 Co-60 0- 0- 3.7E+4 7.3E+4 0- 5.0E+4 2.6E+4 7.7E+3 3.1E+4 Sr-89 - 5.5E+5 1.3E+6 Sr 90 0- 1.0E+6 8.1E+5 0- 6.3E+4 1.1E+5 9.7E+3 1.6E+6 Zr-95 1.6E+6 0- 2.4E+5 4.5E+5 2.8E+3 Nb-95 lb 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 7.6E45 Te 129m 3.8E+7 0- 1.4E+5 0- 1.2E+5 4.7E+3 Cs-134 Cs-136 0- 0- 5.1E+3 4.3E+3 9.5E+4 8.1E+2 3.4E+3 8.3E45 5.7E+7 h
.Cs-137 0- 0- 1.3E+5 5.1E+3 0- 4.3E+3 .7,0E+3 1.2E+5 Ba-140 .
1.5E+3 2.4E+3 2.0E+3 7.9E+4 , Ce 141-Ce-144 - 0- 0- 1.8E+4 0- 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- 0- 6.3E+2 6.8E+3 lA I 133 0- 0- 0- 1.6E 2 8.7E-3 1.2E+4 1.3E+4 I -134 1.6E+2 2.5E+3 lA I -135 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 l-l l Inhalation Pathway, units y= "]j',# l " Food & Ground Pathway, units = 1"? " ""*"#V"I C1/sec 2-46 Revision 23 02-28 91
_.~. _ _ _ - . _ _ _ _ . _ _ _ _ . - _ _ . _ _ . _ _ _ _ _ _ _ _ _ . _ , 4 TAsLE 2-8 D05E PARANETER Rj FOR 5ECTOR Q ' i Page 7 cf 9 ; Pathway.S.C.ResWGgrden Distance 4.1 miles ' -2 X/Q = 1.2E 07 sec/m D/Q = 4.lE 10 m- - Infant Child Teen Adult l Inhala- Food & Inhala- Food & Inhela- Food & Inhala. Food & Radio- tion Ground tion Ground tion Ground tion Ground Pathway' Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide H -3 6.5E+2 0- 1.1E+3 3.8E+3 1.3E43 2.4E+3 1.3E+3 1.9E+3 L Cr-51 1.3E+4 4.7E+6 1.7E+4 9.4E+6 2.lE+4 1.2E+7 1.4E+4 1.lE+7 Mn 54 1.0E+6 1.4E+9 1.6E+6 2.0E+9 2.0E+6 2.2E+9 1.4E+6 2.2E+9 i Co 57 3.8E+5 3.4E+8 5.lE+5 5.6E+8 5.9E45 6.3E+8 3.7E+5 5.8E+8
-Co 58 7.8E+5 3.8E+8 - 1.1E+6 7.1E+8 1.3E+6 8.9E+8 9.3E+5 8.5E+8 Co 60 4.5E+6 2.2E+10 7.1E+6- 2.3E+10 8.7E+6 2.4E+10 6.0E+6 2.4E+10
$r-89. 2.0E+6 2.2E+4 2.2E+6 3.lE+10 2.4E+6 1.2E+10 1.4E+6 7.2E+9 fs Sr-90 4.lE+7 1.0E+8 1.3E+12 1.lE+8 7.7E+11 9.9E+7 5.8E+11 Zr 95 1.8E+6 2.5E+8 2.2E+6 1.0E+9 2.7E+6 1.3E+9 1.8E+6 1.2E+9
. Nb 95 4.8E+ 5 1.4E+8 6.1E+5 3.8E+8 7.5E+5 4.9E+8 5.0E+5 4.5E+8 Ru 303 . 5.5E+5 1.lE+8 6.6E+5 4.4E+8 7'.8E45 5.6E+8 5.0E+5 4.9E+8 lA Te:120m 1.7E+6 2.0E+7 1.8E+6 2.4E+9 2.0E+6 1.4E+9 1.2E+6 9.7E+8 Cs 134 7.0E+5 6.8E+9 1.0E+6 3.lE+10 1.lE+6 2.2E+10 8.5E+5 1.6E+10 > Cs 136- 1.3E+5 1.5E+8 1.7E+5 2.4E+8 1.9E+5 2.1E+8 1.5E+5 1.9E+8 Cs 137 ^ 6.lE+5 1.0E+10 9.lE+5 3.4E+10 8.5E+5 2.3E+10 6.2E+5 1.8E+10 Ba 140 1.6E+6 2.lE+7 1.7E+6 1.3E+8 2.0E+6 8.8E+7 1.3E+6 7.4E+7 1
. Ce 141_ 5.2E+5 1.4E+7 5.4E+5 3.4E+8 6.lE+5 4.2E+8 3.6E+5 3.3E+8 Ce-144 9.8E+6 7.0E+7 1.2E+7 9.3E+9 1.3E+7 1.2E+10 7.8E+6 9.0E+9 1 131 1.5E+7 1.7E+7 1.6E+7 4.lE+9 1.5E+7 2.lE+9 1.2E+7 1.4E+9 I 132 1.7E+5' l.2E+6 1.9E+5 1.2E+6- 1.5E+5 1.2E+6 1.lE+5 1.2E+6 lh- <
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 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 lA , 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 lD. 6.5E+5 7.!s+8 1.0E+6 3.3E+9 1.2E+6 2.4E+9 8.6E+5 1.8E49 T Inhalation Pathway, units =yj#,7 Food & Ground Pathway, units I"' " V"I 4 I 2-47 Revision P.3 02-28 91 , __ _. ___ a.__. _ u._._2_.,._._.__._ __ _ _ _ _ . _ . _
TABLE P-8 DOSE PARAMETER Rt FOR SECTOR Q Page 8 of 9 Pathway Distance 2.2 miles' San Clemente' Ranch (No Residents) D/Q s 1.4E-9 m-X/Q = 3.3E 7 sec/m Child Teen Adult Infant Food & Inhala- Food & Inhala- Food & Inhala. Food & Inhala-Ground tion Ground tion Ground tion Ground
- Radio. tion Pathway Pathway Fathway Nuclide Pathway Pathway Pathway Pathway Pathway 0- 3.BE43 0 2.4E+3 0 1.9E+3 H3 0 0-7.4E+6 6.7E+6 Cr 51 0 0 0- 4.8E46 0-6.lE+8 0- 8.3E+8 -0 8.0E+8 Mn 54 0 -0 0 0- 2.2E+8 0- 2.9E+8 0 2.4E+8 Co.57 0 0-0 3ME+8 0- 5.lE+8 -0 4.7E+8 Co.58 0 0 2.0E+9 0- 3.0E+9 0- 2.7E49 00 60 0 0- 0
-0 3.lE+10 0- 1.2E+10 0- 7.2E+9 >
Sr 89 0
-0 5.8E+11 Sr 90 0- 0 0- 1.3E+12 -0 7.7E+11 0- 0 7.8E+8 0- 1.lE+9 0 9.1E+8 Zr.95 3.lE+8 0 0- 2.4E+8 0- 3.5E+8 -0 Nb 95 0 3.EE+8 0- 3.3E+8 0- 4.5E+8 0- lA Ru.103 0=
0- 0- 2.3E+9 0- 1.4E+9 0 9.5E+8 Te 129m 0
-0 0- 0- 2.4E+10 0- 1.5E+10 0- 9.2E+9 Cs.134 0- 0- 0 9.0E+7 0 5.7E+7 0 3.6E+7 Cs.136 0- 0 2.3E+10 -0 1.3E+10 0- 7.8E+9 ,
Cs.137 0 Ba 140 0- D. 1.lE+8 0- 6.8E4 7 -0 5.3E+7 0- -0 3.3E+8 4.lE+8 0- 3.2E+8 Ce.141 Ce-144 -0 0 0 9.2E+9 0 1.2E+10 0 9.0E+9 1 131 -0 0- 0 4.lE+9 2.lE+9 -0 1.4E+9 I 132 0- 0 0- 6.0E 36 0- 2.6E 36 0- 1.7E-36 16 I .133 0 0- 4.0E ll 0- 1.7E-Il 0- 1.lE-ll 1 134 0- 0- -0 6.lE-37 -0 2.7E 37 0- 1.7E 37 IA I 135 -0 -0 -0 7.0E-35 0 3.lE 35 1.9E-35 IR UN ID 0 -0 0- 2.5E+9 1.7E+9 -0 1.lE+9 c_
- Inhalation Pathway, units "]j'[!"
y Food & Ground Pathway, units I" ' "I L j 2-48 Revision 23 02 28 91
--..n-.mn---, , . - , - - - , , , . - . - - , , _,,,n,.,,-w-_-a..n.., _ . . . , . _ , , , . . , , - , ,, ,, ,,--,n>- - - - - , ~ , , - . - , .
l TAEE 2:.A l DOSE PARAMETER Rj FOR SECTOR Q Pathway San Clemente Ranch Adm. Offices Distance 2.5 miles' X/Q 2.7E 7 sec/(m ) D/Q = 1.1E-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 Nuclide pathway Pathway Pathway Pathway Pathway 0- 0- 0- 4.3E+2 1.9E+3 H -3 0-0- 0- 4.9E+3 8.3E+6 Cr 51 0 0- 0- 4.8E45 1.3E+9 Mn-54 0- Ot 0- 0- 0- 1.3E45 3.6E+8 Co-57 Co 58- 0- 0- 3.2E+5 8 Co 60 0- 0- 0- 2.0E+ti 6.0E+d 1.0E 0- 0- 0- 4.8E+5 7.2E+! Sr 89 0-5.8E11 Sr 90 0 3.4E+7 0- 0- 6.1E+5 9.9E+8 Zr-95 3.6E48 Nb 95 0- 0- 0- 1.7E+5 0- 0- 0- 1.7E45 4.2E+8 lb Ru-103 Te-129m 0- 0- 0- 4.0E45 9.6E+8 0- 0- 2.9E+S 1.2E+10 Cs-134 Cs 136 Cs 137 0 0-5.0E+4 2.lE+5 8,7E+7
.1.1E+10 k
0- 0- 0- 0- 0- 4.4E+5 6.0E+7 Ba 140 Ce-141 0- 1.2E+5 3.2E+8 Ce-144 0- 2.7E+6 9.0E+9 I -131 4.1E+6 1.4E+9 1 -132 0- 0- 3.9E+4 4.2E+ 5 lh I -133 0- 0- 7.4E+5 8.4E+5 I -134 0- 1.0E+4 1.5E+5 [A I -135 1.5E+5 8.6E+5 UN-10 0- 0- 3.0E+5 1.3E+9
-Inhalation Pathway, units "]j',#7 y
Food & Ground Pathway, units I" II""*"#V"I pC1/sec l 2-49 Revision 23 02 28-91 p
JABLE 2-9 DOSE PARAMETER Rj FOR SECTOR R Page 1 of 5 Pathway San Onofre Mgbile Homes Distance 1.2 miles
- 0/0 3.2E 9 m*
X/Q = 5.3E 7 sec/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 Nuclide Pathway Pathway Pathway Pathway Pathway 1.3E43 0- 1.3E+3 , H3 6.5E42 0- 1.lE+3 0 4.7E+6 1.4E+4 4.7E+6 l Cr 51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.lE+4 1.6E+6 1.4E+9 2.0E+6 1.4E+9 1.4E46 1.4E+9 ' Mn 54 1.0E+6 1.4 E49 3.4E+8 5.lE+5 3.4E+8 5.9E45 3.4E+8 3.7E+5 3.4E+8 Co 57 3.8E45 3.8E+8 1.lE+6 3.8E+8 1.3E+6 3.8E48 9.3E45 3.8E+8 g Co 58 7.8E45 2.2E+10 7.lE+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E410 C0 60 4.5E+6 2.2E+4 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr E3 2.0E+6 Sr 90 4.lE+7 1.0E+8 0- 1.1E+8 9.9E+7 2.2E+6 2. 5 E+ 8 2.7E46 2.5E+8 1.8E+6 2.5E+8 Zr-95 1.8E+6 2.5E+8 Nb 95 4.8E+5 1.4E+8 6.lE+5 1.4E+8 7.5E+5 1.400 5.0E+5 1.4E+8 Ru 103 5.5E+5 1 lE+8 6.6E+5 1.lE+8 7.8E+5 1.198 5.0E45 1.1E+8 Ik 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2. 0 E+ 6 2.0E+7 1.2E+6 2.0E+7 Ta 129m Cs-134 7.0E+5 6.8E+9 1.0E+6 6.8E+9 1.1E+6 6.8E+9 8.5E45 6.8E+9 Cs 136 1.3E45 1.5E+8 1.7E+5 1.5E+8 1.9E+5 1.5E+8 1.5E+5 1.5E+8 Cs-137 6.lE+5 1.0E+10 9.1E+5 1.0E+10 8.5E+5 1.0E+10 6.2E45 1.0E410 Ba-140 1.6E+6 2.lE+7 1.7E+6 2.1E+7 2.0E+6 2.lE+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 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E46 1.5E+5 1.2E+6 1.lE+5 1.2E+6 IA I -133 3.GE+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2..lE+6 I -134 4.5E+4 4.5Fr5 5.1E+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E45 IN 2.5E+6 4.5E+5 2.5E+6 I I 135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 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 - y !"
Food & Ground Pathway, units - (m")(mrem /vr) pC1/sec 2-50 Revision 23 02 28 91
TABLE 2 9 l DOSE PAPMETER Rg FOR SECTOR R Page 2 of 5 Pathway Distance 2.3 miles San Clemente' Ranch (No Residents) ^/Q = 1.0E 9 m-' X/Q = 2.0E-7 sec/m Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhal a- Food & Radic- tien Ground tion Ground tion Ground tion Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide H3 3.8E+3 0- 2.4E+3 0- 1.9E+3 Cr 51 0- 0- 0- 4.8E+6 0- 7.4E+6 0- 6.7E+6 Mn 54 0- 6.1E+8 0- 8.3E+8 -0 8.0E+8 Co 57 0- 2.2E+8 0- 2.9E+8 2.4E+8 Co 58 0- 3.3E+8 5.lE+8 4.7E+8 Co 60 2.0E+9 3.0E+9 0- 2.7E+9 Sr 89 0- 0- 3.lE+10 0- 1.2E+10 0- 7.2E+9 Sr 90 1.3E+12 7.7E+11 0- 5.8E+11 Zr-95 0- 7.8E+8 0- 1.1E+9 9.lE+8 Hb 95 0- 2.4E+8 3.5E+8 0- 3.1E+8 Ru 103 0- 0- 3.3E+8 4.5E+8 3.8E+8 lh Te-129m - 2.3E+9 1.4E+9 9.5E+8 Cs-134 0- 2.4E+10 0- 1.5E+10 9.2E+9 Cs-136 0- 9.0E+7 0- 5.7E+7 3.6E+7 Cs 137 2.2E+10 1.3E+10 7.8E+9 Ba-140 1.lE+8 0- 6.8E+7 0- 5.3E+7 "e 141
. 3.3E+8 0- 4.lE+8 3.2E+8 Ce-144 9.2E+9 0- 1.2E+10 9.0E+9 I 131 4.lE+9 2.lE+9 1.4E+9 I -132 6.0E 36 0- 2.6E-36 1.7E-36 IA I -133 4.0E Il 0- 1.7E-11 1.lE-11 I -134 6.lE 37 -U- 2.7E 37 0- 1.7E 37 lA I 135 7.0E 35 0- 3.lE 35 0- 1.9E-35 UN-ID 2.5E+9 1.7E+9 1.1E+9 Inhalation Pathway, units - !"
