ML20005E362
| ML20005E362 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/21/1989 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20005E342 | List: |
| References | |
| GL-89-01, GL-89-1, PROC-891221, NUDOCS 9001050127 | |
| Download: ML20005E362 (34) | |
Text
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6 MANUAL:
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REVISION:
4 PAGE 1 OF 34 LEAD DEPARTMENT:
EFFECTIVE DATE:
ENVIRONMENTAL MONITORI O D EMERGENCY PREPAREDNESS W'
EMEp MANAGER
/
REVISION
SUMMARY
Complete rewrite to incorporate the provisions of USNRC Generic Letter 89-01 in support of submittal of Technical Specification Proposed Amendment No. PA-182 (Appendix C Defueled Technical Specifications).
This revision is administrative in that no REMP requirements (Table 1) or sample locations (Table 6) have been deleted.
Five editorial changes have been made to Table 6 to correct previous omissions.
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9002050127 891228 PDR ADOCK 05000312 PDC P
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MANUAL:
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l
REVISION:
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PAGE 2 OF 34 TABLE OF CONTENTS SECTION TITLE EAGI
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r 1.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 3
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2.0-LAND USE CENSUS 14 i-
~3.0-FUEL CYCLE DOSE 15 4.0.
INTERLABORATORY COMPARISON PROGRAM 17 l
5.0 DEFINITIONS 17 6.0 RADIOLOGICAL REPORT REQUIREMENTS 18
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7.0 REFERENCES
19 8.0-IDENTIFICATION CONVENTION FOR TABLE 6 SAMPLE I4 CATIONS 21 i
TABLE TITLE EAGI i
1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 5
2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION, LLD 10 3
REPORTING LEVELS FOR REMP MEASUREMENTS 13 4
SAMPLE TYPES / CLASSES 22 5
SECTOR DESIGNATIONS 23 6
RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS 24
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MANUAL:
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l
REVISION:
4 PAGE 3 OF 34 RADIOLOGICAL ENVIR030tENTAL MON 1TORING REQUIREMENTS AND BASES I
This Manual contains the minimum requirements for the conduct of the i
l Rancho Seco Radiological Environmental Monitoring Program (REMP).
The requirements are consistent with USNRC regulations formerly contained in the Rancho Seco Accendix A Technical Specifications, through Amendment #114, as Limiting Conditions for Operation, Surveillance Standards (and associated Bases) and Administrative Controls.
This revision was prompted by the provisions of Generic Letter 89-01 (reference 7.14).
For ease of intercomparison, each section contains a reference to the applicable Technical Specification (TS) Accendix A section from which the requirements were derived.
1.0 RADIOLOGICAL ENVIRONMENTAL MONITORING (TS 4.1, 3.22/4.26)
I The REMP shall be conducted AT ALL TIMES as specified in i
Table 1.
1.1 With the REMP not being conducted as specified in Table 1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report (AREOR) required by Section 6.1, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to-hazardous conditions or seasonal unavailability.
1.2 With the level of radioactivity in an environmental sampling medium exceeding the Reporting Level of Table 3 when averaged over any calendar quarter, in addition to complying with the requirements of Section 3.0, FUEL CYCLE DOSE, prepara and submit to the Commission within 30 days after the level of radioactivity has been determined, a Special Report hich includes an evaluation of any release conditions, environmental factors or other aspects which caused the Reporting Levels to be exceeded.
This report will define corrective actions to reduce emissions such that potential exposures will meet 10 CFR 50 Appendix I annual dose limitations.
When more than one of the radionuclides in Table 3 are detected in the sampling medium, the Special Report shall be submitted if the Reporting Level fraction summation equals or exceeds unity (1.0).
When radionuclides other than those in Table 3 are detected and are the result of plant effluents, this Special Report shall be submitted if the potential annual dose to an individual is greater than or equal to the calendar year limits of 10 CFR 50 Appendix I.
This Special Report is not required if the measured level of radioactivity was not the result of plant effluents; however, the condition shall be reported and described in the AREOR.
o MANUAL:
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM j
REVISION:
4 PAGE 4 0F 34 i
1.3 With milk or fesh leafy vegetation samples unavailable from any of the sample locations required by Table 1, identify the cause of the unavailability of samples and the locations for obtaining replacement samples in the next AREOR.
The locations from which samples were unavailable may then be deleted from Table 6 provided the. locations from which the s
replacement samples were obtained are added to Table 4 as replacement locations, if available.
1.4 The radiological environmental monitoring samples shall be collected per Table 1 from the locations shown in Table 4.
These samples shall be analyzed to the requirements of Table 1 and Table 2.
1.5 The environmental air monitors used for sampling the Table 1 AIRBORNE EXPOSURE PATHWAY shall be subject to a MONTHLY function check and shall be calibrated ONCE EVERY 18 MONTHS.
1.6 The REMP required by Section 1.0 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 tha Station operation.
This monitoring program thereby implementsSection IV.B.2 of Appendix I to 10 CFR 50 and supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on tha basis of the effluent measurements and Offsite Dose Calculation Manual (ODCM) modeling of the environmental i
exposure pathways.
Guidance for Section 1.0 was provided by reference 7.13.
REMP L
changes may be initiated based on operational experience and changes in the regional population or agricultural practices.
The detection capabilities required by Table 2 are state of the art for routine environmental measurements in industrial l
laboratories.
The LLD's for drinking water meet the requirements of 40 CFR 141.
