ML20090M244
| ML20090M244 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/28/1992 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13309A977 | List: |
| References | |
| PROC-920228, NUDOCS 9203240102 | |
| Download: ML20090M244 (187) | |
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ATTACHMENT A ODCM, Revision 25 9203240102 920313 FDR ADOCK 05000361 p PDR C
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l february 28, 1992 FEB 2 81992 Al HL1 COr i
SUBJECT:
Uti!TS 2/3 0FFSITE DOSE CAttVLATION MANUAL Revision 25 Enclosed is Revision 25 to the Units 2/3 Offsite Dose Calculation Manual (ODCM). This revision added steam generntor blowdown and the full flow Condensate Polisher Demineralizer (FFCPD) holdup tank (HUT) as liquid release points and revised the Turbine Plant Sump discharge flowrates to reflect the replacement of the pump per DCP 2 6747. In recognition of unequal mixing in the plant vent stac(, minimum instrument requirements for noble gases were revisedtorequirebothradiationmonitorsontheunitspecificbranches whenever the radiation monitor on the common plenum is out of service.
Additionally, radiation monitor calibration constants were updated to reflect recent surveillances and there was one editorial cht.nge for typographical errors. This revision also encompasses the update of tables used in liquid and gaseous dose calculations that resulted specifically from the 1991 Land Use Census. tiene of the changes result in any modifications to either the plant configuration or operation. As such, there is no impact on the accuracy or reliability of methods for determining effluent dose or setpoint values.
A complete list of the changes is attached to this letter and safety reviews have been performed for the following changes:
o batch release of steam generator bludown via 2( )RT 6759 or 2(3)RT-6753 respectively O o o
batch release of the FFCPD HUT via 2(3)RT-7821 instrument requirements for the plant vent stack No positive findings were found in any of the safety evaluations.
No safety evaluations were performed for updating radiation monitor calibration constants or implementing changes frem the 1991 Land Use Census.
Similarly, the increase in the discharge rate f rom the turbine plant surrp will be factored into the existing setpoint equation. These changes reflect results from routine sarvet11ances and as such do not constitute a modification in methodology for determining activity released from the Site and subsequent dose to a member of the public.
Per NRC Generic letter 89-01, no safety review was required or performed for the correction of typograohical errors.
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The following is a complete list of the changes: '
Indicates typogranHeal, sequential sectional and page numbering, and format changes :
GEH' Added 5023 0DCH above rev # in lower right corner of all pages to facilitate incorporation into SDMS i GEN
- The Food and Ground (GF) pathway values for child, teen, and adult (infant is zero) were increased by a factor of (1/0.7) or 437. in Sector P, 0.4 mile (page ?. 38), Sector Q, 0.7 mile (page 2-43), and Sector Q, 1.1 mile (page 2 44). The increase is due to the fact that a shielding factor of 0.7 used in the Regulatory Guide 1.109, equation C 2, for calculation of ground exposure is not applicable to beach use since no structural shielding is arovided for beach users. The increase in GF values does not affect tie controlling location factors but it does increase the dose parameters columns for," Food and Ground" for the mentioned uses. Because, there no food pathway contribution for the beach uses, then the increase in the'" Food and Ground" column will be only due to an increase in the ground GF factor (Food =0) and is expected to be 43?, higher than the 1990 values. The modification to the GF ,
factor was made per recommendation of Dr.-James Brown, a consultant to the Station's Effluent Engineering group.
- 1-2 Added SG Blowdown and FFCPD HUT as liquid batch release points 1-15 Added discharge value for FFCPD Holdup Tank 1-23 Added-separate discharge flowrate value for Unit 2 per DCP 2 6747 1-26 Table 1 3, updated liquid calibrati;n constants for 2RT-6753, 2RT 6759, and 3RT-6753 1-28' Table 1 4, in notes, changed NUREG 0172 to NUREG-0472 1-29' same as pg 1 28 -
1-30 Provided regulatory references for representative sampling 2-35' Table 2 4, deleted note ~'l.17E+3 = 1.17 Y 103" 2 37 Table 2 6, added controlling sector location to table 2-38* Surf Beach Life Guard occupancy factor increased from 0.0685 to 0.0716 (Sector P, 0.4 mile).
(9 Point Loran Military housing was deleted. It was not used for military housing-in 1991 due to cutback in budget (Sector P, 2.7 miles).
2-43 Surf Beach Guard Shack occupancy factor increased from 0.0571 to 0.1712 (Sector Q,_0.7 mile). Also, the " guard shack" for infant, child, and teen uses was deleted and beach use parameters were added to these age O groups .
n+ w + n m r---er - r - v ,,v em. . - - - - . ~ - - . - ~ ~ - > - <a ~ -m-- ~ >>c., , - - - , - ~~m,-, ,.-- >,-, e
2 44 Enlisted Beach campground (a new use) was added with an occupancy factor l O, of 0.0104 (Sector Q, 1.1 mile).
2 49 San Clemente Ranch Administrative Office occupancy factor decreased from 0.5833 to 0.3425 (Sector R. 2.6 miles).
2 51' Child Food and Ground pathway Cs-137 corrected: 2.2Et10 changed to 2.3E+10 2-52 San Clemente Ranch Packing With P,esident occupancy factor decreased from 0.5833 to 0.3425 (Sector R, 2.6 miles).
2 55' Adult Food and Ground pathway Co 60 corrected: 2.3E+10 changed to 2.2E+10 2 58' Adult Inhalation Cs 137 corrected: 3.4E+2 changed to 3.4E+3 2 64 Sheep Heat D/Q changed from 5.3E 8 to 6.lE-8. This does not affect the dose parameters which do not contain the D/Q factor (Sector C, 0.2 mile). [ Adult Inhalation Ct-136 corrected: 8.lE+3changedto8.1E+2')
2-72 San Onofre State Park Guard Shack occupancy factor increased from 0.0571 to 0.1712 (Sector F, 0.8 mile). The X/Q changed from 8.1E 7 to 8.6E 7 and 0/Q changed from 7.lE-9 to 7.5E 9 in that same sector. The " guard shack" description for infant, child, and teen was deleted. GF and ZIN are zero because the uses for San Onofre State Park are listed in Sector G (Campground, the closest use).
2 73 (old 2-73) Beach concession use was deleted due to the closure of the stand (Sector F, 0.9 mile).
2 76 San Onofre Beach Campground occupancy factor for maintenance workers increased to 0.2283 (Sector G, 0.8 mile).
2-80' Reformatted definitions
?-81' Reformatted definitions 2 82' Reformutted definitions 4-2' Table 4-1, to 1.c, added Auxiliary Building Sump, Component Cooling Water Sumps, and Storage Tank Area Sumps 4-7 Modified noble gas monitoring requirement for ' plant vent stack to require both RT-7865s when 2/3RT-7808 is inoperable 4-8 Modified footnote (2) to require process flow verification on the plant vent stack if either RT7865 is not available. Added footnote (3).
5-17 Removed TLD 99, Transit Dose, at completion of comparative study on Lif and CaSO TLDs 6 4' Added definition for Ventilation Exhaust Treatment System
OFFSITE DOSE CALCULATION MANUAL NOCLEAR ORGANIZATION UNITS 2 AND 3 O
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. ODCM TABLE OF CONTENTS I EMt ;
LIST Of FIGURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . iv i LIST OF TABLES . . . . . . . . . . . . . . . . . . . . . . . , . . . v vi f INTRODUCT10N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vii l
l 1.0 LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . 11 thru l 30 1.1 Concentration . . . . . . . . . . . . . . . . . . . . . . . 11 !
1.1.ll Specification . . . . . . . .. . . . . . . . . . . . .11 ;
1.1.1.1, 1.1.1.2 Surveillances . . . . . . . . . . . . . . .11 I
l'.2. Dose . .......................... 1$ >
1.2.1 Specification . . . . . . . . . . . . . . . . . . . 15 1.2.1.1 Surveillance ................... 15 1.3 Liquid Waste freatment .................. 16 1.3.1- Specification . . . . . . . . . . . . . . . . . . . 16 l 1.3.1.1, 1.3.1.2, 1.3.1.3 Surveillances . . . . . . . . . . 16 1.4 Liquid Ef fluent Fonitor Setpoints . . . . . . . . . . . . . 18 1.4.1 Batch '.elease Setpoint Determination . . . . . . . . 1 10 1.4.2 Contit,uous Release Setpoint Determination . . . . . 1-16 ,
1.5 Dose Calculations for liquid Effluents . . . . . - . . . . . 1 27
. 1.6 Representative Sampling . . . . . . . . . . . . . . ! . . . . 1 30 2.0 GASEOUS EFFLUENTS . ... . . . . . . . .:. . . . . . . . . . . . 2-1 thru r 2 82 2.1 Dose Rate . . . . . ... . . . . . . . ,-. . , . . . . . . . 21 i 2.1.1 Specification . . . . , . . . . . . . . . . . . . . 2 1-2.1.1.1, 2.1.1.2 Surveillances . . . - . . . . . .- . . - . . . .21 2.2 Do s e Nobl e Ga s . . . . . . . . - . . . . . . . . . . . . . . 25 2.2,1 Specification ....................25 -
2.2.1,1 - Surveill ance ............'...... 25
- 2.3 Dose Radiciodines, Radioactive Materials in Particulate .
Form and Tritium . . ................... 26 !
2.3.1 Specification ..........-.. ,,,.-.. 26 2,3.1.1 Surveillance . . . . . . . . . . . . . . . . . . . 2-6 5023 00CM Revision 22 ,
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b ODCM TABLE OF CDNTENTS (Continued) fJL41 2.4 Gaseous Radwaste Treatment ................ 27 2.4.1 Specification . . . . . . . . . . . . . . . . . . . . 2-7 2.4.1.1 Surveillance . . . . . . . . . . . . . . . . . . . 2-7 2.4.1.2, 2.4.1.3 Surveillances . . . . . . . . . . . . . 2-8 2.5 Total Dose .... . . . . . . . . . . . . . . . . . . . 2-9 2.5.1 Specification . . . . . . . . . . . . . . . . . . . . 29 2.5.1.1 Surveillance ........... ....... 29 2.6 Gaseous Effluent Monitor Setpoints ............211 2.6.1 Plant Stack . . . . . . . . . . . . . . . . . . . . 2 11 2.6.2 Condenser Evacuation System . . . . . . . . . . . . 2 15 2.6.3 Containment Purge . . . . . . . . . . . . . . . . . 2 18 2.6.4 Waste Gas Header . . . . . . . . . . . . . . . . . 2 21 2.7 Gaseous Effluent Dose Rate . . . . . . . . . . . . . . . . 2-26 2.7.1 Noble Gases . . . . . . . . . . . . . . . . . . . 2 26 2.7.2 Radiciocines and Particuhtes . . . . . . . . . . . 2 27 2.8 ' Gaseous Effluent Dose Cale.ulation . . . . . . . . . . . . . 2 29 G 2.8.1 Noble Cases . . . . . . . . . . . . . . . . . . . . 2 29
_ bl 2.8.1.1 Historical Meteorology . . . . . . . . . 2 29 2.8.1.2 Concurrent Meteorology .........230 2.8.2 Radiciodines and Particulates . . . . . . . . . . . 2 31 2.8.2.1 Historical Meteorology . . -, . . . . . . 2 31 2.8.2.2 Concurrent Meteorology . . . . . . . . . 2 33 2.9 Total Dose Calculations . . . . . . . . . . . . . . . . . . 2 80 2.9.1 Total Dose to Most likely Member of the Public . . . 2 80 2.9.1.1 Annual Total Organ Dose . . . . . . . . . 2 8J 2.9.1.2 Annual Total Whole Body Dose . . . . . . 2-81 2.9.1.3 Annual Total Thyroid Dose . . . . . . . . 2 82 3.0 PROJECTED DOSES t
3.1 Liquid Dose Projection .................. . I thru 31
'3.2 Gaseous Dose Projection . . . . . . . . . . . . . . . . . . 31 4.0 EQUIPMENT . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 1 thru j 4 16 4.1 Radioactive Liquid Effluent Monitoring Instrumentation . . .41 pQ 4.1.1 Specification . . . . . . . . . . . . . . . . . . . .
4.1.1.1, 4.1.1.2 Surveillances 4-1 l
......,,...... 41 5023 0DCM-Revision 25 11 02 28 92
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i ODCH TABLEOFCONTENTS(Continued)
Ek92 4.2 Radioactive Gaseous Effluent Monitoring Instrumentation . . 46 4.2.1 Specification . . . . . . . . . . . . . . . . . . . . 46 4.2.1.1 Surveillance ................... 46 4.3 Operability of Radioactive Waste Equipment . . . . . . . . 4 13 i l
5.0 Radiological Environmental Monitoring . . . . . . . . . . . . . 5 1 t h ru ;
5 25 5.1 Monitoring Program .,,................. 51 5.1.1 Specification . . .... ........... 51 :
5.1,1,1 Surveillance . . . . . . . . . . . . . . . . . . . 52 5.2 Land Use Census . . . . . . . . . . . . . . . . . . . . . . 5 11 5.2.1 Specification . . . . . . . . . . . . . . . . . . 5 11 5.2.1.1 Surveillance . . . . . . . . . . . . . . . . . . . 5 11 5.3 Interlaboratory Comparison Program . ... . . . . . . . . . 5 12 5.3.1 Specification . . . . . . . . . . . . . . . . . . 5 12 5.3.1.1 Surve ill ance . . . . . . . . . . . . . . . . . . . 5 12 1
5.4 Annual Radiological Environmental Operating Report . . . . 5 13 -
5.5 Sample Locations . . . . . . . . . . . . . . . . . . . . . 5 14 6.0 Administrative . . . . . . . . . . . . . . . . . . . . . . . . . 6 1 thru I 6 16 .
6.1 Definitions . . . . . . . . . . . . . ._.. . . . . . . . . . 61 6.2 Adrinistrative Control s . .' . . . . . . . . . . . . . . . . 67 6.3 najor Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) ................... 69 6.4 Bases . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 10 i
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i ODCH i LIST OF FIGURES O
V Title Pace licure l2 Site Boundary for Liquid Effluents . . . . . . . . . . . . . . . . 7 22 Site Boundary for Gaseous Effluents ............... 2 10 45 SONGS 2 all 3 Radioactive Liquid Waste Treatment Systems . . . . . 4 14 46 SONGS 2 and 3 Radioactive Geseous Waste Treatment Systems . . . . 4 15 47 Solid Waste Handling . . . . . . . . . . . . . . . . . . . . . . . 4-16 51 Radiological Environmental Monitorie- Sample Locations . . . . . . 5 23 i
O O S023 0DCM Revision 22 iv 08-02 90 t
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4 ODCM LIST OF TABLES i
, Dole Title Pats 9
11 Radioactive Liquid Waste Sampling and Analysis Program . . 1-2 1-3 Liquid Effluent Radiation Monitors Calibration Constants . . . . . . . . . . . . . . . . . . 1 26 1-4 Dose Comitment Factors A,, . . . , . . . . . . . . . . . 1 28 21 Radioactive Gaseous Waste Sampling and Analysis Program . .22 23 Gaseous Effluent hediMion Monitor Calibration Constant: . . . . . . . . . . . . . . . . . . 2 25 2-4 Dose Factors for Noble Gas and Daughters . . . . . . . . . 2 35 2-5 Dose' Parameters Pu . . . . . . . . . . . . . . . . . . . 2-36 26 Controlling Location Factors . . . . . . . . . . . . . . . 2 37
'2-7 Dose Parameters k, for Sector P . . . . . . . . . . . . . 2-38 2-8 Dose Parameters R, for Sector Q . . . . . . . . . . . . 2-40 <
.2-9 Dose Pararacters Ri for Sector R .......... . . . 2 50 2-10 Dose Parameters R i for Sector A . . . . . . . . . . . . . 2 55 2-11 Dose Parameters iR for tector B . . . . . . . . . . . . . 2 58 2-12 Dose Parameters R i for Sector C . . . . . . . . . . . . . 2-61 2-13 Dose Parameters R i for Sector D . . . . . . , . . . . . 2-66 2 14 Dose Parameters R, for Sector E .............269 2 15 base Parameters Ri _ for Sector F , . . . . . . . . . . . . 2-72 2-16 Dose Parameters R, for Sector G . . . . . . . . . . . . . 2-76 4-1 Radioactive Liquid Effluent Monitoring Instrumentation . . 4-2 4-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements . . . . . . . . . . . . . . . . 4-4 43 Radioactive Gaseous Effluent Monitoring Instrumentation . .47 4-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements , . . . . . . . . . . . . . . . 4-10 (v"1 S023-0DCM Revision 25 v 02-28-92
ODCM LIST OF' TABLES (Cont'inued)
Ig1e ,7it1e Paae 5 1_ Radiological Environmental Monitoring Program . . . . . . 5-3 5-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples .................. 57 53 Maximum Values for tne Lower Limits of Detection (LLO) . . 59 5-4 Radiologiul Environmental Monitoring Sample Locations . . 5-15 5-5 PIC Radiological Environmental Monitoring Locations . . . 5-21 5-6 Sector and Direction Designation for Radiological Environmental Monitoring Sample Location Map . . . . . . . 5-22 6-1 Operational Moder . . . . . . . . . . . . . . . . . . . . 6-5 6-2 Frequency Notation . . . . . . . . . . . . . . . . . . . . 66 q()
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INTRODUCTION D The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the V
RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (NUREG 0472). The ODCM enumera.tes dose and concentration specifications, instrunent requirements, as well as describes the method 01ogy and parameters to be used in the calculation of offsite doses from radioactive liquid and airborne effluents, in order to raet release limits, it additionally provides calculations for liquid and gaseous effluert monitoring instrumentation alarm / trip setpoints. The environmental section contains a list of the sample locations for the radicia * *' environmental monitoring program. -
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maintained at the Site for use as a document of Specifications a -
athodologies and calculations to be used in implementing the Sp, .s . Changes in the calculational methods or parameters wil'l be incorporated into the ODCM in order to assure that the ODCH represents current methodology.
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S023-0DCM Revision 21 vii D2-IS-90
1.0- LIQUID EFFLUENTS 1.1 C.QRQJETRATION M }ffMFICAT10N 1.1.1 The concentration of radioactive material released from the site (see Figure 1-2) shall be limited to the :oncentrations specified in 10 CFR Part 20. Appendix B, Table II, column 2 for radionuclides other than dissolved or entrained noble gaset.
For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10" microcuries/ml total activity.
APPLICABILITY: At all times ACTION
- a. With the concentration of radioactive material released from the site exceeding the above limits, immediately restore the concentration to within the above limits.
SURVEILLANCE RE0VIREMENTS
.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 1-1.
.2 The results of the radioactivity analyses shall be used in accordarce with the methodology and parameters in Section 1.4 to assure that the concentrations at the point of release are
,g maintained within the limits of Specification 1.1.1.
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S023-0DCM l-1 Revision 22 08-02-90
, 4 JABLE l-1 1 RADIOACTIVE L10010 WASTE SAMPLING AND ANALYSIS PROGRRj v
Lower Limit of Detection Minimum Liquid Release Sampling Analysis Type of Activity (LLD)
Type frequency Frequency Analysis (pCi/ml)'
A. Batch Waste P P Principa) Gamma 5x10" Release' Each Batch Each Batch Emitters i 1-131 l x 10
P M Dissolved and lx10 4 One Batch /M Entrained Gases (Gamma emitters)
P M H-3 l x 10
Each Batch' ' Composite
- _ Gross A1,.'ia lx10" P Q Sr 89, Sr-90 5x10
Each Batch Composite
- Fe-55 l x 10
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E BATCH RELEASE POINTS: Primary Plant Makeup Storage Tanks, Radwaste Primary Tanks, Radwaste Secondary Tanks, Miscellaneous Waste Condensate Monitor Tanks, Blowdown Processing Sump, FFCPD sumps (high conductivity, low conductivity) and g holdup tank, Component Cooling Water Sump, Storage Tank Area Sump, S/G Blowdown.
B. Continuous D- W Principa) Gamma 5x10" Releases', Grab Sample Composite
- Emitters 1-131 l x 10
M M Dissolved and lx10
Grab Sample Entrained Gases (Gama emitters)
D M H-3 1x 10
Grab Sample Composite
- d Gross Alpha 1x10 0 Q Sr 89. Sr-90 5x10'8 Grab Sample Composite" Fe-55 l x 10
E CONTINUOUS RELEASE POIN15: Turbine Plant Sump *, Blowdown Processing Sump,"
S/G Blowdown Bypass Line'", S/G Blowdown, Salt Water Discharge from CCW Heat O
V Exchanger, Auxiliary Building Sump.'
S023-00CM l-2 Revision 25 02-28-92
TABLE 1 1 (Continued)
TABLE NOTATION V a, The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particolar measurement system (which may include radiochemical separation):
4,66 s*
LLD =
E*V 2.22 x 106 Y + exp (- ut) where:
LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),
s, is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiency (as counts per transformation),
V is the sample size (in units of mass or volume),
2.22 x 10' is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
1 is the radioactive decay constant for the particular radionuclide, and At is the elapsed time betwaen midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
The value of s, 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 radionuclide determined by gamma ray spectrometry, the background should include the typical contributions of other radionuclides normally present in the: samples. Typical values of E, V, Y and At should be used in the calculation.
It should be recognized that the LLD is defined as an a priori limit representing the capability of the measurement system and(before not as athe fact) costeriori (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).
l (2) Currie, L. A., " Limits for Qualitative Detection and-Quantitative Determination - Ap31tcation to Radiochemistry" Anal. Chem, 40, 586-93 (1968).
(3) Hartwell, J. K., "Atretion Limits for Radioisotopic Counting Techniques,"
Atlantic Richfield Hanford Company Report ARH-2537 (June 22,1972).
S023-0DCM 1-3 Revision 21 02 15 90
TABLE 1-1 (Cont inued).
IABLE NOTATION
(._/ b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the
-method of sampling employed results in a specimen which is representative of.
the liquids released.
- c. To be representative of the q'uantities and concentrations 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 t. method described in the ODCM, to assure representative sampling,
- e. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release,
- f. The principal gama emitters for which the LLO specification rpplies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-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 measurable and identifiable, together with the above nuclides, shall also be identified and reported,
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- Administrative controls shall ensure that only one continuous release point is discharging through a discharge path at any given time. The normal continuous release point via 2(3)RT-7821 is the turbine plant sump.
The first sump volume of BPS ion exchanger regeneration process shall be treated as a batch release.
Sampling of this flow is not required if at least once per 31 days blowdown bypass isolation valve (S2130lMU618 for Steam Generator 2E088, S21301MU519 for Steam Generator 2E089, S31301MU618 for Steam Generator 3E088 and 531301HU619 for Steam Generator 3E089) is verified locked shut.
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1-4 Revision 24 08-31-91 l
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-1.0l LIQUID EFFLUENTS (Continued)
.~ - 1.2. QQ$1 p
V SPECIFICATION 11.2.1- The dose or dose commitment to an individual from radioactive
. materials:in: liquid effluents released, from each reactor unit, ,
from the site (see Figure 12) shall be limited:
a.' During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ,.and
- b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ. .
APPLICABILITY: At all times ACTION:- .
- a. With calculated dose from the release of radioactive materiais in liquid effluents exceeding any of the above limits, in lieu
- of any other report required by Technical Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the lin.it(s) and defines ,
the corrective actions taken to reduce the releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 1.2.1.
SURVEILLANCE REQUIREMENTS 1 Qpse Calculation. Cumulative dose contributions from liquid effluents shall be determined in accordance with Section 1.5 at least once per 31 days.
4
- O S023-00CM l-5 Revision 21 02-15-90
.w v . - , . .
l.0 LIQUID EFFLUENTS (Continued) 1.3 LIOVID WASTE TREATMEtil SPECIFl(311Q]f 1.3.1 The liquid radwaste treatment system shall be OPERABLE. The appropriate portions of the system shall be used to reduce the ra_dioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site (see Figure 1-2) when averaged over 31 days, wou 0.06 mrem to the total body or 0.2 mrem to any organ.ld exceed APPLICABILITY: At all times ACTION:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the Comission within 30 days pursuant to Technical Specification 6.9.2 a Special Report which includes the following information:
- 1. Explanation of why liquid ridwaste was being discharged without treatment, identification of the inoperable equipment or subsystems and the reason for inoperability,
- 2. Action (s) taken to restore the inoperable equipment to p OPERABLE status, and
- 3. Sumary description of action (s) taken to prevent a recurrence.
SURVEILLANCE RE0VIREMENTS
.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with Section 3.1.
.2 During plant operation (Mode 1-4), the appropriate portions of the liquid radr!aste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 15-minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.
.3 In plant shut-down (Mode 5, 6) the appropriate portions of the liquid radwaste treatment system shall be demonstrated OPERABLE by operating the liquid radwaste treatment system equipment for at least 15-minutes prior to processing liquids unless the appropriate liquid radwaste system has_been utilized to process radioactive liquid effluents during the previous 92 days.
Per reactor unit O
V S023-00CM l-6 Revision 22 08-02-90
6 4
un cutrat mc. tait
=t tatumt ifATCW v vets L 10
% O 00
^^ %
^
. N f- .
n -C'
\ '
l"C.!
- 54. .
+
_ _~ t. ,_
ss<
r j ,a r -
.,.,.n. :. \J m suu as so r
. ) ~
f.
Or N . g SITE BOUNDARY FOR LIOUID EFFLUENTS FIGURE 1-2
REFERENCE:
TECHNICAL SPECIFICATIONS, FIGURE 5.1-4
\ .
5023-0DCM l-7 Revision 21 02-15-90
1.0 LIQUID EFFLUENTS (Continued) 1.4 Liquid Effluent Monitor Methods of Sotpoint Calculation Liquid Radwaste Effluent t.ine Monitors provide alarm and automatic tehnination of release prior to exceeding the concentration limits specified in 10tfR20, Appendix B, Table 11, 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 'or liquid effluent monitors and flow rueasurement devices are set to assure that the following equaticn is satisfied:
C,R (l~l) s MPC,,,
74 where:
MPC,,, - effective effluent maximum concentration permissible limit (pC1/ml) at the release point to the unrestricted area for the radionuclide mixture being released, 3
(1-2)
N'p}
.E i =1 , MPCg l 50?3-0'DCM l8 Revision 21 02-15-90
4
-1.0. LIQUID EFFLUENTS. (Continued) i
- v. - 1.4 Liquid Effluent Monitor Methods of Setpoint Calculation (Continued) where: i F, - fractional concentration'of the i" radienuclide as obtained by
, sample analysis.
N = number ef' radionuclides identified in sample analysis.
MPC, = MPC of the 1" radionuclide (10CFR20, App B, Table 11, Column 2).
C, a setpoint, representative of a radionuclide concentration for the radiation monitor measuring the radioactivity in the waste effluent line prior to dilution and subsequent release, pCi/ml.
-R = : permissible waste effluent flow rate at the radiation monitor
-location, in volume per unit time in the same units as for F.
F = dilution water flow in volume per unit time. .The dilution water flow (F) is 185,000 gpm per circ pump (4 total) and 17,000 gpm per saltwater pump (2-total).
The design flowrate of each circulating water pum) is 205,000 gpm. The value used in'the determination of F ta(es into O- account factors such as frictional losses, pump-inefficiency,-
and tidal flow and provides reasonable assurance that the radioactive release concentration is not underestimated. '
5023-0DCM -
1-9 Revision 21 02 15 '
. - - - -. ., --r- w -- - < - >v-- .- y..-.-.4e, y
1.0 LIQUID E'fLUEKf5 (Continued) 1.4 Liquic Effluent Monitor Methods of Setpoint Calculation (Continued')
Administrative values are used-to reduce each setpoint to account for the potential activity in other releases. These administrative values shall be periodically reviewed based on actual release data (including, for example, any s:.bater discharge of the component cooling water heat exchanger) and revised as necessary.
1.4.1 Batch Release Setpoint Determination.
lne waste flow (R) and monitor setpoint (c) are set to meet the condition of equation (1-1) for the effective NPC (MPC,,,) limit.
The method by which this is accomplished is as follows:
STEP.1: The isotopic concentration for each batch tank (or sump) to be released is obtained from the som of the measured concentrations in the thnk (or sump) as determined by analysis.
( )
C = E, C + C, + C, + C, + C,,
where:
C - total concentration in each batch tank, pCi/mi I,C,, - sum of the measure concentrations for each radionuclide, i, in the gama spectrum, pCi/ml C ,, - Fe-55 concentration as determined in the previous quarterly composite sample, pCi/ml -
i O S023-0DCH 1 10 Revision 22 08-02-90
1.0 LIQUID EFFLUENTS (Continued) 1.4.1 Batch Release Setpoint Determination (Continued) g ,
M C, 6 gross alpha concentration determined in the previous monthly composite sample, pCi/ml C, - Sr-89 and Sr-90 concentrations as determined in the previous quarterly composite sample, pCi/mi C-s H 3 concentration as determined in the previous monthly composite sample, pCi/ml STEP 2: The effective MPC (MPC,n) for each batch tank (or sump) is determined using:
(1-4) 3 MPC'" *
' C,)C ' 'C/C' 'C/C' ' C/C' ' C,)C '
"' , MPC,, , MPC,, MPC s, MPC, MPC,,
the limiting concentrations of the appropriate MPC,,, MPC, racionuclide from 10CFR20, Appendix B, Table II, Column 2.
lq)
'w NOTE: For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 pCi/n1 total rctivity.
STEP 3: The radioactivity monitor setpoint C , pCi/ml, may now be specified based on the values of C,. Ii c,,, F MPC,n and R to provide compliance with the limits of 10CFR20, Appendix B, Table II, Column 2. The monitor setpoint, cpm,,is taken from the applicable calibration constants given in Table 1-3 to'correspohd to the calculated monitor concentration limit C 7, pCi/m).
/D d
5023-00CM 1-11 Revision 21 02-15-90
1.0 LIQUID EFFLUENTS (Continudd) 1.4.1 Batch Release Setpoint Determination (Continued) 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) ( C,,,)
C* s RC 33 R,C, R,C, MPC,,,3 MPC,,,3 MPC,,,,
where:
n - number of tanks to be-rele 5?d.
C,,, - effective gama isotopic concentration at the monitor for the tank combination to be released (equal to I,C,, for single tank releases),
i R (I,C,,), + R, {I,C,,), + , . + R, (I,C,,),
3 l
O
%J R3 + R, + . . . + R, l
l
- (Zi tyi)3, (I iC,,)r, etc. - total gama isotopic concentration of first l
I tank, second tank, etc. (pCi/ml).
- R2 , R,, etc. = effluent flow rate from first tank, second tank, i etc. Values of R for each tank are as follows
Radwaste Primary Tanks R - 140 gp# pump (x no. of pumps to be run)
Radwaste Secondary Tanks R - 140 gpm/ pump (x no of pumps to be run)
Primary Plant Me"up Tank R - 160 gp# pump (x no. of pumps te be run) l l Condensate Monitor Tanks R - 100 gpm/ pump (x no. of pumps to be run) l '
l l
l l
N 1 '
5023-0DCM l-12 Revision 21 02-15-90 i
w *A9 Sf wM
1.0 LIQUID EFFLUENTS (Continued)
( ) 1,4,1.1 RADWASTE DISCHARGE LINE MONITOR (2/3-7813) . (Continued)
NOTE: Since the values of R are much smaller than F, the tern (F + R) in equation (1 1) may be replaced by F.
MPC,,,3, MPC,,,,, etc. - values of MPC,,, from equation (1-4) for first tank, second tank, etc.
values of C, total concentration, from equation C , Cr, etc.
3 (1-3) for the first tank, second tank, etc., in pCi/ml.
RW 7 ,33 and SGu r SG es .ri SG u.s SGes.), B,, 8 , Tre Is are administrative 3
values used for simultaneous releases from the Radwaste Effluent discharge and any or all of the four Steam Generators as well as continuous discharges from the two Blowdown Processing Systems and the two Turbine Plant Sumps. The fractions RW ,337 and SGe.3, SGes.r> SGu 3
(]
V S G.,.3, B2 , B3 , T , T will 3 be assigned such that (RW .337 + SGu-r + SGes.:
+ SGm.3 + SG,,.3 + Br +3 B + T, + 3T ) s 1,0.
O S023-00CM l-13 Revision 11 02-15-90
_ _,--. -- - _.. _ ,_ _ _ : ~
l.0 i.! QUID EFFLUENTS (Continued) 1.4.1.1 RADWASTEDISCHhRGELINEMONITOR(2/3-7813)(Continued)
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 C, s C,,,, then no release is possible. To increase C.,
increase dilution flow F (by run,ning more circulating water pumps in the applicable discharge structure), and/or decrease the effluent flow rates R , Rr, etc., (by 3
throttling the combined flow rs measured on 2/3F1-7643, 2FIC-4055, 2FIC-4056, 3FIC 4055 or 3FIC 4056 as appropriate) and recalculate C,, using the new F, R and equation (1-5).
If there is no release associated with this 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.
O V .
S023-00CM l-14 Revision 21 02-15-90
1.0 LIQUID EFFLUENTS (Continued) 1.4.1.2 NEUTRALIZATION SUMP / FULL FLOW CONDENSATE POLISHER DEMINERALI7ER
(~'s (FFCPD) SUMP DISCHARGE LINE MONITOR (batch) (2RT-7817. 3RT-78171 b The value for C, or C , the concentration limit at the Unit 2 or 3 ,
Unit 3 detector, is determineo by using:
( B,) ( F ) E,C,,
C, 5 (R) (C/MPC,,,)
(')
(83 )(F)E,C,,
' C, s (R)(C/MPC,,,)
where:
C I,C,, , MPC,,, - values of C, I,C,, and MPC ,, as defined in STEPS 1)and2)fortheNeutralizationSump/FFCPD Sumps.
R = 500 gpm Neutralization Sump R - 500 gpm FFCPD High Conductivity Sump R - 600 gpm FFCPD Low Conductivity Sump R = 600 gpm FFCPD Holdup Tank b C2 - instantaneous concentration at the detector (2RT-7817)inpCi/cc C3 = instantaneous concentration at the detector (3RT-7817)-inpC1/cc B and B3 are administrative values used to account for simultaneous releases from both SONGS 2 and SONGS 3 neutralization sumps. The fractions B, and B3 (each normally set to 0.05) will be assigned such that (RWisu + SGar + SGo-r + SG 3 + SGa .3 + B + B3 + T, + T3 ) s 1.0.
