ML20247C880
| ML20247C880 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/01/1989 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13303B126 | List: |
| References | |
| PROC-890701, NUDOCS 8909140129 | |
| Download: ML20247C880 (168) | |
Text
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1 ATTACHMENT C SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 & 3, "OFFSITE DOSE CALCULATION MANUAL,"
PROPOSED REVISION 21 8909140129 890911 PDR ADOCK 05000361 P FDC
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- . .p br 0FFSITE DOSE CALCULATION MANUAL-'
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' NUCLEAR GENERATION SITE a
UNITS 2 AND 3 v ,
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.3081c. man 07-01-89
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E . TABLE OF-CONTENTS q Elat :
l p LIST:0F FIGURES _........................................................ iii L I S T O F 1 T AB L E S . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . .. . . . . . . . . i v - v INTRODUCTION ................................ ................... ..... vi:
-1,0-- LIQUID EFFLUENTS............................................c..... 1-1 m .l.l. -
Concentration................................................ 1-l'
.1.1.1 Specification....... ................................ 1-1 ,
'j b '1.1.1.1, 1.1.1.2, 1.1.1.3 Su rve i11 ance s . . . . . . . . . . . . . . . . . . . . .. . 1-1 1.2. Dose l'.2.14 Specification....................................... 1-5
- 1. 2 .1.1 S u rv e 111 a n c e . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . 1-5
- 1. 3 . L i qui d Wa s te Tre atment . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 -6 l 1.3.1 Specification....................................... 1-6 1.3.1.1,~1.3.1.2 Su rve i 11 an c e s . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . 1-6 1.4 ' Liquid Effluent- Monitor Setpoints. . . . . . . . . . . . . . . . . . . . . . . . . . . 1-8 ;
- 1. 4.1l Batch Release Setpoint Determination. . . . . . . . . . . . . . . . 1-10:
1.4.2 Continuous Release Setpoint Determination. . .. - . . . . . 1-16 1.5 Dose Calculations for Liquid Effluents. . . . . . . . . . . . . . . . . . . . . . 1-26
.l.6 Represent ative Sampl ing. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-29
- 2. 0 l GAS EOUS E F'LU ENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1
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L 2.1 DoseRate...................................................2-1 2.1.1 Spec i fi c at i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 -1 2.1.1.1, 2 l .1. 2 Surve111 ances . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 i
'2.2 Do s e - N o bl e G a s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-5 2.2.1 S pe ci fi c ati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-5 2 . 2.1.1 Su rve i 11 anc e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-E 2.3 Dose - Radiciodines, Radioactive Materials in Particulate
. Form and Tritium............................................ 2-6
- 2. 3 .' 1 Sp ec i fi c a t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-6
- 2. 3.1.1 S u rve i11 a n c e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-6 Revision 21 1 07-01-89
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'2.41 Gaseous Radwaste. Treatment..................................... 2-7 i' 2 . 4 .1. S p e c i fi c a t i o n .' . . . . . . .. . . . . . . . . .. . . . . . . . . . . - . . . . . . . . . . . . . ' 2 uJ 4 2.4.1;1,- 2.4.1.'2 Surveill ances . . . . . . . . . . . .. . . . . . ............ 2-7 W
-2.5 Total 1 Dose.....s.............................................
2-8; "2.5.I' Specification....................................;..-.. 2 2 . 5 '.1.1 : S u rv e i l l an c e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 - 8
' 2.6 ~ Gaseous Effl uent Monitor Setpoints . . . . . . . . 4. . . . . . . . . . . . . . . . 2-10 2 . 6.1 -- Pl a n t S t a c k . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . 2 - 10 f;
2.6.2 LCondenser Evacuation System......................... 2-14 2.6.3 Containment Purge .....................................-2 '
2.7 L Gaseous . Effl uent Dose Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-25 p
- 2. 7.1 - N o bl e G a s e s . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . 2-26 2.7.2 .Radioiodines and Particulate ...................... 2-26' 2 ^ 8 - Gaseous Effluent Dose Cal cul ation . . . . . . . . . . . . . . . . . . . . . . . . . . 2 28
'2.8.1 . N o bl e G a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 - 2 8
~ 2.8.1.1- - Hi stori cal Meteorol ogy . . . . . . . . . . .. . . . . . . . . 2-26 g
2.8.1.2 Concurrent Meteorology....................'2-29 <
c 2.8.2 Radloiodines and Particulate ...................... 2-30 2.8.2.1 Hi storical Meteorology . . . . . . . . . . . . . . . . .- . . .
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-2.8.2.2- Concurrent Meteorology ................... 2-32 2.9 ' Total Dose Cal cul a ti ons . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-77
~2.9.1 . Total Dose to Most likely Member. of the Public ..... 2-77 t- 2.9.2 Thyroid Dose ....................................... 2-19
, 3.0 PROJECTED DOSES 3.1 Liquid Dose Projection ............ ........................ 3-1 3.2 Gaseous Dose Projection .................................... 3-1 4.0 EQUIPMENT,............................ .......................... 4-1 4.1 Radioactive Liquid Effluent Monitoring Instrumentation...... 4-1 4.1.1 Specification......................................... 4-1 4.1.1.1, 4.1.1.2 Surveillance........._.................... 4-1 l;
Revision 21 ii 07-01-89 .
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ODCM -
l 4
TABLE OF CONTENTS (Continued)
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4.2 Radioactive Gaseous Effluent Monitoring Instrumentation..... 4-6 4.2.1 Specification................ ........................
. 4-6 4.2.1.1 Survei11ance........................................ 4-6 4.3 Operability of Radioactive Waste Equipment. . . . . . . . . . . . . . . . . . 4-12 -
5.0 Radiological Environmental Monitoring. . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1 Radiological Environmental Monitoring Program. . . . . . . . . . . . . . . 5-1 5.2 Land Use Census............................................. 5-10' 5.3' Interl aboratory Compari son Program. . . . . . . . . . . . . . . . . . . . . . . . . . 5-10 5.4 Annual Radiological Environmental Operating Report. . . . . . . . . . 5-11 5.5 Sample Locations............................................ 5-12 5.6 Bases....................................................... 5-12 6.0 Administrative........... ..................................... 6-1 5.1 Definitions................................................. 6-1 6.2 Admi ni st rat i ve Control s.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6 6.3 Najor Changes to Radioactive Waste Treatment Systems (Liquid and Gaseaus)........................................ 6-8 6.4 Bases....................................................... 6-9
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. 4-51. SONGS 2 and 3 Radioactive Liquid Waste Treatment-Systems... .....- 4 - 13 ' .~
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, Handling..............................................
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.'l 6 ODCM:
s Il- LIST OF TABLES
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' Table Title Pace F2 h 1-l' Radioactive Liquid Waste Sampling and Analysis Program..... 1-2 '
a f 1 ' Liquid' Effluent Radiation Monitors Calibration Constants . .... ....... .......................'1 25 1-4 Dose Commitment Factors j A , ............................... 1-27
'2-1 Radioactive Gaseous Waste ai.1pling arsd Analysis Program.... 2-2 2-3 ' Gaseous Effluent Radiation Monitors L Calibration Constants ..................................... 2-24 2-4 Dose Factors for Noble Gas and Daughters . . . . . . . . . . . . . . . . . . 2-34 i
2 Dose-Parameters Pik ....................................... 2-35 a; 2-6. Controlling Location Factors ............................... 2-36 2-7 Dose Parameters $R for Sector P............................ 2-37 thru L 2-38 2-8 Dose Parameters $R for Sector Q.................... .......+.2-39 thru-
, 2-46
'2-9. . Dose Parameters $R for Sector R............................ 2-47 thru.
2-51
'2-10 Dose Parameters IR for Sector A............................. 2-52 thru-2-54 w
2-11 Dose Parameters $R for Sector B............................ 2-55 thru 2-57 2 ~ Dose Parameters$R for Sector C............................. 2-58 thru 2-62 2 Dose-Parameters $R for Sector D............................ 2-63 thru
) 2-65 2-14 Dose Parameters $R for Sector E............................ 2-66 thru 2-68 L 2-15 Dose Parameters 4R for Sector F............................ 2-69 thru 2-72 2-16 Dose Parameters $R for Sector G............................ 2-73 thru 2-76 v Rev. 21 07-01-89 l
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- _ . LISTOF. TABLES.(Continued))
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! Table Title Psoe 4-1 . Radioactive Liquid Effluent Manitoring Instrumentation l.... 4-2 4-2' Radioactive Liquid ~ Effluent Monitoring Instrumentation
- g. Surveill ance Requi rements . .. . . . . . . . . . .'. . . . . . . . . . . . . . . . . . . . . . 4-4
- 4-3 Radioactive Gaseous Effluent Monitoring Instrumentation.... 4-7 4-4 Radioactive ' Gaseous Effluent Monitoring Instrumentation Surveill ance Requi rements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-9 5-1 Radiological Environmental Monitoring Program. . . . . . . . . . . . . . 5-2 5 Reporting Levels for Radioactivity Concentrations in Envi ronmental Sampi es . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . .. . . . 5- 6 5-3 . Maximum Values for the Lower Limits of Detection (LLD). ... . 5-7
~
5-4 Radiological Environ $1 ental Monitoring Sample Locations..... 5-14 5-5 PIC Radiological Environmental Monitoring Locations........ 5-20 5-6 . Sector and Direction Designation for Radiological Environmental Monitoring Sample Location Map . . . . . . . . . . . . . . 5 6 Ope rati on al Mode s . . . . . . . . . . s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-4 6-2 Frequency Notation......................................... 6-5 vi Rev. 21 07-01-89 I l
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INTRODUCTION
-^ [TheOFFSITEDOSECALCULATION. MANUAL--(0DCM)isa.supportingdocumentofthe s,
RADIOLOGICAL' EFFLUENT TECHNICAL SPECIFICATIONS:(NUREG 0472). The ODCM L 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.
Th'e-0DCM 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 present methodology.
i vii Rev. 21 07-01-89
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f 52 N 1 3 M LIQUID EFFLUENTS a
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1.I' CONCENTRATION t
k gr. - SPECIFICATION
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LM '
'1.1.1 - The ~ concentration of. radioactive material released from the:
I *' , site -(see. figure'l-2) shall be limited to the concentrations-L- 4 Lspecified in 10 CFR Part 20, . Appendix B, Table II,' column 2'
.for radionuclides other than dissolved or: entrained noble gases. For' dissolved or entrained noble gases, the
. concentration shall . be . limited to' 2 x 10 t microcuries/ml' g total activity.
p ' APPLICABILITY: At all times:
ACTION:
With the' concentration of' radioactive material released from the-site exceeding tbe above limits, immediately restore:the concentration to within:the above limits.
SURVEILLANCE RE0VIREMENTS
~
.1 . The radioactivity content of each batch of radioactive liquid waste
- shall be determined' prior to release by sampling and analysis in accordance with Table 1-1. .The results of pre-release analyses
- shall be used.with the calculational methods.in Section 1.4 to assure that the concentration at the point of release s ma.intained within'the-limits of Specification 1.1.1.
.2 Post-release analyses of samples composited: from batch 1 releases shall be performed in accordance with Table 1-1.. The results of the previous post-release analyses shall be used with the calculational methods'in,Section 1.4 to assure that the concentrations-at the point of release were maintained within the limits of Specification
. l.1.1.
.3 The radioactivity concentration of liquids discharged from continuous ~ release points shall be determined by collection and analysis.of samples in accordanse with Table 1-1. 'The results of
' the analyses shall be' used with the calculational methods-in Section 1-4 to assure-that the concentrations at the point of release are maintained within the . limits of Specification 1.1.1.
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1-1 Rev. 21 07-01-89
TABLE 1-1 RADIOACTIVE LIOVID WASTE SAMPLING AND ANALYSIS PROGRAM
-~ _
Lower Limit
) - - Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)
Tvoe Frecuency Frecuency Analysis (uCi/ml)A <
A. Batch Waste P P Releage Each Batch Each Batch 5x10 '
Principa} Gamma
-Tanks Emitters
- 1. Primary Plant Make- 1-131 1x10 '
up Storage Tanks P H Dissolved and 1x10 '
, 2. Radwaste Primary One Batch /M Entrained Gases Tanks (Gamma emitters) i P H r
- 3. Radwaste Primary Each Batch Compositeb H-3 1x10 '
Secondary Tanks
- 4. Miscellaneous Gross Alpha 1x10 '
Waste Condensate-Monitor Tanks _
- 5. Neutralization P Q Sr-89, Sr-90 5x10
- B. Continuous D W Principal Gamma Releasesed Grab Sample Compositec Emitterst 5x10 7
- 1. Steam Generator.
Blowdown 1-131 1x10 '
M M Dissolved and
- 2. Turbine Building Grab Sample Entrained Gases 1x10" Sump (Gamma emitters) i
- 3. Miscellaneous !
Waste Evaporator D M Condensate
- Grab Sample Composite c H-3 1x10 '
- 4. Salt Water Gross Alpha Disch?rge From 1x10-'
Component Ccoling Heat D Q Exchanger Grab Sample Compositec Sr-89, Sr-90 5x10 *
- 5. Sb_am Generator Blowdown Bypass ** b-55 1x10-'
i 1-2 Rev. 21 l 07-01-89 i . . _ _ .__
i
[ TABLE 1-1 (Continued)
TABLE NOTATION 1 a.
i 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 Ee Ve 2.22 x 10* Y e exp (-Aat)
Where:
LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),
sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per transformation),
V is the sample size (in units of mass or volume), i 2.22 x 106 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
q A is the radioactive decay constant for the particular radionuclides, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
The value of sb used in the calculation of the LLD for a particular measurement system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.
In calculating the LLD for a radionuclides 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 (before the fact) limit representing the capability of the measurement system and not as a posteriori (after the fact) limit for a particular measurement.*
- For a more complete discussion of the LLD, and other detection limits, see the following:
(1) HASL Procedures Manual, HASL-300 (revised annually).
(2) Currie, L. A., " Limits for Qualitative Detection and 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 Rev. 21 07-01-89
%.t TABLE 1-1 (Continued)
TABLE NOTATION "i ' b.. A composite sample is one in which the quantity of liquid sampled is L ' proportional to the quantity of liquid waste discharged and in which the-method of sampling employed results in a specimen which is representative of the liquids released.'
- c. :To be representative of the quantities'and coheentrations of radioactive materials in liquid effluents, samples 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.
- 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 principa) gamma emitters for which the LLD specification applies exclusively are the followir.g radionuclides: Mn-54, fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which
^
are measureable and identifiable, together with the above nuclides, shall also be identified and reported.
- - Sampling of this flow is not required if, at 'least once per 31 days, condensate monitor tank bypass valve, SA 1415-2\"-200, is verified lacked
-shut.
L
- Administrative controls shall provide for composite sampling of the continuous releases per note b vice note c until January 1, 1983.
i, ' Continuous proportional sampling shall be in accordance with note c from January 1.1983 and all times subsequent at required by Table 1-1.
- Sampling cf this flow is not required if at least once per 31 days blowdnwn bypass isolation valve (S21301MU618 for' Steam Generator 2E088, S21301MU619 for Steam Generator 2E039, S31301MU618 for Steam Generator 3E058 and S31301MU619 for Steam Generator 3E089) is verified locked shut.
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1-4 Rev. 21 07-01-89
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h S.h 11101 -LI'QUIDIEFFLUINTS:(Continuad) {
p i a 1.2' DREE -l i
W SPECIFICATION l.2.1-The dose or dose commitment-'to an individual from radioactive !
- materials in. liquid effluents released, from each reactor. ]
unit, from the site (see. Fiaure 'l-2) shall- be. limited: 1
'?
a.- During any calendar; quarter to11ess. than or equal to' 1.5 mrem l
' to the- total body and.to less than or equal to 5 mrem to any
- organ, and o
- b. During any calendar year to'less than or equal- to 3 mrem to l the total body- and to less than or equal' to 10 mrem to any
-organ. ,
APPLICABILITY: At . all times
' ACTION:
l
- a. - With calculated dose from the release of radioactive .
materials in l! quid 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 Technica' Specification 6.9.2, a
- - Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective ac.tions taken to .
reduce the. releases and the proposed actions;to be taken to t
assure that subsequent releases will be,in compliance with
. Specification 1.2.1.
SURVEILLANCE REQUIREMENTS
.1 Dose Calculation. Cumulative dose contributions' from liquid effluents shall be determined in accordance with Sectien .1.5 at _
least once per 31 days.
i; i
1-5 Rev. 21 07-01-89
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(,~'ill.01 . LIQUID; EFFLUENTS (Continued):
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~~1;3l-LIOUIDWASTETREATMENT:
g:q' FECIFICATION
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h 3.1 The liquid radwaste treatment system f shallL be OPERABLE. The T
appropriate portions of the system shall be,used to reduce:
-the! radioactive materials.in liquid wastes: prior to their discharge when the projected doses due to the liquid effluenti from the' site (see Figure-1-2) when averaged'over 31, days,-
2,- <
- would' exceed 0.0G nrem to the tctal body or 0.2 mrem to anyl '
crgan.*' '
[M/ APPLICABILITY: At all times -
.A ~ ACTION:~
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a .- With the liquide radwaste treatment. system inoperable for: more than 31' days or with radioactive liquid waste.being ..
-discharged withou treatment and in excess 'of ti,e above.
limits,;in lieu o any other report' required by Technical Specification 6.9 3, prepare and' submit to'the Commission.
, _ within'30' days purst ant. to Technidal Specification 6.0.2 a ;
L Special Report which. includes the following-information:.
- 1.- JIdentifict. tion of the-inoperable equipment. or subsystems -
-and the reason for inoperability, 2.. Action (s) taken to restore the' inoperable equipment,to OPERABLE status, and
- 3. . Summary description of action (s) taken to prevent i recurrence.
- SURVEILLANCE REQUIREMENTS
.1l Doses;due to liquid releases shall 'be projected at least once per 31 days, in:accordance with Section 3.1.
~
.2 _ The liquid radwaste treatment system shall be demonstrated OPERABLE
~by' operating the liquid radwaste treatment system equipment for at least 15-minutes _at lea:;t once per 92 days unless.the' liquid radwaste system'has been utilized to pre ess radioactive liquid effluents during the previous 92 days.
- Per reactor unit v
1-5 Rev. 21 07-01-89 j n
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[.
, ,/ \
SITE BOUNDARY FOR LIOUID EFFLUENTS FIGURE 1 2
REFERENCE:
TECHNICAL SPECIFICATIONS, FIGURE 5.1-4 1-7 Rev. 21 07-01-89
1.0f LIQUID EFFLUENTS (Continued)-
1.4 -Liquid Effluent Monitor Methods of- Setpoint Calculation
~
b y Liquid Radwaste Effluent Line' Monitors provide alarm and_ automatic'
' termination of release prior 16 exceeding the concentration limits
~
specified in 10CFR20," Appendix B, Table II, 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 effluer.t conitors and flow measurement devices are set to a:,sure that the following equation .
is satisfied:
C*R I MPC,ff F+R (3;3)'-
Where:S MPCeff - the effective effluent maximum concentration permissible limit ( Ci/ml) at the release point to the unrestricted area for the radionuclides mixture being. released, 1
F I
f(
i-1 MPC,
)
(1-2) l 1-8 Rev. 21 07-01-89
_______=__-_____-_-____
1.4 Liquid Effluent Monitcr Metheds .of Setpoint calculation (Continued)
Where:
s
- fractional concentration of the i th radionuc^lide as F
I i
obtained by sample analysis.
N -= Number of radionuclides identifi9d in sample analysis.
MPC 4
- MPC of the i th radionuclides (10CFR20, App B, Table II, Column 2).
l
- the setpoint, in pCi/ml, representative of a C
m radionuclides concentration for the radiation monitor measuring the radioactivity in the waste effluent line prior to dilution and subsequent release.
R = tha 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 utiit time. The dilution uater flow (F) is 185,000 gpm per circ pump (4 total) and 17,000 gpm per saltwater pump (2 total).
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 Rev. 21 07-01-89
r .n
~ -
=- - --- = -
"3
%qmcqgy
- ,, 114y Liquid Effluent M
- nihr Methods of' Setpoint Calculation (Continued)
I t J .. j; - Administrative values are used to reduce each setpoint to account for
,w the. potential activity in other releases. These administrative. values '
. shall be periodically reviewed based :n actual release data -(including, for ba'mple, any saltwater disch'arge of the component. cooling water heat n exchanger) and' revised in accordance wit'h' Unit 2/3.Techn'ical w
- Specifications.
w
'1. 4. I' Satch Release Setpoint Determination The waste flow (R) and monitor setpoint (c) are se't; to meet the condition.of equation (1-1) for the effective-
, 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 reletsed is obtained from ie
- s. the sum of the measured concentrations.in the tank (or sumo) as determined by analysis.
l C-
=ICg + C, + Cs+Ct+C, p (1-3) e I Where:
l C = The total concentration in each batch tank. (ucifml) l L
ICi = The sum of the measured concentrations for each j 7 ,
radionuclides, 1 3 in the gamma spectrum. (uti/ml) l C
Fe.
- The Fe-55 concentration as determined in the previous quarterly composite sample. ( Ci/ml) 1-10 Rev. 21 07-01-89 l -
7 , 2 -
, fIh.k yg 'l.4.1-
- Batch RelCase Setpoint' Determination ~' (Continued) .
d C - The gross-alpha, concentration determined.inLthe PJ . 'previously ' monthly composite: sample. (hCi/El).
}'-
.(
C s - The 3r-89 and Sr-90: concentrations as' determined in the i
C previou[ quarterly composhe sample. (uCi/ml)-
t C
t:
The H-3 concentration as determined in the pri.vious monthly compoCite sample. (pCi/ml)
STEP 2: The effective MPC (MPC,ff)'for.each batch tank (or. sump) is determined.using:
ppg" I. ..- 1 (1-4) 2:- (Cwi/C)+(h)+(h),(E)'+(Cfe/C)
'i' (MPCg) (MPC3 ) (MPCt ) (MPC,) (MPC7 ,) ,
.MPC $, MPC s , MPC t ,.= the limiting. concentrations of the
.MPCFe, MPC, appropriate radionuclides from 10CFR20f Appendix B,' Table II, Column 2.
i NOTE: For dissolved or entrained noble gases, the concentration shall be limited to' 2.0E-4-pci/ml total activity.
i 1-11 Rev. 21 07-01 R9
._-____- ----_ O
w -
- i
%e,.. J .1 6
- i. i K,'=e ; 1. 4.1.', Batch.Raleass Sotpoint-Determin'ation: (Continued)
{
'I STEP 3: The radioactivity monitor setpoint:C , (pti/ml), . l
,t .
-t p, ,
may.now be specified based on the values of m C, Z $, F, MPC,7f end-R to. provide compliance
.( yith' the limits of 10CFR20, Appendix. B',' Table II, Column:2. ;The monitor setpoint (cpm) is taken from the applicable calibration constants given t
in Table 11-3_to correspond _to the calculated monitorconcentrationlimit.C,(pCQml).
1.4.1.1' RADWASTE DISCHARGE LINE MONITOR (2/3-7813)
The value for C,, the concentration limit at the detector, ,
.is determined by using:
-(RW) (F) .(1-5)
C < RC (Ceff)- RC-_
m - R 3C). + p2 nn MPC,7f3 MPC eff2 +**'+ MPC effn l
'Where:
n - Number of. tanks to be released.
l_
C eff
- Effective gamma isotopic concentration at.the monit'or ,
for the tank combination to be released (equal to IC for single tank releases).
i 79 E
R3 (rCg)) + R2 (ICg )2 + . . . +Rn%C,9)n (1-6)
.. a R3+R2 + ... + R n 1-12 Rev. 21 07-01-89
- ~ ~ ~- ' - ~~ ~
y .g - l b' :
YJk y 11.4.l'.11 RADWASTE DISCHARGE LINE MONIT0f1 (2/3-78131 (Continued)- 4 j;: lir j s
, q
^ a (I C g)3, (% C g)2, etc. = The total gamma isotopic concentration -
j
~
. of- first tank, second tank, etc. _ (gCi/ml);
' :c s.
R3 , R2 , etc. = The effluent flow rate from first tank, second tank, etc. Values of'R for each tank are as follows:
p Radwaste Primary Tanks R = 140 gpm/ pump (x no. of pumps to be run) b Radwaste Secondary Tanks .R = 140 gpm/ pump (x no. of pumps to be'run)-
-Primary Plant Makeup Tank R - 160 gpm/ pump (x no. of pumps to be run)
Condensate Monitor Tanks R = 100 gpm/ pump (x no, of pumps to be run)
NOTE: Since the values of R are much smaller than F, the term (F +;R) in equation (1-1) may be replaced by F.
MPC,773, MPCeff2, etc. - Values of MPCeff from equation (1-4) for first tank, second tank, etc.
C , C , etc. - Values of C, the total concentration, from 3 2 equation (1-3) for the first tank, second tank, etc. in pCi/ml.
li L
)..'
l-13 Rev. 21 07-01-89 i
yx , = , .
s p , % , 1,3 , ,
j ; < , sn M #
<p l ]+p. M
[3(4,g,31':RADWASTEDISCHA'R'ELINEMONITO'R12/3-7813Ii(Cdntinued) o
. G
< -.4
, RWfand SG88-2';3089-2' 30 881 33089 ' 0 2 ,'B 3 ,;T2 , T 3 are!
d '
administrative values used- for: simultaneous; releases from thei ky w,
< Radwaste Efflu'ent discharge' and any .or alll o.f. the four Steam?
i f [ Generators as wel1Has continuous' discharges from the :two' Blowdown .
7
.ProcessingLSystemsand_the..two:TurbinePladtSumps..Thet '
fractions RW andLSG88-2' S089-2'~SOM 23 ' M89-3OL2 , ,83 , .T2 , T 3 will_be-assigned such that RWL+JSGp +;SG89-2 /+ 3088-3h
'+' SG 5 120.
89-3 B2+B3+ 2+T3 .
- Thet0 is an administrative valm used to account f$r.the p'o tential activity released simultanemly from other release .
.. points'. This assures that theIt otal cucentration' from ail-release points.to the plant ~discharite will not result 'n a 1
- release of concentrations eXCCEding. the limits of 10 CFR 20, Appendix B,. Table II, Column 2: from the site.1 NOTE: If C, s C,ff, Hun no release is possible. To
-increase C,, fmerease -dilution flow F. (by running.
more circulating water pumps in the applicable dis-charge structure), and/or decrease the effluent flow rates R3 , f1,.
g etc. (l'y throttling the combined flow as measured on 2/3FI-7643, 2FIC-4055, 2FIC-4056, 3FIC-4055 or 3FIC-4056 as appropriate) and recalculate C, ud ng the new F, R and equation (1-5).
If there is no velear,e associated with this monitor, the monitor setpoht :h.ould be established as close to background as practical to prevent . spurious alarms ar.d yet assure an alarm should an inadvertent release occur. +
1-14 Rev. 21 07-01-89
__m _ _ . _ _ - . _ . _ _-_ _2-..-. _ - - --
) ,
i ; '
.i .<
.u.-
- 1 h >
N
- 1.4.1.21 " NEUTRALIZATION' SUMP DISCHARGE LINE MONITOR (bat'ch)
!(2RT-7817. 3RT-78171-7)j 1 The~ value for C 2 r C , the concentration. limit at the:
3 Unit-2 or' Unit'3 detector,' is. determined by using:
(B)(F)sC^
2 i <' g .