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MANUAL:
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REVISION:
4 PAGE 5 OF 34 Table 1 Page 1 of 5 i
RADIOLOGICAL ENVIRONMENTAL MONITORING Program
- AIRBORNE BIPOSURE PATNWAY Samnlina and Analysis Reauirements Minimum Sample Load 8
Collection Method Continuous air sample Collection Frequency:
At least WEEKLY as required by filter dust loading Analysis Type:
8 Iodine Adsorber - Iodine-131 (pCi/m )
D 8
Particulate Filter - Gross Beta & Gamma Spe:
(pCi/m )
Analysis Frequency:
Iodine Adsorber - Each sample Particulate Filter - Gross Beta each sample', Gamma Spec each sample" and QUARTERLY' DIRECT RADIATION EXPOSURE PATMWAY l
Samnlina and Analysis Recuirements Minimum Sample Load:
40 Collection Method:
Continuous monitoring' Collection Frequency:
At least QUARTERLY Analysis Type:
Integrated gamma exposure (mR or mrem)
Analysis Frequency:
Gamma exposure QUARTERLY SURFACE WATER EXPOSURE PATRWAY Samelina and Analysis Reauirements Minimum Sample Load:
5 l-Collection Method:
Four (4) grab and one (1) downstream composite Collection Frequency:
Downstream Composite - CONTINUOUS 8 Grab - At least WEEKLY M
Analysis Type:
Gamma Spec, tritium and iodine-131 (p$i/L)
Analysis Frequency:
Composite - MONTHLY and/or FORTNIGHTLY 4
Grab - Each Sample a-
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MANUAL:
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REVISION:
4 PAGE 6 OF 34 I
.i Table 1 (cont.)
Page 2 of 5
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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM *
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GROUNDWATER EXPOSURE PATNWATI Samnlina and Analysis Reauirements I
Sample Load:
3 e
t Collection Methods.
Grab i
Collection Frequency:
Grab - At least QUARTERLY
.i Analysis Typer Gamma Spec, tritium and iodine-131 *' (pCi/L)'
h Analysis Frequency:
Each sample i
SEDIMENT REPOSURE PATNWAY l
t Samnlina and Analysis Reauirements i
Minimum Sample Load:
2 t
L Collection Methods _
Surface deposit grab (top 3 inches, 2 feet from shoreline)
Collection Frequency:
At least SEMI-ANNUALLY Analysis Type Gamma Spec (pCi/kg-wet) l Analysis Frequency:
Each sample AQUATIC LIFE CONSUNPTION PATNWAY Samelina and Analysis Reauirements Minimum Sample Load:
3 Collection Method Net, line or trap Collection Frequency:
At least QUARTERLY Analysis Type:
Gamma Spec of edible portions (pCi/kg-wet)
Analysis Frequency:
Each sample
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MANUAL:
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REVISION:
4 l
PAGE 7 OF 34 l
t Table 1 (cont.)
Page 3 of 5 t
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- i MILE CONSUMPTION PATHAY.
j Samelina and Analysis Reauirementg i
Minimum Sample Load:
4 I
i Collection Method:
Grc'o I
Collection Frequency:
At least WEEKLY" or MONTMLY Analysis Type:
Gamma Spec and Iodine-131 (pCi/L) l Analysis Frequency:
Each sample j
i IRRIGATED CROP ("TOODH) CONSUMPTION PATEWAY
{
Samelina and' Analysis Recuirements Minimum sample Load:-
2 Collection-Method:
Grab Collection Frequency:
At time of harvest or MONTHLY"
l-Analysis Type:
Gamma Spec,of edible portions (pCi/kg-Wet)
Analysis Frequency:
Each sample NON-IRRIGATED CROP ~ (HPOODH) CONSUMPTION PATNAY i
Samolina and Analysis Reauirements i
Minimum Sample Load 2
Collection Method Grab Collection Frequency:
At time of harvest or MONTHLY'
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Analysis Type Gamma Spec of edible portions (pcifNg-wet) f Analysis Frequency:
Each sample l
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MANUAL:
RADIOLOGICAL ENVIRONMENTAL MONITORING PRdu J.M REVISION:
4 PAGE 8 OF 34 Table 1 (cont.)
Page 4 of 5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
' Notes for Table 1 Sample site descriptions implementing Table 1 are ider.tified in Table 5.
b For purposes of Table 1, analysis by gamma spec (troscopy) is defined as the identification and quantification of gamma-emitting nuclides that may be attributable to Station effluents.
As a minimum, specific searches shall be made for the applicable Table 2 nuclides.
Particulate filters should be analyzed after at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> have elapsed to allow for'the decay of interfering radon and thoron daughter nuclides.
Applies only to each field indicator particulate filter having l
d gross beta activity which is greater than ten (10) times the highest field control particulate filter gross beta activity for the same sampling interval.
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Analysis shall be performed of each location composite of filters accumulated over a quarter.
Monitoring shall be provided by thermoluminescence dosimeter (TLD) having at leart two (2) phosphors AND/OR'one (1) dose rate recording device such as a pressurized ion chamber.
i o 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 analysis frequency (e.g., MONTHLY).
h Iodine analysis is required only if the water is utilized as a drinking water. supply for human consumption.
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Required only if the calculated predicted potential dose delivered as a result of annual drinking water consumption exceeds one (1) arem.
The dose shall be calculated for the maximum member of the
-public using the methodology contained in the ODCM and actual Station source terms.
-MANUAL:
RADIOLoll' CAL _ ENVIRONMENTAL MONITORING PROGRAM REVISION:
4 PAGE 9 OF 34 Table 1 (cont.)
Page 5 of 5 RADIOLOGICAL ENVIRONMENTAL MONITORING PRoakAM l'
Includes groundwater supplies utilized for domestic consumption.
"~ When milch animals are grazing on pasture.
