ML20199B161
| ML20199B161 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/05/1986 |
| From: | Julie Ward SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 86-08, 86-8, JEW-86-087, JEW-86-87, TAC-64735, NUDOCS 8606170047 | |
| Download: ML20199B161 (22) | |
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h SACRAMENTO MUNICIPAL UTIUTY DISTRICT C 6201 S Street, P.O. Box 15830. Sacramento CA 95852-1830.(916)452 3211 AN ELECTRIC SYSTEM SERVING THE.UEpN -Q';F GALIFORNIA RT "v
d I: !I JEW 86-087 June 5, 1986
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- J B MARTIN REGIONAL ADMINISTRATOR REGION V 0FFICE OF INSPECTION AND ENFORCEMENT U S NUCLEAR REGULATORY COMMISSION 1450 MARIA LANE SUITE 210 WALNUT CREEK CA 94596 DOCKET N0. 50-312 LICENSE NO. DPR-54 SPECIAL REPORT N0. 86-08, CALCULATED DOSE TO THE MAXIMUM HYP0THETICALLY EXPOSED INDIVIDUAL SURPASSING THE NUMERICAL GUIDES FOR DESIGN OBJECTIVES OF 10 CFR 50, APPENDIX I The Sacramento Municipal Utility District hereby submits Special Report 86-08 in accordance with Action a. of Rancho Seco Nuclear Generating Station Technical Specification 3.17.2.
This report supersedes Special Report No. 86-08 dated May 9, 1986 which documented the District's request for a 30 day extension in the submittal of the final report.
Stone & Webster has completed a review of the original draft technical material and has confirmed, by independent calcu-lations, the District's conclusions in this report.
In the course of the District's efforts to reconcile the apparent ambiguities between the Controls for Environmental Pollution, Inc. (CEP) composite sample results for liquid effluents during 1985 (Attachment I) and the results reported in the " Environmental Radiological Studies Downstream From the Rancho Seco Nuclear Power Generating Station - 1985," developed by Lawrence Livermore National Lab-oratory, and the quantities of gross beta gamma activities reported in the Rancho Seco Semi-Annual Radioactive Effluent Release Reports of 1985, an evaluation has revealed that the quarterly numerical guides for design objectives in the third quarter of 1985 and the annual numerical guides for design objectives were sur-passed in 1985 as described in Attachment II.
An internal Occurrence Description Report was generated on April 10, 1986 documenting this preliminary finding.
The causes for apparently surpassing the numerical guides for design objectives of Appendix I of 10 CFR 50 were:
- 1) the strict reliance on the Lower Limit of Detection (LLD) values provided in the Rancho Seco Technical Specification 4.21.1 i
and Table 4.21-1 (i.e., 5X10-7 pCi/ml);
- 2) the release of liquid effluent in quantities not originally contemplated for normal plant operation;
- 3) operation after steam generator tube leaks which allowed minute quantities of radioactivity g
in the secondary coolant system; 4) routing of slightly contaminated secondary
-m coolant to the liquid radwaste treatment system for processing resulted in the j@
release of discrete quantities of tritiated evaporator condensate which contained op trace quantities of other isotopes; and 5) dose calculation models, which though C
conservative, are overly conservative in estimating the dose to actual public y
receptors of Rancho Seco liquid effluent.
00W When more appropriate modeling techniques are utilized (Attachment II) the liquid g
effluent releases during 1985 from Rancho Seco did not exceed the numerical om guides for design objectives of 10 CFR 50, Appendix I, for the maximum hypo-
$@a thetically exposed individual.
J RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 33 5
Special Report 86-08 June
, 1986 It should be emphasized that the Appendix I numerical guides for design objectives are not measures of any public health risk but are merely present to ensure that radiation exposure remains as low as reasonably achievable (ALARA) consistent with the public's need for electric power, as stated in 10 CFR 50.34a(a). Appendix I states that, "the licensee is permitted the flexibility of operation, compatible with considerations of public health and safety, to assure that the public is provided a dependable source of power even under unusual operating conditions which may temporarily result in releases higher than such numerical guides for design objectives but still within levels that assure that the average population ex-posure is equivalent to small fractions of doses from natural background radiation."
The calculated theoretical dose commitment for 1985 from the Rancho Seco Nuclear Generating Station to the maximum hypothetically exposed individual with the current overly conservative dose calculation methodology is still well within this stated guideline of being a small fraction of doses from natural background radia-tion.
