ML20205A169
| ML20205A169 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/31/1998 |
| From: | Delezenski J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Merschoff E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| NQA-99-029, NQA-99-29, NUDOCS 9903300311 | |
| Download: ML20205A169 (76) | |
Text
r-7 O suun SACRAMENTO MUMCIPAL UTILrrY DISTRICT O P. O. Box 15830. Sacramento CA 95852-1830. (916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA I
NQA 99-029
& rch 23, 1999 U. S. Nuclear Regulatory Commission
)
Attn: E. W. Merschoff, Regional Administrator Region IV f
Parkway Central Plaza Building 611 Ryan Plaza Building, Suite 400 Arlington, Texas 76011-4085 Docket No. 50-312 1
i Rancho Seco Nuclear Station License No. DPR-54 1998 RANCHO SECO ANNUAL RADIOLOGICAL ENVIRONMENTAI, OPERATING REPORT
Dear Mr. Merschoff:
Enclosed is the Rancho Seco Annual Radiological Environmental Operating Report (AREOR) for 1998. The enclosed report contains the information required by Rancho Seco Permanently Defueled Technical Specification (PDTS) D6.9.2.3,
" Annual Radiological Environmental Operating Report."
Members of your staff requiring additional information or clarification may contact
/
Mr. Steve Nicolls at 732-4850.
/
Sin I
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(@
.-' U erry Delezenski Quality Assurance / Licensing / Administration Superintendent Enclosure cc w/ Encl:
Document Control Desk, NRC, Washington D.C. 20555
. R. Dudley, NRC, Rockville onan44 f
9903300311 981231 PDR ADOCK 05000312 R
PDR t
RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Cities Road. Herald. CA 95638-9799;(209) 333-2935 i
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ANNUAL RADIDLOGICAL T'
ENVIRONMENTAL to OPERATING REPORT z
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(Rancho Seco Nuclear Station' Herald, California License Number DPR-54
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I ANNUAL RADIOLOGICAL g
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OPERATING REPORT i
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I JANUARY -- DECEMBER 1998 I
Rancho Seco Nuclear Station I
Herald, California License Nurnber DPR-54 g
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1998 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l
TABLE OF CONTENTS TAB LE O F CO NT ENTS........................................................................................
........I I
LI ST O F F I G U R E S..............................................................................................
.............. i1 LISTOFTABLES......................................................................................................
......... iii I. EXECUTIVE SU MMARY.............................................................................
..............1
- 11. LAND USE CENSUS.........
................................................................................................2 I
lit. RADIOLOGICAL IMPACT EVALUATION..................
............................................................2 PREDICTED POTENTIAL RADIOLOGICAL IMPACT................................................................... 2 FU EL CYCLE DOS E EVALUATION....................
.......................................................... 3 OBSERVED POTENTIAL RADIOLOGICAL IMPACT..................................
.......................... 3 IV, PROG RAM ANALYSIS R ESULTS
SUMMARY
........................................................................ 6 IV A. ATMOSPHERIC MONITORING..................................
..........................6 IV-B. DIRECT RADIATION MONITORING.........................
...................7 IV C. TERRESTRIAL MONITORING..............
7 j
IV D. AQUATIC LIFE MONITORING.............
.....................................................8 3
IV-E. WATER MON ITORING.................................
...................................................9 V.
R EFERENCES............
..................................................................................19 VI. APPENDICEO.................
...... 20 1998 LAND USE GNSUS RESULTS........
.........................................................A-1 SAMPLE SITE DESCRIPTIONS AN D MAPS................................................................. B-1 OUALITY CONTROL SAMPLE ANALYSIS RESULTS................................
.........C-1 a
SAMPLE COLLECTION AND ANALYSIS METHODS.....................................
...D-1 ENVIRONMENTAL MONITORING PROGRAM DESIGN...............................................E-1 1998 SAMPLE ANALYSIS RAW DATA TABLES.......
.....................................F-1 1998 MISSED SAMPLE REPORT.....
..... G-1 j
ADDENDUM TO 1997 AREOR REPORT..........._.......................
....... H 1 j
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I ii Rancho Seco Nuclear Station i
1998 AREOR i
o Ii LIST OF FIGURES I,
FIGURE TITLE PAGE FIGURE B-1 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS ON AND NEAR THE SITE-B-3 FIGURE B-2 RADIOLOGl CAL ENVIRONMENTAL SAMPLING LOCATIONS WITHIN 1 MILE FROM THE REACTOR BUILDING B-4
- 1 FIGURE B-3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS FROM 1 TO 5 MILES FROM THE REACTOR BUILDING B-5 FIGURE B-4 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS 5 TO 25 MILES FROM THE REACTOR BUILDING B-6 l
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I Rancho Seco Nuclear Station ii 1998 AREOR I
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LIST OF TABLES TABLE TITLE PAGE i
1 1998 LIQUID EFFLUENT PATHWAY POTENTIAL DOSE COMPARISON
--5 2
ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
-- 11 I
RADIOLOGICAL ENVIRONMENTAL MONITORING SITES AND MAP LOCATIONS-
- - B-7 B1 C-1 1998 lNTERLABORATORY COMPARISON PROGRAM
--- C-4 E-1 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES E 10 E-2 MAXIMUM (REQUIRED) LLD VALUES FOR ENVIRONMENTAL SAMPLES
- E-11 F-1 1998 WEEKLY AIR SAMPLE
SUMMARY
- F-2 F-2 1998 TLD
SUMMARY
(DIRECT RADIATION)
- F-4 I
F-3 1998 GARDEN VEGETABLES -
F-5 F-4 1998 SOIL AND SEDIMENT
F-5 F-5 1998 FISH -
F-8 F-6 1998 ALGAE-
-- F-8 F-7 1998 WELL WATER -
F 9 F-8 1998 RUNOFF WATER ------
F-10 F9 1998 SURFACE WATER-------
~~---------- F 1 1 F-10 1998 DRINKING WATER -------
F 13 F-11 1998 RAIN WATER-
----- F-14 I
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Rancho Seco Nuclear Station iii 1998 AREOR I
I 1998 ANNUAL RADIOLOGICAL ENVIRONMENTAL I
OPERATING REPORT l.