I If harvest occurs continuously, frequency shall be at least MONTHLY
-throughout the growing season.
- To effectively monitor this pathway, tuberous, _ root and vegetable crop samples should be obtained.
Irrigated grasses should be sampled if used as forage for beef or milch animals.
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RADIOIDGICAL ENVIRONMENTAL MONITORING PROGRAM
- REVISION:
-4 PAGE 11 OF' 34 Table 2 (cont.)
Page 2 of 3 MAXIMUM VALUES FOR 'THE IDWER LIMIT 'OF DETECTION, LLD" The Lower Limit of Detection (LLD) values for the radionuclides' presented in Table 2 are those.
recommended ir; reference 7.13.
The LLD of a radioanalysis system is that value which will indicate the presence'or absence'of.-
radioactivity in a sample when the probability of a false positive'and of a false negative:
datermination is, stated.
The' probabilities of the false positive and false-negative determinations, are taken as equal to 0.05.
The equation for' estimating the maximum LLD is given. by the following -
equation:
LLD =
2.71/t.
+ 3.29Su
, pCi/L, pCi/kg-wet or pCi/m#
0.037 (YEV) exp(-lt )
e where:
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factor to account for Poisson statistics at very low background count rate 2.71
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i twice the constant used to establish the one-sided 0.95 confidence interval 3.29
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=
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[ B/ (t t.) +
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=
background count interval, sec ts
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sample count interval, sec t,
=
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7 MANUAL:
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REVISION:
4 PAGE 12 OF 34
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Table 2 (cont.)
Page 3 of 3
' MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION, LLD**d Y
= radiochemical process yield.(product of all factors such as abundance, chemical yield, etc.)
E
= counting efficiency, cts / dis V = sample volume or mass, L or kg 1
= physical decay constant for the associate nuclide, sec" te = elapsed time from the midpoint of sample collection to the midpoint of counting, see The LLD is defined as an a priori (before the fact) estimate and is not to be calculated for each sanple analyzed on an a posteriori (after the fact) basis.
Occasionally, unavoidably small sample sizes or other uncontrollable circumstances may result in a priori LLD values not being met.
In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.
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LLD for water samples utilized for human consumption only.
Composite analysis LLD is shown; individual sample LLD is 0.05.
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Other peaks which are measurable and identifiable, together with the nuclides in Table 2, shall be identified and reported.
I Total for parent and Vaughter.
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MANUAL:
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
. REVISION:~
4' PAGE 13 OF 34 Table 3 REPORTING LEVELS FOR REMP MEASUREMENTS Airborne Water Particulate or Fish
-Milk Food Products Analysis (pCi/L)
Gases (pCi/m )
(pCi/kg-vet)
(pci/L)
(pCi/kg-wet) 3 H
20,000*
Mn" 1,000 30,000 Fe" 400 10,000 Co" 1,000 30,000 Co" 300 10,000 Zn" 300 20,000 6
Zr Nb" 400 I'
2 0.9 3
100 Cs*
30 10 1,000 60 1,000 Cs'37 50 20 2,000 70 2,000 6
Ba,La*
200 300*
Gross Beta 40 2
(
Applies to water samples utilized for human ' consumption only.
This value is as specified in 40 8
CFR 141.
6 Total for parent and daughter.
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MANUAL:
RADIOLOGICAL ENVIRONMENTAL MONITORING PRbGRAM REVISION:.
4 PAGE 14 OF 34 4
2.0 LAND USE CENSUS (TS 3.23/4.27)
A Land Use Census shall be conducted annually and shall identify the location of the nearest milk animal, the nearest residence r
and the nearest garden of greater than 500 square feet producing
-fresh leafy vegetation in each of the 16 meteorological sectors-within a distance of five (5) miles. - Broad leaf vegetation sampling may be performed at the Station site boundary in the direction sector with the highest deposition parameter in lieu of-the garden census.
The Land Use Census shall also include information relevant to the liquid effluent pathway and gaseous effluent pathway such that the ODCM-and the REMP Manual can-be kept current with existing environmental and societal use of land surrounding the Station.
2.1 The Land Use Census shall be conducted by using methods that will provide the best results, such as-door-to-door survey, aerial survey, or by consulting local agriculture authorities.
The I.and Use census, or portions thereof, shall be conducted during the appropriate time of the year to provide the best results.
The results of the Land Use census shall be included in the AREOR covering the censused year as required by section 6.1.2.
2.2 With the Land Use Census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in the ODCM for compliance with 10 CFR 50-Appendix I, identify the new locations in the next AREOR.
2.3 With the Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location-from which samples are currently being obtained in accordance with Section 1.0, RADIOLOGICAL ENVIRONMENTAL MONITORING, add the new location (s) to Table'6 within 30 days or submit a Special Report to the Commission that identifies the cause(s) for exceeding these requirements and the proposed corrective actions for precluding recurrence.
The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s) (via.the same exposure pathway) may be deleted from Table 6 after October 31 of the census year.
Identify the new location (s) in the next AREOR including a revised figure (s) and table for the REMP Manual reflecting the new location (s).
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MANUAL:- RADIOLOGICAL-ENVIRONMENTAL MONITORING PROGRAM REVISION:
4 PAGE 15 OF 34 2.4 The Section 2.0 requirements are provided to ensure that changes-in the use of unrestricted areas are identified and that modifications to the'REMP and the ODCM are made if required by the-results of the Land Usa census.
These requirements also satisfy the requirements of Section IV.V.3 of Appendix I to 10 CFR 50.