Confirmation that the real world dose is a small fraction of the dose due to natural background radiation is provided in the District's Annual Environmental Operating Report submitted May 27, 1986, which indicated a radiological dose impact of only 2 mrem for 1985.
Immediate actions were taken to control compliance in 1986 with the numerical guides for design objectives of 10 CFR 50, Appendix 1.
These actions were:
- 1) all liquid samples for effluent releases are being counted for 2,000 seconds; 2) the average plant effluent release rate has been increased to 5,000 gpm; 3) all documentation relating to liquid effluent releases are placed in a separate folder to ensure records retrievability; 4) the stated LLD values from the gamma scan, gross beta, or tritium analysis will be written on Enclosure 4.1 of AP.305.13; and 5) changes were initiated to preclude the contamination of glassware used in the compositing of samples from the regenerative hold up tanks (RHUTs).
Additionally, to further control compliance with the numerical guides for design objectives of Appendix I for normal operating conditions in 1986, individual liquid effluent releases will no longer rely solely on the LLD values prescribed by the Technical Specifications.
Recognizing the potential for varying quantities of liquid effluent releases over a given year, procedures are being revised to adjust the LLDs to preclude surpassing the numerical guides for design objec-tives of 10 CFR 50, Appendix I for normal operation with varying effluent re-lease rates.
As indicated in Attachment II, efforts have been taken to carefully review and quantify the conservative assumptions which are currently in use in the calculation of dose to the maximum hypothetically exposed individual. As a result of these efforts to be more realistic, the Offsite Dose Calculation Manual will be revised by January 1, 1987, to more appropriately reflect the maximum hypothetically exposed individual and thereby obviating the need for unnecessary reports in the future.
Longer term actions which are also being evaluated to provide greater margin to the numerical guides for design objectives of Appendix ! are:
- 1) installation of piping from the RHUTs back to the liquid radioactive treatment system to permit the treatment of any proposed releases as radioactive waste; 2)investi-gation of the installation of additional tanks for storage of extremely low t
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Special Report 86-08 June, 1986 activity liquids; 3) investigation of the installation of a low activity water treatment system to remove even trace quantities of radioactivity from the RHUT liquids; and 4) an evaluation of waste streams and processing techniques to further minimize activity transfer to the RHUT, consistent with the numerical guides for design objectives of Appendix I.
In conclusion, the District recognizes an apparent transgressing of the numerical guides for design objectives of 10 CFR 50, Appendix I.
Subsequent analyses have confirmed that with realistic and representative dose calculation methodology, the Rancho Seco Nuclear Generating Station has not exceeded the numerical guides for design objectives of Appendix I to 10 CFR 50 for 1985 as documented in Table 9 of Attachment II.
If there are any questions concerning this response, please contact Mr. Ron Colombo at the Rancho Seco Nuclear Generating Station Unit No. 1.
E. WARD ASSISTANT. GENERAL MANAGER, NUCLEAR (ACTING)
Attachments (2) cc:
I&E, Wash DC t
ATTAC K NT I SACRAMENTO MUNICIPAL UTILITY DISTRICT OFFICE MEMORANDUM To: E. Bradley DATE: April 24, 1986 7-FROM: D. Kahn
SUBJECT:
REVIEW LAWRENCE LIVERMORE ANALYSIS OF RETENTION BASIN SAMPLES
Reference:
1.
UCID - 20641 Environmental Radiological Studies Downstream from the Rancho Seco Nuclear Power Generating Station.
2.
Letter from Controls for Environmental Pollution, Inc. to Steve Manofsky dated April 8,1986 As per your request, a review has been performed of the effluent release data for October of 1935 in an effort to draw a correlation between the information reported in the Liquid Waste Relt.ase Permits, the Effluent Release Permits, the results of the Lawrence Livermore (LLNL) Environmental Study (Reference 1) and the results of the gamma spectral analysis per-formed on the monthly composite sample (Reference 2). The results of this review indicate that each of the data sets are consistent with the other and that there are no anomalies present. The following paragraphs are intended to provide an explanation of these conclusions.
Since it has previously been concluded that the major contributors to the estimated dose to individuals are Cesium 134 (Cs-134) and Cesium 137 (Cc-137) only these two isotopes are considered in the discussion.
The Lawrence Livermore study (Reference 1) analyzed two retention basin samples which were collected on October 17, 1985.
The reported Cs134 and Cs137 levels were 11.3 and 7.2 picoCuries per liter (pCi/1) and 51.2 and 26.3 pCi/1, respectively.