EXECUTIVE
SUMMARY
I This report contains results from the Radiological Environmental Monitoring Program (REMP) for the Rancho Seco Nuclear Station (RSNS) compiled for the period January 1,1998 through December 31,1998.' This program is conducted by the Radiation Protection / Chemistry Group at RSNS and is conducted in accordance with section 06.8.3.b of the RSNS Permanently Defueled I
Technical Specifications.
The results of the 1998 Radiological Environmental Monitoring Program showed that the I
operation of RSNS had no significant radiological impact on the environment.
Currently, the Plant is (1) permanently shutdown, (2) in a SAFSTOR condition, and (3) undergoing dismantlement known as incremental Decommissioning. The Post Shutdown Decommissioning Activities Report (PSDAR) describes performing incremental Decommissionir.g during SAFSTOR.
The SMUD Board of Directors has approved an incremental Decommissioning Action Plan, which I
will be evaluated on an ongoing basis to determine cost effectiveness. Fuel off-loading into dry
]
1 storage is currently scheduled to begin in 1999 to an Independent Spent Fuel Storage Installation (ISFSI). The ISFSI civil construction was completed in 1995, with concrete storage modules in place.
During the reporting period, the atmospheric, terrestrial and aquatic environs adjacent to RSNS
,I were monitored. The sample measurements showed that the levels of radioactivity in the sampled media were consistent with previous evaluations and Station operations. All positively detected results were well below the reporting levels.
Doses resulting from ambient exposure to terrestrial and atmospheric direct radiation sources were measured through the placement and retrieval of thermoluminescent dosimeters (TLD's).
Direct radiation measurements attributable to Station operations, based on control and indicator I
locatiorc, were indistinguishable above background levels.-Two TLD locations, placed in an area near the effluents discharge creek are being used to evaluate the higher than average soil activity.
This activity is a result of historic monitored liquid effluent releases during Station operation. One TLD location in this area is indicating dose higher than the indicator average. The dose does not l
exceed tegulatory limits.
I isotopic identificatior.s were consistent with known releases of radioactive material from the Station to the atmospheric and aquatic environments. As expected, algae and sediment samples obtained from the aquatic environment of the No Name, Clay, Hadselville, and Laguna Creeks I
contributed the major;ty of positive isotopic identifications. Cesium -137, Cobalt-60, and Cesium-134 were the predominant nuclides identified in the aquatic environment. Tritium activity was detected during periods of i; quid effluent releases. Nuclides of Station origin were not detected in l
the gaseous effluent exposure psthways.
l l
Rancho Seco Nuclear Station 1
1998 AREOR lI
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LAND USE CENSUS The 1998 Land Use Census was conducted in accordance with the Rancho Seco Permanently E
Defueled Technical Specification (PDTS) section D.6.8.3.b.2 and Radiological Environmental E
Monitoring Program (REMP) manua! section 4.0. The 1998 Land Use Census identified the transition to grape vineyards from pasture Usage of the areas north, west, and se h of the site.
E' Evaluation of additional samples, because of this change, is in progress. One asoitional well E:
water sample has been added to the program for eva t'.,g doses to individuals from principal
)
s pathways of exposure. This evaluation and determination are in accordance with the g'
requirements of 10CFR50, Appendix I, section IV.B.3. The land use census is performed on a 3
biennial schedule and was performed during 1998 and completed in 1999. The next land use l
census is scheduled to be conducted in 2000.
I 111.
RADIOLOGICAL IMPACT EVALUATION I
PREDICTED POTENTIAL RADIOLOGICAL IMPACT Gaseous Effluent Exposure Pathways The maximum calculated annual organ dose commitment due to gaseous releases of tritium and particulate isotopes was 0.093 mrem (as calculated using the Rancho Seco Offsite Dose Calculation Manual (ODCM)). This calculated organ dose ccmmitment was 0.62 % of the associated PDTS limit (10CFR50, Appendix l guideline).
Since no detected noble gas activity was released from RSNS during 1998, there is no calculated gamma or beta air dose calculation from the ODCM. Therefore, the calculated air doses were within the applicable PDTS limits (10CFR50, Appendix I guidelines).