Restricting the Land Use Census to gardens of greater than 500 square feet provides assurance that.significant exposure pathways via leafy vegetation consumption will be identified and monitored since a garden of this size is theminimum required to produce the quantity (26 kg/ year) of leafy vegetation assumed (reference 7.15) to be consumed by a child.
In specifying this minimum garden size, it was further assumed that 20. percent of the garden was used for growing broad leaf vegetation (e.g.,
lettuce or abbage) and that the productivity was two (2) kg/m In addition, by gathering information on the liquid effluent pathway and the gaseous effluent pathway, the Land Use census provides assurance that proper radiological environmental monitoring and radioactive effluent controls are in place for the adequate protection of the health and safety of the general public.
3.0 FUEL CYCLE D)SE (TS. 3.25; TS 4.29 does not apply to the REMP)
The dose or dose commitment to any real MEMBER OF THE PUBLIC due to releases of radioactive material in gaseous and liquid effluents and to direct radiation from uranium fuel cycle sources shall AT ALL TIMES be limited to less than or equal to 25 mrem (total: body or any organ), and 75 mrem (thyroid), in a calendar year.
3.1 With any of the Reportir:g Levels of Table 3 being exceeded, calculations shall be made to determine whether the section 3.0 fuel cycle dose / dose commitment limits have been exceeded.
Contributions from direct radiation sources (including outside storage tanks, etc.) shall be included in this calculation.
3.2 If the Section 3.0 limits have been exceeded, prepare and submit to the Commission within 30 days a Special Report that defines the corrective action to be taken to reduce subsequent releases to-prevent recurrence of exceeding the Section 3.0 limits.
This Special Report shall also include a schedule for achieving conformance with the Section 3.0 limits.
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MANUAL:
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REVISION:
4 PAGE 16 OF 34 This_Special Report,-as defined in 10 CFR 20.405(c), shall 1
include an analysis that estimates the radiation exposure (dose).to a MEMBER OF THE PUBLIC_from uranium fuel cycle i
sources, including all effluent pathways and direct radiation,
-in a calendar year that includes the release (s) covered by this-Special Report.
This Special Report shall also describe levels of radiation and concentrations of radioactive material involved, and.the cause of the' exposure levels or concentrations.
3.3 If the estimated dose (s) exceeds Section 3.0 limits, and if the release condition resulting in the violation of 40 CFR 190 has not already been corrected, the Special Report shall also include a request for a variance in accordance with the provision of_40 CFR 190.
Submittal of the Special Report is considered a timely request, and a variance is granted until USNRC staff action on the request is complete.
3.4 The Section'3.0 requirements are provided, in part, to meet the dose limitations of 40 CFR 190 that have been-incorporated into 10 CFR 20 by 46 FR 18525.
For the Rancho Seco site, it is unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the Station remains within twice the numerical guides for design objectives of 10 CFR 50 Appendix I and if direct radiation'is kept small.
The Special Report will describe a course of action which should result in the limitation of the dose to a MEMBER OF THE s
PUBLIC for a calendar year 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 L
i uranium fuel cycle sources is negligible, with the exception L
that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of five (5) miles must be considered.
If the dose to any MEMBER OF THE PUBLIC is evaluated to exceed p
the requirements of 40 CFR 190, the Special Report along with a request for a variance (provided the release conditions y
resulting in violation of 40 CFR 190 have not already been corrected) is considered to be a timely request and fulfills the requirements of 40 CFR 190 until USNRC staff action is completed.
An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any i
l operation which is part of the uranium fuel cycle.
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t MANUAL:
R\\DIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REVISION:
4 PAGE 17 OF 34 4.0 INTERLABORATORY COMPARISON PROGRAM (TS 3.26/4.30)
The laboratory performing analysis of Table-6 samples pursuant to the requirementslof Table i shall AT ALL TIMES participate in an Interlaboratory Comparison Program (ICP) approved by the Commission.
4.1 With ICP analyses not being performed as required in Section 4.0, report the corrective actions taken to prevent a recurrence to the Commission in the AREOR as required by section 6.1.
4.2 A summary of the results obtained as a participant in the ICP shall be included in the AREOR as required by section 6.1.
4.3 The requirement to participate in an ICP is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR 50.
5.0 DEFINITIONS (TS 1.0) 5.1 FORTNIGHTLY - Once per fourteen (14) days 5.2 RESTRICTED AREA - That portion of the Station property, access to which is controlled by security fencing, equipment and personnel.
5.3 SITE BOUNDARY-- That portion of the Station property beyond which the District has no legal basis for controlling access.
The distance from the Reactor Building to the closest Site Boundary location in each of the 16 meteorological sectors is shown below:
Sector Distance (m)
Sector Distanca (m)
N 659 S
1759 NNE 674 SSW 1107 11 NE 801 SW 1153 ENE 1211 WSW 983 E
3796 W
966 ESE 1673 WNW 987 SE 1153 NW 788 SSE 1202 NNW 670 5.4 MEMBER (S) OF THE PUBLIC - Individuals, who by virtue of their occupational status, have no formal association with the plant.
This category shall include non-employees of the District who are permitted to use portions of the site for
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MANUAL:
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REVISION:
4 PAGE 18 OF 34 recreational, occupational or other purposes not associated' with Station functions.
This category shall D21 include non-1 employees (such as vending machine service men or postmen) who, as part-of their formal job function, occasionally enter an area that is controlled by the Station for purposes of protection of individuals from exposure to radiation and radioactive materials.
- 5. 5 -
MAXIMUM. EXPOSED - (HYPOTHETICAL). INDIVIDUAL - An imaginary individual who, with regard to usage or exposure pathway parameters in the vicinity of the Station, has habits greater than usually expected for the average of the population in general.