I" Food & Ground Pathway, units
"{#Y"I e
2-51 Revision 23 02-28-91 l
TABLE 2-9 DOSE 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-10m*' 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 Patnway Pathway Pathway H3 0- 7.4E+2 1.9E+3 Cr 51 -0 0- 8.4E+3 9.5E+6 Mn-54 0- 8.2E+5 1.6E+9 Co-57 I 0- 2.2E+5 4.4E+8 Co-58 1- 5.4E+5 6.9E+8 Co-60 0- 0- 3.5E+6 1.5E+10 Sr-89 0- 8.2E+5- 7.2E+9 Sr-90 5.8E+7 5.8E+11 Zr-95 0- 0- 1.0E+6 1.1E+9 Nb-95 0- 2.9E+5 3.9E*8 Ru-103 ' 2.9E+5 4.4E+8 lb Te-129m 6.8E+5 9.6E+8 Cs-134 -0 . 4.9E+5 1.3E+10 Cs-136 Cs-137
- 0.-
S-0- 8.5E+4 3.6E+5
- .2E+8 1.4E+10 g
Ba-140 0- 0- 7.4E+5 6.5E+7 Ce-141 2.lE+5 3.3E+8 Ce-ld4 -C- 4.5E+6 9.0E+9 a I -l'i 7.0E+6 1.4E+9 I 132 6.7E+4 7.2E+5 [b I -133 1.3E+6 1.4E+6 I -134 1.7E+4 2.6E+5 lk I -135 2.6E+5 1.5E+6 UN-ID 5.0E+5 1.5E+9 Inhalation Pathway; units "C1/m p f" Food & Ground Pathway, units - (m')(mrem /vri pC1/sec 2-52 Revision 23 02-28-91
TABLE 2-9 005E PARAMETER Rj FOR SECTOR R ' Page 4 of 5 Pathway - Sheep Meat Distance - 0.9 miles X/Q - 8.3E-7 sec/m' D/Q - 5.2E 9 m ' Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- food & Ir5ala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Pathway Pathway Pathway Nuclide Pathway Pathway Pathway Pathwa) Pathway 1.5E+0 1.2E+0 7.0E+0 2.1E+0 H -3 0-5.1E+1 1.0E+2 7.9E+1 2.6E+4 Cr-51 7.6E+6 7.8E+2 1.4E+3 7.7E+3 Mn-54 4.7E+3 8.1E+3 2.0E+3 1.9E+6 C? 57 9.7E+3 2.0E+4 5.1E+3 2.1E+6 to-58 3.7E+4 7.3E+4 3.3E+4 1.2E+3 Co-60 5.0E+4 2.6E+4 7.7E+3 3.1E+4 br 29 , 0- 1.0E+6 -0 8.1E+5 5.5E+5 1.3E+6 Sr-9:- 9.7E+3 1.6E+6 Zr-95 2- 6.3E+4 1.1E+5 2.4E+5 4.5E+5 2.8E43 1.6E+6 Nb-95 3 4.2E+5 7.6E+5 2.BE+3 1.9E+6 lb Ru-103 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Te-129.w 1.2E+5 4.7E+3 3.8E+7 S!; y at Cs-134 Cs-136 Cs-137 1.4E+5 5.1E+3 1.3E+5 0-4.3E+3 9.5E+4 8.1E+2 3.4E+3 8.3E+5 5.7E+7 k Ba-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5 9'- 2.4E+3 2.0E+3 7.9E+4 Ce-141 1.5E+3 + 1.8E+4 3.0E+4 4.3E+4 4.3E+5 Ce-!44 I -131 6.6E+5 4.4E+5 6.6E+4 7.0E+5 I -132 6.3E+2 6.8E+3 lA I -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 1 -134 1.6E+2 2.5E+3 th
, I -135 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6
*/
Inhalation Pathway, units
""'1/m!"
pC Food & Ground Pathway, units - (m')(mrem /vri pCi/sec 2-53 Revision 23 1 02-28-91
TABLE 2 D05E PARAMETER Rj TOR SECTOR R ' Page-_5 of 5 4 Pathway Deer Consumeg Distance = 2.2 miles ' X/Q = 1.8E-7 sec/m D/Q-- 8.8E 10 m-Infant Child Teen Adult a Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Ground tion Ground tion Ground Radio- tion- Ground tion Pathway Pathway Pathway Pathway Pathway Nuclide Pathway Pathway Pathway 2.3E+1 3.5E+1 3.9E+1 l H 3- 2.8E+1 5.0E+4 -0 1.0E+5 3.9E+2 3.2E+5 1 Cr-51 3.8E+4 4.1E+7 Mn 54- 7.7E+5 1. 4 E+ t,
-0 4.6E+6 8.0E+6- 1.0E+4 -2.3E+7 Co-57 I 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-58 l 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Co 60 3 lE+7 1
4.9E+7 2.6E+7 3.8E+4 Sr-89 1.2E+9 1.0E+9 8.0E+8 2.7E+6 Sr-90 2.0E+8 6.2E+7 1.lE+8 4.8E+4 Zr 95 1.4E+4 8.2E+8 Nb-95 0- 2.3E+8 4.5E+8
-Ru-103 4.2E+8 7.5E+8 1.4E+4- 1.3E+9 (E
-Te 129m 5.9E+8 4.5E+8 3.2E+4 6.4E+8 1.4E+E 1.2E+8 2.3E+4 3.4E+8 Cs-l?4-Cs-136 - 5.lE+6 4.2E+6 4.0E+3 9.5E+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-Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 1.8E+7 2.9E+7 2.lE+5 4.9E+7-
- 1 -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 1 -132- - 3.lE+3 3.4E+4' 10 1 -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 11-134 =8.2E+2- 1.2E+4 16 I -135.- 1.1E-15 6.3 E-'16 1.2E+4 6.9E+4 UN ID - 1.1E+8 9.4E+7 2.4E+4 -1.4E+8-Inhalation Pathway, units = "C1/m7 Food & Ground Pathway, units - (m')(mrem /vr) pC1/sec 2-54 Revision 23 02-28-91
. . - . , . . . - . - _ . . _ =- - _ - . - - .
TABLE 2-10 1 DOSE PARAMETEi! Rg FOR SECTOR A Page 1 of 3 f I Pathway Camp San Mateo Distance - 3.6 miles
- X/Q = 7.1E-8 sec/m' D/Q - 4.1E-10 m-Child Teen Adult Infant Food & Inhala- Food &
Inhala- Food & Inhala- Food & Inhala- Ground tion Ground tion Ground tion Ground tion Radio- Pathway Pathway Pathway Pathway Pathway Nuclide Pathway Pathway Pathway 0- 1.3E+3 H -3 1.4E+4 4.7E+6 0-Cr-51 1.4E+6 1.4E+9 Mn-54 3.7E+5 3.4E+8 Co-57 0- 3.8E+8 9.3E+5 Co-58 6.0E+6 2.3E+10 Co-60 1.4E+6 2.2E+4 Sr-89 R 9.9E+7 Sr-90 1.8E+6 2.5E+8 Zr 95 5.0E+5 1.4E+8 Nb 95 1.1E+8 lA 0- 0- 5. 0i.+ 5 Ru-103 1.2E+6 2.0E+7 Te-129m 0-8.5E+5 6.8E+9 Cs-134 1.5E+8 1.5E+5 Cs-136 1.0E+10 Cs-137 6.2E+5 1.3E+6 2.lE+7 Ba-140 1.4E+7 Ce-141 3.6E+5 7.8E+6 7.0E+7 Ce-144 1.7E+7 I -131 1.2E+7 1.lE+5 1.2E+6 IA I -132 I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 b I -l?5 4.5E+5 2.5E+6 UN-ID 8.6E+5 7.5E+8 Inhalation Pathway, units - F 2 Food & Ground Pathway, units - (m )(mrem /vri pCi/sec i 2-55 Revisit,n 23 02-28 91
TABl.E 2010 FOR SECTOR A COSE PARAMETER R$ Page 2 of 3 Pathway-Sheep (Meat)' Distance = 0.2 miles X/Q = 6.7E-6 sec/m 0/0 - 5.2E-8 m** Child Teen Adult Infant Food & Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Ground tion Ground tion Ground tion Ground tion Radio- Pathway Pathway Pathway Pathway Pathway Nuclide Pathway Pathway Pathway 1.5E+0 1.2E+0 7.0E+0 2.1E+0 H -3 0-1.0E+2 7.9E+1 2.6E+4 Cr-51 0- 5.lE+1 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 C0-58 0 9.7E+3 2.0E+4 7.3E+4 3.3E+4 1.2E+8 Co-60 3.7E+4 3.lE+4 5.0E+4 2.6E+4 7.7E+3 Sr-89 5.5E+5 1.3E+6 Sr-90 0- -0 1.0E+6 8.1E+5 6.3E+4 1.1E+5 9.7E+3 1.6E+6
- Zr-95 0- 0- 1.6E+6 0- 2.4E+5 4.5E+5 2.8E+3 Nb-95 1.9E+6 lb 4.2E+5 7.6E+5 2.8E+3 Ru-103 's - 7.6E+5 6.0E+5 4.5E+5 4.4E+3 Te-129m 3.8E+7 1.4E+5 1.2E+5 4.7E+3 Cs-134 Cs-136 Cs-137 5.1E+3 1.3E+5 4.3E+3 9.5E+4 8.lEt2 3.4E+3 8.3E+5 5.7E+7 h 5.lE+3 4.3E+3 7.0E+3 1.2E+5 Ba-140 % Ce-141 1.5E+3 2.4E+3 2.0E+3 7.9E+4 1.BE+4 3.0E+4 4.3E+4 4.3E+5 Ce-144 6.6E+5 4.4E+5 6.6E+4 7.0E+5 I -131 6.8E+3 lb I -132 6.3E+2 1.6E-2 8.7E-3 1.2E+4 1.3E+4 I -133 lh I -134 0- 1.6E+2 2.5E+3 1.l'-18 6.4E-19 2.5E+3 1.4E+4 I -135 4.8E+3 4.2E+6 UN-ID 1.lE+5 0- 9.5E+4 Inhalation Pathway, units mrem /yr pC1/m Food & Ground Pathway, units = I*9 IIS"**/VII pCi/sec l
2-56 Revision 23 02-28-91
TABLE 2-10 DOSE PARAMETER R g FOR SECTOR A 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 & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground 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 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn 54 0- 0- 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 4.6E+6 8.0E+6 1.0E+4 ' 2.3E+7 Co-58 0- 9.6E+6 1.9E+7 2.5E+4 4.7E+7 00-60 0- 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 0- 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Hb-95 0- 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 lb Te-129m 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 n Cs-136 5.lE+6 4.2E+6 4.0E+3 9.5E+6 D Cs-137 . 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 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E+6 Ce-144 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 3.1Es 3 3.4E+4 lb I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 lb 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 - !" Food & Ground Pathway, units I" "T**/ vfl pCi/sec 2-57 Revision 23 02-28 91
_ - . - . . - - . . - - -.--~.- - TABLE 2-11 DOSE PARAMETER R j FOR SECTOR 8 Page 1 of'3-Pathway-Sheep (Meat)' Distance - 0.2 miles , X/Q - 6.lE-6 sec/m 0/Q 5.3E 0 m Infant Child I 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 Nuclide Pathway H 1.5E+0 1.2E+0 7.0E+0 2.1E+0-Cr-51 5.lE+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 4.7E+3 8.1E+3 2.0E+3 1.9E+6 Co-58 -9.7E+3- 2.0E+4 5.lE+3 2.lE+6-3.7E+4 - 7.3E+4 3.3E+4 1.2E+8 Co-60 Sr-89 5.0E+4 2.6E+4 7.7E+3 3.lE+4 Sr-90; -1.0E+6 8.lE+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.lE+5 9.7E+3 -1.6E+6 Nb-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 r- Ru-103 4.2E+5 7. 6E+ 5 2.8E+3 1.9E+6 lb Te-129m -
' 0- 6.0E+5 4.5E+5 ~6.4E+3 -7.6E+5 Cs-134 1.4b 5 1.2E+5 4.7E+3 3.8E+7
.Cs-136 - 5.1E+3 4.3E+3 8,1E+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+2 5.7E+7 Ba-140 - 5.1E+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 I 4132 6.3E+2 6.8E+3- (k -
I -133. 1.6E-2 8.7E-3 1.2E+4 1.3E+4 I -1341 . 1.6E+2 -2.5E+3 lb-I -135 'l.lE-18 - S.4E-19 2.5E+3 1.4E+4-UN-ID 1.lE+5 9.5E+4 4.8E<3 4.2E+6 d Inh'alation Pathway, units = yf,F , Food & Ground Pathway, units I*'II""**/V"I
.pCi/sec 2-58 Revision 23 02-28-91
TABLE 2-11 DOSE PARAMETER Rg FOR SECTUR B Page 2 of 3 Pathway Deer Consumer Distance 1.1 miles X/Q 3.4E ? sec/m' D/Q = 2.4E 9 m*' Child Teen Adult Infant Food & Inhala- Food & Inhala- Food & Inhala- Food & In' al a-Radio- tion Ground tian Ground tion Ground tion Ground Pathway Pathway Pathway Pathway Pathway Nuclide Pathway Pathway Pathway 2.3E+1 2.3E+1 3.5E+1 3.9E+1 H -3 3.2E+5 5.0E+4 1.0E+5 3.9E+2 Cr-51 3.8E+4 4.1E+7 Mn 54 7.7E+5 1.4E+6 0- 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-57 9.6E+6 1.9E+7 2.5E+4 4.7E+7 Co-58 7.2E+8 0- 3.6E+7 0- 7.2E*7 1.6E+5 Co 60 3.8E+4 3.1E+7 Sr-89 4.9E+7 2.6E+7 0- 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Sr-90 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Zr 95 8.2E+8 2.3E+8 4.5E+8 1.4E+4 Nb 95 lb Ru-103 4.2E+8 7.5E+8 '. T+4 1.3E+9 5.9E+8 4.5E+8 3.2E+4 6.4E+8 Te-129m 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs 134 5.lE+6 4.2E+6 4.0E+3 9.5E+6 Cs-136 1.3E+8 S.3E+7 1.7E+4 4.0E+8 Cs-137 5.0E+6 4.2E+6 3.5E+4 7.4E+6 Ba-140 Ce-141 1.5E+6 C.4E+6 9.9E+3 4.2E+6 1.8E+7 2.9E+7 2.1E+5 4.9E+7 Ce 144 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -131 lb I -132 3.1E+3 3.4E+4 I -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 jfA 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 - !" . Food & Ground Pathway, units - (m')(mrem /vr) pCi/sec 2-59 Revision 23 02-28-91