Liauid Effluent Exposure Pathways During 1998,3.73 E+06 liters of waste water were released into "No Name" Creek from the two onsite Retention Basins. This volume of wastewater was dispersed into 1.53 E+10 liters of a
dilution water. The estimated error associated with determining these volumes were 5% and g
20%, respectively.
The Uquid source term resulted in a calculated annual child total body dose commitment of 0.094 mrem and a calculcied child liver dose commitment of 0.147 mrem (as calculated using the ODCM). These calculated dose commitments were 3.14 % and 147 %, respectively, of the associated PDTS limits (10CFR50, Appendix I guidelines). The dose commitments reflect the age groups that could have received the highest annual dose commitment from the liquid st rce term. This information is summarized in Table 1.
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I Rancho Seco Nuclear Station 2
1998 AREOR I
- lil, RADIOLOGICAL IMPACT EVALUATION (Continued)
FUEL CYCLE DOSE EVALUATION PDTS section D6.9.2.3 (NRC74] requires each Annual Radiological Environmental Operating Report (AREOR) to include information related to REMP manual section 5.0; Fuel Cycle Dose.
The Fuel Cycle Dose Specification limits the dose or dose commitment to any ieal member of the public to 25 mrem to the total body or any organ, except the thyroid which is limited to 75 mrem.
This specification implements requirements promulgated by the United States Environmental Protection Agency (CFRd].
Consistent with REMP manual section 5.0, no fuel cycle dose evaluation was required to be performed during 1998 since no REMP measurement exceeded the established reporting levels.
Additionally, the Station effluent dose predictions did not exceed twice the dose guidelines of I
10CFR50, Appendix I [CFRc]. The station operated within the Appendix I guidelines envelope for radioactive effluents (a condition supported by Program measurements); therefore, determination of an actual dose commitment delivered to a real member of the public was not required.
OBSERVED POTENTIAL RADIOLOGICAL IMPACT I
Gaseous Effluent Exoosure Pathways The calculated gaseous effluent dose commitment calculation of 0.093 mrem (RS98] is based on tritium activity. No particulate or gaseous isotopes of Station origin were released during 1998.
The observed dose commitment dose calculation, if completed, using the gross beta data (which I
is primarily due to naturally occurring radioisotopes) would not provide an accurate correlation.
.Therefore, no dose comparison was completed. This was also confirmed during 1998, as none of the REMP gamma isotopic analysis results for the airbome pathway indicated the presence of nuclides of Station origin.
Direct Radiation Exposure Pathway Based on thermoluminescent dosimeter (TLD) control and indicator locations measurement results obtained during 1998, the Station proper did not contribute an observable component to the recorded direct gamma radiation field. This TLD data supports the Gaseous Effluent I
Exposure Pathway conclusions and supports the conclusion that the Plant has no direct radiation effect on the environment.
TLD's placed near the effluent stream were used to evaluate the dose from this area. As expected, the dose from this area is exhibiting the normal decay. Dose levels at these locations are only slightly higher than the mean of the control and indicator locations reported.
[
Rancho Seco Nuclear Station 3
1998 AREOR W
lil.
RADIOLOGICAL IMPACT EVALUATION
)
(Continued)
OBSERVED POTENTIAL RADIOLOGICAL IMPACT
' Liauid Effluent Exoosure Pathways To evaluate the impact on the environment from the liquid effluent pathway, dose calculations J
were performed and compared with the annual dose commitment calculations reported in the E
January - December 1998 Rancho Seco Annual Radioactive Effluent Release Report [RS98].
5 The observed results presented in Table 1 were obtained using the minimum detectable activity (MDA) for Cs-137 activity reported for the fish samples from 1998 (Appendix F, Table F-5), default 5
consumption quantities for fish (ODCM), and nuclide-specific dose factors [NRC77]. The lower of 3
the two values was selected for evaluation. This MDA value is approximately twice the previous values obtained for fish samples. This calculation using a MDA value results in a "less than" g
number for the observed dose' This methodology was chosen to provide a value versus gl indicating that all fish and vegetable samples collected in 1998 resulted in less than detectable data.
I As in past reports, the observed potential dose commitments listed in Table 1 are subject to additional uncertainty, principally due to the assumption that the observed radioactivity was due to 1998 Station operations only and was not affected by radioactivity introduced into the environment prior to 1998. A major portion of the activity identified by Program measurements in 1998 is attributable to historical releases documented in previous annual reports. Additionally, the observed dose commitment calculations are based on conservative default consumption factors l<
for fish.
W The 1998 Land Use Census indicates the potential for a liquid / fish or liquid / irrigated vegetation g
pathway. This potentialis based on the possibility and not actual data supporting the use of the E
effluent streams for a source of fish or irrigation of vegetation. Conservative consumption factors for fish were used for the observed dose commitment based on this potential.