O S023-0DCM 1-15 Revision 25 02-28-92
. -. -~ . - - . . .- .. - - - - . - . - - . . - . - . . - . - - . - . _ . -
-1.0 LIQUID EFFLUENTS (Continued) )
. . - l'. 4.1. 2 NEUTRAllIATION SUMP / FULL FLOW CONDENSATE p0L15HER DEMINERALIZER (FFCPD) SUMP DISCHARGE LINE MONITOR (batch) (2RT-7817. 3RT-78171
--0I (Continued)
NOTEi If C, or C s I ig 3 C , then no release is possible. To increase C, or C3 , increase dilution flow F (by. running more pumps), -
and/or decrease the effluent flow rate R. (by throttling the flow as' measured on 2F1-3722 and 3FI 3772), and recalculate C2 >
or C3 using the new F,'R and equation (1-7) or (18). ]
If there is no release associated with this monitor, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet assure an- alarm should an inadvertent release occur.
1.4.2 Continuous Release Setpoint Determination -
The waste flow (R) and monitor setpoint (C,) are set to meet the condition of equation (1-1) for the effective MPC (MPC,,,) limit. The method' by which this is accomplished is as follows:
STEP 1:. The Lisotopic concentration for the continucus releases are obtained for each releasesstream (steam generator blowdown, steam generator blowdown bypass, blowdown neutralization sump and turbine plant sump) from the sum-
'of the respective measured concentrations as determined by.
analysis:
C = I,Cg + C, + C, + C, + C,,
O-S023-00CM 1-16 Revision 22 08 02-90
" " ~ - d=*^'
~ - - ---- ---
b.-- -
y w pC_. . m6-w w w z m m . '
.1.0 LIQUID EFFLUEKTS (Continued)
- 1.4.2- Continuous Release Setpoint Determination (Continued) where:= .
C = total .oncentration (pCi/ml)
Zi tg = total gama activity associated with each radionuclide, i, in the weekly composite analysis for the release stream, pCi/mi C, = total measured gross alpha concentration determined from the previous monthly composite analysis for the-release stream,pCi/ml Cr, = total Fe 55 concentration as determined in the previous quarterly composite sample for the release stream, pCi/ml C.i
= total measured H 3 copeentration determined from the previous monthly composite analysis for the release ,
stream,pCi/mi C.
- total measured concentration of Sr-89 and Sr 90 as determined from the previous quarterly composite analysis for the release stream, pCi/ml STEP 2: The effective MPC (MPC,rr) for each release stream (steam- r generator _ blowdown, blowdown neutralization sump, or turbine plant sump),is determined using:
_3 (1 10)
MPC'" =
'C,/C' 'C/C' .
' CJC' .
' Cp/C' I C,/C' '
m, .
l S023-0DCM 1-17 Revision 22 08-02-90
4 1.0. LIQUID EFFLUENTS (Continued) 1.4.2 Continuous Release Setpoint Determination (Continued)
}JIP,_1: The setpoint, C, (pCi/ml), for each continuous release radioactivity monitor may now be specified based on the respective values of C, I,C,,, F. HPC,,,, and R to provide compliance with the limits of 10CFR20, Appendix B, Table 11, Column 2. The monitor setpcint, cpm, is taken from the applicable calibration constants given in Table
.1-3 to correspond to the calculated monitt - limit C.,
pCl/ml.
O O S023-0DCH 1-18 Revision 21 02-15-90
1.0 LIQUID EFFLUENTS (Continued) 1.4.2.1 NEUTPALIZATION SUMP DISCHARGE LINE MONITORS p (2RT 7817. 3RT-7817) i The value for C, or C , the concentration limit at the Unit 2 or Unit 3
3 detector is determined by using:
O' (B,) ( F) E,C,,
C, s (R)(C/MPC,,,)
( }
(83)(F)E,C,,
Cs 3
(R)(C/MPC,,,)
where: ,
C , I,C,, , MPC,,, - values of C, I,C,, and MPC,,, as defined in STEPS I and 2 for the Steam Generator blowdown / BPS neutralization sump. '
R = effluent flow rate at the radiation monitor as defined in STEP 2 (maximum of S00 gpm).
C, - instantaneous concentration at the Unit 2
(')
%.J detector (2RT-7817) in pCi/cc C3 = instantaneous concentration at the Unit 3 detector (3RT-7817) in pCi/cc B, and B3 are administrative values used to account for simultaneous releases from both SONGS 2 and SONGS 3 neutralization sumps. The fractions B2and B 3will be assigned such that (RW 78u + SG38 ., + SGn r +
SG 3 + SGn.3 + Br + 3B + T + T3 ) s 1.0 i
C)i q
5023-0DCM 1-19 Revision 22 08-02-90
4 1.0 LIQUID EFFLUENTS (Continued)
[D fl.4.2.1 EEUTRALIZATION SUMP DISCHARGE LINE MONITOR 12RT-7817,3RT-7817) (Continued)
NOTE: If C3 or C s I,C,i, then no release is possible. To increase 3
Cr or C3 , increase dilutien flow F (by running more circulating water pumps), and/or decrease the effluent flow rate R, (by throttling the flow as measured on 2F1-3722 and 3F1-3772), and
. recalculate C3 or C3 using the new F, R and ecuation (1-11) or (1-12).
If there is no release associated with this moottor, 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.
O S023-00CM l-20 Revision 21 02-15-90
1.0._ LIQUID EFFLUENTS (Continued)' ,
1.4.2.2 STEAM GENERA 10h_ BLOWDOWN BYPASS DISCHARGE LINE MONITOR]
(2RT-6753. 2RT-67C4, 3RT 6753. 3RT-6759)
The value' for C ,.,, Cs..r, C 3,.3 or Cs3 3, the concentration limit at the 5
Unit 2 or Unit 3 detectors, is determined by using:
(1-13)
C s (SG"4)(F)E,C,,
8 (R)(C/MPC,,,)
(1-14)
(SG,4)(F)E,C,,
e 534 ~
(R)(C/MPC,,,)
(1-15)
(SG.3)(F)E,C,,
~3 (R)(C/MPC,,,)
(1 16)
(SGe ,.,)(F)E,C,y 53-3 , *
(R)(C/MPC,,,)
where:
C , I,C,, , MPC,,, - values of C, E,C , and MPC ,-(as defined in
- STEPS 1and2ab,ove)forI.,hesteamgenerator blowdown bypass.
R = maximum blowdown bypass effluent flowrate per steam generator, 200 gpm.
Co.r- -- -instantaneous concentration at the Unit 2-detector (2RT-6759) in pCi/mi C,3,3 = instantaneous concentration at-the Unit 2 detector (2RT-6753) in pCi/ml Ca.3 -
instantaneous concentration at the Unit 3 detector (3RT-6759)inpCi/mi Cs3 3 instantaneous concentration at the Unit 3 detector (3RT-6753) in pCi/mi O S023-00CM 1-21 Revision 21 02-15 90
l.0 LIQUID EFFLUENTS (Continued) 1.4.2.2 E[EAM GENERATOR BLOWDOWN BYPASS DISCHARGE LINE MONITORS (2RT-6753, 2.ET 6759. 3RT-6753. 3RT-67591 (Continued) k' RW,,n and SG .,, SG,,,,, 8 , Tr, T are administrative SGas.3 SGe s.3, B,, 3 3 values used for sinultaneous releases from the Radwaste Effluent discharge and any or all of the four Steam Generators as well as continuous discharges from the-two Blowdown Processing Systems and the two Turbine Plant Sumps. The fractions RWien and SG .,, SG e,,,, SGas.3 SG,, 3, B,, B3 , T,, T3 will be assigned such that (RWien + SGas.r + SC3 ,,,
+ SGen.3 + SG ,.3 B, + B3 + T, + T3) 5 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 /0, Appendix B, Table II, Column 2 from the site.
NOTE: If C ,,,. C33.,, C 3 3 ,.3, or Cn.31 I,C,i (for the respective steam generator), then no release is possible. To increase C 3 ,.3, Co-a, C3 , 3 or Cn.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 C3 ,,,, Cu.z, C 3 ,.3 or Cn.3 using the new values of F, R and equation (1-13), (1-14), (1-15) or (1-16).
O S023-0DCM l-22 Revision 21 02-15-90
- - _ _ _ _ - - . - . - _ _ _ . ._ . _ k
1.0 LIQU10 EFFLUENTS (Continued) .
1.4.2.2 STEAM GENEPAIOR BLOWDOWN _ BYPASS DISCHARGE LINE MONITORS
"'''"'''"''""'''' (' "'"*d)
(~)
' If there is no releas'e 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.
1.4.2.3 TURBINE PLANT SUMP MONITORS (2RT-7821. 3RT-7821)
The value ')r Cr or C3 (the concentration limit at the Unit 2 or Unit 3 detector) is determined by using:
(' )
(T3 )(F) AC,,
C, s (R)(C/MPC,,,)
(Ts )(F)I,C,,
C, s (R)(C/MPC,,,)
OV where:
C , Ii c,,, MPC,,, - values of C, I,C,, and MPC,,, (as defined in STEPS I and 2 above) for the turbine plant sue:p R = 100 gpm/ pump (x no. sump pumps to be run) Unit 2 A 50 gpm/ pump (xno.sumppumpstoberun) Unit 3 C = instantaneous concentration at the Unit 2 detecter (2RT-7821), pC1/ml.
-C 3 = instantaneous concentration at the Unit 3 -
detector (3RT-7821), pC1/ml.
i I
l t
5023-0DCM l-23 Revision 25 02-28-92 l
_ _ _ . . __. _ ~ , . . . . , .- ._. . _
.- __ =
1.0 LIQUID EFFLUENTS (Continued) 1.4.2.3 . TURBINE PLANT SUMP MONITORS (2RT-7821. 3RT-7821) (Continued)
T and T3 are administrative values ~used to account for simultaneout releases from both SONGS 2 and SONGS 3 turbine plant sumps. The fractions T, and T will 3 be assigned such that (RWie33 4 SGas-r + SGes. +
SGes.3 + SGe93 Br + B3 + T + T3 ) s 1.0.
NOTE: If C, or C3 i I,C,, (for the respective sump), then no release is possible. To increase C, or 3C , increase the dilutim flow F (by running more circulating nter pumps) and recalculate C, or C3 using the new value of F and equation (1-17) or (1-18).
Use of a temporary discharge path from the Turbine Plant Sump is allowed providing the radiation monitor, 7821, in service and the normal discharge path is used concurrently. Temporary pumps
- facilitate faster discharge when draining the condenser to the outfall via thit pathway. The following conditions shall be met:
- a. The release permit shall account for the entire volume of water discharged from the Turbine Plant Sump.
- b. The alarm setpoint for the monitor shall be adjusted to take into account the entire discharge flow through both the normal and temporary paths.
- c. Procedures shall require the imediate termination of the discharge via the temporary path if the monitor on the normal path al arms.
O S023-00CM l-24 Revision 21 02-15-90
1.0 LIQUID EFFLUENTS (Continued)
O
. (J 1.4.2.3 TURBINE PLANT SUMP MONITORS (PRT-7821. 3RT-7821) (Continued)
If there is.no release associated with this monitor, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet assure an alarm should an inadvertent release occur.
(3 Q) 5023-00CM l-25 Revision 22 08 02-90 m., , -*- ..m..--,,, - r , .,,,r ,-, e v. , - , -
Table'l 3 Liquid Effluent Radiation Monitor Calibration constants i O- (pci/cc/ cpm)
HONITOR Co 60 Ba 133 Cs 137 2RT 6753 1.74E 8 1.91E 8 2RT 6759 1.7tE 8 1.93E 8 3RT 6753 1.66E 8 1.93E 8 3RT 6159 1.79E 8 1.94E 8 ,
2.12E 9 3.59E! 9 5.20E 9 2/3RT 7813 2RT 7817 2.43E-9 3.40E 9 4.69E 9 2RT 'iB21 2.14E 9 3.63E 9 5.21E 9 3RT-7817 2.33E 9 3.22E 9 4.73E 9 n 3RT-7821 P.13E 9 3.64E 9 5.20E 9
() _.
1 i
l i
l
(*) This ?.able provides typical (2 207.) calibration constants for the liquid effluent radiation monitors.
5023 0DCM l 26 Revision 25 02-28 92 l
1.0 L!gitDcrFLbENTS (Continued) 1.5 Dose Calc'J1ation for Liquid Effluents O The liquid releases considered in the following dose calculations are described it. Section 1.4. The dose commitment to an individual from radioactive miterials in liquid effluents released to unrestricted areas are calculated for the purpose of implementing Specification 1.2.1 using the following expression.
, , (1 19) 0, " E q A,, E/At, C y f,),
idere: ,
A,i - Sits related adult ingestion dose commitment factor to the total body or an organ, t, for each ident(fied principal gamma and beta emitter, i, from Table 1 4 in mrsm/hr per pCi/ml.
C ,; = average concentrstion of radionuclide, i, in the undiluted liquid effluent during time period At), in pCi/ml.
D, = dose commitment to the total body or an organ, t, from the liquid effluent for the time period At), in mrem.
F)
= near field aversge dilution factor for Cn during the time period.
At3 . This factor is the ratio of the maximum undiluted liquid waste flow during time period, At , to the average flow from the 3
site discharge structure to unrestricted receiving waters, or maximum ljauid radioactive waste flow discharga structure exit flow At j = length of the j" time period over which C y and F) are averaged for all liquid releases, in hours.
O S023 0DCM l 27 Revision 23 02 28 91 s
TABLE l 4
, DOSE COMMITHENT FACTOR 5*, A,,
(mrem /hr per pCi/ml) l
~ '
P)dio- Total Nuclide Bone Liver Body Thyroid Kidney Lung GI LL1 1 H3 2.62E 1 2.82E 1 2.82i 1 2.82E 1 TSH 1 2.02E 1 Na 24 4.57E 1 4.57E 1 4.57E 1 4.57E 1 4.57E 1 4.57E 1 4.57E 1 <
Cr 51 5.5BE+0 3.34E+0 1.23E+0 7.40E+0 1.40E+3 Mn 54 7.06E+3 1.35E+3 2.10E+3 2.16E44 Mn 56 1.78E+2 3.15E+1 2.26E42 5.67E+3 Fe 55 5.11E+4 '!.53E+4 8.23E+3 1.97E+4 2.03E+4 Fe 59 8.06E+4 1.90E45 7.27E+4 5.30E+4 6.32E+5 Co-57 1.42E+2 2.36E+2 3.59E+3 Co 58 6.03E+2 1.35E43 1.22E+4 Co 60 1.73E+3 3.82E+3 3.25E+4 Cu 64 2.14E+2 1.01E+2 5.40E+2 1.83E+4 Zn 65 1.61E+5 5.13E+5 2.32E+5 3.43E+5 3.23E45 Br 84 9.39E 2 . 7.37E-?
Rb 88 1.79E+0 9.49E 1 2.47E ll Sr 89 4.99E+3 1.43E+2 8.00E+2 Sr 90 1.23E+5 .
3.01E+4 3.55E+3 Sr+91 9.18E+1 3.71E+0 4.37E+2 Sr 92 3.48E+1 1.51E+0 6.90E+2 Y 90 6.06E+0 1.53E-1 6.42E+4 Y 91m 5.73E+2 2.22E 3 1.6BE 1 Y 92 5.32E 1 1.56E 2 9.32E+3 Zr 95 1.59E+1 5.11E+0 3.46E+0 8.02E+0 1.62E+4 Zr 97 8.81E 1 8.13E 2 2.68E 1 O Nb 95 Nb.95m 1.84E+0 J.84E+0 3.78E 1 1.03E+0 1.C3E+0 5.51E-1 5.51E 1 1.01E+0 1.01E+0 5.51E+4 6.22E+3 6.22E+3 Nb 97 1.55E 2 3.91E 3 1.43E 3 4.56E 3 1.44E+1 Mo 99 1.28E+2 2.43E+1 2.89E+2 2.96E+2 Tc 99m 1.30E 2 3.66E 2 4.66E-1 5.56E 1 1.79E 2 2.17E+1 Ru-103 1.07E+2 4.60E+1 4.07E+2 1.25E+4 Ra 106 1.59E+3 2.01E+2 3.06E+3 1.03E+5 Ag llom 1.42E+3 1.32E+3 7.82E+2 2.E9E+3 5.37E+5 Sn ll3 2.26E+5 Sn ll7m 2.26E+5 Sb 124 2.76E+2 5.22E+0 1.09E+2 6.70E 1 2.15E+2 7.84E+3 Cb 125 1.77E+2 1.97E+0 4.20E+1 1.79E 1 1.36E+2 1.94E+3 Te 129m 9.31E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 4.69E+3 Te 132 2.04E+P. 1 M E+2 1.24E+2 1.46E+2 1.27E+3 6.24E+3 1 131 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E+2 8.23E+1 1 132 1.06E+1 2.85E+1 9.96E+0 9.96E+2 4.54E+1 5.35E+0 1-133 7.45E+1 1.30E+2 3.95E+1 1,90E+4 2.26E+2 1.16E+2 1-134 5.56E+0 1.512+1 5.40E+0 2.62E+2 2.40E+1 1.32E-2 L1 135 2.32E+1 6.0BE+1 2.24E+1 4.01E+3 9.75E+1 6.87E+1 NOTE: where no value it given, no data are available.
- Source: Reg. Guide 1.109 Table E-11, Table A 1 USNRC NUREG 0472, Table 4 Me$hodology: USNRC NUREG4133 Section 4.3.1 5023-0DCM l 28 Revision 23 02 28 91
= = ex , w: n- ~ n - -- . - - - -
IMLL1:A DOSE COMMITMENT FACTOR 5*, A,,
(mrem /hr per pC1/ml)
Radio- Total Nuclide Bone Liver Body Thyroid Kidney Lung GI LLI i l
Cs 134 6.84E+3 1.63E+4 1.33E+4 5.27E+3 i.75E+3 2.85E+2 l Cs 136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21E+2 l Cs 137 8.77E43 1.20E44 7.85E+3 4.07E+3 1.35E43 2.32E+2 Cs 138 6.07E+0 1.20E41 5.94E40 8.91E+0 8.70E 1 5.12E 5 <
Ba 139 7,85E+0 5.59E 3 2.30E 1 5.23E 3 3.17E 3 1.39E+1 Ba 140 1.64E+3 2.06E+0 1.08E+2 7.02E 1 1.18E+0 3.38E+3 l La 140 1.57E+0 7.94E 1 2.10E 1 5.83E+4 Ce 141 3.43E+0 2.32E40 2.63E 1 1.08E+0 8.86E+3 Ce 143 6.04E 1 4.46E+2 4.94E 2 1.97E 1 1.67E+4 '
Ce 144 1.79E+2 7.47E+1 9.59E+0 4.43E+1 6.04E+4 Nd 147 3.96E+0 4.58E+0 2.74E 1
- 2.68E+0 2.20Ev.
W .187 9.16E+0 7.66E+0 2.68E40 2.51E+3 Np 239 3.53E 2 3.47E 3 1.91E 3 1.08E 2 7.llEn NOTE: where no value is given, no data are available.
- Source: Reg. Cuide 1.109 Table E-II, Tablo A 1 USNRC NUREG-0472, Table 4 Methodology: USNRC NVREG 0133, Section 4.3.1 4
O S023 0DCM l 29 Revision 23 02-28 91
= - - . . - . - _ - .
1.0 L10VID EFFLUENTS (Continued) 1.6 Representative Sampling Prior to satepling of a batch release, each batch shall be thoroughly mixed to assure representative sampling in accordance with the requirements of Regulatory Guide 1.21 and NUREG 0800, Section 11.5. The methodology for mixing and sampling is described in 50123 !!! 5.11.23.
" Units 2/31iquid Effluent Release Permit" and 50123 111 5.2.23, " Units 2/3 Liquid Effluent Sample Collection".
t O
O 5023-0DCM 1 30 Revision 21 02 15 90
. . _ _ _ _ _ - _ _ _ _ - - ~ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ - _ _ _ __ _ _
i 2.0 GASE0V! LFFLUENTS 2.1 QOSE RATE EL(JFICATION 2.1.1 The dose rate in unrestricted areas due to radioactive materials released in gaseous effluen'ts from the site (see Figure 2 2) shall be limited to the following:
- a. For noble gases: Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, and
- b. For all radiciodines, tritium and for all radioactive materials in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.
APPLICABILITY: At all times mil 0!fi
- a. With dose rate (s) exceeding the above limits, immediately decrease the release rate to within the above limit (s).
SURVEILLANCE REQUIREMENTS
.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 radiciodin6s. tritium and radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents shall be determined to be within the above 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.
5023 0DCH 21 Revision 21 02 15 90
, , - . - ,- ----m-r---wr --
-r- .-.- n a 4 w
TLBLE 2d PJJ.10 ACTIVE GASEOUS WASTE SAMPLING AND ANALYS15 PROGRAM Gaseous Minimum Type of Lower Limit Release Sampling Analysis Activity of Detection Type Frequency Frequency Analysis, (uCi/ml)'
Batch P P Principal Gama Emitters }x}o 8 Waste Gas Each Tank Each Tank Decay Tank Grab Sample Incinerated Each Batch' Each Batch' Principal Gama Emitters' Sx10" 011" Grab Sample Continuous *
- Principal Gama Emitters' l x 10**
- Tritium lx10 4
/ 1 131 1 x 10*"
Continuous' Charcoal
- Sampler Sample ,i.133 lx10
/
Continuous' Particulate Principal Gama Emitters' lx10*"
Sampler Sample (1 131 and Others)
M Continuous' Composite Gross Alpha lx10*"
Sampler Particulate Sample ,
Continuous' Composite Sr 89 and Sr 90 lx10*"
Sampler Particulate Sample Continuous' Noble Gas Noble Gases lx10 4 Monitor Monitor Gross Beta or Gama
- Sampling frequencies for noble gases and tritium are: .
CONTINUOUS PATHWAYS: Containment Purge 42' : Each Purge'd Containment Purge 8' : Monthly Grab' Condenser Air Ejector : Monthly Grab' Plant Vent Stack : Weekly Grab'd l
l 5023 0DCM 22 Revision 22 O 08 02 90
-.,,+..,..-+.,.,-__,.n.-- _
i TABLE 2 1 (Continuedl IfR E NOTAT103
- a. The LLD is the smallest concentration of radioactive material in a' sample Os that will be detected with 95% probability with 5% probability of f alsely concluding that a blank observation represents a "real" signal, j for a particular measurement system (which may include radiochemical separattor.):
4.66 s*
LLD =
E + Y + 2.22 x 10' + Y + exp (-Aat) where:
LLD is tL. *a priert' lower limit of detectinn as defined above (as microcuris per unit mass.or volume),
s, is the st6ndard deviation of the background counting rate or of the counting rate of a blank sample as arprop'riate (as counts per minute),
E is the counting efficiency (as counts por transformation),
V is the sample size (in units of mass or volume),
2.22 x 10' is the number of transformations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
1 is the radioactive decay constant for the particular radionuclide, and At is _the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples).
The value of s, 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.
l In calculating the LLD for a radionuclide determined by gama 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 criori (before the fact) limit representing the capability of the measurement :;ystem and not as A Dosteriori (after the fact) limit for a particular measurement.*
- For a more complete , discussion of the LLD, and other detection limits, see the following:
l
, (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-2532 (June 22,1972).
$023 0DCM 21 Revision 21 02 15 90
TABLE t.1 (Continuedi TABLE NOTATION
- b. Analyses shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of the RATED THERHAL POWER within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period. This requireoent does not apply if: (1) analysis shows that the DOSE EQUlVALENT l 131 concentration in the reactor coolant has not increased more than a factor of 31 and (2) the noble gas monitor shows that effluent act,vity has not increased more tLan a factor of 3..
- c. Trirlum grab samples 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 t efueling t.eal is flooded,
- d. Saspies shall Le changed at least once per 7 days and analyses shall be cwpletea within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler).
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 hilowing each shutdown, startup, or a THERMAL POWER change exceeding 15 percent of f.ATED THERMAL POWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and analyses shall be completed withir 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. This requirement does not apply if:
(1) analysis shows that the DOSE E0V! VALENT l-131 concentration in the reactor cooiar.t has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 2. 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 correspending 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 sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 2.1, 2.2, 2.3.
- g. The principal gamma emitters for which the LLD specification applies e.9clustvely 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, 2n 65, Mo 99, Cs 134, Ce 141 and Ce 144 for pnticulate emissions. This list does not mean that only these nuclides are to be detected and reported, i
Other peaks which are measurable and identifiable, together with the above l nuclides, shall also be identified and reported.
- h. Incinerated oil may be discharged at points other than the plant vent stack.
Release shall be accounted for based on pre release grab sample data.
- 1. Samples for incinera+.ed oil releases shall be collected from representative samples of filtered oil in liquid form.
l l
O S023-0DCM 24 Revision 22 08 02-90 w L AW 9ms.
- me m mehmege.e.wts w w w w as mi es-m u -ama,-- -
- w _g _ - - - -. _ _ _
- ... . -.- - . =- - . - = . _ - - _ _ - . - . - ._- __ - _ - . . ._.
P 2.0 GA$E005 EFTLUENTS (Continued) 2.2 DOSE NOBLE GASES
}PLCIFICATION 2.2.1 The air dose due to noble gases released in gastous effluents, from each reactor unit, frem the site (see Figure 2 2) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrad for gama radiation and less than or equal to 10 mrari for beta radiation and,
- b. During any calendar yeer: Less than or equal to 10 mrad for gama radiation and less than or equal to 20 mrad for beta radiation.
APPLICABILITh At all times LCTIDN:
- 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 6.9.1, prepare and submit to the Comission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the 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 s subsequent releases will be in compliance with Specifica-tion 2.2.1.
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.
O S023-00CM 2-5 Revision 21 02-15 90
-ym- ,r -%.,e,ww- --w-- ye-,r-- *e
. av', - --e r ---'
l l
2.0 GA$E005 EFFLUENTS (Continued) 2.3 DOSE RAD 1010 DINES. RADIOACTIVE MATERIALS IN PARTICULATE FORM AND TRITlVM
)
SPECIF IC ATl0.!j 2.3.1 The dose to an individual frem tritium, radiciodines and radioactive materials in particulate form with half lives greater than 8 days in gasms effluents released, from each reactor unit, from the Site (sec figure 2 2) shall be limited to the following:
- 4. During any calendar quartee: Less than or equal to 7.5 mrem to any organ and,
- b. During any calendar year: Less than or equal to 15 mrem to any organ,
- c. Less than 0.1% of the limits of 2.3.1 (a) and (b) as a result of burning contaminated oil.
6,.PPLICABillTY: At all times ACTION:
- a. With the calculated dose from the release of tritium, radiciodines, and radioactive materials in particulate form, with half lives greater than 8 days, in gaseous affluents p)
(
exceeding any of the above limits, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the Commission within 30 days pursuant to Technical Specification 6.9.2 a Special Report which identifies the cause(s) for exceeding the limit 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.
JVRVEILLANCE RE0l'IREMENTS .
.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.
A b S023-0DCM 2-6 Revision 21 02-15-90
4 i
2.0 GASE0US EFFLUDUS (Continued) 2.4 GASEOUS.RADWASTE TR QlM MI SPECIFICATIOS 2.4.1 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be operable. The appropriate portions of the GASEOUS RADWASTE TREATHENT 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 gama 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 when the projected doses due to effluent releasea from the site (see Figure 2 2)gaseouswhen averaged over 31-days would exceed 0.3 mrem to any organ.*
MPLICABILITY: At all times ACTION:
- a. With gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the Comission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which includes the following information:
- 1. Explanation of why gaseous radwaste was being discharged without treatment', identification of the inoperable equipment or subsystems and the reason for inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Sumary description of action (s) taken to prevent a recurrence.
SURVEILLANCE RE0VIREMEN11 .
.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with Section 3.2.
i
- These doses are per reacter unit.
l O 5023-0DCH t 2-7 Revision 22 08 02-90 4
_ . _ _ _ . . . _ _ _ _ _ . _ _ . _ _ . . _ _ . _ . . _ . _ . . _ . _ _ _ . . ~ . . _ _ . _ _ _ . . _ . _ . _ _ .
2.0 &ASE005 EFFLUENTS (Continued) 2.4 GASEOUS RADWASTE TREATMENT (Corittnued)
SURVElllANCE RE0VIREMFM1 (Continued) ,
t
.2 Duringplantoperation(Modes 14),theapplicableportionsofthe l i
GASEOUS RADWASTE TREATMENT SYSTEM and VENT!lATION EXHAUST TREATMENT SYSTEM shall be demonstrat6d OPERABLE by operating the GASEOUS RA0 WASTE TREATMENT SfSTEM equipment and VENTILATION EXHAUST i TREATMENT SYSTEM equipment for at.least 15 minutes, at least once per 92 days unless the appropriate system has been utilized to ,
process radioactive gaseous effluents during the previous 92 days. l
.3 In plant shut down (Mode S, 6) the applicable portions of the !
GASE0US RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT I SYSTEM shall be demonstrated OPERABLE by operating the GASEOUS l RADWAS1E TREA1 MENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15 minutes prior to processing gsses unless the appropriate gaseous radwaste system has
-been utilized to process radiocctive gaseous effluents during the -!
previous 92 days.
i O .
i t
l i
LO S023 0DCM 28 Revision 22 08 02 90 L . ,
L
2.0 GASE0US Eff!.utNTS (Continued) 2.5 TOTAL DOSE b
d $HC1fICAT10N 2.5.1 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from urar.ium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months.
APPLICABILITY: At all times ACTION: ,
- s. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exteeding twice the limits of Specifications 1.2.4.a.1.2.1.b C.I.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' 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 O all effluent pathways and direct radiation) for a 12 consecutive month period that includes the release (s) covered by this report. If the estimated dose (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 s)ecified information of paragraph 190.11(b). Submittal of tie report is considered a timely request, and a vr.iance 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 ODCH.
SURVEILLANCE RE00lRFJiU{IS
.1 Dpse Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accoroance with surveillance 1.2.1.1, 2.2.1.1, and 2.3.1.1.
5023 0DCM 29 Revision 21 02-15 90
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,,-,.,4,., ,---.._b.,...-.,..,,,,e,_J-.-__----._,,--.- .
9203240102-ol
. - . . . . . . . . _ . ~ . . . . _ . . _ . - . . , . . -_--...#--,.....--..,.-.-_.
l 2.0 GA!!0US EFFLUENTS (Continued) l 2.6 helb.9.di_.pLC11s.plation for Gaseous Effluent Monitor _.}etooints Administrative values are used to reduce each setpoint to account for the potential activity in other releases. These administrative values shall be periodically reviewed based on actual release data and revised as required. 2.6.1 PLART VENT STACK 2/3RT-7808, 2RT 7865 1, 3RT 7865 1 2.6.1.1 2/?RT-7808 Plant Vent Stack Monito,t For the purpose of implementation of Specification 2.1.1, the i alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion
- factor.
Igtal Body l The concentration at the detector corresponding to a 3 (V 500 mrem /yr total body dose rate at the exclusion area boundary is determined by: (2 1) f i
*" 4 3 (0.38) 2120 ( 500 mrem /yr) (10 m /cc) i = '
m /sec, ' C cet i r i r 3 mrem /yr C, (Flow rate, cfm) (X/Q, sec/m') I, K,, pCi/m 3 , C , ,, where: C ., = the instantaneous concentration at the detector, pCi/cc 0.38 - an administrative value used to account for potential activity from other gaseous release pathways O $023-0DCM 2-11 Revision 22 08 02 90
l l 2.0 GASE0US EFFLUEN15 (Continued) 2.6.1 ELANT VENT STAE 2/3RT 7808, 2RT 7865 1, 3RT 7865 1 (7 b ' (Continued) K, = total body dose conversion factor from Table 2 4 for the 1" g,amma emitting noble gas, mreVyr per pCi/m C, = concentration of the 1" noble gas as - determined by sample analysis, pCi/cc Ct ,i = total concentration of noble gases as ' determined by sample analysis, pC1/cc = I,C, flow Rate = plant vent flow rate, cfm
= 82,000 cf# fan (x nc. of fans to be run) 2120 = conversion constant, cfm per m 8/sec 500 mrem /yr = total body dose rate limit, as specified by Specification 2.1.1.a X/0 =
historical annual average dispersion factor, sec/m
=
4.8E 6 sec/m' O v rid The concentration at the detector corresponding to a 3000 mrem /yr skin dose rate at the exclusion area boundary is determined by: (2 2) ( "I" (0.38) 2120 ( 2000 mre#yr) (104 m'/cc)
= ' m /sec, C
Get <
,,C,,
(flow rate, cfm) (X/Q, sec/m 3) E, L, 1.1H,, mr W yr 3 pt1/m ,,C,g l l . OV S023-00CM 2 12 Revision 24 08-31 91 l
- _ _ . - _ _ _ _ _ , _ - - _ - - -_ , , . . 1--
+ e l
, 2.0 GA$E005 EFFLUENTS (Continued) 2.6.1 21 ANT VENT-STACK 2/3RT 7808, 2RT 78651, 3RT 78651 ; (Continued) . . where!
- t. , sgin Dose Conversion Factor'frorg Table 2 4 for the i noble gas, mreWyr per pCi/m M, = air Dose Conversion Factor from8 Table 2 4 for the 4 1" noble gas, mreWyr per pCi/m 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 Other values in equation (2 2) are defined in equation (2 1). The smaller of the values of C,,, from equations (21) or (2 2) , is to be used in the determination of the maximum permissible ! monitor alarm setpoint (cpm), as follows: i O t 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 value ' cpm" corresponding to the concentration C,,, (the
- smallervalue.fromequation(21)or(22)). Thecalibration ,
constant used .is based _on Kr 85 or on Xe-133, whichever yields a lower detection efficiency (the . largest value in terms of pC1/cc/ cpm). The alarm setpoint will be maintained at a value not greater than the maximum permissible alum setpoint. O S023i DCM O 2 13 Revision 21 02 15 90 f
-w--1 4 y y =,y-,,y -e y n w -* s g **-4tr v s' ---*p'*~s* ~ " * - * = -"e v="" * * "'"""8'*7**-" *' " ' ' " " ' ^ ' " *
- 4 2.0 [d$fR5_ EFFLUENT 5 (Continued) 2.6.1 PLANT VENT STACK 2/3RT-7808, 2RT 7865 1, 3RT-7865 1 (Continued)
If there is no release associated with this monitor, the monitor setpoint should be established as close as practical to background to prevent spurious alarms and yet assure an alarm should inadvertent release occur. 2.6.1.2 2RT 786$ 1 and 3RT 7865 1 Wide _Rance Gas Monitors The maximum release rate (pci/sec) for Wide Range Gas Monitors is determined by converting the concentration at the detector, C ,, (pC1/cc) to an equivalent release rate in pCi/sec, as follows: (C,,,, pC1/cc)(flowrate, cc/sec)
~}
A,, = whera: Am = maximum pennissible release rate, pCi/sec C ,, = smaller of the values of C,,, obtained from equations (2 1) or (2 2). Flow Rate = flow rate,'cc/sec
,= (3.87 x 10 cc/see per fan) (number of fans) 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 i maximum release rate determined above, when this monitor is
- i. being used to meet the requirements of Specification 2.1.1.