For the purpose of this comparison these values are converted to microcuries per milliliter (uCi/ml) (see attached table) by multiplying the values by 10-9 The lower limits of detection for the in-house gamma spectral analysis system are 3.87E-08 and 5.92E-08 for Cs-134 and Cs137, respectively.
As can readily be seen the level reported by LLNL would be below the detectable levels of the in-house system, and thus be reported as below LLD or no peaks on the Effluent and Liquid Waste release permits.
The CEP Inc. data consisted of a gamma spectral analysis of a composite sample of all Regenerant Holdup Tank (RHUT) effluent for the month of October.
The reported level of Cs-134 was less than the detection level of the CEP system (1.0E-08) while that of Cs-137 was 59.0 pCi/1.
Here again, the levels were at or below the detection limits of the in-house system (see Table),
c
' The next step in the review consists of a review of the various RHUT discharges to the retention basins.
Since the in-house gamma analyses performed on the RHUT discharges shows all activities below LLD, it becomes necessary to employ another means to perform this assessment.
The chosen method is to make an assumption of the Cs-137 activity based on the Gross Beta measurement performed.
This assumption yields an estimate that the Cs-137 activity would have an approximately one to one correlation to the Gross Beta activity.
This correlation will be used in the following discussion.
Two RHUT discharges to the South retention basin occurred on 10/15, each with a measured activity less than 2.76E-08 uCi/ml @ross Beta). The contents of the south retention basin were subsequently released on 10/16 with a measured
-activity of 5.61 i 2.97E-08 uCi/ml (gross Beta). The contents of the retention basin when the LLNL sample was taken would be sludge and residual liquid.
Given these conditions, a grab sample activity of 2.63 10.20E-08 uCi/mi Cs-137 is considered reasonable.
A discharge.to the north retention basin occurred on 10/17 (early morning).
The measured activity of the discharge was 6.08 i2.99E-08 uCi/ml (gross Beta) which correlates well with the LLNL grab sample (taken 10/17) results of 5.12 10.20E-08 uCi/mi Cs-137. The north retention basin had previously been discharged.
The mean activity for all the detectable releases in October was 6.19 14.99E-08 uCi/ml (gross Beta).
This result correlates well with the CEP composite result of 5.9 i1.6E-08 uCi/ml for Cs-137.
Taken toghether the above results show an excellent correlation which is well within the bounds of statistical error.
This therefore supports the con-clusions of no observable anomalies among the various sets of data.
Should you have any questions or comments, please feel free to contact me.
DK:sw cc: F.KellieW/
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COMPARISON OF DATA Source of Data Activity Concentration (uCi/ml)
Cs 134 Cs 137 LLNL' 1.13 10.30E-08 and 5.12 i.020E-08 anc Study 7.20 10.30E-09 2.63 10.20E-08 (grab sample 10/17/83)
CEP, Inc.
Less than 1.0E-08 Composite Results 5.9 i1.6E-08 i
Lower Limit of Detection 3.87E-08 5.92E-08 in-house gamma spectral analysis System for 10/17/86 Cs-137 Correlation To North Basin from Gross Beta 6.08 i 2.99E-08 Results (assume 1:1 ratio)
None (LWR 85-190) for Release Permits From South Basin 5.61 2.97E-08 (ERP 85-074) i l
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8 ATTAC K NT II l
10 CFR 50, APPENDIX I NUE RICAL GUIDES FOR DESIGN OBJECTIVES CALCULATIONS l
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NUMERICAL GUIDES FOR DESIGN OBJECTIVES FOR 10 CFR 50, APPENDIX I Conforming to the guidelines of 10 CFR 50 Appendix I conclusively shows that the quantity of radioactive effluents (liquid or gaseous) from a commercial nuclear power station are in compliance with the "as low as is reasonably achievable" (ALARA) requirements of 10 CFR 50.34a and 50.36a. Conformity with the numerical guides for design objectives shall be demonstrated by calculational procedures based upon models and data delineated in the Licensee's Offsite Dose Calcula-tion Manual (0DCM).
The conformance boundary is generally assumed to be the ex-clusion area boundary for gaseous effluents and the site property boundary for the liquid effluents. The numerical guides for design objectives for radioactive liquid effluents are:
Calendar Quarter Calendar Year Total Body 1.5 mrem 3 mrem Any Organ 5 mrem 10 mrem As stated in 10 CFR 50.34a(a), these numerical guides for design objectives are not to be interpreted as radiation protection standards.