C25 II~7)
(R)(C/MPC,ff) g L ._ (8
.C 3 5 3)(F)rci '4 - (1-8)
+
.(R)(C/MPC,ff) r, Where:
.C, --
IC,$, MPC,ff The values of C IC,$ and MPC,77 as defined in STEPS 1) and 2) for the Neutralization Sump.
'~
R = 400 gpm/ pump x (number of sump pumps to be run)
C 2
= the instantaneous concentration at the b . detector(2RT-7617) in pCi/cc C
3
= the instantaneous concentration at the detector (3RT-7817) in pCi/cc B3 .and B3 are administrative values used to account for l~ simultaneous releases from both SONGS 2 and SONGS 3
-neutralization sumps. The fractions 8 2and 83 (each normally set to 0.05) will be assigned such that RW + SG 88-2
+ SG g 9-2 + 3088-3 + 3089-3 + O2+B3+T2+T3 1 1.0.
1-15 Rev. 21 07-01-89
- '; - , iY, ~,
L 1.4L 1121 NEUTRALIZATION SUMP' DISCHARGE'LINE MONITOR (ba'tch) 9 <
- (2RT-7817. 3RT-7817):'(Continued)-
n mq P! NOTE: , If C 2 rC3 (I C,j, then .no release isl possib1'e.
- g ,
To increase'C 2 r C3 , increase dilution flow F (by b running more pumps), and/or decrease theLeffluent flow-rate R, (by throttling 'the flow as measured en 2FI-3722:
and 3FI-3772), and recalculate C 2 rC using the new 3
n s
[ F, R and equation (1-7) or (1-8).-
E 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 Deterrnination:
The waste flow (R) and monitor setpoint (C,) are set to meet the condition of' equation (1-1) 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 and turbine building sump) from the sum of the respective measured concentrations as determined by analysis:
C = IC,4 + C, + Ct + C, + Cp , (1-9) o 1-16 Rev. 21 07-01-89
UTRW n <
~ '
'i 4 ,. F; 1s; ,' ;p , , ,,
1.4.2;l ' C:ntinu;us Releasa-Setpoint Determination (Continued)
(
Where:
Total' concentration-(pCi/ml)'
us C. =
1; i i IC ' 4
.Th'e total. gemma activity (pCi/ml)~ associated with 19 each radionuclides, i, in the weekly composite:
analysis for the release stream..:
C - The total measured gross alpha concentration (pci/ml)'
determined from the' previous. monthly composite analysis for the release stream.
'C, p
=
The: total F.e-55 concentration (uti/ml) as determined in the previous quarterly composite . sample for the.
release stream.
C t
- The total measured H-3 concentration (pCi/ml determined from the previously monthly composite analysis for the release stream.
C s
- The total measured concentration (pCi/ml) of Sr and Sr-90. as determined from the previous quarterly composite analysis for the release stream.
STEP 2: The effective MPC (MPC,ff) for each release stream (steam
, generator blowdown, or turbine building sump) is determined using:
3 (1-10)
- II C E
((MPC yi/C) + ((Cs/C) (baLC) i 4
) MPC 3
) , (MPC,)
( pg)+ (MPCFe/C) (MPCg ) , (Cgfq) 1-17 Rev. 21 07-01-89
'~ ,
m.
4 L ga 1
9:6 C'
,4 .
g <
.q
.1'. 4. 2 : .'Cintinuous Relcase Setpoint Determination (Continued)L 1
STEP 3:- Thesetpoint,C,-(pCi/ml),for.eachcontinuous. release J%f b ' radioactivity monitor may now be specified based on the - f 1
. respective values.!of.C, ICg ,~F, MPC,7f, and R-to'
- a. provide compliance with the limits' of 10CFR20, Appendix B, Teble II, Column 2. _ The monitor setpoint (cpm):
L: is' taken from the applicable calibration constants given :
in Table 1-3 to correspond'to the calculated monitor. limit u
C,(uCi/ml)'.
x
. b,
_l i.
1-18 Rev. 21 07-01-89
s ....y . m
j y,p31; T l[db -
G n-V Thetvalue'for.C2 ; r C3,..the concentration limit at the Lunit 2'or Unit 3 detector is deterniined by using:-
(B2 )(F)rC g- -(1-11):
C2 I i (R)(0/MPC,ff) p.
'(8 3)(F)EC j. (1-22).
Q C3 I i j) (R)(C/MPC,ff) v:
e Where:
C, IC j, MPC,7f -- The values of C, I C,4 and MPC,7f as defined in STEPS 1) and 2) for the Steam Generator blowdown.
R- blowdown flow rate (maximum of 500 gpm)-
Where R is the effluent flow re.te at the radiation monitor as defined in STEP 2.
C 2- the instantaneous concentration at the Unit 2 detector (2RT-7817) in pCi/cc C
3- the instantaneous concentration at the Unit 3 detector (3RT-7817) in pC1/cc B2 and B3are administrative values used to account for simultaneous releases from both SONGS 2 and SONGS 3 neutralization sumps. The fractions B2 and B3 will be assigned such that RW + SG88-2 + 3089-2 + 3088-3 + S089-3 L'
+B2+03+T2+T3 I I'd
, 1-19 Rev. 21 07-01-89 u
, ,; . ., .m,,.,..
a, 3
_ , 'Lb, _ ; ^^'
^
_, _-'j .
ff g', av
) 3,4,:2.'l(> T NEUTRALIZATION SUMP DISCHARGE LINE MONITOR .:
E '
, 1, , ',
, '(2RT-7817. 3RT-7817);.(Continued)-
- {
NOTE: 'If.C 2 r C3 A z.C,4 then no. release is possible.
p ,
- To increase.C2 or. C3 , ' increase dilution flow F;(by .
f N. running more circulating water pumps),;and/or decrease
? <
the effluent flow rate R,- (by . throttling the flow as'-
L measured on 2FI-3722 'and '3FI-3772), :and recalculate-L-
C' 2
" ;3 C .using the new F, R and equation(1-11) or.
(1-12).
r r
LIf thereils no release. associated with.this monitor, the o
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. ,
1-20 Rev. 21 07-01-89 i- -__------_-------__ _ _ _ _ _ --_ _ _ _
2
- g - ,
l c ' .1, ; e
-o
- 1. 4. 2.,2 x
. STEAM GENERATOR BLOWDOWN. BYPASS DISCHARGE LINE MONITORS-1 p (2RT-6753. 2RT-6759. 3RT-6753. 3RT-62}.21' ,;
o y The'value for.C59-2'.C53-2, C59-3 or C 53-3, the concentration limit at the Unit'2 or Unit 3 detectors, is determined by using:
~
j-D
'(SG88-2)(F)IC.'4i f
" C59 2 1 (I~I3)
-(R) (C/MPC,ff) - ,
q
- (SG89-2)(F)II C $
53a2 ~II'24)
(R)(C/MPC,ff) {
'(SG 88 *2)(F)I C $
1 59-3 5
.C (1-15)
(R)(C/MPCeff)
E (SG89-3)(F)I C g q C 1 (1-16) 53-3 1.
(R)(C/MPC,ff) ,
Where:-
C, I C,4, MPC,7f = values of C, C,4 and MPC,ff j t
.(asdefinedinSTLPS1and2above)
- , for the steam generator blowdown bypass. !
l R - 200 gpm 1
Where R is the maximum blowdown bypass. effluent f"lowrate per steam generator.
-C 59-2
= the instantaneous concentration at the Unit 2 detector (2RT-67E9) in pCi/ml I C
53-2
= the instantaneous concentration at the Unit 2 detector I (2RT-6753) in pCi/ml j
C 59-3
= the instantaneous concentration at the Unit 3 detector i (3RT-6759) in pCi/mi C
53-3
= the instantaneous concentration at the Unit 3 detector I (3RT-6753) in pCi/ml i
1-21 Rev. 21 1 07-01-89
t; 1.4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LJJiE MONITORS (2RT-6753u2RT-6759. 3RT-6753. 3RT-6759,1 (Continued)
RW and SG88-2' bC89-2' S088-3' 3089-?' b2 ' 3, T 2, . T3 are i administrative values used for simultaneous releases from the Radwaste Effluent discharge and any or all of the four Steam p Generators as well as continuous discharges from the two Blowdown Processing Systems and the two Turbine Plant Sumps. The q
fractions RW and SG88-2' 3089-2' 5088-3' b089-3' 02 ' 0 3, T g, T3 ]
will be assigned such that RW + SG88-2 + S0.89-2 + S088-3
+ SG 99-3 82+B3+T2+T3 s 1.0. .
The 1.0 is an administrative value used to account for the potential activity released simultaneously from other release points. This assures that the total concentration from all release points to the plant discharge will not result in a release of concentrations exceeding the limits of 10 CFR 20, Appendix B, Table II, Column 2 from the site.
NOTE: If C59-2, C53-2, C59-3, or C53-3 s I C $ (for the i ?
respective steam generator), then no release is possible.
To increase C59-2, C53-2, C59-3 or C 53-3, 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, 3FIC-4055, 3FIC-4056 or 2/3FI-7643, as appropriate) and recalculate C59-2, C53-2, C59-3 cr C 53-3 using the new values of F, R and equation (1-13), (1-14), (1-15) or (1-16).
1-22 Re'v. 21 07-01-89 l
_ _ _ ____- O
n f
. 1;4.2.2 STEAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT-6753, 2RT-6759. 3RT-6753. 3RT-6759) (Continued)
If there is no release associated with this monitor, the monitor setpoint should be established as close to backgreund'as practical to prevens spurious alarms and yet assure and alarm should an inadvertent' release occer.
l.4.2.3 TURPINE PLANT SUHP MONITORS (2RT-7821. 3RT-7821)
The value for C2 or C3 (the concentration limit at the Unit 2 or Unit 3 detector) is determined by using:
(T2 )(F)IC $
(1-17)
C2 5 I (R)(C/MPCeff) i (T3 )(F)IC (1-18)
C3s i 7$
(R)(C/MPCeff)
Where:
C, IC,4, MPCeff = values of C, IC $ and MPCeff i (as defined in STEPS I and 2 above)
[ for the turbine building sump I
l
!- R = 50 gpm/ pump (x no. sump pumps to be run)
C.' = the instantaneous concentration at the Unit 2 detector (2RT-78?l) in Ci/ml.
C 3- the instantaneous concentration at the Unit 3 detector (3RT-7821) in pCi/ml. -
l L l l
l bl 9
._________________________._.______.___--__h
' ~ ~ ' -
a, cAglgti
{ mfg R 1e R
- .o' .
3 -n .
H Qy,-l cp 1
L', i *' .
,T2_andLT. are, administrative ' values: used to account for '
h@. squ t .. ,. . 3
~
14 simultaneous' releases _ from both SONGS 2 and SONGS 3 turbine.
- '
- plant sumps. ;The: fractions T2 and_T3 will be; assigned.such' q!
/that RW + SG88-2 +
89-2'I 8088-3 + 0089 13 02+B3+T2-
+ T3 .i 1.0.
1;
. NOTE: _ If-C 2 or C3 4 I C,$ (for tlie respective sump), then no' release is possible. To increase C 2 r'C ,. increase _
3 the dilution flow F (by running more'. circulating water-pumps) and recalculate C2 or C3.uring the new value
~
' of _ F'.anc!- equation (1-17) or (1-18).
cy -
s 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 r+1 ease occur..
1-24 Rev. 21 07-01-89 f
_m.._._ .- _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . . _ - - _ _ . - _ _ _ _ _ _ _ _ _ . - _
-x . , .
,. - :q ,
9 ;
P #, 4 , ;N r ry J'
L Table' l-3 y
- p,-: ' ' 4: , , > .
J.s J y y , . Liquid' Effluent Radiation Monitor .
g ;
Calibration Constants gi:
'~ Q..g, - -(pCi/cc/ cpm);
, j_
' MONITOR Co-60 Ba-133 -Cs2137 i2RT-6753 1.84E-8 .1.91E-8 2RT-6759L 1.92E-8i 1.97E-8
.3RT-6753 1.71E-8 1.92E-8 lg 3RT-6759 1.94E .1.94E -'T
' '2/3RT-7813 ' 2.10E-9 3.14E-9 4.77E '
'. 2RTs 7817 - 2.14E-9 2.76E-9' 4.74E-9 a :12RT-7821 2.24E-9 .3.82E-9 5.39E-9 3RT-7817 2.13E-9 3.2EE-9 4.73E-9.
3RT-7821 2.11E-9 3.24E 4.80E-9.
).
e
.4
(*) This!ta' ole provides' typical (120%) calibration constants for the liquid effluent radiation monitors.
i 1-25 Rev. 21 07-01-89
-1.5 Dose Calculation fcr Liquid Effluents y The dose commitment to an-individual from radioactive materials in' liquid effluents relc:. sed to unrestricted areas are p ,
calculated for the purpose of implementing Specification 1.1.2
/
using the following expression.
D, =
r[A4 , I(at3 C 43 F3 )] (1-19)
Where:
~
A,4
- th'e site related adult ingestion dose commitment <
factor to the total body or an organ, r, for each identified principal gamma and beta emitter, i, from
,- Table 1-4 in mrem /hr per Ci/ml.
C = the average concentration of radionuclides, f, in the 43 undiluted liquid effluent during time period, at in ( Ci/ml).
3 D, - the dose commitment to the total body or an organ, r, from the liquid effluent for the time period, 1 at , in mrem 3
F 3
the near field average dilution factor for C43 during the time period, at . This factor is the ratio of '
3 the maximum undiluted liquid waste flow during time period, at j, to the average flow from the site discharge structure to unrestricted receiving waters, or maximum liauid radioactive waste flow
- discharge structure exit flow th time period over which at = the length of the j d
C and F are averaged for all liquid releases, 43 3 in hours.
1-26 Rev. 21 07-01-89
. , x.
TABLE'1-4 i
DOSE COMMITMENT FACTORS *, A I'
_Tb (mrem /hr per Ci/ml)
~
Radio- Total .
I Nuclide Body Bone. Liver Thyroid Kidney Lung GI-LLI H-3. 2.80E-l' .. . 2.80E-1 2.80E-1 2.80E-1. 2.80E-1 2.8DE 'Na-24 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.37E0 4.57E-1 4.57E-1 Cr-51 -5.60E0 . 3.30E0 1.20E0 7.04E0 1.40E3
^
Mn-54 1.35E3 7.08E3 2.11E3 2.17E4 !
Mn-56 =3.15El 1.78E2. 2.26E2 5.67E3 !
Fe-55 8.24E3 5.12E4 3.53E4 1.97E4 2.03E4 ;
Fe-59 7.27E4 8.07E4 1.90E5 5.30E4 6.23E5 -!
Co-57 2.36E2 1.42E2 3.60E3 Co-58 1.35E3 6.04E2 >
1.22E4 ,
Co-60 3.83E3- 1.74E3 3.26E4 i
, Cu-64 1.01E2 2.14E2 5.40E2 1.83E4 Zn-65 2.32E5 1.61E5 5.13E5 3.43E5 3.23ES-Br-84 9.39E-2 2.14E2 7.37E-7 Rb-88. 9. 49 E- 1 ~. .
1.79E0 0.00E0 i Sr-89 1.43E2 .4.99E3 8.00E2 Sr-90 :3.01E4 1.23E5 3.55E3 Sr-91 3.70E1 4.37E2 ;
Sr-92 1.50E0. 3.48E1 ~6.90E2- !
Y-90 1.62E-1 6.06E0 6.42E4- .
Y-91m 2.22E-3 5.72E-2 1.68E-1 !'
Y-92 1.55E-2 5.32E-1 9.32E3 Zr-95 3.47E0 1.60E1 5.12EC 8.03E0 1.62E4 l Zr-97 8.14E-2 8.80E-1 1.80E1 2.70E-1 5.51E4 :
Nb-95 5.51E-1 1.84E0 1.02E0 1.01E0 6.22E3 hb-95m 5.51E-1 1.84E0 1.02E0 '1.01E0 6.22E3 l Nb-97 1.43E-3 1.55E-2 3.91E-3 4.56E-3 1.44E1 1 Mo-99 2.44E1 1.28E2 2.90E2 2.97E2 Tc-99m 4.66E-1 1.30E-2 3.66E-2 5.56E-1 1.79E-2 i 2.1751 Ru-103 4.61El 1.07E2 4.08E2 2.25E4 i Ru-106. 2.01E2 1.59E3 3.07E3 1.03E5 )
Ag-110m. 8.61E2 1.57E3 1.45E3 2.85E3 5.91E5 i in-113 2.20E5 Sb-124 1.10E2 2.77E2 5.23E0 6.70E-1 7.85E3 Sb-125 4.42E1 2.20E2 2.37E0 2.00E-1 2.30E4 1.94E3 4 Te-129m 1.48E2 9.33E2 3.48E2 3.20E2 3.89E3 4.67E3 Te-132 1.24E2 2.40E2 1.32E2 1.46E2 1.27ES 6.2SE3 )
I -131 1.79E2 2.18E2 3.12E2 1.02E5 5.36E2 8.24E1 '
I- 132 9.96E0 1.06El 2.84E1 9.96E2 4.54E1 5.35E0 I'-133 3.95El 7.46El 1.30E2 1.91E4 2.26E2 1.17E2 I -134 5.40E0 5.56E0 1.51El 2.52E2 2.40E1 1.32E-2 ;
I -135 2.24E1 2.32E1 6.08E1 4.01E3 9.75El 6.87El i
- Source: USNRC NUREG-0133, Section 4.3.1 1-27 Rev. 21 07-01-89 i
--_______L
e .
$6:
IABLE:1-1 DOSE COMMITMENT FACTORS *, A 4*
.[~j (mrem /hr per pCi/ml)
Radic- Total Nuclide Body. Bone Liver -Thyroid Kidney Lung GI-LLI Cs-134: 1.33E4 6.84E3 1.63E4 5.27E3 1.75E3 2.85E2 Cs-136 -2.04E3. 7.16E2 2.83E3 1.57E3 2.16E2 3.21E2-Cs-137 7.85E3. 8.77E3 1.20E4' 4.07E3 1.35E3 2.32E2 Cs-138 5.94E0 6.07E0 1.20El- 8.81E0 8.70E-1 5.11E-5 Ba-139. 2.~30E-1 7.85E0 5.59E-3 5.23E-3 3.17E 1.39El Ba-140 1.08E2 1.65E3' 2.07E0 7.00E-1 1.18E0 3.39E3 La-140 ~'2.10E-1. 1.58E0 8.00E-1 5.84E4 Ce-141 2.50E-1 3.43E0 2.32E0 1.08E0 8.86E3 Ce-143 4.94E-2 6.00E-1 4. /. 7 E- 2 2.00E-1 1.67E4' Ce-144- 9.59E0 1.99E2 7.47El 4.43E1 6.04E4 Nd-147 2.74E-1 3.96E0 4.58E0 '2.68E0 2.20E4 W:-187 2.68E0 9.16E0 7.66E0 2.51E3:
Np-239 '1.92E-3 .3.53E-2 3.47E-3 1.08E-2 -7.13E2-L
- Source: OSNRC NUREG-0133, Section'4.3.1 1
1-28 Rev. 21 07-01-89
-_____-_-_____-_a
i L.1,6 ' Representa2ive Sampling - 1 Prior to sampling of a batch release, each batch shall be i
{
') - .tl.oroughly mixed to assure' representative sampling. The i methodology for mixing and sampling is described in 50123-111-5.11.23, " Units 2/3 Liquid. Effluent Release Permit" and S0123-III-5.2.23, " Units 2/3 Liquid Effluent Sample Collection".
l l; 3081c. man 1
I l-29 Rev. 21 07-01-89
- - ___-__-_____.O
p*
Xx,
(, '
fl 12.0; GASE0US EFFLUENTS
- a. ,.
2.1. DOSE-RATE-
' SPECIFICATION
, 2.~ 1.1.- The dose rate in~ unrestricted areas due to radioactive' L materials' released in-gaseous effluents from the siteL(see L .
, Figure 2-2) shal_1-be limited to the following:
,~
a~. For noble gases: Less than or equal to 500~ mrem /yr to .the total body;and 1ess than or equal. to 3000 mrem /yr to the skin, and b .- For all radiciodine: tritium and forLall-radioactive materials in particulate form with half lives greater than 8 days:'- Less th6n or equal to =
1500Lmrem/yr to any organ.
APPLICABILITY: At all- times .g ACTION:
With dose rate (s) exceeding the_above. limits, immediately decrease'
/-
the release rate to within the above limit (s).
.SVRVEILLANCf ,a..REMENTS.
.1 'The dose rate due to noble gases .in gaseous effluents.shall..be determined to be within the above-limits in accordance:with Section 2.'7.
.2- The dose rate'due to radiciodines, tritium and radioactive-materials in particulate from with half lives greater than 8 days in gaseous effluents shall'be determitied-to be within the~abova. limits in accordance with Section 2.7 by obtaining representative samples and performing analyses in accordance with the sampling-and analysis program specified in Table 2-1.
L 2-1 Rev. 21 07-01-89 1 m .1-- - - - -- - - - - - - - - _ - - - - - - - .--__--_-. _ _ _
'y l y
)
TABLE 2-1 RADIOACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM-Lower Limit.
Minimum .
of Detection Ga'seous Release. Sampling Analysis . Type- (LLD).
Type- Frequency Frequency Activity - Analysis (pCi/ml)a
.. , : A.. Waste Gas .
P . .P ,
- Storage Tank Each Tank Each Tank Principal Gamma Emitters 9 1x105' Grab Samole P P Principal Gamma Emitters 9 1x10
- B. Containment Purge Each Purgeb ,c Each Purge b 42 inch H-3 1x10
8 inch Mb .gb Principal Gamma Emitters 9 1x10
H-3 1x10
- Mb gb Principal Gamma Emitters 9 lx10-*
C'. 1. Conder.sar. Grab >
Evacuation Sample
'iystem H-3 1x10 *
- 2. Plant Vent
Stack W b ,e- gb D. All Release Types Continuous f Wd 1 131 1x1D***
as' listed in B Sampler Charcoal and C abcve. Sample I-133 1x10 2 Continuousf .Wd Principal Gamma Emitters 9 1x10 **
Sampler Particulate (I-131,Others)
Samole Concinucasf M Gross Alpha 1x10 ** i Sampler Composite Particulate Samole Continuousf Q Sr-89, Sr-90 1x10-**
Sampler Composite Particulate Samole Continuousf Noble Gas Noble Gases 1x10
- Monitor Monitor Gross Beta or Gamma E .- Incinerated Oii'h Cach batchi Each Batchi Principal Gamma Emitters 9 5x10
- Grab Sample 2-2 Rev. 21 07-01-89
=, - - _ _ . _ _ _ _ . --
S
t t F - TABLE 2-1 (Continued)
L i TABLE NOTATION-
]la.- The LLD'is the smallest concentration of radioactive material in a sample that t
will be detected with 95% probability with 5% probability of falsely concluding that ta bisnk observation represents.a "real" signal.
For a particular measurement ' system (which may include radiochemical separation)i-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 cbove (as microcurie _per unit mass or volume),
sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),
E.is-the counting efficiency (as counts per transformation),
V.is;the sample size (in units of mass or volume),
2.22 x 106 is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
f is the radioactive decay constant for the particular radionuclides, and at is the elapsed time between midpoint of sample :.oll?ction and time of counting (for plant effluents,. not environmental sample;,?.
The value of sb used in the calculation of the LLD for a particular measurement system shall be based on the actual observed variance of the I background counting rate or of the counting rate of. the blank samples (as L
appropriate) rather than on an unverified theoretically predicte ' variance.
In calculating the LLD for a radionuclides determined by gamma ray L 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 (before the fact) limit representing the capability of the measurement system and not as a costeriori (after the fact) limit for a particular measurement.*
[ *For a more complete discussion of the LLD, and other detection limits, see the i following:
L (1) HASL Procedures Enual, lim-300 (revised annually).
(2) Currie, L. A.. " Limits for Qualitative Detection and Quantitative Determination -
Application t1 Radiochemistry" Anal . Chem. 40, 586-93 (1968).
.(3) Hartwell, J. F., " Detection Limits for Radioisotopic Counting Techniques," Atlantic Richfield Hanf3rd Company Report ARH-2537 (June 22, 1972).
2-3 Rev. 21 07-01-89
3: , , ;
q .j TABLE 2-1 (Continued)
'1 L
, TABLE NOTAT'ON- i t
.."q:b. , Analyses shall also be' performed following shutdown, startup, or a THERMAL L POWER change' exceeding 15 percent of the RATED THERMAL POPER within a 1-hour -i
. period. l:(
- c. 1ritium gn sample ~s shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the '
refueling canal is flooded.
L d. Samples- shall be changed at least once per 7 days and analyses shall be completed within18 hours after changing (or after removal from sampler). '
L Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 tnalyses shall be con;1eted within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />'of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding ~ LLDs may be increased by a factor of 10.
- 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 scnpled stream flow rate shall be
- known for the time period covered by'each dose.or dose nte calculation made in accordance with Specifications 2.1, 2.2, 2.3.
- g. The princ'ipal gamma emitters for which the LLD specification'n applies ,
exclusively are the following radionuclides: Kr-87, Kr-88,'Xe-133,.Xe-133m, Xe-135, and.Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, In-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 measurable and identifiable, together with the above nuclides, shall also be identified and reported.
- h. Incinerated oil may be discharged.at paints other than the plant vent stack.
Release shall be accountad for based on pre-release grab sample data.
- 1. Samples for ir.cinerated oil releases shall be collected from representative samples of filtered oil in liquid. form.
4 1
2-4 Rev. 21 '
07-01-89
Uky
,.g~ s
.s 5 3 .i:IL? .
3
' L2.2; DOSE'- NOBLE GASES s
E ; SPECIFICATION.
- 2. 2.1; The. air dose due to noble gases: released :in gaseous .
? ,
- ~
effluents, <from' each reactor unit, frcm the site (see Figure .
2-2) shall be }imited to.the following:
- a. During any calendar.. quarter: 4 Less than or. equal to 5 mrem
- for gamma. radiation and-less than'or equal to 10 ead for beta radiation and,-
) b. During any calendar year: Less than or equal to 10 mrad for
_g amma radiation-and'less than:or equal to 20 mrad'for beta radiation, o .- APPLICABD.ITY: At all times
- 9. ACTION:
- a. With~ calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the.above limits,= in lieu of any other report required by Technical Specification m 6.9.1, prepare and submit to the Commission within 30 days, pursuant totTechnical Specification'6.9J,' a Special Report which. identifies;the cause(s) for exceeding the limit (s).and, defines <the corrective ~ actions taken to reduce releases and the proposed corrective actions to be:taken to assure that:
subsequent release,s will be in compliance with Specifica-c ,. ,
tion 2.2.1. .
SURVEILLANCE RE0UIREMENTS-
.1- Dose Calculations Cumulative dose-contributions for the current
- ca'endar quarter and curret t calendar year shall be determined in accordance with Section 2.8 at least once per 31 days.
t i
( L. 2-5 Rev. 21 07-01-E9 ,
)
i
_- ___-__-______-__a
g m -
j g .
h;, ,
s 2.3 L DOSE -~ RADIOI0 DINES; ' RADI0 ACTIVE lATERI Al.S ' f N PARTfCUlfqE FORM AND :
SPECIFICATION-2.3.1 . The dose' to an individual:from tritium, radioiodinns and b radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released, from eachi
' reactor- unit.. frpm the site (see figure 2-2); shall be limit'ed.