A V S023 00CM 2 14 Revision 24 l 08 31-91
, _ - ~
. f, -----%w,#,,,. _ _, , .u- . , - -
2.0 (iASE005 EFFLUENTS (Continued) 2.6.1 ELANT VENT STACK 2/3RT-7808, 2RT 7865 1, 3RT 7865 1 (Continued) O- 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 and yet assure an alarm should an inadvertent release occur. 2.6.2 (_Q!!Q[NSER EVACUATION SYSTEM - 2RT-7810, 'RT-78701, 3RT-7818 or 3RT 78 % 1 2.6.2.1 2RT 7818 and 3RT 7818 Condenier Air Eiettor ligfiitors For the purpose of implementation of Specification 2.1.1, the alarm .tetpoint level for noble gas monitors is based on the gaseous effluent flow rate and the meteorological dispersion factor. The concentration at the detector corresponding to a total body dose rate of 500 mrem /yr at the exclusion area boundary is determined by using: Total Body (2 4)
, 3 (0.1)(0,5)
** ( 500 mrem /yr) (10 4 3 m /cc) 2120
= ' * **" -
Ce .t i 3 . (Flow rate, cfm) (X/Q, sac /m') E, K,, ""*I## b.3 pCi/m 8 , C The concentration at the detector corresponding to a 3000 mren/yr skin dose rate at the exclusion area boundary is determined by using: liki.Q , , (24a) (0.1)(0,5) 2120 . ( 3000 mrem /yr) (10 m /cc) 3
= ' m /sec, C **
cet
},,
(Flow rate, cfm) (X/0, sec/m') E, L, + 1. lM,, mreWyr 3 pCi/m Cs ,s O S023-00CM 2-15 Revision 21 j 02 15 90 (** f fM99*'85ck oudD* ++ *
- O A w 3aye pew p ,- g , , , , _
. - . -- _- -.-.~._-- -----_. -. _-__
l 2.0 GASEOUS EFFLUENTS 2.6.2 CONDEER EVACUkTION SYSTEM 2RT-7818, 2RT 78701, 3RT-7818 or 3RT 78701 (Continued) where: 0.1 is an administrative value used to account for potential activity from other gaseous release pathways. 0.5 is an administrative value used to account for releases from both SONGS 2 and SONGS 3 condenser air ejectors simultaneously. Other parameters are specified in 2.6.1.1, above. The smaller of the values C,,, from equations (2 4) or (2 4a) is to be used in determining the maximum permissible monitor alarm setpoint (cpm), as follows: 1 The maximum permissible alarm setting (cpm) is determined by - using the calibration constant for the corresponding Condenser Evacuation System Monitor given'in Table 2 3. The maximum permissible alarm setpoint is the epm value corresponding to the concentration, C,,,, (smaller value from equation (24)or(24a)). The calibration constant used is based on Kr-85 or on Xe-133, whichever yields a lower detection efficiency (higher value in tems of pCi/cc/ cpm). The alarm setpoint will not be set greater than the maximum permi tsible alarm setting determined above. l O 5023 0DCH l 2 16 Revision 21 02-15 90 e ,-
,..,-c...g,- .y- g ,,v., -
,--,..r,. ,,,a, . , . _.,.n,- - - - _ - . - .- - . , , , - , . - - - - - , ,
4 4 2.0 SAILQU5 EFFLUQill (Continued) . 2.6.2 CONDENSER EVACUATION SYSTEM . 2RT 7818, 2RT 78701, 3RT 7818 O or 3RT 7870 1 (Continued) If there is no release associated 'with this monito*, the monitor setpoint should be estabitsbed as close as practical to ; background to prevent spurious alarms yet ossure an alarm should an inadvertent release occur.
- 2. 6. 2. '2 2RT.78701 and 3RT 78701 tideA e hs Monitors The maximum release rate (pti/sec) for Wide Range Gas Monitor is determined by converting the concentration at the detector, C,,3 (pCi/cc),.to an equivalent release rate in pCi/sec.
A., = (C,,,, pCi/cc) (flow rate, cc/sec) where: A., = maximum permissible release rate, pCi/sec C ,, , . smaller value of C as obtained from equations (2 4) an ,1(,2 d 4a) i flow rate - flow rate of the condenser air ejector, cc/sec
- 4.719ES cc/sec (conservatively assumed as design flow rate)
If there is no release associated with this monitor, the monitor setpoint should be established as close as practical ti, background to prevent spurious alarms yet assure an alarm should an inadvertent release occur. l l - 5023 0DCM 2 17 Revision 21
^2 25 90 4
,_,- ,, __p vwe-ve-- , ,-r- -
-.----1sy . y a~ , - ,- , - ,--e-.e-
2,0 GA${aus EFFLUENTS (Continued) 2.6.3 CONTAINMENT PURGE 2RT 7828, 3RT 7828, 2RT 7265, 3RT-7865 For The purpose of implementation of Specification 2.1.1, the alarm setpoint level for noble gas monitors is based on the gaseous effluent flow rate and the ineteorological dispersion factor. i The concentration at the detector corresponding to a total body dose rate of 500 mrem /yr at the exclusion boundary is determined ' by using: Total Body
, , (2-6)
- 4m 3 /cc)
(0.38)(P,) 2120 ( 500 mrem /yr) (10 m,/sec, gcett , . (Flow rate, efm) (X/Q, sec/m') I, K,, pC i/m' , , C,,, , (2 7) (0.38)(P3) 2120 ( 500 mrem /yr) (lod m'/cc) 3 m /seC, gcet3 , 1 % r t !
**/#' '
(Flow rate, cfm) (X/Q, sec/m') E, K,, pCi/m 3 , C , ,, The concentration at the detector corresponding to a 3000 mrern/yr skin dose rate at the exclusion area boundary is determined by using: Eliu , , (26a)
'I* 4 8 (0.38)(P,) 2120 ( 3000 mrem /yr) (10 m /cc)
C esti
=- ' */8
*I# i (Flow rate, cfm) (X/Q, sec/m') E, L, + 1.1H,,
pCi/m 3 , C,,, l 3 (2 7a)
- 4 3 (0.38)(P3) 2120 ( 3000 mrem /yr) (10 m /cc)
=
m,'/sec, C ,
- eet T / ,1 w
l (Flow rate, cfm) (X/Q, sec/m') E, L, + 1. lM,, mrem /yr ,, , , pC i/m' , , Ct ,t,' l O S023 00CM 2 18 Revision 22 08-02 90 i
2.0 AM100$ EFFLM (Continued) 2.6.3 CONTAINMENT PURGE + 2RT 7828, 3RT 7828, 2RT 7865, 3RT-7865 (Continued) Cu oe
= instantaneous concentration of the Unit 2 detector,pCi/cc.
C,,o = instantaneous concentration of the Unit 3 detector,pCi/cc. 0.38 is an administrative values used to account for potential activity from other gaseous release pathways. P, ar.d P 3 are administrative values used to account for-simultaneous purges of both SONGS 2 and SONGS 3. The fractions P, and P 3 will be assigned such that P, + 3 P 51.0. Flow rate - observed maximum flowrate in efm from the unit specific monitor 7828. - Default values will be the O following conservative messered 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 Cau from equation (2 6) or
-(2 6a) and C a o from equations- (2 7) er (2-7a) is to be used in determining the maximum permissible monitor alarm setpoints.
O -5023-00CM 2-19 Revision 22 08-02-90 i c v is t+ - - - - - - _ - , .ey e r *'e4 -r -'"ad e r r''-- - '- w er w t e v.s te *7 '"
*v"i"7 v v* ' y -
-&-- v' v v m ' v 7 -
cwvr =+--+ - y#
2.0 GASEOUS EFF,Lylf(Li (Continued) 2.6.3 CONTAINMENT PURGE 2R1' 7828, 3RT 7828, 2RT 7855, 3RT 7865 (Continued) V 2.6.3.1 daximum.brmissible Alarm Settino (RT 7865) The maximum permissible alarm setting for the Wide Range Gas Monitor expressed as a maximum release rate (4Ci/sec) is . determined by converting the concentration at the detector, C,,, (pCi/cc),to an equivalent release rate in pCi/sec. A., = (C,,,, pCi/cc) (flow rate, cc/sec) where:
-A , = maximum permissible release rate, pCi/cc C ,,, a smaller value of C ,,, 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
= 1.416E6 cc/see for mit.: purge. +
- 2.360E7 cc/see for mani purge.
.2 Maximum Permissible Alarm Settina (RT '82.6.),
The maximum permissible alarm setting for RT 7828 is in pCi/cc and is the smaller of the values of C,,,, (pC1/cc) from equations (2-6)and(26a). If there is no release associated with this monitor, the , monitor setpoint should be established as close as practir;al to i background to prevent spurious alams yet assure an alarm should an inadvertent release occur. t 4 e O S023 00CM
, 2 20 Revision 22 08 02 90
--+ ,vw -. .-,., - ~ - -me
4 2.0 CASE 0V$ EFFLUENT 1 (Continued) l 2.6.4 WASTE GAS HEADER 3RT 7865, 2/3RT 7808 For the purpose nf Specification 2.1.1, the alarm setpoint level for noble gas monitors is based en the gaseous effluent flow rate and the meteorological dispersion factor. Since the waste gas he M er discharges to tht plant vent stark, either 3RT 7865 or 2/3RT 7808 may be used to monitor waste gas header releases. The concentration at the detector corresponding to a total body dose rate of 500 mrem /yr or a' skin dose rate of 30)0 mrem /yr at the exclusion area boundary is determined by unng equations (2 1) v ' 12) with sample concentration (C,) and (C,,,) being obtained from the waste gas decay tank to be released. The smaller of the values of maximum permissible concentration (C,,,) from equation (2 1) or (2 2) is to be used in determining the maximum permissible monitor alarm setpoint. 2/lB M S.QA The maximum permissible alam 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 corresr onding to the concentration C,,,, (smaller value from equation (2 1) or (2 2)). O S023 0DCM 2 21 Revision 21 02-15 90 + +e t eenster"th-FB**wasegeme www ,et was eye- ocw we ymmerg ynyAs eqqqueygeyag=. ;t gy.' g _1s e . _ _ _ , e meenetstagssa m
2.0 SAst005 EFFLUENTS (Continued) 2.6.4 WASTE CAS HEADER 3RT 7865, 2/3RT-7808 (Continued) 3RT-7865 The maximum permissible alarm setting is expressed as a maximum release rate (pci/sec) and is determined by converting the concentration at the detector, C.,1, to an equivalent release rate in pCi/sec by equation (2-8). (C,,,, pCi/cc) (flowrato, cc/sec) A = m where: A ,, - the maximum ptrrdssible release rate, pCi/sec C ,,, - the smaller value of C ,,, as obtained from equation (2-1) or (2 2), flowrate = flowrate, cc/sec
= 7.74E7 cc/sec for 2 fan operation or
- 3.87E7 cc/sec for 1 fan operation
= correction for 3-7865 viewing only 1/2 the total O 2 Plant Vent Stack Flow.
.1 A release from the waste gas header is not possible if:
, , (2-9)
(I,C,) >c,,, O S023-0DCH 2-22 Revis nn 24 , 08 31-94
2.0 fd}iEU$ EFFLUENIX (Continued) 2.6.4 - WASTE GAS -HEAQ[E - 3RT-7865, 2/3RT-7808 (Continued)
, . l2.6.4.1-(Continued) rthere:
E,C, - total concentration in waste gas holdup t_ank to be released f = vaste gas header effluent flow rate, cfm F = plant vent stack flowrate in efe (166,000 cfm for 2_ fan operation; 82,000 for 1 fan operation) C., - smaller of the values of C fromequation(21) or (2 2) with C, being obtaYned from the waste gas holdup tank to be released If a release is not possibb., i- .st the waste gas eader flow by datermining the inaximum permissible waste gas header ' sffluent flow re. :orresponding to the Vent Stack Monitor-
- setpoint in-accorfance with the following:
N-q (0.9)(C g)(F) (2-10) Ei C,- where: f= waste gas header efflue;;t flow rate (cfm) F.- plant vent stack flow rate (cfm) used in equation (2-1) or(2-2) . 4 4 S023-00CM
, 2-23 Revision 24 -
08 31-91
,w. , - e me., . - - - ,s ,-m m-e.'w y, , 4 ,, w y,., ,,,--,.,m.- --r- --
---.a-2-1, -,se-- , --r----- .i v.v--
\
2.0 GASE0US EFFLUENTS (Continued) 2.6.< WASTE GAS HEADER - 3RT-7865, 2/3RT-7808 (Continued) (f 2.6.4.1 (Continued) C ,,, - smaller of the value of C,,, from equation (2-1) or (2-2) I i c, - total gamma activity (pCi/cc) of the waste gas holdup tank to- be relea.ed, as determined from the pre-release sample analysis. The 0.9 is an administrative value to account for the potential activity from other releases in the same release pathway,- (G OV S023 00CM 2-24 Revision 21 02-15 90 % _- v t ea w,mg e wv g er n reir.m ..- p. m , c .ep+ y w . p y y ,m+.g,ewy"*r r _e- m e ==ew"+ ~
Table 2-3(8)
, Gaseous Effluent Radiation Monitor i
Calibration Constants (pCi/cc/cnm) 4 HONITOR Kr-85 Xe 133 2/3RT-7808C 3.90E 8 4.62E 8 2RT-7818A 4.27E 8 6.63E-8 2RT-7818B 7.31E 5 2.07E 5 3RT 7818A 3.73E-8 5.09E 8 3RT-7818B 9.31E-5 2.21E 5 t V(% I
=
(*)This table provides typical (220%) calibration constants for the gaseous effluent radiation monitors. l S023 00CM ~ 2-25 Revision 21 02-15 90
2.0 GASEOUS EFFLUENIS (Continued) 2.7 Gsseous Effluent Dose Rate The methodology used for the purpose of implementation of Specification 2.1.1 for the dose rate above background to an individual in an unrestricted area is calculated by using the following expressions: 2.7.1 FOR NOBLE GASES: (2-11) Du = I, K,(X7Q)Q,
.' (2-12)
D, " Et li+IIM)(IIU)0 t 1 where: /~T l D . Du - total body dose rate in unrestricted areas due to l radioactive materials released in gr.seous ! effluents, mrem /yr ; D, - skin dose rate in unrestricted areas due to i radioactive materials released in gaseous effluents, mretn/yr K, - the total body dose factor due to gamma emissions from Table 2 4 for each identified nogle gas l radionuclide, i, in mrem /yr per pCi/m ' A V S023-00CM 2-26 Revision 21 02-15-90 NN# MbWESTM p pegg ,
-7,- y-rw-
~ _ . , , - , _ . _ - . - . _ _ _ _ _ _ - _ . _ - - . _ _ . _ . . _
o.-,
)2,0 GA5200$ EFFLUENTS (Continued) 9 2.7.1 -[QEJOBLE GASES:: (Continued)
O li_ =. skin dose factor due to the beta emissions.from Table 2 4 for each identified noble gas iadionuclide, i, in mrem /yr per.pCi/m e - Me a air dou factor due to gamma emissions from Table.2 4 for each identifjed noble gas radionuclide, i,-in mrad /yr per pCi/m 3 (conversion constant'of 1.1 mrem / mrad converts air dose to skin dose.) Q, - measured or calculated release rate of , radionuclide, i. for either continuous or batch - gaseous effluents, in pC_1/sec (X/Q) - Maximum annual average atmospheric dispersion factor for an;.te'ctor or'distante at or beyond the unrestrictedgreayoundary. 4.8E 6 sec/m 2.7.2 FOR ALL RAD 1010 DINES. TRITIUM-AND FOR ALL RADIOACTIVE MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER THAN EIG9T DAYS: , (2-13) (- D, =4 g(Pn 9,) Q, . where: D.
- organ dose rate =1' unrestricted areas due to
-radioactive materials released in gaseous effluents, mremfyr S023-0DCM 2-27 Revision 22 08 02
- tNa* twitsu- --. ; ._ _ __._ ___.,_m.,, ..m ,, _
2.0 GASEOUS EFFLUENTS (Continued)
?.7.2- f.Q,B_ALL RA01010D.ly.[i. TRlTIUM AND FOR ALL RADIOACTIVE ' r]. MATERIALS IN PARTICULATE FORM WITH HALF LIVES GREATER .V THAN EIGHT-DA_YS: (Continued)
Q, - measured or calculated release rate of radionuclide, i, for either continuous or batch gaseous' effluents, pCi/see Pu - dose parameter for radionuclide, i, for pathway, k, from Table 2-5 for the inhalation psthway in mrem /yr per pCi/m . The dose factors are based on the critical 3 individual organ and the child age group. . 9, - highest calculated annual average dispersion parameter for estimating the dose to an individual at or beyond the unrestricted area boundary for pathway k.
- (T/Q), 4.8E-6 sec/m3 for the inhalation pathway. The location is the unrestricted area in the NW sector.
- (R),4.3E8m'3 for the food and ground plane pathways. The location is the unrestricted area in the E sector.
O) !O 1 \.J L' S023-00CM l 2-28 Revision 22 l 08-02-90 l l t
,. ~ ~ . - - _ .- - - ... --. . . . . . . . . . . . . . ,
.. ,' u
- 2.0 GASE0US EFFLUENTS (Continued) 4 2.8 --Gaseous Effluent, Dose ~ Calculation O 2.8.1 :00SE FROM NOBLE GASE.S IN_ GASEOUS EFFLUENTS ,
The gaseous releases considered in the following dose calculations are described in Section 2.6. The air dose in unrestricted areas due to noble gases released in gaseous effluents is calculated using the following expressions: , 4 2.8.1.1 For historica1'meteoroloav: 4
.. (2-14)
D, = 3;17x10 E, H, (T/Q)Q, 4 (2 15) 0, = 3.17x10 I, N, (T/U)Q,
.- where :
D, - total gamma air dose from gaseous effluents, mrad total-beta air dose from gaseous effluents, mrad D, . = 3.17x10-e = inverse seconds per year
. M, - air dose _ factor due to gamma emissions from Table 2 4 for each identified noble gas radionuclide, i, in mrad /yrperpCi/m Ni= air dose due to beta emissions from Table 2-4-for each identified noble gas ~ radiontclide, i, in mrad /yr per pCi/m 4
'o .
' 5023-00CM 2-29 Revision 22 08-02-90
.) .
*<b,,- yr %'n; . - - + , . . , , . .#r. s. E ., ,, , ,o m , - - -
?,, 0 GA$E005 EFFLUENTS (Cr,tinued) 2.8.1.] For historical meteorology: (Continued)
(X7Q) - 4.8E-3 sec/m3. The maxintum annual average atmospheric dispersion factor for any sector or distance at or beyond the unrestricted area boundary, Q, - amount of noble gas radionuclide, i, released in gaseous effluents: uti. 2.8.1.2 For meteorolooy concurrent with release: NOTE: Consistent with the methodology provided in Regulatory Guide 1.109 and the following equations, RRRGS (Radioactive Release Report Generating System) software is used to perform the actual calculaticos.
, (2 16)
D,, = 1.14x10" E, H, E,(ot, (X/0)3 g
,. (2-17)
D, = 1.14 x10" E, N, E,( At, (X/Q), g , A where: D,, - totai gamma air dose from gaseous effluents in sector e, mrad D3 - total beta air dose from gaseous effluents in sector e, mrad 1.14x10" - inverse hours / year Mi - air dose factor due to gamma emissions from Table 2-4 for each identified noble gas radionuclide, i, in mrad /yr per pCi/m 3 [0
%J 5023-00CM 2-30 Revision 22 08-02-90 l
_- __ _ _ . _ ~ - . _ - . _ . _ _ . . _ . _ _ _ P
-- 2.0c EA5[005 EFFLUENT $' (Continued).
2.8'l.2 For meteoroloav concurrent with release: (Continued) N = ' -air dose factor due to beta emissions from ' Table 2 4 for_each identified-noble gas radionuclide 1, in mrad /yr per pCi/m 3 At j = Tieng}h of' the -j" time period over which -(X/Q)3 and Qy are averaged for gaseous releases in hours , (X/Q)3
= atmospheric dispersion factor for tir.o_ period At 3 at exclusion bounda;y loution in sector e 3 ~
determined by concurrent meteorology, sec/m > _Qy = average release rate of radionuclide, i, in gaseous effluents during time period, Atf, pCi/ set 2.8.2' DO$E FROM TRITIUM.-RADIOI0 DINES AND RADIOACTIVE ,
- MATERIALS IN PARTICULATE FORM WITH HALF LIVES GdtsIER THAN 8 DAYS IN GASEOUS EFFLUENTS The dost to an individual _ from tritium, radiciodines and t 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:
i' 2.8.2.1 For' historical meteoroloov: (2-18)
- D, = 3.17x10* K f( R,,W,)Q, f
^
5023-0DCM 2-31 Revision 21 02-15-90 9m s.
.v. ,e S ,- , l o.,-, r ,e ~d,,v-,w,-- -, L , w. ,, r -- ,,-r- , , - -- ~ , ~ ~. - ----.-- - --- , + w - - -
2.0 $15_E09jLiff_U!ENIS (Continued) 2.8.2.1 For historical _ggteoroloav: (Continued) C\ i) where: D, = total projected dose from gaseous effluents to an individual, mrem Qi
= amount of each radionuclide, i, (tritium, ridiciodine, radioactive material in particulate form with half lives greater than eight days),
released in gaseous effluents, pCi 2,RnW, - sum of all pathways, k, for radionuclide, i, of the R, W product, in mrem /yr per pCi/sec. The I RuW , value for each radionuclide, i, is given in Table 2-6. The value given is the maximum Ig RuW, for all locations and is based on the most restrictivt age groups. Rn - dose factor for each identified radionuclide, i, forpathwayk,(fprtheinhalationpathwayin mrer/yr per pCi/m and for the food and ground plane ptthways in m'-mrem /yr per pCi/sec), at the controlling location. The Ra's for each controlling location for each age group are given in Tables 2-7 thru 2-16. Data in these tables are derived using the NRC code, PARTS. (See ('~') i, , s
" Submittal of 1990 00CM Dose Parameters for SONGS 1, 2, and 3" from E. S. Medling to P. H.
Penseyrcs, dated 1/29/91). i l l tO O S023-0DCM 2-32 Revision 23 02-28-91
. - _ . .- - . - . - - . ..... - .- . ....-.-.~. -.. -c -.- . - ~ . . .- . .-
2.0 GASEOUS _EFFLUETS-(Continued) 2.8.2.1 For historical meteoroloov: (Continued) W, = annual average dispersion parameter ft, estimating the dose to an individual at the controlling location for pathway k.
= (T/Q)_f.or the~ inhalation pathway in- sec/m3 .
The.(X/Q) for-each controlling location is given in Tables 2-7 thru 2-16. . = (D/6)forthe_fg.pdandgroundplanepathways in m',. The (D/Q)-for each controlling location-are given in Tables 2-7 thru 2-16. - l 2.8.2.2 For meteoroloov concurrent with releasn: NOTE: Consistent with the methodology provided in Regulatory , Guide 1.109 and the following equations, RRRGS (Radioactive Release Report Generating System) software-is used to perform the actual calculations. Imn e (2 19)- r, D, = 1.14 x 10" IEE ( At3 )(R,,)(Wg)g% ' ijk .
?where:
D.-
= -total annual- dose from gaseous effluents to an in sector e, mrem.
At 3- length of the j" period over which W3a and Qy are averaged for gaseous released,: hours
. Qg - average release rate of radionuclide, i, in-gaseous effluents during time period At), pCi/sec b
i i-i I i-t- LO S023-00CM 2-33 Revision 22 08-22-90 c . l l
._u 1 _ , p. -
3 , - . . . - . .
2.0 GASEOUS JEELUENTS (Continued) 2.8.2.2 For meteoroloav concurrent with releases: (Continued) Rn, a dose factor for each identified radionuclide i, for pathway k for sector 3 e (for the inhalation pathway in mrem /yr per pCi/m and for the food and ground plane
, pathways in m 8 mrem /yr per pCi/sec) at the controlling location. A listing of Rn for the controlling locations in each landward sector for each group is given in Tablet 2 7 thru 2-16. The e is determined by the concurrent meteorology.
W~ u, - dispersion parameter for the time period Atj for each pathway k for calculating the dose to an individual at the controlling location in sector e using concurrent meteorological conditions.
- (X/Q) for the inhalation pathway, sec/m3
- (IT/Q) for the food and ground plane pathways, m 2
.(
S023-0DCM 2-34 Revision 21 02-15-90
^
TABLE 2 ,4 DOSE FACTORS FOR NOBLE GASES 1.HD DAUGFTERS** O v Total Body Dose Skin Dose Gamma Air Dose Beta Air Dose Factor K, Factor L, Factor M, Factor N, Radio- (mrem /yr (mrem /yr (mrad /yr (mrad /yr Nuclide per pCi/m3 ) per pti/m 3) per pCi/m3 ) per pCi/m3) Kr-85m 1.17E+3 1.46E+3 1.23E+3 1.97E+3 Kr 85 1.61E+1 1.34E+3 1.72E+1 1.95E+3 Kr-87 5.92E+3 9.71E+3 6.17E+3 1.03E+4 Kr-88 1.47E+4 2.37E+3 1.52E+4 2.93E+3 Xe-131m 9.15E+1 4.76E+2 , 1.56E+2 1.11E+3 Xe 133m 2.51E+2 9.94E+2 3.27E+2 1.48E+3 Xe-133 2.94E+2 3.06E+2 3.53E+2 1.05E+3 Xe-135m -3.12E+3 7.llE+2 3.36E+3 7.39E+2 Xe-135 1.81E+3 1.86E+3 1.92E+3 2.46E+3 g Xe-138 8.83E+3 4.13E+3 9.21E+3 4.75E+3 Ar-41 8.D4E+3 2.69E+3 9.30E+3 3.28E+3 I
** Source: USNRC Reg. Guide 1.109, Table 8-1 O
V S023-00CM 2-35 Revision 21 02-15-90
TABLE 2-5 DOSE PARAMETER Pu* t CHILD AGE GROUP CRITICAL ORGMi , Radionuclide InhalationPathwaz (mrem /yr per pCi/m ) Radionuclide inhalation'Pathwaz (mrem /yr per pCi/m ) H-3 1.lE+3 1 -131 1.6E+7 Cr-51 1.7E+4 1 -132 1.9E+5 Mn 54 1.6E+6 1 -133 3.BE+6 Co-57 5.lE+5 1 134 5.lE+4 Co 58 1.1E+6 1 '135 7.9E+5 Co-60 7.1E+6 Cs-134 1.0E46 Sr-89 2.2Et6 Cs-136 1.?E+5 Sr-90 1.0E+8 Cs-137 3.lE+5 Zr-95 2.2E+6 Ba-140 1.7E+6 () Nb-95 6 lE+5 Ce-141 5.4E+5 Ru-103 6.6E+5 Ce-144 1.2E+7 Te-129m 1.8E+6 L
- Source: USNRC NUREG-0133, Section 5.2.1.1 O S023-0DCM 2-36 Revision 23 02-28-91 s., _
, 1 .. _ _ _ . 1_ _ ___ _. _ . -- _ . . - _ - . . . . . _ . . . . .
IM LL L.fi CONTROLLING LOCATION FACTORS i O I RuW, i Radionuclide mrem /yr per pCi/sec Use: H -3 9.62E-4 Q: San Onofre Mobil. Homes Cr-51 0.25E 2 Q: San Onofre Mobil. Homes Mn 54 6.52E+0 Q: San Onofre Mobil. Homes Co 57 1.66E+0 Q: San Onofre Mobil. Homes Co-58 2.33E+0 0: San Onofre Mobil. Homes Co 60 8.56E+1 Q: San Onofre Mobil. Homes Sr 89 4.34E+1 0: SC Ranch (No. Res.) Sr-90 1.82E+3 Q: SC Ranch (No. Res.) g Ir-95 2.90E+0 Q: San Onofre Mobil. Homes Nb-95 6.81E+0 E: Deer Consumer Ru-103 1.nRE+1 E: Deer Consumer Te-129m 5.32E+0 E: Deer Consumer Cs-134 3.36E+1 0: SC Ranch (No. Re:.) Cs-136 6.81E-1 0: San Onofre Mobil.;iomes Cs-137 3.67E+1- Q: San Onofre Mobil. Homes Ba 140 1.56E+0 Q: San Onofre Mobil. Homes Ce-141 5.74E-1 0: SC Ranch (No Res.) Ce-144 1.68E+1 Q: SC Ranch (No. Res.) I -131 1.19E+1 0: San Onofre Mobil. Homes o I -132 1.45E-1 Q: San Onofre Mobil. Homes Q 1.-133 1 -134 2.82E+0 3.94E-2 Q: Q: San Onofre Fobil.Homn San Onofre Mobil. Homes I -135 5.94E-1 Q: San Onofre Mobil.Hous UN ID 3.59E+0 Q: San Onofre Mobil. Homes Footnote: These values to be used in manual calculations are the maximum I,RnW, for all locations based on the most restrictive age group. 5023-00CM 2-37 Revision 25 02-28 92
~W t .) .w% e y% @~W '* e* P W 99 6'Te=* * *FW W 99" "' '*
IMLE 2-7 DOSE PARAMETER R, FOR SECTOR P -A V Page 1 of 2 Pathway Surf Beach 3 Distance 0.4 miles X/Q 1.8E 6 sec/m D/Q 8.2E-9 m infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhaia- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathwty Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 0- 0- 1.2E+1 5.1E+1 9.6E+1 Cr-51 0- 1.8E+2 3.2E+4 8.4E+2 1.5E+5 1.1E+3 3.5E+5 Mn 54 0- 1.6E+4 9.5E+6 8.0E+4 4.5E+7 1.lE+5 1.lE+8 Co-57 5.3E+3 2.4E+6 2.4E+4 1.1E+7 2.eE+4 2.6E+7 Co-58 0- 1.2E+4 2.6E+6 5.4E+4 1.2E+7 7.lE+4 2.9E+7 Co-60 0- -0 7.3F+4 1.5E+8 3.5E+5 7.0E+8 4.5E+5 1.6E+9 Sr 89 0- 2.2E+4 1.5E+2 9.7E+4 7.lE+2 1.lE+5 1.6E+3 n Sr 90 0- 1.lE+6 4.4E+6 7.5E+6 B Zr-95 2.3E+4 1.7E+6 1.1E+5 8.2E+6 1.3E+5 1.9E+7 Nb-95 6.4E+3 9.4E+5 3.0E+4 4.5E+6 3.8E+4 1.0E+7 Ru-103 6.9E+3 7.5E,5 3.2E+4 3.6Et6 , 3.8E+4 8.3E+6 te-129m 1.8E+4 1.4E+5 8.0E+4 6.4E+5 8.8E,4 1.5E+6 Cs-134 1.lE+4 4.7E+7 4.5E+4 2.2E+8 5.5E+4 5.2E+8 Cs-136 1.8E+1 1.0E+6 7.8E+3 4.9E+6 1.lE+4 1.lE+7 O Cs-137 9.4E+3 7.lE+7 3.4E+4 3.4E+8 4.7E+4 7.8E+8
'V Ba-140 1.8E+4 1.4E+5 8.2E+4 6.7E+5 9.7E+4 1.6E+6 Ce-141 5.7E+3 9.4E+4 2.5E+4 4.5E+5 2.8E+4 1.0E+6 Ce-144 - 1.2E+5 4.8E+5 5.4E+5 2.3E+6 5.9E+5 5.3E+6 I -131 1.7E+5 1.2E+5 5.9E+5 5.6E+5 9.lE+5 1.3E+6 I -132 2.0E+3 8.5E+3 6.1E+3 4.lE+4 8.7E+3 9.4E+4 1 -133 4.0E+4 1.7E+4 1.2E+5 8.0E+4 1 6E+5 1.9E+5 I -134 0- 5.3E+2 3.lE+3 1.6E+3 1.5F+4 2.3E+3 3.4E+4 I -135 0- 40- S.2E+3 1.7E+4 2.5E+4 8.2E+4 3.4E+4 1.9E+5 UN ID 1.0E+4 5.1E+6 5.0E+4 2.4E+7 6.6E+4 5.7E+7 Inhalation Pathway, units " "
4 "C / Food & Ground Pathway, units I* " " Ci/se O S023-00CM 2-38 Revision 25 02-28-92
TABLE 2-1 DOSE PARAMETER Ri FOR SECTOR P Page 2 of 2 (~T V Pathway - Former Nixon Estate (no garden) Distance - 2.8 miles X/0 - 1.2E-7 sec/m' D/0 3.4E 10 m Infant Child Teen Adult .