The NRC specified general public radiation protection standard is prescribed in 10 CFR 20.105 and is a value of 500 mrem to the whole body of any indivi-dual in an unrestricted area in any one calendar year.
It should be noted that even though the ODCM calculates numerical values in units of radiological dose to hypothetical individuals, it is generally accepted that these values should not be interpreted as a real radiological exposure to a real individual.
The 00CM is a calculational methodology that generates a conformance value which is then compared with the numerical guides for design objectives of 10 CFR 50, Appendix I.
The calculational methodology of the ODCM also assumes that the radioactive effluents are discharged at a constant rate over a long period of time and that they are in equilibrium with the environment.
The conservatism inherent in the methodology of the ODCM and 10 CFR 50, Appendix I provides an early indication of approaching analytical limits so that modifications can be made to procedures or equipment over a period of time to reduce the quantity of radioactive effluents before a real radiological exposure to a real individual approaches the same low value.
OFFSITE DOSE CALCULATION MANUAL (0DCM)
The calculational methodology of an ODCM is modeled after the US NRC Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents For the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," October 1977. This regulatory guide describes basic features of the calculational models and suggests parameters for the estimation of radiation doses to man from effluent releases. The licensee is encouraged to use site-specific values but the assumptions and methods used to obtain these parameters should be fully described and documented.
The Rancho Seco 0DCM uses the calculational methodology described in Regulatory Guide 1.109 and implements it by using the LADTAPII computer code described in NUREG/CR-1276, " User's Manual for LADTAPII, A Computer Program for Calculating Radiation Exposure to Man From Routine Releases of Nuclear Reactor Liquid Effluents," May 1980.
i
, Specific site related parameters which are used in the Rancho Seco 0DCM, other than those suggested in Regulatory Guide 1.109, are documented in the follow-ing reports:
1.
Final Environmental Statement related to the operation of Rancho Seco Nuclear Generating Station Unit 1, March 1973, US AEC.
2.
Appendix I Evaluation Report Rancho Seco Nuclear Generating Station, June 1, 1976 Tera Corporation.
3.
Usage Survey Report, March 15, 1985, District correspondence to NRC Region V.
4 Environmental Radiological Studies Downstream from Rancho Seco Nuclear Power Generating Station, March 22, 1985, UCID-20367, Lawrence Livermore National Laboratory.
5.
User's Manual for LADTAPII, A Computer Program for Calculating Radiation Exposure to Man From Routine Release of Nuclear Reactor Liquid Effluents, May 1980, NUREG/CR-1276.
Some of the suggested parameters from Regulatory Guide 1.109 for effluent path-way analysis are provided in Table 1.
Current Rancho Seco ODCM parameters for the liquid effluent pathway are listed in Table 2.
The drinking water pathway is not included due to the information in the Final Environmental Statement and confirmed by the Usage Survey Report.
Boating and irrigated leafy vegetables are not included due to information in the Usage Survey Report.
The parameters YIELD and GROW were added to the LADTAPII code asinputparameterstoaccomodateinformationprovidedjntheAppendixIEval-uation Report. An irrigation rate of 263 liters / meter / month is used in the irrigated foods pathway which also comes from the Appendix I Evaluation Report.
Reduced freshwater invertebrate consumption values and increased freshwater fish consumption values are used due to the Usage Survey Report.
The bioaccu-mulation factor for cesium in freshwater fish was reduced from 2000 to 1400 due to information in UCID-20367.
It is important to realize that it is the product of the consumption value and the bioaccumulation factor that enter into the re-sultant dose and that the current Rancho Seco 0DCM would calculate a higher dose than if the suggested values of Regulatory Guide 1.109 were used.
Some additional minor changes to the LADTAPII code were made in the FOOD and WATER subroutines as a result of personal communications between Mike Wangler, NRC Washington, and E. W. Bradley of the District.
Dairy cattle are also assumed not to be drinking water directly from the effluent str^am.
Modified Rancho Seco ODCM parameters are listed in Table 3.
These parameters have not yet been through the complete review process required by Section 6.16.2 of the Rancho Seco Technical Specifications, but they are included in this report in an effort to make a realistic and representative assessment of the Appendix I ODCM calculated dose.
The 1985 Land Use Census, the results of which is summarized in the 1985 Annual Radiological Environmental Operating Report submitted May 27, 1986, generally observes that the consumption and usage along the liquid effluent pathway has been significantly reduced since the previous Usage Survey Report.