.to the following:
a '. . During any calendar quarter: : Less than .or equal to 7.5 ~ mrem
- to any organ and,-
- b. -During any r indar 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 of. burning contaminat2d oil.
APPLICABILI W !At all times ACTION:
- a. With the calculated dose from the release bf tritium, radiciodines, 'and radioactive materials in particulate form,
'with half livcs greater than 8' days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Technical Specification 6.9.1, prepare-and submit.to the Commissi'on within 30. days' pursuant to Technical Specification 6.9.2 a Special Report which identifies the
- *
- cause(s) for exceeding the' limit and defines the corrective actions taken to~ reduce releases and the proposed actions.to be taken to assure that subsequent releases will be in compliance with Specification 2.3.1 H SURVEILLANCE RE0VIREMENTS
.1 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar. year shall be determined in accordance with Section 2.8 at least once per 31 days.
2-6 Rev. 21 07-01-89
U~ ; ?
wy e' -; , _
,i ~ -- 2 .' 4 GASE0US RADWASTE TREATMENT 7
,j SPECIFICATION k .
2.4;l The GASEOUS'RADWASTE TREATMENT SYSTEM and the w
F' VENTILATION EXHAUST TREATMENT SYSTEM shall be'0PERABLE.
~
The appropriate portions of the GASE0US RA0 WASTE TREATMENT. SYSTEM shall be used to reduce radioactive -
materials in. gaseous waste prior to their discharge when the projected gaseous effluent air doses due to: ,
. gaseous effluent releases from the site (see Figure 2-2),.when averaged over 31. days, would exceed-0.2 mrad for gamma radiation and 0.4 mrad for beta' radiation.
The~ appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce. radioactive materials _'in gaseous' waste prior to .their discharge U , when the projected dosesi due to gaseous' effluent releases from the site (see Figure 2-2) when averaged-
'over 31 days would exceed 03 rtrem to any organ.*
APPLICABILITY: At all times s
ACTION: .
- a. 'With the GASE0US RADWASTE TREATMENT SYSTEM and/or the VENTILATIONEXHAUSTTREATMENTS1STEMinoperable~for more than 31 days or with gaseous waste being discharged.without treatment and in excess of the above
. limits, in lieu of any other report required by Technical Specificai .on 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. Identification of the inoperable equipment er subsystems and the reason for inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and -
- 3. Summary description of action (s) taken to prevent a recurrence.
SURVEILLANCE RE0VIREMENTS l-h .1 Doses due to gaseous releases from the site shall be projected I
at least once per 31 days, in accordance with Section 3.2.
.2 The GASEOUS RA0 WASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by operating i L the GASE0US RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15 3.
minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.
- These doses are per reactor unit.
2-7 Rev. 21 07-01-89
r: .
2.5 ~ TOTAL 00jiE l
SPECIFICATION y 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 j less than or equal to 25 mrem to the total body or any, i 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 limit:, 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 Commission, Washington, D.C. 20555, within 30. days, ,
which defines the corrective action to be taken to i 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) l covered by this report. If the estimated dose (s) exceeds the limits of Specification 2.5.1, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of paragrcph 190.11(b).
Submittal of the report is considered a timely request, l 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 RE0VIREMENTS
.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.
2-8 Rev. 21 07-01-89
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> 2.0 . GASEOUS EFFLUENTS.
.. 2 .' 6 Methods ' Calculation fer Gaseous Effluent Monitor Setooints i%
! Administrative v' alues 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 y and revisd as required.:
2.6.1 PLANT VENT STACK - 2/3RT-780s, 2RT-7865-1, 3RT-7865-1 m 2.6.1.1 2/3RT-7808 - Plant Vent Stack Monitor t.*
For the purpose of implementation of Specification'2.1.1, i the alarm setpoint level for noble gas monitors '.15. based on the gaseous effluent flow rate and the meteorological i dispersion. factor; Total Body
-The concentration at the detector corresponding to a t- -
500 mrem /yr. total body dose rate at the exclusion area- !
boundary'is' determined by:
I C (0.45)(2120 'hsec)(500 mrem /yr)(10"m*/cc) (2-1) det - (Flow rate, cfm) (X/Q, sec/m")[I (K ,g mrem /vr) ( __qj_ )]
i pCi/m* C tot j i
Where: !
C det
- the instantaneous concentration at the detector, i pCi/cc an administrative value used to account for O.45 -
j potential activity from other gaseous release pathways
'1 2-10 Rev. 21 l' 07-01-89
' 1
._i____._________._. _ . _ _ . I
my y.p~ ,
m y a
r
- 2. 6 ; 1.: PLANT VENT STAC_K -: 2/3RT--7808, 2RT-7865-1, 3RT-7865-l' K -
- (Continued).-
the total body dose conversion factor for'theLi th-Kj; = q f ,
L.
E
.ganma emitting noble gas, mrem /yr per; Ci/ms, from Table'2-4 1
1 th noble gas, as determined ' '
3 14 Cj =
Concentration of theLi 7,
by sample analysis, pCi/cc C
tot
- Total concentration. of_ noble gases,- as determined '
' by. sample analysis, (kCi/cc) = IC 4 'l 1
1
~ Flow Rate . the plant vent ' flow rate,' cim:
= -83,000 cfm/ fan (x no. of' fans"to.be run) -
+ 17,500 cfm (laundry facility) i i
2120 - conversion constant, cfm per m_8/sec .l .
1 500 mrem /yr - total body dose rate-limit, as specified by '
j Specification 2.1.1.a j 1
j X/Q = historical annual average dispersion factor, !
seC/ms
- 4.8E-6 sec/ms Skin .l l
The concentration at the detector corresponding to a- y 3000 mrem /yr skin dose rate at the exclusion area boundary i
.is determined by: j l
(0.45)(2120 m* c
) (3000 mrem /yr) (10" m*/cc)
C (2-2) det - (Flow rate, cfm) (X/Q, sec/m*)[I(L 4 + 1.1Mj , mrem /vr)( _qj._ )) j i pCi/m* C tot i
2-11 Rev. 21 )
07-01-89 1
7 l
)c; - 2.6.1.
' PLANT' VENT STACK:- 2/3RT-7808, 2RT-7865-1, 3RT-7865-1(Continued)-
I [p; Wilere:
-s Lg - Skin Dose Conversion factor for the i th noble gas, mrem /yr per uCi/ms, from Table 2-4 Mj Air Dose Conversion Factor for the i th noble gas, mrem /yr per uC1/ms, from Table '2-4 i.
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 1
Other values in equation (2-2) are defined in equation (2-1).
J The smaller of the values of C det from equations (2-1) or (2-2) is to be used in the determination of the maximum permissible monitor alarm 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 permissible alarm setpoint is the value
" 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 terms of gCi/cc/ cpm).
!~ The alarm setpoint will be maintained at a value not greater than the maximum permissible alarm setpoint.
l l 2-12 Rev. 21
(
07-01-89 I
l
tjy w 4' '
V1 <
.)
l '
~
1 )
- t
[ l" 2.6.1 ' PLANT VENT STACK - 2/3RT-7808, 2RT-7865-1, 3RT-7865-1 '(Continued)L
, If 'there is no release associated with this monitor, the monitor . .
x .. vv
[if,;L setpoint should be established as close as practical to background lto prevent spurious alarms and yet assure an alarm
- should inadvertent release occur.
1 2.6.1.2 2RT-7865-l'and 3RT-7865-1 Wide Rance Gas Monitors The-maximum release rate ( Ci/sec) for Wide Range Gas.
- Monitors is determined by converting the concentration at
' the detector, Cdet (gCi/cc) to an equivalent release rate:in gC1/sec,'as follows:
~
A max . 10deta PC1/cc)(flowrate. cc/sec) (2-3)-
2.
Where:
.A max
- the maximum permissible release rate, pCi/sec
'C det := the smaller of the values of C det btained from equations (2-1) or (2-2).
Flow Rate - flow rate, cc/sec
= (3.917 x 10 cc/sec per fan) 8 (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 determined above, when this monitor is being used to meet threquirements of Specification 2.1.1.1.
2-13 Rev. 21 07-01-89
p s .
1 2.6.I' PLANT' VENT STAE - 2/3RT-7808,L2RT-7865-1, 3RT-7865-1 (Continued) i _
1 If there-is no release associated with this nonitor, the.
Mp monitor setpoint should be established as close as practical 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 L' -
2.6.2.1 2RT-7810 and 3RT-7818 Condenser Air E.iector Monitors For the purpose of implementation of Specification 2.1.1, the alarm 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 l
' is determined.by using:
Total Body C ( - )( sec) ( 500 mrem /yr) (10" m*/cc) (2-4)'
def;)(Flowrate,cfm)(X/Q,.sec/ms)[I(K,meem/vr)(_qt_.));
g i pCi/m" C tot The concentration at the detector corresponding to a 3000 mrem /yr skin dose rate at the exclusion area boundary L is determined by using:
Skin C (0.1)(0.5)(2120 Cf*,,c)(3000 mrem /yr)(10'm*/cc) (2-4a) det - (Flow rate, cfm) (X/Q, sec/m8)[I(L 4 + 1.1M$ , mrem /vr)( _(j_)]
i gCi/m* C tot-l 2-14 Rev. 21 07-01-89
" o m ,
I z 2.. 6 . 2 CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-l', 3RT-7838'or g; y -
3RT-7870 (Continued). -
h <
Where:
h 9 ,
0.1 is an administrative value used.to account for y
potential- activit; from _other gaseous release pathways.
q a
0.5 is an administrative value used to account for I 1
releases from both SONGS 2 and SONGS 3 condenser air -
'l 1
L' ~
ejectors simultaneously. Other parameters ~are specified -l
.in.2.6.1.1, above.
det from equations (2-4) or
- The smaller of the values C (2-4a) is to be used in determining the maximum permissible {
L l
monitor alarm setpoint (cpm), as follows:.
i The maximum permissible alarm setting (cpm) is-determined by using the calibration constant for- -]
q the corresponding Condenser Evacuation System Monitor- !
given in Table 2-3. The maximum permissible alarm setpoint. is the cpm value corresponding to the concentration, Cdet, [ smaller value from equation (2-4) or (2-4a)].
l The calibration constant used is based on Kr-85 or on )
Xe-133, whichever yields a lower detection efficiency (higher value in terms of uti/cc/ cpm). The 2
alarm setpoint will not be set greater than the maximum permissible alarm setting determined above.
l l
2-15 Rev. 21 07-01-89 !
a V!
- q:
'tr , ,
2.6.2- : CONDENSER EVACUATION SYSTEM - 2RT-7818, 2RT-7870-l', 3RT-7818 or 3RT-7870-1 -(Continued)
If there is no' release ~ associated'with this monitor, o the monitor'setpoint should be established as close as practical to bac'kground to prevent' spurious alarms yet assure an alarm should an inadvertent release occur.
2.'6.2.2 2RT-7870-l'and 3RT-7870-1 Wide Ranoe Gas Monitors
' The maximurr release rate (pCi/sec) for Wide Range Gas Monitor is determined by converting theLconcentration at the detector, Cdet (uCi/cc), to an equivalent release rate in pCi/sec.
A max = (Cdet, Ci/cc) (flow rate, cc/sec)
.Where:-
A max
- the maximum permissible release rate, Ci/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-
- 4.719E5 cc/sec (conservatively assumed as design flow rate)
If there is no release 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.
2-16 Rev. 21 07-01-89
= _ - - _
it. ~
1 s g n g LL .' , 2.6.3 . CONTAINMENT PURGE -L2RTa7828,E3RT-7828, 2RT-7865, 3RT-7865-x u
For the purpose of implementation of Specific'ationl2.1.1, y
- the alarm setpoint level for, noble ' gas monitors is' based on u . m.
p: -the. gaseous; 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 boundary 'is P ' determined by using:
i Total Bodv' f
C (O'.45)(P)(2120 ,f/ ec )-('500Lmrem/yr) l10" m*/cc)-
(2-6).
det2 -(Flow rate .cfm)-(X/Q, sec/m")[I (K g, mrem /vr) ( _Cj_ )]-
- i. gCi/m* C tot C (0.45)(P3)(2120 ,$/ ec ( 500 mre#yr)-(10" m*/cc)' .(2-7) det3 -(Flow rate, cfm)-(X/Q, sec/m")[I (K g,-mrem /vr) ( _qj_-))
i-uCi/m* C tot The, concentration at the detector corresponding to a 3000 mrem /yr skin dose rate at the exclusion area boundary is determined by using:
.S. kin f
C (0.45)(P )(2120 ,f[,c)(3000 f mrem /yr)(10"m*/cc) (2-6a) det2 -(Flow rate, cfm) {X/Q, sec/ms)[r(L g + 1.1Mg , mrem /vr)( _Ci_ ))
i pCi/m* C tot f
C (0.45)(Ps)(2120 ,$j[,c ) (3000 mrem /yr) (10" m*/cc) (2-7a) det3 -(Flew rate, cfm) (X/Q, sec/m"){I(L g + 1.1M , mrem /vr)( _Gj_ ))
i Ci/m* C tot i
2-17 Rev. 21 07-01-89 4 1
- g ac: ,
,. j m
7 ,
s q
4 / '-
(Tf" ,j U > >
I
( m 2.'6. 3 ~ : CONTAINMENT PURGE '- 2RT-7828, 3RT-7828, 2RT-7865, 3RT-78ti5 y ,,' , .(Continued).
e a p e . .
- h. where::
' ,Cdet2 - The instantaneous corr,entration'of the Unit 2 detector.
[bf"/ in pCi/cc.
h k ,
Cdet3 = The instantaneous concentration of the Unit 3 detector
- in pCi/cc.
s
(, , 0.45 is an administrative values used to account for potential .
y'
activity from other gaseous release pathwa.ys..
e
.P2 and P are administrative values used to account for .
simultaneous purges of both SONGS 2 and SONGS 3. The fractions P2 and Ps.will be assigned such-that e P2 + Ps s l'.0.
-Flow rate = 'the observed maximum flowrate in efm 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- the smaller. design-flowrates.
Other parameters are as specified in 2.6.1.1 above.
The smaller of the values of maximum permissible f.det2 from equaticn (2-6) or (2-6a) and C det3 from equations (;!-7) or (2-7a) is to be used in determining the maximum permissible monitor alarm setpoints.
2-18 Rev. 21 07-01-89
_________________ Q
m;
. u _y p %, '
l
~
?
M - 2. 6. 3.. CONTAINMENT PURGE '2RT-7828, 3RT-7828, 2RT-7865, 3RT-7865
_ ..(Continued).
y B ' 2.6.3.I' Maximum' Permissible Alarm Settino -(RT-7865) cT'he maximum permissible l alarm setting for the: Wide Range Gas Monitor expressed as a. maximum release rate (pCi/sec),is L-determined by converting-the' concentration at the detector, Cdet' (pC1/cc),to an _ equivalent- release rate in gCi/sec.
p A max = (Cdet, pCi/cc) (flow rate, cc/sec)
Where:.-
A max
= the maximam permissible release rate Cdet - the smallor' value of Cdet' as obtained from equation (2-6, 2-6a) for Unit 2 or (2-7, 2-7a) for Unit 3.
flow rate = flow rate, cc/sec ,
= either 1.416E6 cc/sec for mini-purge-or
.2.360E7 cc/sec for main purge.
L
.2 Maximum Permissible Alarm Settina (2RT-7828)
The maximum permissible alarm setting for 2RT-7828 is in gCi/cc and is the smaller of the values of Cdet2 (gCi/cc) from equations-(2-6) and (2-6a).
If there is no release 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 19 Rev. 21 07-01-89 l
ll l;
f -
_. _ _ _ - _a
p" W p .
c n.
h ;2.6.4L
' WASTE GAS HEADER: . 3-7865 0 2/3RT-7808-'-
For the purpose of Specification 2.1;1, the alarm setp'oint-
~
, .leve1L forL noble gas monitors is'. based on the gaseous effluent.
,y flow rate and the meteorological dispersion . factor. Since the waste gas header discharges to the plant vent stack,:either l 3RT-7865.or 2/3RT-7808 may be used to monitor waste gas:headerg releases.
The concentration at the detector corresponding to a~ total body; dose rate of 500 mrem /yr or a skin dose rate of 3000 mrern/yr at the exclusion area boundary is determined by using equations (2-1)
- or:(2-2) with sample concentration (C $) 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 maxhnum permissible alarm setting (cpm) is determined
-by using the calibration constant for plant vent stack monitor 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)).
r 2 20 Rev. 21 07-0149
m " - -
~
is ,
n
.l J. '!
hls@ g',l1 12.' 6. 4, ' WASTE' GAS ~ HEADER.-:3-7865,2/3RT-7808L(Continued)L )
- w' ' - s g )RT-7865 l 1 m.,.
x , ep t '
The maximum ~ permissible alarm setting..is expressed asa 7 % '
maximum release rate (pCi/sec) and is determined by converting:the concentration at'the detector, C det' ste.in'Ci/sec by:
~
to.'an~ equivalent releas'e -I l
. equation (2-8).
6 A
max " $ det. uti/cc) (flowrate cc/sec) . (2-8)
\
2 K ,
, .Where:
Adet_ = tLe maximum permissible release rate, pCi/sec
~
det - the smaller vaita of Cdet, as obtained from C
. equation (2-1) or (2-2). 'i li flowrate - flowrate, cc/sec j
- 7.83E7 cc/sec for 2 fan operation or 3.92E7'cc/sec for 1 fan _ operation 2 - corrects for: 3.-7865 viewing only 1/2 the total Plant Vent Stack Flon'.
A release from the waste gas header is not possible iff
.1
.I (fC){4 f
y
),Cdet (2-9) b
,l 1
1 i
l 2-21 Re'v. 21 07-01-89 ;
i I
'i
[7 4; ;x ,
R ei}
J.; ; ' " " 4 I# 'c ,
12l641.: WASTE GAS' HERDER 3-7865; 2/3RT-7808--(Continu'ed) 1"I 2.6.4.1--(Continued)=
- u. -
t- -
- ~
Where't x -
IC 4.= ' total concentration in' waste-
'i a gas holdup: tank to bedreleased
- I L ,
f: waste" gas header effluent flow ~ rate, cfm fN ,
F p1 ant. vent stack flowrateLin efm.(166,000'cfm-
, for 2 fan operation; 83,000 for lefan operation) + 17,500 cfm (laundry facility)
C from det - smaller of the values of C det
"< equation (2-[)er(?-2)withC $being '
obtained from the. waste gas holdup. tank:
to be released If a release is not possible, adjust the waste gas header flow '
'by determining the maximum permissible waste gas header effluent flow rats corresponding to the Vent Stack Monitor setpoint in accordance with the following:
f < (0.9)(Cdet)(F): .(2-10)'
z C; i
Where:
l f- waste gas header effluent flow rate (cfm) i h ^F= plant vent stack flow rate (cfm) used in equation (2-1) or (2-2) i
[.
$01 9 g
l l.
pp -
- gr n=
n.: . ,
n.
is y ' ,l '
2M.4L MASTE GAS HEADER -- 3-7865, 2/3RT-7808; (Continued) h N ... .
..2.6.4.1 i: c
].t. ' - -
(Continued)~
i Cdet "' the smaller ofL the value of: Cdet 'from~
I, ,
. equation (2-1) or i (2-2)
I C g: =' tota'l gamma activity ('Ci/cc) of.the i
s- waste ' gas f holdup; tank to be released,
~ '
'asidetermined from the pre-release. sample analysis, i- The 0.9 'is. an administrative value to account' for the. potential activity from other releases in the.same' release pathway.
(.
h.
u L
2-23 Rev. 21 07-01-89
=- - - - - - - - - - - - - -
g&@ '
-V -- -
- ' -- ,t#
yGq , ,< ,, ,
L r
- t. ;
s}.m;. ,", , ,
a Myn%
m* , ,
a i j o .iy.3 Table'2-3(a)- ,
ne y >w'
- 4 "
Gaseous Effluent Radiation' Monitor'
~
y ,
Calibration Constants ~'
44 V '1, (pCi/cc/ cpm) pe,p-H , i.
7 -,
l E,f l
+
-MONITOR'- Kr-85 Xed33 ' r, H d ? 'f. ! k ?
v ,
3
-1 .,
1
. ; j ,'
r,,,, L
_ i 2/3RT-7808C :. '3 84E-8.. -
7.06E , .(.
? '
J 2RT-7818A. !4.27E-8'- 6.63E-8 9 2RT-78188- 7.31E-5 2 07E-5.
. i
,3RT-7818A- 3.i3E-8 5.09E 8 L.
- 3RT-78188 '- -9.31E-5 ~2 .212-5: .
- t. .,
, 9, a
a . . .i't y J
p
.g h
i . v i i
a
'l
.j 1
J H
i.
. p; i
1
.4
'l (a)This table provides typical ( 20%) calibration constants for the gaseous effluent radiation monitors. ,
1 1
2-24 Rev. 21 07-01-89 e
_____--__---_----_--__-___m
'_f t
, ,, z
..,,.,.m W -- '
'C '
1 b21 ~ Gaseous Effluent Dose Rate "
>J s ,, .
L, <,
fThe;methodo1'ogy. used for the purpose -ofJ implementation'of
- e. .
lj r * ' ~
Specification'251 6 for the. dose rate above'b'ackground 4
<to an individual in an' unrestricted area:is calculated by using the following expressions:
o
~
2 l. 7 '.1 FOR NOBLE GASES:. ,
y ,
}', . K j.(X/Q) Q $ - (2-11)'
W. D. TB "=r1 -
k , ,
D- "'E (b (2a12) s 1- i +~I'IN )i (X/Q) Q-4_
Where:
b = total body dose rate. in unrestricted areas due TD to radioactive materials released in gaseous:-
effluents, in mrem /yr i
b s
= su n dose rate in unrestricted areas due to radioactive raterials, released in gaseNs effluents, in mrem /yr the total body dose facter due to gamma K -
4 emissions for each identified noble gas a
radiow clide, i, in mrem /yr per Ci/m' from 76ble 2-4. ;
i 2-25 Rev. 21 ,
07-01-89 j w ,
4
.p_
_ _ . _ _ _ - - _ _ _ _ . ~ _ . _ -- .__.- _.-.-._ a
y m ; .m - , ,, c ,
- 1 n=;~ m ,
,s p; : i A
fhp <
x 4 2.7+1: FORE NOBLE GA'Esi-S (Continued)-
~""
s""
Wu 7 g vp c .y '
q ,
~
b , $$k ' k ,
l: i -wskinLdosv factor due.to the beta emissions forr
~
p,(? ,
each identified noble: gas radionuclid'e,.1, in ,
6 m 7 > mrem /pr per $Ci/m* from Table 2-4 ~
af ,
- q. y
+
7 f" ~
s .
,M9 + ; the' air dose factor due to gainma; emissions 1for; '
I;; -
each identified; noble -gas radionuclides, i', ini o.
f '
~
-(
sv t
in:ra'd/yr per pC1/m* : from Table 2-4. , '
E ,
-(conversion constant of 1.1 mrem / mrad. converts c ,,
i '
S ~ air dose to' skin dose.)- ea e
~
hg '= the rplease - rate 'of radionuclides, i, . in;
- gaseous effluents in pCi/sec'
%, .Tf/ W '= '4.8E-C sec/m*.
The maximum annual average atmospheric dispersion factor for-
- any sector or distance at or beyond the
. unrestricted area- bound try.
s
(,
'2.7.2 FOR ALL:RADIOI0 DINES. TRITIUM AND FOR ALL:RADI0 ACTIVE.
e MATERIALS'IN PARTICULATE FORM WITH HALF LIVES GREATER
'THAN'EIGHT DAYS:
- . . c
=
D, zi '[I k(Pik' k)~Oi l (2'I3)
Where:
a bo = organ dose rate in unrestricted areas due to e i
4; radioactive materials released in gaseous m
efG uents, in mrem /yr
-c
. 2-26 Rev. 21 07-01-89
)
, , ; D:: , . . , : ,
g-,
_- ---- y
.g
[ '
. p. 4 4 _
r i l i b?
,;4 f :l t 4
s j;
>j Ji p ', ?y; ,
- 2. 7.;2 N .FOR A'll RADIOI0 DINES. TRITIUM-AND FOR All. RADIOACTIVE.
L' .
.. W " '
MATT' RIALS IN PARTICULATE FORM WITH HALF LIVES GREATER (r,- [e" THAN EIGHT DAYS:'- (Continued)
- . at h[' ,
h:j = the release rate of radionuclides, i,.in gaseous effluents in.pci/sec h P = t.he dose parameter for radionuclides, i,.for ik I. pathway, k, from Table 2-3 for the inhalation -
pathway in mrem /yr per pri/m8 -
The-do~se;
'r
~
' factors are based on the critical individual organ and the child age group.
p U
k
= the highest. calculated annus1 average v, dispersion parameter for estimating the dose to an individual. at or beyond the
/
unrestricted area boundary for pathway .k.
- 4.8E-6 sec/ms for the. inhalation patcway.
e The incation is the unrestricted area in the
, Mi sector.
L 4.3E-8 m9 for the food and ground plane
~
pathways. The location'is the unrestricted
. area in the E sector.
u-e 2-27 Rev. 21 07-01-89 ,
l
mw L- , ,
s f
- e. m ib[ . c .
'i l , ,
.c
' ' ., c; I2. 8 7 Gaseous' Effluent Dose Calculation ,
p@!y.hhf t*.. . >
4 q 1 ~
g y.y, 2'.8.10 ' DOSE ~FROM NOBLE GASES IN GASEOUS EFFLUENTS
..N r'.my'&
?
l .y - The air:aose in unrestricted areas.dueltofnobl.'egases 1 l.
%v '
, , . released;in gaseous effluents-is calculated using the; i.; , ' following ; expres sions: . 1 ,
~
3.. 0, ' , . 2.8.1.1l' ;For historical meteoroloav:
7 i
D 7.
3.17x10 I M$ [ (X/Q) Qg ]
g c(2-14)~
3.17x10 I N4 [ (X/Q) Q4 )-
.Dg -
(2-15)
I siL " Where:
D -
the total projected gama air dose from gaseous '
- t; -7 f
effluents, in mrad
-D - 'the total projected b' eta air' dose from gaseous
- effluents, in mrad
,e 3.17x107 ' - (inverse. seconds per year)
M = the air dose factor due to gamma' emissions for 4
each identified noble gas radionuclides, i, in mrad /yr per pCi/m' from Table 2 Ng - the a'1r dose due to beta emissions for each identified noble gas radionuclides, i, in mrad /yr
[ per pCi/m* from Table 2-4 2-28 Rev. 21 07-01-89
>b a
a un ,
c
! t i
( n K',o x 2, .
- 2. 8.1.1. For historica1 meteroloov: (Continued) g ,
.E.
4, '
atmospheric disparsion factor forany ' sector or;
. distance at'or.beyond theiunrestricted area boundary. < ,
. s .
$ . gQ: ,- the' amount of. noble' gas radionuclides, i, released in; gaseous t effluents!in C1.
L5 : ' ' 2'.8.1.2 For meteoroloav concurrent 'with release:
?