6.0 RADIOLOGICAL REPORT ~REOUIREMENTS (TS 6.9.2) 6.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR) 6.1.1 An AREOR covering the operation of the Station during the previous calendar year shall be. submitted to the USNRC prior to-May 1 of each year.
6.1.2 The AREOR shall include summaries and statistical evaluations of the results of the radiological environmental surveillance activities for the report period, including (as appropriate) a comparison with operational controls.
The AREOR shall also include the 1
results of the Land Use Census required by Section 2.0, LAND USE CENSUS.
In the event a radionuclide concentration
' should be confirmed in excess of the Reporting Level in Table 3 by environmental measurements, the AREOR shall describe a planned course of corrective action.
l 6.1.3 The AREOR shall include summarized and tabulated results of all radiological environmental samples taken during the E
AREOR period.
In the event that some results are not available for inclusion, the AREOR shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in l-a supplementary report.
l-l 6.1.4 The AREOR shall include a summary description of the REMP (including a map of all sampling locations keyed to a table giving di, stances and directions from the Reactor Building) and the results of participation in the Interlaboratory Comparison Program required by Section 4.0.
The AREOR shall also include information related to Section 3.0, URANIUM FUEL CYCLE DOSE.
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JMANUAL:
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 5
REVISION:
4 PAGE 19 OF 34 6.2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (SARERR)
Any, changes made to the REMP MANUAL during the SARERR reporting period shall be included in that SARERR.
7.0 REFERENCES
The following documents pertain to the design and conduct of radiological environmental monitoring programs:
7.1 American National Standards Institute (ANSI}
Performance.
Testina and Procedural Soecifications for Tiiwrmoluminescence Dosimetry (Environmental Aeolications), ANSI Standard N545 (1975).
7.2 American' Nuclear Insurers and Mutual Atomic Energy Liability Underwriters (ANI/MAELU), Environmental Monitorina Procrams, Information Bulletin 86-1 (1986).
7.3 ANI/MAELU, " Radiological Environmental Monitoring,"
Engineering Inspection Criteria for Nuclear Liability Insurance, Section 5.2, Revision 2 (1988).
7.4 ANI/MAELU, Nuclear Liability Insurance Records Retention, Information. Bulletin 80-1A, Rev. 2 (1986).
7.5 Committee on the Biological Effects of Ionizing Radiations (BEIR), The Effects on Pooulations of Excosure to Low Levels of Ionizina Radiation:
1980, BEIR III Report (1980).
7.6 National Council on Radiation Protection (NCRP), A Handbook of Radioactivity Measurements Procedures, NCRP. Report No. 58, Second Edition (1985).
7.7 NCRP, Radiolocical Assessment:
Predictina the Transcort, Bioaccumulation and Uotake by Man of Radionuclides Released to the Environment, NCRP Report No. 76 (1984) 7.8 Sacramento Municipal Utility District, " Radiological Environmental Monitoring Program Evaluation," Internal Report (1987).
7.9 USEPA, " Environmental Standards for the Uranium Fuel Cycle,"
40 CFR 190,.Subpart B (1987).
7.10 USEPA, Ucaradina Environmental Radiation Data, Health Physics Society Committee Report HPSR-1, EPA 520/1-80-012 (1980).
7.11 USNRC, " Criterion 64 - Monitoring Radioactive Releases," 10 CFR 50, Appendix A (1988)
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-7.12 USNRC, " Numerical Guides for Design Objectives and Limiting Conditions'for Operation to Meet the Criterion 'As Low As Is Reasonably Achievable' for Radioactive Material In Light Water Cooled Nuclear Power Reactor Effluents," 10 CFR 50, Appendix I L
(1988).
7.13 USNRC, "An Acceptable Radiological Environmental Monitoring Program," Branch Technical Position, Rev. 1 (November 1979).
7.14' USNRC, " Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or the Process Control Program", Generic Letter 89-01 (January 31, 1989).
7.15 USNRC, Calculation of Annual Doses to Man from Routine H
Releases of Reactor Effluents for the Purcose of Evaluatina-
'Comoliance with 10 CFR 50. Accendix I, Regulatory Guide 1.109 (1977) 7.16 USNRC, Estimati-na Acuatic Discersion of Effluents from I
Accidental and Routine Reactor Releases for the Purnose'of Imolementina Accendix I, Regulatory Guide 1.113 (1977).
7.17 USNRC, Measurina and Reportino of Radioactivity in the Environs of Nuclear Power Plants, Regulatory Guide 4.1 (1973).
7.18 USNRC, Precaration of Environmental Reoorts for Nuclear Power Stations, Regulatory Guide 4.2, Rev. 2 (1976) 7.19 USNRC, Performance. Testina and Procedural Soecifications for Thermoluminescence Dosimetry:
Environmental Aeolications,"
7.20 USNRC, Ouality Assurance for Radiolocical Monitorina Procrama (Normal Ooerations) - Effluent Streams and the Environment, Regulatory Guide 4.15, Rev. 1 (1979).
7.21 USNRC, Radiolocical Assessment:
A Textbook on Environmental Dose Assessment, NUREG/CR-3332 (1983) 7.22 UENRC, Lower Limit of Detection:
Definition and Flaboration of a Procosed Position (or-Radioloaical Effluent and Environmental Measurements, NUREG/CR-4007 (1984).
7.23 USNRC, Radioloaical Effluent Technical Soecifications for PWRs, NUREG-0472, Rev. 2 (July 1979).
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MANUAL:. RADIOI.OGICAL ENVIRONMENTAL MONITORING PROGRAM REVISION:
4 PAGE 21 OF 34 7.24 USNRC, Radiolocical Monitorina by NRC Licensees for Routine Operations of Nuclear Facilities, NUREG-0475 (1978).