L
I g The freshwater fish consumption values were reduced to the Regulatory Guide 1.109 suggested values even though the survey information suggests smaller values.
The stream is posted for "N0 HUNTING, N0 FISHING, NO TRESPASSING" from District property _ west to Folsom South Canal.
The freshwater invertebrate consumption values are reduced by a factor of five from the suggested values in Regulatory Guide 1.109.
It is highly unlikely that either site specific values for fresh-water fish or invertebrate consumption would be exceeded due to the difficulty experienced by Lawrence Livermore National Laboratory in obtaining aquatic food samples in their continuing environmental studies. Shoreline and swimming usage continues to be higher than the suggested values of Regulatory Guide 1.109 due to maintenance and operation of irrigation pumps and a known swimming hole at Alta Mesa Road and Laguna Creek.
In an effort to make the ODCM calculations more realistic and representative, dilution factors were added to all the liquid effluent pathways except for beef cattle.
Stream flow data came from the Final Environmental Statement and is summarized in Table 3B and Table 4.
Some beef cattle still have access to Clay Creek water and irrigated pasture.
It may be possible to use the Laguna Creek dilution for all the aquatic food, shoreline and swimming pathways due to the limited consumption and usage along the Clay and Hadselville Creek areas but further evaluation is necessary and was not done in this report. The bioaccumulation factor for cesium in freshwater fish was changed back to the suggested value of 2000 in Regulatory Guide 1.109 for the calculation of doses which utilize the modified ODCM parameters. The District plans to make these changes to the next revision of the ODCM.
CALCULATION RESULTS FOR 1985 Two estimates of the 1985 liquid effluent source term have been generated.
Source Term Estimate No. 1 was generated very early in the evaluation and was the basis of the Occurrence Description Report.
Source Term Estimate No. I was obtained from the same data provided to NRC Region V in the District transmittal dated April 17, 1986, (RJR 86-135). To summarize this data, monthly composite samples are collected for each month from each of the RHUT discharges that have either a positive tritium analysis or posi-tive gross beta analysis.
These monthly composites are then sent to Controls for Environmental Pollution, Inc. (CEP) for strontium and alpha analysis.
The District requested that CEP reanalyze these monthly composites for gamma emitting radionuclides to better estimate the 1985 liquid effluent source term.
For monthly composites that did not have adequate volume for gamma spectal analysis or were contaminated, a weighted average LLD (lower limits of detection) value for the monthly RHUT discharges was calculated.
The weighting was based upon the RHUT discharge volumes.
The weighted average LLD would then be an uper estimate of the monthly radioactive liquid effluent. The 1985 Radioactive Liquid Effluent Estimate No. 1 is summarized in Table 5.
Tritium releases are reported in the Rancho Seco Semi-Annual Radioactive Effluent Releases Reports of 1985.
Source Term Estimate No. 2 is the same as Estimate No. 1 except for the months of March and December 1985. A reanalysis by CEP of the March composite determined that Cr-51 was not present.
The March composite was determined then not to have been contaminated and that the 79 pCi/ ECs-137 value was the correct value to L
. use in the evaluation. The weighted average LLD value for March was then not used.
Beginning in November 1985, the RHUT composite samples were separated into radiological and nonradiological composite samples.
If the RHUT sample analysis resulted in observable tritium or gross beta, the sample was added to the radiological composite and its discharge volume added to the radiological liquid effluent volume.
If no tritium or gross beta were observed, the sample was added to the nonradiological composite and its volume added to the nonradio-logical liquid effluent volume. An analysis by CEP of the nonradiological composite sample for December 1985 resulted in a value of 28 pCi/E Cs-137.
This data.was added to the source term estimate. The 1985 Radioactive Liquid Effluent Estimate No. 2 is summarized in Table 6.
Tritium releases are as re-ported in the Rancho Seco Semi-Annual Radioactive Effluent Release Reports of 1985.
Additional evaluations were made of liquid transfers between the demineralized reactor coolant storage tank (DRCST T-621) and the RHUTs during 1985.
Radio-nuclide analysis by gamma spectroscopy of liquid samples prior to transfer indicated small quantities of radionuclides not observed in the composite samples analyzed by CEP for the months of March and June 1985. These small quantities were added to the 1985 Radioactive Liquid Effluent Estimate No. 2 and are summar-ized in Table 6A.