D,, =1.14x10rM[I(at.(X/Q)3,hj3)]
4 3 (2-16)_
D p =.1.14x10'*r N g [I (ot3 (X/Q)3, h )]
$3 (2-17)'
Where:
0,, - - the total gamma air dose from gaseous effluents in sector e, in mrad -
D g .the total beta air dose from gaseous '
effluents in sector e, in mrad h
p Mg = the air. dose. factor due'to gamma emissions
< for each identified noble: gas radionuclides, i, in mrad /yr per pCi/m* from Tab 1 A 2-4.
Ng = the air dose factor due to' beta emissions for each identified noble gas radionuclides, i, in mrad /yr per uti/m* fron Table 2-4.
2-29 Rev. 21 07-01-89 f
75 7 c, 9 a'
, Tjl: t E! -
- 2. 8.'I . 2 - .ForL met.qc.rolooy t cor.cyrrent with release: (Continued) q q f.[
at) .
-Lthe 1bngth of-the jth time period over which'(X/Q)3,andQ43=are averaged.-for gaseous releases..in hours
' : a the atmospheric dispersion factor for
'(X/Q)3, time period at) at exclusion boundary location -
in sectorfe: determined by.~. concurrent-r meteorology,!in sec/m*
Q,3 . the average. release rate of radionuclides, i, in gesaous effluents during time period .
at), in pCi/sec 2.8.2- DOSE FROM TRITIUM. RADIOI'0 DINES AND RADI0 ACTIVE
[4ATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN 8 DAYS IN GASEOUS EFFLVENTS 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 meteoroloov:
t Dg -
3.17x10 *Z [(IR ikNk) 0 1) (2-18) i k K
2-30 Rev. 21 07-01-89 l-L lt w
~b-g
,yl:l '? t * '
t 3,'
j >s l y ' ,
- y_?.fl-n .1
-ys ] .
I
[ , %,yg Q y, ' 2.8.2.1: For historical meteoroloovn (Continued) 4.
,1, g) -s-Where:
[' g' + '
E the. total projected dose' from gaseous:
) ![ ' D o
7
' gl , ,
effluentsito an indivi<iual i in mrem g , Qg == the amount cf each radionuclides,;i,-
t,, '
S' (tritium,radiciodine, radioactive-g
, material.I.in particulate form with half-
- y s
- lives greater than eight days), released:
9; in gaseous effluents.in pCi _
RikNk- - the sum of allipathways k~ for radionuclides,
, 1, of-the R ,g W product in mrem /yr'per
.~pCi/sec. The I RikNkvalue for each k
radionuclides, i', is given;in-Table 2-6.
The given is the maximu:a z R
. . k ikN k f r all locations'and is based on the most t ,
restrictive age groups.
R ik. the dose factor for each identified' 4
radionuclides,1, for pathway k (for the e inhalation' pathway in mrem /yr per pCi/m*
h and for the food and ground plane' pathways in m' - mrem /yr per pCi/sec) at'the controlling location. .The R ik 's for each contro11'ing location for each age group are .
I given in Tables 2-7 thru 2-16.
f 2 31 Rev. 21 07-02 89 t
e ,w y
(< l
\b' m
4 y..
, g m. ,
2.8.2.1) For'historici1 meteoroloov: .(Continued)
W := the annual average- dispersion parameter for - -
[h. ., k
??
. estimating the~ dose to an individual at'the ,
s controlling location for pathway k.
g
- (X/Q)' for the inhalation pathway in sec/ms.
p..
, The (X/Q) for each contro111ng' location is:
given in Tables 2-7 thru 2-16.
w (D/Q) for the food and groun'd plane pathways in m. 'The (D/Q) for each controlling location are given in Tables 2-7 thru 2-16.
r-2.8.'2.2 - Ear meteoroloav concurrent with releases:-
- 1. m n . . .
D'g 1.14 x 10 E I E [(at )3 (Rgg)'(Wjke) ' (Oij)) (2-19)_
v:c.
Where:
D, = ~ the total annual dose from gaseous effluents to an-individual in sector e in mrem. -I the length of the j th period over which.Wjke and
'at) 1 are averaged for gaseous released in hours
.Q
$3 Q = the average release rate of radionuclides, i, in 43 gaseous effluents during time period at 3 ni pCi/sec 2-32 Rev. 21 07-01-89
. t .-
C-
y=- -
g' ,
m '
!p - <
~
-2.8.2.2. ' For meteoroloav concurrent with releasesi (Continued).
f ,
j ~'
Rike;= the ' dose factor for each ^ identified radionuclides'i,,
for. pathway k for sector el(for the inhalation-1
.pathwayfin mrem /yr per gC1/m' and for.the food .and ground plane p'athways . in_ m' mrem /yr per, z gCi/sec) at the controlling location...A listing ofi Ri 'k for the controlling'. locations in each landward:.
sector for each. group is given in Table's 2-7 thru-2-16. . The e is determined by the concurrent-meteorology.
Wjke = the dispersion parameter for the time period aty for each pathway k for calculating the dose to an individual. at the controlling location in sector el '!
f L using concurrent meteorological conditions.
L
= (X/Q). for the inhalation pathway'in sec/m'
= (D/Q) for the food and ground p1'ane pathways in m-
4 l'
2-33 Rev. 21 07-01-89
n ic,
, 4
- ' ji
~
TABLE 2-4 m . DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS **
Q-
, Total. Body Dose -Skin Dose Gamma Air Dose Beta Air Dose
' Factor K Factor L i ' Factor M i Factor N Radio- i (mrem /yr. -(mrem /yr i (mrad /yr (mrad /yr Nuclide per.pCi/m*) per Ci/m*)- per C1/m*) per Ci/m*)
Kr-85m- I I.17E3*-- l'.46E3 - 1.23E3- 1.97E3 Kr-85 .1.61El l'. 34 E3 - 1.72E1 ~1.95E3 Kr-87 5.92E3- 9.73E3 6.17E3 1.03E4 Kr-88 1.47E4 2.37E3 '.52E4 2.93E3 Xe-131m 9.15El' 4.76E2 1.56E2 1.11E3
< Xe-133m 2.51E2 '9.94E2 3.27E2 1.48E3 Xe-133 2.94E2 3.06E2 3.53E2 1.05E3 Xe-135m 3.12E3' 7.11E2 3.36E3 7.39E2 Xe-13 5 '- 1.81E3 1.86E3 1.92E3 2.46E3' Xe-138 8.83E3 4.13E3 9.21E3 4.75E3 Ar-41 8.84E3 2.69E3 9.30E3 3.28E3.
a L
- 1.17E3 = 1.17 x 10 8
- source: USNRC Reg. Guide 1.109, Table B-1 1
2-34 Rev. 21 07-01-89 L _ . _ _ _ _ _ _ - - _ _ _ _ .
7.
bs > ' i
- ,..~,
TABLE 2-5, p.
L' -
DOSE PARAMETER P * "
ik I9 , ,h ; CHILD' AGE GROUP
' CRITICAL ORGAN t,
~
.-(mrem
' Inhalation Pathway)-Radionuclides Inhalation. Pathwag Radionuclides /yrLper pCi/m (mrem /yr per pCi/m ).
b 'H-3 1.1E3 I -131- 15E7
'Cr-51; 1.7E4~ I'-132 1.9E5 I .Mn-54 1.6E6 I -133 3.8E6 i
Co-57 5.1E5 I -134 5'1E4 Co-58 1.1E6- I -135- .7.9E5
.Co-60 7.1E6- Cs-134 1.0E6 Sr-89 2.2E6- Cs-116 1.7ES
-Sr-90 1.0E8 Cs-137 9.1E5 Zr-95. 2.2E6 Ba-140 1.7E6' Nb-95 6.1E5 Ce-141 5.4E5.
Te-129m 1.8E6 Ce-144 1.2E7:
'* Source: USNRC NUREG-0133, Section 5.2.1.1 2-35 Rev. 21 07-01-89
c.. .
W 4 TABLE 2 h CONTROLLING' LOCATION FACTORS a .t y Z:RikWk k
Radionuc1'de'i mrem /yr per uCi/sec
, H -3 9.62E-4 Cr 1.58E-2.
Mn-54 4.02E0.
Co-57 9.95E-1 Co-58 1.16E0 Co 6.14E1 Sr-89 4.34El-t Sr-90 1.82E3 Zr-95 1.66E0 Nb-95 6.81E0 Ta-129m 4.90E0 Cs-134 3.36El ,,
Cs-136 5.73E-1 Cs-137 3.08E1 Ba-140 2.28E-1 Ce-141 5.74E-1 Ce-144 1.68E1 I -131 2.16E1 I -133 2.82E0 I -135 5.92E-1 UN-ID 3.53E0 i
Footnote:- These values to be used in manual calculations are the maximum ERikN kf r all locations based on the most restrictive age group.
k 2-36 Rev. 21 07-01-89
IAB.LL2-Z
, DOSE. PARAMETER Rj.FOR SECTOR P
, W Page'1 of 2
- n. y -1 g . Pathway. . Surf Beach Distance = 0.4 miles Mg X/Q.-~l'.8E-6 sec/m*- D/Q = 8.2E-9 m '
Infant Child Teen Adult Inhala- Food & Inhala- Food &: Inhala-- Food & Inhala- Food &
Radio-- tion Ground tion Ground. tion Ground tion ' Ground' N Nuclide Pathway Pathway Pathway . Pathway Pathway Pathwey Pathway' Pathway .
H'3-1.2E1 - '5.1El 8.7El Cr-51 - O'- - l'.1 El 2.2E4 1.2E2 1.1E5 2.3E2 3'.2E5
, Mn-54 4.5E2 6.6E6 2.7E3 1.2E7 5.3E3 9.5E7 Co-57 - ' 0-1.4E2 1.6E6- 1.3E3 7.)E6 2.2E3' 2.3E7' Co-58 -0 . .3.6E2 1.8E6 3.8E3 8.7E6 7.3E3 2.6E7 Co-60 - 1.0E3 1.0E8 ; 1'. 0E4 4.9E8 2.0E4' 1.5E9 Sr-89 -0 ' 6.2E3 1.0E2 - 1.8E4 .4.9E2 2.1E4 1.5E3 Sr-90 l'.1E6 4.4E6 . 6.8E6 Zr-95 6.3E2 1.2E6 6.0E3 5.8E6 1.0E4 1.7E7 Nb-95 3.8E2 6.6ES 3.9E3- 3.1E6 7.1E3 9.4E6 Te-129m - 5.2E2 9.4E4 2.1E3 4.5E5 2.5E3 1.3E6 Cs-134 - 1.1E4 3.3E7 4.5E4 1.6E8 5.8E4 4.7E8 Cs-136 . 1.8E3' 7.2E5 7.8E3 3.4E6 1.0E4 1.0E7 Cs-137 8.6E3 4.9E7 3.4E4 2.4E8 4.3E4 - 7.1E8 Ba-140 -7,7E2 9.9E4 9.2E3 4.7E5 1.5E4 1.4E6 Ce-141' - 5.9E2 6.6E4 5.1E3 3.1E5 8.2E3 9.4E5 Ce-144 4.0E3 3.3E5 3.5E4 1.6E6 5.6E4 4.8E6 I -131- 1.7E5 8.3E4 5.9E5 3.9E5 8.2E5 1.2E6 I -133 4.0E4 1.?E4 .1.2E5 5.6E4 1.5E5 1.7E5 I -135 8.2E3 1.2E4 2.5E4 5.8E4 3.1E4 1.7E5 UN-ID. 1.2E3 3.6E6 5.4E3 1.7E7 7.1E3 5.1E7 4
Inhalation Pathway, units = ]j"(!"
Food & Ground Pathway, units = (m r "
j c 2-37 Rev. 21 07-01-89
- - - - , - - . - - . - - - - - - - - - - - - - - _ ___-____---._a __ &
?
TABLE 2-7 DOSE PARAMETER Rj FOR SECTOR P Page 2 of 2
~
Pathway - Former Nixon Estate (no_ garden) Distance = 2.8 miles X/Q = 1.2E-7 sec/m*' D/Q = 3.4E-10 m-'
Infant- Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio-- tien Ground tion Ground tion Ground tion Ground Nuclide Pathway.- Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5EP 1.1E3 1.3E3 1.3E3 Cr-51 3.6E2 3.7E6 1.1E3 3.7E6 3.0E3 3.7E6 3.3E3 3.7E6
, Mn-54 2.5E4 1.1E9 4.3E4 1.1E9 6.7E4 1.1E9 7.7E4 1.1E9 Co-57. 4.9E3 2.7E8 1.3E4 2.7E8 3.1E4 2.7E8 3.1E4 2.7E8 Co-58 1.1E4 3.0E8 3.4E4 3.0E8 9.5E4 3.0E8 1.1E5 3.0E8 Co-60 3.2E4 1.7E10 9.6E4 1.7E10 2.6ES 1.7E10 2.8E5 1.7E10 Sr-89 4.0E5 1.7E4 6.0E5 1.7E4 4.3E5 1.7E4 3.0E5 1 7E4 Sr-90 4.1E7 1.0E8 1.1E8 9.9E7 Zr-95 2.2E4 2.0E8 6.1E4 2.0E8 1.5E5 2.0E8 1.5E5 2.0E8 Nb-95 1.3E4 -1.1E8 3.7E4 1.1E8 9.7E4' 1.1E8 1.0E5 1.1E8 Te-129m 3.2E4 1.6E7 5.0E4 1.6E7 5.2E4 1.6E7 3.7E4 1.6E7-Cs-134 7.0E5 5.5E9 1.0E6 5.5E9 1.1E6' 5.5E9 8.5E5 5.5E9' Cs-136 1.3E5 1.2E8 1.7E5 1.2E8 1.9E5 1.2E8 1.5E5 1. F.E8 Cs-137 6.1E5 8.2E9 8.3E5 8.2E9 8.5E5 8.2E9 6.2E5 8.2E9 Ba-140 5.6E4 1.6E7 7.4E4 -1.6E7 2.3E5 1.6E7 2.2E5 1.6E7 Ce-141 2.2E4 1.1E7- 5.7E4 1.1E7 1.3E5 1.1E7 1.2E5 1.1E7 Ce-144 1.5ES 5.6E7 3.9E5 5.6E7 8.6E5 5.6E7 8.2E5 5.6E7 L I -131 1.5E7 1.4E7 1.6E7 1.4E7 1.5E7 1.4E7 1.2E7 1.4E7 I -133 3.6E6 2.0E6 3.8E6 2.0E6 2.9E6 2.0E6 2.2E6 2.0E6 I -135 7.0E5 2.0E6 7.9E5 2.0E6 6.2E5 2.0E6 4.5E5 2.0E6 UN-ID 6.3E4 6.0E8 1.1E5 6.0E8 1.3E5 6.0E8 1.0E5 6.0E8
}
Inhalation Pathway, units =y *]j* !"
I* " "I Food & Ground Pathway, units 7
2-38 Rev. 21 07-01-89 l _ _ . _ _ _ _ _ - _ - - _ _ _ _ _ _ _ -
TABLE 2-8 DOSE PARAMETER Rj FOR SECTOR Q-
^.__. Page 1 of 8 T
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 .
4 Inhala- Food & Inhala- Food & Inhala- Food &- Inhala- Food &
Radio- tion Ground tion Ground tion Ground - tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E2 1.1E3 1.3E3 1.3E3 Cr-51 3.6E2 3.7E6 1.1E3 3.7E6 3.0E3 3.7E6 3.3E3 3.7E6 Mn-54 2.5E4 1.1E9 4.3E4 1.1E9 6.7E4 1.1E9 7.7E4 1.1E9 Co-57 4.9E3 2.7E8 1.3E4 2.7E8 3 1EA 2.7E8 3.1E4 2.7E8 Co-58 1.1E4 3.0E8 '3.4E4 3.0E8 9.5E4 3.0E8 1.1E5 3.0E8 Co-60 3.2E4 1.7E10 9.6E4 1.7E10 2.6E5 1.7E10 2.8E5 1.7E10 Sr-89 4.0E5 1.7E4 6.0E5 1.7E4 4.3E5 1.7E4 -3.0E5 1.7E4 Sr-90 4.1E7 1.0E8 1.1E8 9.9E7 Zr-95 2.2E4 2.0E8 i 6.1E4 2.0E8 1.5E5 2.0E8 1.5ES 2.0E8 Nb-95 -1.3E4 1.1E8 ' 3.7E4 1.1E8 9.7E4 1.1E8 1.0E5 1.1E8 Te-129m 3.2E4 1.6E7 5.0E4 1.6E7 5.2E4 1.6E7 3.7E4 1.6E7 Cs-134 7.0E5 5.5E9 1.0E6 5.5E9 1.1E6 5.5E9 8.5E5 5.5E9 Cs-136 1.3E5 1.2E8 1.7ES 1.2E8 1.9E5 1.2E8 1.5E5 1.2E8 Cs-137- 6.1E5 8.2E9 8.3E5 8.2E9 8.5ES 8.2E9 6.2E5 8.2E9 Ba-140 5.6E4 1.6E7' 7.4E4 1.6E7 2.3E5 1.6E7 2.2E5 1.6E7 Ce-141 2.2E4 1.1E7 5.7E4 1.1E7 1.3E5 1.1E7 1.2E5 1.1E7 Ce-144 1.5E5 5.6E7 3.9E5 5.6E7 8.6E5 5.6E7 8.2E5 5.6E7 I -131 1.5E7 1.4E7 1,6E7 1.4E7 1.5E7 1.4E7 1.2E7 .1.4E7 I -133 3.6E6 2.0E6 3.8E6 2.0E6 ~2.9E6 2.0E6 2.2E6 2.CE6 I -135- 7.0E5 2.0E6 7.9E5 2.0E6 6.2E5 2.0E6 4.5E5 2.0E6 UN-ID 6.3E4 6.0E8 1.1E5 6.0E8 1.3E5 6.0E8 1.0E5 6.0E8 l'
l Inhalation Pathway, units
- C /
Food & Ground Pathway, units - (m r r) f 2-39 Rev. 21 07-01-89
L
, ---TABLE 2-8 DOSE PARAMETER Ri FOR SECTOR Q
% ~Page 2 of'8 Pathway".- State Park Office Trailer Distance = 0.6 miles X/Q = 2.2E-6 sec/m* D/Q = 1.2E-8 m
- Infant Child -Teen Adult Inhala- Food & Inhala- Food & Inhala- Food'&- Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide. Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H_-3 - 5.8E1 'Cr-51 1.5E2 2.1E5 Mn-64 '0--
3.5E3 6.3E7 Co-57 - 0.- 1.4E3 l .' 6E7 -
Co-58 4.9E3 1.7E7 Co-60 1.3E4 9.8E8 Sr-89 1.4E4 9.9E2 Sr-90 - 4.5E6 Zr-95 6.9E3 1.1E7 Nb-95 4.8E3 6.2E6 Te-129m 1.7E3 9.0E5
.Cs-134 3.9E4 3.1E8 -
Cs-136 -U- 6.7E3 6.9E6 Cs-137 - 2.8E4 4.7E8 Ba-140 1.0E4 9.4E5 Ce-141 - 5.5E3 6.2E5 Ce-144 3.7E4- 3.2E6 I -131 5.4E5 7.9E5 I -133 - 9.8E4 1.1E5 1 -135 2.0E4 1.2E5 UN-ID 4.7E3 3.4E7 I
Inhalation Pat.iway, units = *C /
I*
Food & Ground Pathv:ay, units
[c^"
2-40 Rev. 21 07-01-89
- - 1 TABLE 2-8 i
1 DOSE PARAMETER Rj FOR SECTOR Q j
. Page 3 of.8 a w%'b Pathyay - Surf. Beach Guard Shack Distance - 0.7 miles t
X/Q ='1.8E-06 sec/m* D/Q = 9.9E-09 m ' .),
Infant' Child Teen Adult Inhala . Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3. 7.2E1 Cr-51 1.9E2 2.7E5 Mn-54 4.4E3 7.9E7 Co-57 1.8E3 2.0E7 -!
Co-58 6.1E3 2.2E7 Co-60 1.6E4 1.2E9 Sr-89 1.7E4 1.2E3 Sr-90 -
0 -- 5.7E6 Zr-95 8.6E3 1.4E7 Nb-95 5.9E3 7.8E6 Te-129m 2.1E3 1.1E6 Cs-134 -0 ' 4.8E4 3.9E8 Cs-136 8.4E3 8.6E6 Cs-137 3.5E4 5.9E8 Ba-140 1.2E4 1.2E6 Ce-141 6.9E3. 7.8E5 Ce-144 1 4.7E4- 4.0E6 I -131 6.8E5 9.8E5 I -133 1.2E5 1.4E5 I -135 . ' D-2.6E4 1.4E5 UN-ID 5.9E3 4.3E7 l Inhalation Pathway, units = 5" Food & Ground Pathway, units I" 2-41 Rev. 21 07-01-89 i
TABLE 2 DOSE PARAMETER Rj FOR SECTOR Q
~
Pathway - Enlisted Beach Check-In Distance - 1.4 miles X/Q = 6.8E-7 sec/m* D/Q - 3.2E-9 m-" ;
Infant Child Teen' Adult Inhala- Food &- Inhala- Food & Inhala- Food.&- Inhala- ' Food &
Radio- tion- Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.9E2 Cr-51 7.6E2 1.1E6' Mn-54 1.8E4 3.2E8 Co-57 7.2E3 7.8E7-
'Co-58 2.4E4' 8.7E7 Co-60 . 6.5E4 4.9E9 Sr-89 . 6.9E4 4.9E3 Sr-90 2.3E7 Zr-95 3.4E4 5.7E7 Nb-95 2.4E4 3.1E7 Te-129m 0- 8.3E3 4.5E6 Cs-134- 1.9E5 1.6E9 Cs-136 3.3E4 3.4E7 Cs-137 1.4E5 2.3E9 Ba-140 5.0E4 4.7E6 Ce-141 ' 2.7E4 '3.1E6 Ce-144 -
0- .1.9E5 1.6E7 I -131 2.7E6 3.9E6 I -133 0-- 0- 4.9ES 5.6E5 I -135 1.0E5 5.8E5 UN-ID - 2.4E4 1.7E8 1
Inhalation Pathway, units "C I* " "I Food & Ground Pathway, units 2-42 Rev. 21 07-01-89 i
I
f' L
1 TABLE 2-8 1
DOSE.' PARAMETER Rj FOR SECTOR Q Page 5 of 8
- l. ~
"i Pathway ='Sh'eep (Meat)* Distance - 1.6 miles p X/Q 5.6E-7 sec/m D/Q = 2.6E-9 til-*
Infant Child Teen Adult Inhala- Food & Inhala . Food &- Inhala- ' Food'& Inhala- Food'&- ;
Radio- tion Ground tion Ground tion Ground tion Ground l l Nuclide- Pathway Pathway Pathway Pathway. Pathway- Pathway Pathway Pathway l-H -3 10- -0 . 1.5E0 -
0-- 1.2E0 7.0E0 2.1E0 Cr-51 5.1 El- 1.0E2 1.8El' 2.6E4 Mn-54 7.8E2 -
0- 1.4E3 4.3E2 7.6E6 Co 4.7E3 -
0- 8.1E3 -1.7E2 1.9E6 Co-58 9.7E3 -
0- 2.0E4 5.9E2 2.1E6 Co : 3.7E4 7.3E4 1.6E3 1.2E8 Sr-89 5.0E4 2.6E4 1.7E3 3.1E4 Sr-90 - 1.0E6 8.1E5 5.5E5 1.3E6 Zr 6.3E4 -
0- 1.1E5 8.3E2 1.6E6 Nb 2.4E5 -
0- 4.5E5 5.7E2 1.6E6 Te-129m 6.0E5 -
0- 4.5E5 2.0E2 6.5E5 Cs-134 1.4E5 1.2E5 4.7E3 3.8E7 Cs-136 5.1E3 -
0- 4.3E3 8.1E2 8.3E5 Cs-137 -0 . 1.3E5' -
0- 9.5E4 3.4E3 5.7E7 Ba-140 5.1E3 -
0- 4.3E3 1.2E3 1.2E5 Ce-141 1.5E3 2.4E3- 6.6E2 7.9E4 Ce-144 1.8E4 3.0E4 4.5E3 4.3E5 I -131 6.6E5 -
0- 4.4E5 6.6E4 7.0E5 13133 1.6E-2 --
0- 8.7E-3 1.2E4 1.3E4 I -135 1.1E-18 -
0- 6.4E-19 2.5E3 1.4E4 UN-ID 1.1ES -
0- 9.5E4 5.7E2 4.2E6 Inhalation Pathway, units = ]j"(!"
Food & Ground Pathway, units = I* " "I j
2-43 Rev. 21 07-01-89 e
_ _ . _ _ _ _ . . . . _ . - _ _ _ _ .mm_..______.____________m______.__m.._.__m____ ____mm___-
I' r
TABLE 2-8 OOSE PARAMETER Rj FOR SECTOR QJ Pathway - S. C. Res W Garden Distance - 3.9 miles X/Q - 1.3E-07 sec/m* D/0 -'4.5E-10 m-*
Infant ~ Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Fcod &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 4.0E3 2.6E3 1.3E3 2.3E3
'Cr-51 6.1E6 1.0E7- 3.3E3 1.5E7 Mn-54 -0 . 6.5E8 9.2E8 7.7E4 2.0E9 Co-57 2.4E8 3.2E8 3.1E4 5.6E8 Co-58 3.7E8 5.9E8 1.1ES 9.lE8 Co-60 2.1E9 3.2E9 2.8E5 2.0E10 Sr-89 3.5E10 1.5E10 3.0E5 9.8E9 Sr-90 1.4E12 8.3E11 9.9E7 6.7E11 Zr-95 8.8E8 1.2E9 1.5E5 1.4E9 Nb-95 2.9E8 4.5E8 1.0E5 5.8E8 Te-129m 2.9E9 1.8E9 3.7E4 1.2E9 Cs-138 2.6E10 1.6E10 8.5E5 1.6E10 Cs-136 2.2E8 1.7E8 1.5E5 2.9E8 Cs-137 2.4E10 1.4E10 6.2E5 1.7E10 Sa-140 2.8E8 2.1E8 2.2E5 2.8E8 Ce-141 4.0E8 5.3E8 1.2E5 5.1E8 Ce-144- 1.0E10 1.3E10 8.2E5 1.1F10 I -131 4.8E10 3.lE10 1.2E7 3.ff10 I -133 8.lE8 4.6E8 2.2E6 5.3E8 1 -135 -0 9.8E6 5.7E6 4.5E5 8.6E6 UN-ID. 2.7E9 1.9E9 1.0E6 1.9E9 Inhalation Pathway, units = *C /
I" Food & Ground Pathway, units f{j"'*f##
2-44 Rev. 21 07-01-89
'b
7 TABLE 2-8 DOSE PARAMETER Rj FOR SECTOR Q Page 7 of 8 1 !
Pathway - San Clemente Ranch (No Residents) Distance'- 2.2 miles X/Q = 3.3E-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 Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 '3.8E3 ~ 2.4E3 1.9E3 Cr-51 4.8E6 7.4E6 6.7E6 Mn-54 6.1E8 - 8.3E8 '8.0E8 Co-57 2.2E8. 2.9E8 2.4E8 Co-58 3.3E8 5.1E8 4.7E8 ,
Co-60 2.0E9 3.0E9 2.7E9 R Sr-89 3.1E10 1.2E10 7.2E9 Sr-90 1 3E12 7.7E11 5.8E11 Zr-95 7.8E8 1.1E9 9.1E8 Nb-95 2.4E8 3.5E8 3.1E8 Te-129m 2.3E9 1.4E9 7.9E8 Cs-134 2.4E10 - 1.5E10 9.2E9 Cs-136 9.0E7 - 5.7E7 3.6E7-Cs-137 2.2E10 1.3E10 7.8E9 Ba-140 1.1E8- 6.8E7 5.3E7 Ce-141 - 3.3E8 4.1E8 3.2E8 Ce-144 9.2E9 1.2E10 9.0E9 I -131 4.1E9 2.1E9 1.4E9 I -133 4.0E-11 1.7E-11 - 1.1E-11 1 -135- 6.9E-35 3.0E-35 1.9E-35 UN-ID' 2.5E9 1.7E9 1.1E9 Inhalation Pathway, units = ]j* !"