'nhala- Food & Inhala- Food & Inhala- Food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 0- 1.lE+3 L3E+3 1.3E+3 Cr 51 1.3E+4 4./E+6 1.7E+4 4.7E+6 E.lE+4 4.7E+6 1.4E+4 4.7E+6 Mn 54 1.0E+6 1.4E,9 1.6E+6 1.4E+9 2.0E,6 1.4E+9 1.4E+6 1.4E,9 Co-57 3.8E+5 3.4E+8 5.lE+5 3.4E+8 5.9E+5 3.4E+8 3.7Ev5 3.4E+8 Co 58 7.8E+5 3.8E+8 1.lE+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 Ca 60 4.5E+6 2.2E+10 7.lE+6 2.2E+10 8,7E+6 2.2E+10 6.0E+6 2.2E+10 Sr 89 2.0E+6 2.2E44 2.2E+6 2.2E+4 2.4E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 4.lE+7 1.0E+8 0- 1.lE+8 9.9E+7 Zr-95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E,6 2.5E+8 1,8E+6 2.5E+8 : Nb-95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E,5 1.4E+8 5.0E+5 1.4E+8 Ru-103 5.5E+5 1.lE+8 6.6E+5 1.lE+8 7.8E+5 1.lE+8 5.0E+5 1.1E+8 Te.129m 1.7E+6 2.0E+7 1.8E+6 2.0E-7 2.0E-6 2.0E+7 1.2E+6 2.0E,7 Cs-134 7.0E,5 6.8E+9 1.0E+6 6.8E+9 1.lE+6 6.8E+9 8.5E+5 6.8E+9 Cs 136 1.3E+5 1.5E+8 1.7E+5 1.5E+8 1.9E+5 1.5E+8 1.5E+5 1.5E+8 Cs-137 6.lE+5 1.0E+10 9.lE+5 1.0E+10 8.5E+5 1.0E+10 6.2E+5 1.0E+10 g Ba 140 1.6E+6 2.1E+7 1.7E+6 2.lE+7 2.0E+6 2.lE+7 1.3E+6 2.1E+7 g Ce-141 Ce-144 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.lE+5 1.4E+7 3.6E+5 1.4E+7 J.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 1 -131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 1 -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.lE+5 1.2E+6 1 -133 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4EM l'-134 4.5E+4 4.5E+5 5.lE+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5EJ l -135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN-ID 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 inhaiation Pathway " nits = *C / V Food & Ground Pathway, units I* II*"'*g'c "I ggj3
'O Q
S023-0DCM 2-39 Revision 23 02 28-91
TABLE 2-8 DOSE PARMETER R FOR SECTOR Q Pace 1 of 10 X./ Pathway = Enlisted Bch Trailers Distance - 1.1 milesd 3 X/Q = 9.3E-7 sec/m D/0 - 4.6E 9 m Infant . Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhal a- Food & Radio-- tion Ground tion Ground tion Gro'*d tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pa ti...ay Pathway Pathway H -3 0- 6.3E+2 Cr-51 0- 0- 0- 7.2E+3 2.3E+6 Mn 54 0- 0- 0- 0- 7.0E+5 6.9E+8 Co 57 0- 1.8E+5 1. 7 E+ 8
, co 58 0- 0- 0- 4.6E+5 1.9E+8
;.i 9 0 -0 '0- 3.0E+6 1.lE+10
.Y e 0- 0- -0 7.0E+5 1.lE+4 3r J s 0- 0- 5.0E+7 er-95 0- 8.8E+5 1.3E+8 4
- 40 95 0- 0- 0- 0- 2.5Et5 6.8:+7 Ru-103 0- 0- 2.5E+5 5.4E+7 Te-129m 0- 0- 0- 5.8E+5 9.8E+6 Cs-lM 0- 4.2E+5 3.4E+9 Cs-136 -0 7.3E+4 7.5E+7 Cs-137 0- 3.lE+5 5.lE+9 Ba-140 0- 0- 0- 6.4E+5 1.0E+7 Ce 141 0- 1.8E+5 6.8E+6 Ce-144 0- 3.9E+6 3.5E+7 I -131 0- 0- 6.0E+6 8.6E+6 I -132 5.7E+4 6.2E+5 I -133 0- 0- 0- 1.lE+6 1.2E+6 I -134 1.5E+4 2.2E+5 I -135 0- 0- 2.2E+5 1.3E+6 UN-ID 4.3E+5 3.7E+8 InhalationPathway, units-yj"(7" I* "I Tood & Ground Pathway, units "$*,
j LO l S023-0DCM 2-40 Revision 23 02-28-91
_. ~ _ _ . _ . - - _ - ._ . _. _ _ _ . . TABLE 2-8 DOSE PARAMETER R, FOR SECTOR Q Page 2 of 10 V Pathway - San Onofre Mobil Homes Distante - 1.3 miles X/Q - 7.4E-7 sec/m D/Q = 3.6E-9 m Infant Child Teen . Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food-& Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 6.5E+2 1.lE+3 0- 1.3E+3 1.3E+3 { Cr 51 1.3E+4 4.7E+6 1.7E+4 4.7E+6 2.lE+4 4.7E+6 1.4E+4 4.7E+6 l Mn 54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 2.0E46 1.4E+o 1.4E+6 1.4E+9 ; Co-57 3.8E+5 3.4E+8 5.lE+5 3.4E+8 5.9E+5 3.4Et6 3.7E+5 3.4E+8 ! Co 58 7.8E+5 3.8E+8 1.lE+6 3.8E+8 1.3E+6 3.8E+8 9.3E+5 3.8E+8 i Co 60' 4.5E+6 2.2E+101 7.lE+6 2.2E+10 8.7E+6 2.2E+10 6.0E+6 2.2E+10 Sr 89 2.0E+6 2.2E+4 ' 2.2E+6 2.2E+4 2.'4 E+6 2.2E+4 1.4E+6 2.2E+4 Sr-90 4.lE+7 1.0E+8 0- 1.1E+8 9.9E+7 Zr 95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+8 1.8E+6 2.5E+8 Nb 95 4.8E+5 1.4E+8 6.1E+5 1.4E+8 7.5E+b 1.4E+8 5.0E+5 1.4E+8 l Ru 103 5.5E+5 1.lE+8 6.6E45 1.lE+8 7.8E+5 1.lE+8 5.0E+5 1.lE+8 Te 129m 1.7E+6 2.0E+7 1.8E+6 2.0E+7 2.0E+6 2.0E+7 1.2E+6 2.0E+7 Cs-134 7.0E+5 6.8E+9 1.0E+6 6.8E+9 1.lE+6 6.8E+9 8,5E+5 6.BE+9 Cs-136 1.3E+5 1.5E+8 1.7E+5 1.5E+0 1.9E+5 1.5E+8 1.5E+5 1.5E+8 Cs-137- 6.lE+5 1.0E+10 9.lE45 1.0E+10 8.5E+5 1.0E+10 6.2E+5 1.0E+10 Ba 140 1.6E+6 2.lE+7 1.7E+6 2.lE+7 2.0E+6 2.lE+7 Ce-141 1.3E+6 2.lE+7 5.2E+5 1.4E+7 5.4E+5 1.4E+7 6.lE+5 1.4E+7 3.6E+5 1.4E+7 Ce-144 9.8E+6 7.0E+7 1.2E+7 7.0E+7 1.3E+7 7.0E+7 7.8E+6 7.0E+7 I el31 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.lE+5 I -133 1.2E+6 3.6E+6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 1 -134 2.4E+6 4.5E+4 4.5E+5 5.lE+4 4.5E+5 4.0E+4 4.5E+5 I -135 3.0E+4 4.5E+5 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 UN ID 4.5E+5 2.5E+6 6.5E+5 7.5E+8 1.0E+6 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 inhalation Pathway, units = 7" j Food & Ground Pathway, units I* II'#'*/VII pCi/sec O S023-00CH 2-41 Revision 23 02-28-91 _ .~ _ _
TABLE 2-8
~
DOSE PARAMETER Ri FOR SECTOR Q q Pace 3 of 10 b/ Pathway-StateParkOfficeTrailer Distance - 0.6 milesd X/Q = 2.2E-6 sec/m D/0 - 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 0- 5.8E+1 0-Cr 51 0- 0- 0- d.6E+2 2.lE+5 Mn 54 0- 0- 6.4E+4 6.3E+7 Co-57 0- 0- 0- 1.7E+4 1.6E+7 Co 58 -0 4.2E+4 1.7E+7 Co-60 :0- 2.7E+5 9.8E+8 Sr-89 6.4E+4 9.9E+2 Sr 90 0- 4.5E+6 0-Zr-95 0- 8.1E+4 1.1E+7 Hb 95 0- 0- 0- 2.3E+4 6.2E+6 Ru-103 0- 2.3E+4 5.0E+6 Te-129m 0- 0- 5.3E+4 9.0E+5 Cs-134 -0 3.9E+4 3.1E+8 Cs-136 6.7E+3 6.9E+6 Cs 137 2.8E+4 4.7E+8
^ Ba-140 5.8E+4 9.4E+5 i
Ce-141 0- 0- 1.7E+4 5.2E+5 Ce-144 0- 3.6E+5 3.2E+6 I -131 0- 0- 5.4E+5 7.9E+5 I 132 0- 0- 5.2E+3 5.7E+4 I -133 9.8E+4 1.lE+5 1 -134 1.4E+3 2.1E+4 1 -135 2.0E+4 1.2E+5 UN-ID 0- 3.9E+4 3.4E+7 Inhalation Pathway, units
*C /
Food & Ground Pathway, units IS " Ci/ ec O S023-00CM l 2-42 Revision 23 02-28 91
TABLE 2-8 DOSE PARAMETER R, FOR SECTOR Q Page 4 of-10 Pathway Surf. Beach i Distance = 0.7 miles X/Q = 1.8E 06 sec/m 0/Q 9.9E-09 m'2 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 0- 1.2E+1 5.lE+1 - 2.2E+2 0-Cr-51 0- 1.8E+2 3.2E+4 8.4E+2 1.5E+5 2.5E+3 8.0E+5 Mn 54 .l.6E+4 9.5E+6 8.0E+4 4.5E+7 2.4E+5 2.4E+8
-Co-57 - 5.3E+3 2.4E+6 2.4E+4 1.lE+7 6.3E+4 5.9E+7-Co 58 -0 0- 1.2E+4 2.6E+6 5.4E+4 1.2E+7 1.6E+5 6.5E+7 Co-60 Sr-89 0-7.3E+4 2.2E+4 1.5E+8 1.5E+2 3JE+5 9.7E+4 7.0E+8 7.lE+2 1.0E+6 2.4E+5 3.7E+9 3.7E+3 M
Sr-90 0- 0- 1.lE+6 0- 4.4E+6 0- 1.7E+7 Zr-95 0- 2.3E+4 1.7E+6 1.1E+5 8.2E+6 3.0E+5 4.3E+7 Nb-95 E.4E+3 9.4E+5 3.0E+4 4.5E+6 8.6E+4 2.3E+7 Ru-103 6.9E+3- 7.5E+5 3.2E+4 3.6E+6 8.6E+4 1.9E+7 Te 129m 1.8E+4 1.4E+5 8.0E+4 6.4E+5 2.0E+5 3.4E+6 Cs-134 1.lE+4 4.7E+7- 4.5E+4 2,2E+8 1.5E+5 1.2E+9 Cs-136 .l.8E+3 1.0E+6 7.8E+3 4.9E+6 2.5E+4 2.6E+7 Cs-137 9.4E+3 7.lE+7 3.4E+4 3.4E+8 1.1E+5 1.8E+9 0- O Ba-140 Ce-141 Ce-144 1.BE+4 5.7E+3 1.2E+5 1.4E+5 9.4E+4 4.8E+5 8.2E+4 2.5E+4 5.4E+5 6.7E+5 4.5E+5 2.3E+6 2.2E+5 6.2E+4 1.3E+6 3.5E+6 2.3E+6 1.2E+7 I -131 1.7E+5 1.2E+5 5.9E+5 5.6E+5 2.0E+6 2.9E+6 I -132 2.0E+3 8.5E+3 6.1E+3 4.1E+4 2.0E+4 2.lE+5 1 -133 4.0E+4 1.7E+4 1.2E+5 8.0E+4 3.7E+5 4.2E+5 I -134 5.3E+2 -3.1E+3 1.6E+3 1.5E+4 5.lE+3 7.7E+4 I -135 8.2E+3 1.7E+4 2.5E+4 8.2E+4 7.7E+4 4.3E+5
.UN-ID 0- 1.0E+4 5.lE+6 5.0E+4 2.4E+7 1.5E+5 1.3E+8 l
Inhalation Pathway, units *]j"(!" , Food & Grouno_ Pathway, units I* IImrem/vri C o S023-00CM 2-43 Revision 25 02 28-92 w -,_ _ ,-- - . - - - . = - -. - - -- --
4 IfBLE 2-8 DOSE PARAMETER R, FOR SECTOR Q Page 5 of 10 V Pathway'- Enlisted Beach Distance 1.1 miles X/Q = 9.3E 07 sec/m D/0 - 4.6E-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 H3 1.2E*1 5,1E+1 0- 1.3E+2
- Cr 51 1.8E+2 3.2E+4 8.4E+2 1.5E+5 1.5E+3 4.7E+5 Mn-54 1.6E+4 9.5E+6 8.0E+4 4.5E+7 1.4E+5 1.4E+8 Co 57 5.3E+3 2.4E+6 2.4E+4 1.1E+7 3.7E+4 3.5E+7 Co 58 1.2E+4 2.6E+6 5.4E+4 1.2E+7 9.4E+4 3.9E+7 Co 60 7,3E+4 1.5E+8 3.5E+5 7.0E+8 6.lE+5 2.2E+9 Sr 89 2.2E+4 1.5E+2 9.7E+4 7.lE+2 1.4E+5 2.2E+3 Sr 90 0- 1.lE+6 4.4E+6 1.0E+7 -0 Zr 95 0- 2.3E+4 1.7E+6 1.lE+5 8.2E+6 1.8E+5 2.5E+7 Nb 95- 6.4E+3 9.4E+5 3.0E+4 4.5E+6 5.lE+4 1.4E+7 A Ru 103 Te 129m 0-6.9E+3 1.8E+4 7.5E+5 1.4E+5 3.2E+4 8.0E+4 3.6E+6 6.4E+5 5.lE+4 1.lE+7 fi 1.2E+5 2.0E+6 Cs-134 0- 1.1E+4 4.7E+7 4.5E+4 2.2E+8 8.6E+4 6.9E+8 Cs-136 1.8E+3 1.0E+6 7.BE+3 4.9E+6 1.5E+4 1.5E+7 Cs 137 0- 9.4E+3 7.lE+7 3.4E+4 3.4E+8 6.3E+4 1.0E+9 Ba-140 1.8E+4 1.4E+5 8.2E+4 6.7E+5 1.3E+5 2.lE+6 Ce 141 0- 5.7E+3 9.4E+4 2.5E+4 4.5E+5 3.7E+4 1.4E+6 l Ce-144 1.2E+5 4.8E+5 5.4E+5 2.3E+6 7.9E+5 7.lE+6 l 1 -131 1.7E+5 1.2E+5 5.9E+5 5.6E+5 1.2E+6 1.7E+6
- I -132 2.0E+3 8.5E+3 6.1E+3 4.lE+4 1.2E+4 1.3E+5 1 -133 4.0E+4 1.7E+4 1.2E+5 8.0E+4 2.2E+5 2 C45 I -134 5.3E+2 3.lE+3 -1.6E+3 1.5E+4 3.0E+3 4.6E+4 I -135 8.2E+3 1.7E+4 2.5E+4 8.2E+4 '4.5E+4 2.6E+5 UN-10 1.0E+4 5.lE+6 5.0E+4 2.4E+7 8.8E+4 7.6E+7 Inhalation Pathway, units - g j !"
Food & Ground Pathway, units - " " Ci/sec O SO23-0DCM 2-44 Revision 25 02-28-92
Ifl8LE 2-8 005E PARAMETER R, FOR SECTOR Q Pace 6 of 10 Pathway Enlisted Beach Check.In Distance = 1.4 miles X/Q = 6.8E 7 sec/m' D/Q = 3.2E-9 m inf6nt Child Teen Adult Inhala- Food & Inhala- Food & Inhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclida Pathway Pathway Pathway Path,iy Pathway Pathway Pathway Pathway H -3 0 '2.9E+2 0-Cr 51 0- 0- 3.3E+3 1.1E+6 Hn-54 -0 0- 0- 3.2E+5 3.2E+8 Co-57 0- 0- B.4E+4 7.0E+7 Co.58 0- 0- 2.lE+5 8.7f+7 Co 60 0- 1.4E+6 4.9E+9 Sr-89 ~0- '0-
- 3.2E+5 4.9E+3 Sr-90 0- 0- 0- 2.3E+7 0-Zr-95 0- 0- 0- 4.0E+5 5.7E*7 Nb 95 0- 0- 0- 0- 0- 1.2E+5 3.lE+7 Ru-103 0- 0- 0- 1.2E+5 2.5E+7 Te-129m 0- 0- 0- 0- 0- 2.5E+5 4.5E-6 Cs 134 0- 0- 0- 1.9E+5 1.6E+9 Cs-136 0- 3.3E+4 3.4E+7 Cs-137 0- 1.4E+5 2.3E+9 Ba-140 2.9E+5 4.7E+6 Ce-141 0- -0 8.3E+4 3.lE+6 \ -
Ce-144 0- 0- 1.8E+6 1.6E+7 l I -131 0- 0- 2.7E+6 3.9E+6 l I -132 0- 2.6E+4 2.8E+5 I -133 4.9E+5 5.6E+5 1 -134 6.8E+3 1.0E+5 I -135 0- 1.0E+5 5.8E+5 UN-ID 0- 2.0E+5 1.7E+8 InhalationPathway, units =}}j"(7" Food & Ground Pathway, units - (m mremhr) pC1/sec l O 5023-0DCM i 2-45 Revision 23 02-28-91
4 TABLE 2-8 00SE PWetAMETER R, FOR SECTOR Q A _ Page 7 of 10 Pathway Sheep (Meat)3 Distance = 1.6 miles X/0 5.6E 7 sec/m D/0 - 2.6E-9 m Infant Child Teen Adul t Inhala- Food & Inhala- Food & Inhala. Tood & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway hthway Pathway Pathway H -3 0- 1.5E+0 1.2E+0 7.0E+0 2.lE+0 Cr-51 0- 5.1E+1 1.0E+2 7.9E+1 2.6E+4 Mn-54 0- 0 7.8E+2 1.4E+3 7.7E+3 ' 6E+6 Co-57 4.7E+3 0- 8.lE+3 2.0E+3 1.9E+6 Co-58 0- 20- 0- 9.7E+3 0- 2.0E+4 5.lE+3 2.lE+6 Co 60 0- 3.7E+4 ,0 - 7.3E+4 3.3E+4 1.2E+8 Sr 89 5.0E+4 0- 2.6E+4 7.7E+3 3.lE+4 Sr-90 0- 0- 1.0E+6 0- 8 lE+5 5.5E+5 1.3E+6 Zr 95 -0 6.3E+4 0- 1.1E+5 9.7E+3 1.6E+6 Nb 95 0- 2.4E+5 0- 4.5E+5 2.8E+3 1.6E+6 Ru 103 0- 4.2E+5 0- 7.6E+5 2.8E+3 1.9E+6 Te-129m 0- 6.0E+5 0- 4.5E+5 6.4E+3 7.6E-5 Cs 134 . 1.4E+5 0- 1.2E+E 4.7E+3 3.8E+7 Cs-136 0- - 5.lE+3 4.3E+3 8.lE+2 8.3E+5 Cs-137 0- 0- 1.3E+5 -0 9.5E+4 3.4E+3 5.7E+7 Ba-140 5.1E+3 4.3E+3 7.0E+3 1.2E+5 (( Ce-141 Ce-144 0-1.5E+3 1.8E+4 2.4E+3 3.0E+4 2.0E+3 4.3E+4 7.9E+4 4.3E+5 I -131 -0 0- 6.6E+5 4.4E+5 6.6E+4 7.0E+5 I -132 0- 6.3E+2 6.8E+3 1 -133 1.6E-2 0- 8.7E-3 1.2E+4 1.3E+4 1'-134 0- 1.6E+2 2.5E+3 I -135 1.lE-18 6.4E-19 2.5E+3 1.4E+4 UN-ID 0- 1.lEt5 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units = ]j*[ I* ' Food & Ground Pathway, units C[/sje (b - 5023-0DCM 2-46 Revision 23 02-28 91
4 TABLE 2-8 00SE PARAMETER R, FOR SECTOR Q x Pathway - S. C. Res W Garden 3 Distance - 4.1 miles X/Q 1.2E 07 sec/m D/0 - 4.lE-10 m Infant Child Teen Adult Inhala- ' Food & Inhala- food & Inhala- Food & Inhala- l Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathwi.y H -3 6.5E+2 1 lE+3 3.8E+3 1.3E+3 2.4E+3 1.3E+3 1.9E+3 Cr-51 1.3E+4 4.7E+6 1.7E+4 9.4E+6 2.lE+4 1.2E+7 1.4E44 1.1E+7 Mn-54 1.0E+6 1.4E+9 1.6E+6 2.0E+9 2.0E+6 2.2E+9 1.4E+6 2.2E+9 Co 57 3.8E+5 3.4E+8 5.lE+5 5.6E+8 5.9E+5 6.3E+8 3.7E+5 5.8E+8 Co-58 7.8E+5 3.8E+8 1.lE+6 7.lE+8 1.3E+6 8.9E+8 9.3E+5 8.5E+8 Co-60 4.5E+6 2.2E+10 7 lE+6 2.3E+10 8.7E+6 2.4E+10 6.0E+6 2.4E+10 Sr-69 2.0E+6 2.2E+4 2.2E+6 3.lE+10 2.4E+6 1.2E+10 1.4E+6 7.2E+9 Sr 90 4.1E+7 1.0E+8 1.3E+12 1.lE+8 7.7E+11 9.9E+7 5.8E+11 Ir-95 1.8E+6 2.5E+8 2.2E+6 1.0E+9 2.7E+6 1.3E+9 1.8E+6 1.2E+9 N'o-95 4.8E+5 1.4E+8 6.lE+5 3.8E+8 7.5E+5 4.9E+8 5.0E+5 4.5E+8 Ru-103 5.5E+5 1.lE+8 6.6E+5 4.4E+8 7.8E+5 5.6E+8 5.0E+5 4.9E+8 Te-129m 1.7E+5 2.0E-7 1.8E-5 2.4E+9 2.0E+6 1.4E+9 1.2E+6 9.7E+8 Cs 134 7.0E+5 6.8E+9 1.0E+6 3.lE+10 1.lE+6 2.2E+10 8.CE+5 1.6E+10 Cs-136 1.3E+5 1.5E+8 1.7E+5 2.4E+8 1.9E+5 2.lE+8 - 1.5E+5 1.9E48 Cs-137 6.1E+5 1.0E+10 9.lE+5 3.4Er10 8.5E+5 2.3E+1Cl6.Mt5 1.SE+10 f Ba-140 1.6E+6 2.lE+7 1.7E+6 1.3E+8 2.0E+6 8.8E+7 1.3E+6 7.4E+7 / Ce-141 5.2E+5 1.4E+7 5.4E+5 3.4E+8 6.lE+5 4.2E+8 3.6E+5 3.3E+8 k Ce-144 9.8E+6 7.0E+7 1.2E+7 9.3E+9 1.3E+7 1.2E+10 7.8E+6 9.0E+9 I 131 1.5E+7 1.7E+7 1.6E+7 4 lE+9 1.5E+7 2.1E+9 1.2E+7 1.4E+9 I -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.lE+5 1.2E+6 I -133 3.6E+6 2.4E+6 3.8E46 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 1 -134 4.5E+4 4.5E+5 5.lE+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I 135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN ID 6.5E+5 7.5E+8 1.0E+6 3.3E+9 1.2E+6 2.4E+9 8.6E+5 1.8E+9 Inhalation Pathway, units = j(!" Food & Ground Pathway, units I* " C /se O S023-00CM 2-47 Revision 23 02-28-91
TABLE 2 8 DOSE PARAMETER R i FOR SECTOR Q Page 9 of 10 b Pathway San Clemente3 Ranch (No Residents) Distance = 2.2 milesd 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 0- 3.8E+3 2.4E+3 1.9E+3 Cr 51 4.8E+6 0- 7.4E+6 6.7E+6 Mn 54 0- 0- 6.1E+8 8.3E+8 8.0E+8 Co-57 2.2E+8 2.9E+8 2.4E+8 Co-58 3.3E+8 5.1E+8 4.7E+8 Co 60 2.0E+9 .0 - 3.0E+9 0- 2.7E+9 Sr-89 3.lE+10 1.2E+10 7.2E+9 Sr-90 0- 1.3E+12 0- 7.7E+11 5.8E+11 Ir-95 0- 7.8E+8 1.1E+9 9.lE+8 Nb-95 2.4E+8 3.5E+8 0- 3.lE+8 Ru-103 0- 3.3E+8 0- 4.5E+8 0- 3.8E+8 Te 129m 0- 2.3E,9 1.4E+9 9.5E+8 Cs 134 0- 2.4E+10 0- 1.5E+10 0- 9.2E+9 Cs-136 9.0E+7 5.7E+7 3.6E+7 Cs-137 2.3E+10 0- 1.3E+10 7.8E+9 Ba-140 1. lE+8
- 0- 6.8E+7 0- 5.3E+7
'y' Ce 141 Ce-144 3.3E+8 9.2E+9 4.lE+8 1.2E+10 0-3.2E+8 9.0E+9 I 131 4.1E+9 2.lE+9 1.4E+9 l -132 6.0E-36 2.6E-36 1.7E-36 1 -133 4.0E-11 1.7E-11 1.1E-11 1 134 0- 6.lE-37 0- 2.7E-37 1.7E-37 I -135 7.0E-35 3.1E-35 1.9E 35 UN-ID 2.5E+9 1.7E+9 0- 1.lE+9 Inhalation Pathway, units = *C / ' Food & Ground Pathway, units - I* " " C /sec O" S023 0DCM 2-48 Revision 23 02-28-91
TABLE 2-8 DOSE PARAMETER R, FOR SECTOR Q Pace 10 of l__0 Pathway San Clemente Ranch Adm. Offices 3 Distance 2.5 miles X/Q = 2.7E 7 sec/m D/Q 1.1E 9 m s .- Infant Chil'd 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 H3 0- 0 2.9E+2 1.9E+3 Cr 51 0- 0- 0- 0- 3.3E+3 7.8E+6 Mn-54 0- 0- 3.2E+5 1.1E+9 Co-57 0- 0- -0 8.4E+4 3.2E+8 Co-58 0- 2.lE+5 5.6E+8 Co 60 so- 1.4E+6 7.5E+9 Sr 89 3.2E+5 7.2E+9 Sr-90 0- 0- 0- 2.3E+7 5.8E+11 Zr-95 0- 0- 0 4.0E+5 9.7E+8 Nb 95 0- 0- 0 0- 1.2E+5 3.4E+8 o Ru-103 0- 0- 1.2E+5 4.lE+8 b Te 129m 0 0- 0- 2.6E+5 9.5E+8 Cs-134 0- 1.9E+5 1.1E+10 Cs-136 0- 3.3E+4 7.0E+7 Cs-137 0- 0- 1,4E+5 1.0E+10 p v Ba-140 Ce 141 0-0-
-0 0
2,9E+B 8,3E+4 5.8E+7 3.2E+8 Ce-144 0- 0- 0- 1.8E+6 9.0E+9 I -131 0- ?.7E+6 1.4E+9 I -132 0- 2 GE+4 2.8Et5 1 -133 4.9E,5 5.6E+5 1 -134 0- 6.8E+3 1.0E+5 1 -135- -0 1.0E+5 5.8E+5 UN-ID 0- 2.0E+5 1.2L+9 Inhalation Pathway, units = j(7" Food & Ground rathway, units I* " C see , f) V l S023-0DCM 2-49 Revision 25 02-28-92 l
I
. 1 1&BLE 2 9 DOSE PARAMETER R, FOR SECTOR R I Pace _,l_o,f 5 i Pathway.SanOnofrrMpbileHomes Distance 1.2 miles X/0 5.3E ,7 56c/m D/0 = 3.2E 9 m*' ]
Infant Child Teen Adult i inhala. rood & Inhala- food & Inhala- food & Inhala. Food & Radio
- t. ion Ground tion Ground tion Ground tion Ground Nuclice Pathway Pathway Pathway Pathway Pathway Fathway Pathway Pathway H3 6.5E+2 0- 1.lE+3 0- 1.3E+3 0- 1.3E+3 0 Cr 51 1.3E44 4.7E46 1.7E+4 4.7E+6 2.lE+4 4.7E+6 1.4E+4 4.7E.6 Mn 54 1.0E+6 1.4E+9 1.6E+6 1.4E+9 7.0E+6 1.4E+9 1.4E+6 1.4E+9 '
Co-57 3.8E+5 3.4E+8 5.lE+5 3.4E+8 5.9E+5 3.4E+8 3.7E+5 3.4E+8 Co 58 7.8E+5 3.8E+8 1.lE+6 3 8E+8 1.3E+6 3.8E+3 9.3E+5 3.8E+8 Co 60 a.5E+6 2.2E+10 7.lE+6 2.2E+10 8.7E+6 2.2E410 6.0E+5 2.2E+10 Sr 89 2.0E+6 2.2E+4 2.2E+6 2.2E+4 2/4E+6 2.2E+4 1.4E+6 2.2E+4 Sr 90 4.lE+7 0- 1.0E+8 0- 1.lE+8 0- 9.9E+7 0-Zr 95 1.8E+6 2.5E+8 2.2E+6 2.5E+8 2.7E+6 2.5E+B 1.8E+6 2. 5E< 8 Nb 95 4.8E+5 1.4E+8 6.lE+5 1.4E+8 7.5E+5 1.4E+8 5.0E+5 1.4E+8 Ru 103 5.5E+5 1.1E+8 6.6E+5 1.1E+8 7.8E+5 1.lE+8 5.0E+5 1.lE*8 Te 129m 1.7E+6 2.0E+7 1.SE+6 2.0E+7 2.0Ed 2.C +7 1.2E+6 2.0E 7 7.0E,5 Cs 134 6.8E+9 1.0E46 6.8E+9 1.lE+6 6474 0.5E+5 6.8E+9 Cs.136 1.3E+5 1.5E+8 1.7E+5 1.5E+8 1.9E+E 1. b d 1.5E+5 1.5E+8 Cs 137 6.1E+5 1.0E+10 9.lE+5 1.0E+10 8.5E+5 1.0E+10 6.2E+5 1.0E+10 Ba 140 1.5E+6 2.1E+7 1.7E+6 2.1E+7 2.0E+6 2.lE+7 1.3E+6 2.lE+7 O Ce 141 Ce l+4 5.2E45 9.8E+6 1.4E+7 7.0E+7 5.4E+5 1.2E+7 1.4E+7 7.0E+7 6.lE+5 1.4E+7 1.3E+7 ' 7.0E+7 3.6E+5 7.8E+6 1.4E+7 7.0E+7 1 +131 1.5E+7 1.7E+7 1.6E+7 1.7E+7 1.5E+7 1.7E+7 1.2E+7 1.7E+7 1 -132 1.7E+5 1.2E+6 1.9E+5 1.2E+6 1.5E+5 1.2E+6 1.lE+5 1.2E+6 1 133 3.6EF6 2.4E+6 3.8E+6 2.4E+6 2.9E+6 2.4E+6 2.2E+6 2.4E+6 I 134 4.5E+4 4.5E+5 5.lE+4 4.5E+5 4.0E+4 4.5E+5 3.0E+4 4.5E+5 I 135 7.0E+5 2.5E+6 7.9E+5 2.5E+6 6.2E+5 2.5E+6 4.5E+5 2.5E+6 UN ID 6.5E+5 7.5E+6 1.0E46 7.5E+8 1.2E+6 7.5E+8 8.6E+5 7.5E+8 Inhalation Pathway, units - f$7F , Food & Ground PatMy, units - '* # g(j3[c O S023 0DCM 1-50 Revision 23 02 28 91 9 r- . _ o_...,. - , . . . - ,# m . . , - , - - . - . . , ,
t IAl[E29 i DOSE PAPAMETER R i FOR SECTOR R l Page 2 of 5 O Pathway San Clemente.8 Ranch (No Residents) X/0 = 2.0E 7 sec/m
% ?ance = 2.3 miles D/0 = 1.0E 9 tr' Infant Child Teen Adult Inhala. Food & Inhala- Food & Inhala- food & Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground 1 Nuclide Pathway , Pathway Pathway Pathway Pathway Pathway Pathway Pathway H3 0- ' 0- 0 3.8E+3 2.4E+3 0- 1.9E+3 Cr 51 0 0- 0- 4.8E+6 0- 7.4E+6 0- 5.7E46 Mn 54 0- 0 0- 6.lE+8 8.3E+8 8.0E+8 Co 57 0- 0- 0- 2.2E+8 0- 2.9E+8 2.4E+8 Co 58 0- 0- 3.3E+8 0- 5.lE+8 4.7E+8 Co 60 0 0- 0 2.0E+9 0 3.0E+9 -0 2.7E+9 Sr 89 0- 0- 0- 3.1E+10 0- 1.2E+10 '- 7.2E+9 Sr- 90 0- 0- 0- 1.3E+12 0- 7,7E+11 0- 5.8E+11 Zr 95 0- 0- 0- 7.8b8 0- 1.lE+9 0- 9.lE+8 Nb 95 0- 0- 1 AE+8 0 3.5E+8 0- 3.1Ed8 Ru 103 0- 0- 0- 3.3E+8 4.5E+6 3.8E+8 Te 129m 0- 0- 2.3E+9 0- 1.4E+9 0- 9.5E+8 Cs 134 0- 0- >- 2.4E+10 0- 1.5E+10 0- 9.2E+9 Cs 135 0 9.0E+7 0- 5.7E+7 3.6E+7 Cs 137 0- 0- 2.3E+10 1.3E+10 0- 7.8E+9 Ba 140 0- 0- 0- 1.lE+8 0- 6.8E+7 0- 5.3E+7 O Ce-141 0- 0- 3.3E+8 0 4.lE+8 0- 3.2E+8 Ce 144 0- 0- 0- 9.ZE+9 1.2E+10 9.0E+9 1 131 0- 0- 0- 4.1E+9 0 2.lE+9 0- 1.4E+9 I -132 0- 6.0E 36 0- 2.6E-36 0- 1.7E 36 1 133 0- 0- 4 OE 11 0- 1.7E il 1.lE 11 1 134 +0- 0- 0- 6.lE 37 0- 2.7E-37 0- 1.7E 37 I -135 0- 0- 7.0E 35 3.lE-35 0- 1.9E 35 UN ID 0- 0- 0- 2.5E+9 0- 1.7E+9 0- 1.lE+9 i Inhalation Pathway, units = ]j"(f I" ' Food & Ground Pathway, units Cj/sec O S023 000M 2 !! Revision 23 02 28 91
-- -r --- 9 -, ,~w r.,- r ,.,r- ,c -
--c-, , - - + - - , - .w--- v - -, w +w- T- T rT N---- *-
. i TABLE 2 9 ,
DOSE PARAMETER R i FOR SECTOR R Page 3 of 5 O P athway SC Ranch Packing .'