7.25 USNRC, Methods for Demonstratina LWR Comoliance With the EPA Uranium Fuel Cycle Standard (40 CFR 1901, NUREG-0543 (1980).
7.26 USNRC, " Permissible Levels of Radiation in Unrestricted Areas," 10 CFR 20.105 (1988).
-7.27 USNRC, " Reports of Overexposures and Excessive Levels and Concentrations," 10 CFR 20.405 (1988).
7.28 Merril Eisenbud, Environmental Radioactivity From Natural.
Industrial', and Military Sources, Third Edition (1987).
8.0 IDENTIFICATION CONVENTION FOR TABLE 6 SAMPLE LOCATIONS Sampling and monitoring sites designated in Table 6 are identified using the following convention:
8.1 -
To establish the fact that the Table 6 samples originate from i
the Rancho Seco REMP, the letter "R" precedes every sample site designator.
8.2 The next two (2) letters are selected to identify SAMPLE TYPE.
Refer to Table 4 for a listing of the SAMPLE CLASSES / TYPES and the associated two letter abbreviation.
8.3 The numbers following the SAMPLE TYPE abbreviation reflect the straight-line DISTANCE (miles) to the sample site, referenced to the center of the Reactor Building.
8.4 Following the distance, a SECTOR DESIGNATOR letter is included to specify which of the 16 meteorological sectors the sample site is encompassed.
Refer to Table 5 for a listing of the sector designators.
8.5 The final character in the sample site designation is the letter "O" which designates the sample as being one added to the REMP following Station initial criticality.
l 8.6 The present identification convention has been selected in preference to the system originally used to identify samples and sites..Since it is desireable to retain the ability to identify, and continue to use data from, previously collected samples, the former identification convention is also shown parenthetically in Table 6.
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' t' Table 4 SAMPLE TYPES / CLASSES Type / Class Desianation Definition AG Algae
-AS Airborne Particulate / Iodine BF Cattle Beef BT Cattle Thyroid CF Crawfish CON Control (CLASS)
DU Duck DW Drinking Water FG Frog FS Fish HS Honey IND Indicator (CLASS)
LV Garden Vegetation MF Raw Milk MS Mud & Silt, Sediment PH Pheasant PV Pasturage (forage)
RB Rabbit RI Rice RW Runoff, Surface Water SG Small Game SL Soil SW Surface Water TL Direct Radiation (TLD)
WW Well huter
Fu
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4 PAGE 2 3 OF 3 4 Table 5 SECTOR DESIGNATIONS Sector Letter Sector Decrees and True North Commass Sector A
348.75
<N>
11.25 B
11.25
<NNE>
33.75 C
33.75
<NE>
56.25 D
56.25
<3NE>
78.75 E
78.75
<E>
101.25 F
101.25- <BSE>
123.75 G
123.75
<SE>
146.25 H
146.25
<8SE>
168.75 J-168.75
191.25 K
191.25
<ssW>
213.75 L
213.75
<8W>
236.25 M
236.25
<W8W>
258.75 N
258.75
<W>
281.25 P
281.25
<WNW>
303.75 Q
303.75
<NW>
326.25 R
326.25
<NNW>
348.75
+-a
r:
u a
-h t
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PAGE 24 OF 34 Table 6 Page 1 of 11 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS -
-Sample Sample Collection Identification Class Frequency Location Identification-(Former ID)
AIB-(Particulates and Iodine) 4 RASO.1CO.
IND Neekly On Site (PAP Building (RAHO)
Carport)
RASO.6KO IND Weekly Tokay Substation (RADO) _
' RAS 6.2QO IND Weekly Miller Residence
.(RAAO)-
RAS 7.8CO IND.
Weekly Carbondale (RAFO)
RAS 9.0E0 IND Weekly Ione (RAEO)
RAS 10.H0 CON Weekly Fish Hatchery 1
(RAGO)
RAS 18.KO CON-Weekly Lodi Substation (RACO)
RAS 23.QO CON Weekly SMUD Headquarters (RABO)
MILE RMFO.8DO IND Weekly Marciel Ranch (RMFDO)
RMF5~.8PO IND Weekly Mederios Dairy (RMFAO)
RMF8.2KO IND Weekly Angelo Dairy (RMFBO)
RMF24.0LO CON Weekly DeSnayer Dairy (eff. 10/07/88) i
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Page.2 of 11 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS Sample Sample Collection Identification Class
- Frequency-Location Identification (Former ID)
RUNOFF WATER RRWO.3MO IND Biweekly Effluent Discharge (RRWCO)
RRWO.6MO IND Biweekly Site Boundary SURFACE WATER RSWO.7NO IND Monthly Water Sump-RSW1.3F0 IND Monthly Rancho Seco Reservoir-(RSWCO)
RSW3.7NO CON Monthly Folsom South Canal (RSWBO)
Composite Sample RSW15.5FO IND Monthly Lake Pardee Reservoir (eff. 08/09/88)
RSW12.OGO CON Monthly Camanche Reservoir (RSWAO)
RSWO.3MO IND Monthly Effluent Discharge composite Sample DRINKING WATER RDWO.lGO IND Monthly Rancho Seco Site (RWWCO)
Consumption (potable water)
RAIN WATER RRNO.6E0 IND Seasonal Met Station RRN23.OQ.0 CON Seasonal SMUD Headquarters i
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Page 3 of 11-RADIOI4GICAL ENVIRONMENTAL MONITORING LOCATIONS 1
Sample _
Sample Collection 1
Identification Class.