TABLE 2-11 DOSE PARAMETER Rg FOR SECTOR B Page 3 of'3 Pathway - Sanitary Landfill ' Distance 2.1 miles' D/Q 1.2E-9-m-X/Q = 1.4E-7 sec/m* Child Teen Adult Infant Food & Inhala- Food & Inhala- Food & Inhala- Food & Inhala-tion Ground tion Ground tion Groard tion Ground Radio- Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide 2.9E+2 H -3 1.1E+6 0- 3.3E+3 Cr 51 3.2E+5 3.2E+8 Mn-54 8.4E+4 7.8E+7 Co-57 2.1E+5 8.7E+7 Co-58 0- 1.4E+6 4.9E+9 Co 60 0- 3.2E+5 4.9E+3 Sr-89 Sr-90 2.3E+7 4.0E+5 5.7E+7 Zr 95 - 3.1E+7 Nb 95- 1.2E+5 1.2E+5 2.5E+7 lb Ru 103 4.5E+6 Te 129m 2.6E+5 0- 1.9E+5 1.6E+9 0 Cs-134 Cs-136 3.3E+4 3.4E+7 b Cs-137 1.4E+5 2.3E+9 2.9E+5 4.7E+6 Ba-140 Ce-141 8.3E+4 3.1E+6 Ce-144 1.8E+6 1.6E+7 I -131 2.7E+6 3.9E+6 I -132 2.6E+4 2.8E+5 % I -133_ 4.9E+5 5.6E+5 I -134 6.8E+3 1.0E+5 lb I -135 1.0E+5 5.8E+5 UN-10 2.0E+5 1.7E+8 Inhalation Pathway, units "T**/ P pC1/m! 2 Food & Grounc Pathway, units - (m )(mrem /vri pCi/sec j 2-60 Revision 23 ' 02-28-91
TABLE 2-12 DOSE PARAMETER R g FOR SECTOR C Page 1 of 5 Pathway Camp San Ono Distance = 8.4E-10 2.6 miles ' m-X/Q=9.2E-8sec/m{re 0/0 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 Nuclide Pathway H -3 -0 1.3E+3 Cr-51 0- 1.4E+4 4.7E+6 Hn-54 1.4E+6 1.4E+9 Co-57 0- 0- 3.7E+5 3.4E+8 Co-58 9.3E+5 3.8E+8 Co-60 6.0E+6 2.2E+10 Sr-89 1.4E+6 2.2E+4 9,9E+7 R Sr-90 Zr 95 0- 1.8E+6 2.5E+8 Nb-95 0- 5.0E+ 5 1.4E+8 Ru-103 5.0E+5 1.1E+8 lA Te 129m -C- 1.2E+6 2.0E+7 Cs-134- 0- 8. 5 E+ 5 6.8E+9 Cs-136 0- 1.5E+5 1.5E+8 Cs-137 -0 6.2E+5 1.0F+10 Ba-140 1.3E+6 2.lE+7 Ce-141 3.6E+5 1.4E+7 Ce-144 7.8E+6 7.0E+7 I -131 1.2E+7 1.7E+7 I -132 1.1E+5 1.2E+6 lA I -133 2.2E+6 2.4E+6 I -134 3.0E+4 4.5E+5 I A-I -135 4.5E+5 2.5E+6 UN-ID - 8.6E+5 7.5E+8 Inhalation Pathway, units = "C / - Food & Ground Pathway, units Im r vr) j 2-61 Revision 23 02-28-91
\
TABLE 2-12 l l l FOR SECTOR C 00SE PARAMETER R$ Page 2 of 5 Pathway - Camp San Onofre Fr. Stn Distance 2.3 miles 0/Q - 1.lE-9 m ' X/Q = 1.lE-7 sec/m' Child Teen Adult Infant Food & Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Ground Ground tion Ground tion Ground tion Radio- tion Pathway Pathway Pathway Pathway Pathway Nuclide Pathway Pathway Pathway 5.2E+2 H3 0- 1.9E+6 5.9E+3 Cr-51 5.8E+5 5.7E+8 Mn-54 1.5E+5 1.4E+8 Co 57 3.8E+5 1.6E+8 C0 58 8.8E+9 0- 2.5E+6 Co-60 0- 5.8E+5 8.9E+3 Sr-89 4.iE+7 Sr-90 7.3E+5 1.0E+8 Zr-95 2.lE+5 5.6E+7 Nb-95 2.lE+5 4.5E+7 (4 Ru-103 4.8E+5 8.lE+6 Te-129m 0- 3.5E+5 2.8E+9 Cs-134 0- 6.0E+4 6.2E+7 O Cs 136 2.6E+5 4.2E+9 B Cs-137 5.2E+5 8.4E+6 Ba-140 5.6E+6 1.5E+5 Ce-141 Ce-144 3.2E+6 2.9E+7 4.9E+6 7.lE+6 I -131 5.lE+5 4.7E+4 lb I -132 8.8E+5 1.0E+6 I -133 I -134 1.2E+4 1.8E+5 [h I -135 1.8E+5 1.0E+6 3.6E+5 3 lE+8 UN-ID Inhalation Pathway, units mrem /yr - pCi/m I"3 II*I'*/Y"I Food & Ground Pathway, units pC1/sec l 2-62 Revision 23 02-28-91
TABLE 2-14 DOSE PARAMETER R g FOR SECTOR E Page 3 of 3 Pathway - Deer Consumer Distance = 1.2 miles X/Q = 3.7E 7 sec/m* D/Q = 8.3E-9 m 2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radic- tion Ground tion Ground tion Ground tior. Ground Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide H -3 2.8E+1 2.3E+1 3.5E+1 3.9E+1 Cr-51 5.0E+4 1.0E+5 3.9E+2 3.2E+5 Mn-54 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 4.6E+6 8.0E+6 1.0E+4 2.3E+7 Co-58 9.6E+6 1.%+7 2.5E+4 4.7E+7 C0-60 3.6E+7 7.2E+7 1.6E+5 7.2E+8 Sr-89 4.9E+7 2.6E+7 3.8E+4 3.1E+7 Sr-90 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Zr-95 6.2E+7 1.1E+8 4.bi+4 2.0E+8 Nb-95 2.3E+'8 4.5E+8 1.4E+4 8.2E+8 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 [h Te 129m 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 n Cs-137 1.3E+8 9.3E+7 1.7E+4 4.0EA8 6 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 1.8E+7 2.9E+7 2.lE+5 4.9E+7 1 -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 3.1E+3 3.4E+4 lh 1 -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 1 -134 8.2E+2 1.2E+4 [A 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 = Food & Ground Pathway, units = (m mrem /vr) pC1/sec 2-71 Revision 23 02-28-91
TABLE 2-15 FOR SECTOR F DOSE PARAMETER R$ Page 1 of 6 Pathway San Onot.e State Park Guard Shack Distance = 0.8 miles' X/Q = 8.lE-7 sec/m* D/Q = 7.lE-9 m-Child Teen Adult Infant Food & Inhala- Food & Inhala- Food & Inhala- Food & Inhala-tion Ground tion Ground tion Ground tion Ground Radio- Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide 3 H -3 7.2E+1 8.2E+2 2.7E+5 Cr-51 8.0E+4 7.9E+7 Mn-54 2.lE+4 2.0E+7 Co-57 5.3E+4 2.2E+7 Co-58 3.4E+5 1.2E+9 Co-60 8.0E+4 1.2E+3 S.-89 5.7E+5 St-90 1.0E+5 1.4E+7 Zr-95 7.8E+6 Nb 95 2.9E+4 Ru-103 2.9E+4 6.2E+6 lb 6.6E+4 1.lE+6 Te-129m Cs-134 0- 4.8E+4 3.9E+8 n Cs-136 8.4E+3 8.6E+6 B Cs-137 3.5E+4 5.9E+8 Ba-140 7.3E+4 1.2E+6 Ce-141 2.1E+4 7.8E+5 Ce-144 4.4E+5 4.0E+6 I -131 6.8E+5 9.8E+5 I -132 6.5E+3 7.1E+4 lb I -133 1.2E+5 1.4E+5 1 -134 1.7E+3 2.6E+4 iA I -135 2.6E+4 1.4E+5 UN-ID 4.9E+4 4.3E+7 Inhalation Pathway, units e ""em/vr pCi/ms Food & Ground Pathway, units = (m')(mrem /vri pCi/sec 2-72 Revision 23 02-28-91
TABLE 2-15 DOSE, PARAMETER R9 FOR SECTOR F . Pathway Beach Concession Distance - 0.9 miles D/Q 6.0E-9 m 2 X/Q--6.9E-7sec/m* Infant Child Teen Adult { Food & Inhalt- Food & Ir.hal a- Food & ! Inhala- Food & Inhala-tion Ground tion Ground tion Ground tion Ground Radio- Pathway Pathway Pathway Nuclide Pt.thway Pathway Pathway Pathway Pathway 1.2E+2 H3 1.3E+3 4.4E45 Cr-51 1.3E+5 1.3E+8 Mn-54 3.2E+7 Co-57 0- 0- 3.5E+4 Co 58 -0 8.7E+4 3.6E+7 5.6E+5 2.0E+9 l Co-60 1.3E+5 2.0E+3 l Sr-89 Sr-90 9.3E+5 Zr-St 1.7E+5 2.4E+7 Nb-95 -0' 4.7E+4 1.3E+7 Ru-103 4.7E+4 1.0E+7 lb 1.lE+5 1.8E+6 Te-129m Cs-134 7.9E+4 6.4E+8 Cs-136 1.4E+4 1.4E+7 Cs-137 5.8E+4 9.6E+8 Ba-140 1.2E+5 1.9E+6 Ce-141 3.4E+4 1.3E+6 > Ce-144 7.3E+5 6.5E+6 I I -131 - 1.lE+6 1.6E+6 I -132 1.1E+4 1.2E+5 lb I -133 2.0E+5 2.3E+5 I -134 2.8E+3 4.2E+4 lk L I -135 4.2E+4 2.4E+5 UN-ID 8.1E+4 7.0E+7 l l I Inhalation Pathway, Units y yr) Food & Ground Pathway, units I" y'c 1 2-73 Revision 23 02-28-91
TABLE 2-15 DOSE PARAMETER R g FOR SECTOR F Page 3 of~5 Pathway - Border Patrol Checkpt. Distance = 1.8 miles X/Q = 2.4E-7 sec/m' 0/Q = 1.8E-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 0- 3.6E+2 H -3 Cr-51 4.1S3 1.3E+6
-0 0- 4.0E+5 3.9E+8 Mn-54 Co-57 0- 1.1E+5 9.8E+7 Co 58 2.6E+5 1.lE+8 1.7E+6 6.1E+9 Co 60 Sr-89 4.0E+5 6.2E+3 Sr-90 2.8E+7 Zr 95 5.0E+5 7.2E+7 Nb-95 1.4E+5 3.9E+7 Ru-303- 1.4E+5 3.lE+7 lb Te 120m 3.3E+5 5.6E+6 Cs-134 2.4E+b 1.9E+9 4.2E+4 4.3E+7 Cs-136 Cs-137 1.8E+5 2.9E+9 %
Ba-140 -C- 3.6E+5 5.9E+6 Ce-141 1.0E+5 3.9E+6 Cc-1?4 2.2E+6 2.0E+7 1 -131 ^ 3.4E+6 4.9E+6 1 -132 u- 3.?E+4 3.5E+5 lh 1 -133 6.lE+5 7.0E+5 1 -134 8.5E+3 1.3E+5 lh 1 -135 1.3E+5 7.2E+5 UN-ID 2.5E+5 2.1E+8 Inhalation Pathway, units - f . 9 Food & Ground Pathway, units = (m )(mrem /vri pCi/sec 2-74 Revision 23 02-28-91
TABLE 2-15 DOSE PARAMETER Rg FOR SECTOR F Page 4 of 5 Pathway - Sheep (Meat)* Distance - 0.5 miles D/Q = 1.7E-8 m ' X/Q = 1.9E-6 sec/m Child Teen Adult infant Food & Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Ground tion Ground Radio- tion Ground tion Ground tion Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide Pathway 1.2E+0 7.0E+0 2.1E+0 H -3 1.5E+0 5.lE+1 1.0E+2 7.9E+1 2.3E+4 Cr 51 7.6E+6 7.8E+2 1.4E+3 7.7E+3 Hn 54 1.9E+6 4.7E+3 8.1E+3 2.0E+3 Co-57 5.1E+3 2.1E+6 Co 58 9.7E+3 2.0E+4 3.7E+4 7.3E+4 3.3E+4 1.2E+8 Co-60 0- 3.1E+4 5.0E+4 2.6E+4 7.7E+3 Sr-89 5.5E+5 1.3E+6 Sr-90 1.0E+6 8.1E+5 6.3E+4 1.1E+G 9.7E+3 1.6E+6 Zr-95 1.6E+6 2.aE+5 4.5E+5 2.8E+3 Nb-95 Ru 103 0- 4.2E+5 7.6E+5 2.8E+3 1.9E+6 (b 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Te-129m 1.2E+5 4.7E43 3.CE+7 Cs-134 1.4E+5 5.lE+3 4.3E+3 8.1E+2 3.3E+5 Cs-136 5.7E+7 1.3E+5 9.5E+4 3.4E+3 Cs-137 1.2E+5 5.1E+3 4.3E+3 7.0E+3 Ba-140 7.9E+4 1.5E+3 2.4E+3 2.0E+3 Ce-141 4.3E+5 1.8E+4 3.0E+4 4.3E+4 Ce-144 7.0E+5 6.6E+5 4.4E+5 6.6E+4 I -13) 6.3E+2 6.8E+3 Ib I -132 0- 0- ' 1.6E-2 8.7E-3 1.2E+4 1.3E+4 I -133 lh
-I -134 1.6E+2 2.5E+3 1.1E-18 6.4E-19 2.5E+3 1.4E+4 I -135 4.2E+6 UN-ID 1.1E+5 9.5E+4 4.8E+3 P
Inhalation Pathway, units = Food & Ground Pathway, units I*'IISP'*/YPI pCi/sec 2-75 Revision 23 1 02-28-91