. stance =8.2E-10 0/0 2.6 miles m* '
X/Q = 1.7E 07 sec/m infant Child Teen Adult Inhala- Food & Inhala- Food & Inhala. Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tien Ground t Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H3 0- 0- 0- 0 - 0 - 0- 4.3E+2 1.9E+3 Cr 51 0- 0- 0- - 0- - 0- 4.9E+3 8.3E+6 Mn 54 0- 0 0- - 0 - 0- 4.8E+5 1.3E+9 Co-57 - 0 0 0- 0- - 0 0- 1.3E+5 3.6E+8 Co 58 0 0 0- - 0 0- 3.2E+5 6.0E+8 Co 60 0- 0- 0- - 0 0- 2.0E+6 ).fE+10 Sr 89 0 0- 0- - 0- 0- 4.8E+5 7.2E+9 L Sr 90 - 0- 0 0- 0- - 0- 0- 3.4E+7 5.8E+11 Zr it5 - 4 0- 0- 0- - 0 0- 6.lE+5 9.9E+8 . Nb.95 0- 0 '0
- 0- - 0- 4- 1.7E+5 3.6E+8 0 Ru 103- 0- 0 0- - 0 -0 1.7E+5 4.2E+8 D Te 129m 0- 0- 0 0- + 0- 0- 4.0E+5 9.6E+8 Cs 134 0- 0- 0- - 0 0- 2.0E+5 1.2E+10- -
Cs 136 0- 0- 0- 0- - 0- - 5.0E+4 8.7E+7 Cs-137 0- -0 0- 0- - 0- 0- 2.lE+5 1.lE+10 Ba 140 0- 0 0- 0- 0- 4.4E+5 6.0E+7 O Ce 141 Ce 144 0- 0-0- 0-0- 0-0-
. 0-0 1.2E+5 2.7E+6 3.2E+8 9.0E+9 I -131 0- 0- 0- 0 0- 4.lE+6 1.4E+9 I -132- 0- 0- 0 0- 0- 3.9E+4 4.2E+5 1 133 0- 0- 0- 0- 7.4E+5 '.4E+5 o
.I -134 .0- 0- 0- 0- - 0 0- 1.0E+4 1.5E+5 1 -135 0- -0 0- 0- - 0- 1.5E+5 8.6E+5, UN ID- 0- 0- 0- 0- 3.0E+5- 1.3E+9 9
InhalationPathway, units =[j*(7" Food & Ground Pathway, units = im re p, O $023 0DCM 242 Revision 25 02 28 92
- - < , . w.w..4m-. ..._:.,_...4 ,,~.,,,._,.,_...m._,.ed....-.-.
.m..w. ,-..--,y _.~_,-,-r. _ w e- ; , , u,, ,.r,,-.,_,.. % , , - , , .-v,. ,, , -
IAEL2d DOSE PARAMETER R, FOR SECTOR R Page 4 of 5 Pathway Sheep Heat Distance 0.9 miles, X/0 8.'E 7 sec/m' D/0 5.2E 9 m' infant Child Teun Adul+ 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 Dathway , H3 0- 0- 0- 1.5E+0 0- 1.F.C+0 7.0E+0 2.lE+0 Cr 51 0- 0- 0- 5.lE+1 0- 1.0E+2 7.9E+1 2.6E+4 Mn 54 0- 0 0- 7.8E+2 0- 1.4E+3 7.7E+3 7.6E46-Co 57 0 0- 4.7E+3 0- 8.lE+3 2.0E+3 1.9E4 6 Co SS 0- 0- 0- 9.7E+3 +0- 2.0E+4 5.lE+3 2.lE+6 Co 60 0- 0- 0- 3.7E+4 so- 7.3E+4 3.3E+4 1.2E+8 Sr-89 0- 0- 0- 5.0E+4 0- 2.6E+4 7.7E+3 3 lE+4 Sr 90 0- 0- 0- 1.0E+6 0- 8.lE45 5.5E+5 1.3E+6 Zr 95 0 0- 0- 6.3E+4 0- 1.lE+5 9.7E+3 1.6E+6 Nb 95 0 0 0- 2.4E+5 0- 4.5E+5 2.8E+3 1.6E46 Ru 103 0- 0- 4.2E+5 0- 7.6E+5 2.8E+3 1.9E+6 Te 129m 0- 0- 0- 6.0E+5 0- 4.5E+5 6.4E+3 7.6E45 Cs 134 0- 1.4L+5 0- 1.2E+5 4.7E+3 3.8E+7 , Cs 136 0- 0- 0- 5.1E+3 0- 4.3E+3 8.lE+2 8.3E+5 Cs 137 0- 0- 0- 1.3E+5 0- 9.5E+4 3.4E+3 5.7E+7 O Be 140 Ce 141 Ce 144 0-0- 0-0- 0-0- 0-0- 0-5.lE+3 1.5E+3 1.8E+4 0-0- 4.3E+3 2.4E+3 3.0E+4 7.0E+3 2.0E+3 4.3E+4 1.2E+5 7.9E+4 4.3E+5 I -131 0- 0- 6.6C+5 0- 4.4E+5 6.6E+4 7.0E+5 I -132 0- 0- 0- 0- 0- 6.3E+2 6.8E+3 1 13 '0- 0- 1.6E 2 0- 8.7E-3 1.2E+4 1.3E+4 1 -134 0- 0- 0- 0 0- 0- 1.6E+2 2.5E+3 - I 135 0- 0- 1.lE-18 0- 6.4E 19 2.5E+3 1.4E+4 UN 10 0- 0- 0- 1.lE+5 0- 9.5E+4 A.8E+ 4.2E+6 Inhalation Pathway, units - ]j"(7" Food & Ground Pathway, units - gfj',*,/g *"I O-5023 0DCM 2-53 Revision 23 02 28-91
i TABLE 2 9 1 DOSE PARAMETER R, FOR SECTOR R Pace 5 of 5 , Pathw:y.DeerConsume[ Distance = 2.2 miles X/Q = 1.8E 7 sec/m D/0 8.8E 10 m*8 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 H3 0 0- 0- 2.8E+1 0- 2.3E+1 3.5E+1 3.9E+1 Cr-51 0 0- 0 5.0E+4 0- 1.0E+5 3.9E+2 3.2E+5 Mn 54 0- 0- 0- 7.7E+5 0- 1.4E+6 3.8E+4 4.lE+7 Co 57 0- 0- 0- 4.6E+6 0 8.0E+6 1.0!+4 2.3E+7 Co 58 0 0- 0- 9.6E+6 0- 1.9E+7 2.5E+4 4.7E+7 Co 60 0- 0- 0- 3.6E+7 0 7.2E+7 1.6E+5 7 iE+8 Sr 89 0- 0- 0- 4.9E+7 0- 2.6E+7 3.8E+4 3.lE+7 Sr 90 0- 0- 0- 1.0E+9 0 8.0E+8 2.7E+6 1.2E+9 Zr 95 0- 0- 0- 6.2E+7 0- 1.lE^8 4.8E+4 2.0E+8 Nb 95 0- 0- 0- 2.3E+8 0- 4.5E+8 1.4E+4 8.2E 8 Ru 103 0- 0- 4.2E+8 0- 7.5E+8 1.4E+4 1.3E+9 Te 129m 0- 0- 0- 5.9E+8 0- 4.5E+8 3.2E+4 6.4E-8 Cs 134 0- 0- 0- 1.4E+8 0- 1.2E+8 2.3E+4 3.4E+8 Cs 136 0- 0- 0- 5.lE+6 0- 4.2E+6 4.0E+3 9.5E+6 Cs 137 0- 0- 0- 1.3E+8 9.3E+7 1.7E+4 4.0E+8 8a 140 0- 0- 0- 5.0E+6 0- 4.2E+6 3.5E+4 7.4E+6 O Ce 141 Ce-144 I -131 0 0-0- 0-0- 0-0- 1.5Et6 1.8E+7 0-0- 2.4E+6 2.9E+7 9.9E+3 2.lE+5 4.2E+6 4.9E+7 0- 6.5E+8 0- 4.3E+8 3.3E&S 5.9E+8 , ! 132 0- 0- 0- 0.
- 3.lE+3 3.4E+4 1 133 0 1.6E+1 0- 8.6E+0 5.9E+4 6.7E+4 I 134 0- 0 0- 0 0- 8.2E+2 1.2E+4 I 135 0- 0- 1 lE 15 0- 6.3E-16 1.2E+4 6.9E+4 UN-ID 0- 0- 0- 1.lE+8 0- 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = "g"{j7" i Food & Ground Pathway, units I* "
C/sje i i O S023-0DCM 2 54 Revision 23 02-28-91 .
^ ^ ^ ^
-w, w'*e-n * ,e,.m w~w,m,,,v-w n,w "~n-~~-o -,s -r-v,
d 4 IABLE 2 10 DOSE PAPANETER Ri FOR SECTOR A Pace 1 of 3 i. O Pathway Camp San Matpo Distance = 4.lE 3.6 10 miles' m' X/Q = 7.lE 8 sec/m D/0 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 0 0- 0- 0- 0- 0- 1.3E+3 0-Cr 51 0- 0- 0- 0- 0- 0- 1.4E+4 4.7E+6 Mn 54 -0 0- 0 0- 1.4E+6 1.4E+9 Co 57 0 0 0- 0- -0 3.7E45 3.4E+8 Co 58 -0 0- 0- 0- 9.3E+5 3.8E+8 Co 60 0- -0 0 +0- :0- 0 6.0E+6 2.2E+10 Sr 89 0- 0- 0- 1.4E+6 2.2E+4 Sr 90 0 0- 0- 0 0 0- 9.9E+7 Zr 95 0- 0- 0- 0- 0- 0- 1.8E+6 2.5E+8 Nb 95 0- 0 0- 0- 0 0- 5.0E+5 1.4E+8 Ru 103 0- 0- 0- 0- 0- 0- 5.0E+5 1.lE+8 Te 129m 0- 0- C- 0- 0- 0 1.2E.6 2.0E+7 Cs 134 0- 0 0 0- 0 8.5E45 6.8E+9 Cs-136 0- >0 +0 0 1.5E45 1.5E+8 Cs 137 0- 0- 0- 0- 0- 0- 6.2E+5 1.0E+10 Ba lio 0 0- 0- 1.3E+6 2.1E+7 O Ce 141 Co 144 0-0- 0-0- 0-0- 0-0 0 0-0- 3.6E+5 7.8E+6 1.4E+7 7.0E+7 I 131 0- 0 0- 1.2E+7 1.7Ef7 1 -132 0- 0- 0- 0 0- 0- 1 lE+5 1.2E+6 1 133 0 0 0- 0- 0- 2.2E+6 2.4E46 1 -134 0- 0- 0- 0- 3.0E+4 4.5E+5 I 135 0- 0- 0- 0- 0- 4.5E+5 2.5E+6 UN ID 0- 0- 0 0- 0 8.6E+5 7.5E+8 InhalationPathway, units ="C$/ , Food & Ground Pathway, units - I'5# # gj3,c O S023 0DCM 2 55 Revision 23 02-28 9)
. - - .. - ._.- ~ - .. - ~ ~. - - . - - - - - - - - .- - - .._ - - - -
TABLE 2-10 DOSE PARAMETER 4 FOR SECTOR A Pathway Sheep (Meat)' Distance = 0.2 miles , X/Q = 6.7E 6 sec/m 0/0 = 5.2E 8 m . Infant Child Teen Adult ' inhale- Food & Inhala- Food & Inhala. Food & .nhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H3 0- 0- 0- 1.5E,0 0- 1.2E+0 7.0E+0 2.lE+0 Cr 51 0 0- 0- 5.lE42 0- 1.0E+2 7.9E+1 2.6E+4 Mn 54 0- 0- 0- 7.8E+2 0- 1.4E+3 7.7E+3 7.6E+6 Co 57 0 0- 0- 4.7E+3 0- 8.lE43 2.0E+3 1.9E+6 Co-58 0- 0- 0- 9.7E+3 0- 2.0E+4 5.lE+3 2.lE+6 , Co 60 -0 0- 0- 3.7E+4 :0- 7.3E+4 3.3E+4 1.2E+8 Sr 89 -0 0- 0- 5.0E+4 0- 2.6E+4 7.7E+3 3.lE+4 Sr 90 0- 0- C- 1.0E+6 0- 8.1E+5 5.5E+5 1.3E+6 2r-95 0- 0 0- 6.3E+4 0- 1.lE+5 9.7E*3 1.6E+6 Nb-95 0- 0- 2.4E+5 0- 4.5E+5 2.8E+3 1.6E+6 Ru 103 0 4.2E+5 0- 7.6E45 2.8E+3 1.9E+6 Te 129m 0 0- 0- 6.0E+5 0- 4.5E+5 6.4E+3 7.6E+5 Cs 134 0- 0- 0- 1.4E+5 0- 1.2E+5 4./E+3 3.8E+7 Cs 136 0- 0- 0- 5 lE+3 0- 4.3E+3 8.lE+2 8.3E+5 Cs-137 04 0- 0- 1.3E+5 0- 9.5E+4 3.4E+3 5.7E+7
- Ba 140 0- 0- 0- 5.lE+3 0- 4.3E+3 7.0E+3 1.2E+5 Ce-141 -0 0- 0 1.5E+3 0- 2.4E+3 2.0E+3 7.9E+4 Ce644 0- 0- 0- 1.8E+4 0- 3.0E+4 4.3E+4 4.3E+5 ,
1 131 0 0- 0- 6.5E+5 4.4E+5 6.6E+4 7.0E+5 1 132 -0 0- ' 0-0- 0- 6.3E42 6.8E+3 1 -133 0- 0- 0- 1.6E-2 0- 8.7E 3 1.2E+4 1.3E+4 1 134 0- 0- 0- 0- 0- 1.6E+2 2.5E+3 1 -135 0 0. 1 lE-18 6.4E 19 2.5E+3 1.4E+4 UN 10 0- 0- 1.1E+5 0- 9.5E+4 4.8E+3 4.2E+6 InhalationPathway, units =[f 7" Food & Ground Pathway, units I* *
- V"I g[g[e O 5023-00CM 2 56 Revision 23 02 28 91
. _ _ . _ ~ . . . _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ . _ - _ . _ _ . _ _ _ _
IMLE 210 7 DOSE PARAMETER R, FOR SEcr0R A Pace 3 of 3 l Pathway Deer Consumep Distance 2.2 miles X/Q = 1.9E 7 sec/m 0/0 1.4E 9 m*' Infant Child Teen Adult Inhala. Food & Inhala - Food & Inhala. Foo4 & Inhala. Food & Radio- tion Ground tien Ground tion Ground tion Ground Nxlide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H3 0- 0- 0- 2.8E+1 0- 2.3E+1 3.5E+1 3.9E 1 Cr-51 0- 0 0- 5.0E+4 0- 1.0E45 3.9E+2 3.2E*5 Mn 54 0- 0- 7.7E+5 0- 1.4E+6 3.8E+4 4.lE*7 , Co 57 0- 0- 0- 4.6E+6 0 8.0E+6 1.0E+4 2.3E+7 l Co 58 0- 0- 0- 9.6E46 0- 1.9E+7 2.5E+4 4.7E+7 l Co 60 0- 0- 3.6E+7 0- 7.2E+7 1.6E+5 7.2E+8 Sr 89 0- 4.9E+7 20- 2.6E+7 3.8E+4 3 lE+7
$r 90 0- 0- 0- 1.0E+9 0- 8.0E+8 2.7E+6 1.2E+9 Zr 95 0- 0- 0- 6.2E+7 0- 1.lE+8 4.8E+4 2.0E+8 Nb 95 0 0- 0- 2.3E+8 0- 4.5E+8 1.4E+4 8.2E+8 .
Ru-103 0- 0- 0- 4.2E+8 0- 7.5E+8 1.4E+4 1.3E+9 Te-129m 0- 0- 0- 5.9E+8 0- 4.5E+8 3.2E*4 6.4E+8 Cs 134 0- 0- 0 1.4t+F 1.2E+8 2.3E+4 3.4E+8 Cs-136 0- 0- 5.lE+6 4.2E+6 4.0E+3 9.5E46 Cs 137 0- 0- 1.3E+8 0- 9.3E+7 1.7E+4 4.0E+8 Ba 140 0- 0- 0- 5.0E+6 4.2E+6 3.5E+4 7.4E+6 O Ce 141 Ce 144 0-0- 0-0- 0-1.5E+6 1.8E+7 0-0- 2.4E+6 2.9E+7 9.9E+3 2.lE+5 4.2E46 4.9E+7 1 -131 0- 0- 0- 6.5E+8 0- 4.3E+8 3.3E+5 5.9E+8 I 132 0- 0- 0- 0- 0- 3.lE+3' 3.4E+4 1 -133 0- 0- 0- 1.6E+1 8.6E+0 5.9E+4 6.7E+4 1 -134 0- 0 8.2E+2 1.2E+4 1 -135 0- 0- 1.lE 15 6.3E 16 1.2E+4 6.9E+4 UN ID -_ 0 - 0- 1 lE+8 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units -] j*(7" Food k Ground Pathway, units I* re d Cip e O S023 0DCM 2 57 Revision 23 02-28 91
'l TABLE 2 11 l DOSE PARAMETER R, Fr~ SECTOR B Page 1 of 3
, Pathway Sheep (Heat)' Distance = 0.2 milesd X/0 6.lE 6 sec/m D/0 5.3E-8 m Infant . Child Teen Adult Inhala. Food & Inhala- Food & Inhala- Food &' Inhala- Food &
Radio- tion Ground tion Ground tion Ground tion Ground l Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway
- H3 0- 0- 1.5E+0 0- 1.2E+0 7.0E+0 2.lE+0 '
Cr 31 0 0- 0- 5.lE+1 0- 1.0E+2 7.9E+1 2.6E+4 Mn 54 0- 0- 0 7.8E+2 0 1.<E+3 7.7E+3 7.6E,6 Co 57 0- 0- 0- 4.7E+3 8.lE+3 2.0E+3 1.9E+6 Co 58 0- 0- 0- 9.7E43 0- 2.0E+4 5.lE+3 2.lE+6 Co 60 0- 0- 0- 3.7E+d 0- 7.3E+4 3.3E+4 1.2E+8 Sr 89 0- 0- 0- 5.0E+4 V- 2.6E+4 7.7E+3 3.lE+4 Sr 90 0- 0- 0- 1.0E+6 0 8.lE+5 5.5E+5 1.3E+6 Zr 95 0- 0- 0 6.3E+4 0- 1.lE+5 9.7E43 1.6E+6 Nb 95 0- 0- 0- 2.4E+5 -. 0 4.5E+5 2.8E+3 1.6E+6 Ru 103 0- 0- 4.2E+5 0- 7.6E+5 2.8E+3 1.9E+6 Te 129m 0 0- 0- 6.0E+5 0- 4.5E+5 6.4E+3 7.6E+5 Cs 134 0- 0- 1.4E45 0- 1.2E+5 4.7E+3 3.8E+7 Cs 136 .0- 0- 0- 5.lE+3 4.3E+3 8.lE+2 8.3E+5 Cs 137 0- 0- 0- 1.3 E4 5 0- 9.5E+4 3.4E+3 5.7E+7 Ba 140 0- 0- 0 5.lE+3 0- 4.3E+3 7.0E+3 1.2E+5 O Ce 141 Ce 144 0-0- 0-0- 0-1.5E+3 1.8E+4 0-0- 2.4E+3 3.0E+4 2.0E+3 4.3E+4 7.9E+4 4.3E+5 1 131 0- 0- 6.6E+5 0- 4.4E+5 6.6E+4 7.0E+5 , 1 132 0- 0- 0- 0- 6.3Ev2 6.8E+3 1 -133 0- 1.6E 2 0- 8.7E 3 1.2E+4 1.3E+4 - 1 -134 0- 0- 0- 1.6E+2 2.5E+3 1 135 0- 0- ,1.lE-18 0- 6.4E-19 2.5E+3 1.4E+4 UN-ID 0- 0- 1.lE+5 0- 9.5E44 4.8E+3 4.2E+6 Inhalation Pathway, units y ff il Food & Ground Pathway, units I* " C[/ jc O S023 0DCM 2 58 Revision 23 02 28 91
TABLE 2-11 005E PARAMETER Ri FOR SECTOR 8 Pace 2 of 3 Pathway Oistance 1.1 milesd Deer Consume [ 2.4E 9 m X/0 3.4E 7 sec/m D/0 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 H3 0- 0- 2.8E 1 0- 2.3Ed 3.5E+1 3.9E+1 Cr-51 0- 0 0- 5.0E+4 0- 1.0E+5 3.9E+2 3.2E+5 Mn 54 0- 0 0- 7.7E+5 0- 1.4E+6 3.8E+4 4.lE+7 Co 57 0- 0- 0- 4.6E+6 0- 8.0E+6 1.0E+4 2.3E+7 Co 58 0- 0- 0 9.6E+6 0- 1.9E+7 2.5E+4 4.7E+7 Co 60 0- 0- 0- 3.6E+7 0- 7.2Ef/ 1.6E+5 7.2E+8 Sr 89 0~ 0- 4.9E+7 <0- 2.6E+7 3.8E+4 3,lE+7 Sr 90 0- 0- 1.0E+9 0- 8.0E+8 2.7E+6 1.2E+9 Zr 95 0- 0- 0- C.2E+7 1.lE48 4.8E+4 2.0E+8 Nb 95 0- 0- 2.3E48 0- 4.5E4B 1.4E+4 8.2E+8 Ru-103 0- 0- 0- 4.2E+8 0- 7.5E+8 1.4E+4 1.3E+9 Te 129m 0- 0- 0- 5.9E+8 0- 4.5E+8 3.2E+4 5.4E-8 Cs-134 0- 0- 0- 1.4E+8 0- 1.2E+8 2.3E+4 3.4E+8 Cs l?6 0- 0- 0- 5.lE+6 0- 4.2E+6 4.0E+3 9.5E+6 Cs 137 0- 0- 0- 1.3E+8 0- 9.3E+7 1.7E+4 4.0E+8 Ba 140 0 0- 5.0E+6 0- 4.2E+6 3.5E+4 7.4E+6 O Ce 141 0- 0- 1.5E+6 0- 2.4E+6 9.9E+3 4.2E46 U Ce 144 0- 0- 0- 1.8E+7 0- 2.9E+7 2.lE+5 4.9E+7 1 -131 0- 0- 0- 6.5E+8 0- 4.3E+8 3.3E+5 5.9E+8 1 132 0- 0- 0- 0- 0- 3.lE+3 3.4E+4 1 -133 0- 1.6E+1 0 8.6E+0 5.9E+4 6.7E44 1 -134 0- 0- 0- 8.2E+2 1.2E+4 1 -135 0- 0 0- 1.lE-15 0- 6.3E-16 1.2E+4 6.9E+4 UN ID 0- 0- 0- 1.lE+8 0- 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units - yr Food & Ground Pathway, units - gfjf,vri g O S023-0DCli 2 59 Revision 23 02-28 91
i i TABLE 2-11 DOSE PARAMETER R, FOR SECTOR B Page 2 of 3 Pathway Sanitary Landfill Distance = 2.1 miles 3 X/Q 1.4E 7 sec/m D/0 = 1.2E 9 m l 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 H3 0 0- 0- 0- 0- 0- 2.9E+2 0-Cr 51 0 0- 0- 0- 0- 3.3E+3 1.1E+6 Mn 54 0- 0- 0- 0- 0- 0- 3.2E+5 3.2E+8 Co 57 0- 0- 0- 0- 8.4E+4 7.8E+7 Co 58 0 0- 0 0- 0- 0- 2.lE+5 8.7E+7 Co 60 0- 0- 0- 0- ,0 - 1.4E+6 4.9E+9 , Sr 89 0- 0- 0- 0- 0- 3.2E+5 4.9E+3 Sr 90 0- 0- 0- 0- 0- 2.3E+7 -0 Zr 95 0- 0- 0- 4.0E+5 5.7E+7 Nb 95 0- 0- 0- 0- 1.2E+5 3.lE+7 Ru 103 0- 0- 0- 1.2E+5 2.5E+7 Te-129m 0- 0- 0- 0- 2.6E+5 4.5E+6
; Cs 134 0- 0 0- 0- 1.9E+5 1.6E+9 Cs-136 0- 0 0- 3.3E+4 3.4E+7 Cs 137 0- 0- 0- 0- 1.4E+5 2.3E+9 Ba 140 0- 0- 0- 0- 0- 2.9E+5 4.7E+6 O Ce-141 Ce-144 0-0-
0-0- 0-0- 0-0- 8.3E+4 1.8E+6 3.lE#6 1.6E+7 1 131 0 0- 0- 0- 2.7Eo6 3.9E+6 1 -132 0- 0- 0- 0- 2.6E+4 2.8E+5 I -133 0- 0- 0- 0- 0- 4.9E+5 5.6E+5 1 -134 0 0- 0- 0- 6.8E+3 1.0E+5 1 -135 0- 0- 0- 0- 0- 1.0E+5 5.8E+5 UN ID 0- 0- 0- 0- 2.0E+5 1.7E+8 1 i l Inhalation Pathway, units = ]j"(7" Food & Ground Pathwsy, units I* " " Ci/ e O S023-0DCH 2-60 Revision 23 02 28 91
~ . _ _
IABLE 2-12 DOSE PARAMETER R, FOR SECTOR C Page 1 of 5 O Pathway Camp San Ono[re Distance 2.6 miles ' X/Q = 9.2E-8 sec/m D/0 - 8.4E 10 m' infant Child Teen Adult Inhala- Food & Inhala. Food & Inhala , Food & Inhala. Fo6d & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H3 -0 0- 1.3E+3 -0 Cr 51 0- 0- 0- 1.4E+4 4.7C+6 Hn 54 0- 0- 0- 0- 0- 1.4E+6 1 4E+9 Co-57 0- 0- 0- 0- 0- 0- 3.7E+5 3.4E+8 Co 58 0- 0- 0- 9.3E<5 3.8E+8 Co 60 0- 0 0- :0- 0- 6.0E+6 2.2E+10 Sr 89 0- 0- 0- 0- 1.4E+6 2.2E+4 Sr 90 0- 0- 0- 0- 9.9E+7 0-Zr 95 -0 . 0- C. 0- 0- 0- 1.8E+6 2.5E48 Hb-95 0- 0- 0- 0- 0- 0- 5.0E+5 1.4E48 Ru-103 -0 0- 0- 0- 0 5.0E+5 1.lE+8 Te 129m' 0- 0- 0- 1.2E+6 2.0E+7 Cs-134 0- 0- 0- 0- 8.5E+5 6.8E+9 Cs-136 0- -0 0 0- 1.5E+5 1.5E48 Cs 137 0- 0- 0- 6.2E+5 1.0E+10 Ba 140 0- 0- 0- 0- 0- 1.3E+6 2.lE+7 O Ce-141 Ce-144 0-0- 0-0- 0-0- 0-0- 3.6E+5 7.3E+6 1.4E+7 7.0E+7 . I -131 0 . 0- 0- 0- 1.2E+7 1.7E+7 I -132 0- -C. 0- -0 0- 1 lE+5 1.2E46 I 133 0- 0- 0- 0- 2.2E+6 2.4E+6 I -134 0- 0- 0- 3.0E+4 4.5E+5 I 135 0- 4.5E+5 2.5E46 UN ID 0- 0- 0- 0- 8.6E+5 7.5E+8 Inhalation Pathway, units - ft / Food & Ground Pathway, units I* " Ci/s n U S023-00CM 2 61 Revision 23 02-28-91
1 l TABLE 2-11, OOSE PARAMETER R, FOR SECTOR C Page 2 of 5 O Pathwa/-CampSanOnofreFr.Stn Distance 2.3 miles j X/Q 1.lE 7 sec/m 0/0 1.lE 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 0- 3- 0- 0- 0 5.2E+2 0-Cr 51 0- 0- 0- 0- 0- 5.9E+3 1.9E+6 ) Mn 54 0- 0 0- 0- 0- 5.8E+5 5.7E+8 Co 57 0 0- 0- 0- 0- 1.5E+5 1.4E+8 Co 58 0 -0 0- 0- 3.8E+5 1.6E+8 l Co 60 0- 0- 0- '0- 0- 2.5E+6 8.8E+9 Sr 89 0- 0- 0- 5.8E+5 8.9E+3 Sr 90 0- 0 0 0- 0- 0- 4.lE+7 0-Zr 95 0 0- 0 0- 0- 7.3E+5 1.0E+8 Nb 95 0- 0- 0- 0- 0- 2.lE+5 5.6E+7 Ru 103 0- 0- 0- 0 2.lE+5 4.5E+7 i Te 129m 0- 0-
.,- 0- 4.13 E+ 5 8.lE45 Cs 134 0- 0- 0- 3.5E+5 2.8E 9 Cs 136 0- 0- 6.0E+4 6.2E+7 Cs-137 0- 0- 0- 0- 0- 0- 2.6E+5 4.2E+9 8a 14C 0- 0- 0- 0- 5.2E+5 8.4f+6 O- Ce 141 Ce 144 0-0-
0-0- 0-0- 1.5E+5 5.6E+6 3.2E+6 2.9E+7 I -131 0 0- 0- 4.9E+6 7.lE+6 1 -132 0- 0- 0- 4.7E+4 5.lE+5 1 133 0- 0- 0- C- 8.8E+5 1.0Ed 1 -134 0- 0- 0- 0- 1.2E+4 1. L b I 135 0- 0- 0- 0- 0- 1.8E+5 1.0E+6 UN ID 0- 0- 0- 0- 0- 3.6E+5 3.lE+8 4 m Inhalation Pathway, units = ]j(yr Food & Ground Pathway, units I* "f'*# " gj,ec l O - 5023-0DCM 2 62 Revision 23
, 02-28-91
_. _ _ . - - . . ~ - - - _.- , . - _- - - _ _ . . . - - - -
1 TABl.E 2-12 : l DOSE PARAMETER R, FOR SECTOR C l Pace 3 of 5 i Pathway Sewage Facility Distance 2.2 miles i X/0 1.2E 7 sec/m D/0 1.2E 9 m 1 i lnfant Child Teen- Adult [ 1 Inha14- Food & Inhala- Food & Inhala- Food & Inhala- Food & i Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway l i i H3 0 0 0 0- 0- 0- 2.9E+2 0-
- Cr 51 % 0- 0- 0- 0- 0- 3.3E+3 1.lE+6 l Mn 54 0- 0- 0- 0- 0- 3.2E+5 3.2E+8
- co 57 0- 0- 0- 0- 0- 0- 8.t,E+4 7.8E+7
! C0 58 0- 0- 0- 2.lE+5 8.7E+7 i Co 60 0 0- 0 0- so- 1.4f+6 4.9E+9
$r 89
- s. 0- 0- 0- 0- 3.2E+5 4.9E+3
- Sr 90 40- 0- 0- 0- 0- 0- 2.3E+7 ! Zr 95 0- 0- 0- 0- 0- 4.0E+5 5.7E+7 l Nb 95 0- 0- 0- 0- 0- 0- 1.2E+5 3.lE+7
- Ru 103 0 0- 0- 1.2E+5 2.5E+7
- Te 129m 0- 0- 0- 0- 0- 2.6E+5 4.5E-6
- Cs 134 0- 0- 0- 0- 0- 0- 1.9E+5 1.6E+9
! Cs 136 0- 0- 0 0- 0- 3.3E+4 3.4E+7 Cs 137 0 0- 0- 1.4E+5 2.3E+9 O Ba 140 Ce 141 Ce 144 0-0- 0-0- 0-0- 0-0- 0-0- 0-0- 0-2.9E+5 8.3E+4 1.8E+6 4.7E+6 3.1E+6 1.6E+7 1 131 0- 0- 0- 2.7E+6 3.9E+6 1 132 -0 0- 0- 0- 0- 2.6E+4 2.8E+5 1 133 0- 0- 4.9E+5 5.6E+5 1 134 0- 0- 0- 6.8E+3 1.0E+5 1 135 0- 0- 0- 0- 0- 1.0E+5 5.8E+5 UN ID 0- 0- 2.0E+5 1.7E+8 Inhalation Pathway, units = ]j*(7" Food'& Ground Pathway, units * ' * " l* g[j3[c ' lO S023-00CM 2-63 Revision 73 02-28 91
IAllLL.2:12 OOSE' PARAMETER R, FOR SECTOR C Page 4 of 5 O Pathway Sheep (Meat)8 6.5E 6 sec/m Distance = 0.2 mi ns
- 6. lE 8 m
X/Q 0/0 lR 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 t'athway H -3 0 0- 0- 1.5E+0 0 1.2E+0 7.0E+0 2.lE+0 Cr-F1 0- 0- 5.lE+1 1.0E+2 7.9E+1 2.6E44 Mn-54 0- 0- 0- 7.8E,2 0- 1.4E+3 7. i E4 3 7.6E+6 Co 57 0- 0- 4.7E+3 8.lE+3 2.0E+3 1.9E+6 i Co 58 0- 0- 0- 9.7E43 0- 2.0E+4 5.lE+3 2.lE+6 Co-60 0- 0 3.7E+4 0- 7.3E+4 3.3E+4 1.2E+8 Sr 89 0- 0- 5.0E+4 :0- 2.6E+4 7.7E+3 3.lE+4 Sr 90 0- 0- 0- 1.0E+6 8.lE+5 5.5E+5 1.3E+6 Zr 95 0- 0- 0- 6.3E+4 0- 1.lE+5 9.7E+3 1.6E+6 , Nb 95 0- 0- 2.4E+5 0- 4.5E+5 2.8E+3 1.6E+6 Ru 103 0- 0- 4.2E+5 0- 7.6E45 2.8E+3 1.9E+6 Te-129m 0- 0- 0- 6.0E*5 0- 4.5E+5 6.4E*3 7.5E45 Cs-134 0- 1.4E+5 0- 1.2E+5 4.7E+3 3.8E+7 Cs-136 0- 5.lE43 0- 4.3E+3 8.lE+2 8.3E+5 Cs-137 0- 0- 0- 1.3E45 0- 9.5E+4 3.4E+3 5.7E+7 Ba-140 0- 5.lE43 4.3I+3 7.0E+3 1.2E+5 Ce-141 0- 1.5E+3 0- 2.4E+3 2.0E+3 7.9E+4 Ce-144 0- 0- 0- 1.8E+4 0- 3.0E+4 4.3E+4 4.3E+5 I -131 0- 0- 0- 6.6E+5 0- 4.4E+5 6.6E+4 7.0E+5 1 -132 0- 0- 0- 6.3E+2 6.8E+3 1 -133 0- 1.6E 2 0 8.7E 3 1.2E+4 1.3E44 I -134 0- 0- 0- 0- 0- 0 1.6E+2 2.5E+3 I -135 0- 1.lE 18 6.4E-19 2.5E+3 1.4E+4 , UN-ID 0- 0- 1.lE+5 0- 9.5E+4 4.8E+3 4.2E+6 InhalationPathway, units =}{*(!" Fo'sd & Ground Pathway, units U" IImrem/vr) C O S023 00CM 2-64 Revision 25 02 28 92
TABLE 2 12 DOSE PARAMETER C, FOR SECTOR C Page 5 of 5 Fathway=DeerConsume[ Distance 1.0 miles X/Q = 3.4E 7 sec/m D/Q 5. l E 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 P6thway H? 0- 0 - J- 2.8E+1 0- 2.3E+1 3.5E+1 3.9E+1 Cr. a' l 5 0- - 0- 5.0E44 1.0E+5 3.9E+2 3.2E+5 Mn 54 0- 0- - 0- 7.7E+5 1.4E+6 3.8E+4 4.lE+7 Co 57 0 0- - 0- 4.6E+6 0- 8.0E+6 1.0E+4 2.3E+7 Co 58 0- 9.6E+6 0- 1.9E+7 2.5E+4 4.7E+7 Co 60 3.6E+7 7.2E+7 1.6E+5 7.2E+8
- Sr-89 0- 0- 4.9E+7 *0- 2.6E+7 3.8E+4 3.lE+7 Cr-90 0- 0- 1.0E+9 0- 8.0E+8 2.7E+6 1.2E+9 Zr 95 0- 6.2E+7 0- 1.1E+8 4.8E+4 2.0E+8 Nb 95 0- 0- 2.3E48 0- 4.5E+8 1.4E44 8.2E+8 Ru-103 0- 0- -
0- 4.2E+8 0- 7.5E+8 1.4E+4 1.3E+9 Te 129m 0- 0- 5.9E+8 0- 4.5E+8 3.2E+4 6.4E+8 Cs-134 0- 1.4E+8 0- 1.2E+8 2.3E+4 3.4E+8 Cs-136 0- 0- - 0- 5.lE+6 0- 4.2E+6 4.0E+3 9.5E+6 Cs-137 0- 1.3E+8 0- 9.3E+7- 1.7E+4 4.0E+8 Ba 140 0- 5.0E+6 0- 4.2E+6 3.5E+4 7.4E+6 O Ce 141 Co-144 0-1.5E+6 1.8E+7 0-0- 2.4E+6 2.9E+7 9.9E+3 2.lE+5 4.2E+6 4.9E+7-1 -131 0- 6.5E+8 0- 4.3E+8 3.3E+5 5.9E+8 1 -132 0- 0- 3.lE+3 3.4E+4 1 -133 0- 0- - 0- 1.6E+1 0- 8.6E+0 5.9E+4 6.7E+4 - I -134 0- 0- 8.2E+2 1.2E+4 1 -135 -0 1.lE 15 0- 6.3E-16 1.2E+4 6.9E+4 UN 10 1.lE+8 9 4E+7 2.4E+4 1.4E+8 l f I Inhalation Pathway, units = j!" , l I* *"*5 "I Food & Ground Pathway, units ggf3, l O -5023-0DCM 2-65 Revision 23 02 28 91