' ^"
Food & Ground Pathway, units = I* j[c 2-45 Rev. 21 07-01-89
h J
, TJASLE 2-8 o DOSE PARAMETER'Rj FOR SECTOR Q Pathway --San Clemente Ranch Adm.J0ffices 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 &'
Radio- tion- ' Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway
'H -3' 249E2 1.9E3
, Cr-51 7.6E2 7.8E6 Mn-54 - -0 ' 1.8E4 1.1E9 Co-57 7.2E3 -3.2ES Co-58 2.4E4 5.6E8 t- -Co-60 - 6'.5E4 7.6ES Sr-89 6.9E4 7.2E9 Sr-90 2.3E7 5.8E11 Zr-95 3.4E4 9.7ES Nb-95 2.4E4 3.4E8 Te-129m 8.3E3 7.9E8
.Cs-134 1.9E5 1.1E10 Cs~136 - 3.3E4 7.0E7 Cs-137- 1.4E5 1.0E10 Ba-140 ' 0-5.0E4 5.8E7
=Ce-141 2.7E4 3.2E8 Ce-144 1.9E5 9.0E9-I'-131 2.7E6 1.4E9 I -133 4.9E5 5.6E5 I -135 1.0E5 5.8E5 UN-ID 2.4E4 -1.2E9 l
Inhalation Dathway, units
- ]f(!"
y
. food & Ground Pathway, units = (m')(mrem /vr) gCi/sec 2-46 Rev. 21 07-01-89
l
- TABLE 2-9 DOSE PARAMETER Rj FOR SECTOR R Page 1 of 5
,)
Pathway - San Onofre Mobile Homes Distance - 1.2 miles
, X/Q - 5.3E-7 sec/m*
D/Q - 3.2E-9 m
Infant- Chiid Teen Adult Inhala- hood & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E2 1.1E3 1.3E3 1.3E3 4 Cr 3.6E2 3.7E6 1.1E3 3.7E6 3.0E3 3.7E6 3.3E3 3.7E6
-Mn-54 2.5E4 -1.1E9 4.3E4 1.1E9 6.7E4 1.1E9 7.7E4 1.!E9 Co-57 4.9E3 2.7E8 1.3E4 2.7E8 3.1E4 2.7E8 3.1E4 2.7E8 Co-58 1.1E4 3.0E8 3.4E4 3.0E8 9.5E4 3.0E8 1.1E5 3.0E8 Co.60 3.2E4. 1.7E10 9.6E4 1.7E10 2.6E5 1.7E10 2.CES '1.7E10 Sr-89' 4.0E5 1.7E4 6.0E5 1.7E4 4.3E5 1.7E4 3.0E5 1.7E4
'Sr-90 4.1E7- 1.0E8 1.1E8 9.9E7 Zr-95 ~2.2E4 2.0E8 6.1E4 2.0E8 1.5E5 2.0E8 1.5E5 2.0E8 Wb-95 1.3E4 1.1E8 3.7E4 1.1E8 9.7E4 1.1E8 1.0E5 1.1E8
-Te-129m 3.2E4 1.6E7 5.0E4 1.6E7 5.2E4 1.6E7 3.7E4 1.6E7 Cs-134 7.0E5 5.5E9 1.0E6 5.5E9 1.1E6 5.5E9 8.5E5 5.5E9-
'Cs-136 1.3E5- 1.2E8 1.7E5 1.2E8 1.9ES 1.2E8 1.5E5 1.2E8 Cs-137 6.1E5 8.2E9 8.3E5 8.2E9 8.5E5 8.2E9 6.2E5 8.2E9 Ba-140 '5.6E4 1.6E7 7.4E4 1.6E7 2.3E5 1.6E7 2.2E5 1.6E7 Ce-141 2.2E4- 1.1E7 5.7E4 1.1E7 1.3E5 1.1E7 1.2E5' 1.1E7 Ce-144 1.5E5 5.6E7 3.9E5 5.6E7 8.6E5 5.6E7 8.2E5 5.6E7 I -131- 1.5E7 1.4E7 1.6E7 1.4E7 1.5E7 1.4E7 1.2E7 1.4E7 I -133- 3.6E6 2.0E6 3.8E6 2.0E6 2.9E6 2.0E6 2.2E6 2.0E6 I -135 7.0E5 2.0E6 7.9E5 2.0E6 6.2E5 2.0E6 4.5E5 2.0E6 UN-ID 6.3E4 6.0E8 1.1E5 6.0E8 1.3E5 6.0E8 1.0E5 6.0E8 1
Inhalation Pathway, units = 5" Food & Ground Pathway, units =
f 2-47 Rev. 21 07-01-89 l
j
,6 '
. TABLE 2-9 t
DOSE PARAMETER Rj FOR SECTOR R q Page 2 of 5 !
4]:
- LPathway = San Clemente Ranch (No Residents) Distance.= 2.3 miles L. ;X/Q = 2.0E-7.sec/m' D/Q = 1.0E-9 m-'
[ Infant Child Teen Adult Inhala- : Food & Inhala- 'Foo'd & Inhala- Food & Inhala- Food & I Radio . tion Ground tion Ground tion Ground tion Ground 1 Nuclide Pathway- Pathway Pathway Pathway Pathway Pathway Pathway. Pathway ;
H -3 3.8E3 - 2.4E3 1.9E3 Cr-51 4.8E6 - 7.4E6 -0 ' 6.7E6:
!- Mn-54 ' - 6.1E8- 8.3E8 8.0E8 Co-57 2.2E8 - 0- 2.9E8 2.4E8 Co-58 - 3.3E8 5.1E8 4.7E8' )
Co-60 2.0E9 , 3.0E9. 2.7E9 !
- Sr-89' 3.1E10- 1.2E10. ' 7.2E9 Sr-90 .-0-. 1 3E12 - 7.7E11 5.8E11- l Zr-95 7.8E8 '1.1E9 9.1E8 j Nb 2.4E8- 3.5E8 3.1E8 - i Te-129m - 2.3E9 . 1.4E9 7.9E8: i Cs-134 - 2.4E10 1.5E10 '9.2E9 j its-136- 9.0E7 5.7E7 '3. 6 E7.
Cs-137- 2.2E10' 1.3E10 7.8E9 Ba-140- 1.1E8 6.8E7 5.3E7 i
-Ce-141' , -
0- . 3.3E8 4.1 E8 . 3.2E8 !
Ce-144 9.2E9 1.2E10 9.0E9 I -131 . : 4.1E9 2.1E9 1.4E9 I -133 4.0E-11 1.7E-11 1.1E-11 I -135 ~ 6.9E-35 3.0E-35 1.9E-35 1 UN-ID 2.5E9 1.7E9 1.1E9 l
i Inh'alation Pathway, units = !"
Food'& Ground Pathway, unitr = I* " "
j 2-48 Rev. 21 07-01-89 a ,
..___m . _ _ _ _ _ . _ _ . _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . . _. _ _ _ _ _ _ _ . _ . _ _ _ _ _
u, .' :
L TABLE 2-9
, DOSE PARAMETER Rj FOR SECTOR R.
Page 3 of 5 t Pathway'--SC Ranch Packing Distance - 2.6 miles
'X/Q - 1.7E-07.sec/m* D/Q = 8.2E-10 m
- Infant Child Teen Adult Food & Inhala-Inhal a- Food &' Inhala- Food & Inhala- Food-&- .
Radio-- tion Ground tion Ground l tion Ground tion Ground Nuclide Pathway. Pathway Pathway Pathway Pathway Pathway Pattway- Pathway H -3 3.8E3 2.4E3 1.2E3 1.9E3 Cr-51 4.8E6 7.4E6 3.0E3 '1.0E7-Mn -0.- 6.1E8 - 8.3E8 7.1E4 1.9E9-Co 2.2E8: 2.9E8 2.9E4 5.2E8 00-58 - 3.3E8- 5.1E8. 9.8E4 7.8E8~
b LCo-60 2.0E9 3.0E9 2.6E5 2.0E10
'Sr-89' 0- 3.1E10 1.2E10 2.8E5 7.2E9-
.Sr~90- - 1.3E12 7.7E11. 9.1E7. 5.8E11 Zr -0 7.8E8 '1.lE9 1.4E5 'I.1E9 Nb 2.4E8 - 3.5E8 9.5E4 4.2E8 Te-129m- - - 2.3E9 - 1.4E9 3.4E4 8.0E8 Cs-134 - 2.4E10 1.5E10 7.625 1.5E10 Cs-136 9.0E7 5.7E7- 1.3E5 1.6E8 Cs-137 . - 2.2E10 1.3E10- 5.7E5 l'.6E10 Ba-140 1.1E8 6.8E7 2.0E5 : 7.0E7 '
- .Ce-141 3.3E8 4.1E8 1.1E5 3.3E8 Ce-144 9.2E9 .l.2E10 7.5E5 9.0E9 I -131 4.lE9- 2.lE9 1.1E7 1.4E9 I -133> , 4.0E-11 1.7E-11 2.0E6 2.0E6
-I.-135 ' 6.9E-35 3.0E-35 4.1E5 2.0E6
.UN-ID- 2.5E9 1.7E9 9.5E4 1.7E9 n
s.
Inhalation Pathway, units - ]j5" Food & Ground Pathway, units - (m r r1 j
2-49 Rev. 21
_ 07-01-89 i
p TABLE 2-9 DOSE PARAMETER Rj FOR SECTOR R m
Page 4 of 5 3
f Pathway - Sheep Meat Distance.- 0.9 miles
.X/Q = 8.3E-7-sec/m". D/Q - 5.2E-9 m-*
. Infant Enild Teen Adult Inhala- Food & Inhala- -Food & Inhala- Food & Inhala-- Food &
Radio'- tion Ground tion Ground tion Ground tion Ground Nuclide' Pathway Pathway Pathway Pathway Pathway Pathway Pathway' Pathway H -3' - fi- 1.5E0 1.2E0 7.0E0 2.1E0 Cr-51 - 5.1El 1.0E2 1.8E1 2.6E4 Mn-54 . 7.8E2 1.4E3 4.3E2 7.6E6 Co-57 4.7E3 8.1E3 1.7E2 1.9E6 Co-38 9.7E3 2.0E4 o.9L2 2.1E6
'Co 3.7E4 7.3E4 1.6E3 1.2E8 l Sr-89 5.0E4 2.6E4 1.7E3 3.1E4 Sr-90. 1.0E6 8 IE5 5.5E5 1.3E6 Zr-95 6.3E4 1.1E5 8.3E2 1.6E6 Nb-95 2.4E5 4.5E5 5.7E2 1.6E6 Te-129m '
6.0E5 4.5E5 2.0E2 6.5E5 Cs-134~ 1.4E5 1.2E5 4.7E3 3.8E7 Cs-136 5.1E3 4.3E3 '8.1E2 8.3E5 Cs-137 -D - 1.3E5 9.5E4 3.4E3 5.7E7 Ba-140 5.1E3 4.3E3. 1.2E3 1.2E5 Ce-141 1.5E3 2.4E3 6.6E2 7.9E4
. Ce-144 1.8E4 3.0E4 4.5E3 4.3E5 I -131 6.6E5 4.4E5 6.6E4 7.0E5 I -133 1 6E-2 8.7E-3 1.2E4 1.3E4 1 -135 1.1E-18 6.4E-19 2.5E3 1.4E4 UN-ID 1.1ES 9.5E4 5.7E2 4.2E6
-1 Inhalation Pathway, units = ]j"(!"
Food & Ground Pathway, units -
m r) 2-50 Rev. 21 !
07-01-89 {
l l
l
?
TABLE 2-9 DOSE PARAMETER Rj FOR SECTOR R 3 Page 5 of 5
) Pathway - Deer Consumer Distance - 2.2 miles X/Q - 1.BE-7 sec/m* D/Q - 8.8E-10 m '
Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
fi Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8El 2.3E1 3.5El 3.9El Cr-51 5.0E4 1.0E5 9.1El 3.2E5 Mn-54 7.7E5 1.4E6 2.lE3 4.lE7 Co-57 4.6E6 8.0E6 8.6E2 2.3E7 Co-58 9.6E6 1.9E7 2.9E3 / 'E7 Co-60 3.6E7 7.2E7 7.8E3 7.2E8 Sr-89 4.9E7 2.6E7 8.3E3 3.1E7
-Sr-90 1.0E9 8.0E8 2.7E6 1.2E9 ;
Zr-S5 6.2E7 1.lE8 4.lE3 2.0E8 Nb-95 2.3E8 4.5E8 2.8E3 8.2E8 Te-129m -G- 5.9E8 4.5E8 1.0E3 5.3E8 Cs-134 1.4E8 1.2E8 2.3E4 3.4E8 Cs-136 5.lE6 4.2E6 4.0E3 9.5E6 Cs-137 1.2E8 9.3E7 1.7E4 4.0E8 b6-140 5.0E6 4'.2E6 6.0E3 7.4E6 i
Ce-141 1.5E6 2.4E6 3.3E3 4.2E6 Ce-144 1.8E7 2.9E7 2.2E4 4.9E7 I -131 6.5E8 4.3E8 3.3E5 5.9E8 l I -133 1.6El 8.6E0 5.9E4 6.7E4 l I -135 1.1E-15 6.3E-16 1.2E4 6.9E4 i
UN-ID 1.1E8 9.4E7 2.8E3 1.4E8 1
Inhalation Pathway, units - ]f(5#
Food & Ground Pathway, units I* " " '
7[ c
~
l 1
3102c. man 2-51 Rev. 21 07-01-89
p- -
n-s, -
.tj
/ l ',' ' ;. ;g .' i
, i
, , TABLE 2-10 DOSE PARAMETER R ;FOR SECTOR A
]
~~
Pathway = Camp San Mateo' Distance - 3.6 miles X/Q = 7.1E-8 sec/m*- ' ,D/Q = 4.1E-10 m * .j
.y
' Infant Child Teen Adult- ]
L- Inhala- Food & Inhala- Food & Inhala- Fo;.1 & Inhala- Food &- :
Radio- tion Ground' tion Ground tion . Ground: tion ' Ground- ;
Nuclide- Pathway . Pathway Pathway Pathway Pathway. : Pathway Pathway' Pathway 1
H -3 ' 1.3E3 j Cr-51 3.3E3 3.7E6 1 Mn-54. . . -0 . 7.7E4 1.1E9 Co-57 3.1E4 2 . .' E8 o Co-58 - -1.1E5 3.0E8 '
Co-60 -- -0 . - 2.GES .1.7E10
.Sr-89 - ' 0-3.0E5 1.7 E4.
Sr-90 . . 9.9E7 ,, Zr 0- 1.5E5 2.0E8 Nb-95 -0 . -0 . 1.0E5. 1.1E8:
Te-129m - ~ 3.7E4 1.6E7 Cs-134 ~ 8.5E5 5.5E9-Cs-136 - 1.5E5' 1.2F8' Cs-137 -
0- 6.2E5: 8.2E9 Ba-140 2.2E5 ~1,6E7T Ce-141- - - -1.2E5 1.1E7 Ce-144 8.2E5- 5.6E7 I -131 1.2E7 1.4E7 I -133 2.2E6 2.0E6 I -135 4.5E5 2.0E6-UN-ID 1.0E5 6.0E8 L
Inhalation Pathway,' units - 5" l.
I" ' "I Food & Ground Pathway, units j 2-52 Rev. 21 ,
07-01-89 l . .
- m. ,' '
TABLE 2-10
- f. ,
. DOSE PARAMETER.R FOR SECTOR A~
l' Page 2 of 3- -
')l ;
Pathway - Sheep (Meat)*
Distance - 0.2 miles
, X/Q - 6.7E-6 sec/m D/Q'- 5.2E-8 m-*
?' Infant Cnild Teen Adult Inhala- Inhala- Food & Inhala' Food & Inhala- Food &
Food & -
Radio- tion Grounc: tion Ground tion Ground tion Ground Nuclids Pathway Pathway Pathway Pathway Pathway Pathway Pathway. Pathway H - 1.5E0 1.2E0 7.0E0 2.1E0 Cr-51 5.1El 1.0E2 l'.8E1 ~2. 6E4
'Mn-54 L 7.8E2 -1.4E3 4.3E2 7.6E6-Co-57 ' 4.7E3- 8.1E3 1.7E2 1.9E6:
Co ' 9.7E3 2.0E4 5.9E2 2.1E6 Co-60 - 3.7E4 -C- .7.3E4 1.6E3 1. 2 E8 -
Sr-89 5.0E4 2.6E4 1.7E3 '3.1E4 Sr-90 - 1.0E6- 8.1E5 5.5E5 1.3E6
, .Zr'-95 6.3E4 1.1E5 8.3E2 1.6E6-
'Nb-95 ~0- 2.4E5 -4.5E5 5.7E2 1.6E6 Te-129m 6.0E5 4.5E5 2.0E2 6.5E5
.Cs-134 0- 1.4E5 1.2E5 4.7E3 3.8E7 .
.Cs-136- -0 . 5.1E3 4.3E3 8.1E2 8.3E5 l Cs-137 1.3E5 9.5E4~ 3.4E3- 5.7E7 4
.Ba-140 >0- 5.1E3 . 4.3E3 1.2E3 1.2E5 Ce-141 1.5E3^ 2.4E3 6.6E2 7.9E4 Ce-144 - 1.8E4 3.0E4 4.5E3 4.3ES-
.I -131 6.6E5 4.4E5 6.6E4 7.0E5 I -133 1.6E-2 8.7Ee3 1.2E4 1.3E4 I -135 -0 ' 1.1E-18 6.4E-19 2.5E3 '1.4E4 r
UN-ID 1.1E5 9.5E4 5.7E2 4'. 2E6
, 1 Inhalation Pathway, units
- C /
y I" V"I Food & Ground Pathway, units 2-53 Rev. 21 07-01-89 j
% ~
+
p V g ,
, TABLE 2-10 DOSE PARAMETER R g FOR SECTOR A Page 3.of 3 l
[,g
%g o =
Pathway = Deer Consumer- Distance - 2.7. miles 'k lff.
'X/Q = 1.9E-7'sec/m*' D/Q = 1.4E-9 m-* .l I
Infant Child -Teen Adult-Inhala- food & Inhaka- Food & Inhala- Food &- Inhala- Food & .
Radio- tion Ground tion Ground tion Ground tion Ground Nuclidef Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway 'j j/ H'-3 ' - 2.8E1 2.3E1 3.5El 3.9El Cr-51 - 5.0E4 0- -1.0E5 9.1El 3.2E5' Mn-54' -0 K -0 ' 7.7E5 1.4E6 1 2.1E3 4.1E7~ d '
Co-57 9~ 4.6E6 --0 8.0E6 8'.6E'2 : 2.3E7 Co-58 s- 9.6E6 1.9E7 2.9E3 '4.7E7
.C0-60 - 3.6E7 7.2E7 7.GE3 7.2E8 Sr-89' 4.9E7 -0~ 2.6E7 8.3E3 3.1E7
.Sr-90 1.0E9 8.0EB '2.7E6' 1,2E9 Zr-95' . 6.2E7 1.1E8 4.1E3 2.0E8-Nb-95s 2.3E8 4.5E8 2.8E3 8.2E8~
'Te-129m - 5.0E8 4.5E8 1.0E3 5.3E8
'Cs-134: 1.4E8 1.2E8 2.3E4 3.4E8 Cs-136 ' <0- 5.s:6 .4.2E6- 4.0E3 9.5E6L Cs-137 1.2E8 .9.3E7- 1.7E4 4.0E8 Ba-14D. 5.0E6 4 2E6 6.0E3- 7.4E6 '
'Ce-141 ~ 1.5E6 2.4E6 3.3E3 4.2E6-Ce-144' +0- "
,1.8E7- 2.9E7- 2.2E4 4.9E7 T-13). ' 6.5E8 - 4.3E8 3.3E5 5.9E8 g 1 -133- -1.6El 8.6E0 5.9E4 6.7E4
.I -135 ' 0-
- 1.'1E-15 6.3E-16' 1.2E4 6.9W UN-ID 1.1E8 9.4E7 2.8E3 1.4E8 h
.f i =
Inhalation Pathway, units = y* !"
food & Ground Pathway, units = #* N 2-54 Rev. 21 07 01-89 e .
(). <
N .U ,
TABLE 2-11 M< ' DOSE PARAMETER R g FOR SECTOR S
., Page 1 of- 3
)" ", '
Pathway = Sheep (Meat)* Distance = 0.2 miles
. X/Q. 6.1E-6 sec/m .D/Q = 5.3E-8 m-*
Infant -Child Teen. Adult Inhala- Food'a Inhata- Food & Inhalae Food & Inhalai- Food &
> Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway 11 :-3 ' '
1.5E0 1.2E0 7.0E0 2.1EO Cr-51 0- - .5.1El 1.0E2 1.8E1 2.6E4 Mn-54 -7.8E2 1.4E3 4.3E2 7.6E6 Co-57' -0 . -0 . 4,7E3 8.1ES 1.7E2 1.9E6 Co-68 9.7E3 2.0E4 5.9E2 2.1E6 Co-60 - 3.7E4 7.3E4 1.6E3 1.2E8 .,
Sr-89 5,0E6 2,6E4 1.7E3 3.1E4 i Sr-90 : 1.0E6 '-0 .
8.-1E5 S.5E5 1.3E6-Zr-9ii ' 0- o 6.3E4 1.1E5 8.3E2 1.6E6 Wo-95 2.4E5 4.5E5 5.7E2 1.6E6 Te-129m 6.0E5 4.5E5 2.0E2 6.5E5 Cs-134- . 1.4E5- 1.2E5 4.7E3 3.8E7 Cs-136. 5.1E3 -0 . 4.3E3 8.1E2 8.3E5-Cs-1371 -On 1.3E5 9.5E4 3.4E3 5.7E7
'Ba-140. :5.1E3 4.3E3 1.2E3 1.2E5
'Ce-141- I ',5 E3 2.4E3 6.6E2' -7.9E4' Ce-144 1.8E4 3.0E4 4.5E3 '4.3E5 I -131 6.0E5 4.4E5 6.6E4 7.0E5
'I -133' 1.6E-2 8.7E-3 1.2E4' 1.3E4 I -135- 1.1E-18 6.4E-19' 2.5E3 1.4E4 UN-ID. 1.1E5 '
9.5E4 5.7E2 4.2E6 h
L l
m Inhalation Pathway, unitr. = }hm yr
- I' Food.& Ground Pathway, units -
f 2-55 r,ev. 21 07-01-89
w yl ,LY.4 r;.
- o
' TABLE 2 11' E y DOSE PARAMETER R ' FOR SECTOR B
~
, Page 2 of:3-
' } Pathway Deer Consumer Distance - 1.1 miles X/Q = 3.4E-7 sec/m* D/Q = 2.4E-9 m"*
Infant Child' Teen Adult Inhala? Food &- Inhala- Food &. Inhala- l Food &- Inhala- . Food &
Radio-1 tion Ground tion , Ground tion- Ground tion- Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 2.8E1 2.3E1 3.5El 3.9El Cr-51 -0; 5.0E4 1.0E5: 9.1El 3.2E5' Mn-54 7.7ES 1.4E6 2.1 E3. 4.1E7 Co-57 - 4.6E6 - 8.0E6 8.6E2: 2.3E7.
Co-58 - 0 :- 9.6E6 1.9E7 2.9E3 4.7E7 Co-60 3.6E7- '7. 2 E7- 7.8E3 7.2E8 Sr-89 : -Os 4.9E7 2.6E7' 8.3E3 3.1E7-Sr-90 1.0E9 - 8.0E8 2.7E6: 1.2E9 Zr-95 - 6.2E7 1.1E8 -4.1E3- 2.058 Nb-95.. - 2.3E8 4.5E8- 2.8E3 8.2E8 Te-129m 5.9E8 '4.5E8' 1.0E3 5.3E8 Cs-134. 1.4E8 1.2E8 2.3E4- 3.4E8 Cs-136- 5.1E6 - 4.2E6 4.0F3 9.5E6
'Cs-137: 1.2E8 9.3E7- 1.7E4 4.0E8 '
8a-140- 5.0E6 4.2E6 6.0E3 7.4E6 Ce-141 1.5E6 2.4E6 3.3E3 4.2E6, Ce-144 --0-- 1.EE7 2.9E7 2.2E4 4.9E7 I -131 6.5E8 4.3E8 3.3E5 5.9E8 I -133 1.6El -G- 8.6E0 5.9E4 6.7E4 I -135 1.1E-15 6.3E-16 1.2E4 6.9E4 UN-ID 1.1E8 9.4E7 2.8E3 1.4E8 Inhalation Pathway, units *]j*[
y Food & Ground Pathway, units = I*
2-56 Rev. 21 ,
07-01-89 i
-_-_________________ _ A
1 . .
. TfBLEi2-11 DOSE PARAMETER R, FOR 5ECTOR B.
Page 3 of.3
- m. -
'4 .
Pathway - Sanitary Landfill Distance - 2.1' miles R
-X/Q il.4E-7 sec/m* D/Q = 1.2E-9 m * '
. Infant Child Teen Aduit Inh al 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 H -3 ' 2.! '.2 ,.
lCr-51 ' - 7.N2 l'.1E6 W 54 - 1.8E4 3.2E8 T, 57 '
-0 . -0 . 7.2E3 7.8E7 Cu . 2.4E4: 8.7E7 Co-60' 40- -0 : 6.5E4 4.9E9 Sr-B9 . 6.9E4' 4.9E3 Sr-90. - 2.3E7 2r-95 - 3.4E4. 5.7E7.