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I Il Rancho Seco Nuclear Station 4
1998 AREOR I
- lit, RADIOLOGICAL IMPACT EVALUATION (Continued)
I OBSERVED POTENTIAL RADIOLOGICAL IMPACT I
TABLE 1 1998 Liquid Effluent Pathway Potential Dose Comparison POTENTIAL DOSE COMMITMENT j
(Based on the maximally exposed group)
I PREDICTED DOSE OBSERVED DOSE PERCENT OF THE COMMITMENT (a)
COMMITMENT (b)(c) 10CFR50 APPENDIXi DOSE LIMITS (mrem)
(mrem) 0.094
< 0.337
< 11.2 %
(Child-Total Body)
(Teen-Total Body)
Total Body (3 mrem limit) 0.147
< 0.507
< 5.1 %
(Child-Bone)
(Child - Bone)
Organ (10 mrem limit)
I Notes:
(a)
Reported in the 1998 Annual Radiological Effluents Report 1
(Based on Tritium activity)
(b)
Calculated using Minimum Detectable Activity Cs-137 value for fish samples (Appendix F, Table F-5).
(c)
The observed dose commitments for doses reflect the age group that could have received the highest annual dose commitment from the liquid I
source term I
I I-Rancho Seco Nuclear Station 5
1998 AREOR
IV.
PROGRAM ANALYSIS RESULTS
SUMMARY
This section compiles all Program data with corresponding evaluations. Each of the following five subsections preserits information about each of the principal environmental exposure pathways monitored by the Program:
=> Atmospheric (Section IV-A)
=> Direct Radiation (Section IV-B)
=> Terrestrial (Section IV-C)
=o Aquatic Life (Section IV-D)
=> Water (Section IV-E)
Each of these sections contains a data evaluation subsection, which provides a summary of the data collected, j
Table 2 is a comprehensive, all-media data summary presented in a format considered lj acceptable by the US Nuclear Regulatory Commission. Information contained in Table 2 was derived from data presented in Appendix F.
IV-A. ATMOSPHERIC MONITORING DATA EVALUATION No radionuclides attributable to the operation of Rancho Seco were observed in gamma spectrometry analyses of the quarterly composites of the particulate filters. No table is 3
presented for this data since all the data was reported as being below the associated minimum E
detectable activity for the nuclides of interest.
The data indicates that there was no measurable contribution to the airborne radioactivity inventory, which could reasonably be attributable to Station operations.
The results of the gross beta analyses of the particulate samples are given in Appendix F, Table F-1.
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Rancho Seco Nuclear Station 6
1998 AREOR I
p IV-B DIRECT RADIATION MONITORING
. DATA EVALUATION A comparison review of all TLD data for the indicator and control locations during 1998 showed
'g that there was no observable direct radiation component due to Station operations (i.e., storage 3
or utilization of licensed radioactive material within the restricted area.)
Two TLD locations are being used to characterize the dose in areas next to the effluent stream.
The data from these locations indicates doses are within regulatory limits.
The summary data for 1998 direct radiation monitoring is presented in Table 2. Comprehensive data tables are given in Appendix F, Table F-2.
IV-C. ' TERRESTRIAL MONITORING DATA EVALUATION Garden Vegetation - Six routine garden vegetation samples were collected and analyzed for nuclides of interest during 1998. No gamma emitting isotopes were found in any of the I
samples analyzed. A site boundary irrigated garden has been evaluated to be a conservative method for evaluating the liquid effluent pathway. This method meets the requirement of the Land Use Census for monitoring gardens. This site boundary garden is used for the Land Use Census.
j Soil (discharge canal) -- Eight soil samples were collected and analyzed for nuclides of I
interest from the effluent discharge canal and downstream creeks during 1998. Cs-137 (8 samples,32 to 1538 pCi/kg,510 pCi/kg mean) and Co-60 (4 samples,29 to 187 pCi/kg,85 pCi/kg mean) was detected by the analyses. The remaining nuclide identifications were numerically below the required LLD-equivalent activity concentration. The presence of the 1
I identified nuclides is attributed to historical Station operations and Cs-137 fallout sources. The decay trend for these locations is as anticipated. Soil sampling at these locations is not required by the REMP (administratively controlled).
Soil (storm drain outfall) -- Thirty soil samples were collected from fifteen storm drain outfall locations during 1998. These outfalls are located along the perimeter of the Industrial Area Boundary (Restricted Area). Three (3) locations at the ISFSI were added in 1997 to obtain pre-operational data. Gamma spectrometry analysis of these samples revealed the presence of Cs-137 (16 samples,9 to 54 pCi/kg,36 pCi/kg mean). These results are within the range of the I
activity levels previously detected near Rancho Seco and are within the anticipated decay trend.
Soil sampling at these locations is not required by the REMP(administratively controlled).
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Rancho Seco Nuclear Station 7
1998 AREOR I
e Ii IV-C. TERRESTRIAL MONITORING (continued)
II DATA EVALUATION Soil (depression area)- Samples were taken in 1998 as part of the decommissioning site characterization program. The site characterization surveys are being conducted to monitor areas near the discharge canal, within District property, to provide data on activity levels from historical, permitted releases. These sample points were added to provide programmatic g
control and correlation for the data collected. Fourteen (14) soll samples at seven locations g
were collected in 1998 as part of this program. Gamma spectrometry analysis of these
)
samples indicated the presence of Cs-137 (14 samples,73 to 61770 pCl/kg,11651 pCl/kg gl mean), Co-60 (8 samples,54 to 2358 pCi/kg,662 pCi/kg mean), and Cs-134 (5 samples,48 to 3]
414 pCi/kg,180 pCl/kg mean). The results for these samples are within the anticipated decay trend indicated by the initial site characterization samples. Soil sampling at these locations is a'
not required by the REMP(administratively controlled).
g i
The summary data for 1998 terrestrial monitoring is presented in Table 2. Comprehensive data tables are given in the following Appendix F tables:
=> F-3 (Garden Vegetables)
I
=> F-4 (Soil and Sediment).