The calculated quantity of radiocesium transferred from the DRCST to the RHUTs was always less than the quantity estimated by the CEP composite analysis or the weighted average LLD estimate and were not added to the overall estimate.
Three different design objective dose calculations were performed.
These were:
1.
1985 Radioactive Liquid Effluent Estimate No. 1 using the current Rancho Seco 0DCM.
2.
1985 Radioactive Liquid Effluent Estimate No. 2 using the current Rancho Seco 0DCM.
3.
1985 Radioactive Liquid Effluent Estimate No. 2 using the modified Rancho Seco ODCM.
The results of Calculation No. I are summarized in Table 7.
These calculations resulted in the generation of an Occurrence Description Report which initiated this report.
It was observed that the quarterly numerical guides for design objectives were surpassed in the 3rd quarter 1985 (2.36 mrem adult whole body and 5.80 mrem child liver) and the annual numerical guides for design objectives were surpassed in 1985 (5.10 mrem adult whole body, 3.14 mrem teenager whole body, 3.15 child whole body, and 12.4 mrem child liver).
The results of Calculation No. 2 are summarized in Table-8.
It is observed that the quarterly numerical guides for design objectives were surpassed in the 3rd quarter 1985 (2.37 mrem adult whole body and 5.80 mrem child liver) and the annual numerical-guides for design objectives were surpassed in 1985 (4.80 mrem adult whole body and 11.7 mrem child liver).
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,.. It is important to note that both calculations did not' result in values that' surpassed ~twice the numerical guides for design objectives (Technical Speci-fication 3.25) so a uranium fuel cycle dose evaluation is not required.
The results of-Calculation No. 3 are summarized in Table 9.
It' is observed that none of the-numerical guides for design objectives were surpassed.
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,a TABLE 1 US NRC REGULATORY GUIDE 1.109 TABLE E-5 RECOMMENDED VALUES FOR Uap TO BE USED FOR THE MAXIMUM EXPOSED INDIVIDUAL IN LIEU OF SITE-SPECIFIC DATA Pathway Infant Child Teen Adult Fruits, vegetables &
520 630 520 grain (kg/yr)*,**
Leafy vegetables 26 42 64 (kg/yr)*
Milk (g/yr)*
330 330 400 310 Meat & poultry 41 65 110 (kg/yr)*
Fish (fresh or salt) 6.9 16 21 (kg/yr)***
Other seafood (kg/yr)*
1.7 3.8 5
Drinking water (t/yr)#
330 510 510 730 Shoreline recreation 14 67 12 (hr/yr)#
3 Inhalation (m /yr) 1400##
3700###
8000###
8000##
- Consumption rate obtained from Reference 19 for average individual and age-prorated and maximized using techniques contained in Reference 10.
- Consists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24% grain.
Consumption rate for adult obtained by averaging data from References 10 and 21-24 and age-prorated using techniques contained in Reference 10.
- Data obtained directly from Reference 10.
- Data obtained directly from Reference 20.
- Inhalation rate derived from data provided in Reference 20.
L