Frequency Location Identification (Former ID)
PASTURAGE-RPVO.8DO IND Monthly Marcial Ranch
-(RLVHO)
RPV24.0LO CON Monthly DeSnayer Dairy.
(off. 10/07/88)
RPV5.8PO IND-'
Monthly Moderios Dairy (RLVFO)
RPV8.2KO IND Monthly Angelo Dairy (RLVGO)
~
WELL WATER RWWO.3E0 IND Quarterly Site Well (RWAO)
RWWO.8DO CON Quarterly Marciel Ranch (also serves as a drinking water control sample)
RWWO.8HO IND Quarterly Clay Cattle Feedlot (RWWEO)
RWW3'.7MO IND Quarterly Silva Feed Lot (NEW)_
RWW2'.1NO-IND Quarterly Silva Rancho Vaquero Well (NEW)
RWW1.8F0 IND Quarterly Rancho Seco Reservoir (RWWEO)
RWW2.1MO IND' huarterly Clay Area Well (RWWBO)
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Page 4 of 11 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS Sample Sample Collection
--Identification Class Frequency Location Identification-(Femer ID)
SEDIMENT (" MUD AND SILT")..
RMSO.3MO IND Quarterly Effluent Discharge RMSO.6MO IND Quarterly Site Boundary (RMSEO)
RMSO.7NO.
IND Quarterly Water Sump RMS1.3F0 IND Quarterly Rancho Seco Reservoir (RMSCO)
RMS1.8NO IND Quarterly Confluence of Clay and Hadselville Creeks RMS2.2NO IND Quarterly Hadselville Creek and Clay Station Road (eff.1/88)
RMS14.OMO IND Quarterly Laguna Creek at Twin Cities Road RMSO.2HO IND Quarterly Storm Drain Outfall 1 RMSO.2HO IND Quarterly Storm Drain Outfall 2 RMS3.7NO IND Quarterly Laguna Creek at Folsom South Canal RMSS.4MO IND Quarterly Laguna Creek at Laguna Road RMS10.ONO IND Quarterly Laguna Creekjat McKenzie Road RMS12.OGO CON Quarterly Camanche Reservoir ELSH Include predator (e.g., bass, sunfish) and scavenger (e.g.,
catfish, sucker) species.
RFSO.3MO IND Quarterly Clay Creek near the PREDATOR Restricted Area Boundary
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Page 5 of 11 q
J RADIOIDGICAL ENVIRONMENTAL MONITORING LOCATIONS Sample Sample Collection Identification Class Frequency Location Identification i
(Former ID)
RFSO.3MO IND Quarterly Clay Creek near the SCAVENGER Restricted Area Boundary RFSO.6MO IND-Quarterly Clay Creek near the Site PREDATOR Boundary RFSO.6MO IND Quarterly Clay Creek near the Site RFSO.7NO
'IND Quarterly Water sump (pond) at the PREDATOR Site Boundary RFSO.7NO IND Quarterly Water sump (pond) at the SCAVENGER
- Site Boundary RFSl.5F0 CON Quarterly Rancho Seco Reservoir PREDATOR
-RFS1.5F0' CON Quarterly Rancho Seco Reservoir i
SCAVENGER RFSl.8NO IND Quarterly Confluence of Clay and PREDATOR Hadselville Creeks t
RFSl.8NO IND Quarterly Confluence of Clay and SCAVENGER Hadselville Creeks RFS2.2NO IND Quarterly Hadselville Creek at PREDATOR Clay Station Road RFS2.2NO IND Quarterly Hadselville Creek at SCAVENGER Clay Station Road l
RFS3.7NO IND Quarterly Laguna Creek near Folsom PREDATOR South Canal RFS3.7NO IND Quarterly Laguna Creek near Folsom SCAVENGER South Canal RFSS.4MO IND Quarterly Laguna Creek at Laguna PREDATOR Road l
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Table 6 (Cont.)
Pagc 6 of 11 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS 1
l l
Sample Sample Collection Identification Class Frequency Location Identification (Former ID)
RFS10.0MO IND Quarterly Laguna Creek at McKenzie l
PREDATOR Road RFS10.0MO IND Quarterly Laguna Creek at McKenzie
- E SCAVENGER Road l
RFS14.0MO IND Quarterly Laguna Creek at Twin PREDATOR Cities Road RFS14.0MO IND Quarterly Laguna Creek at Twin SCAVENGER Cities Road RFS5.4MO IND Quarterly Laguna Creek at Laguna SCAVENGER Road ALGAE SAMPLES RAGO.3MO IND Quarterly Effluent Discharge (RBAO)
RAGO.6MO IND Quarterly Site Boundary RAGO.7NO IND Quarterly Water sump (pond) at the Site Boundary RAG 1.3F0 CON Quarterly Rancho Seco Reservoir RAG 1.8NO IND Quarterly Confluence of Clay and Hadselville Creek RAG 2.2NO IND Quarterly Hadselville Creek near Clay Station Road RAG 3.7NO IND Quarterly Hadselville Creek (RBBO) at Folsom South Canal RAG 5.4MO IND Quarterly Laguna Creek at Laguna Road RAG 10.ONO IND Quarterly Laguna Creek at Twin Cities Road
e)
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Page 7 of 11 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS 1 ample
. Sample Collection
' Identification Class Frequency Location Identification (Former ID)
RAG 14.OMO-IND Quarterly
. Laguna Creek at McKenzie Road E.Ql.L RSLO.2JO IND Quarterly Storm Drain outfall 3 IND Quarterly Storm Drain Outfall 4' RSLO.2KO RSLO.3LO IND Quarterly
' Storm Drain Outfall 5 RSLO.2HO IND Quarterly Storm Drain Outfall 6 RSLO.3MO IND.