IV-D. AQUATIC LIFE MONITORING DATA EVALUATION I
Fish - Two fish samples were collected during 1998 and analyzed for nuclides of interest by gamma spectrometry. No gamma emitting isotopes were found in any of the samples analyzed.
Sediment - 17 samples of sediment were collected from the discharge canal and the Clay /
Hadselville/ Laguna Creeks during 1998. Gamma spectrometry analysis of these samples indicated the presence of Cs-137 (17 samples,19 to 329 pCi/kg,169 pCi/kg mean) and Co-60 (6 samples,8 to 16 pCi/kg,13 pCi/kg mean).
5 The presence of nuclides of interest in sediments is attributed to historical permitted liquid 3,
effluent discharges with some contribution from fallout sources.
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Rancho Seco Nuclear Station 8
1998 AREOR I
IV-E. WATER MONITORING I
DATA EVALUATION Algae - Eight samples of algae were collected from the discharge canal and the Clay /
HadseMile/ Laguna creeks during 1998. Cs-137 (6 samples,288 to 1260 pCi/kg,634 pCl/kg mean) was detected by gamma spectrometry analysis.
The identification of nuclides of interest in the algae samples is attributed to permitted historical liquid effluent discharges. Additional contributions would be expected to have occurred from
- sediment activity and fallout sources.
Well Water - 26 well water samples were collected at indicator and control locations around the site during 1998. Tritium analysis of the samples indicated results less than LLD. Gamma spectrometry of the sample collected on September 15,1998 at location RWWO.8LO ldentified Co-60 at 30.6 +- 14 pCi/L. A recount of the sample verified the identification at 24.7 +- 5.7 pCi/L. All other isotopes were less than MDA. Two additional samples were collected on November 18,1998. One sample was sent to Thermo NUtech for analysis and the other sample was analyzed using the Rancho Seco gamma spectrometry system. Both samples indicated values less than MDA for all isotopes of interest. Routine samples collected for the I
fourth quarter indicated no gamma emitting isotopes. Based on these analysis results, the sample for RWWO.8LO (dated 9/15/98) which identified the Co-60 activity will be invalidated.
Gross beta activity levels for all samples were within regulatory limits. An additional location I
was administratively added in 1998 to collect pre-operational data for the observed transition to commercial grape vineyards around the site, I
Runoff Water - No nuclides of interest were identified by gamma spectrometry or tritium analysis of the 31 samples collected in 1998.
I Surface Water - Five locations (3 indicator and 2 control) were included in the surface water monitoring Program. Composite samplers located at the Plant intake (Folsom South Canal) and effluent discharge provide monthly composite samples. During 1998,65 samples were collected and analyzed for nuclides of interest. No gamma-omitting nuclides were detected in I
any of the samples analyzed, Tritium activity was detected in the samples collected during the fourth quarter of 1998 during planned liquid effluent releases. The tritium activity was measured at 358 - 9780 pCi/ L, with an average concentration of 2610 pCl/L.' Tritium activity was detected in the composite and grab samples.
Drinking Water - Water supplied from the site well is distributed in a potable water supply I
system for Station personnel consumption and use. On a monthly frequency, a sample of this water was collected and analyzed for nuclides of interest. A sample from the Rancho Seco Reservoir Well is collected as a control location. No gamma emitting isotopes or tritium was I~
found present in the 24 samples collected in 1998. Gross Beta analysis showed activity within regulatory limits.
^
Rainwater - On a seasonal basis, rainwater is collected at an off site location. The sample is analyzed for gamma emitting isotopes and tritium. During 1998,16 samples were collected at this location. No isotopes of interest were detected in these samples. Rainwater samples are not required to be collected by the REMP (administratively controlled).
Rancho Seco Nuclear Station 9
1998 AREOR W
IV-E. WATER MONTrORING DATA EVALUATION (continued)
The summary data for the water monitoring program is shown in Table 2. Comprehensive data tables are given in the following Appendix F Tables:
=> F-4 Soil and Sediment
=> F-6 Algae
=o F-7 Well Water
=> F-8 Runoff Water
=> F-9 Surface Water
=o F-10 Drinking Water
=> F-11 Rain Water I
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I Rancho Seco Nuclear Station 10 1998 AREOR g
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TABLE 2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
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I V.
REFERENCES CFRa Code of Federal Regulations,1996, " National Primary Drinking Water Regulations," Title 40, Part 141.
CFRb Code of Federal Regulations,1997, " Standards for Protection Against Radiation," Title 10, Part 20.
CFRc Code of Federal Regulations,1997, " Domestic Licensing of Production and Utilization Facilities," Title 10, Part 50.