Ig lE 2-15 I DOSE PARAMETER Rg FOR SECTOR F Pathway Deer Consumer Dista'nce 1.4 miles' ' D/Q 2.3E 9 m-X/Q 3 0E-7 sec/m' Child Teen Adult Infant Food & Inhal a- Food & Inhala- Food & Inhala- Food & Inhala- Ground tion Ground tion Ground tion Ground tion Radio- Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide 2.3E+1 3.5E+1 3.9E41 H -3 2.8E+1 3.2E+5 5.0E+4 1.0E+5 3.9E+2 Cr-51 3.8E+4 4.lE+7 Mn-54 7.7E+5 1.4E+6 8.0E+6 1.0E+4 2.3E+7 Co 57 4.6E+6 4.7E+7 9.6E+6 0- 1.9E+7 2.5E+4 Co 58 1.6E+5 7.2E+8 Co 60 3.6E+7 7.2E+7 4.9Ev7 2.6E+7 3.8E+4 3.1E+7 Sr-89 2.7E+6 1.2E+9 Sr-90 1.0E+9 8.0E+8 6.2E+7 1.1E+8 4.8E+4 2.0E+8 Zr-95 8.2E+8 Nb-95 2.3E+8 4.5E+8 1.4E+4 4.2E+8 7.5E+8 1.4E+4 1.3E+9 lb Ru-103 6.4E+8 5.9E+8 4.5E+8 3.2E+4 Te-129m 3.4E+8 Cs-134 1.4E+8 1.2E+8 2.3E+4 Cs-136 5.lE+6 4.2E+6 4.0E+3 9.5E+6 Q 9.3E+7 1.7E+4 4.0E+8 D Cs-137 1.3E+8 5.0E+6 4.2E+6 3.5E+4 7.4E+6 Ba-140 4.2E+6 Ce-141 1.5E+6 2.4E+6 9.9E+3 1.8E+7 2.9E+7 2.1E+5 4.9E+7 Ce-144 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -131 lb I -132 3.1E+3 3.4E+4 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -133 I -134 8.2E+2 1.2E+4 lb I -135 1.1E-15 6.3E-16 1.2E+4 6.9E+4 UN-10 1.lE+8 9.4E+7 2.4E+4 1.4E+8 mrem /vr Inhalation Pathway, units gC1/mi Food & Ground Pathway, units - (m')(mrem /vr) pC1/sec 2-76 Revision 23 C2-28-91
TABLE 2-16 l DOSE PARAMETER R g FOR SECTOR G ~ Page 1 of 4 Pathway - San Onofre State Beach Campground Distance = 0.8 miles X/Q = 7.7E-7 sec/m* D/Q - 3.9E-9 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 H -3 8.0E+1 1.4E+2 1.6E+2 1.6E+2 Cr 51 1.6E+3 5.7E+5 2.1E+3 5.7E+5 2.6Ed 5.7E+5 1.8E+3 5.7E+5 Mn-54 1.2E+5 1.7E+8 1.9E+5 1.7E+8 2.4E+5 1.7E+8 1.7E+5 1.7E+8 Co-E7 4.7E+4 4.2E+7 6.3E+4 4.2E+7 7.2E+4 4.2E+7 4.6E+4 4.2E+7 Co-58 9.6E+4 4.7E+7 1.4E+5 4.7E+7 1.7E+5 4.7E+7 1.1E+5 4.7E+7 Co-60 5.6E+5 2.7E+9 8.7E+5 2.7E+9 1.1E+6 2.7E+9 7.4E+5 2.7E+9 S" 89 2.5E+5 2.7E+3 2.7E+5 2.7E+3 3.0E+5 2.7E+3 1.7E+5 2.7E+3
! ') 5.0E+6 1.2E+7 1.3E+7 1.2E+7 Zr-95 2.2E+5 3.1E+7 2.8E+5 3.1E+7 3.3E+5 3.1 EO 2.2E+5 3 lE+7 Nb-95 5.9E+4 1.7E+7 7.6E+4 1.7E+7 9.3E+4 1.7E</ 6.2E+4 1.7E+7 Ru-103 6.8E+4 1.3E+7 8.2E+4 1.3E+7 9.7E+4 1.3E+7 6.2E+4 1.3E+7 @
Te-129m 2.1E+5 2.4E+0 2.2E+5 2.4E+6 2.4E+5 2.4E+6 1.4E+5 2.4E+6 Cs-134 8.7E+4 8.4E+8 1.3E+5 8.4E+8 1.4E+5 8.4E+8 1.0E+5 8.4E+8 Cs-136 1.7E+4 1.9E+7 2.1E+4 1.9E+7 2.4E+4 1.9E+7 1.8E+4 1.9E+7 ,
. Cs-137 7.5E+4 1.3E+9 1.1E+5 1.3E+9 1.0E+5 1.3E+9 7.7E+4 1.3E+9 i Ba-140 2.0E+5 2.5E+6 2.lE+5 2.5E+6 2.5E+5 2.5E+6 1.6E+5 2.5(+6 Ce-141 6.4E+4 1.7E+6 6.7E+4 1.7E+6 7.6E+4 1.7E+6 4~. 5 E+4 1.7E+6 Ce-144 1.2E+6 8.6E+6 1.5E+6 8.6E+6 1.6E+6 8.6E+6 9.6E+5 8.6E+6 +. I -131 1.8E+6 2.1E+6 2.0E+6 2.1E+6 1.8E+6 2.1E+6 1.5E+6 2.1E+6 I -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 lb - I -133 4.4E+5 3.0E+5 4.7E+5 3.0E+5 3.6E+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 5.5E+4 lA I -135 8.6E+4 3.1E+5 9.8E+4 3.1E+5 7.7E+4 3.1E+5 5.5E+4 3.1E+5 UN-ID 8.0E+4 9.2E+7 1.2E+5 9.2E+7 1.5E+5 9.2E+7 1.1E+5 9.2E+7 Inhalation Pathway, units - f Food & Ground Pathway, units I* " VII 7c 2-77 Revision 23 02-28-91
TABLE 2-16 DOSE PARAMETER R j FOR SECTOR G Page 2 of 4 Pathway - Hwy Patrol Weigh Station Distance = 2.0 miles X/Q - 2.0E-7 sec/m* D/Q - 8.5E-10 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 Nuclide Pathway 2.9E+2 H -3 1.lE+6 Cr 51 3.3E+3 Mn-54 0- 3.2E+5 3.2E+8 Co-57 8.4E+4 7.8E+7 Co-58 2.lE+5 8.7E+7 Co-60 1.4E+6 4.9E+9 Sr-89 3.2E+5 4.9E+3 2.3E+7 Sr-90 i Zr-95 4.0E+5 5.7E+7 Nb-95 1.2E+5 3.lE+7 Ru-103 1.2E+5 1.5E+7 lk Te-129m 2.6E+5 4.5E+6 Cs-134 1.9E+5 1.6E+9 Cs-136 3.3E+4 3.4E+7- () Cs 137 1.4E+5 2.3E+9 1% Ba-140 2.9E+5 4.7E+6 Ce-141 8.3E+4 3.lE+6 Ce-144 1.8E+6 1.6E+7 I -131 2.7E+6 3.9E+6 I -132 2.6E+4 2.8E+5 lh 1 -133 4.9E+5 5.6E+5 I -134 6.8E+3 1.0E+5 lA I 135 0- 1.0E+5 5.8E+5 UN-ID 2.0E+5 1.7E+8 mrem /vr Inhalation Pathway, units pCi/m* 2 Food & Ground Pathway, units - (m )(mrem /vr) pCi/sec 2-78 Revision 23 02-28-91
TABLE 2-16 DOSE PARAMETER Rg FOR SECTOR G Page 3 of'4 Pathway - Sheep (Meat)' Distance - 2.7 miles X/Q = 1.2E-7 sec/m 0/Q - 4.8E-10 r' infant Child Teen Adult 4 Food & Inhala- Food & Inhal a- Food & Inhala- Food & Inhala-Radio- tion Ground 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 2.1E+0 H -3 2.6E+4 Cr-51 5.1E+1 1.0E+2 7.9E+1 Mn-54 7.8E+2 1.4E+3 7.7E+3 7.6E+6 Co-57 0- 4.7E+3 8.1E+3 2.0E+3 1.9E+6 Co-5S 9.7E+3 2.0E+4 5.1E+3 2.1E+6 Co-60 3.7E+4 7.3E+4 3.3E+4 1. 2 E+ 8 3.1E+4 Sr-89 5.0E+4 2.6E+4 7.7E+3 Sr-90 1.0E+6 8.1E+5 5.5E+5 1.3E+6 Zr-95 6.3E+4 1.1E+5 9.7E+3 1.6E+6 Nb-95 2.4E+5 4.5E+5 2.8E+3 1.6E+6 R9-103 4.2E+5 7.6E+5 2.8E+3 1.9E+6 lA Te-129m 6.0E+5 4.5E+5 6.4E+3 7.6E+5 Cs-134 1.4E+5 1.2E+5 4.7E+3 3.8E+7 Cs-136 5.1E+3 4.3E+3 8.1E+2 8.3E+5 O Cs-137 1.3E+5 9.5C+4 3.4E+3 5.7E+7 h Ba-140 5.1E+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 I -132 6.3E+2 6.8E+3 lb 1 -133 1.6E-2 8.7E-3 1.2E+4 1.3E+4 I -134 1.6E+2 2.5E+3 lA I -135 -G- 1.1E-18 6.4E-19 2.5E+3 1.4E+4 UN ID 1.1E+5 9.5E+4 4.8E+3 4.2E+6 P Inhalation Pathway, units - Food & Ground Pathway, units - (m')(mrem /vri pC1/sec l 2-79 Revision 23 02-28-91
IABli 2-16 FOR SECTOR G DOSE PARNiETER R9 Page 4 of 4 Pathway a Deer Consumer Distance - 3.3 miles X/Q = 8.8E-8 sec/m' 0/Q - 3.2E-10 m ' Child Teen Adult Infant Food & Inhala- Food & Inhala- Food & Inhala- Food & Inhala-tion Ground tion Ground tion Ground tion Ground Radio- Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway Nuclide 2.8E+1 2.3E+1 3.5E+1 3.9E+1 H -3 3.9E+2 3.2E+5 Cr-51 5.0E+4 1.0E+5
' 7E+5 1.4E+6 3.8E+4 4.1E+7 Mn-54 .
2.3E+7 4.6E+6 8.0E+6 1.0E+4 Co-57 9.6E+6 1.9E47 2.5E+4 4.7E+7 Co 58 0- 7.2E+8 3.6E+7 7.2E+7 1.6E+5 Co-60 3.8E+4 3.1E+7 Sr 89 -C- 4.9E+7 '< .6E+7 1.0E+9 8.0E+8 2.7E+6 1.2E+9 Sr-90 2.0E+8 6.2E+7 1.1E+8 4.8E+4 Zr-95 8.2E+8 2.3E+8 4.5E+8 1.4E+4 Nb-95 Ru-103 4.2E+8 7.5E+8 1.4E+4 1.3E+9 lb 5.9E+8 4.5E+8 3.2E+4 6.6E+8 Te-129m 3.4E+8 1.4E+8 1.2E+8 2.3E+4 Cs-134 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 Ce-141 1.5E+6 2.4E+6 9.9E+3 4.2E46 Ce-144 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 3.1E+3 3.4E+4 lb 1 -133 1.6E+1 8.6E+0 5.9E+4 6.7E+4 1 -134 8.2E+2 1.2E+4 lb 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 = im')(mrem /vr) pC1/sec l 1 2-80 Revision 23 02-28-91
2.9 TOTAL DO5E CALCULATIONS , 2.9.1- -Total Dose to Most Likely Membes of the Public , The total annual dose or total dose commitment to any member of the public, due to releases of radioactivity and to radiation, from uranium fuel cycle sources within 5 miles of the Site is calculated using the following wxpressions. 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 & lic:uid), whole body (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 mrem respectively.
.1 Annual Total Organ Dose (f0T(organ))
12 2/3 - H D,(organ)=I I D (OG) + D (OL) + D ,(OG) (2-20) TOT 1-1 j-1 j1 j1 j1 ; j Units 1, 2 and 3 1 months 1 - 12** Hs
- NOTE: D j1 (OG) = 0 for bone
**All to be summed over the most recent 12 months, where:
n (2-21) D (OG) - K I C)IRik j Wk; i - each isotope in j1 11 specific organ category K - 3.1688E-2 V' ,""c 2-81 Revision 21 02-15-90
2.9 TOTAL DOSE CALCULATIONS (Continued) 2.9.1 Total Dose to Most Likely Member of the Public (Continued) n number of isotopes in the specified organ category ,
- total particulate gas curies released for the month C) j IRik Wk controlling location factors from 00CM Tables 2-6, Units 1 and 2/3 D(OL) = liquid orvan dose for the specified organ in mrem for the j1 month. ineference ODCM Units 2/3 (1-19), Unit 1 (1-13))
DH8(OG) - gas organ dose form tritium in mrem for the month, ji (Note: H' bone contribution - 0)
.2 - pnnual Total Whole Body Dose D TOTE 12 2/3 -
D (WB)= I I D (WBL) + DH8(OG)-+ 0.9 D (7)+0(Direct); (2-22) TOT 1-1 j1 j1 j1 j1 j - Units 1, 2 and 3 1 - months 1 - 12*
*To be summed over the most recent 12 months.
i where: l D jl(WBL) =(Referenceliquid whole ODCMbody organ Units doseUnit 2/3 (1-19), in arem 1 ODCM for(1-13)) the whole month
~DH8(OG) = gas organ dose from tritium in mrem for the month.
L ji (from(2-21)) l D(y)
- gamma air dose in mrad for the month- .
l ji 0.9 converts mrad to mrem.- L [ Reference ODCM Units 2/3 (2-14), Unit 1 ODCM (2-10)]. 4 n D (Direct) = I I max [D(beach)4) 1-1 D(bkgd)4 .0342 (2-23) j-1 n i - for all TLDs per quarter j = for Quarters 1-4 2-82 Revision 21 02-15-90
2.9 TOTAL DOSE CALCULATIONS (Continued) 2.9.1.2 Annual Total Whole Body Dose JTOT.(ES.). (Continued)
- Direct Radiation The direct radiation levels are evaluated most recently using cadmium covered TLDs. The TLDs are placed at 59 locations around the site. The average dose from TLDs 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 hours, or 8 hours for landward occupancy, yr yr D
.3 Annual Total Thyroid Dose TOT (THYROID) l 12 2/3 - -
D (THYROID) = I I (D (OG) + D (OL) ; (2-24) l TOT- 1-1 j-1 j1 j1 ! j = Units 1, 2 and 3 1 - months 1 - 12*' L)
*To be summed over the most recent 12 months, where:
D (OG) - thyroid organ dose from gaseous iodine for the month j1 in mrem. (from 2-21) , l L D (OL) = liquid thyroid organ dose for the month in mrem. L ji (Reference ODCM Units 2/3 (1-19), Unit 1 ODCM (1-13)) o l 2-83 Revision 21 02-15 90
3.0 PROJECTED DOSES 3.1 Liquid Dose Projection ~ , . The methodology used for projecting a liquid dose over 31 days for Specification 1.3.1 is e.s follows: ,
- 1. Determine the monthly total body and organ doses resulting ,
from relecses 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 Dose Projection The methodology used for projecting a gaseous dose over 31 days for Specification 2.4.1 is as follows:
- 1. Determine the monthly gamma, beta and organ dose resulting from releases during tiie previous twelve months.