---,.--,,,-..,,w.....w- -
-,--.v, -
-,er- , , , -- -~
-e.-e1- w w- g
IABLE 2-13 DOSE PARAMETER R, FOR SECTOR D Pace 1 of 3 Pathway Camp San Ono[re Distance = 2.8 miles d X/Q = 6.6E 8 sec/m D/Q = 6.4E-10 m Infant Child Teen Adult l Inhala- food & Inhala- Food & Inhala- Food & Inhala- food L ' Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H3 0- 0 0 0- 0- 1.3E+3 0-Cr 51 0- 0- 0- 0- 0- 1.4E44 4.7E+6 Mn 54 0- 0- 0 0- 0- 0- 1.4E+6 1.4E+9 Co 57 0- 0- 0- 0- 3.7E+5 3.4E48 Co 58 0 0- 0- 0- 0- 0- 9.3E+5 3.8E+8 Co 60 0- 0- 0- 0- 6.0E+6 2.2E+10 Sr 89 0- 0- 0- 0- 0- 1.4E+6 2.2E+4 Sr 90 0- 0- 0- 0- 0- 9.9E+7 0-Zr 95 0- 0- 0- 0- 0- 1.8E+6 2.5E+8 Nb 95 0- 0- 0- 0- 5.0E+5 1.4E+8 Ru 103 0- 0- 0- 5.0E+5 1.lE+8 Te 129m 0- 0- 0- 0 0- 0- 1.2E+6 2.0E47 Cs 134 -0 0- 0- 0- 8.5E+5 6.BE+9 Cs-136 0- 0- 0- 0- 1.5E+5 1.5E+8 Cs-137 0- 0- 0- 0- 6.2E+5 1.0E+10 Ba-140 0- 0- 0- 0- -0 1,3E+6 2.lE+7 O Ce 141 Ce 144 0-0- 0-0- 0-0 0-0- 0-3.6E45 7.8E+6 1.4E+7 7.0E+7 1 131 0- 0- 0- 0- 0- 1.2E+7 1.7E+7 1 -132 0- 0- 0- 0- 1.1E+5 1.2E+6 1 133 0- 0- 0- 2.2E+6 2.4E+6 I -134 0- 0- 0- 3.0E+4 4.5E+5 1 135 0- 0- 4.5E+5 2.5E+6 UN ID 0- 0 0- 0- 0- 8.6E+5 7.5E+8 Inhalation Pathway, units = % Food & Ground Pathway, units I" ' " C/sjc S023-0DCM 2 66 Revision 23 02 28 91
TMLE 2-11 DOSE PARMETER R, FOR SECTOR D Page 2 of 3 O Pathway Sheep (Heet)' Distance = 0.2 miles X/Q = 6.3E 6 sec/m D/0 6.6E 8 m d 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 0- 0- 0- 1.5E+0 c0- 1.2E+0 7.0E+0 2.lE+0 Cr-51 0- 0- 0 5.lE+1 ' 1,0E+2 7.9E+1 2.6E+a Hn 54 0- 0- 0- 7.8E+2 0- l.4E+3 7.7E+3 7.6E46 Co-57. 0- 0 0- 4.7E+3 0 8.1 ?+3 2.0E+3 1.9E+6 Co 58 0- 0- 0- 9.7E+3 0- 2.0E+4 5.lE+3 2.lE+6 Co 60 0- 3.7E+4 . 0- 7.3E+4 3.3E+4 1.7E+8 Sr 89 0- 0- 0- 5.0E+4 0- 2.6E+4 7.7E+3 3.lE+4 , Sr-90 0- 0- 0- 1.0E+6 0 8.lE+5 5.5E+5 1.3E+6 Zr 95 0- .0- 6.3E+4 0- 1.1E+5 9.7E+3 1.6E46 Nb 95 0- 0- 0- 2.4E+5 0- 4.5E+5 2.BE+3 1.6E+6 Ru-103 0- a0- 4.2E+5 0- 7.6E+5 2.8E+3 1.! E+6 Te 129m 0- 0- 0- 6.0E45 0 4.5E+5 6.4E+3 7.6E+5 Cs 134 0- 0- 1.4E+5 0- 1 2E+5 4.7E+3 3.8E+7 Cs-136 0- 0- 5 lE+3 0- 4.3E+3 8.lE42 B.3E+5 Cs 137 -0 0- 1.3E+5 0- 9.5E+4 3.4E+3 5.7E+7 Ba 140 0- 0- 0-O Ce 141 Ce-144 0-0 0-0- 0-5.1E+3 1.5E+3 1.8E+4 0 0-4.3E+3 2.4E+3 3.0E+4 7.0E+3 2.0E+3 4.3E+4 1.2E+5 7.9E+4 4.3E45 1 -131 0- 0- 6.6E+5 4.4E+S 6.6E+4 7.0E+5 1 -132 0- 0- 0- 0- 6.3E+2 6.8E+3 1 -133 1.6E 2 8.7E 3 1.2E+4 1.3E+4 1 -134 0- 0- 0- 0- 0- 1.6E+2 2.5E43 I -135 0- 0- 1.lE 18 6.4E 19 2.5E+3 1.4E+4 UN-!D 0- 1.lE+5 0- 9.5E+4 4.8E+3 4.2E+6 Inhalation Pathway, units = *Ch " - Food & Ground Pathway, units I* *" *'*"I g g[,,g O S023-0DCM 2 67 Revision 23 02 28 91
_ _ _ _ _ _ _ . _ ___..______.-_._.._..m._.- _ _ . _ _ _ _ _ . _ _ _ _ IM LE 2-13 DOSE PARAMETER R, FOR SECTOR D Pathway Deer Consumep Distance = 1.0 miles X/0 = 3.3E 7 sec/m D/0 4.3i i n" Infant Child Teen Adult Inha14- Food & Inhala- Food & Inhala- Food & Inhala. Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pt.thway I H -3 0- 0- 0- 2.8E+1 0 2.3E+1 3.5E+1 3.9E+1 Cr 51 0 0- 5.0E+4 0- 1.0E+5 3.9E+2 3.2E+5 Mn 54 0 0 0- 7.7E+5 ' 0- 1.4E+6 3.8E+4 4.lE+7 Co 57 0- 0 4.6E+6 0- 8.0E+6 1.0E+4 2.3E+/ Co 58 0- 0- 9.6E+6 0- 1.9E+7 2.5E+4 4.7E+7 Co 60 0- 0- 0- 3.6E+7 .0 7.2E+7 1.6E+5 7.2E+8 Sr 89 0- 0- 0- 4.9E+7 0- 2.6E+7 3.8E+4 3.1E+7 Sr 90 0 0- 0- 1.0E+9 0- 8.0E+8 2.7E+6 1.2E+9 Zr 95 0 -0 0- 6.2E+7 0- 1.lE+8 4.8E+4 2.0E+8 Nb 95 0- 0- % 2.3E+8 4.5E+8 1.4E+4 8.2E+8 Ru-103 0- 0- u- 4.2E+8 7.5E+8 1.4E+4 1.3E+9 Te 129m 0- 0- 0- 5.9E+8 0- 4.5E+8 3.2E+4 6.4E+8 Cs 134 0- 0- 0- 1.4E+8 0- 1.2E+8 2.3E+4 3.4E+8 Cs 136 0 0 5.lE+6 0- 4.2E+6 4.0E+3 9.5E+6 Cs-137 0- 0- 1.3E+8 0- 9.3E+7 1.7E+4 4.0E+8 Ba-140 0- 0- 5.0E+6 0- 4.2E+6 3.5E+4 7.4E+6 O Ce 141 Ce 144 0-0- 0-0- 0-0- 1.5E+6 1.8E+7 0-0- 2.4E+6 2.9E+7 9.9E+3 2.lE+5 4.2E+6 4.9E+7 I 131 0- 0- 0- 6. W B 0- 4.3E+8 3.3E+5 5.9E+8 . I 132 0- +0- 0- - 0 3.lE+3 3.4E+4 I -133 0 0- 1.6E+1 8.6E+0 5.9E+4 6.7E+4 I -134 0- 0- 0- 0- 0- 6.2E+2 1.2E+4 I 135 0- 0- 0- 1.1E 15 0- 6.3E-16 1.2E+4 6.9E+4 UN ID 0- 0- 0- 1.lE+8 0- 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units r hc / I* I Food & Ground Pathway, units pC1/sec O 5023 00CM 2-68 Revision 23 02-28-91
i
. TABLE 2 14 1
005E PARAMETER R, FOR SECTOi E Page 1 of 3 Pathway Camp Horno Distance 4.0 miles d i 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 tion Ground tion Ground tion Ground Nuclide Pathway Psthway Pathway Pathway Pathway Pathway Pathway Pathway H3 0 0- 0 0- 0- 1.3E+3 Cr 51 0- 0- 0- 0 0- 0- 1.4E+4 4.7E+6 Mn 54 0- 0- 0- 0- 0- 0- 1.4E+6 1.4E+9 Co 57 0- 0- 0- 0- 0- 3.7E45 3.4E+8 Co 58 0- 0- 0 0- 0- 9.3E+5 3.8E+8 Co 60 0- 0- 0 0 0- 6.0E+6 2.2E+10 Sr 89 0- 0- 0- 0- 10- 9- 1.4f+6 2.2E+4 Sr 90 0- 0- 0- 0- 0- 0- 9.9E+7 0-Zr 95 0- 0- 0- 0* 0 0- 1.8E+6 2.5E+8 Nb 95 0- 0- 0 0- 0- 0- 5.0E+5 1.4E+8 Ru 103 0 0 +0- 0- 0- 5.0E+5 1.lE48 Te.129m 0- 0- 0- 0 0- 0- 1.2E+6 2.0E+7 Cs 134 0- 0- 0- 0- 0- 0- 8.5E+5 6.8E+9 Cs-136 0- 0- 0 0- 0- 1.5E+5 1.5E+8 Cs-137 -0 0- 0- 0- 6.2E+5 1.0E+10 Ba-140 0- 0- 0- 0- 1.3E+6 2.lE+7 O Ce 141 Ce-144 0-0- 0-0- 0-0- 0 0-0- 0-3.6E+5 7.8E+6 1.4E+7 7.0E+7 1 -131 0- 0- 0- 0- 1.2E+7 1.7E+7 I 132 0- 0- 0- 0- 0- 1.lE+5 1.2E+6 1 133 0- 0- 0 0- 0- 0- 2.2E+6 2.4E+6 1 134 0- 0- 0- 0- 0- 3.0E+4 4.5E+5 1 135 0- 0 0- 0- 4.5E+5 2.5E+6 UN ID 0- 0- 0- 0 0- 8.6E+5 7.5E+8 Inhalation Pathway, units a mrem /yr pCi/m food & Ground Pathway units - (mrem /vr) pCi/sec S023-0DCM 2-69 Revit ion 23 02 28 91
IABLE 2-14 DOSE PARAMETER R, FOR SECTOR E Page 2 of 3
' Pathway Sheep (Heat)3 Distance 0.3 miles l X/0 4.5E 6 sec/m D/Q 5.9E 8 m d 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 H3 0 1.5E+0 0- 1.2E40 7.0E+0 2.lE+0 Cr-51 0- 0- LIE +1 0- 1.0E+2 7.9E+1 2.6E+4 Mn 54 0- 0- 0- 1.8E+2 0- 1.4E+3 7.7E+3 7.6E,6 Co 57 0- 0- 0- 4.7E+3 0 8.lE+3 2.0E+3 1.9E+6 Co 58 0- 0- 0- 9.7E+3 0- 2.0E+4 5.lE+3 2.lE+6 Co 60 0- 0- 0- 3.7E+4 0- 7.3E+4 3.3E+4 1.2E+8 Sr 89 0- 0- 5.0E+4 4- 2.6E+4 7.7E+3 3.lE+4 Sr 90 0- 0 0- 1.0E+6 0- 8.lE+5 5.5E+5 1.3E+6 Zr 95 0- 0- 6.3E+4 0- 1.lE+5 9.7E+3 1.6E+6 Nb 95 0- 0 0- 2.4E+5 0 4.5E+5 2.8E+3 1.6E+6 Ru 103 0- 0- 0- 4.2E+5 7.6E+5 2.8E+3 1.9E+6 Te 129m 0- 0- 0- 6.0E+5 0- 4.5E+5 6.4E+3 7.6E+5 Cs-134 0- 0- 0- 1.4E+5 0- 1.2E+5 4.7E+3 3.8E+7 Cs 136 0- ' 0- 5.lE+3 0- 4.3E+3 8.1E+2 8.3E+5 Cs 137 0 0- 0- 1.3E+5 9.5E+4 3,4E+3 5.7E+7 Ba 140 0- 5.lE+3 0- 4.3E+3 7.0E+3 1.2E+5 O Ce 141 Ce 144 0-0- 0-0- 0-1.5E+3 1.8E+4 0-0- 2.4E+3 3.0E+4 2.0E+3 4.3E+4 7.9E+4 4.3E+5 I 131 0- 0- 6.6E+5 0- 4.AE+5 6,6E44 7.0E+5 I -132 0- 0- -0 -0 0 0- 6.3E+2 6.8E+3 1 133 0- 0- 0- 1.6E 2 0- b.7E 3 1.2E+4 1.3E+4 1 -134 0- 0- 0- -0 0- 1.6E42 2.5E+3 1 135 0- -De 1.lE-18 6.4E 19 2.5E+3 1.4E+4 UN ID 0- 0- 1.lE+5 9.5E+4 4.8E+3 4.2E46 Inhalation Pathway, units = "C / Food & Ground Pathway, uni.ts = I" " " *" C /s c O S023 0DCH j 2 70 Revision.23 02-28 91 L- _
TABLE 2-14 DOSE PARhiETER R, FOR SECTOR E Page 3 of 3 Pathway Deer Consumep Distance 1.2 miles X/Q = 3.7E 7 sec/m D/Q = 8.3E 9 m Infant Child . Teen Adult Inhala- food & Inhala- Food & Inhala. Food & Inhala. Food & 4 Radio- tion Ground tion Ground tion Ground tion Ground i Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H3 0- 0 2.8E+1 0- 2.3E+1 3.5E+1 3.9E+1 Cr 51 0- 5.0E+4 0- 1.0E+5 3.9E+2 3.2E+5 Hn 54 0- 0- 7.7E+5 0- 1.4E+6 3.8E+4 4. l E. 7 Co 57 0- 0 4.6E+6 0 8.0E+6 1.0E+4 2.3E+? Co 58 0- 0- 9.6E+6 0- 1.9E+7 2.5E+4 4.7Ed Co 60 0- - 0 0- 2.6E+7 0- 7.2E+7 1.6E+5 7.2E48 Sr 89 0- 4.9E+7 0- 2.6E+7 3.8E+4 3.lE+7 Sr 90 0- 0- 1.0E+9 0 8.0E+8 2.7E+6 1.2E+9 < Zr 95 0- 0- 6.2E+1 0- 1.1E+8 4.8E+4 2.0E+8 Nb 95 0 0- 2.3E48 0- 4.5E+8 1.4E+4 8.2E+8 Ru 103 0- - 0- 0- 4.2E+8 0- 7.5E+8 1.4E+4 1.3E+9 Te 12Sn - 0- 0- 5.9E48 0- 4.5E+8 3.2E+4 6.4E48 Cs 134 r 0 1.4E+8 0- 1.2E+8 2.3E+4 3.4E.8 (s 136 -0 0- 5.lE+6 0- 4.2E+6 4.0E+3 9.5E46 Cs 137 0- 0- 1.3E+8 9.3E+/ 1.7E+4 4.0E+8 Ba 140 0 5.0E+6 0- 4.2E+6 3.5E+4 7.4E+6 O Ce 141 Ce 144 0-0
. 0-0-
- 1. 5 E46 1.8E+7 0-0-
2.4E+6 2.9E+7 9.9E+3 2.lE+5 4.2E46 4.9E+7 1 131 0- 0- 6.5E+8 0- 4.3E+8 3.3E+5 5.9E+8 1 -132 0- 0- 0- 3.1E+3 3.4E+4 1 133 0 - 0 0- 1.6E+1 0 B.6E+0 5.9E+4 6.7E*4 1 134 0- 0- 0- 0- 0- 8.2E+2 1.2E+4 I 135 0- 0- 1.lE 15 0- 6.3E 16 1.2E+4 6.9E+4 UN ID- 0- 1.1E+8 0- 9.4E+7 2.4E+4 1.4E+8 i e m
, InhalationPathway, units-{j(yr Food L Ground Pathway, units I* IImrem/vri pC O $023-0DCM 2 71 Revision 23 1 02 28 91
,-- .__,d
. 1 TABLE 2-15 DO5E PAPANETER R, FOR SECTOR F
-,_ Page )_ of 4 Pathway San Onofre S} ate Park Guard Shack Distance 0.8 X/Q 8.6E 7 sec/m D/0 7.5Emiles' 9 m' infant Child Teen Adult Inhala- Fo>d & Inhala. Food & Inhala- Food & Inhala. Food &
Radio. tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H3 0- 0 0- 0 0- 0- 2.2E+2 0- ! Cr 51 0 0- 0 0- 0- 0- 2.5E+3 0.0E4 5 l Mn 54 0- 0- 0- 0- 0- 0- 2.4E45 2.4E+8 i Co 57 0- 0 0- 0- 0- 6.3E+4 5.9E+7 i ! Co 58 0- 0- 0 +0- 0- 1.6E+5 6.5E+7 \ Co 60 0 0- 0 0- 0 7- 0- 1.0E+6 3.7E+9 D l Sr 89 0- 0- 0- 0- 0- 2.4E+5 3.7E+3 b Sr 90 0- -De 0- 0 0- 0- 1.7E+7 0-Zr 95 0- 0- 0- 0- 0- 3.0E+5 4.3E+7 i Nb 95 0- 0- 0- 0 0- 0- 8.6E+4 2.3E+7 Ru 103 0- 0 0 0- 0- 0 8.6E+4 1.9E+7 Te 129m 0- 0- 0- 0- 0- 0 2.0E+5 3.4E+6 Cs 134 0- 0- 0- 0- 0- 1.5E+5 1.2Ev9 l Cs 136 0- 0- 0- 0- 0- 0- 2.5E+4 2.6E+7 Cs-137 0- 0- 0- 0- 0- 1.lE+5 1.8E+9 Ba 140 0- 0.. 0 0- 2.2E+5 3.5E+6 O Ce-141 Ce-144 0-0 0-0 0-0- 0-0- 0-0- 0-0- 6.2E+4 1.3E+6 2.3E46 1.2E+7 I -131 0- 0- 0- 0. 0- 0- 2.0E+6 2.9E+6 1 132 0* 0.- 0- 0- 0- ~0- 2.0E+4 2.lE+5 1 -133 0- 0- 0- 0- 0- 0- 3.7E+5 4.2E+5 I 134 0- 0- 0- 0- 5.lE+3 7.7E+4 1 -135 0- 0 0- 0- 0- 7.7E+4 4.3E+5 UN !D 0- 0- 0- -0 0- 1.5E+5 1.3E+8 Inhalation Pathway, units Food &GroundPathway,uriits- " " Ci/sjc O 5023 0DCM 2 72 Revision 25 02 28-92
l' IA!!LE 2-15
- 005E PALME7ER R iFOR SECTOR F Page 2 of 4 O
Pathway - Border Patro) fneckpt. Distance = 1.8 miles4 X/Q = 2.4E 7 sec/m 0/0 = 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 0 0 0 0- 0 0- 3.6E+2 0 Cr 51 0- 0- 0- 0- 0- 0- 4.1E+3 1.3E+6 Hn 54 0- 0- 0- 0 0- 0- 4.0E+5 3.9E+8 Co 57 0 0- 0- 0 0- 0- 1. lE4 5 9.8E+7 Co 58 0- 0 0- -0 0- 2.6E+5 1.lE+8 Co 60 0- 0 0 :0- 0- 1.7E+6 6.lE+9 Sr 89 0 0- 0- 0- 4.0E+5 6.2E+3 Sr 90 0- 0 0 0 0- 2.8E+7 0-Zr 95 0- 0- 0- 0- 0- 5.0E45 7.2C+7 Nb 95 0- 0- 0- 0 0- 0- 1.4E+5 3.9E+7 Ru 103 0- 0- 0- 0- 0- 1.4E+5 3.lE+7 Te 129m 0- 0 0- -0 0- 3.3E45 5.6E46 Cs-134 0- 0- 0- 0- 0- 0- 2.4E+5 1.9E+9 Cs-136 0- 0- 0 0- 0 0- 4.2E+4 4.3E+7 Cs 137 0- 0 0- 0- 0 0- 1.8E+5 2.9E+9 Ba 140 0- 0- 0- 0- 0- 3.6E+5 5.9E+6 O Ce 141 Ce 144 0-0- 0-0- 0-0 0-0- 0-0. 0-0- 1.0E+5 2.2E+6 3.9E+6 2.0E+7 1 131 0- 0- 0- 0- 0- 3.4E+6 4.9E+6 1 132 0- 0- 0- 0- -0 0- 3.3E+4 3.5E+5 1 133 0- 0- 0 0- 6.lE+5 7.0E+5 1 134 0- 0- 0- 0- 0- 8.5E+3 1.3E+5 1 -135 0- 0- 0- 0- 1.3E+5 7.2E+5 UN-lD 0- 0- 0- 0- 0- 0- 2.5E+5 2.lE+8 InhalationPathway, units ="C1/m!" p Food & Ground Pathway, units IS
- P'*/ " I pCi/sec O S023 0DCH 2 73 Revision 23 02 28 91
TAFLE 2 lh D0$E PARAMETER R, FOR SECTOR F Pace 3 of 4 O Pathway Sheep (Heat)' Distance 0.5 miles X/Q - 1.9E 6 sec/m D/0 1.7E 8 m d Infant Child Teen Adult Inhala- Food & Inhala. Food & Inhala. Food & Inhala- Food & Radio- tion Ground t'on Ground tion Ground tion Ground Nuclide Pathway Pathway Fathway Pathway Pathway Pathway Pathway Pathway H3 0- 0- 0- 1.5E+0 0- 1.2E+0 7.0E+0 2.lE+0 Cr 51 0- 0- 0- 5.lE+1 0- 1.0E+2 7.9E+1 1.6E+4 Mn 54 0- 0- 0 7.SE+2 0- 1.4E+3 7.7E+3 7.6E+6 Co 57 0- 0- 0- 4.7E+3 0- 8.1E+3 2.0E+3 1.9E+6 Co 58 0- 0- 0- 9.7E+3 0- 2.0E+4 5.lE+3 2.1E+6 Co 60 0- 0- 0- 3.7E+4 :0- 7.3E+4 3.3E+4 1.2E+8 Sr 89 0- 0- 0- 5.0E+4 0- 2.6E+4 7.7E+3 3.lE+4 Sr 90 0- 0 0- 1.0E46 0- 8.lE+5 5.5E+5 1.3E+6 Zr 95 0- 0- 0- 6.3E+4 0 1.lE+5 9.7E+3 1.6E+6 kb 95 0- 2.4E+5 4.5E+5 2.8E+3 '1.6E+6 Ru 103 0- 0- 0- 4.2E+5 0- 7.6E+5 2.8E+3 1.9E+6 Te 129m 0- -0 0- 6.0E+5 0- 4.5E+5 6.4E+3 7.6E+5 Cs 134 0- 0 0- 1.4E+5 0- 1.2E+5 4.7E+3 3.8E+7 Cs 136 0 0- 5.lE+3 0- 4.3E+3 8.lE+2 8.3E+5 Cs 137 0- 0- 0- 1.3E+5 9.5E+4 3.4E+3 5.7E+7 Ba 140 0- 0- 0- 5.lE+3 4.3E+3 O Ce 141 Ce 144 0-0- 0-0- 1.5E43 1.8E+4 0 0-2.4E+3 3.0E+4 7.0E+3 2.0E+3 4.3E+4 1.2E+5 7.9E+4 4.3E+5 1 131 0- 0- 0 6.6E+5 0- 4.4E+5 6.6E+4 7.0E+5 1 -132 0- 0- 0- 0- 0- 0- 6.3E+2 6.8E+3 1 133 0- 0- 0- 1.6E 2 0- 8.7C 3 1.2E+4 1.3E+4 1 134 0- 0- 0- 0- 0- 1.6E42 2.5E+3 1 135 0- 0- 0- 1.lE 18 0- 6.4E-19 2.5E+3 1.4E+4 UN ID 0- 0- 0- 1.lE+5 0- 9.5E+4 4.8E+3 4.2E+6 InhslationPathway, units-{"h" I* Food & Ground Pathway, units C /s ; O S023 0DCM 2-74 Revision 23 02 28 91
. _t
ID11 h11 DOSE PARAMETER Ri FOR SECTOR F Page 4 of 4 O Pathway =DeerConsumep Distance = 2.3E 1.4 miles' X/0 3.0E-7 sec/m 0/0 9 m' Infant Child Teen Adult Inhala. Food & Inhala- FMd & Inhala. rood & Inhala. Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pcthway H3 0- 0- 2.8E+1 0 2.3E+1 3.5E+1 3.9E+1 Cr 51 0 0 0 5.Or+4 0- 1.0E+5 3.9E+2 3.2E+5 Hn 54 0- 0 7~ 0- 1.4E+6 3.8E+4 4.lE+7 Co 57 0 0- 0 8.0E+6 1.0E+4 2.3E+7 Co 58 0- 0- 0- > 0- 1.9E+7 2.5E+4 4.7E+7 Co 60 0- 0- 0- 3.et+7 so- 7.2E+7 1.6E+5 7.2E+8 Sr 89 0- 0- 0- 4.9E+7 2.6E+7 3.8E+4 3.lE+7 Sr 90 0- 0- 0 1.0E49 0- 8.0E+8 2.7E+6 1.2E+9 Zr 95 0- 0- 0 6.2E+7 0- 1.lE+8 4.8E+4 2.0E+8 Nb 95 0 0- 0- 2.3E+8 0- 4.5E+8 1.4E+4 8.2E+8 Ru-103 0- 0- 0- 4.2E+8 0- 7.5E+8 1.4E+4 1.3E+9 Te 129m 0- 0- 0- 5.9E+8 0- 4.5E+8 3.2E+4 6.4E+8 Cs 134 0- 0- 1.4E48 0- 1.2E+8 2.3E+4 3.4E+8 Cs 136 0- 0- 5.lE+6 0- 4.2E+6 4.0E+3 9.5E46 Cs 137 0- 0- 0- 1.3E+8 0 9.3Es? 1.7E+4 4.0E+8 Ba 140 0- 0- 0- 3 5Et4 O 0 5. 0E+ 6 4.2E+6 7.4E+6 Ce 141 0- 0 0- 1.5E+6 0- 2.4E+6 9.9E+3 4.2E+6 Ce 144 0- 0- 1.8E+7 2.9E+7 2.lE+5 4.9E+7 1 131 0 0 6.5E+8 0- 4.3E+8 3.3E+5 5.9E+8 I -132 0- 0- 0- 0- 3.lE+3 3.4E+4 1 -133 0- 0- 0- 1.6E+1 0- 8.6E+0 5.9E+4 6.7E+4 1 134 0 0- 0- 0- 0- 8.2E+2 1.2E+4 1 135 .0- 0- 0- 1.lE 15 0- 6.3E 16 1 2E+4 6.9E+4 UN 10 0- 1 lE+8 0- 9.4E+7 2.4E+4 1.4E+8 Inhalation Pathway, units = yr j l Food & Ground Pathway, units " l I* CY/sc O S023 00CM 2-75 Revision 23 02-28-91
l IAELLli 005E PARAMETER Ri FOR SECT 0k G Pace ] of 4 O Pathway X/0 San Onofre $} ate Beach Campground 7.7E-7 sec/m Distance 0.8 milesd D/0 = 3.9E 9 m Infant rhild Teen Adult inhala- Fooi & Inhala- Food & Inhala- Food & Inhala- food & Radio- tion Ground tion Grcund tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H3 8.0E+1 0- 1.4E+2 0- 1.6E+2 0- 2.9E+2 0- i Cr 51 1.6E+3 5.7E+5 2.lE+3 5.7E+5 2.6E+3 5.7E+5 3.3E+3 1.lE+6 , Hn 54 1.2E+5 1.7E+8 1.9E45 1.7E+8 2.4E+5 1.7E+d 3.2E+5 3.2E+8 l 1 Co 57 4.7E+4 4.2E+7 6.3E44 4.2E+7 7.2E+4 4.2E+7 8.4E+4 7.8E+7 Co 58 9.6E44 4.7E+7 1.4E+5 4.7E47 1.7E+5 4.7E+7 2.lE+5 8.7E+7 Co 60 5.6E+5 2.7E+9 8.7E+5 2.7E49 1.1E+6 2.7E+9 1.4E+6 4.9E+9 Sr 89 2.5E+5 2.7Ed 2.7E+5 2.7E+3 3.'0 E+ 5 2.7E+3 3.2E+5 4.9E43 Sr 90 5.0E+6 0- 1.2E+7 0- 1.3E+7 2.3E+7 0-Zr 95 2.2E+5 3.lE+7 2.8E+5 3.lE+7 3.3E+5, 3.lE+7 4.0E+5 5.7E+7 Nb 95 5.9E+4 1.7E+7 7.6E+4 1.7E+7 9.3E+4 1.7E+7 1.2E+5 3.lE+7 Ru 103 6.8E+4 1.3E+7 8.2E+4 1.3E+7 9.7E+4 1.3E+7 1.2E+5 2.5E+7 f. Te 129m 2.1E+5- 2.4E.6 2.2E+5 2.4E+6 2.4E+5 2.4E 6 2.6E45 4.5E+6 , Cs 134 8.7E+4 8.4E+8 1.3E+5 8.4E48 1.4E+5 8.4E48 1.9E+5 1.6E+9 Cs 136 1.7E+4 1.9E+7 2.lE+4 1.9E+7 2.4E+4 1.9E+7 3.3E+4 3.4E+7 Cs 137 7.5E+4- 1.3E+9 1.1E+5 1.3E+9 1.0E+5 ' l.3E+9 1.4E+5 2.3E+9
+ 8a 140 2.0E+5 2.5E+6 2.lE+5 2.5E46 2.5E+5 2.5E+6 2.9E+5 4.7E+6 Ce 141 6.4E+4 1.7E+6 6.7E+4 1./E+6 7.6E+4 1.7E+6 8.3E+4 3.lE+6 i Ce 144 1.2E+6 8.6E+6 1.5E+6 8.6E+6 1.6E+6 8.6E46 1.8E+6 1.6E+7
. I 131 1.8E+6 2.lE+6 2.0E+6 2.lE+6 1.8E+6 2.lE+6 2.7E+6 3.9E+6 1 132 2.lE+4 1.5E+5 2.4E+4 1.5E+5 1.9E+4 1.5E+5 2.6E+4 2.8E+5 1 133 4.4E+5 3.0E+5 4.7E+5 3.0E+5 3.6E45 3.0E+5 4.9E+5 5.6E+5 i
! -134 5.5E+3 5.5E+4 6.3E+3 5.5E+4 4.9E+3 5.5E+4 6.8E43 1.0E45 1 135 8.6E+4 3.lE+5 9.8E+4 3.lE+5 7.7E+4 3.lE+5 1.0E+5 5.8E+5 UN IG 8.0E+4 9.2E+7 1.2E+5 9.2E+7 1.5E+5 9.2E+7 2.0E+5 1.7E+8 ,
m Inhalation Pathway, units = "g]j(yr I* ' Food & Ground Pathway, units C /se O S023 0DCH 2 76 Revision 25 02 28 92
IABLE 2 16 005E PARAMETER R, FOR SECTOR G Pace 2 of 4 r PathwayHwyPatrolWhghStation Distance = 2.0 miles ' X/Q = 2.0E 7 sec/m D/0 a b.5E 10 m' infant Child Teen Adult Inhala. Food i inha14- Food i Inhala. Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway + H3 0- 0- 0- 0 0- '0- 2.9E+2 0* Cr 51 0- 0- 0 0- 0- 0 3.3E+3 1.lE+6 Mn 54 0 0- 0- 0- =0- *0- 3.2E*5 3.2E 8 Co 57 0- U- 0 0- 0 0 8.4E+4 7 . 8 '.+ 7 Co 58 0- 0- 0- 0- 0- 0- 2.1E+5 8.iE+7 Co 60 0 0- 0 0- 0- 0- 1.4E+6 4.9E+9 Sr 89 0 0 0- 0- 20 0- 3.2E+5 4.9E+3 Sr 90 0- 0- 0- 0- 0- 2.3E+7 Zr 95 0- 0- 0- 0- 0- +0- 4.0E+5 5.7E+7 Nb 95 0- 0- 0- 0 -0 0- 1.2E+5 3.lE+7 Ru 103 0- 0- 0 0- 0- 0- 1.2E+5 2.5E+7 Te 129m 0- 0- 0- 0- 0- 0- 2.6E+5 4.5E+6 Cs 134 0- 0- 0 0- 0 0- 1.9E+5 1.6E+9 Cs 136 0- 0- 0- 0- 0- 0- 3.3E+4 3.4E+7 Cs 137 0- 0- 0- 0 0- 0- 1.4E+5 2.3E+9 Ba 140 0- 0 0- 0- 0- 0- 2.9E45 4.7E+6 O Ce 141 Ce-144 1 131 0-0- 0-0- 0-0- 0-0- 0 0-0- 8.3E+4 1.8E+6 3.lE46 1.6E+7 0 0- 0- 0.. 0- 2.7E+6 3.9E+6 3 1 132 0 0- 0- 0- 0- +0- 2.6E+4 2.8E+5 1 133 0- 0- 0- 0- 4.9E+5 5.6E45 1 134 0- 0- 0- 0- 0 6.8E+3 1.0E+5 1 135 0- 0- 0- 0- 0- 0- 1.0E+5 5.8E+5 UN ID 0- 0- 0- 0- 2.0E+5 1.7E+8 Inhalation Pathway, units = ]j"(7" . Food & Ground Pathstay, units I* IImrem/vri pC ' O - S023-0DCM 2 77 Revision 23 02 28-91 l
-. . - , ...--. ,._._., --. .., -. ,,. . . _ ,,m- - . , , . - - - . . ,n-,.,- .- -
TABLE 2-16 DOSE PARAMETER R, FOR SECTOR G Pace 3 of 4 Pathway - Sheep (Meat)3 Distance 2.7 miles X/Q = 2E 7 sec/m D/0 4.8E-10 m-r Infant Child Adult } , Teen 9 Inhala- Food & Inhal a- Food & Inhala- Food 5 Inhala- Food & Ra- . tion Ground tion Ground tion Ground tion Ground
, Nuciidt Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway 9
j 0- 1.5E+0 1.2E+0 ' 7.0E+0 E.1E+0 t i. 0- 5.lE+1 0- 1.0E+2 7.9E+1 2.6E+4 l" 0- ' BE+2
. 1.4E+3 7.7E+3 7.6E+6
- 4.7E+3 0- 8.1E+3 2.0E+3 1.9E+6 4 - 0- 0- 9.7E+3 2.0E+4 5.lE+3 2.lE+6
+v . J- 3.7E+4 0- 7.3E+4 3.3E+4 1.2E+8 s !c -0 5.0E+4 :0- 2.6E+4 7.7E+3 3.lE+4 Sr 0- 0- 0- 1.0E+6 0- 8.lE+5 5.5E+5 1.3E+6 j Zr-h i + 0- 6.3E+4 0- 1.lE+5 9.7E+3 1.fE+6 Nb-9! t 2.4E+5 0- 4.5E45 2.8E+3 1.6E+6
< Ru-H.3 4.2E+5 7.6E+5 2.8E+3 1.9E+6 s Te.'.29m 6.0E+5 4.5E*5 6.4E+3 7.6E+5 0 134 1.4E+5 1.2E+5 4.7E+3 3.8E+7
!;i Cs 136 ! 5.1Et3 4.3E+3 8.lE+2 8.3E+5 Cs-137 1.3E+5 9.5E+4 3.4E+3 5.7E+7 1 Ba-140 0- 5.1E+3 4.3E+3 7.0E+3 1.2E+5 @
h N-141 Ce-144 1 131 0-1.5E+3 1.8E+4 2.4E+3 3.0E+4 2.0E+3 4.3E+4 7.9E+4 4.3E+5 6.6E+5 4.4E+5 6.6E+4 7.0E+5 , I -132 0- 6.3E+2 6.8E+3 >- 1 -133 %- 2 0- 1.6E-2 8.7E-3 1.2E+4 1.3E+4 1 -134 ,
-0 1.6E+2 2.5E+3 1 -135 3 1.lE 18 6.4E 19 2.5E+3 1.4E+4 ~
UN-ID 1.1E,5 0- 9.5E+4 4.8E+3 4.2E+6 m O m.e. t Inhalation Pathway, units = [I Food L Ground Pathway, units I* " " Ci/sjc O 5023 00CM 2-78 Revision 23 02-?8-91
- ..- - - -- . . .. . . ~~-. -- - .. . - .