Quarterly Storm Drain Outfall 7 RSLO.31MO IND' Quarterly Storm Drain Outfall 8 RSLO.32MO IND Quarterly Storm Drain Outfall 9 RSLO.5AO.
IND Quarterly North Site Garden RSLO.6MO IND Quarterly Site Boundary RSLO.3AO IND Quarterly Storm Drain Outfall 10 (eff. 7/88)
RSLO.3QO IND Quarterly Storm Drain outfall 11 (eff. 9/88)
RSLO.3NO IND Quarterly Storm Drain Outfall 12 RSLO.7NO IND
. Quarterly Silva Property RSL1.3F0~
CON Quarterly Rancho Seco Reservoir RSLl.5NO IND Quarterly Silva Property RSL1.8NO IND Quarterly Silva Property I
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MANUALt RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REVISION:
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.l Table 6 (Cont.)
Page 8 of 11 RADICI4GICAL ENVIRONMENTAL MONITORING LOCATIONS Sample Sample Collection Identification Class Frequency Location Identification (Former ID)
CRAWFISH
-RCFO.6MO IND Quarterly Clay Creek at the Site Boundary RCF3.8PO CON Quarterly Folsom South Canal RCFO.7No IND Quarterly Water sump (pond) at the Site Boundary RCF3.7NO IND Quarterly Hadselville Creek at Folsom South Canal RCF10.0MO IND Quarterly Laguna Creek at McKenzie Road i
GARDEN VEGETABLES HARVESTED AT LEAST SEMI-ANNUALLY (SA),
MONTHLY THROUGHOUT THE GROWING SEASON (MTGS) 1 RLVO.5A0 IND SA-MTGS Broadleaf Vegetation Deposition Garden-(3 broadleaf samples)
RLVO.6MO IND SA-MTGS Site Boundary Vegetable Irrigation Garden (1 I
vegetable sample)
RLV18.KO CON SA-MTGS Truck Farm in the Lodi (RLVFO)
Area (3 broadleaf and 1 vegetable sample)
BEEF TISSUE RBFX.XNO IND SA Beef Tissue From Cattle Raised West Of The Site RBFX.XXO CON' SA Beef Tissue From Cattle Raised In Least Prevalent Wind Direction FROGS RFGO.6MO IND Quarterly Clay Creek at the Site Boundary
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13ble 6 (Cont.)
Page 9 of 11 RADIOIhGICAL ENVIRONMENTAL MONITORING LOCATIONS Sample Sample hollection Idenfitication Class Frequency Location Identification 1
(Former ID)
RFG1.5FO
. CON Q'uarterly Rancho Seco Reservoir-RFG2.2NO IND Quarterly Hadselville Creek at Clay Station Road RFG3.7No IND Quarterly Hadselville Creek at Folsom South Canal RFG10.0MO IND Quarterly Laguna Creek at McKenzie Sectors l
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Page 10 of 11 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS i
Sample Sample Sample Sample-Identification Class TID Mao #
Identification Class TLD Mao #
RTLO.3RO IND 1
RTL1. 7 LO IND 21 RTLO.3CO IND 2
RTL1.6JO IND 22 RTLO.3NO I!!D 3
RTL1.8KO IND 23 RTLO. 3 LO IND 4
RTL1.7HO IND 24 RTLO.3HO IND 5
RTL3. 8 LO IND 25 RTLO.4FO IND 6
RTL3.9KO IND 26 RTLO.5CO
_IND 7
RTL3.6JO IND 27 RTL6.2QO IND 8
RTL3.7HO IND 28-a RTL23.QO CON 9
RTL4.2JO IND 29 RTL18.KO CON 10 RTL7.4MO IND 30 RTLO.6KO IND 11 RTL3.7NO IND 31 RTL9.0E0 CON 12 RTL4.8PO IND 32 RTL10.NO IND 13 RTL3.8MO IND 33 RTL11.MO CON 14 RTL3.8QO IND 34 RTL10.HO CON 15 RTL1.9NO IND 35 RTL2. 7MO IND 16 RTL1.6PO IND 36 RTL8.2KO IND 17 RTL1.9QO IND 37 RTL7.8CO IND 18 RTL1.6RO IND 38 RTL1.8GO IND 19 RTL1.5BO IND 39 RTL1.5MO IND 20 RTL1.5AO IND 40 RTL1.8CO IND 41 RTL14.PO CON 51 RTL4.4GO IND 42 RTL11.MO CON 62
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Page 11 of 11 RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS Semple.
Sample Sample Sample Identification Class TLD Mao #
Identification Class TLD Mao #
RTLO.8FO IND 43 RTLO.8DO IND 63
.RTL1.8EO IND 44 RTL9.5EO IND 64 RTL1. 4 DO IND 45 RTLO. 6MO IND 65 RTL1.4DO IND 46 RTLO. 4 NO IND.
66 (eff. 7/89)
RTL3. 0C0 IND 47 RTLO". 41NO IND 67 RTL3.7DO IND 48 (eff.-7/89)
RTL3.2EO IND 49-RTLO.3PO IND 68 (eff. 7/89)
RTL3.5FO IND 50 RTL10.EO.
CON 51 RTL19.EO, CON 52
-RTL12.GO CON 53 RTL11.JO IND 54 RTL8.0PO IND 55 RTL4.6QO IND 56 RTL7.6AO IND 57 RTL6.6BO IND 58 RTL11.RO CON 59 RTL11.AO CON 60
,.