TABLE 2 - A CURRENT ODCM CONSUMPTION AND USAGE PARAMETERS LIQUID EFFLUENT PATHWAY MAXIMUM EXPOSED INDIVIDUAL Pathway l'ni ts Infant Child Teenager Adult Freshwater Fish Kg/yr 0
21 21 35 Freshwater Invertebrate Kg/yr 0
1 1
1 Drinking Water E/yr 0
0 0
0 Shoreline Deposits hr/yr 0
14 100 1000 Swimming br/yr 0
100 100 100 Boating br/yr 0
0 0
0 Irrigated Foods Fruits, Vegetables, Grain Kg/yr 0
520 630 520 Leafy Vegetables Kg/yr 0
0 0
0 Milk t/yr 0
330 400 310 Meat, Poultry Kg/yr 0
41 65 110 TABLE 2 - B CURRENT 00CM DILUTION PARAMETERS LIQUID EFFLUENT PATHWAY MAXIMUM EXPOSED INDIVIDUAL Maximum Exposed Individual Quarter 1 Quarter 2 Quarter 3 Quarter 4 Freshwater Fish 1
1 1
1 Freshwater Invertebrate 1
1 1
1 Drinking Water Shoreline Deposits 1
1 1
1 Swimming 1
1 1
1 Boating Irrigated Foods Fruits, Vegetables, Grain 1
1 1
1 Leafy Vegetables Milk 1
1 1
1 Meat, Poultry 1
1 1
1 i
TABLE 3 - A MODIFIED 00CM CONSUMPTION AND USAGE PARAMETERS LIQUID EFFLUENT PATHWAY MAXIMUM EXPOSED INDIVIDUAL Pathway Units Infant Child Teenager Adult Freshwater Fish Kg/yr 0
6.9 16 21 Freshwater Invertebrate Kg/yr 0
0.34 0.76 1
Drinking Water g/yr 0
0 0
0 Shoreline Deposits hr/yr 0
14 100 200 Swimming br/yr 0
100 100 100 Boating hr/yr 0
0 0
0 Irrigated Foods Fruits, Vegetables, Grain Kg/yr 0
520 630 520 Leafy Vegetables Kg/yr 0
0 0
0 Milk t/yr 0
330 400 310 Meat, Poultry Kg/yr 0
41 65 110 TABLE 3 - B MODIFIED 00CM DILUTION PARAMETERS LIQUID EFFLUENT PATHWAY MAXIMUM EXPOSED INDIVIDUAL Maximum Exposed Individual Quarter 1 Quarter 2 Quarter 3 Quarter 4 Freshwater Fish (a)
(a)
(a)
(a)
Freshwater Invertebrate (a)
(a)
(a)
(a)
Drinking Water Shoreline Deposits (a)
(a)
(a)
(a)
Swimming (a)
(a)
(a)
(a)
Boating Irrigated Foods Fruits, Vegetables, Grain (b)
(b)
(b)
(b)
Leafy Vegetables Milk (b)
(b)
(b)
(b)
Meat, Poultry 1
1 1
1 3
(a) Hadselville Creek 3000 acre-feet / year (4.142 ft /sec annual average flow) 3 (b) Laguna Creek 13000 acre-feet / year (17.95 ft /sec annual average flow)
TABLE 4 STREAM FLOW DIl.UTION - 1985 Quarter Plant Discharge Dilution (ft3/sec)
Hadselville Laguna 1
16.731 1.248 2.073 2
7.882
~1.526 3.277 3
8.955 1.463 3.004 4
11.754 1.352 2.527 p3r<
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TABLE 5 1985 RADI0 ACTIVE LIQUID EFFLUENT ESTIMATE NO. 1 (Curies)
Month Effluent Volume Detection (pCi/t) Effluent Estimate Gallons Liters Cs-134 Cs-137 Cs-134 Cs-137 January 3.202E+06 1.212E+07
<10
< 2 0
0 February 2.808E+06 1.063E+07
<47.2
< 58.2 5.017E-04 6.186E-04 March 2.395E+06 9.066E+06
<73.6
< 91.2 6.673E-04 8.268E-04 April 4.552E+05 1.723E+06
<80.1
<109.4 1.380E-04 1.885E-04 May 3.972E+05 1.504E+06
<69.8
< 85.0 1.049E-04 1.278E-04 June 1.610E+06 6.095E+06 29 84 1.767E-04 5.119E-04 July 8.161E+05 3.089E+06 98 151 3.027E-04 4.665E-04 August 9.560E+05 3.619E+06
<54.3
< 85.2 1.965E-04 3.083E-04 September 2.929E+06 1.109E+07
<59.1
< 77.3 6.553E-04 8.571E-04 October 7.247E+05 2.743E+06
<10 59 0
1.619E-04 November 1.331E+05 5.038E+05
<10
< 2 0
0 December 5.009E+04 1.896E+05
<10
< 2 0
0 June Co-60 21pCi/E 1.280E-04ci CS-134 CS-137 Co-60 H-3 1st Quarter 1985 1.169E-03 1.455E-03 0