- 2. Projected dose = Previous 12 months' dose divided by 12 for the gamma, beta and organ doses.
l 3-1 Revision 22 08-02-90
4.0 E0VIPMEtE 4.1 RADIDACTIVE L1001D EFFLUENT MONITORING INSTRUMENTATION SPECIFICATI0li 4.1.1 1he radioactive liquid effluent monitoring instrumentation channels shown in Table 4-1 shall be OPERABLE with their alarm / trip 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. ARL]CABILITY: 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 ftr greater than 30 days, explain in the next Semiannual Radioactive Ef fl.ient Release Report why the inoperability was not correc.ted in a ',imely manner,
- c. With less than the minimum number of Iadioactive liquid effluent monitoring instrumentation channels O9ERABLE and either the appropriate ACTION items in Table 4-1 ~t taken or the necessary surveillances not performed at the specified frequency prescribed in l Table 4-2, an INVESTIGATIVE REPORT shall be prepared which identifie the cause(s) for the event and defines the corrective actions to be taken to preclude recurrence of the event.
SURVEILLANCE RE0VIREMENTS
.1 Each radioactive liquid effluent monitoring 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 structure.
4-1 Revision 23 1 1 02-28-91
- q. TA E 4-1 RADI0 ACTIVE L10UI(tEFFLUENT~ MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRLME!H?. - OPERABLE ACTION
- 7. GROSS RADIGACTI*ilTY MONITORS PROVIDING ALARM 4 TERMINATION OF Ei. EASE
- a. Liquid Radwaste Effluent Line - 2/3 RT-7813 1 28
- b. Steam Generator B1cadown'(Neutralization Sump),
full Flow Condensate Prlisher Effluent Line - 2(3)RT-7817 1 29 .;
-l
- c. Turbine Wi.t -Supps Effluent Line - 2(3)RT-7821
~ 1 30
- d. Steam GeneratGr (E088). Blowdown Effluent L..se - 2(3)RT6759- 1 29
- e. Steam Generator (E089) Blowdown Effluent
^
Line - 2(3)RT6753 1 29
- 2. FLOW RATE MEASUREMENT DENICES-
- a. Liquid Radwests Effluent' Line 1 31
- b. Steam Gener4toi B1oudown -(Neutralization Sump),
Ft91 Flow Condensate Polisher Effluent' Line 1 31
- c. Steam Generator (E086) Blowdown Bypass Effluent Line 1 31
- d. Steam Generator (E089) Blowdown Bypass Effluent Line 1 31 i
L
--l 4-2 Revision 22 08-02-90 :
i
~
, y y &-u.< w u. _>p oeme,- y a- ~- y-
TABLE 4-1 (Coatinuedl TABLE NOTATION , ' ~ ' ~
- Monitor Recorders are not required for the Operability of the monitor,
- providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based upon surveillance requirements) and isolation function (if appi: cable), the loss of the recorder does not render the monitor inoperable.
ACTION 28 - With the number of channels OPERABLE less that required by the Minimum Channels OPERABLE requirements, effluent releases may continue provided that prior to initiating a release:
- a. At least two independent camples are analyzed in accordance with Specification 1.1.1 and
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculation and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathwsy.
ACTION 29 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gama) 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 I-131;
- b. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/ gram DOSE EQUIVALENT I-131; or
- c. Lock closed valve HV-3773 and divert flow to T-064 for processing as liquid radwaste.
ACTION 30 - With the :. umber of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours, grab samples are collected and analyzed within 4 hours of collection time for gross10 at least radioactivity (/ml or lock closed valve S22U19-MUO77 orbeta or g microcuries 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 may be used to estimate flow. 4-3 Revision 22 OB-02-90
i .b~ l , in8LE 4-2 RADIORCTIVE LIQUID. EFFLUENT NMITORIM INST 180TATION SUFiVEILUINCE REOUIRDfENTS CHMMEL l CHMEEL SOURCE CMMNELS FUNCTIOML + INSTIMENT** CHECK CECK. CALIBRATI9d TEST _
- 1. GROSS BETA OR GNOWL RADI0 ACTIVITY NOMITORS
, PNOVIDING AUUBE MS AUTORRTIC TElWIIMTION OF RELEASE
- a. Liquid Radmaste Effluents Line -
! 2/3 RT-7313 D P R(2) Q(1) 1-i b. Steam Generator 81oudoun (Neutralization Sump), ' i Full Flow Condensate Polisher Effluent Line - 2(3)RT-7817 D M R(2) Q(1) !
- c. Turbine Plant Sump Effluent Line -
- j. 2(3)RT-7821 D M R(2) Q(I)
! d. Steam Generator (E088) Bloueown Bypass l Effluent Line - 2(3)RT-6759. O M R(2) Q(1) l e. Steam Generator (E089) 81oudoun Bypass Line - 2(3)RT6753 D M R(?' Q(I) t l l 2. FLOW RATE M ASUREMENT DEVICES i
- a. Liquid Radmaste Efn ueet Line D(3) N.A R Q !
i ! b. Steam Generator 81oudoun (Neutralization Samp), ! Full Flow Condensate Polisher Effluent Line D(3) N.A R Q !
- c. Steam Generator (E088) Blowdown Bypass !
Efn eent Line N.A D(3) R Q i d. Steam Generator (E089) 81oudoun Bypass i Effluent Line D(3) N.A R Q
- 4-4 Revision 22 08-02-90 l -
.. .. , = - ,, , . _ , . ~ - .-
. , , . . -- . ~ . -- .,, -
j . l TABLE 4 2 (Continued) e IABLE NOTAT10E
- ** Monitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become a inoperable As long as the monitor has indication, alarmcapab(i.e.,feedbacksignal).ility(ifapplicable),properresponse(basedupo requirements) and isolation function does not render the monitor inoperable (if applicable), the loss of the rec i
i The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of (1) effluent path isolation closure and Control Room alarm annunciation if j any of the following conditions exist:* j 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
(2) The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These 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 reiease CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made.
*If the instrument controls are not in the operate mode, procedures shall require that the channel be declared inoperable.
l l l l 45 Revision 22 08 02-90
~- . .
4.0 EOUIPMENT l 4.2 RADIDACTIVE GASEOUS EFFLUENT MONITORING IMTRUMENfATION SPECIFICATION 4.2.1 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 alarWtrip setpoints of these channels shall be determined in accordance with ODCH. APPLICABillTY: At all times ACTION:
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.
- b. With less than the minimum number of radiotetive 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, additionelly, than 30 days, explain in the(next Semiannual Radioactiveif the ino Effluent Release Report why the inoperability was not corrected in a timely manner,
- c. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE and either the appropriate ACTION items in Table 4 1 not taken or the necessary surveillances not performed at the specified frequency prescribed in Table 4-2, an INVESTIGATIVE REPORT shall be prepared which identifies the cause(s) for the event and defines the corrective actions to be taken to preclude recurrence of the event. l SURVEILLANCE RE0VIREMENTS
.1 Each radioactive gaseous effluent monitoring 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 4.
4-6 Revision 23 02-28-91
.JLE 4-3 L l RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRWlENTATION i
MINIMUM CHANNELS
- INSTRLMENT*** OPERABLE APP 1ICABILITY ACTION
! 1. WASTE GAS HOLDUP SYSTEM i
- a. % 1e Gas Activity Monitor -
Providing Alarm and Automatic Termination of Release - I'
- 35
- 2/3 RT-7808, 2 RT-7865-1 mr i 3 RT-7865-1 i b. Process Flow Rate Monitoring Device 1
- 36 3-
- 2. CONDENSER EVACUATION SYSTEM -
- a. Noble Gas Activity Monitor - 2(3)RT-7818 or 2(3)RT-7870-1 1
** 37
- b. Iodige Samplar 1 ** 40
- c. Particulate Sampler I ** a0 i d. Associated Sample Flow Measuring Device I ** 36 ,
i e. Process Flow Pate Monitoring Device 1(1)
** 36
- 3. PLANT VENT STACK
- a. Noble Gas Activity Monitor - 2/3 RT - 7808, 2RT-7865-1 1
- 37 or 3RT-7865-1 '
! b. Iodine Sampler . 1
- 40
- c. Particulate Sampler 1 49
- d. Associated Sample Flow Measuring Device 1
- 36 i
- e. Process Flow Rate Monitoring Device
- 36
, 1(2)
- 4. CONTAllWIENT PURGE SYSTEM t
- a. Noble Gas Activity Monitor - Providing Alans and Automatic !
Tennination of Release'- 2(3)RT-7828, or 2(3)RT-7865-1 1
- 38 l
- b. Iodine Sampler I 40 Particulate Sampler
- i c. 1 40 .
! d. Process Flow Rate Monitoring Device 1 36 i Associated Sample Flow Measuring Device *
- e. 1 36 4-7 Revisten 22 !'
08-02-90
^
I t i . !
H
}
TABLE 4 3 (Continued) ! TABLE NOTATION . ;
- At all times. .
^
** MODES 1-4 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, .
Providing the inoperable recorder does not cause the monitor to become
. inoperable (i.e., feedback si nal). As long as the monitor has triication, alarm capability if applicable), proper response (based upon ,
surveillance requirements) an isolation function (if ap>11 cable), the loss of the recorder does not render the monitor inoperaale. . (1) 2(3)RT 7818 is not equipped to monitor process flow. If another means of , continuously monitoring process flow is not available, tVn comply with 4 ACTION 36. , 2/3 RT 7808 is not equipped to monitor process flow. .!f 2RT 7865 or i (2) i 3RT 7866 is not available to continuously monitor plant vent stack flow, ' then comply with ACTION 36. ACTION:35 - With the number of channels OPERABLE 1ess than required by the i MinimusChannelsOPERABLErequirement,thecontentsofthetank(s) . may be released to the environment provided that prior to initiating the release: , 4
- a. f.t least two independer t senples 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 lineupt
.0therwise, suspend releases of radioactive effluents via this :
pathway. ACTION 36 - With the number of channels OPERABLE'.less than required by the , Minimum Channels OPERABLE requirement, effluent releases via this ; pathwty may continue provided the flow rate is estimated at least once per 8 hours. System design characteristics may be used to . estimate flow.
~
ACTION 37-- With the number of channels 0PERAB'LE less than required by the -- Minimum Channels OPERABLE requirement, effluent releases via this 1 pathway may continue provided grab samples:are taken at least once per 12 hours'and these samples are analyzed for gross activity within 24 hours.
-ACTION # With the number of channels OPERABLE 1ess than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.
- ACTION 39 - Remaining in Technical Specifications.
48 Revision 22 08 02-90
TABLE _4 3 fContinued) f 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 21. l 49 Revision 22 08-02-90
m8LE 4-4 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRiffENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE FOR WHICH CHANNELS FUNCTIONAL SURVEILLANCE CHANNEL SPURCE CHECK - CALIBRATION TEST IS REQUIRED. INSTRUdENT**' CHECK-
- 1. WASTE GAS HOLDUP SYSTEM _
- a. Noble Gas Activity Monitor -
Providing Alarm and Automatic Tensinatten of Release - " 2/3 RT-780t', 2RT-7865-I,
- 3RT-7865-1 P P R(3) Q(1)
- b. Process F14e Rate Monitoring
- Device P N.A R Q
- 2. CONDENSER EVACUATION SYSTLA
- a. Noble Gas Activity Monitor - **
l 2(3)RT-7818,2(3)RT-7870-1 D M R(3) Q(2) ** Iodine Sampler W N.A N.A N.A
- b. N.A **
- c. Particulate Sampler W N.A N.A l d. Associated Sample Flow **
Measuring Device D N.A R Q
- e. Process Flow Rate Monitoring **
Device (2(3)RT-7870-1) D N.A R Q I i 4-10 Revision 22 08-02-90
reBLE 4-4 (Continued) RADI0ACTITt LIQU_ID EFFLUENT MONITORING INSTRUNENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODE FOR WHICH i CHANNEL FUNCTIONAL SURVIILLANCE CHANNEL SOURCE TEST IS REQUIRED-CHECK CHECK CALIBRATION _ INSTRUMENT ***
- 3. PLANT VENT STACK
- a. Noble Gas Activity Monitor - D M R(3) Q(2}
2/3 RT-7808, 2RT-7865-1,- 3RT-7865-1
- W N.A N.A N.A
- b. Iodine Sampler N.A Particulate Sampler W N.A N.A c.
- d. Associated Sample Flow
- N.A R Q Measuring Device D
- e. Process Flow Rate Monitoring
- D N.A R Q Device
- 4. CONTAIlffENT PURGr SYSTEM
- a. Noble Gas Activity Monitor -
Providing Alarm and Automatic Tenuination of Release - Q(1) 2(3)RT-7828,2(3)RT-27865-1 D P(4) R(3)
- W N.A N.A N.A
- b. Iodine Sampler N.A Particulate Sampler W N.A N.A c.
- d. Process Flow Rate Monitoring
- D N.A R Q Device
- e. Associated Sample Flow
- D N.A R Q Measuring Device 4-11 Revision 22 08-02-90
-.. . . - . - - - . - - . -- .~ .. - - . - - - . - -
P TABLE 404 (Continued) TABLE NOTATION ,
- At all times.
** Mooe., l$4 with any mhin steam isolation valve and/or any main steam isolating bypass valve not fully closed.
*** Honitor kecorders tre not required for the Operability of the monitor, pituiding tho inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal). As lon P.s the monitor has indication, alarm capability (if applicable , proper response (based upon sutveillance requirements) and isolation fu ction (if applicable), the
' loss of the recorder does not render the monitor inoperable. (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation closure and control room alarm annunciation if any of the following conditions exist:#
- 1. Instrumentindicatesmeasuredlevelsabovethealarm/t-ipsetpoint.
- 2. Circuit failur2.
- 3. Instrument indicates a downscale failure.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:f ,
- 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 more of the reference standards certified by the National Bureau of Standards or using stancards that have been obtained from sup)11ers.that participate in measurement assurance activities with NBS. Tiese standards shall permit calibrating the system over Its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.- (4) Prior to each release and at least once per month.
#If 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
4.3 OPERABILITY OF RAD 10ACT!YE WAITE E511PMENT , The flow diagrass' defining the treatment paths and the components of the
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-4 2RT-7865-1 ,
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is j. Ventilation Exhausts g
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~
_- 4 Radioactivity Monitor. . i 2 and 3. figure 4'-6 Release pathways and monitors of radioactivek gaseous effluents for SO
'RT-7865 can be aligned to either containment purge or the plant vent stac (1) YSTEMS
, FIGURE 4-6.50NGS 2 & 3 RADIDACTIVE CASEOUS 18ASTE TREATMENT S
. Revision 22
.4-15 08-02-90
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- aus si rvante to 02Gs 21 SPECstsC rorNts S toCasaro t0 Cats 0NS Ct0INrMG Cit Astser0 9 A CKtt r SectrN0 9U NE FIGURE 4-7 SOLID WASTE IIANDLING Revision 21 4-16 02-15-90 e-
_7. _ _ 5.0 RADIOLOGICAL ENVIROWlENTAL NON!TORING. l 5.1 llopiterina Procram SPECIFICATION 5.1.1 The radiological environmental monitoring program shall be
- conducted as specified in Table 51. The requirements are applicable at all times.