I CFRd Code of Federal Regulations,1996, " Environmental Radiation Protection Standards for Nuclear Power Operations," Title 40, Part 150.
I NRC74 United States Nuclear Regulatory Commission,1974, " Permanently Defueled Technical Specifications for the Rancho Seco Nuclear Station,"
Appendix A to Facility License No. DPR-54 (as amended).
NRC77 United States Nuclear Regulatory Commission,1977, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the I
Purpose of Evaluating Compliance with 10CFR50, Appendix I," Regulatory Guide 1.109, Revision 1.
NRC79a United States Nuclear Regulatory Commission,1979, "An Acceptable Radiological Environmental Monitoring Program," Branch Technical Position, Revision 1.
NRC79b United States Nuclear Regulatory Commission,1979, " Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment," Regulatory Guide 4.15, Revision 1.
NRC92 United States Nuclear Regulatory Commission, " Air Sampling in the Workplace", Regulatory Guide 8.25, June 1992 NUREG79 United States Nuclear Regulatory Commission,1979, " Radiological Effluent Technical Specifications for PWRs," NUREG 0472, Revision 2.
NUREG80a United States Nuclear Regulatory Commission,1980, " Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40CFR190)," NUREG-0543.
RS98 Rancho Seco Nuclear Station,1998, " Annual Radioactive Effluent Release Report, January -December 1998," Sacramento Municipal Utility District
]
report.
u Rancho Seco Nuclear Station 19 1998 AREOR l
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r-.w I
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VI. APPENDICES Il I
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I Rancho Seco Nuclear Station 20 1998AREOR I
APPENDIX A 1998 LAND USE CENSUS RESULTS In compliance with the Rancho Seco Permanently Defueled Technical Specifications, section D6.8.3.b.2 and the REMP Manual, section 4.0, " Land Use Census", a land use census was completed on March 14,1999. The method of conducting the primary survey was to use an aerial survey that was conducted Juring June 1998. Evaluating the aerial photographs continues to provide an accurate method of determining locations and distances of the nearest residences.
When the review of the survey photos indicated that an actual on-scene survey was needed to verify the use of identified structures; a visual observation was made. The aerial photos also provided a method to identify any changes in the agricultural, commercial, ot industrial use of the
- land surrounding the site. The use of conservative dose factors for the purpose of projected dose calculations still requires that we evaluate the use of the area surrounding the site. The information that is presented is to verify this assumption and ve:!idate the process.
The land use census covered an area bounded by each of the sixteen meteorological sectors out to a two-mile radius from the Reactor Building.
The 1998 Land Use Census did not Identify any changes in the use of the unrestricted areas that would require modifications in the Radiological Environmental Monitoring Program for evaluating doses to individuals from principal pathways of exposure. This evaluation and determination are in accordance with the requirements of 10CFR50, Appendix 1, section IV.B.3.
The Land Use Census is completed on a biennial schedule. Aerial surveys will be conducted during 2000 and the Galt irrigation report covering 1990 and 2000 will be rcquested during the last quarter of 2000. This information will be used to complete the 2000 census scheduled to be completed in 2001.
Rancho Seco Nuclear Station A-1 1998 AREOR
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A.
RESIDENT EXPOSURE PATHWAY
SUMMARY
Inhalation, Ground Plans and Water Consumption The 1998 census determined that seven of the 16 radial sectors have residences that are within E
the 2-mile (3219 meters) Land Use Census radius. The closest residence in each of the seven g
sectors is identified below:
Sector Distance Ranking (meters)
(Nearest to Farthest)
A
>3219 NA D
>3219 NA C
1267 3
D 1038 1
E
>3219 NA F
>3219 NA G
2315 6
H
>3219 NA J
>3219 NA K
2267 5
L 1133 2
M 1943 4
N 3181 7
P
>3219 NA O
>3219 NA R
>3219 NA j
it is expected that all seven residences use well water for consumption and other domestic purposes.
Ei I
Rancho Seco Nudear Station A-2 1998 AREOR I
B.
DEPOSITION EXPOSURE PATHWAY
SUMMARY
Beef Consumption Based on conservative dose calculation parameters in use, the following is a summary for the 1998 land use census of the potential deposition exposure pathways at the locations listed below:
Sector Distance Consumption Pathway Comment (meters)
A 433 Beef Unrestricted Area Boundary B
430 Beef Unrestricted Area Boundary C
430 Beef Ursrestricted Area Boundary D
448 Beef Unrestricted Area Boundary E
472 Beef Unrestricted Area Boundary F
667 Beef Unrestricted Area Boundary G
235 Beef Unrestricted Area Boundary H
198 Beef Unrestricted Area Boundary J
195 Beef Unrestricted Area Boundary K
195 Beef Unrestricted Area Boundary L
286 Beef Unrestricted Area Boundary I
M 404 Beef Unrestricted Area Boundary N
509
- Beef Unrestricted Area Boundary P
442 Beef Unrestricted Area Boundary Q
SOG Beef Unrestricted Area Boundary R
448 Beef Unrestricted Area Boundary Because of the extremely small amount of radioactive gaseous effluent released from the site, Deposition Exposure Pathway changes were considered inconsequential. The changes indicated in the beef consumption table does not necessitate modification of ODCM or REMP practices.