'Nb-95: .2.4E4- 3.1E7 Te-129m : 8.3E3 4.5E6 1;6E9
~
Cs-134 -D- - 1.9E5 Cs-136- - - 3.3E4 3.4E7 Cs-137 0- , - 1.4E5 2.3E9 Ba-140
5,0E4 :4.7E6 Ce-141: - - ~ 2. TE4 ' 3.1E6-
>Ce-144 1.1E5 1.6E' I -131 2./E6 3.9E6 1 -133 . 4.9E5 5.6E5 z I -135 1.0E4 5.8E5 L -UN-ID 2.4E4 1.7E8 Inhalation Pathway, units
- C /
2 "I
Food & Ground Pathway, units A h j" "7
3% A9
- w. - - -- - _-
lABLE 2-12 DOSE PARAMETER R g FOR SECTOR C
_ Page 1 of 5
) Pathway - Camp San Onofre Distance - 2.6 miles X/Q = 8.2E-8 sec/m* D/Q - 8.4E-10 m
- Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway l Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.3E3 Cr-51 3.3E3 3.7E6 Mn-54 7.7E4 1.1E9 Co-57 3.1E4 2.7E8
. Co-58 1.1E5 3.0E8 Co-60 2.8E5 1.7E10 Sr-89 3.0E5 1.7E4-Sr-90 9.9E7 Zr-95 -C- 1.5E5 2.0E8 Nb-95 1.0E5 1.1E8 Te-129m 3.7E4 1.6E7 Cs-134 8.5E5 5.5E9 Cs-136 1,5E5 1.2E8 Cs-137 6.2E5 8.2E9 Ba-140 2.2E5 1.6E7 Ce-141 1.2E5 1.1E7 Cc-144 8.2E5 5.6E7
'I -131 1.2E7 1.4E7 I -133 2.2E6 2.0E6 I -135 4.5E5 2.0E6 UN-ID 1.0E5 6.0E8 i
" " j Inhalation Pathway, units = *C /
Food & Ground Pathway, units I* " "I j
2-58 Rev. 21 07-01-89
w i
TABLE 2-12 DOSE PARAMETER R FOR SECTOR'C Page 2 of 5
.4 Pathway - Camp-San Onofre Fr. Stn Distance - 2.3 miles X/Q.= 1.1E-7-sec/m* D/Q ='1.1E-9 m
- Infant- Child Teen Adult Inhala - Food & Inhala- Food & Inhala- Food & Inhala- Food & .
Ground tion Ground tion Ground tion Radio- ti on .' Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway -Pathway 2-H 5.2E2' Cr-51 1.4E3 1.9E6 Mn-54 ' 3.2E4 5.7E8 Co 1.3E4 1.4E8 Co-58 -C- 4.4E4- 1.6E8 Co-60 1.2E5 8.8E9 Sr-89 -
0- 1.2E5 8.9E3 Sr-90' . 4.1E7 Zr-95 6.2E4 1.0E8
,Nb-95 4.3E4 5.6E7 Te-129m '1.5E4 8.1E6-Cs-134 -0 . 3.5E5 2.8E9
'Cs-136 6.0E4- 6.2E7 Cs-137 2.6E5 4.2E9 Ba1140 9.0E4 8.4E6 Ce-141 4.9E4- 5.6E6 Ce-144 3.4E5 2.9E7 I'-131 4.9E6 7.1E6 I -133 8.8E5 1.0E6 I -135 1.8E5 1.0E6 UN-ID 4.2E4 3.1E8 Inhalation Pathway, units = !"
Food & Ground Pathway, units - (m r vri 2-59 Rev. 21 07-01-89
q
)
TABLE'2-12 .,
1 DOSE PARAMETER Rj .FOR SECTOR C .I
_. Page 3 of 5 b 3
- Pathway - Sewage' Facility Distance - 2.2 miles X/Q - 1.2E-7 sec/m* D/Q - 1.2E-9 m ' l 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
H -3 - - 2.9E2 Cr-51 7.6E2 1.1E6
.Mn-54 . 1.8E4 3.2E8 Co-57 - 7.2E3 '7.8E7
, Co - 2,4E4 8.7E7 ,
Co 6.5E4 4.9E9 -l Sr-89 - 6.9E4- 4.9E3 Sr-90 2.3E7. Zr-95 L . 3.4E4 5.7E7-Nb-95 . 2.4E4 '3.1E7 Te-129m 8.3E3 4.5E6 Cs-134 1.9E5- 1.6E9
'Cs-136 3.3E4 3.4E7 Cs-137 1.4E5 2.3E9 Ba-140 . 5.0E4~ '4.7E6 Ce-141 2.7E4 3.1E6 Ce-144 . 1.9E5 .1.6E7-I. 131 - 2.7E6 3.9E6 I -133 .
4.9E5 5.6E5 1 -135 1.0E5 5.8E5 UN-ID. <0- 2.4E4 1.7E8 l
i I
Inhalation Pathway, units = !"
' Food & Ground Pathway, units - (m rs r) f 2-60 Rev. 21 07-01-89
- _ ._. _____-_________O
)
K m j
~
TABLE 2-12 OOSE PARAMETER R FOR SECTOR C- . . I a Page 4 of 5 )
I) ' Pathway = Sheep'(Meat)8 Distance - 0.2 miles l
X/Q - 6.5E-6 sec/m D/Q'- 5.3E-8 m 2
' Infant Child ~ Teen . Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & 4 Radio- tion Ground tion Ground tion Ground. tion Ground l Nuclide' Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway l I
H -3 Cr -
1.5E0 5.1El
-0 .
1.2E0 1.0E2 7.0E0 1.8E1
.2.IE0 2.6E4
)
l Mn-54 7.8E2 1.4E3 4.3E2 7.6E6 i Co-57 4.7E3 8.1E3 1.7E2 1.9E6 Co - 9.7E3 2.0E4 5.9E2 2.1E6 Co-60 '3.7E4 7.3E4 1.6E3 1.2E8 Sr-89 5.0E4 2.6E4 1.7E3 3.1E4 Sr-90 1.0E6 8.1ES 5.5E5 1.3E6 Zr-95 - - 6.3E4 1.1E5 8.3E2 1.6E6 L , . .g Nb-95 2.4E5 4.5E5 5.7E2 1.6E6 Te-129m 6.0E5 4.5E5 2.0E2 6.5E5-Cs-134 -
0-- - 1.4E5 1.2E5 4.7E3 .3.8E7 Cs-136- 5.1E3 4.3E3 8.1E2 8.3E5 Cs-137 1.3E5 9.5E4- 3.4E3 5.7E7 Ba-140 5.1E3 ~4.3E3 1.2E3- 1.2E5 Ce-141 1.5E3 2.4E3- 6.6E2 7.9E4 Ce-144 1.8E4 3.0E4 4.5E3 4.3E5 I -131- 6.6E5 4.4E5 6.6E4 7.0E5 I -133 1.6E-2 8.7E-3 1.2E4 1.3E4 I -135 -Os 1.1E-18 6.4E-19 2.5E3 1.4E4 UN-ID - 1.1ES 9.5E4 5.7E2 4.2E6 InhalationPathway, units y=*]j"(!"
Food & Ground Pathway, units = (m r vr) j c
2-61 Rev. 21 07-01-89
y TABLE 2-12 I
DOSE. PARAMETER R FOR SECTOR;C" Page 5 of 5 ;
~[ '
Pathway e Deer Consumer Distance - 1.0 miles ,
X/Q : 3.4E-7 sec/m* D/Q = 5.1E-9 m '
L
. Infant Child Teen Adult Inhala- Food &. Inhal a- Food & Inhala- Food & Inhala- . Food &
Radio- tion Ground tion Ground tion Ground tion Ground-Nuclide Pathway Pathway . Pathway Pathway Pathway Pathway Pathway . Pathway H -3 2.8E1 '2.3El- 3.5El 3.9El-W Cr-51 5.0E4 '0---
1.0E5 9.1El 3.2E5 Mn-54 7.7E5 1.4E6 2.1E3 4.1E7 -
Co-57 -0 . 4.6E6 8.0E6 8.6E2 2.3E7
'Co-58 9.6E6 1.9E7 '2.9E3 4.7E7 Co-60 3.6E7 7.2E7 '7.8E3 7.2E8 Sr-89 4.9E7 2.6E7 8.3E3 3.1E7 Sr-90 1.0E9 8.0E8 2.7E6 1.2E9 !
Zr-95 6.2E7 1.1E8 4.1E3 2.0E8 !
Nb 05 2.3E8 4.5E8 2.8E3 8.2E8 le-l'29m 5.9E8 4.5E8 .1.0E3. 5.3E8
.Cs-134 ' 1.4E8 1.2E8 2.3E4 3.4E8 Cs-136 5.1E6 4.2E6 '4.0E3 9.5E6 Cs-137 1.2E8 9.3E7 1.7E4 4.0E8 Ba-140 - 5.0E6 4.2E6 6.0E3 7.4E6
'Ce-141 1.5E6 2.4E6 3.3E3 4.2E6 Ce-144 1.8E7 2.9E7 2.2E4 4.9E7 1.-131 6.5E8 - 4.3E8 3.3E5 5.9E8 I -133- 1.6El 8.6E0 5.9E4 6.7E4 I -135 1.1E-15 6.3E-16 1.2E4 6.9E4-UN-ID '1.1E8 9.4E7 2.8E3 1.4E8 I
i y . 1 Inhalation Pathway, units = yr L
Food & Ground Pathway, units = -(m r vr) 2-62 Rev. 21 07-01-89
______-___7_.
- .~,
r-
'IABLE 2-13 m 1
, DOSE1 PARAMETER R FOR. SECTOR D Page 1 of 3
- 3. ' '
Pathway -LCamp San Onofre Distance - 2.8 miles
.X/Q.-6.6E-8'sec/m* D/Q - 6.4E-10 m
' Infant Child Teen Adult Inhala- Food &. Inhala- Food & Inhala- ' Food & Inhala- Food &
n Radio- tion' Ground- tion' Ground tion ~ Ground tion Ground Nuclide- Pathway Pathway Pathway Pathway Pathway' Pathway Pathway Pathway
'H -3 - ' 1. 3 E3 ' - Cr-51 -0 ; 3.3E3 3.7E6 L Mn-54 > .7.7E4 1.1E9 Co 3.1E4 2.7E8 Co-58 ' 0-
. 1.1E5 '3.0E8 Co-60 ' 0-2.8E5 1.7E10 Sr-89 .-0-- -
0- 3.0E5 1.7E4 Sr-90 - 9.9E7: Zr-95. -0 1.5E5' '2.0E8.
Nb-95' '
0-- 1.0E5 1.1E8 Te-129m ' ' 3.7E4 1.6E7 Cs-134 --0 -
8.5E5 5. 5 E9 '
Cs-136 -0 . -0 . ~ 0-1.5E5 1.2E8 Cs-137 6.2E5 -8.2E9 Ba-140 2.2E5 1.6E7
.Ce-141 - 1.2E5 1.1E7
'Ce-144 -04 8.2E5 5.6E7 I -131 1.2E7- 1.4E7 I'-133' - - 2.2E6 2.0E6
-I -135 4.5E5 2.0E6 UN-ID' 1.0E5 6.0E8
'Ir.halation Pathway, units "C 2
Food & Ground Pathway,. units = (m )(mrem /vr) .
uC1/sec 2-63 Rev. 21 07-01-89
- p TABLE 2-13 DOSE PARAMETER Rg FOR SECTOP. D Page 2 of 3
- } ,
Pathway - Sheep (Meat)* Distance = 0.2 miles X/Q - 6.3E-6 sec/m D/Q - 6.6E-8 m 2 Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground f' Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 1.5E0 1.2E0 7.0E0 2.1E0 Cr-51 5.1El 1.0E2 1.8E1 2.6E4 Mn-54 7.8E2 1.4E3 4.3E2 7.6E6 ,
C0-57 4.7E3 8.1E3 1.7E2 1.9E6 Co-58 9.7E3 2.0E4 5.9E2 2.1E6 Co-60 3.7E4 7.3E4 1.6E3 1.2E8 '
Sr-89 5.0E4 2.6E4 1.7E3 3.1E4 Sr-90 1.0E6 8.1E5 5.5E5 1.3E6 Zr-95 6.3E4 1.1E5 8.3E2 1.6E6 Nb-95 2.4E5 4.5ES 5.7E2 1.6E6 Te-129m 6.0E5 4.5E5 2.0E2 6.5E5 Cs-134 1.4E5 1.2E5 4.7E3 3.8E7 Cs-136 5.1E3 4.3E3 8.1E2 8.3E5 Cs-137 1.3E5 9.5E4 3.4E3 5.7E7 Ba-140- 5.1E3 4.3E3 1.2E3 1. 2E5 Ce-141 1.5E3 2.4E3 6.6E2 7.9E4 Le-144 1.8E4 3.0E4 4.5E3 4.3E5 I -131 6.6E5 4.4E5 6.6E4 7.0E5 I -133 1.6E-2 8.7E-3 1.2E4 1.3E4 I -135 1.1E-18 6.4E-19 2.5E3 1.4E4 UN-ID 1.1E5 9.5E4 5.7E2 4.2E6 l
Inhalation Pathway, units = *C /
Food & Ground Pathway, units - (m r vr!
f 2-64 Rev. ?!
07-01-89
g -
W TABLE 2-13 in L' DOSE PARAMETER R j FOR SECTOR D Page 3 of 3 f
w} -.
Pathway - Deer Consumer Distance = 1.0 miles X/Q.= 3.3E-7~sec/m* D/0'=.3.3E-9 m '
n
' Infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &-
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway- Pathway H -3 2.8E1 2.3E1 3.5El 3.9El-Cr-51 - 5.0E4 - 1.0E5 9.1El 3.2E5
=Mn 7.7ES 1.4E6 2.1E3 4.1E7 Co-57 '4.6E6 8.0E6 8.6E2' 2.3E7 Co-58 9.6E6 1.9E7 2.9E3- 4.7E7 Cc-60 3.6E7 17.2E7 7.8E3 -7.2E8 Sr-89 4.9E7 2.6E7 8.3E3 3.1E7 Sr-90 1.0E9 8.0E8 2.7E6 1.2E9-Zr-95 6.2E7 1.1E8 4.1E3 2.0E8 Nb-95 - -0+ 2.3E8 4.5E8 2.8E3 8.2E8 Te-129m 0-- 5.9E8 4.5E8 - 1.0E3- 5.3E8 Cs-134. 1.4E8 1.2E8 2.3E4 3.4E8 Cs-136 --C- . 5.1E6 4.2E6 4.0E3' -9.5E6 '
Cs-137 1.2E8 9.3E7 1.7E4 4.0E8 Ba-140 5.0E6 - 4.2E6 6.0E3 7.4E6 Ce-141- 1.5E6 0- 2.4E6- 3.3E3 4.2E6 Ce-144 1.8E7 - 2.9E7 2.2E4 4.9E7 l~-131. 6.5E8 4.3E8 3.3E5- 5.9E8
- j. I -133 1.6El 8.6E0- 5.9E4 6.7E4 I -135 1.1E-15 6.3E-16 1.2E4 6.9E4 UN-ID 1.1E8 9.4E7 2.8E3 1.4E8 I
y Inhalation Pathway, units = [#
Food & Ground Pathway, units - m r r) j i
2-65 Rev. 21 07-01-89
o TABLE 2-14 y
DOSE PARAMETER R FOR SECTOR E Page 1 of 3 e) : Pathway - Camp Horno Distance - 4.0 miles X/Q'='6.6E-8 sec/m* D/Q = 6.4E-10 m '
Infant- Child Teen Adult -
Inhala- Food &. Inhala- Food &- Inhala- Food & Inhala- Food &-
Radio - tion Ground ti on.: Ground tion Ground tion Ground-Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 - 1 1.3E3 Cr-51 -0 . 3.3E3 3.7E6-Mn-54 - 7.7E4 1.1E9:
Co-57 3.1E4 2.7E8 Co-58 1.1E5 3.0E8 Co-60 2.8E5 1.7E10 -
Sr-89 3.0E5 1.7E4 Sr-90 -0 ' 9.9E7 Zr-95 1.5E5 2.0E8' Nb-95 :- 1.0E5 1.1E8 Te-129m '3.7E4 1.6E7 Cs-134 -0 . . 8.5E5 5.5E9 Cs-136 .
1.5E5 1.2E8' Cs-137 6.2E5 8.2E9 Ba-140 ' . '2.2E5 1.6E7 Ce-141 - 1.2E5 1.1E7 -
Ce-144 . 8.2E5 5.6E7
, :I -131 : 1.2E7. '1.4E7 I -133 2.2E6 2.0E6 I:-135 4.5E5 2.0EG UN-ID - 1.0E5 6.0E8 Inhalation Pathway, units = "C '
Food & Ground Pathway, units I* " VII 7
2-66 Rev. 21 07-01-89
TABLE 2-14 DOSE PARAMETER R FOR SECTOR.E 9
t .PageL2 of 3 Pathway - Sheep (Meat)*. ' Distance - 0.3 miles X/Q - 4.5E-6 sec/m D/Q = 5.9E-8 m
- Infant ' Child . Teen Adult Inhala- Food & Inhala- l Food & Inhala- Food &- Inh'ala . ' Food &
Radio- tion- Ground tion Ground- tion ' Ground- tion' Ground.
Nuclide. Pathway Pathway Pathway Pathway Pathway Pathway Pathway. Pathway
-H -3 1.5E3 1.2E0 7.0E0 2.1E0' Cr-51 5.1El 1.0E2 1.8E1 2.6E4-Mn-54~ 7.8E2 1.4E3 4.3E2 7.6E6 Co-57 4.7E3 8.1E4 1.7E2' 1.9E6 Co-58 9.7E3 2.0E4 5.9E2 2.1E6 Co-60 3.7E4 7.3E4 '1.6E3 1.2E8.
Sr-89 5.0E4 2.6E4 1.7E3 3.1E4 Sr 1.0E6 ~8.1E5 5.5E5 1.3E6 Zr-95 6.3E4- -0 ' 1.1E5 '8.3E2 1.6E6 Nb - 2.4E5 4.5E5 5.7E2 1.6E6 Te-129m . - .6.0E5 4.5E5 2.0E2 6.5E5 Cs-134 1.4E5 1.2E5 4.7E3 3.8E7 Cs-136: 5.1E3 4.3E3 8.1E2 8.3E5' Cs-137 - 1.3E5 9.5E4 3.4E3 5.7E7 Ba-140- 5.1E3 4.3E3 1.2E3 1.2E5 Ce-141 1.5E3 2.4E3- 6.6E2- - 7. 9E4 --
Ce-144- 1.8E4 3.0E4 4.5E3 '4.3ES-I -131 6.6E5 4.4E5 6.6E4 7.0E5 I--133- 1.6E-2 8.7E-3 1.2E4 1.3E4 1 -135 1.1E-18 6.4E-19 2.5E3 1.4E4 UN-ID 1.1ES 9.5E4 5.7E2 4.2E6 Inhalation Pathway, units = ["
I*
food & Ground Pathway, units {
2-67 Rev. 21 07-01-89
n . , .
m+n
(~
TABLE 2-14
, DOSE PAP.AMETER R FOR SECT 0ri E
_ Page 3 of 3
, g.
Pathway - Deer Consumer Distance .1.2 miles X/Q = 3.7E-7Lsec/m* , D/Q 8.3E-9 m
- Infant Child. Teen Adult.
Inhala- Food &- Inhala- Food & Inhala- Food &_ Inhala- Food &
Radio- tion Ground tion Ground- tion ; Ground tion Ground Nuclide Pathway Pathway Pathwsy Pathway Pathway . Pathway Pathway Pathway y,e H -3 2.8El' ~2. 3 E1 3.5El 3.9El
'Cr-51 -0 . ' 0-5.0E4 1.0E5 9.1 E1. 3.2E5 Mn-54. 7.7E5 1.1E6~ 2.1 E3 -- 4.1E7 L .Co-57 - 4.6E6- 8.0E6 8.6E2 2.3E7 H Co-58 -0; 9.6E6 -C- 1.9E7' 2.9E3 -4.7E7 Co-60 3.6E7 7.2E7' 7.8E3 7.2E8 Sr-89 4 '. 9 E7 2.6E7 8.3E3 3.1E7 Sr-90 1.0E9 8.0E8 2.7E6 1.2E9 Zr 6.2E7 1.1E8 4.1E3 2.0E8 Nb-95 '2.3E8 4.5E8 2.8E3 8.2E8 Te-129m 5.9E8 . 4.5E8 '1.0E3 5.3E8 Cs-134- 1.4E8 1.2E8 2.3E4 3.4E8 Cs-136 -5.1E6 4.2E6 4.0E3 9.5E6 Cs-137 1.2E8 9.3E7 1.7E4 4.0E8 Ba-140 5.0E6 4.2E6 6. 0E3 '- 7.4E6 Ce-141 1.5E6 2.4E6 3.3E3 4.2E6-Ce-144- 1.8E7 2.9E7 2.2E4 4.9E7 I -131 6.5E8 4.3E8. -3.3E5 5.9E8:
I -133 1.6El 8.6E0 5.9E4 6.7E4 I -135 1.1E-15 6.3E-16 1.2E4 6.9E4 UN-ID 1.1E8 9.4E7 2.8E3 - l'. 4 E8 1
Inhalation Pathway, units = "C$/
Food & Ground Pathway, units I" ^"
/]c I
L 2-68 Rev. 21 07-01-89 V _-- -_ _ _____- _ _ _ _ -
TABLE 2-15 DOSE PARAMETER R FOR SECTOR F 1-Pathway = San Onofre State Park Guard Shack Distance = 0.8 miles, X/Q = 8.1E-7 sec/m* D/Q = 7.1E-9 m-'
Infant Child l Teen Adult
. Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 7.2E1 Cr-51 1.9E2 2.7E5 Mn-54 4.4E3 7.9E7 Co-57 1.8E3 2.0E7 i Co-58 6.1E3 2.2E7 Co-60 1.6E4 1.2E9 Sr-89 1.7E4 1.2E3 Sr-90 5.7E6 Zr-95 8.6E3 1.4E7 Nb-95 5.9E3 7.8E6 Te-129m 2.1E3 1.1E6 Cs-134 4.8E4 3.9E8 Cs-136 S.4E3 8.6E6 Cs-137 3.5E4 5.9E8 Ba-140 1.2E4 1.2E6 Ce-141 6.9E3 7.8E5 Ce-144 4.7E4 4.0E6 I -131 6.8E5 9.8E5 I -133 1.2E5 1.4E5 I -135 2.6E4 1.4E5 UN-ID 5.9E3 4.3E7 I
InhalationPathway, units =]j*h" l
Food & Ground Pathway, units - (m r r) ,
j 2-69 Rev. 21 07-01-89 i
_ - _ - . - _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ O
P
~
m _
TABLE 2-15 DOSE PARAMETER R g FOR SECTOR F-
,=
-Pathway = Border Patrol Checkpt. Distance = 1.8 miles *
, X/Q - 2.4E-7 sec/m* D/Q = 1.8E-9 m-Infant Child Teen Adult Inhala - Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide- Pathway Pathway Pathway Pathway Pathway- Pathway Pathway Pathway H -3 - 3.6E2 ~Cr-51 '
. 9.5E2 l'3E6-
.Mn-54' 2.2E4 3.9E8 Co ' 0-9.0E3 9.8E7
-Co-58 '0-3.0E4- 1.1E8 Co-60 8.1E4 6.1E9 Sr-89 - 8.7E4 6.2E3 Sr-90' - 2.8E7 Zr-95 4.3E4 7.2E7 Hb-95 ' -3.0E4 3.9E7 i Te-129m - 1.0E4 5.6E6
-Cs-134 :2.4E5 1.9E9 Cs-136 4.2E4 4.3E7 Cs-137 1.8E5 2.9E9-Ba-140 - 6.2E4 5.9E6 Ce-141 3.4E4 3.9E6 Ce-144 - 2.3E5 2.0E7 I -131' 3.4E6 4.9E6 I:-133 6.1E5 7.0E5 I -135 - 1.3E5 2.2E5 UN-ID- 2.9E4 2.1E8 Inhalation Pathway, units = }{h" I* " "I Food & Ground Pathway, units 7
2-70 Rev. 21 07-01-89
f 3 ,
. TABLE 2-25
' DOSE PARAMETER R g FOR SECTOR F .J
- A~ Page 3 of 4 1 o
1 Pathway = Sheep (Meat)* Distance - 0.5 miles
'X/Q'= 1.9E-6 sec/m D/Q - 1.7E-8 m
- Infant. Child Teen Adult
, Inhala - Food & Inhala- Food & Inhala- Food & Inhala- . Food &
Radio-- tion Ground- tion. Ground tion Ground tion' Ground Nuclide - Pathway- Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3' . 1.5E0 1,2E0 7.0E0 2.1E0-Cr-51 - 5.1El 1.0E2 1.8E1 2.6E4 Mn-54 ' 7.8E7 1.4E3 4.3E2 7.6E6.
Co-57, - 4.7E3 8.1E3 1.7E2 1.9E6 Co-58. 9.7E3 2.0E4 -5.9E2 2.1E6
'Co-60' 3.7E4 7.3E4 1.6E3 1.2E8 Sr-89 5.0E4 -0 . 2.6E4 1.7E3 3.1E4 Sr-90 :0- 1.0E6 8.1E5 5.5E5 1.3E6 Zr-95 6.3E4 1.1E5 8.3E2' 1.6E6 1.6E6
.Nb-95 2.4E5 4.5E5 5.7E2 Te-129m 6.0E5 4.5E5 2.0E2 '6.5E5 Cs-134- 1.4E5 1.2E5 '4.7E3 '3.8E7 Cs-136 5.1E3 4.3E3 8.1E2 8.3E5:
Cs-137 -0 . 1.3E5 9.5E4 3.4E3 5.7E7 Ba'-140 -0 . 5.1E3 '4.3E3 1.2E3 1.2E5 .
Ce-141 1.5E3 2.4E3 6.6E2- 7.9E4 Ce-144 '1.8E4 0- 3.0E4 4.5E3 4.3E5 I -131' - 6.6ES 4.4E5 6.6E4- 7.0E5 1.6E-2 8.7E-3 1.2E4 1.3E4 I -133 . 1.1E-18 '6.4E-19 2.5E3 1.4E4 I -135' 4.2E6 UN-ID -0 , 1.1E5 9.5E4 5.7E2 l
Inhalation Pathway, units = %j*h" I" # ^"
Food & Ground Pathway, units /{c 2-71 Rev. 21 07-01-89
1 e ,
.I TABLE 2-15 l DOSE PARAMETER R g FOR SECTOR F q Page 4 of 4
')- .
Pathway.- Deer Consumer Distance - 1.4 miles r X/Q = 3.0E-7 sec/m". D/Q - 2.3E-9 m
- Infant Child Teen Adult Inhala- Food & Inhal a-- Food & Inhala- Food & Inhala . Food &
Radio-- tion -Ground tion Ground tion- Ground tion. Ground Nuclide: Pathway- Pathway Pathway Pathway Pathway ~ Pathway Pathway Pathway H -31 2.8El 2.3E1 3.5El 3.9El Cr-511 5.0E4 ' 0-1.0E5 9.lEl' 3.2E5 Mn-54 7.7E5 1.4E6 2.1E3 4.1E7-Co-57 - 4.6E6 8.0E6 8.6E2 -2.3E7 Co-58 - 9.6E6 1.9E7 2.9E3 4.7E7:
.Co-60 3.6E7 7.2E7. 7.8E3. 7.2E8
-Sr-89 . - 4.9E7. 2.6E7 8.3E3 3.1E7 Sr-90. -1.0E9 - 8.0E8 - 2.7E6 1.2E9 Zr-95 6.2E7 1.1E8 4.lE3 2.0E8 Nb-95 2.3E8 4.5E8 2.8E3 8.2E8 Te-129m 5.9E8 4.5E8 ~1.0E3 5.3E8 Cs-134. 1.4E8 1.2E8 2.3E4 3.4E8.