8,r0LICABI'I?ti At all times ACTIONi I 1
- a. Should the radiological environmental monitoring program i 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 Comission, in the Annual (
Radiological Operating Report (see Section 5.4), a description of the reasons for not conducting the program ; i as required and the plans for preventing a recurrence.
- b. .Should the level of radioactivity in an environmental ,
sampling medium exceed the reporting levels of Table 5 2 when averaged over any calendar quarter, in lieu of any ! other report required by Technical Specification (s) 6.9.1, prepare and submit to the Commission, within 30 days from ' the end of the affected calendar quarter a Report pursuant
'c to Technical Specification (s When more than one of the radionuclides in 5Table) 6.9.1.13.
2 are detected in the sampling medium, this report shall bc submitted if: : concentration (1) + concentration (21- + . . 2 1.0 limit level-(1) . limit 'evel (2)
- c. When radionuclides other than those in Table 5 2 are '
detected and are the result of plant affluents, this report shall be submitted:if the potential annual-dose to an . individual is equal-to or
.-limits of Specification (s) greater than2.3.1, 1.2.1,-2.2.1.or the calendar as- year appropriate. This report is not required-if the measured.
Llevel of radioactivity was-not the. result.of plant: effluentsi-however, in such an event,tthe condition shall i be reported and described in the Annual Radiological 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- 11eu of any other - report required by Technical Specification ~6.9.1, prepare-and submit to the commission 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.
- The locations from which samples were unavailable may then- t be deleted from those required by Table 5-1, provided the .
locations from which the replacement samples were obtained are added to the environmental monitoring progran as replacement locations. 1 51 Revision 22
- 08 02-90..
- a. = =-.-- . ~ , . - - - - . . . a...- - - . - - .. . - . . - .
' 5.0 RADIOLC:lCAL DfVIRONMENTAL NON!TORING (Continued)
SURVEILLANCE REQUIREMENTS
.1 The radiological environmental monitoring samples shall be collected pursuant to Table 5 1 from the locations given in 1
-- Tables 5 4 and 5 5 and Figure 51 and shall be analyzed pursuant to the requirements of Tables 5 1 and 5 3. ,
l l l 1 1
+
e l 5-2 Revision 22 08 02-90 l
IABLE 5-1 RADIOLOGICAL ENVIR0 MENTAL MONITORING PROGRAN Exposure Pathway Number of Samples Sampling and and Sample locations a Collection Frecuencri Type and Frecuency of Analyses and/or Sample Samples from at least Continuous operation Radioiodine cartridge. Analyze
- 1. AIRBORNE at least once per 7 days for I-131.
Radiciodine 5 locations of sampler 3 samples from offsite with sample collection Particulate sampler. Analyze for and Particulates locations (in different as required by dust gross beta radioactivity 2 24 hours sectors) of the highest loading, but at followingfiltgrchange. Perform calculated annual average onceper7 days.jeast gama isotopic analysis on each ground level D/Q. sample when gross beta activity is
> 10 times the yearly mean of control 1 sample from the vicinity samples. Perform gama isotopic of a community having the analysis on composite (by location) the highest calculated sample at least once per 92 days.
annual average ground-level D/Q. . I sample from a control loca-lion 16-30 La (10-20 miles) distant and in the least pre-valent wind direction C At least . 'per Gama dose. At least once per 92 days.
- 2. DIRECT At least 30 locations includ-RADIATION 8 ing an inner ring of stations 92 days.
In the general area of the . site boundary and an outer ring approximately in the 4 to 5 mile rar.ge from the site with a station in each sector of each ring. The balance of the stations are in special interest areas such as popula-tion centers, nearby residences, schools, and in 2 or 3 areas in serve as control stations. 5-3 Revision 21 02-15-90 . O
IABLE 5-1 (Continued) RADIOLOGICAL Uffil10lWIDITAL NORITORING PROGRAN Exposure Pathway Number of Samples Sampling and __and/or Sample and Sample Locationsa Collection Fr m ..cya Tree and Frecuency of Analyses 36 WATERBORNE
- a. Ocean 4 locations At least once per Gaussa isotspic analysis of each month and composited f monthly sample. Tritium analysis
. quarterly of composite sample at least once per 92 days.
- b. Drinking 2 locations Monthly at each Gasuna isotopic and tritium location.- analyses of each sample.
, c. Sediment 4 locations At least once per Gasuna isotopic analysis of each ! from 184 days. sample. i Shoreline 6
- d. Ocean 5 lxations At least once per Gamma isotopic analysis of each Botton 184 days. sample.
Sediments 5-4 Revision 22 08-02-90 pw ,,_1.. _ ._.. -- . _ . . - - - - , - _ . . , -
TABLE 5 (Continued)- WIOLOGICAL EMIRWWENTAL MITORIM PRBERAR Exposure Pathway Number of Samples Sampling and i and/or Sample and Samole Locations * ' Collection Fre w .;va Twee and Fr;_ ;v of Analyses
-4. INGESTION
'3 locations-
~
- a. Nonmigratory- One sample in season, Gamma isotopic analysis on Marine . or at least once per edible portions.
Animals < 184 days'if not seasonal. One sarple of each of the follow-ing species:-
- 1. Fish-2 adult species such as perch or-si. 40.;ad.
- 2. Crustaceae-such as crab or lobster.
- 3. Mollusks-such as limpets, seahares or class.
- b. Local Crops 2 locations Representative Garza isotopic analysis on edible vegetables, normally portions semiannually and I-131 1 leafy and I fleshy analysis for leafy crops.
collected at harvest time. At least 2 vegetables collected - semianegally from each location. 5-5 Revision 21 02-15-90
-. _ , - _ ... - - . - . , -.---..a -
------.s.,
.g ABLE 5-1i (Continued)'
TABLE 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 of this' sample is to obtain background information.. '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 severs 1 should be mounted in series to prevent loss of fodine.
- e. 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 may be used in place of, or in addition to, integrating dosimeters.
For the purpose of this table, a thermoluminescent desteeter may be considered to be one phosphor and two or more phosphors in a packet may be 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).
a 5-6 Revision 22 08-02-90 m._m_m---- _m4_,___ , .
-TAbtE 5-2 REPORTING LEVELS FOR RADIGACTIVITY CONCDmtATIONS IN DIVIROINENTAL SAWLES Reporting Levels Airbo m Particulate Water or Gases Marine Anisals local Crops Anilysts (pC1/1) (pci/a*) (pci/Kg, wet) (pCf/Kg, wet}
i H-3 2 x 10*(a) Mn-54 1 x 10' 3 x 10* Fe-59 4 x 10' 1 x 10* Co-58 1 x 10' 3 x 10' Co-60 3 x 10' 1 x 10' Zn-65~ 3 x 10' 2 x 10' Zr-Mb-95 4 x 10' I-131 2 0.9 1 x 10' Cs-134 3G 10 1 x 10' 1 x 10' Cs-137 50 20 2 x 10' 2 x 10' Ba-la-140 2 x 10' (a) For drinding water samples. This .is de CFR Part 141 value. 5-7 Revision 21 02-15-90 ,
.. -- __ - . . _ _i _______._______
TABLE 5-3 a,c MAIIMUN VALUES FOR THE LOWER LIMITS OF DETECTION (LLJD Airborne Particulate sedinent or Gases Marine Animals local Crops Water (pCf/kg, dry) Analysis (pCi/1) (pC1/m") (pC1/Kg, wet) (pCi/Kg, wet) gross beta 4 1 x 10 ' H-3 2000 Mn-54 15 130 j ' Fe-59 30 260
)
130 l 00-58, 60 15 ! i In-65 30 260 Zr-95 30 Mb-95 15 60 I-131 Ib 7 x 10 5 60 150 Cs-134 ' 15 5 x 10
- 130 80 180 ;
Cs-137 18 6 x 10
- 150 Ba-140 60 La-140 15 5-8 Rettston 21 02-15-90
jag E 5-3 (Continued) TABLE NOTATION
- a. The 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 'real' signal.
Foraparticularmeasurementsystem(whichmayincluderadiochemical separation): , 4.66 s l LLD . b 4 Ee V e 2.22 x 10' e Y e exp (Aot) I where: LLD is the 'a priori" lower limit of detection e t 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), Eisthecountingefficiency(ascountspertransformation), V is the sample size (in units of mass or volume), 2.22 x 10' is'the number of transformations per minute per microcurie, . Y is the fractional radiochemicci yield (when applicable), A is the radioactive decay constant for the particular' radionuclide, and at is the elapsed time between midpoint of sample collection or end of the collection period and time of counting (for environmental- samples, not plant effluents ). The value of sb used in the calculation of the LLD for a detection system ! shall be based on the actual observed variance of the background counting , rate or of the counting rate of the blank samples (as appropriate) rather i than on an unverified theoretically predicted variance. In calculating the , LLD for a radionuclide detemined by gansna ray Spectrometry, the background ! shall include the typical contributions of other radionuclides normally present in the-samples of E,V,Y and At shall be(e.g., potassium used in 40 in milk samples). Typical values the calculations. ' 59 Revision 22 i 08-02-90
, 2, as-e-,
I&BLE 5 3 (Continued) TABLE NOTATION 1 It should be recognized that the LLD is defined as an a oriori (before the , fact) limit representing the capability of the measurement system and not as Anosteriori(afterthefact)limitforaparticularmeasurement.*
- 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)d Quant (2 Currie, L. A., ' Limits for Qualitative Detection an De".ermination Application to Radiochemistry' Anal. Chem. 40, 586 93 (1968). (3) Hartwell, J. K., ' Detection Limits for Radioisotopic Counting Techniques,' Atlantic Richfield Hanford Company Report ARH-2537 (June 22, 1972).
~
i L i 5-10 Revision 21 02-15-90
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.2 LAND USE CENS!1 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 distanco of five miles. For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land 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 ACTION:
- a. With a land use census identifying a location (s) which yields a calculated doie or dose commitment 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, tursuant to Technical Specification 6.9.2, a Special Report which identifies the nee location (s).
- b. With a land use census identifying a location (s) which yields a calculated dose or dose comitment via the same exposurs pathway 20 percent greater than at a location from which samples are currently being obtained in accordance with Section 5.1. in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days. The sampling location, excluding the control station location, having tie lowest calculated does or dose commitment 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 mouths 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/0 in lieu of the garden census.
5 11 Revision 22 08-02 90
5.0 RADIOLOGICAL ENVIRONNENTAL NONITORING (Continued) 5.3 INTERLABORATORY COMPARISON PROGRAM l SPECIFICATION 5.3.1 Analyses shall be performed on radioactive materials Supplied as part of an Interlaboratory Comparison Program 1 which has been approved by the Commission. APPLICABILITYi At all times ACTION:
- a. With analyses not being performed as required above, !
i report the corrective actions taken to prevent a ' recurrence to the Commission in the Annual Radiological Environmental Operating Report. SURVEILLANCE REQUIREMENTS
.1 A summary of the results obtained as part of the above required Interlaboratory Comparison Program and in accordance with Section 5.4.1 of this document shall be included in the Annual Radiological Environmental Operating Report (see Section 5.4),
i l l l 1 1 l ' 5 12 Revision 22 08-02-90
5.0 RADIOLOGICAL ENVIRONMENTAL NONITORING (Continued) 5.4 ANNUAL RADI0l0GICAL ENVIRONMENTAL OPERATING REPORT 0 5.4.1 The annual radiological environmental operating reports shall include sumaries, interpretations, and an analysis of' trends of the results of the radiological environmental I surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environment 01 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 irreversible damage are detected by the monitoring, the ! report shell provide an analysis of the problem and a planned course of action to alleviate the problem. The annual radiological environmental operating reports shall include sumarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report perind. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted 'as soon as possible in a supplementary report. The reports shall a' Iso include the following: a sumary description of the radiological environmental monitoring program; a map of all sempling locations keytd to a table giving distances and directions from the mid point of reactor Units 2 and 3; and the results of licensee participation in the Interlaboratory comparison Program, required by Section 5.3. Asinglesubmittalmaybemadeforamultipleunitstation,combiningthose sections that are comon to all units at toe station. 1
- 5 13 Revision 21 02-15-90
l 5.0 RADIOLOGICAL ENVIRtWNENTAL MONITORING (Continued) l 5.5 kHif.LLL(CATIONS The Radiological (nvironmental Monitoring Sample Locations are identifitd in Figure 5 1. These sample locations are descr' abed in Tables 5 4 and 5 5 and indicate the distance in miles and the direction, determined from dearts s true ni rth, from the center of the Units 2 cod 3 building complex. Table b o gives the sector and direction designation for the Radiological Environmental Monitoring Sample Location on Map, Figure F-1. d 1
\
5 14 Revision 21 02 15 90 s
- - - - ~ . _
Page 1 of 6 TABLE 5-t RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS i DISTANCE * ) TYPE OF SAMPLE AND SAMPLING LOCA',10N*** (miles) DikcCTION* Direct Radiation City of San Clemente (Former SDGtE Offices) 5.6 kW 1 Camp San Mateo (MCB, Camp PMdittoni 3.5 N 2 Camp San Onofra (MCB, Camp Pendicton) 2.6 NE 3 Ca ip Horno (MCB, Camp Pendleton) 4.5 E
$ r mp a Las Pulgas (MCB, Camp Pendleton) 8.5 E 6 O d R ute 101 (East Southeast) 3.0 ESE 7 Oli Route 101 (East-Northeast) 0.5 ENE 8 Non orrnissioned Officers' Beach Club 1.5 NW 9 Bs long Road /I 5 Freeway Offramp 2.0 NW 10 E' f (Aajacent +,o PIC #1) 0.7 WNW il fe, vier Visitors' Center 10.3** NW 1r South Edge of Switchyard 0.2** E
, 13 Southeast Site boundary (Bluff) 0.4** SE 14 4h'ntington Beach Generating Station .-7.0 NW 15 Sw.Snart Site Boundary (Office Building) u.'** SE 16 ITst t;7theast Site Boundary R9' ESE 17 sransit hse 18 Trans% acte I 39 San Clt.nonte Highlands 5.0 NNW
- 5. ?, NW 20 San Clemente N er ,
21 09ncordia Elementar.v School - San Clemente 3.5 NW - 22 Former U.S. Coast Guard Station - San Mateo Point 2.7 WNW
!? %n Clenente Ger,e%1 Hospital 8.2 NW i 24 .i: Clemente High Schoci 6.0 NW
- Distanc/ (miler
- nd Direction (sector) are measured relative to Units 2 and j 3 midpoin Tlirection is determined from degrees true north.