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L 4
Rancho Seco Nuclear Station A-3 1998 AREOR 6
e
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C.
IRRIGATED CROP EXPOSURE PATHWAY
SUMMARY
Laguna Creek l
Based on information stated in the Galt irrigation District's 1998 Crop Report; 2657.471 acre-feet of Laguna Creek water was diverted for irrigation purposes during the 1998 crop production season. A total land crea of 1086 acres was subject to irrigation as follows:
Acre Feet Acreage Crop Water irrigated 199.444 50 Sudan 136.666 90 Clover 344.399 156 Sudan 101.547 20 Clover 244.394 130 Pasture 243.313 50 Clover 286.827 135 Sudan-73.128 50 Clover 161.598 120 Corn, alfalfa 195.856 60 Corn 55.014 30 Alfalfa 196.594 100 Sudan in addition to the above, SMUD has contracted with Rossini Farming Co., the owners of the vineyards adjacent to Rancho Seco Station, to supply irrigation water from Clay Creek on an as needed basis. No water usage was reported for 1998.
Based on direct observation cattle consume water from the Clay, Hadselville, and Laguna Creeks.
i Rancho Seco Nuclear Station A-4 1998 AREOR l
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[I lI l
D. -
OTHER EXPOSURE PATHWAYS The 1998 Land Use Census confirmed previous knowledge that the Clay / Laguna Creeks are utilized by the general public for aquatic life consumption purposes. Past census evaluations have been unsuccessful in deterr.ning the usage / occupancy factors for their consumption, e
1 Therefore, insufficient data existed to justify ODCM usage factor modification.
1 E.
REMP EVALUATION I
An objective of the 1998 Land Use Census was to compare census and current REMP Manual I
locations to ensure consistency exists between monitoring activities and actual land utilization.
The following discussion is a summary of the comparison evaluation for each of the four t
exposure pathways.
I Resident Exoosure Pathway I
The inhalation and ground plane exposure pathways, the principal components of the Resident Exposure Pathway, are monitored directly and indirectly by thermoluminesence dosimetry (TLD), air, and soil sampling and analysis. Well water was monitored at six locations.
Since the existing REMP was more conservative with respect to Resident Exposure Pathway monitoring, no changes were required.
Deposition Exposure Pathway The Deposition Exposure Pathway (Section B) is monitored directly within the Station Site Boundary through garden vegetation sampling and analysis. The potential for a deposition pathway has been evaluated by the ODCM and REMP programs and found to have little potential for the current plant status. Since the current REMP was representative and conservative with respect to Deposition Exposure Pathway monitoring, no. changes were required.
Irriaated Croo Exoosure Pathway-The REMP was effective in monitoring the identified irrigated crop exposure pathways. This I
conclusion was because the REMP included irrigated vegetation sampling. The commercial grape vineyards will be evaluated and sample program will be established as the vineyards reach maturity.
REMP surface water surveillance activities monitor irrigation water radiological quality. Current ODCM calculations are conservative since dilution effects are not included when predicting potential dose delivered through downstream pathways.
1 Rancho Seco Nuclear Station A-5 1998 AREOR F
L_.
E.
REMP EVALUATION (continued)
' Other Exposure Pathways Existing aquatic !!fe, surface water and sediment sampling and analysis practices are effective in monitoring potential observable effects associated with recreational activities occurring at the Clay Creek, Hadselville Creek, Laguna Creek, Folsom South Canal and Rancho Seco Lake.
With respect to availability and quantity of food sources, the other identified consumption activities were considered inconsequential for pathway monitoring purposes.
No REMP changes were required to monitor other exposure pathways.
F.
ODCM EVALUATION Based on 1998 Land Use Census findings, the following potential exposure pathways exist at j
the indicated locations:
GASEOUS EFFLUENT Exoosure Pathway Location Comment Inhalation 1128 m ENE Resident location having the highest dispersion parameter El um i
Ground Plane 1128 m ENE Resident location having the highest deposition parameter I
LIQUID EFFLUENT Exoosure Pathway Location Comment Freshwater Fish Clay Creek Recreation beyond the Site Boundary Swimming Clay Creek Recreation beyond the Site Boundary Shoreline Deposits Clay Creek Recreation beyond the Site Boundary irrigated vegetation Clay Creek Potential for residences beyond the site boundary irrigated forage Clay Creek Cattle grazing b.eyond the Site Boundary Drinking Water Clay Creek Cattle drinking water beyond the Site l
Boundary 5
Rancho Seco Nuclear Station A-6 1998 AREOR
I F.
ODCM EVALUATION (continued)
The GASEOUS EFFLUENT locations for inhalation and ground plane used by the ODCM are conservative since they are located at the Station Site Boundary.
Specifying the Laguna Creek location also provides additional conservatism since the beneficial effects of downstream dilution are not considered when specifying effluent release restrictions.