5.60E+01 2nd Quarter 1985 4.196E-04 8.282E-04 1.280E-04 1.215E+01 3rd Quarter 1985 1.155E-03 1.632E-03 0
1.884E+01 4th Quarter 1985 0
1.619E-04 0
2.958+00
TABLE 6 1985 RADI0 ACTIVE LIQUID EFFLUENT ESTIMATE NO. 2 (Curies)
Month Effluent Volume Detection (pCi/t)
Effluent Estimate Gallons Liters Cs-134 Cs-137 Cs-134 Cs-137 January 3.202E+06 1.212E+07
<10
<2 0
0 February 2.808E+06 1.063E+07
<47.2
<58.2 5.02E-04 6.19E-04 March 2.395E+06 9.066E+06
<10 79.0 0
7.16E-04 April 4.552E+05 1.723E+06
<80.1
<109.4 1.38E-04 1.88E-04 May 3.972+05 1.504E+06
<69.8
< 85.0 1.05E-04 1.28E-04 June 1.610E+06 6.095E+06 29 84 1.77E-04 5.12E-04 July 8.161E+05 3.089E+06 98 151 3.03E-04 4.66E-04 August 9.560E+05 3.619E+06
<54.3
< 85.2 1.97E-04 3.08E-04 September 2.929E+06 1.109E+07
<59.1
< 77.3 6.55E-04 8.57E-04 October 7.247E+05 2.743E+06
<10 59 0
1.62E-04 November 1.331E+05 5.038E+05
<10
< 2 0
0 December 1.57 E+06 5.943E+06
<10 28.0 0
1.66E-04 June Co-60 21 pCi/t 1.280E-04 Ci Cs-134 Cs-137 Co-60 H-3 1st Quarter 1985 5.02E-04 1.34E-03 0
5.60E+01 2nd Quarter 1985 4.20E-04 8.28E-04 1.28E-04 1.215E+01 3rd Quarter-1985 1.16E-03 1.63E-03 0
1.884E+01 4th Quarter'1985 0
3.28E-04 0
2.958E+00
TABLE 6A 1985 RADI0 ACTIVE LIQUID EFFLUENT-ESTIMATE NO. 2 (Curies)
Additional Radionuclides Due to Analysis of DRCST(l) Liquid Transfer to RHUT(2)
Nuclide Quarter 1 Quarter 2 Quarter 3 Quarter 4 Co-58 3.05 E-05 Co-60 Nb-97 7.11 E-05 Ag-110m 6.62 E-05 Sb-124 3.35 E-04 Sb-125 2.74 E-04 1.70 E-04 I-131 9.92 E-05 (1) DRCST - Demineralized Reactor Coolant Storage Tank (T-621)
(2) RHUT - Regenerate Hold-Up Tanks b
~-
5 I
TABLE 7 10 CFR 50 APPENDIX I DESIGN OBJECTIVE CALCULATIONS NO. 1 MAXIMUM HYP0THETICAL INDIVIDUAL DOSE (MREM) 1985 Quarter Adult Teenager Child Liver Total Body Liver Total Body Liver Total Body
.1 1.79 1.42 1.82 9.49E-01 3.30 1.04 2
1.61 1.22 1.61 7.36E-01 2.99 7.25E-01 3
3.12 2.36 3.12 1.39 5.80 1.31 4
1.38E-01 1.00E-01 1.42E-01 6.67E-02 2.65E-01 7.40E-02 Total 6.66 5.10 6.69 3.14 12.4 3.15 Basis 1.
1985 ODCM 2.
1985 Radioactive Liquid Effluent Estimate No. 1
t TABLE 8 10 CFR 50 APPENDIX I DESIGN OBJECTIVE CALCULATIONS NO. 2 MAXIMUM HYP0THETICAL INDIVIDUAL DOSE (MREM) 1985 Quarter Adult Teenager Child Liver Total Body Liver Total Body Liver Total Body 1
1.31 1.03 1.34 7.33E-01 2.43 8.61E-01 2
1.61 1.22 1.61 7.37E-01 2.99 7.25E-01 3
3.12 2.37 3.12 1.40 5.80 1.31 4
2.57E-01 1.79E-01 2.59E-01 1.08E-01 4.94E-01 1.08E-01 Total 6.30 4.80 6.33 2.98 11.7 3.00 Basis 1.
1985 ODCM 2.
1985 Radioactive Liquid Effluent Estimate No. 2 w-.---..
TABLE 9 10 CFR 50 APPENDIX I DESIGN OBJECTIVE CALCULATIONS NO. 3 MAXIMUM HYP0THETICAL INDIVIDUAL DOSE (MREM) 1985 Quarter' Adult Teenager Child Liver Total Body Liver Total Body Liver Total Body 1
7.95E-01 6.14E-01 8.94E-01 4.59E-01 1.06 4.07E-01 2
7.78E-01 5.79E-01 8.60E-01 3.77E-01 9.34E-01 2.33E-01 3
1.60 1.20 1.78 7.72E-01 1.92 4.43E-01 4
1.42E-01 9.76E-02 1.61E-01 6.43E-02 1.84E-01 4.21E-02 Total 3.32 2.49 3.70 1.67 4.10 1.13 Basis 1.
Modified ODCM 2.
1985 Radioactive Liquid Effluent Estimate No. 2 4
i
,.