Cs-136' 5.1E6 4.2E6 4.0E3. 9.5E6-Cs-137 -G 1.2E8 9.3E7 1.7E4 4.0E8 Ba-140 5.0E6 4.2E6 6.0E3 7.4E6 Ce-141 1.5E6 2.4E6 '3.3E3 4.2E6 Ce-144 1.8E7 2.9E7- 2.2E4' 4.9E7-I -131 6.5E8 4.3E8 3.3E5 - 5.9E8 I -133 - 1.6El- 8.6E0 5.9E4~ 6.7E4 I -135 1.1E-15 6.3E-16 1.2E4 6.9E4 UN-ID 1.1E8 9.4E7~ 2.8E3 1.4E8 Inhalation Pathway, units = ["
I* ' "I Food & Ground Pathway, units j 2-72 Rev. 21 07-01-89
TABLE 2-16 DOSE PARAMETER R FOR SECTOR G 4
! . Pathway - San Onofre State Beach Camprgound Distance'- 0l.8 miles X/Q = 7.7E-7 sec/m* D/Q - 3.9E-9 m
- Infant Child Adult Teen Inhala- Food &. Inhala-- Food & Inhala- Food & Inhala- Food &'
Radio - tion Ground. tion Ground tion Ground tion Ground-Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway
'H--3 8.0El 1.4E2 1.6E2 -- 1.6E2 Cr 4.4E1 5.7E5 1.3E2 5.7E5 3.7E2 5.7E5 -4.1E2 5.7E5 Mn 3.lE3 1.7E8 5.3E3 1.7E8 8.2E3 1.7E8 9.5E3. 1.7E8 Co-57 6.0E2 4.2E7 1 6E3
. 4.2E7 3.9E3 4.2E7 3.9E3 4.2E7 Co-58 1.4E3: 4.7E7 4.2E3 4.7E7 1.2E4 4.7E7 1.3E4 4.7E7 j Co-60 3.9E3 2.7E9 1.2E4 2.7E9 3.2E4 2.7E9 3.5E4 2.7E9 Sr-89 4.9E4 2.7E3 7.4E4 2.7E3 5.4E4- 2.7E3 3.7E4 2.7E3 Sr-90 5.0E6 1.2E7- 1.3E7 . 1.2E7- Zr-95 2.7E3 3.lE7 7.5E3 3.lE7 1.8E4 3.1E7 1.9E4 3.lE7-Nb 1.6E3 1.7E7. 4.6E3 1.7E7 1.2E4 1.7E7 1.3E4 ' l.7E7 Te-129m '3.9E3 2.4E6 6.2E3 2.4E6 6.4E3 2.4E6- 4.5E3 2.4E6 Cs-134 8.7E4 8.4E8 1.3E5- 8.4E8 1.4E5 8.4E8 1.0E5 8.4E8 Cs-136 1.7E4 1.9E1 2.lE4 1.9E7 2.4E4 1.9E7 1.8E4 1.9E7-
.Cs-137 7.5E4 1.3E9 1.0E5 1.3E9 1.0E5 1.3E9 7.7E4 1.3E9 Ba-140 6.9E3 2.5E6' 9.1E3 2.5E6 2.8E4 2.5E6 2.7E4' 2.5E6 Ce-141 2.7E3 1.7E6 -7.0E3 1.7E6 1.6E4 1.7E6 1.5E4 1.7E6 Ce-144 1.8E4' '8.6E6- 4.8E4 8.6E6 .i.1E5 8.6E6 1.0E5 8.6E6 .i 1 -131 1.8E6 2.lE6 -2.0E6 2.1E6 1.8E6 2.1E6- 1.5E6 2.lE6 1 -133 4.4E5 3.0E5 4.7E5 3.0E5 3.6E5' 3.0E5 2.7E5 3.0E5 1 -135 8.6E4 3.1ES 9.8E4: 3.1E5 7.7E4 3.1E5 5.5E4 3.1E5 UN-ID 7.7E3' 9.2E7 1.4E4 9.2E7 1.6E4 9.2E7 ' 1.3E4 9.2E7-Inhalation Pathway, units = "C I* "
Food & Ground Pathway, units j 2-73 Rev. 21 07-01-89 y -
%, t w IABLE 2-16 L
DOSEPARAMETERR[FORSECTOR-G Page 2 of 4 .)
- g.'
Pathway - Hwy: Patrol Weigh Station Distance - 2.0 miles
'i b ~X/Q J2.0E-7-sec/m* D/Q = 8.5E-10 m '
Infant Child : Teen, Adult?
Inhala- Food & Inhala- Food & Inhala- ' Food'&. Inhal a- Food & .
Radio- tion : Ground tion Ground tion Ground tion Ground-Nuclide Pathway Pathway Pathway' Pathway Pathway Pathway Pathway. Pathway i
Hi-3 -0 ' ~ 2.9E2' Cr-51 7.6E2 1.lE6 Mn-54 - 1.8E4 3.2E8 Co -0 ' 7.2E3 7.8E7 Co-58 2.4E4 8.7E7 Co ~ - 6.5E4 4.9E9
-Sr-89 6.9E4- 4.9E3 Sr-90 2.3E7- 2r-95 - 3.4E4 5.7E7 Nb-95 2.4E4 3.lE7 Te-129e. -0 . 8.3E3 4.5E6 ,
CS-134L . 1.9E5 1.6E9 Cs-136 3.3E4 3.4E7 Cs-137- - 1.4E5 2.3E9 Ba-140' 5.0E4 4.7E6 Ce-141. 2.7E4 3.lE6
.Ce-144 1.9E5 .l.6E7'
.I -131 l-0- 2.7E6 3.9E6' I -133- 4.9E5 5.6E5 I -135 1.0E5 5.8E5-UN-ID '2.4E4 1.7E8 Inhalation Pathway, units = ]j*h" I* " "I
~
Food & Ground Pathway, units j 2-74 Rev. 21 07-01-89
- p. . ,
o . ,
TABLE 2-16 DOSE' PARAMETER R FOR SECTOR G Page 3 of 4
,1@' -l Pathway _'- Sheep-(Meat)*' Distance = 2.7 miles X/Q -11'.2E-7 sec/m D/Q = 4.8E-10 m
- Infant'1 Child . Teen Adult -
Inhala- Food & Inhala- Food &- Inhal a.- Food & Inhala- Food &
Radio-: tion ' Ground- tion Ground tion' Ground tion Ground Nuclide. Pathway Pathway Pathway . Pathway Pathway Pathway Pathway Pathway H -3 1.5E0 1.2E0 7.0E0 -2.1E0 Cr-51 5.1El 1.0E2 1.8E1 2.6E4 Mn-54 7.8E2 1.4E3 4.3E2 7.6E6 Co 4.7E3 8.1E3 1.7E2 1.9E6 Co 9.7E3 2.0E4 5.9E2 2.1E6 Co-60 0- 3.7E4 7.3E4 1.6E3 1.2E8-Sr-89 . 5.0E4 2.6E4 1.7E3 3.1E4 Sr-90 - 1.0E6 8.1E5 5.5E5 1.3E6 Zr -0 . 6.3E4_ 1.1E5 8.3E2 1.6E6 Nb-95 - 2.4E5 4.5E5 5.7E2 1.6E6
'Te-129m 6.0E5 4.5E5 2.0E2 6.5E5 Cs-134 1.4E5 1.2E5 4.7E3 3.8E7 Cs-136' 5.1E3 4.3E3 ~8.1E2 8.3E5 Cs-137' 1.3E5 9.5E4 3.4E3 5.7E7 Ba-140 -0 . 5.1E3 4.3E3 1.2E3 1.2E5-Ce-141 '- 1.5E3 2.4E3 6.6E2 7.9E4 Ce-144 1.8E4 3.0E4 4.5E3 4.3E5 I -131 0- 6.6E5 . 4.4E5 6.6E4 7.0E5
'I -133 1.6E-2 8.7E-3 1.2E4 1.3E4 I -135 1.1E-18 6.4E-19 2.5E3 1.4E4 UN-ID: 1.1E5 9.5E4 5.7E2 4.2E6 i
Inhalation Pathway, units = *]j*h" Food & Ground Pathway, units I* " "I j
2-75 Rev. 21 07-01-89
~.y
TABLE-2-16
[.
H DOSE PARAMETER R FOR SECTOR G U ._
Page 4 of 4
- j. s.
K 'I ' Pathway Distance = 3.3 miles Deer Consumer-X/Q = 8.8E-8 sec/m* D/Q = 3.2E-10 m
- Infant. Child Teen- ' Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio ' tion Ground tion ' Ground tion _ Ground tion Ground
. Nuclide. Pathway Pathway Pathway ! Pathway Pathway Pathway Pathway Pathway 7.-
H -3 2.8E1 2.3E1 3.5El ;3.9El Cr-51 5.0E4' 1.0E5 9.]E1. 3.2E5
. Mn-54. ' 0-7.7E5 1.4E6 2.1E3 4.1E7 -
Co-57 0- 4.6E6 8.0E6 8.6E2 2.3E7 Co-58 9.6E6 1.9E7 2.9E3 4.7E7 Co-60 ' - 3.6E7 -7.2E7 7.8E3 7.2EB Sr-89 4.9E7 2.6E7 '8.3E3 3.1E71 Sr-90 1.0E9 8.0E6 2.7E6 1.2E9 Zr-95 - 6.2E7 1.1E8 4.1E3 2.0EC Nb-95 2.3E8 4.5E8 2.8E3 8.2E8 Te-129m -0 5.9E8 4.5E8 1.0E3 5.3E8; Cs-134 -0 . 1.4E8 1.2E8 2.3E4 3.4E8 Cs-136 5.1E6 4.2E6 4.0E3 9.5E6 C3-137 - 1.2E8. 9.3E7 1.7E4 , 4.0E8 Ba-140 5.0E6 4.2E6 6.0E3
- 7.4E6 Ce-141 1.5E6 2.4E6 3.3E3 4.2E6 Ce-144 1.8E7 2.9E7 2.2E4- 4.9E7 I -131 - 6.5E8 4.3E8 3.3E5 5.9E8 I -133 -0 . 1.6El 8.SE0 5.9E4 6.7E4 I ~135 1.1E-15 6.3E-16 1.2E4 6.9E4 UN-ID 1.1E8 - 9.4E7 2.8E3 1.4E8 l
Inhalation Pathway, units = '}h*
I* " "I Food & Ground Pathway, units j 2-76 Rev. 21 07-01-89
.m -
. , . .1
- q. . .f g-I g f'.9iTOTAL!DOSECALCULATIONS.
2 aj '2.9.1 : Total' Dose to Most Likely Member cf the Public e.
M'.
b ,
The.. total. annual. dos'e or total. dose commitment.to.any member of the'public,.due to releases of radioactivity and
. to. radiation,z from uranium' fuel . cycle' sources within ,
i 5, miles' of1the Site is calculated using the following (a
expressions. This methodology'is used.to meet the dose
.~1 imitations of 40 CFR 190 per twelve consecutive months.
p The transportation of radioactive material is excluded r
!from the" dose calculations.
.The Annual Total Dose is determined monthly for maximum-organ (gas & liquid), whole body (gas & liquid) and
- thyroid _(gas & liquid) to verify that the Site total E (Units 1, 2 and 3) is less than or equal to 25 mrem, 25 mrem and 75 mrem respectively.
.1 Annual Total Organ' Dose ( OT(organ))
. . 12 2/3- H
'D (organ) - I I -D (0G) + D (OL) + D *(0G)- (2-20)
. TOT 1-1 j-1 jl- j1 jl ;
a j - Units 1, 2 and 3 1 - months 1 - 12**
~
- NOTE: d#(0G)=0forbone
.11
- All to be summed over the most recent 12 months. ,
ere:
p n _ (2-21)
L 0 (0G) - K I C)Riki 4 N k; i - each :sotope in ji 1-1 specific organ category L
K = 3.1688E-2 { [i 2-77 Rev. 21 07-01-89
- c. , g. .
g; L , ' '
~*;" l 2". 9 ; 1 : 'LTotal !Dose'to..Most Likely Member of the Public (Continued) fi:'
- n - Nutbeltof isotopes in the'specified organ category cy y . Cg ) --Total.. particulate gas curies . released for the month m- 1
, Li .,
RgW'-Controlling g 1ccationfactorsfrom ODCM Tables 2-6, Units.1'and 2/3 D (0L) - Liquid organ dose for the specified organ in mrem for the -
jl- month. -[ Reference ODCM Units 2/3 (1-19), Unit 1 (1-13))_
Y
- ji (0G) - Gas organ (Note: H *dose bone'form tritium in =mrem contribution 0) for the month.
- r. 2 , Annual Total Whole ' Body Dose ID TOT E
- 12. 2/3 -
, :0' (WB) - I:
. 121 D (WBL) 4 DH8(0G) + 0.9 D (y) + D(Direct);. (2-22)
TOT ' 1-l' j=l j1 j1 j1 j ' Units'1, 2 and 3
' - months 1 - 12*
- To be summed over the most recent 12 months.
, .i Where:
D (WBL) - Liquid whole body organ dose in mrem for the whole month.
j1 [ Reference ODCM Units 2/3 (1-19), Unit 1 ODCM (1-13)]'
7 DH8(0G) , : Gas organ dose .from tritium in ,nrsm for it 9 month.
ji (from (2-21))
i D (y) = Gamma air' dose in mrad for the month.
- jl- 'O.9 converti mrad to mrem.
L
[ Reference ODCM Units 2/3 (J.-14), Unit 1 ODCM (2-10))
1 4 n D (Direct) - I max [D(beach),) I D(bkgd)$ .0342 (2-23) j-1 1-1 s n L <
i - for all TLDs per quarter j - for Quarters 1-4 p j 2-78 Rev. 21 07-01-89 p ,
~
J
- ' .. 1
-___----.______--__._____._-___---D
fL '
i ,di e
,m ,
, . .a -
"' '2".'9112l Arinual? Total-Whole B'o'dy Dose (Q TOT fWB)) (Continued)'
e i.s .
M
'O 1
1* Direct Radiation.
1 di,_ '
+ -
Th'e direct' radiation levels are evaluated most recently
'k?!
n.
Z.O ,
, using' cadmium'c' overed TLDs.-lThe TLDs are placed at 59-
'; locations ~~around th'e site. The; average: dose:from'TLDs- .
5' to: 50 'milesifrom the "dte islused as background.. These .
sites'are. subject to change. y
- The' background is. subtracted from the highest reading
- plant. surrounding area TLD. :This value isitheidirect 1 W- dose.but must be prorated by the' occupancy factor.
' Example: beach time of.300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, or 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for' landward occupancy.
v yr yr
.3' ~ AnnualL Totali Thyroid Dose -( OT(THYROID))-~
, p.- .
- 12. 2/3 .
D'(THYROID);- I: Il '(D (OG) + D-(OL) ; .(2-24)-
. TOT.. 1-1 . j-1. ;jl j1 j'= Units l', 2 and;3 1 - months 1 - 12*
- To be summed over the most recent 12 months'.
1 Where:
i
'D-(OG) - Thyroid organ dose from gaseous iodine for the' month E , jl in. mrem. (from 2-21)-.
R'oa. 1
'D (OL) - Liquid thyroid organ dose for the month in mrem.
X' ji . [ Reference ODCM Units 2/3 (1-19), Unit 1 ODCM (1-13)]
6 a
R;l, tY i
2-79 Rev. 21
- b. y; 07-01-89 go QJ; ' l j
.a...
n.. .= - -
192gi r i >
1 ,.
,M >
g , ,[3 0 ~ PROJECTED DOSES
't i
, i .' . 3.lc Liquid Dose Projestion 3
fr- 'The' methodology used for projecting a liquid. dose over 31 days for Specification 1.3.1.'1 is as followsi
' 1. Determine the monthly [ total bocy and' organ doses resulting.
-from releases during_the previous twelve' months.
- 2. Projected dose - Previous'12 months'. dose d'ivided'by 12'for the total body and each organ.
3'.2 Gaseous' Dose' Projection The metho'dology. used for.' projecting a gaseous dose over 31 days for specification.'2.4.1.1 is as follows:
l '. . Determine ~the monthly gamma beta and organ dose resulting from releases during the previous twelve months.
- 2. Projected dose - Previous l12 months' dose divided by 12 for-the gamma,. beta and organ. doses.
E .
3-1 Rev. 21 07-01.-89 l- , _
c- - -
i L - l
.4.0 E0VIPMENT. l 4.1 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION q
~'j SPECIFICATION The radioactive liquid effluent monitoring instrumentation 4.1.1 "l channels shown in Table 4-l'sha?1 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 gz of these channels shall be determined in accordance with Section 1.4. 1 APPLICABILITY: At all times ll ACTION:
- a. With a radioactive liquid effluent monitoring. instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 4-1. Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument (s) remain inoperable for greater than .30 days, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrbeted in a timely manner.
SURVEILLANCE RE0UIREMENTS
.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 i operations at the frequencies shown in Table 4-2.
.2 At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, all pumps required tn 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 4-1 Rev. 21 07-01-89
j I 1
- 1]4 yR - _
e a
- yQ A I [
N
.O -
.'9 I 8 - 9 0 9 1 1 g't-1 1 T 2 2 3 2 2 3 3 3 3 t .C v ;, A y: 18 2 -
9
. 1 y
MLL UEB SE i0 .
v-e7.
R0
=
MNA
=
1 - l 1 l 1 1 1 l' 1 I NR g ~
NAE IHP MCO e
g N
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A T =
N n~ E M
-: U R
T S
- N I
G z
N -
2 I
R 4 O
, T I
1 2 N 1 e e 4 O 2 n n
- M 8 i i E T 7 L L L
B N - t t
. E a U )
p
)
p n n L 3 T. e e F 1 m R m u u F 8 u ) u l l E 7 S 3 S. f f
( f f
, D M L- n o
2 t n
t n
'no E E -
I R T e e s ~s U
O A L
R i
t a e l
u l
u' i t
a s
a s
a I
L A 3 z n f f z p p
/ i i f f i y y E G 2 l~ L E E l B B
- ' V N a a I
I - r- t n n r n n g T D t-~ n w w t w w C
I e u7 e o o e u o o A V n e1 u d d n e d d 0 O i N8 l w w i N w w I R L (7 f o o L ( o o D P -
f l l -
l l A t .
E B B S t n B B R S n ws - E n w 7
R e oT s ) ) C e o ) )
O u dR p 8 9 I u d 8 9 T l f
w) m u
8 8 V E
l f o w 8 8 I o3 0 0 0 0 N f l( S E E D f l E E OE E B2 (9 (3 E B ( (
MS g 5 5 T A e r- n r7 r7 N e r r r YE t s
o i o6 o6 E t o o o TL t e d tT tT M s te t t IE VR I -
d a
w an ri eL l
i u
aR r) e3 aR r) e3 E
R U d a
w an ri eL a
r e
a r
e b
TF a n B n( n( S a n n n CO R et e2 e2 A 3 et e e A Gn e G G E Gn G G 0N d e n - - M d e T
N I O DI i
u mu al i
b m
ae m
ae E i
u mu al m
a m
a
- E AT q ef r en en T q ef e e
, M RA i tf u ti ti A i tf t t U N L SE T SL SL R L SE S S R SI T SM W S OR O N RE . . . . . L . . .
I GT a b c d e F a b c d i
1 2
_~
s ll l I
73 '
+
- i. .!
TABLE 4-1 (Continued) p TABLE NOTATION'
~ "~~
ACTION 281- With the number of. channels 0PERABLE. less than required by the:
Minimum Channels OPERABLE ' requirements, -effluent _ releases may continue.provided!that prior to_ initiating _a release:
- a. ~At"least two independent' samples are analyzed in accordance with. Specification 1-.1.1;l and
- b. ;At least-two technically ' qualified members o.f the Facility Staff. independently verify _the release rate ' calculation- and-
' discharge line. valving; Otherwise,: suspend release of radioactive effluents via this
_ pathway.
ACTION 29 - With the number of channels OPERABLE less than required by the L Minimum Channels OPERABLE requirement, effluent releases via this pathway may. continue provided_ grab samples are analyzed for gross
- r. radioactivity'(beta or gamma) at a limit of detection of at least 10 microcuries/ gram:
- a. .At least once per.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity cf 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.
in ACTION 30 With the' number of channels OPERABLE less than required by the Minimum Channels GPERABLE requirement, effluent releases'via_this pathway'mty continue provided that, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, grab l; samples, are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10" microcuries/ml or
. lock closed valve S22U19-MUO77 or:S22U19-MUO78 and divert ' flow to the'radwaste sump.for processing'as: liquid radwaste.
ACTION 31 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least l once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump curves may be used to
- estimate flow.
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TABLE NOTATION
,)
-(l) The ' CHANNEL TEST shall also deraonstrate that automatic isolation of this
- - pathway and control room alarm annunciation occurs if any of the-following conditir " exists
- *
- 1. Instrument indicat measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
(2) The initial CHANNEL CALIBRATION 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 Cf.LIBRATION, sources th:t have been related to the initial calibration shall be used.
(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of' release CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases.are made.
l
- If the instrument controls are not in the operate mode, procedures snall require that the channel be declared inoperable.
i 4-5 Rev. 21 01-01-89
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[4[0i
- IOUIPMENT
[.4.'2 : IRADI0 ACTIVE GASEOUS' EFFLUENT = MONITORING INSTRUMENTATION-SPECIFICATION. ,
4 .- 2.1 The. radic::.~.ive gaseous effluent monitoring instrumentation:
channels shown in Table' 4-3 shall be OPERABLE"with' their -
Lalarm/ trip setpoints-set l to ensure that the limits of Specification' 2.1.1 are not exceedeo.. The alarm / trip setpoints of 'these' channels shall' be determined' in accordance,with ODCM.
' APPLICABILITY: -At all times
.a. --With a radioactive gaseous effluent monitoring instrumentation channel .larm/ trip setpoint,.less conservative than required by,
-the above specification, immediately suspend the release:of radiohetive gaseous effluents monitored by the affected channel t
or declare the channel inoperable.
- b. '
With less than the minimum number of radioactive gaseous-
' effluent monitoring instrumentation ' channels OPERABLE, take the ACTION shown in Table 4-3. Exert-best efforts to return the
^
instrume,.t to OPERABLE. status within 30 days 'and, additionally, if the inoperable instrument (s) remain inoperable for greater than 30.. days, explain in the next Semiannual: Radioactive Effluent Release Peport why the inoperability was not corrected in a timely _ manner.
SURVEILLANCE RE0VIREMENTS
.1 EachLradioactive 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.
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TABLE 4-3 (Continued) ,
i TABLE NOTATION 3
At all times.
t
- MODES 1-4 with any main steam isolation elve and/or any main steam isolating bypass valve not fully closed.
(1) 2(3)RT-7818 is not equipped to monitor process flow. If another means of ,
continuously monitoring process flow is not available, then comply with {
ACTION 36.
(2) 2/3 RT-7808 is not equipped to monitor process flow. If another means of '
continuously monitoring plant vent stack flow is not available, then comply with ACTION 36.
ACTION 35 - With the number of channels OPERABLE lesr. than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s)~
may be released to the environment provided that prior to initiating the release. :
- a. At least two independent samples of the tank's contents are !
analyzed, and
- b. At least two technically qualified members of the Facility i Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, 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 pathway may continue provided the flow rate is estimated at laast once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. . System design characteristics.may be used to estimate flow. i
! ACTION 37 - With the number of channels OPERABLE less than requirec by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once
, per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i l ACTION 38 - With the number of channels OPERABLE less than required by the l Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway.
ACTION 39 - Remaining in Technical Specifications.
ACTION 40 - With the number of channels OPERABLE less than required by the
- Minimum Channels OPERABLE requirement, effluent releases via the ,
l effected pathway may continue provided samples are continuously j, collected with auxiliary sampling equipment as required in Table 2-1.
l l
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m@ ; & ",
- ~ l=. TABLE NOTATION':-
f Q '
?,>' *.
At lall Ttimes.
n -
- Moder l-4 with- any main: steam isolation valve.and/or any mainisteam isolating Wg
~ m a s bypass valve..not fully closed.
~(1). (The CHANNEL FUNCTIONAL TEST.:shall also demonstrate that automatic sisolation_ cf this pathway and control room alarm annunciation occurs if qs
- any;of the folloWing conditions exists:#-
'l. Instrument? indicates measured levels above'the alarm / trip setpoint.
- 2. . Circuit failure.
3.1 Instrument indicates a downscale failure.
+
'(2) .ThelCHANNEL FUNCTIONAL TEST shall also i demonstrate tht control room alarm -
annunciation occurs if any of the following conditions exists #:
m 1. :In's trument indicases measured levels above the alarm setpoint. ' '
- 2. Circuit failure.
3 lnstrument indicates a downscale failure.
4
(?) )The . initial CHANNEL CALIBRATION _ 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 froni suppliers that participate.
- in. measurement assurar,ce' activities with NBS. These standards shall permit calibrating the system over its intended range of. energy and- a measurement range. For stbsequer.t CHANNEL CALIBRATION, sources that have
. heen related to the ir.itial . calibration shall be used. .
(4) -Prior to 'each release and et least once 'per month,
- If the instrument controls are not set in the operate mode, procedures shall call for declaring the chaimel inoperable.
1
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5.0 RADIOLOGICAL. ENVIRONMENTAL MONITORING 5.1 The radiological environmental monitoring program shall be conducted as L
specified in Table 5-1. The requirements are applicable at all times.
}- 5.1.1 Should the radiological environmental monitoring program L not be conducted as specified tin Table 5-1, in lieu of any other report required by Technical Specification (s)
(U 2,3) 6.9.1, prepare and submit to the Commission, in the Annual Radiological Operating Report (see Section 5.4),
a description of the reasons for not conducting,the program as required and the plans for preventing a recurrence.
5.1.2 Should the l'evel of radioactivity in an environmental sampling nedium 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) ,
(U 2,3) 6.9.1, prepare and submit to the Commission, q within 30 days from the end of the affected calendar quarter a Report pursuant to Technical Specification (s)
(U 2,3) 6.9.1.13. When more than one of the radionuclides in Table 5-2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) + concentration (2) 4 . . 2 1.0 l limit level (1) limit level (2) t When radionuclides other than those in Table 5-2 are detected and-are the result of plant effluents, this report shall be submitted if the pate.Aial annual dose to an individual is equal to or greater than the calendar'yeat limits of Specification (s) (U 2,3) 1.2.1, (U 2,3) 2.2.1 or (U 2,3) 2.3.1, as appropriate. This report is not required if the measured level of radioactivity was' not the result of plant effluents; however, 'in such an event, the j condiUon shall be reported and described in the Annual Radiological Environmental Operating Report (see Section 5.4).
a 5.1.3 With fresh leafy vegetable samples or fleshy vegetable i samples unavailable from one or more of the sample locations required by Table 5-1, in lieu of any other report required by Technical Specification (s) (U 2,3) 6.9.2, a Special Report which identifies the cause of the unavailability of sampler and identifies locations for obtaining replacement samples. The locations from which samples were unavailable may then be deleted from those :
required by Table 5-1, provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations.
5.1.4 The radiological environmental monitoring samples snall be collected pursuant to Table 5-1 from the locations given in Tables 5-4 and 5-5 and Figure 5-2 and shall be analyzed pursuant to the requirements of Tables 5-1 and 5-3.
5-1 Rev. 21 1 07-01-89 !
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TABLE NOTATION' N
] .a. .The LLD. is' the smallest' concentration' of ra'dioactive material 'in a sample-that will be detected with 95% probability with 5% probability of falsely
- concluding .that al blank observation represents a "real" signal.
l: :For a particular measurement. system (which may include radiochemical separation):
4.66 s 4 LLD - b E . V . 2.22 x IO* . Y . exp (-Aat)
Nhere:
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 mintite),
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 picocurie, Y is the fractional radiochemical yield (when applicable),
1 is the radioactive decay constant for the particular radionuclides, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
The value of sb used in the calculation of the LLD for a particular measurement system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.