-TABLE 2-11 DOSE PARAMETER R, FOR SECTOR G Pathway Deer Consume [ Distance - 3.3 miles X/Q 8.8E-8 sec/m D/0 - 3.2E 10 m
infant Child Teen Adult Inhala- Food & Inhala- Food & 'nhala- Food & Inhala- Food & Radio- tion Ground tion Ground tion Ground tion Ground Nuclide Pathway Pathway Pathway Pathway Pathway Pathway Pathway Pathway H -3 0- 0- 2.8E+1 0- 2.3E+1 3.5E+1 3.9E+1 Cr 51 0- 5.0E+4 0- 1.0E+5 3.9E+2 3.2E+5 Mn 54 0- 7.7E+5 1.4E+6 3.8E+4 4.1E+7 Co-57 0- 0 4.6E+6 0- 8.0E+6 1.0E+4 2.3E+7 C0-58 0- 0- 0- 9.6E+6 0- 1.9E+7 2.5E+4 4.7E+7
-Co 60 0- 0- 3.6E+7 :0- 7.2E+7 1.6E+5 7.2E+8 Sr 89 0- 0- 0- 4.9E+7 2.6E+7 3.SE+4 3.1E+7 Sr-90 0- 1,0E49 0- 8.0E+8 2.7E+6 1.2E+9 Zr-95 0- 0- 6.2E+1 0- 1.lE+8 4.8E+4 2.0E+8 Nb 95 0- 2.3E+8 0- 4.5E+8 1.4E+4 8.2E+8 Ru-103 -0 4.2E+8 0- 7.5E+8 1.4E+4 1.3E+9 Te-129m 0- 0- 5.9E+8 0- 4.5E+8 3.2E-4 6.4E-8 Cs-134 0- 1.4E+8 1.2E+8 2.3E+4 3.4E+8 Cs-136 5.1E+6 4.2E+6 4.0E+3 < 9.5E+6 Cs 137 1.3E+8 0- 9.3E+7 1.7E+4 4.0E+8 Ba 140 0- 5.0E+6 O Ce-141 Ce-144 0-0-
0-1.5E+6 1.8E+7 0-4.2E+6 2.4E+6 2.9E+7 3.5E+4 9.9E+3 2.lE+5 7.4E+6 4.2E+6 4.9E+7 I -131 6.5E+8 4.3E+8 3.3E+5 5.9E+8 I -132 0- 3.lE+3 3.4E+4 I -133 0- 1.6E+1 0- 8.6E+0 5.9E+4 6.7E+4 I -134 8.2E+2 1.2E+4 I -135 1.1E-15 0- 6.3E-16 1.2E+4 6.9E+4 UN-ID 1.lE+8 0- 9.4E+7 2. 4 E+ 4 1.4E+8 inhalation Pathway, units E C/ Food & Ground Pathway, units I* " C1/se O- . S023-00CM 2-79 Revision 23 02-28-91
\ 2.9 TOTAL DOSE CALCULATION 5 2.9.1 Total Dese to Most Likely Hember of the Public
~
The total annual dose or total cose commitment to any member of th+ public, due to releases of radioactivity and to radiation, from uranium fuel cycle souNes within 5 miles of the Site is calculated using the following expressions. This methodology is used to meet the dose limitations of 40 CFR 190 per twelve consecutive months. The transportation of radioactive material is excluded from the u dosa calculations. The Annual Total Dose is deter:.11ned monthly for maximum organ (gas
, & liquid), whole body (gas & liquid) and thyroid (gas & liquid) to verify that the Site total (Units 1, 2 and 3) is less than or equal to 25 mrem, 25 mrem, and 75 mrem respectively.
.1 Annual Total Oroan Dose (Q7e3 (01) ,
k 12 2/3 * , ( - 0) Dro7 (0) = L E t.p(0G)+ D p (Oli+ Di(OG) 3 j =1 l =1 where: , 3
- NOTE: 0 (OG) = 0 for (ane
**All to be sunned over the most recent 12 months.
n (2-21) Dj3 (OG) = K E C,3 R,, W, i =1 i - each isotope in specific organ category j - Units 1, 2 and 3 1 - months 1 - 12** X = 3.1688 E-2 Y'"#~ sec-Ci O S023-0DCM 2-80 Revision 21 02-15-90 1
. . . _ _ _ _ _ _ _ _ . , .,.~m _ __.m _ __ . __ . ._- - _ _ _ - _ - - -
2.9 TOTAL DOSE CRCULATIONS (Continued) 2.9.1 To'tal Dose to Most Likely Member of the Public (Continued) [ n, - number of isotopes in the specified organ category Cn - total particulate gas curies released for the month IR,,W, - controlling location factors from ODCM Tables 2 6, Units 1 and 2/3 Dp(OL) .. liquid organ dose for the specified organ in mrem for the month. [ Reference ODCM Units ?/3 (1-19), Unit 1 (1 13)] H 0l(OG)* = gas organ dose form tritium in mrem for the month. 3
.2 $nnual Tctal Whole Body Dos.g_ftniWjl (2-22)
D7n(WB) = I E 'Df(WBL)+ Di(OG) - 0.9 Dp(y) -0(DIRECT) 3 ' l=1 j=1 where: j- Units 1, 2 and 3 1- months 1 - 12, to be summed over the most recent 12 months O Dp(WBL) - liquid whole body organ dose in mrem for the whole month. (1 13)] (Reference ODCM Units 2/3 (1-19), ODCM Unit 1 u3 D"i(OG) 3
- gas organ dose from tritium in mrom for the month.
(from (2-21)) Dp (y) = gamma air dose in mrad for the month. 0.9 converts mrad to mrem. [ Reference ODCM Units 2/3 (2-74, ODCM Unit 1 (2-10)] (2-23) n 4 I D(bkgd), E" D (Direct) = I max (D(beach),] .0342 q =1 - p = for all TLDs.per quarter q = for Quarters 1-4 S023-00CM 2-81 Revision 21 02-15-90 . . ._ . - , . - . ~
l l
\
2.9 TOTAL DOSE CALCULATIONS (Continued) 2.9.l'.2 Ann!Ld_Iotal Whole Body Dose D io ,.(yR). (Continued)
- Direct Radiation The direct radiation levels are evaluated most recently using cadmium covered TLDs. The TLDs are placed at 59 locations around -
the site. The avcrage dose from TLDs 5 to 50 miles from the site is usec as background. These site', are subject to change. he background is subtracted fr6m the highest reading plant surrounding area TLD. This value is the direct dose but must be prorated by the occupancy factor. Example: beach time of 120 hours, or 8 hours for landward occupancy. yr yr
,3 anD.qp1 Total Thyroid Dose 0,n, (T)
~
12 2/3 ,
, 01 ,3(T) = E E Dp (OG) + Of(OL) 11 j 1 where:
j= Units 1, 2 and 3 1- months 1 - 12, to be summed over the most recent 12 months Op-(OG) = thyroid organ dose fro.n gasecus-iodine for the month in mrem. (from 2-21) Dp (OL) = liquid thyroid organ dose for the month in mrem. (Reference ODCM Units 2/3 (1-19), Unit 1 ODCM (1-13)] 4 r-i i [.. L 5023 00CM 2-82 Revision 21 , 02-15-90 g-
3.0 PROJECTED DOSES l
? 3.1 Liqui / Pose Projection The methodology used for projecting a liquid dose over 31 days for Specification 1.3.1 is as follows:
- 1. Determina the monthly total body and organ doses resulting from releases during the previous twelve months.
- 2. Projected dose - Previous 12 months' dose divided by 12 for the total body and each organ.
3.2 Gaseous Lose Projectior. The methodology used for projecting a gaseous dose over 31 days for Sracification 2.4.1 is as follows: lVO
- 1. Determine the monthly gamma, beta and organ dose resulting from releases during the previous twelve months.
- 2. Projected dose Previous 12 months' dose divided by 12 for the gamma, beta and organ doses.
l l l 1 s I f
- 5) ._
~
S023-0DCM 3-1 Revision 22 1 00-02-90
4.0' EOUTPMENT 4.1 RADIOACTIVE LIO1110 EFFLUENT MON TORING INSTRUMENTATION
)~ SPECIFICATION 4.1.1 The radioactive liquid effluent monitoring instrumentation channels shown in Table 41 shall be OPERABLE with the':
alarm / trip setpoints set to ensure that the limits of Specification.1.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with Section 1.4 APP (ICABILITY: At all times ACTION:
- a. With a radioactive licuid effluent monitoring instrumentation channel alarm /t"ip setpoint less conservative than requir.ed by tLa 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 q inoperable ft,r greater than 30 days, explain in the next Q Semiannuni Radioactive Effluent Release Ceport why the inoperellity was not corrected in a timely manner.
- c. With less than the minimum number of radioactive liqu'id affluent monitoring instrumentation channels OPERA 8LE and either the appropriate ACTION items in Table 4-1 not taken or the necessary surveillances not performed at the specified frequency prescribed _in Table 4-2, an INVESTIGATIVE REPORT shall be prepared which identifies the cause(s) for the event and defines the corrective actions to be takri to preclude recurrence of the event.
, SURVEILLANCE RE0VIREMENTS
.1 Each radioactive ligt.id effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE C'<tECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4-2.
r .2 At least once per 4 hours, all pumps required to be. providing dilution to meet the site radioactive effluent concentration limits of Specification 1.1.1 shall be determined to be operating and providing dilutior, to the discharge structure. 10 S023-00CM 4-1 Revision 23 02-2e3-91
.] 0 '%. TABLE 4-1 EM10 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM Cl!ANNELS JNSTRUMENT* OEL'tAILt.E _ E1103
- 1. GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM TEPJilNATION OF RELEASE
- a. Liquid Radwaste Effluent I.ine - 2/3 RT-7813 1 28
- b. Steam Generator Blewdown (Neutralization Sump),
. Full Flow Condensate Polisher Effluent Line - 2(3)RT-7817 1 29
- c. Turbine Plant Sumps, Auxiliary Building Sump, Component Cooling Water Semps, Storage Tank Area Sumps ld 30 I Effuent Line- 2(3)RT-7821 1
- d. Steam Generator (E088) Blowdown Effluent Line - 2(3)RT6759 1 29
- e. Steam Generator (E089) Blowdown Effluent Line - 2(3)RT6753 1 29
- 2. FLOW RATE MEASUREMENT DEVICES
- a. Liquid F.adwasto Effluent Line 1 31
- b. Steam Generator blowdown (Neutralization Sump),
Full Flow Condensatc Polisher ' Effluent Line 1 31
- c. Steas. Generator (E088) Blowdown Bypass Effluent Line 1 31
- d. Steam Generator (E0991 R10wdown Bypass Effluent Line 1 31 S023-0DCM 4-2 Revision 25 02-28-92
i TABLE 4-1 (ContinurB 4 TABLE NOTAT1QH a *- Mohlter Recorders are not required for the Operability of the monitor. providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback signal . - alarm capability (if applicable),) proper response (based upon surveillanceAs lo requirements) and isolation function (if applicable), the loss of the recorder does not render the monitor inoperable. . ACTION 28--- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases may continue provided that prior to initiating a release:
- a. At hast two independent samples are analyzed in ,
accordance with Specification 1.1.1 and
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculation and discharge line valving; Otherwise, suspend reles;e of radioactive effluents via this pathway.
ACTION 29 - With the number of r.hannels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may contiaue provided grab samples are analyzed for gross radioactivity (beta or gama) at a limit of detection of at least 10 microcuries/ gram: O
- a. At least once per 8 hours when the specific activity of the secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT I 131;
- b. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 microceies/ gram DOSE EQUIVALENT.1-131; or
- c. .
-Lock closed valve HV-37/3 and divert flow to T-064 for
=
processing as liquid radwaste. Ati10N 30 - With the number of channels' OPERABLE less than required by the Minimum _ Channels OPERABLE recuirement, effluent releases via this pathway may continue providec that, at least once por 12 hours, grab samples are collecteo and analyzed within 4 hours of L collection time for-gross racioactivity-(beta-or gamma) at a -limit of detection of at least- 10 microcuries/ml or lock closed valve 52(3)2419MUO77 or 52(3)2419MUO78 and divert flow to the radwaste sump for processing as'11guid radwaste. ACTION 31 - With the number of channels'0PERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway. may enntinue provided the flow rate is estimated at least once per. 4 hours during actual releases. Pump curves may be used to esti;nate flow. S023-00CM 4-3 Revision 22 l , 08-02-90 v
,r 3 A f^N V V V TABLE 4-Z RADI0 ACTIVE LIQUID EFFLUENT (CNITORING INSIRUMENTATION SURVEILL,iNCE REQUIREMENTS CilANNEL C:lANNEL SOURCE CllANNELS IUNCTIONAL INSTRUMENT ** _.C_llE(_K_ CllECK CAllBRATION TEST
- 1. GROSS BETA Fi W9tA RADI0 ACTIVITY MONITORS
- PROVIDING Alf A AND AUTOMATIC TERMINATION 0F RELEASE
- a. Liquid Radwaste Effluents Line -
2/3 RT-7813 0 P R(2) Q(1)
- b. Steam Generator Blowdowr. (Neutralization Sump),
Full Flow Condensate Polisher Effluent Line - 2(3)ltT-7817 D M R(2) Q(1)
- c. Turbine Plant Sump, Auxiliary Building Sump, Compoinent Cooling Vater Sumps, Storage Tank Arer Sumps Effluent Line - 2(3)RT-7821 D H R(2) 78 (1)
- d. Steas Generator (E088) Blowdown Bypass Effluent'Line - 2(3)RT-6759 D M R(2) Q(1)
- e. Stem Generator (E089) Blowdown Bypass Line - 2(3)RT6753 D' M R(2) Q(I)
- 2. FLOW RATE MEASUREMENT DEVICES .
w
- a. Liquid Radwaste Effluent Line U(3) N.A R Q
- b. Steam Generator Blowdown (Neutralization Sump),
Full Flow Condensate Pollsher Effluent Line D(3) N.A R Q
- c. Steam Generator (E088) Blowdown Bypass Effluent Line D(3) M.A R Q
- d. Steam Generator (E0891 Blowdown Bypass Effluent Line 0(3) N.A R Q S023 ODCM 4-4 Revision 22 08-02-90
TABLE 4-2 (Coatinuedi TABLE NOTATIM f3 . V ** Monitor Recorders are not required for the Operability of the monitor, providng the inoperable recorder does not cause the monitor to become incperable (i.e , feedback signal). As long as the monitor has indication, alarm capability (if applicable), pr oer response (based upon surveillance
. requirements) and isolation function (if applicable), the loss of-the recorder does not render the monitor inoperable. )
l (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent l path isolation closure and Control Rc.om alarm annunciation if any of the t following conditions exist:* l
- 1. Instrument indicates measured levels above the alarm / trip setpoint. i
- 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 Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with HIST. These standards shall permit calibrating the system over its intended range of energy and measurteent range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. (3) CHANNEL CHECK shall consist cf verifying indication of flow during ceriods of release CHANNEL CHECK shall be made at least once per 24 hours on days on' which continuous, periodic, or batch releases are made.
*If the.inrtrument controls are not in the ope' D.e mode, procedures shall require that the channel be declared inoperable.
(v} S023-0DCM 4-5 Revision 22 08-02-90
. -_. . ._ ~ ~ .- - - -
4.0 E0VIPMENI 4.2 PAD 10AQ,TIVE GASE0US EFE.l&@LMCNITORING INSTRUMENTATI0ff SPECIUCATION 4.2.1 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 4-3 shall oe
.0PERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 2.1.1 are not exceeded.
The alarm / trip setpoints of these channels shall be determined in accordance with ODCM. APPLICABILITY: At all times ACTION:
- a. With a r:dioactive gaseous effluent coattoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable. .
- b. With less than the minimum number of radioactive gaseous effluent monibring instrumentation channels OPERABLE, take the ACTION shown in Table 4 3. Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument (s) remain A inoperable for greater than 30 days., explair. in the next U Semiannual Radioactive Effluent Release Report why the inoperability wac not corrected in a timely manner,
- c. With less than the minimum number of radioactive gaseous effluent monitoring instrumentatica channels OPERABLE and either the appropriate ACTION items in Table 4-3 not taken or the necessary surveillances not performed at the specified frecuency prescribed in Table 4-4, an INVESTIGATIVE REPORT shaU be prepared which identifies the cause(s) for the event and defines the corrective actions to be taken to preclude recurrence of the event. .
SURVEILLANCE Rf0VIREMENTS
.1 fach radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPEPABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4-4.
D O S023-00CM 46 Revision Z3 02 %
n . HADIDA?TIVE GASEGUS QFLUENT MONITORING INSTRUMENTATION
. MINIMUM CHAi1NELS OPERABLE APPLICABIL - ACTION lHSTRUMENT***
- 1. WiSTE GAS HOLDUP SYSTEM-
- a. Noble Gas Activity MonitorL-Providing Alarm and Automatic *- 35 1
' Termination of' Release -
i 2/3 RT-7808, 2 RT-7865-1 or
- 3 RT-!865-1
- 36
- b. Process Flow Rate Monitoring Device 1
- 2. CONDENSER EVACUATION SYSTEH
** 17
- a. Noble Gas Activity Honitor .2f,3)RT-7818 or 2(3)RT-7870-1 1 1 40
- b. Iodine Sampler ** 40
- c. Particulate Sampler 1
** 36 -
- d. Asscciated Sample Fiow Heascring Device 1 Process ~ Flow Rate Monitoring Device 1(1) 36 e.
- 3. PLANT YENT STACK
- 37 R
- a. Noble Gas Activity Monitor - 2/3 RT-7808, or 2RT-7865-1 1(3) gad 3RT-7865-1 .
- 40
'b. lodine Sempler 1(3)
- 1 3) 40 .
- c. Particulate Sampler
- 36
- d. Associated Sample flow Measuring Device 1 3)
- 2 2) 36
- e. Process Flow Rate Monitoring Device 4 .' CONTAINMENT PURGE SYSTEM
- a. Hoble Gas Activity Monitor - Providing Alarm and Automatic
- Termination of Release - 2(3)RT-7828, or 2(3)RT-7865-1 1 38
- 40
- b. Iodine Sampler 1
- 40
- c. Particulate Sampler I Process Flow Rate Monitoring Device 1
- 36
- d.
- 36
- e. Associated Sample Flow Measuring Device 1
$023-00CM 4 .7 Revision 25 02-28-92
~ - . -- . -
- - H IMLE 4-3 (Continued) l i
TABLE NOTATL0E 'l At all times.
** H0 DES 1-4 with any maii, iteam isolation valve ar d/or any main steam isolating bypass valve not fully closed. *** Honitor Recorders are not required for the Operability of the monitor, providing the inoperable recorder does not cause the monitor to become inoperable (i.e., feedback si As long as the monitor has indication, alarm capability (if applicab}'nal).e),properresponse(baseduponsurveillance requirements) and isolation function (if applicable), the ioss of the recorder does not render the monitor inoperable.
(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) 2/3RT-7808 is not equipped to monitor process flow. If 2RT-7865 and 3RT-7855 R is not available to continuously monitor plant vent stack flow, then comply with ACTION 36. (3) Due to unequal mixing in the Plant Vent Stack, both 2RT-7865 and 3RT-7865 are A required to be operable when 2/3RT-7808 is inoperable. ACTION 35 - With the number of channels OPERABLE less 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 qut'ified members of the Facility 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 recuirement, effluent releases via this pathway may continue providet the flow rate is estimated at laast . once per 8 hours. System design characteristics may be used 'o estimate flow. ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken et least once per 12 hours and these samples are analyzed for gross activity within 24 hours. ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway. S023-0DCM 4-8 Revision 25 02-28-92 n . -- ._.
. , _ . . - . . . . . . . - , , , ~ .- . .-
i 1 TABLE 4-3 (Continued) TABLE NOTATION O. ACTION 39 - Rema'ning in Technical Specifications. ACTION 40 - -With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the effected pathway may continue provided samples are continuously collected with auxiliary sampling equipment as required in Table 2-1. i i 7O ' i d R 4 5023-0DCM 4-9 Revision 22
- 08-02-90
, : gj
_ TABLE 4-4 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRtHENTATION SURVEILLANCE REOUIREMENTS. CHANNEt MODE FOR MIICH CilANNEL - SOURCE CliANNELS FUNCIIONAL SURiEILLANCE IffSIEUttm1*** CilECK CilECK CALIBPATION TEST IS REQUIRED
- 1. WASTE GAS liOLDUP SYSTEM
- a. Noble; Gas Activity Monitor -
Providing Alarm and Automatic , Termination of Release - 2/3 RT-7808, 2RT-7865-1, 3RT-7865-1 P P R(3) Q(1)
- b. Process Flow Rate Monitoring Device P N.A R Q
- 2. C0f'.0ENSER EVACUAT?ON SYSTEM
- a. Noble Gas Activity h alior - ,
2(3)RT-7818,2(3)RT-7370-1 0 M ~ R(3) Q(2) ^
- b. Iodine Sampler . W N.A N.A N.A
- c. Particulate Sampler W N_A N.A N.A
- d. Associated Sample Flor Me.asuring Device O N.A R Q
- e. Process Flow Rate Monitoring .
Device (2(3)RT-7870-1) D H.A R 0 C 5023-ODCH 4 10 Revision 22 08-02-90
i5 t b l TABLE 4-4 (Continued) 1 RADI0 ACTIVE L1001D EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS-CHANNEL MODE FOR WHICH CilANNEL SOURCE CilANNELS FUNCTIONAL. SURVEILLANCE CHECK - CllECK CALIBRATION - TEST IS REQUIRED INSTRUMENT ***
- 3. PLANT VENT STACK
- a. Noble Gas Activity Monitor - 0 M R(3) Q(2) h 2/3 RT-7808, 2RT-7865-1, 3RT-7865-1
- Iodine Sampler W N.A N.A N.A
- b. N.A *
- c. Particulate Sampler W N.A N.A
- d. -Associated Sample Flow
- I Measuring Device D N.A R Q
- e. Process Flow Rate Monitoring *
. Device . D N.A R Q
- 4. CONTAINMENT PURGE SYSTEM
- a. Noble Gas Activity Monitor -
Providing Alare and Automatic fermination of Release -
- 2(3)RT-7828,2(2)RT-7865-1 0 P(4) R(3) Q(1)
- Iodine Sampler ~ W N.A N.A, H.A
- b. *
- c. Particulate Sampler W N.A N.A N.A
- d. Process Flow Rate Monitoring *
'Cavice D H.A R Q .
- e. Associated Sample Flow
- Measuring Device D N.A R Q 5023-0DCM Revisien 22 4-11 00-02-90
TABLE 4 4 (Continued) g . ,1 ,,, 1,,,,,
*=
Modes 14 with any main steam isolation valve and/or any main steam isolating bypass valve not fully closeo.
*** Monitor Recorders 4re not required for the Operability of the monitor, providing the inoperable recorder does.not cause the monitor to become inoperable (i.e., feedback signal). As long as the monitor has indication, alarm capability (if applicable), proper response (based upon surveillance requirements) and isolation function (if applicable), the loss of the recorder does not render the menitor inoperable.
(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate verification of effluent path isolation closure and control room alarm annunciation if any of the following conditions exist:#
- 1. Instrument indicates measured level: sbove the alarm / trip setpoint.
- 2. Circuit failure.
3.- Instrument indicates a downscale failure. (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:# 1.- Instrument indicates measured levels above the alarm setpoint.
- 2. Circuit failure.
- 3. -Instrument indicates a downscale failure.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the referenco 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 inter..+: renge of energy and measurement range, for subsequent CHANNEL CALIB E ON, sources that have been related to
' the initial calibration shall be used.
(4) Prior to each release and at least once per month. T!T"the instrument controls are not set in the operate mode, procedures shall call for declaring the channel inoperable. O V ' S023-00CM 4-12 Revision 22 08-02-90
W 4.3 OPERABILITY OF RADIGACTIVE WASTE EQUIPMENT p cJ The flow diagrams defining the treatment paths and the components of the radioactive liquid, gaseous and solid waste management' systems are shown in Figures 4 5 thru 4-7. I a 4 - rD V 5023-00CM 4-13 Revistort 11 02-15 90
.- . ~ . - . _ _ _ _ . _ _ _ _ _ . _ _ , . - . _ , -
_.-.,_____.m . s. FIGURE 4 5 SONGS 2 & 3 RADI0 ACTIVE LIQUID WASTE TREATMENT SYSTEMS O Hain Storage Tank CCW Sump Area Sump Condenser (Batch) (Batch) A i I Aux Building Turb5ne v Sump a-r Plant Sump 3 -RT7821[+ (Continuous) _ (Continuous)
-. , y Neutralization +
- BPS 4 Sump RT 7817
..- 4 jg (Batch / Cont).
I I I HCS LCS (Batch) (Batch) A /\ FFCPD S/G E089 lRT6753
- RT 6759 + ,
s/G E080 CCW HX SAMPLED Saltwater * (Continuous) Radwaste Primary Tanks Radwaste becondary Tanks Primary Makeup Tanks 2/3 RT 7813 + , Condensate Monitor Tanks (Batch) f%d E O Raolation Monitor Intake NOTE: Monitor pathways are unit specific unless
. indicated to be common to Units 2 and 3. Outfall V
Pacific Ocean O S023-00CM 4 14 Revision 24 08 31 . , . . _
7- , Atcosphere Atmosphere mwspies e m~,,._ V[] - l Unit 3 Vent
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I - Unit 3 Building Unit 2 Building g Ventilation bhausts Ventilation Exhausts y G2s decay LIall 3. Condenser, Unit 2 fondenser tvacuatica Systera j l-fvacuatica Systes Tanks (6) 4 Radioactivity Honitor . 1G5 Units 2 and 3. figure 4'-6 Release pathways and monitors of ra<floactive gaseous ef fluents for 50: RT-7865 can be aligned to either containment purge or the plant vent stack (1) flGURE 4-6 SONGS 2 & 3 RADI0 ACTIVE GASEOUS WASTE TREATMENT SYSTEMS 5023-00CH 4-15 Revision 24 08-31-91
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<j 5.0 RADIOLOGICAL EWIRONMENTAL MONITORING 5.1 Monitorina Procram 'I SPECIFICATION 5.1.1 The rMiological environmental monitoring program shall be conducted as specified in Table 5-1. The requirements are applicable at all times.
A?PLIC ABILITv.;. At'all times ACTION:
- a. Should the radiological environmental monitoring program not be conducted as specified in Table 51, in lieu of any other report required by Techgical Specification (s) 6.9.1, prepare and submit to the Comission, in the Anr. val Radiological Operating Report (see Section 5.4), a description of tne reasons for not conducting the program as required and the plans for preventing a recurrence,
- b. Shculd the level of rWoactivity in an environmental sampling medium exceed the reporting levels of Table 5-2 when averaged over any calendar quarter, in lieu of any other report required by Technical Specification (s) 6.9.1, prepare and submit to the Commission, within 30 days from the end of the affected calendar quarter a Report pursuant to Technical Specification (s) 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:
(s concentration (1) limit level (1)
+ concentration (2) limit level (2)
+ . 1 1.0
- c. 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 potential annual dose to an individual is equal to or year limits of Specification (great.r than s) 1.2.1, theorcalendar 2.2.1 2.3.1, as appropriate. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological-Environmental Operating Report (see Section 5.4).
d.
~
With fresh leafy vegetable samples or fleshy vegetable samples unavailable from one or more of the sample locations required by Table 5-1, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the comission within 30 days, pursuant to Technical Specifications 6.9.2, a Special Report which identifies the cause of the unavailability of samples and identifies locations for obtaining replacement samples. The locations from which samples were unavailabic may then be deleted from those required by Table 5-1, provided the locations from which the replacement samples were obtair.ed a're added to the environmental monitoring program as replacement locations. O) Q S023-0DCM 5-1 Revision 22 08-02-90
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) lyRVEILLANCE' RE0VIREME I\
.1 The radiological environmental monitoring samples shall be cellected pursuant to Table 5-1 from the locations given in Tables 5-4 and 5-5 and Figure 51 and shall be analyzed pursuant to the requirements of Tables 51 and 5-3.
s- . 4 O.