** Distances are .1 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 l
5 15 Revision 23 02-28 91
Page 2 of 6 TABLE 5-4 RADIOLOGICAL ENVIR03:4 ENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- TYPE OF SAMPLE AND SAMPLING LOCATION ***
(miles) DIRECTION
- DirectRadiation(Continued) 25 Convalescent Home - San Clemente 8.0 NW 26 Dana Hills High School 11.0 -NW U.S. Post Office Dana Point 30.6 NW 27 28 .Doheny Fire Station - Capistrano Beach 9.5 NW 29 San Juan Capistrano Fire Station 10.8 NW
-30 Laguna Beach Fire Station 17.5 NW
- 31 Aurora Park Mission Viejo 18.7 NNW 32 Santa Ana Policc Department 32.0 NW 33 Camp Talegt (MCB, Camp Pendleton) 5.7 N 34 San Onofre School (MCB, Camp Pendleton) 1.9 NW 35 Range 312(MCB,CampPendleton) 4.7 NNE 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 L 47 Camp Las Flores (MCB, Camp Pendleton) 8.6 SE
'48 Mainside(MCB,CampPendleton). 15.0 ESE L Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 mi 4 oint. Direction is determined from degrees true north.
l ** _ Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.
*** MCB - Marine Corp *, Base PIC - Pressurized Ion Chamber l
5-16 Revision 21 l 02-15-90 m _. _
Page 3 of 6 TABLE 5-4
- ' RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- TYPE OF SAMPLE AND SAMPLING LOCATION *** (miles) DIRECTION
- Direct Radiation (Continued)
. 49 CampChappo(MCB,CampPendleton) 12.8 ESE 50 Oceanside Fire Station 15.5 SE 51 Ca.rlsbad Fire Station 18.6 SE ,
52 ~ Vista Fire Station 21.0 ESE 53 - San Diego County Operations Center 45.0 SE 154 Escondido Fire Station 3?.0 .ESE 55 San Onofre State Beach (Unit 1. West Southwest) 0.2** WSW 56 San Onofre.5 tate Beach (Unit 1, Southwest) 0.l** SW- , ! 57- San Onofre State Beach (Unit-2) 0.l** SSW 58 SanOnofreStateBeach(Unit 3) 0.1** S 59 SONGS Meteorological Tower 0.3** WNW 60 Transit Control Storage Area - - . 0.7
.61' Mesa - East Boundary (Adjacent to PIC f4) N 62 :MCB - Camp Pendleton (Adjacent to.PIC.#5) 0.6 NNE ,
63 MCB . Camp Pendleton (Adjacent to PIC #6)_ 0.6 NE 64 MCB - Camp Pendleton (Adjacent to PIC.#7) 0.5 ENE 65' MCB-CampPendleton(AdjacenttoPIC#8) 0.7 E 66 SanOnofreStateBeach'(AdjacenttoPIC#9) 0.6 ESE 67 - Former SONGS Evaporation Pond (Adjacent to PIC #2) 0.6 NW , 68 Range 2100(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 determined from degrees t"ue north.
** Distances are within 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 L
1 5-17 Revision 21 02-15-90
Page 4 of 6 TABLE 5-4
. RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- TYPE OF SAMPLE AtlD SAr4PLING LOCATION (miles) DIRECTION
- 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/ WNW 11 Mesa EOF 0.7 NNW 12 Former SONGS Evaporation Pond 0.6 NW 13 Marine Corps Base (Camp Pendleton East) 0.7 E Soil Samples 1 Camp San Onofre 2.5 NE 2 Old Route 101 - East Southeast 3.0 32 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 B Outfall - Unit 2 0.7 SW C Outfall - Unit 3 0.7 SW D Newpert 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. l 1
** 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
Page 5 of 6 i TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS
- 1 DISTANCE
- TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION * ,
Drinkirg Water 1 Tri Cities Municipal Water District Reservoir 8.7 NW
.2 San Clemente Golf Course Well 3.5 NNW 3 Huntington Beach 37.0 NW 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 NewportBeach(NorthEnd) 30.0 NW Local Crops 1 San Mateo Canyon (San Clemente Ranch) 2.6 NW 2 Southeast of Oceanside 22.0 SE D
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 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- TYPE OF< SAMPLE AND SAMPLING LOCATION (miles) DIRECTION
- Non-Migratory Marine Animals Unit 1 Outfall 0.9 WSW A
B- Units 2 and 3 Outfall 1.7 SSW C Newport Beach 18.2 NW Kelp A San Onofre Kelp Bed 1.5 S B San Mateo Kelp Bed 3.8 WNW C Barn Kelp Bed 6.3 SSE D Newport Beach 15.6 NW Ocean Bottom Sediments A Unit 1- Outfall (0.5 mile West) 0.6 W 0.8 SSW B Unit 1 Outfall (0.6 mile West) 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
PIC - RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS Theta DISTANCE
- Meters miles- DIRECTION / SECTOR *-
PRESSUR17ED ION CHAMBERS (Dearees)* 1070 0.7 WNW P S1 San Onofre Beach 298* S2 SONGS Former Evap. Pnd 313' 890 0.6 NW Q 0.7 NNW R S3 Japanese Mesa 340' 1150 0.7 N A 54 MCB - Camp Pendleton 3' 1120 S5 NCB - Camp Pendleton 19' 1050 0.6 NNE B S6 MCB Camp Pendleton 46' 940 0.6 NE C 70' 870 0.5 ENE D S7 MCB - Camp Pendleton 0.7 E E SB MCB - Camp Pendleton 98* 1120 S9 San Onofre State Beach 121' 940 0.6 ESE F Distance (meters / miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Theta direction is determined from degrees true north. , 5-21 Revision 21 02-15-90
IABLE 5-6 SECTOR AND DIRECTION DESIGNATION FOR RADIOLOGICAL ENVIRONMENTAL MONITORING SANPLE LOCATION MAP DEGREES TRUE NORTH NOMENCLATURE FROM SONGS 2 AND 3 MID-POINT Sector Center Sector 22.5' Line Limit Sector
- Direction Limit.
A N 348,75 0 & 360 11.25 8 NNE 11.25 22.5 33.75 C NE 33.75 45.0 56.25 D ENE 56.25 67.5 78.75 E E 78.75 90.0 101.25 F ESE 101.25 112.0 , 123.75 146.25 G SE 123.75 135.0 168.75 H SSE 146.25 157.0 168.75 180.0 191.25 J S 191.25 202.5 213.75 K SSW P 213.75 225.0 236,25 L SW 236.25 247.5 258.75 M WSW 258.7:i 270.0 281.15 N W , 281.25 292.5 303.75 P WNW 303.75 315.0 326.25 Q NW 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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6.0'6pMINISTRAUyl 6.1 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable through these Specifications. ACTION 6.1.1 ACTION shall be that part of a specification which prescribes remedial measures required under designated conditions. CHANNEL CAllBRATION 6.1.2 A CHANNEL CALIBRATION shall be the adjustment, as 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. The CHANNEL CALIBRITION shall encompass the entire channel, including tk mm and alarm and/or trip functions, and shall iir'. the CHANNEL FUNCTIONAL TEST. The CHANNEL UL,'ft10N may be performed by any series of sequential,
~,ntlapping or total channel steps such that the entire cimnel is calibrated.
CHANNEL CHECK 6.1.3 A GANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination 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 channels - 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. Digital comp' uter channe's - the exercising of the digital computer hardware using diagnostic programs and the injection of simulated process data into the channel to verify OPERABILITY.
t 6-1 Revision 21 02-15-90
l 6.0 80tilNISTRATIVE (Continued) i DOSE EQUIVALENT I-131 l l 6.1.5- DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, I 133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of 110-14844,
" Calculation of Distance Factors for Power and Test Reactor Sites."
FRE0VENCYNOTATION 6.1.6 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 6.2. GASEOUS RADWASTE TREATMENT SYSTEM , 6.1.7 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous efflutats 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 REPORT 6.1.8 The group responsible for the missed ACTION or survoillance shall perform an evaluation which covers the t rootcause(s),correctiveaction,andrecommendationsto A preclude recurrence of the event. Copies of the resulting report shall be provided to Effluent Egineering and the Unit Superintendent with the original sent to CDM SONGS for retention. MEMBERS OF THE PUBLIC 6.1.9 MEMBER (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 permitted to use. portions of-the site for recreational, occupational, or purposes not associated with. plant functions. This category shall not include non-employees suc.h as vending-machine servicemen or postmen who, as part of their formal job '"nction, occasionally enter an area that is contic1)d by the licensee for purposes of protection of individuals-from exposure to radiation and radioactive materials. 6-2 Revision 23 02-28-91 e z = = = _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _
=1 600 ADMINISTRATIVE (Continued)
OPERABLE - OPERABILITY 6.1.10 A system, subsystem, train, component or device shall Lc 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 equipmsnt that cre required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support functit is). PURGE - PURGING 6.1.11 PURGE or PURGING 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 confinement. SITE BOUNDARY 6.1.12 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee. SOLIDIFICATION 6.1.13 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with defir.ite volume and shape, bounded by a stable surface' of distinct outline on all sides (free-standing). SOURCE CHECK 6.1.14 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. THERMAL POWER 6.1.15 THERMAL POWER shall be the total reactor c::ra heat transfer . rate to the reactor coolant. VENTING 6.1.16 VENTING is the contro.11ed 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 not provided or required during VENTING. Vent, used, in system names, does not imply a VENTING process. l 6-3 Revision 23 02-28-91
TABLE 6-1 OPERATIONAL MODES
, REACTIVITY % OF RATED AVERAGE COOLANT CONDITION. K THERMAL POWER
- __T[MPERATURE
... OPERATIONMODE eff
- 1. POWER OPERATION 1 0.99 > 5% 2 350'F
- 2. STARTUP 2 0.99 $ 5% 2 350*F ,
- 3. HOT STANDBY < 0.99 0 2 T'F .
- 4. HOT SHUTDOWN < 0.99 0 350'F> T,yg>200'F
] 5. COLD SHUTDOWN < 0.99 0 s 200'F
- 6. REFUELING ** s 0.95 0 s 140'F
- Excluding decay heat.
** Fuel in the. reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
6-4 Revision 21 02-15-S0
. - .. . . ~ . - .
-_ .= - -. . .
, : TABLE 6 2 FREQUENCY NOTATION NOTATION ERE00ENCY S At least once per 12 hours D At least once per 24 hours ,
J W- -At least once per 7 days 1 M At least once per 31 days.
-Q At least once per 92 days SA At least once per 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 exceed'24 months Interval
' *A month is defined as a 31-day period.
i
]
l i l; ii i
- 1. I 6-5 Revision 22 08-02-90
6.0 ADMINISTRATIVE (Continued) l 6.2 ADMINISTRATIVE CONTROLS SEMIANNUAL RADIDACTIVE EFFLUEC RELEASE REPORT
- Routine radioactive effluent release reports covering the
~
6.2.1 operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 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 sumary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-cooled Nuclear Power Plants, " Revision 1 June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. The radioactive effluent release report to be submitted 60 days after January 1 each year shall include an annual sumary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an 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 distributions of wind speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due tc the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 1-2 and 2-2) during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the OFFSITE DOSE CALCULATION MANUAL (0DCM). 6-6 Revision 22 08-02-90
6.0 ADMINISTRATIVE (Continued) 6.2 - ADMINISTRATIVE TSNTROLS (Continued) y 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 MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources (i.ncluding doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are 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 by measurement or estimate),
- c. Principal radionuclides (specify whether detennined by measurement or estimate),
- d. Type of waste (e.g., spent resin, compacted dry '
waste,evaporatorbottoms),
- e. Type of container (e.g., LSA, Type A, Type B, LargeQuantity),and
- f. Solidification Agent (e.g., cement, urea formaldehyde) .
The radioactive effluent release reports shall include unplanned releases 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.
- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are comon to all units at the Station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit. :
6-7 Revision 22 08-02-90
6.0 ADMINISTRATIVE (Continued) l 6.3 MAJOR CHANGES TO RADIDACTIVE WASTE TREATMENT SYSTEMS (Liquid, & l Gaseous) Licensee initiated major changes to the radioactive waste systems
\ (liquid & gaseous):
- 1. Shall be reported to the Commission in the Monthly Operating Report for the period in which the evaluation was performed pursuant to Technical Spedfication 6.5.2. The discussion of each change shall contain:
- a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;
- b. hfficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;
- c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;
- 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 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 made;
- g. An estimate of the exposure to plant operating personnel as 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 pursuant to Technical Specification 6.5.2.
68 Revision 22 08-02-90
6.0 ADMINISTRATIVE (Continued) 6.4 IMUi LIOUID EFFLUENTS CONCENTRATION (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 II, Column 2. This limitation provides additional r.ssurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A design objectives of Appendix I,10 CFR 50, to an individual, and (2) the limits of 10 CFR20.106(3) to the population. The concentration limit for dit, solved or entrained noble gases is based upon the 1 assumption that Xe 135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. DDE (1.2) 6.4.2 This specification is provided to implement the require-ments of Section II.A, III.A and IV.A of Appendix 1, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix'I. The ACTION statements provide the required operating flexi-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 dese calcu-lations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be 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 ODCM for cMculating 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 Reletses of Reactor Effluents for the Purpose of Evaluating Cotipliance with 10 CFR Part 50, Appendix I," Revision 1, Oc.tober 1977 cnd Regulatory Guide 1.113, *
" Estimating Anatic Dispersion of Effluents from Accidental anc Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
This specification applies to the release 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 sharing that system. ! 6-9 Revision 21 02-15-90
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'6.0 ADMINISTRATIVE (Continued) 6.4 BMifji (Continued)
QqUID WASTE TREATMENT (1.3) 6.4.3 The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions ' of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable. " This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix 1 to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatinent system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix 1, 10 C;R Part 50, for liquid effluents. GASEOUS EFFLUENTS D0.SE RATE (2.1) 6.4.4 This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from
. all units on the site will be within tnc arcaual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20. Appendix B, 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 site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gama and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem / year to the total body or to less than or equal ,to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to1500mre# year.
This specification applies to the release of gaseous 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 sharing that system. l 6-10 Revision 21 02-15-90
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- 4 .i L6001 ADMINISTRATIVE (Contir.ued). md y ,
;6.4 agli .(Continued): _
DOSE-NOBLEGASES-(2.2)- This specificatien is provided to implement the
~
1
. 6.4.5:
requirements of Sections II.B. 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.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 I to assure
" that the releases of radioactive material in gaseous -
effluents will be kept "as~10w as is reasonably achievable." The Surveillance Requirements implement the-
', requirements in Section-III.A of Appendix I'that conformance with the guides of Appendix I-be shown by- . 1
. calculational procedurestbased on models and data cuch that j J the actual exposure of an individual. through appropriate t
- pathways is unlikely to be substantially. underestimated.