In calculating the LLD for a radionuclides 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.
5-8 Rev. 21 07-01-89
TABLE'5-3 iContinued)
TABLE NOTATION 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.
A DOSteriori (after the fact) limit for a particular measurement.*'
,b. LLD'for drinking water.
- c. -Other peaks which are measurable and identifiable, together with the radionuclides in Table 5-4, shall be. identified and reported.
- For a more complete discussion of the,LLD, and other detection limits, see the following:
(1) HASL Procedures Manual, HASL-300 (revised annually).
(2) Currie, L. A., " Limits for Qualitative Detection and 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).
5-9 Rev. 21 07-01-89
5.2- LAND USE CENSUS 5.2.1 A land use census shall be conducted and shall identify the
] lccation 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 l meteorological sectors within a distance 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 witnin o distance of three miles.
5.2.2 With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Technical Specification (U 2,3) 2.3.1, as appropriate, in lieu of any other report required by Technical Specification (s)
(U 2,3) 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Technical Specification (s) (U 2,3) 6.9.2, a Special Report which identifies the new location (s).
5.2.3 With a land use census identifying a location (s) which yields a calculated dose or dose commitment via the same exposure pathwLy 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 (s) (U 2,3) 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Technical Specification (s) (U 2,3) 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 the 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.
5.2.4 The lar.d use census shall be conducted at least once per 12 months between the dates of June I and October 1 using that information which will provide the best results, such as by a door-to-door survey, aerial survey, or Dy consulting local agriculture authorities.
5.2.5 The requirements of Section 5.2 are applicable at all times. 1 5.3 INTERLABORATORY COMPARISON PROGRAM 5.3.1 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.
- Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.
5-10 Rev. 21 07-01-89 l 1
1
_____- - _ = - - - - _ _ _ .__ - - - - . - .- - -- __ ____ .
5.3 INTERLABORATORY COMPARISON' PROGRAM (Continued) 5.3.2 With analyses' not being performed as required above, report
<, _ . -the corrective _ actions taken to_ prevent a recurrence to
't the Commission in- the Annual Radiological Environmental Operating Report.
5.3.3 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-b.e included in the Annual Radiological Environmental Operating.
Report (see.Section 5.4).
5.3.4 The requirements of Section 5.3 are applicable at all times.
5.4: ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 5.4.1 The annual' radiological . environmental operating reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.' The reports shall also include the results of land use censuses required by Section 5.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of th;) problem and a planned course of action to alleviate the problem.
The annual radiological-environmental operating reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all l radiological environmental samples taken during the report l period. 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 also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from the mid-point of reactor Units 2 and 3; and the results of licensee participation in the Interlaboratory Comparison Progrh%
required by Section 5.3. N
- A single submittal may be made for a multiple unit station, combining those sections that are common to all units at the station.
5-11 Rev. 21 07-01-89 l
---2----__----__-_a------ - - - - -- . - - - - - -
Y Q4 [ '5.5 SAMPLE'LOCAT10ts;
& , The Radiological' Environmental; Monitoring Sample Locations are -
i ' identified in Figurei5-1. These. sample locations are described in h, ,
Tables 5-4~ and 5-5 and indicates- the distance in miles -and. the-direction, determined'from degrees true north, from the center of the.
Units-2 and 3: building complex. .. Table 5-6 gives the sector and direction designation for the. Radiological Environmental . Monitoring Sample Location on Map, Figure 5-1.
5.6 M EEs b
MONITORING PROGRAM
- 5. 6.1 -' , The radiological _ monitoring program required by this specification provides measurements of radiation and of radioactive' materials 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 program thereby-supplements the radiological effluent monitoring program by verifying that the measurable concentrations of. radioactive materials ~and levels of radiation _are not higher than expected on the basis of the effluent measurements and modeling.of the environmental exposure pathways. The
. initially specified monitoring program will be effective.
for at least the first three years of commercial operation.
Following this period, program changes may be initiated based on operational experience.
' The detection capabilities required by Table are state-of-the-art for routine environniental measurements in industrial laboratories. It should be recognized that the LLD is: defined as an a oriori (before the fact) . limit representing the capability of a measurement system and not-as.a costeriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering 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.
e 5-12 Rev. 21 07-01-89
5.6 BASES (Continued) 1 LAND USE CENSUS 3 5.6.2 This specification is provided to ensure that changes in the use of. unrestricted areas are identified and that
~
modifications to the monitoring program are made if required by the results of this census. The best survey information from the door-to-door, . aerial or consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR'Part 50. Restricting the census to gardens of greater than 500 square . feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this ;
minimum garden size, the following assumptions were used,
- 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter.
INTERLABORATORY COMPARISON PROGRAM 5.6.3 The requirement for participation in an Interlaboratory Comparison Program is provided to' ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.
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i 5-13 Rev. 21 07-01-80 I l
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Page 1 of 6' TABLE 5 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS-DISTANCE *
. TYPE OF SAMPLE AND SAMPLING LOCATION *** (miles)' DIRECTION
- Direct Radiation 1 City'of San Clemente (SDG&E Offices) 5.6 NW 2 Camp _ San Mateo (MCB, Camp Pendleton)- 3.5 N 3 Camp San Onofre (MCB, Camp Pendleton) 2.6 NE 4 Camp Horno (MCB, Camp Pendleton) 4.5 E.
5 Camp Las.Pulgas (MCB, Camp Pendleton) 8.5 E 6 Old_ Route 101 (East-Southeast) 3.0 ESE 7 Old Route 101 (East-Northeast) 0.5 ENE 8 Noncommissioned Officers Beach Club 1.5 NW 9- Basilone Road /I-5 Freeway Offramp 2.0 NW 10 Bluff (Adjacent'to PIC #1) 0.7 WNW 11 Former Visitor's Center 0.3** NW 12 South Edge of Switchyard 0.2** E 13 Southeast Site-boundary (Bluff) 0.4** SE 14 Huntington Beach Generating-Station 37 NW 15- Southeast Site Boundary (Office Building) 0.2** SE l
16 East Southeast Site Boundary 0.4** ESE l' 17 Transit Dose - -
j 18 Transit Dose - -
19 San Clemente Highlands 5.0 NNW 3
L L 20 San Clemente Pier 5.3 NW
. 21 Concordia Elementary School - San Clemente 3.5 NW L
22 Former Coast Guard Station - San Mateo Paint 2.7 WNW 23 San Clemente General Hospital 8.2 NW 24 San Clemente High School 6.0 NW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
I' ** 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 5-14 Rev. 21 07-01-89
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.'Page 2'of 6-p
. TABLE 5-4
' RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE *
, -TYPE OF SAMPLE AND SAMPLING LOCATION *** (miles)~ DIRECTION *'
' Direct Radiation (Continued) 25 Convalescent Home - San Clemente 8.0- NW 26 Dana Hills High School 11.0- NW 27 U.S. Post Office - Dana Point 10.6 NW 28- Doheny Fire Station - Capistrano Beach 9.5- NW 29 San 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 Police Department' 32.0 NW-33 Camp Talega (MCB, Camp Pendleton) 5.7 N 34 San Onofre School (MCB, Camp Pendleton) 1.9 NW 35 . Range 312 (MCB, Camp Pendleton) 4.7 NNE 36 Range 208C (MCB, Camp Pendleton) 4.2 NE 37 ' Laguna Niguel Fire Station 14.2 .NW 38 San Onof're 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 l
41 Old Route-101 - East 0.4 E 42 Horno Canyon (MCB, Camp Pendleton) 4.7 E i 43 Edson Range (MCB, Camp Pendleton) 10.6 SE 44 Fallbrook Fire Station 18.0 E l 45 Interstate 5 Weigh Station 2.0 ESE 46 San Onofre State Beach Park 1.0 SE 47 Camp Las Flores (MCB, Camp Pendleton) 8.6 SE 48 Mainside (MCB, Camp Pendleton) 15.0 ESE L
Distance (miles) and Direction (sector) are measured relative to Units 2 and 1 3 midpoint. Direction is determined from degrees true north.
- Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.
- MCB - Marine Corps Base PIC - Pressurized Ion Chamber 5-15 Rev. 21 07-01-89 l
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R, .
W Page 3 of 6 i 4 TABLE 5-4'
\
LRADIOLOGICALENVIRONMENTALMONITORING'SAMPLELOCATIONS DISTANCE *
- h. TYPE'0F SAMPLE'AND SAMPLING' LOCATION *** (miles) DIRECTION *
. Direct Radiation (Continued) 49- Camp Chappo (MCB, Camp Pendleton) 12.8 ESE 50 Oceanside Fire Station. 15.5 SE
- 51 ' Carlsbad Fire Station - 18.6 SE 52 Vista Fire. Station '
21 ESE 53 San Diego County Operations Center 45 SE 54 Escondido Fire Station 32 ESE 55 San Onofre State Beach (Unit 1, West Southwest) 0.2** WSW-
- 56. San Onofre State. Beach (Unit 1, Southwest) 0.1** .SW 57 San Onofre State Beach (Unit 2) 0.1** SSW 58 San'Onofre State Beach (Unit 3) 0.1** S 59 SONGS Meteorological Tower 0.3** WNW ;
60 Transit Control Storage Area - -
61 : Mesa - East Boundary (Adjacent to PIC #4) 0.7 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 - Camp Pendleton'(Adjacent to PIC #8) 0.7. E
, 66 San Onofre State Beach (Adjacent to PIC_#9) 0.6 ESE 67 Former SONGS Evaporation Pond (Adjacent to PIC #2) 0.6 NW 68 Range 210C (MCB, Camp Pendleton) 4.3 ENE 99 Transit Dose - -
Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
- Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.
- MCB - Marine Corps Base PIC - Pressurized Ion Chamber 5-16 Rev. 21 07-01-89
m
, Pacje 4 of 6 1
, TABLE 5-4 l p,
, RADIOLOGICAL ENVIRONMENTAL' MONITORING S ' AMPLE ~ LOCATIONS- _g 1
E TYPE OF-SAMPLE AND SAMPLING LOCATION
. DISTANCE *
(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- 0.7 WNW 11 Mesa E0F~ 0.7 NNW 12' Former SONGS Evaporation Pond 0:6 .NW 13 Marine Corps Base (Camp Pendleton East) 0.7 E Soil Samples l' Camp San Onofre 2.5 NE
.- 2 Old Route 101 ' East Southeast 3.0 ESE 3 Basilone Road /I-5 Freeway Offramp 2.0 NW 4 Huntington Beach Generating Station 37.0 NW 5 'Former Visitor's-Center 0.2** NNW.
Ocean Water A Station Discharge Outfall - Unit 1 0.5 SSW B Outfall - Unit 2 0.7 SW C Outfall - Unit 3 0.7 SW D Newport Beach 30.0 NW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
- Distances are within.the Units 2 and 3 Site boundary (0.4 mile in all sectors) and not required by Technical Specification.
5-17 Rev. 21 07-01-89
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-2AL TABLE 5-4' ,
U RADIOLOGICAL ENVIRONMENTAL' MONITORING SAMPLE LOCATIONS +
j i
F ,
DISTANCE *
. TYPE-0F SAMPLE AND' SAMPLING LOCATION (milest . DIRECTION *-
Drinking. Water 7 '
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 w
Shoreline Sediment (Beach Sand) 1 San Onofre State Beach (0.6 mile Southeast)~ 0.6 SE 2: , San Onofre Surfing Beach O.9 NW 3- San Onofre State Beach-(3.1: miles Southeast) 3.1 - SE
~
-4 Newport Beach (North End) 30.0- NW Local Crops 1 San Mateo Canyon (San Clemente Canyon) 2.6 NW 2 Southeast of Oceanside 22.0 SE 1
Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
5-18 Rev. 21 07-01-89
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Page.6.of 6 TABLE 5-4 II.~
RADIOLOGICAL ENVIRONMENTAL MONITORING l SAMPLE LOCATIONS
-J - DISTANCE
- TYPE'0F SAMPLE AND SAMPLING LOCATION (miles) DIRECTION *-
Non-Migratory Marine Animals A " Unit l~ 0utfall! 0.6 WSW B- Units 2 and=3 Outfall' 0;7- S$W-
-C- Newport. Beach 30.0' NW-
.i.
' Kelp. , ,
A San Onofre Kelp Bed 1.5 S B San Mateo Kelp Bed' 3.5 WNW
'A _C- Barn Kelp; Bed 6.6 SSE D- - Newport Beach. 30.0 NW Ocean Bottom Sediments A Unit 1 Outfall (0.5 mile West)1 0.5 W
~
B' Unit'l Outfall (0.6 mile West). 0.6 W C- ' Unit'2 Outfall 0.8 SSW 1 .D Unit 3 0utfall 0.9 S E- Newport Beach _ 30.0 NW
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(
Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
5-19 Rev. 21 07-01-89
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. g-TABLE 5-5'
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.PIC --RADI0 LOGICAL ENVIRONMENTAL MONITORING LOCATIONS' r;
4 -
. . Theta 'DI$TANCE*
-PRESSURIZED ION CHAMBERS (Decrees)*~ Meters miles DIRECTION / SECTOR *'
S1 San Onofre' Beach 298* -1070 0.7 WNW.: P.
S2-c SONGS Former Evap. Pnd 313' 890 0.6 NW Q:
l S3 Japanese Mesa. :340* 1150 .0.7 NNW -R-S4-.MCB,- Camp Pendleton. 3 1120 0. 7 -- N A
, S5 MCB .Camri Pendleton. 19' 1050. 0.6 NNE B S6 MCB - Camp Pendleton 46' 940 0.6 NE C S7 MCB . Camp Pendleton 70* 870 0.5 ENE D
.S8 MCB . Camp Pendleton 98* 1120 0.7 E E 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. 't i'
l 5-20 Rev. 21 07-01-89
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_ . TABLE Si6 4 4i %- < >
SECTOR AND DIRECTION DESIGNATION r0R. RADIOLOGICAL.
ENVIRONMENTAL NONITORING; SAMPLE LOCATION MAP.-
d
];
m.
-DEGREES TRUE NORTH: . .
'FROM SONGS'2 AND 3 MID-POINT NOMENCLATURE J' . Sector ' Center Sector 22.5' p.
Limit' ' ling Jimit 1 Sector *- Direction
-348.75 0 & 360
- 11.25- A -N
- 11.25 22.5 33;75 B. .NNE
<!: 33 ~. 75 - 45.0 56.25 C NE-56.25 67.5 .78.75 ~ D 'ENE 4
78.75 -90.0. 101.25 E E-
'101.25. 112.0 123.75 F ESE 123.75' 135.0- 146.25 G SE y-146.25 157.0 168.75 H SSE' 168.75 180.0 191.25- -J. S
'191.25 202.5 .213.75 K SSW 213.75 225.0 236.25 L SW 236.25- 247.5 258.75 M WSW 258.75 270.0 281.15 N W L ,
281.25 292.5 303.75 P WNW 303.75 315.0 326.25 Q NW 326.25 337.5 348.75 R NNW L
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Distance (miles) and Direction (sector) are measured relative to L Units 2 and 3 midpoint. Direction is determined from degrees true North.
L 3103c. man l~ ' 5-21 Rev. 21 07-01-89 l
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w 1 J;0 6 ADMINISTRATIVE 6'.1i: DEFINITIONS '
IThe'definedte:1ns 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 CALIBRATION' a
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 CALIBRATION shall encompass the entire channel, including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping.or total- channel steps such that the entire channel is calibrated CHANNEL CHECK 6.1.3 A' CHANNEL 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 senscr to verify OPERABILITY, including alarm and/or trip functions.
l- c. Digital computer channels - the exercising of the digital computer hardware using diagnostic programs a:d the injection of simulated process data into tha channel to verify OPERABILITY.
6-1 Rev. 21 07-01-89
6.0 ADMINISTRATIVE (Continued)
DOSE E0VIVALENT I-131 6.1.5 DOSE EQUIVALENT I-131 shall be concentration of I-131 (microcuries/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131,.
1-132,1-133,1-134, and I-135 actually present. -The-thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844,
" Calculation of Distance Factors for Power and Test Reactor Sites."
FRE0VENCY NOTATION 6.1.6 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 6.2. ,
GASE0US RADWASTE TREATMENT SYSTEM i
6.1.7 A GASEOUS RADWASTE TREATMENT SYSTEM is any system dosigned and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
OPERABLE - OPERABILITY 6.1.8 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).
PURGE - PURGING 6.1.9 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 nanner that replacement air or gas is required to purify the confinement.
VENTING 6.1.10 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, l 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.
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K 76'.0/ ADMINISTRATIVE'(Contiaued))
a y . SOLIDIFICATION.
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- . T6.1.11 SOLIDIFICATION: shall' be the conversion 'of radioactive
. wastes from liquid systems to a' homogeneous (uniformly P . distributed), . monolithic, immobilized solid with definite.;
hi . volume and shape, bounded by a stable. surface of distinct outline on all sides.(free-standing)'.
SOURCE CHECK- ,
6.1.12 A SOURCE CHECK shall be the qualitative: assessment of
' channel response when the. channel sensor is exposed'to a P, '
s radioactive source.
e
- THERMAL POWER 6.1.13 THERMAL POWER shall be the total' reactor core' heat transfer rate to' the reactor coolant.
6-3 Rev. 21 07-01-89 l
_ _ _ _ _ _ _ _ _ _ _ _ l
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- OP R'ATIONAL' MODES h 3 ,
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. .. ? REACTIVITY %'0F RATED :
AVERAGE COOLANT =
OPERATION MODE- ' CONDITION.!K THERMAL POWER
- TEMPERATURE eff-a
. , ~. . . .
.g 11.JPOWER OPERATION- 1 0.99 -> 5%= ;2 350*F:
n L2. STARTUP 2: 0.991 -s ' 5% L J2 350*F
, j-l ll } 3. HOT STANDBY- ( 0.99-
.0- '2:350*F.
~
I. ' 4'.' HOT-SHUTDOWN < 0;99 0 350'F> Tavg>200*Fl 1 200'F; 5.. COLD SHUTDOWN. < 0.99.- O.
- 6. REFUELING ** _ $ 0.95_ . 0' i-
'1-:140'F t
- 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 Rev. 21 07-01-89
. . _ _ . _ .__..m. ..m_ _ _ -
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TABLE 6-2
' FRE00ENCY NOTATION:
v.3 Pf. '
. NOTATION- FRE00ENCY' S- :At least once'per-12 hours.
r-Atleast'onc'e;per24 hours.
D W At:least once-per,7 days l
M LAt least once per 31 days 1 Q At'least~once per 92 days l> SA 'At least once per 184 days R At least once per 18 months LS/U Prior'to'each' reactor startup
.P Completed: p~rior to each' release -
N.A. .Not applicable Refueling Not to exceed 24 months l
Interval 1 -
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6-5 Rev. 21 07-01-89 j
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/6.2 -ADMINISTRATIVE CONTROLS <
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a y -SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE-REPORT *-
L-
- h. 6.2.1' Routine radioactive effluent relea'se reports covering the operation of the unit"during the previous 6 months of-L operation.shall .be submitted within 60 days after January 1
- and July- 1 of each year.- The period of the first report.
}-l shall begin with the-date of initial criticality.
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6.2.2 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released' from the unit as.
outlined in Regulatory Guide 1.21, ' Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of-Radioactive Materials in Liquid and' Gaseous Effluerts .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 I each year shall include an annual summary 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 stability.
This same report shall include an assessment of the radiation doses due to 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 eff,luents 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 tne 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 (ODCM).
6-6 Rev. 21 07-01-89 )
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6.2 . ADMINISTRATIVE CONTROLS (Coatinued) i .
. The radioactive ef"luent release report to be-submitted 60'
" days after January 1~ of each year shall- also include,an W assessment of radittion doses to the.likely most exposed z, . member of the public.from reactor; releases and other nearby.
uranium fuel cycle. sources;(including doses from primary effluent pathways and direct radiation) for. the previous 12
,. consecutive months to s N w conformance with 40 CFR_190,.
Environmental RadiationGrotection Standards for Nuclear
' Power Operation. - Acceptable methods- for calculating the dose contribution from liquid and gaseous effluents are .
givon in. regulatory Guide 1.109 .Rev.:-l.
The radioactive' effluents r'elease shall: include the
-following information for each type of solid waste--shippedi offsite during the report period:
- a. Container volume,
- b. Total curie quantity (specify whether determined by measurement or estimate)',
- c. Prir.cipal radionuclides (specify whether-determined by measurement or estimate),
- d. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms),
- e. Type of container (e.g.,,LSA, Type A, Type B, large Quantity), and
~
- f. Solidification (e.g., cement, urea formaldehyde).
The radioactive effluent release reports shall include l
unplanned releases from the site to unrestricted areas of I- radioactive materials in gaseous and liquid effluents on a i.
quarterly basis.
The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.
l L
- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common 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 Rev. 21 07-01-89 l
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.6.3: ' MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS-(Liqdid, & Gaseous)-
h.,' Licensee 1 initiated major changes' to the radioactive' waste systems (liquid &
gaseous).:
L n
- s. 1 1. -- Shall be. reported to the. Commission in th'e Monthly Operating Report for
- the period in whit.h the evaluation was performed pursuant to 6.5.2.
The discussion of. each change shall;.contain:
A summary of the evaluation that led to the determination that.the
~
a.
change could.be made in accordance with 10 CFR 50.59;-
- b. Sufficient detailed information to totally support the reason for
- the change without benefit of additional, or supplemental information; l
- c. A detailed' description of the equipment, components and processes.
involved and the interfaces with other plant systems:
- d. An evaluation of the chr7ge which shows 'the predicted' releases of radioactive materials 'in liquid and gaseous e.~fluents 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 6.5.2..
- 2. Shall become effective upon review and acceptance pursuant to 6.5.2.
6-8 Rev. 21 07-01-89
r 6.4 BASES LIOUID EFFLUENTS ,
i
~
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 assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A design ob.iectives of Appendix I, 10 CFR 50, to an individual, and (2) the limits of 10 CFR 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based uptn the 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.
R0]if 0 (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 I,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 dose calcu-lations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix ! 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 calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Complier.ce with 10 CFR Part 50, Appendix I,"
Revision 1, October 1977 and Regulatory Guide 1.113,
" Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix 1," 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 Rev. 21 07-01-89
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t 1 6.4 BASES (Continued) l w L10VID WASTE TREATMENT'(1.3)-
n 1' l 1 6.4.3 - The OPERABILITY of the liquid radwaste treatment system jf ensures that this system will'be available for une whenever liquid effluents require treatment prior to release to the ll, '
l environment. The requirement that the appropriate portions I
of this system be used when specified provides assurance <
that the releases of radioactive materials in liquid 4 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 obse ctive given in Section-ll.D of Appendix ! to 10 CFR Pa.-t 50. The specified limits governing the use of appropriate portions of the 14 quid radwaste treatment system were specified as a su; table fraction of the dose design-objectives set forth in Section II.A of Appendix I, u 10 CFR Part 50, for liquid effluents.
GASEOUS EFFtVENTS i DOSE 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 the annual dose limits l of 10 CF'l Part 20 for unrestricted areas. The annual dose L limits are the doses associated with the concentrations of l 10 CFR Part 20, Appendix B, Table II, Column 1. These l 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-I . . 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 beundary, the occupancy of the individual will be sufficiently low to compensate for ar.y increase in the l atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma 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 to 1500 mrem / 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.
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~
e ' 6. 4. 5 ' This< specification is-provided to implement the 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 I.~ 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 low 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.
' calculational procedures based on models and data such that L
C the actual exposure of an individual through appropriate 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 with the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of- Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," 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. The ODCM equations provided for determining the air doses at the site boundary are based upon~the historical average atmospheric conditions.
DOSE - RADIO 10 DINES. RADI0 ACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM (2.3) 6.4.6 This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condi-tions for Operation are the guides set forth in Section II.C of Appendix I. 4 The ACTION state-ments 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 materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Require-ments 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 00CM calculational methods 6-11 Rev. 21 L 07-01-89 b____--___---_____-------____---_-------._---- _ - - - - - - - _ _ - - _ _ - - - - . - - - - - . - - - _ _ _ - . - _ . - - - - - . - - - - - - - -
m.
(
6.4L BASES '(Continued)'
bk@
,M z:
- for calculating the' doses due
- to the actual' release ratesL l' - of~thel subject materials.are, consistent with the
. methodology provided in- Regulatory Guide 1.109, .
- " Calculation.of Annual' Doses to lian from Routine ~ Releases o -'of Reactor Effluents for- the' Purpose of Evaluating .
N Compliance with.10 CFR_Part.50, Appendix I," Revision 1,.
. 0ctober.1977.and Regulatory Guide 1.111,.'" Methods'for- -
4 '
Estimating Atmospheric Transport'and. Dispersion of. Gaseous' Effluents. in Routine Releases ~ from Light-Water-Cooled '
Reactors," Revision 1, July 1977. :These equations-also providefor determining the. actual ' doses: based upon .the '
historical average atmospheric conditions. The' release rate specifications for;radiciodines, radioactive
. materials:in particulate. form and tritium are dependent on i the-existing. radionuclides pathways to man,;in the unrestricted area. The pathways which were examined in the-development of these calculat;ons were: 1)J individual.
. inhalation of airborne. radionuclides, 2)LdeposItion~ of.
radionuclides onto green. leafy vegetation.with subsequent-consumption by man, 3) deposition onto grassy areas 1where' milk animals. and meat producing. animals graze'with.
- consumption of the milk and meat by man, andL4) deposition.
on the grcund with subsequent exposure of. man.
GASE0US RADWASTE~ TREATMENT-(2.4)
. 6.4.7 The OPERABILITY of.the GASE0US RADWASTE'TRFATMENT.
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,'rovides p reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."
l This specification implements the requirements of l
10 CFR Part 50.36a, General Design Criterion 60' of Appendix A to 10 CFR Part 50, and the design '
objectives given in Section II.D 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 H design objectives set forth in Section II.B and u L II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
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> 6.4 BASES _(Continued);
TOTAL DOSE (2.5)l
,3; n' .6.4.8 This specification is'provided to meet the dose limitations of_40 CFR 190. The specification requires-the preparation and submittal of a Specici . Report whenever the calculated doses from.
plant. radioactive effluents exceed twiceLthe design objective doses of Appendix;I. For sites containing.up to 4 reactors, it is highly'_
unlikely that the resultanttdose to a member of the public will exceed the dose limits of 40 CFR
~
190 if the individual reactors remain within thei
- reporting requirement level. The Special Report' o 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 Report, it may be assumed th t' the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nulear fuel cycle facilities at the same site or' 4 thin a radius of 5 miles must be considered.-
If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance in accordance with 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.
RADI0 ACTIVE LIOUID EFFLUENT INSTRUMENTATION-(4.1) 6.4.9 The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents'during actual or potential releases of liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.
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.
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L 6.4 BASES (Continu:d)
RADIOACTIVE GASEOUS EFFLUENT INSTRUMENTATION (4.2) 6.4.10 The radioactive gaseous efflutnt 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 will occur prior to exceeding the limits of 10 CFR Part 20.
This instrumentation also includes provisions for monitoring and controlling the concentrations of ,
potentially explosive gas mixtures in the waste I gas holdup system. The OPERABILITY and use of this instrumentation is consistent with the i requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
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