'J SO23-00CH 5-2 Revision 22 08-02-90
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,, TABtE 5-1 RADIOL 0ti! CAL ENVIRONMENTAL MONITORING PROGRAM -
Exposure Pathway 'Humber of Samples Samp1;ag and and/or Sample and Samole locations
- Collection frecuency' Iyce and Frecuency nf Analyses
- 1. AIRBORNE Samples from at least Continuous operation Radioiodine cartridge. Analyze Radiotodine 5 locations. of sampler at least once per 7 days for I-131.
and 3 samples from offsite with sample collection Particulate sampler. Analyze for Particulates- locations (in different as required by dust gross beta radioactivity 2 24 hours sectors) of the highest loading, but at least following filter change. . Porform calculated annual average once per 7 days.d gamma isotopic" analysis on each ground level D/Q.
, sample when gross beta activity is
> 10 times the yearly mean of control
'l sample from the vicinity samples. ' Perform gamma isotopic of a comsunity having the analysis on composite (by loca8.lon) tt.e highest calculated sample at least or.re per 92 days.
annual average ground-level D/Q. I sample from a control laca-tion 15-30 km (10-20 miles) distant and in the least pre-valent wind direction' 9
- 2. DIRECT At least 30 locations includ- At least once per r.amma dose. At least once per 92 days.
RADIATION
- ing an inner ring of stations 92 days.
in the general area of the site boundary and an outer ring approximately in 'he 4 to 5 mile range frca the site with a staticn in each sector of each ring. The balance of the stations is in special - interest areas such as popula-tion centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations. 5023-0DCM 5-3 Revision 21 02-15-90
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i O O O TABLE 5-1 (Continued) i RADIOLOGICAL UlVIR0l#IDITAL MONITORING FROGitM Exposure Pathway Number of Samples Sampling and-and/or Sample and Sample locations' Collection frequingr* Iypg_3pd Trecuency of Analyses -
- 3. WATERBOPM:
- a. Oceaa 4 locations At least once per Gamma isotopic analysis of each month and composited' monthly sample. Tritium analysis quarterly of composite sample at least once per 92 days.
- b. Drinking 2 locations Monthly at each Gaassa isotopic and tritium location. analyses of each sample.
- c. Sediment 4 locations At least once per Gasna isotopic analysis of each I from 184 days. sample. '
Shorellne
- d. Ocean 5 locations At least once per Ganna isotopic analysis of each Bottom 184 days. sample.
Sediments l 5023-00CM 5-4 Revision 22 - 08-02-90
_...m. O - 0 O TABLE 5-1 (Continued) t. RADIOLOGICAL ElWIR0lWKMTAl. MONITORING PROGRAll Exposure Pathway Number of Samples Sampilng and And Sample locations' Colleclion freouency" lyoe and freegenCY of Analyses and/or Sample
- 4. INGESTION
- a. Nonalgratory 3 locations One sample in season, Gaauna isotopic analysis on
. Marine or at Icast once per edible portions.
Animals 184 days l' not seasonal. .* sample ~ i of each of ;e follow-ing species: . ,
- 1. Fish-2 adult species such as perch or sheephead. l
- 2. Crustaceae-such as ;
crab or lobster.
- 3. Mollusks-such as limpets, seahares or class.
- b. Local Crops 2 locations Representative Ganssa isotopic analysis on edible .
vegetables, normally portions semiannually and I-131. , I leafy and I fleshy analysis for leafy crops. collected at harvest time. At least 2 ; vegetables collected seslannually from each location. - } 5023-0DCM 5-5 Revision 21 - l 02-15-90 4
O O O IABLE 5-1 -(Continued) TABLE NOTAILON
- .a. Sample-locations are indicated on figure 5-1.;
- b. Gamma isotopic analysis means' the identification and quantification of gamma-emitting radionuclides that may be attributable to ths affluents from the facility. '
- c. The purpose of this sample is to obtain backgroundLinformation. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites which' provide valid background data may be substituted.
E d. Canisters for the collection of radiolodine in air are subject to channeling. These devices should be 4 carefully checked before operation in the fleid or several should be mounted in series to prevent loss of iodine.
- e. Regulatory'Gulde 4.13 provides alnimum acceptable performance criteria for thermolucinescence dosimetry.(TLD) systems used for environmental monitoring. One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter may.be considered to be one phosphor and two or more phosphors.in a packet may be considered as two or more dosimeters. Film badges should not be, l- used for. measuring direct radiation. ,
- f. Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquot at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly).
4 t e I
'5023 00CM 5-6 Revision 22 08-02-90
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. y O O O JAQ1E_53 REPORTING LEVELS FOR RADIDACTIVITY CONCEMUULTJO_N5 IN ENVIR0ftMENTAl,_5AMPLES A
Reporting Ievels Airborne Particulate Water or Gases Marine Animals local Crops Analysis (pC1/1) (pCl/m') (pCi/Kg. wet) (pti/Kg, wet) 84 - 3 2 x 10*(*3 Hn 1 x 10' 3 x 10' fe-59 4 x 19 1 x 10' Co-58 1 x 10' 3 x 10' Co-60 3 x 10' 1 x 10' - In-65 3 x 10' 2 x 10' Zr Nb-95 4 x 10' I-131 2 0.9 1 x 10' Cs-134 30 10 1 x 10' I x 10' Cs-137 50 20 2 x 10' 2 x 10' Ba La-140 2 x 10' I"I for drinking water samples. This is 40 CFR Part 141 value. i 5023-00CN l 5-7 Revision 21 02-15-90 l
~
O' O O TABLE 5-3 HMINUM VALUES FOR TIILLOWER I.lM115 0F DETECTION (LLDi i
' Airborne Particulate Water or Gases Marine Animals local Crops Sediment Analysis '(pCl/1) -(pC1/m') (pCi/Kg, wet) (pCi/Kg, wet) (pCi/Kg, dry)
' gross beta .4 1 x 10
H-3 2000 , Mn-54 15 130 fe-59 30 260 00-58, 60 15 130 In-65 30 260 Zr-95 30 Nb-95 15
- 1-131 l' 7 x 10 60 Cs-134 15 5 x 10-2 130 60 150 Cs-137 18 6 x 10 150 80 180 -
Ba-140 60 La-140 15 s 5023-00CM 5-8 Revision 21 02-15-90
TABLE 5 3 (Continued) TABLE NOTATION /3 The LLD is the smallest concentration of radioactive mate' rial in a sample !y ' a. that will be detected with 95% probability with 5% probability of falsely concluding that ; blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): 4.66 s* LLD = - E.V 2.22 x 10' Y exp (-Lit) where: LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volumt), se is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),
! is the counting efficiency (as counts per transformation),
V is the sample size (in units of mass or volume), (~T 2.22 x 10' is the number of transformations per minute per V microcurie, Y is the fractional radiochemical yield (when applicable), 1 is the radioactive decay constant for the particular radionuclide, and 6t is the elapsed time between midpoint of sample collection or end of the collection period and time of counting (for environmental samples, not plant effluents ). The value of s, used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance, In calculating the LLD for a radionuclide determined by gamma-ray Spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., potassium-40 in milk samples). Typical values of E.V,Y and At shall be used in the calculations. A V S023-0DCM 5-9 Revision 22 08-02-90
- - . = . . . . . _ _ . . . --
g ... TABLE 5-3 (Continuedl TABLE NOTAT108 lt should be recognized that the LLD is defined as an 1 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.*
- b. LLD for drinking water,
- c. Other peaks which are measurable and identifiable, together with the radionuclides in Table 5 3, shall be identified and reported.
'For a more complete discussion of the LLO, 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, 585-93 (1958). (3) Hartwell, J. K., ' Detection Limits for Radioisotr'r '" Counting Techniques,' Atlantic Richfield Hanford Company Repoe L'H 2537 (June 22,
~
1972). O IO S023 0DCM 5-10 Revision 21 ' l 02-15-90 y- - - - -
1 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING '(Continued) 5.2 LAND USE CENSUS SPECIFICATION 5.2.1 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest carden* of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles. For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles. APPLICABILITY: At all times ACTION-
- a. With a land use census identifying a location (s) which yields a calculated dose or dose comitment greater than the values currently being calculated in Specification 2.3.1, in lieu of any other report required by Technical Specification 6.9.~1, prepare and submit to the Comission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the new location (s).
- b. With a land use census identifying a location (s) which yields a calculated dose or dose comitment via the same Os exposure pathway 20 percent greater than at a location from which samples are currently being obtained in accordance with Section 5.1, in lieu of any other report required by Technical Specification 6.9.1, prepare and submit to the Comission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report which identifies the ,
new location. The new location shall be. added to the radiological environmental monitoring program within 30 days. The sampling location, excluding the control station location, having the lowest calculated does or dose enmitment via the same exposure pathway may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. SURVEILLANCE REOUIREMENTS
.1 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.
- Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.
O S023-00CM 5-11 Revision 22 08-02-90
5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (Continued) 5.3 INTERLABORATORY COMPARIFON PROGRAM SPECIFICATION 5.3.1 Analyses shall be performed on radioattive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission. APPLICABili'Y2 At all times ACTION:
- a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
SURVEllLANCE RE0VIREMENTI ,
.1 A summary of the results cotained as part of the above required Interlaboratory Comparison Program and in accordance with Section 5.4.1 of this document. shall be included in the Annual Radiological Environmental Operating Report (see Section 5.4).
O . O S023 0DCM 5-12 Revision 22 08-02-90
c__- . .. _. . _. _ _ . - - - . . - . . - - _ . -- - . - . _ . . - . - 5.0 RADIOLOGICAL ENYlRONMENTAL MONITORING (Continued) 5.4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPlRAT]Nr. REPORT
- 5.4.1 The anriual radiological environmental operating reports shall include sumaries, 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 shcIl 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 the problem and a planned course of action to alleviate the problem.
The annual radiological environmental operating reports shall include sumarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report 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 sumary description of the radiological environmental monitoring J 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 Program,. required by Section 5.3. A single submittal may be made for a multiple unit station, combining those sections that are comon to all units at the station. O S023-00CM 5-13 Revision 21 02-15-90
.-..._ _ m. . _._ . . _ . _ _ _ _ _ . . . - . . . _ _ _ . _ . . _ . - . . _ . _ _ _ ._ .
5.0: RADIOLOGICAL ENVIRONMENTAL' MONITORING (Continued) 5.5 SAMPLE LOCATIONS Sample Locations are The Radiological identified in Figure 5-1. Environmenta? These Monitorin$ocations sample are described in Tables 5-4 and 5 5 and indicate 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. O l l . l . l l O S023-00CM 5-14 Revision 21 02-15-90
^
t
Page 1 of 6 IABLE S-4 O RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- TYPE OF SAMPLE AND SAMPLING LOCATION *** (milesi DIRECTION
- Direct Radiation 1 City of San Clemente (Former SDGLE 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 Sluff (Adjacent to PIC #1) 0.7 WNW 11 Former Visitors' Center 0.3** NW 12 South Edge of Switchyard 0.2** E 13 Southeast Site boundary (Bl ") 0.4** SE 14 Huntington Beach Generating Station 37.0 NW 15 Southeast Site Boundary (Office Building) 0.2** SE 16 East Southeast Site Boundary 0.4** ESE 17 Transit Dose - -
IB ' Transit Dose - - 19 San Clemente Highlands 5.0 NNW 20 San Clemente Pier 5.3 NW 21 Concordia Elementary School - San Clemente 3.5 NW 22 Former U.S. Coast Guard Station - San Mateo Point 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. Distances are within the Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification. p MCB - Marine Corps Base PIC - Pressurized Ion Chamber V S023-00CM 5 15 Revision 23 02 28-91
Page 2 of 6 TABLE 5-4 RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCA110NS 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 Onofre State Beach Park 3.3 SE 39 Basilone Road Trailer Park (MCB, Camp Pendleton) 1.4 NNW 40 SCE Training Center - Mesa (Adjacent to Plc #3) 0.7 NNW 41 Old Route 101 - East 0.4 E
~
42 -Horno Canyon (MCB, Camp Pendleton) 4.7 E 43 Edison Range (MCB, Camp Pendleton) 10.6 SE 44 Fallbrook Fire Station 18.0 E 45 Interstate 5 Weigh Station 2.0 ESE 46 San Onofre State Beach Park 1.0 SE Camp Las Flores (MCB, Camp Pendleton) 8.6 47 SE 48 Mainside (MCB, Camp Pendleton) 15.0 ESE Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined.from degrees true north. l Distances are within the . Units 2 and 3 Site Boundary (0.4 mile in all sectors) and not required by Technical Specification.
*** MCB - Marine Corps Base Plc - Pressurized Ion Chamber 5023 0DCM l 5-16 Revision 21 l 02-15-90 l
7. Page 3 of 6 IMLLka a A RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS U DISTANCE
- TYPE OF 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 21.0 ESE 53 San Diego County Operations Center 45.0 SE 54 Escondido Fire Station 32.0 ESE 55 San Onofre State Beach (Unit 1 West South, west) 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 Plc #8) 0.7 E 66 San _Onofre State Beach (Adjacent to Plc #9) 0.6 ESE
-67 Former SONGS Evaporation Pond (Adjacent to Plc #2) 0.6 NW 68 Range 210C (MCB, Camp Pendleton) 4.3 ENE D
Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north.
't 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 O S023-0DCM l l 5-17 Revision 25 l l 02-28-92 i
-, - -.- . . ~
Page 4 of 6 T'BLE 5-4 RADIOLOGICAL ENVIRONMENTAL HONITORING SAMPLE LOCATIONS DISTANCE
- TYPE OF SAMPLE AND SAMPLING LOCATION (miles) DIRECTION
- Airborne 1 City of San Clemente (City Hall) 5.5 NW 2 Camp San Onofre (Camp Pendleton) 1.8 NE 3 Huntington Beach Generating Station 37.0 NW 5 Units 2 and 3 Switchyard 0.13** NNE 6 SONGS Meteorological Tower 0.3** WNW 9 State Beach Park 0.6 ESE 10 Bluff -
0.7 WNW 11 Mesa EOF 0.7 NNW 12 Former SONGS Evaporation Pond 0.6 NW
- 13 Marine Corps Base (Camp Pendleton East) 0.7 E Soil Samples 1 Camp San Onofre 2.5 NE 2 Old Route 101 - East Southeast 3.0 ESE 3 Basilone Road /1-5 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. O S023-00CM 5-18 Revision 21 Q2-1S-90
Page 5 of 6 TABLE 5-4 i RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS DISTANCE
- TYP'E OF SAMPLE AND SaMLLING LOCATION (miles) DIRECTION
- Drinking Water 1 Tri Cities Municipal Water District Reservoir 8.7 NW
- 2. San Clemente Golf Course Well 3.5 NNW 3 Huntington Beach 37.0 NW :
Shoreline Sediment (Beach Sand) 1 San Onofre State Beach (0.6 mile Southeast) 0.6 SE 2 San Onofre Surfing Beach - 0.9 NW 3 San Onofre State Beach (3.1 miles Southeast) 3.1 SE 4 Newport hach (North End) 30.0 NW Local Crops 1 San Mateo Canyon (San Clemente Ranch) 2.6 NW 2 Southeast of Oceanside 22.0 SE O'. Distance'(miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north. O S023 0DCM S-19 Revision 23 02-28-91
Page 6 of 6 TABLE 5-4 f') RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATIONS i C' DISTANCE
- TYPE OF SAMPLE AND SAMPllNG LOCATION (miles) DIRECTION
- Hon-Migratory Marine Animals A Unit 1 Outfall 0.9 WSW B Units 2 and 3 Outfall 1.7 SSW C Newport Beach 18.2 NW Kelp A San Onofre Kelp Bed 1.5 S B San Mateo Kelp Bed 3.8 WNW C Barn Kelp Bed 6.3 SSE D Newport Beach 15.6 ,
NW Ocean Bottom Sediments A Unit 1 Outfall (0.5 mile West) 0.6 W B Unit 1 Outfall (0.6 mile West) 0.8 SSW rO C Unit 2 Outfall 1.6 SW D Unit 3 Outfall 1.2 SSW E- Newport Beach 18.2 NW Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true north. O S023-00CM S-20 Revision 23 02-28 91
TABLE 5-5 PIC - RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS O Theta DISTANCE
- PRESSUR12ED 10N CHAMBERS (Dearees)* Meters miles DIRECTION / SECTOR
- S1 San Onofre Beach 298* 1070 0.7 WNW P S2 SONGS Former Evap. Pnd 313' 890 0.6 NW Q 53 Japanese Mesa 340' 1150 0.7 NNW R S4 HCB - Camp Pendleton 3' 1120 0.7 N A 55 MCB - Camp Pendleton 19' 1050 0.6 NNE B 56 HCB - Caro Pendleton 46' 940 0.6 NE C 57 MCB - Camp Pendleton 70' 870 O.S ENE D 58 11CB Camp Pendleton 98* 1120 0.7 E E 59 San Onofre State Beach 121' 940 0.6 ESE F O
J
- Distance (meters / miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Theta direction is determined from degrees true north.
l l l O S023-0DCM 5-21 Revision 21 02-15-90 t . . _ , - _ , _ . - -
.us em_ J,a D 4 -_ 2_ J.A. m @ - a m .& J .m TABLE 5-6 SECTOR AND DIRECTION DESIGNATION FOR RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLE LOCATION MAP DEGREES TRUE NORTH FROM SONGS. 2 AND 3 MID. POINT NOMENCIATURE Sector Center Sector 22.5*
ljp_i,t Line limit Sectorf 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 78.75 90.0 101.25 . E E 101.25 112.0 123.75 F ESE 123.75 135.0 146.25 G . SE 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 l : 236.25 247.5 258.75 M WSW ' 258.75 270.0 281.15 N W 281.25 292.5 303.75 P WNW 303.75 315.0 326,25 Q NW 326.25 337.5 348.75 R HNW l Distance (miles) and Direction (sector) are measured relative to Units 2 and 3 midpoint. Direction is determined from degrees true North. l O S023-0DCM 5-22 Revision 21 1 02-15 90
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i 9203240102-o3 _ _ - _ - - - _ _ _ _ - _ _ s.25 __-____-____-___--_-_->__o1_ Revision 13 07 o
6.0 ~ ADMINISTRATIVE - l 6.1 DEFINITQ![1 The defined terms of this section appear in capitalized type and are applicable through these Specifications. ACTION 6.1.1 ACTION shall be th6t part of a specification which prescribes remedial measures required under designated conditions. CHANNEL CAllBRATION 6.1.2 A CHANNEL CALIBRATION shall be the adjustinent, 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 encompats the entire channel, including the sensor and alarm arJ/or trip functions, and shall include the CHM NEL 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. [HANNEL CHECX 6.1.3 A CHANNEL CHECK shall be the qualitative assessment of p) ( 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 simulateri signal into the sensor to verify OPERABILITY, including alarm and/or trip functions.
- c. Digital computer channels - the exercising of the digital computer hardware using diagnostic programs and the injection of simulated process data into the channel to verify OPEPABILITY.
5023-0DCM 6-1 Revision 21 02-15-90
6.0 ADMINISTRATIVE (Continued) DOSE E0VIVALENT l-131 6.1.5 DOSE EQUIVALENT l-131 shall be that concentration of I 131 (microcuries/ gram) which-alone would produce the same thyroid -dose as the-quantity and isotopic mixture of 1-131, 1 132,1 133,1 134, and 1-135 actually present, The . thyroid dose conversion factors used for this calculation shall be those listed in Table III of T10-14844,
" 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. GASEOUS RADWASTE TREATMENT SYSTEM 6.1.7 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed 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 p-ior to release to the environment. INVESTIGATIVE REPORT 6.1.8 The roup responsible for the missed ACTION or surveillance shal perform an evaluation which covers the root cause(s), corrective action, and recommendations to preclude recurrence of the event. Copies of the resulting report shall b p,;vided to Effluent Engineering and the Unit Superintendent with the original sent to CDM. SONGS for retention. MEMBERS OF THE PUBLIC 6.1.9 MEMBER (5) 0F THE PUBLIC shall include all individuals who by virtue of their occupational status have no formal association with the plant. This category shall include nonemployees of the licensee who are permitted to use portions of the site for recreational, occupational, or purposes not associated with plant functions, This category shall not include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasienally enter an area that is controlled by the licensee for purposes of protection of individuals from exposure.to radiation and radioactive materials. O S023-0DCM 62 Revision 23 02-28 91
6.0 ADMINISTRATIVE (Continued) QPERABLE - OPERABillTY 6.1.10 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, compor,ent or device to perform its function (s) are also capable of performing their related support function (s). M!RGE PURGING 6.1.11 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. SITE BOUNDARY 6.1.12 The SITE BOUNDARY shall be that line beyond which the land
's not ceed, leasec, or otherwise controlled by the licensee.
SOLIDIFICATION 6.1.13 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume ano shape, bounded by a stable surface of distinct outline on all sides (free-standing). SOURCE CHECK 6.1.14 A SOURCE CHECK shall be the qualitative assessment of ' channel response when the channel sensor is exposed to a radioactive source. THERHAL POWEB_ s. 6.1.15 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. O S023-0DCM 6-3 Revision 2, 02-28-91
=
6.0 ADMINISTRATIVE (Continued) VENTILATION EXHAUST TREATMENT SYSTEM () 6.1.16 A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to ' reduce gaseous radiotodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is
-not considered to have any effect on noble gas effluents). ;
Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. VENTING 6.1.17 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or*other operating condition, in , such a manner that replacement air or gas is not provided or ; required during VENTING. Vent used in system names does not imply a VENTING process.
--f3 V
( - S023 00CM 6-4 Revision 25 02-28-9C v.- - , _ -_ - + u
. . .... - _ , . . . . ;=__ -_ ; - - - . - - .- .
IABLE 6 1 OPERATIONAL MODES REAtilVITY % OF RATED AVERAGE COOLANT OPERATION MODE CONDITION. K ,, IRB M' POWER
- TEMPERATURE
- 1. POWER OPERAfl0N 2 0.99 > 5% 2 350'F
- 2. STARTUP 2 0.99 s 5% 1 350'F
- 3. HOT STANDBY < 0.99 0 2 350'F
- 4. HOT SHUTDOWN < 0.99 0 350' F> T.,,>200'F >
5 COLD SHUTDOWN < 0.99 0 s 200'F
- 6. REFUELING ** 1 0.95 0 s 140'F
- Excluding decay heat.
l O ** Fuel in the reactor vessel with the vessel head 1 ure bolts less than fully tensioned or with the head removed. t O ' 5023 0DCM 65 Revision 21 >- 02-15 90 1 Q% ,--~ + , , .. .,+-c. - - .4.;.-,. .,. .--.,....,.,n-., ,. , . - m., -- , ,.
IABLE 6 2 BE0VENCY NOTATION O NOTATION FRE0VENCY S At least once per 12 hours , D At'least once per 24 hours W At least once per 7 days H At least once per 31 days Q At least once per 92 days SA At least once per 184 days R At least once per 18 months
- i 5/U Prior to each reactor startup P Completed prior to each release N.A. Not applicable Refueling Not to exceed 24 months Interval O
*A month is defined as a 31 day period.
~
O SO23-0DCM 66 Revision 22 08-02-90
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6.0 ADMINISTRATIVE (Continued) 6.2 ADMINISTRATIVE CONTROLS 1EMIANNUAL RADIOACTIVE EFFLUENT Rf1 EASE REPORT
- 6.2.1 Routine radioactive effluent release reports covering the operation of the unit during the previous 6 rionths of '
operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the date of initial criticality. 6.2.2 The radioactive effluent release reports shall include a sumary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, 'Heasuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Mate. rials in Liquid and Gaseous Effluents from Light Water Cooled Nuclear Power Plants, ' Revision 1 June 1974, with data sumarized.on a quarterly basis following the format of Appendix B thereaf. The radioactive effluent release report to be submitted 60 days after January I each year shall include an annual sumary of hourly meteorological data collected over the previous year. This annual sumary may be either in the form of an hour by hour listing of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form of joint O frequency distributions of r t d speed, wind direction, and atmospheric stability. This same report shall include an assessment of the radiation doses due to the rudioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same eport shall also include an assessmant of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figure 1 2 and 2 2) during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materit.ls in gaseous effluents (as determined by sampling frequency and measurement) shall be used for detemining the gaseous pathway doses. The assessment of radiation doses shall be perfomed in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM). O S023-0DCM 6-7 Revision Z2 08-02-90 9
, - . . m - .,. , . , . . , - . -
, t 6.0 @'41NISTRATIVE (Continued) l 6.2 ADMINISTRATIVE CONTROLS (Continued)
. 6.2.2 (Continued)
The radioactive effluent release report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor raleases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Accc9 table methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1. The radioactive effluents release shall include the following information for each type of solid wast 6 shipped offsite during the report p'eriod:
- a. Container volume,
- b. Total curie quantity (specify whether determined by measurement er estimate),
- c. Principal radionuclides (specify whether determined by measurement or estimate),
- d. Type of waste (e.g., spent resin, compacted dry wasto, evaporator bottoms),
- e. Type of cont.iner (e.g., LSA. Type A Type B.
Large Quantity), and
- f. Solidification Agent (e.g., cement, urea formaldehyde).
The radioactive effluent relecse reports shall include unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents on a quarterly basis. The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM (PCP) made during the reporting period.
- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are comon to all units at the Station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
O S023 0DCH 68 Revision 22 08 02 90
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i 6.0 ADMINISTRATIVE (Continued) 6.3 HAJOR CHANGES TO RADIOACTIVE WASTE TREATHENT SYSTEMS (Liquid. & Gaseous) Licensee initiated major changes to the radioactive waste systems ; (liquid a gaseous):
- 1. Shall be reported to t'he Commission in the Monthly Operating Report for the period in which the evaluation was performed pursuant to Technical Specification 6.5.2. The discussion of each change shall contain:
- a. A sumary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; t
- b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information
- c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;
- d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the license application and amendments thereto; O 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 p*rsonnel as a result of the change; and
- h. Dncu
- :.entation of the fact that the change was reviewed and found acceptable pursuant to Technical Specification 6.5.2.
- 2. Shall become effective upon review and acceptance pursuar.t to Technical Specification 6.5.2. .
f l O S023-0DCM 69 Revision 22 08 02 90 (
v.0 ADMINISTRailVE (Continued) 6 . .i M hp 1,.h 7 EFFlVENTS
' p5CENTPAllq!i (1.1) p 6.4.1 This specification is provided to ensure that the concentration of radioactive materials released in liquid lI waste effluents from the site will be less than the concentration levels specified in 10 CFR Part 20, Appendix B. Table 11, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section !!.A design objectives of Appendix 1, 10 CFR 50, to an individual, and (2) the limits of 10 CFR 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption tht.t -
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. Q2i[ (1.2) 6.4.2 This specification is provided to implement the recuire-ments of Section ll.A. Ill.A and IV.A of Appendix 1, 10 CFR l Part 50. The Limiting Condition for Operation implements the guides set forth in Section ll.A of Appendix 1. The ACTION statements provide the required operating flexibility O and at the same time implement the guides set forth in Section IV.A rf Appendix ! to assure that the releases of radioactive raterial in liquid effluents will be kept 'as low as is rr asonably achievable.' The dose calculations in the ODCM i'plement the requirements in Section Ill.A of AppeG h: 4 that conformance with the guides of Appendix ! be shoin by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially unde estimated. The equations specified in the 00CH for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109,
' Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1,* 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. .Fcr units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system. O S023-0DCM 6-10 Revision 21 02-15 90
6.0 ADMINISTRailV.E (Continued) 6.4 ILAl[1 (Continued) L10VID WASTE TREATME!H (1.3) 6.4.3 The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept 'as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the desion objective given in Section 11.0 of Appendix ! {o 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were t',ecified as a suitable fraction of the dose design objectives set forth in Section !!. A of Appendix 1,10 CFR Part 50, for liquid effluents. , GASEOUS EFFLUENTS DOSE RATE (2.1) 6.4.4 This specification is provided to ensure that the dose at any time at the site boundary from 9aseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of O 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table 11 of 10 CFR Part 20 (10 CFR Part 20.106(b)). For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gama and beta dose rates above background to an individual at or-beyond the site boundary , to less than or equal to 500 mrenVyear to the total body or l 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 reTease 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. O S023-00CM 6 11 Revision 21 02 15-90
6.0 @MINISTRATIVE (Continued) 6.4 BAl[1 (Continued) DOSE - 10BLE GASE1 (2.2) 6.4.5 This specification is provided to implement the requirn.ents of Sections ll.B, Ill.A and IV.A of Appendix 1, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section !!.B of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 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 Ill.A of Appendix 1 that conformance with the guides of Appendix ! ce shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unl.ikely 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 (A Cooled Reactors," Revision 1, July 1977. For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. For MEMBERS OF THE PUBLIC who traverse the SITE BOUNDARY via highway I 5, the residency time shall be considered negligible and hence the dose "0".
The ODCM equations provided for determining the air doses at the SITE BOUNDARY are based upon the historical average atmospheric conditions. QQ1E - RADIO 10 DINES. PAD 10 ACTIVE MATERI ALS IN PARTICULATE FORM AND TRITIUM (2.3) 6.4.6 This specification is provided to implement the requirements of Sections 11.C, ll!.A and IV.A of Appendix 1, 10 CrR Part 50. The Limiting Conditions for Operation are the guides set forth in Section 11.C of Appendix 1. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix ! to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the Surveillance Requirements implement the t J S023 0DCM 6 12 Revision 22 ; 08 02-90
6.0 ADMINISTRATIVE (Continued) 6.4 flMH (CoMinued) requirements in Section Ill. A of Appendix ! that cor.formance l with the guides of Appendix ! be shown by calculational ! procedures based or, models and data, such that the actual ! exposure of an individual through appropriate pathways is I unlikely to be substantially uderestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109,
' Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1,* Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in 1 Routine Releases from Light-Water Cooled Reactors," Revision !
1, July 1977. These equations also provide for determining l 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 the existing radionuclide pathways to man, in the unrestricted area. The pathways which were j examined in the development of these calculations were:
- 1) individual inhalation of airborne radionuclides, 1
- 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and ;
( 4) deposition on the ground with subsequent exposure of man. GASEOUS RADWASTE TREATMENT (2.4) 6.4.7 The OPERABil. TTY of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILS 1 EXHAUST TREATMENT SYSTEM ensures that the systems wt. se available for use whenever gaseous effluents require treatment )rior to release to the environment. The requirement that tie appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept 'as low as is reasonably achievable.' This specification implements the requirements of 10 CFR Part 50.364, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in , Section !!.D of Appendix I to 10 CFR Part 50. The specified i limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.B and ll.C of l Appendix 1,10 CFR Part 50, for gaseous effluents, l 5023 0DCM 6 13 Revision 21 02-15 90
6.0 ADMINlSJ3aTIVE (Continued) 6.4 fLA1Li (Continued) TOTAL DOSE (2.5) 6.4.8 This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix 1. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action which should result in the limitation of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the ext.cption that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any member of the public is 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 O 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. RADIDACTIVE L10VID EFFLUENT INSTRUMENTATION (4.1) 6.4.9 The radioactise liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during acteil or potential releases of liquid effluents. The alar 1n/ 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. O S023-00CM 6-14 Revision 21 W IS 90
6.0 ADMINISTRATIVE (Continued) . 6.4 JL%[5 (Continued) MD10 ACTIVE GASEOUS EFFLUENT INSTRUMENTATION (4.2) 6.4.10 The radioactive gaseous effluent instrumentation is provided , to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm / trip setpoints for these instruments 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. This instrumentation also includes provisions for monitoring and controlling the concentrations of potentially explosive gas mixtures in the waste gas holdup system. The OPEPABILITY 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. , MONITORING PROBM (5.1) 6.4.11 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 O - 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 comercial operation. Following this period, program changes may be initiated based on operational experience. The detection capabilities required by Table 5-1 are state-of the art for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an A Dr.iori (before the fact) limit representing the capability of a measurement system and not as a costeriori (after the fact) limit for a particular I measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small santple sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render t these LLDs unachievable. In such cases, the contriouting factors will be identified and described in the Annual Radiological Environmental Operating Report. lO l- 5023 0DCH 6 15 Revision 22 08-02 90 1 _ - . - - . - . . _ _ . = , . . _ ~- _ . _ , ~ - - , _ - _ . _ , - - , . _ _ . - _ . . . . _ . - _ ~ . . -
6.0 ADMINISTRATIVE (Continued) 6.4 !! ASH (Continued) LAND USE CENSUS (5.2) 6.4.12 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 1 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. Tq 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. JNTERLABORATORY COMPARISON PROGRAM (5.3) 6.4.13 The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent C 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. O S023 00CM 6-16 Revision 22 08 02 90
,_ .. . . _ = . _ _ _ _ _ f j ATTACllMENT B + Revised Unit 3 January 1992 Unit Shutdowns and Power Reductions SONGS Units 2 and 3 Monthly Operating Report i e i 4 i l I
+
l L __ ___ .;_ __ ______-...___.n_._...-.,.~_....-.. . _ _ ~ . _ . _ . _ _ - . _ _ _ _ - _ . . . . _ - . - . . . - .;.-....__.m
UNIT SHUTDOWMS AND POWER REDUCTIONS DOCKET NO: 50-362 UNIT NAME: SONGS - 3 January 1992 DATE: 3-13-9; REPORT MONTH: COMPLETED BY: M.M.Fer ~ TELEPHONE: (714) 3e!-9787 l Method of Shutting Cause & Corrective LER System Component Action to Duration Down Prevent Recurrence Reason 2 Reactor 3 No. Code' Code'
- No. Date Type l (Nours) l l
174.58 *C 5 NA NA NA Cycle 6 refueling outage. l 63 920124 5 1 l
- Data corrected since previous submittal.
2 2 Method: 'IEEE Std 805-1984 I F-Forced Reason: A-Equipment Failure (Explain) 1-Manual S-Scheduled 2-Manual Scram. S IEEE Std 803A-1983 B-Maintenance or Test C-Refueling 3-Automatic Scram. D-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination Previous Month 5-Reduction in the Average F-Administrative G-Operational Error (Explain) Daily Power Level of more H-Other (Explain) than 20% from the previous day 6-Other (Explain) mor.jan/11
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