The dose calculations ' established in the ODCM for-calculating'the doses due-to the actual; release rates: of - - radioactive noble gases in gaseous effluents are consistent ~a with:the methodology provided in Regulatory Guide 1.109,
" Calculation-of Annual Doses'to Man from Routine Releases 1
of' Reactor Effluents for the Purpose of Evaluating 4 Compliance with 10.CFR Part 50,' Appendix ~I," Revision:1,- " October 1977 and Regulatory Guide 1.111 " Methods for Estimating Atmospheric Transport and' Dispersion of Gaseous / i Effluents'in Routine Releases from Light-Water Cooled D Reactors,". Revision-1, July 1977. For individuals who may i'
-at timas beLwithin the' site boundary, the occupancy of the:
individual will be sufficiently low to compensate for any. increase-in the atmospheric diffusion factor:above that for - the SITE BOUNDARY.- For-MEMBERS OF THE PUBLIC who traverse = the SITE BOUNDARY via: highway:1-5,-the residencystime shall: A a be considered neglig'ible and hence the dose 1'0".-- The-0DCM equations-provided for determining the air doses-at the
- SITE BOUNDARY are based upon the historica1Laverage atmospheric conditions.
t DOSE - RADIOI0 DINES.-RADIOACTIVE MATERIALStIN~ PARTICULATE FORM AND TRITIUM (2.3):
,< 6.4.6< This specification' is provided to implement the requirements of Sections II.C, III.A and1IV.A of:
' Appendix I,10 CFR Part 50.: The Limiting Conditions for Operation-are the guides set forthlin Section II.C of-y , : Appendix 1. The ACTION statements _ provide the' required operating flexibility and at the same Jtime implement-the guides: set forth in'Section'IV.A of Appendix--12to assure H that the releases of radioactive materials in gaseous effluents will be kept "as . low as.is reasonably-achievable." The ODCM calculational methods-specified-in '
the Surveillance Requirements implement the requirements .
- in Section III.A-of Appendix I that conformance with the 4 L guides of Appendix ! be shown by calculational procedures l
L 11 Revision 22 L 08-02-90 ; l L--___-_ --
6.0 ADMINISTRATIVE (Continued). L 6.4 SMEji (Continued) based on models and data, such that the actual exposure of an individual through appropriate pathw'ays is unlikely to be substantially underestimated. Tot f0CM calculational methods for calculating the doses due '.o the actual release rates 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 Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111,
- Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also 3rovide for determining the actual doses based upon the listorical average atmospheric conditions. The release rate specifications for radiciodines, radioactive materials in particulate form and tritium are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these calculations were: 1) individual inhalation of deposition of radionuclides onto airborne green leafyradionuclides, vegetation wit2)h subsequent consumption by man,
- 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumation 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 GASE0US 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 appropriate portions of these systems be used, 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 Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section 11.0 of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives-set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents. 1 6-12 Revision 21 02-15-90
-6.0' ADMINISTRATIVE (Continued) 1 L 6.4 DASLS (Continued)
-TOTAL DOSE (2.5)
~
6.4.8 This specification is provided to meet the dose limitations of 40 CFR ?0. The specification requires the-preparation and submntal- of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Ap)endix I. For sites containing up to 4 reactors, it is hig11y 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 consecutive _ months to within the 40 CFR 190 limits. For the purposes of the Special Re) ort, it may be assumed that the dose commitment to the mem)er of the public from other uranium fuel cycle sources is negligible, with the exception that dose 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 estinated to exceed the requirements of 40 CFR 190, the Special Re) ort with a request for a variance in accordanco wit 1 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. An 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. RADIOACTIVE LIOUID EFFLUENT INSTRUMENTATIM (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 these instruments shall be calculated in accordance with the procedures in the ODCH to ensure that the alar # trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY 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. 6-13 Revision 21 02-15-90
600 AMINISTRATIVE (Continued) L L 6.4 SASES (Continued) RADIOACTIVEGASEOUSEFFLUENTINSTRUMENTATION(4.2) 6.4.10 The radioactive gaserus 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 shall be calculated in accordance with the procedures in the ODCH to ensure that the alarm / trip nill occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provisions for monitoring and controlling the concentraticas of potentially explosive gas mixtures in th'a waste gas holdup system. The OPEPE ILITY and use of this instrumentation is consistent with the reouirements of General Design Critaria 60, 63 and 64 of Appendix A to 10 CFR Part 50. BONITORINGPROGRAM(5.1) 6.4.11 The radiological monitoring program required by this specification provides measurements of radiation and of radioactive mater $als in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring progrcm thereby supplements the radiological effluent monitoring program by verifying that the 11easurable concentrations cf radior.ctive materials and levels of radiation are not higher than expected on the basis of the effluent measurements und modeling of the environmental exposure pathways. The initially specified monitoring program will be offective for at least the first three years of comercial optration. Following this period, program changes may be initiated based on operational experience. The detection cLpabilities required by Table 5-1 are state-of the art for routine environmental measurecents in industrial laboratories. It should be recognized that the LLD is defined as an A criori (before the fact) limit representing the capability of a measurement system and not as A p.011eriori (after the fact) lithit for a particular measurement. Analyses shall be perfot1ned 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 nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report, 6-14 Revision 22 08-02-90 u n _ .- _ _ _ _ _ __ _ . _. - ._ __ __-__
6.0 ADMINISTRATIVE (Continued) 6.4 BME1 (Continued) LARj!SE CENSUI (5.2) 6.4.12 This specification is provided to ensure that changes in the use of UNRF.STRICTE0 AREAS are identified (nd that modifications to the monitoring program rre made if required by the results of this ceccus. The best suwey , information from the door-to-doo', aerial or consulting with local agricultural authoritics shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix 1 to 10 CFR Part 50. Restricting the census to gardens of greathr than 500 square feet provides assuranel
'f. hat significent exposure pattvays via leafy vegetables will be identified and monitor 1d since a garden of this 26 sizeistheminimumrequiredtoproducethequantity(de kg/ year) of leafy vegetables assume 6 in Regulatory Gui 1.109 for consumption by a child, To deternhe this mininum garden size, the following assumptions were used,
)) the.t 20% c,f the garden was used for growing broad leaf wegetation (be., similar to lettuce and t abbage), and 2) a vegetation yield of 2 kg/ square meter, IEEBLABORMORY-_ COMPARISON PROGRAli (5.3) 624.13 Th9 requirement for participatica in an hiterlaboratory ll Comparison Program 13 providcd to et,sure that ' independent checks tn the precision and accuracy of the metsurements of r&dioactive material b) envi*onmental sample mstrices are .
-performed as part of the qJa'sity assurance program for-in order to demonstrate that the environmental mcnitoring resultsJre reasonably va lid.
4
)
6-15 Revision C 08-02-90
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R. i ATTACHMth? B a Mejor Change to the Unit 2 Radioactive Wasce irectr, eat Systen ~ SONGS Units 2:and 3 Monthly Operating Report i O '. 4 5 ( (
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i i ! DESCRIPTION OF A MAJOR CilANGE (0 THE > TF1 UNIT 2 RAD 10ACT1VE WASTE i
- TREATHENT SYSTEN i
Proposed Facility Change (PFC) 2 88 6629 provided modifications to the existing Component Cooling Water (CCW) Area Sump drain, the Storage Tank Building Sump drain located in the Auxiliary Feedwater Pump Building, and the Auxiliary Building Sump drain connections.
- ' Piping and valves were added to direct the' drains from either the CCW Area Sump or the Storage Tank Building Sump, which currently flow to the Radwaste Area
- Sump,totheBlowdownProcessingSystem(DPS) Sump. Piping and valves were also added to the Auxiliary Building Sump to direct the drain which currently flows to
- the Oily Waste Sump, via the East Turbine Area Sump, to the BPS Sump. -
. The reporting of a major change to the radioactive waste treatment system is ' " requirod-by Section 6.9.1.10 of Apendix A TeLhnical Specification to Facility Operating License NPF-10 for San Onofre Unit 2. Additional information regarding i t11s change:is contained in PFC 2 88 6629, e f s r i t t k 9 ' ,,.1,,.-,m.,y ,_--,_..'---.e - . m,4 4v 4,,r-,. 4 r y , , w --- e - . . .m-e ,m,--,we.r_,-r,. -
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ATTACHMENT C Responses to Remaining EG&G Conunents on Revistcr.19 of the SONGS Units 2 and 3 Offsite Dose Calculation Manual (ODCM)
Provided below are sumaries of the responses to remaining EG&G comments (Comments 2, 8, 9,18 and 19) in the Conclusions section of EG&G's " Technical Evaluation Report for the Evaidation of Offsite Dose Calculation Manual (Updated through Revision 19)'. Response to Comments J nder the headina "The followino discrepancies should be addressed;" Comment 2: "Section 1.2 should identify the liquid release considered in the dose calculations, the individuals exposed, the exposure pathways , considered, and the consumption and occupation factors used." Response: The liquid releases considered in the dose calculations are described in Section 1.4 of the Units 2 and 3 Offsite Dose Calculation Manual (ODCM), Revision 23. Doses from liquid releases are calculated using the methodology of NUREG 0133 as indicated in the footnote to Table 1-4,
- Dose Commitment factors", of Revision 23 to the ODCH. Both the individuals exposed and exposure pathways considered are identified in Section H of the San Onofre Semiannual Radioactive Effluent Release Report. SCE uses the adult ingestion .
data given in NVREG 0133 for the censumption factor as indicated in Section 1.5 of the ODCM. There are no occupation factors considered by NVREG 0133 for the liquid pathways. Section 1.5 has been revised to reference Section 1.4 which identifies the liquid pathways considered.- Section 1.2 in Revision 19 is now Section 1.5 in Revision 23 of the ODCM. SCE's-initial- response to Comment 2 in Attachment D of the July 1990 Units 2 and 3 Monthly Operating Reports dated Appd 14, 1990, was incorrect in referencing the NRC PARTS computer cod 4 from NVREG 0133 being used for liquid effluent releases. The PARTS computer code used to obtain parameters for dose calculations is only applicable to gaseous releases. Comment 8: " Sections 2.2.2 (sic) should include all parameters necessary for the calculation of the dose parameters, Ri , in Tables 2 5 through 2-
- 14. The equations used to calculate the values of Ri should also be i identified, either by giving the eqaations or by reference."
! Response:- .All parameters necessary for the calculation of the dose parameters, : Ri , are derived from the Annual Land Use Census Report-using the s specifications listed in NUREG 0133, Appendix D. The values of R i-are calculated using equations implicit in the NRC supplied PARTS code, generally described in NUREG 0133, Sections 5.2.1 through , 5.3.1.5. The definition of R iin Section 2.8.2.1 now references the PARTS code and the values of the )arameters used to calculate R i . These input parameters, along witi other supporting documentation for ODCM Revision 23, were transmitted to Corporate Documentation Management for filing and storage (see Memorandum from E. S. Medling B-1
to P. H. Penseyres dated 01/29/91,"1990 ODCM Dose Parameters for , SONGS 1, 2, and 3"). This supporting documentation,-including the input parameters used to calculate Rn is updated annually using information from the Annual Land Use Census Report as required by , ODCM Specification 5.2.1. Accordingly, resulting changes to R tables and the reference to supporting documentation (in Sectio,n 2.8.2.1 of the ODCM) will be updated annually. The referenced Section 2.2.2 in the comment was. actually Section 2.3.2,
" Dose from Tritium, Radioiodines, and Radioactive Meterials in Partt.ulate Form with Half Lives Greater than 8 Days in Gaseouc Effluents" in Revision 19. Section 2.3.2 is now Section 2.8.2 in L ' Revision 23 of the ODCM. Tables 2 5 through 214, " Dose Parameter R i for Sector...," are now Tables 2 7 through 2 16 in Revision 23 of the ODCM.
Comment 9 - "The exclusion of doses to the lung in Tables 2-5 through 214 should be justified." Response: Doses to the lungs are nra included, as appropriate, in Tables 2-7 through 216 of the ODCM as discussed below. , Tables 2-5 through 214. " Dose Pareneter for Ri- for. Sector...", in Revision 19, are now Tables 2-7 through 2-16'in Revision 23 of the ODCH. SCE uses-the NRC computer code P/R7S from NUREG 0133 Lto calculate the dose parameters tabulated in TableA 2-5-through 2-14 of Revision 19. The
. code has been found to be deficitnt by EG&G in that it assigns-only one critical organ to each radionucli'Je ragardless of the method of-body-entry,-i.e.,-inhalation.or ingest 3cn. Since the NRC supplied database:
for PARTS uses the ingestion pathw0y fo, critical organ determination, .; the_ dose to the lungs is excluded. The Dase Conversion factors used by the PARTS code for the inhalation pathway have been revised to correct this deficiency. The new Dose Conversion Factors were obtained from Rerulatory Guide 1.109. . Tables 2 7 through 2-16 in Revision 23 of the ODUM shows the-inhalation critical organs which includes. lungs, as agrch ii s. Comment 18: 1 "In sectiongl.2, the Licensee mu wis) to use the average dilutions
, , flow for the reporting )eriod in.the calculations of doses due to =r liquid effluents, a metiod allowed by.the NRC Staff."- <
Response
Section 1.c, " Dose Calculations for Liquid Effluents", in Revision
- 19. is now Section 1.5 in Revision 23 of the ODCH. SCE evaluated the EG&G recommendation and determined there are no current changes ";
to SCE's method of using instantaneous dilution in the calculation of liquid effluent doses. Using this instantaneous method may result in a more conservative estimates of dose, but is consistent with- the requirements of both NVREG-0133 and Regulatory Guide 1.109. B2
<a _. _._ .___a_-_ ._ , . . _ _ _ _ _ _ _ _ _ . _ . . _ .
y Comment 19: "The Licensee may wish to modify the requirements in Section 2.2.2 to match the recommendations in the bases statement for Technical Specification 3.11.2.1.b for SONGS Units 2 and 3 and in NUREG 0472: i.e., that the organ dose rate limit may be applied to the thyroid of a child via the inhalation pathway." \ Response: SCE recognizes that NUREG 0472 allows us to consider only the child's thyroid as the significant pathway for inhalation doses. We have evaluated this alternative as described below. However, at this time, SCE will_ continue to use the most conservative organ / age group combination. SCE may evaluate other NRC-approved options at a lacer date. , Section 2.2.2, "Radioiodines and F.cticulates", in Revision 19, is now , Section 2.7.2 in Revision 23 of the OCCM, SCE's evaluation determined the current methodology uses the most canservative organ in the highest e dose sector to develop Table 2 6," Controlling Location factors". . In the
- ma.jority of cases, the critical organ / critical age group is the child's '
thyroid. However, for certain isotopes, such as Co 60, the lung would be ; considered the critical organ as permitted by the existing criteria. This results in additional conservatisms in the calculation of doses from : gaseous releases. l . I 1 I i i l B-3
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