As required by the 1998 Land Use Census t..e above inforfcation for exposure pathways and -
locations was submitted for incorporation in the ODCM for use during 1999.
i I
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Rancho 3eco Nuclear Station A-7 1998 AREOR I
l APPENDIX B SAMPLE SITE DESCRIPTIONS AND MAPS This appendix provides descriptive information about the sampling locations and maps of all the locations for the Radiological Environmental Monitoring Program sites.
Table B-1 provides information on sample type, identification codes, and map location references.
The sample identification code is an alphanumeric string beginning with the prefix 'R" (for Rancho Seco Nuclear Station) followed by two letters to identify the sample media:
AS Air SL Soil RW Runoff Water FS Fish SW Surface Water LV Garden Vegetable
-I DW Drinking Water AG Algae WW Well Water TL Direct Gamma Radiation (TLD)
MS Mud and Silt RN Rainwater The numeric designations, which follow the letter designations, indicate the straight-line distance (in miles) from the center of the Reactor Building to the monitoring site.
The next letter designates the sector in which the monitoring location is located. The letters A through R are used for sector designators. The letters I and~O are not used to prevent confusion with the numbers one and zero in the ID codes.
I Sector Letter Degrees Azimuth Compass Point A
348.75 to 11.25 N
B 11.25 to 33.75 NNE C
33.75 to 56.25 NE D
56.25 to 78.75 ENE E
78.75 to 101.25 E
F 101.25 to 123.75 ESE G
123.75 to 146.25 SE H
146.25 to 168.75 SSE J
168.75 to 191.25 S
K 191.25 to 213.75 SSW L
213.75 to 236.25 SW M
236.25 to 258.75 WSW N
258.75 to 281.25 W
P 281.25 to 303.75 WNW O
303.75 to 326.25 NW R
326.25 to 348.75 NNW l
l Rancho Seco Nuclear Station B-1 1998 AREOR
SAMPLE SITE DESCRIPTIONS AND MAPS (continued)
The final letter designation indicates if the location is part of the operational REMP program ("O")
or post-operational REMP program ("P").
Table B-1 Lists each location referencing the sample type and the location ID code to the map site number on one of the four Radiological Environmental Monitoring Site Maps included in this Appendix.
Figure B-1 Site Location Map: Shows the locations of the sample locations on and/or near the Site (including Storm Drain locations).
Figure B-2 1 Mile Radius map: Sampling locations within one mile of the Reactor Building centerline are shown on this map.
Figure B-3 5 Mile Radius map: Sampling locations between one and five miles from the Reactor Building centerline are shown on this map.
Figure B-4 25 Mile Radius mao Sampling locations between five to 25 miles from the Reactor Building centerline are shown on this map.
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Rancho Seco Nuclear Station B-2 1998 AREOR
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Rancho Seco Nuclear Station B-6 1998 AREOR I
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APPENDIX C QUALITY CONTROL SAMPLE ANALYSIS RESULTS QUALITY ASSURANCE AND CONTROL implementation of the Radiological Environmental Monitoring Program (REMP) consists of a number of discrete steps including:
= Sample collection,
== Packaging,
=o Shipment and receipt,
=o Measurements of radioactivity,
=o Data evaluation, and
=* Reporting.
I These program elements are performed according to approved, written procedures to assure the validity of REMP results. This section discusses the internal quality control measurements made by the analysis laboratory, Thermo NUtech, and the results of their participation in the intenaboratory Comparison Program conducted by the United States Environmental Protection I
Agency (EPA). The Interlaboratory Comparison Program and the analysis laboratories Quality Assurance Programs provide information on the validity (accuracy and precision) of the REMP implementation steps listed above.
Because REMP measurement validity is important for evaluating protection of the health and 1l safety of the public, RSNS has established an Environmental Quality Assurance Program (EOAP) for radiological environmental measurements. The Environmental QA Program implements the J
L guidance provided in Regulatory Guide 4.15, (NRC79a).
INTERLABORATORY COMPARISON PROGRAM Thermo NUtech participates in the interlaboratory Comparison Program (ICP). The ICP is a radiological analysis quality control program sponsored by EPA's Environmental Monitoring Systems Laboratory in Las Vegas. Participation in the ICP is a requirement of the Permanently Defueled Technical Specification (section D6.8.3.b.3). It provides for an independent check of the proficiency of the laboratory, it also provides information on the precision and accuracy of
[
measurements of radioactive material in REMP samples by Thermo NUtech, and other laboratories. The extent of Thermo NUtech participation in this program includes all of the environmental radioactivity determinations that are offered by the EPA and related to the analyses
{
required by the REMP manual.
Rancho Seco Nuclear Station C-1 1998 AREOR u
~
I I
INTERLABORATORY COMPARISON PROGRAM g
(continued)
E The EPA Intercomparison Program consists of a variety of sample media spiked with known quantities of specific radioactive materials at levels normally found in environmental samples.
These levels are generally quite low. Most samples require long counting times to determine if any activity is present, and the results may have large deviations from the mean. When the samples are distributed by the EPA, there is an implied precision requirement given in terms of the analysis requested to be performed. After all the labs provide the results of their analyses a
(three are required from each lab), the EPA publishes a statistical summary of all the results by all l
laboratories. This report includes the EPA acceptance control limits, the mean of all laboratories and the standard deviation of the results by all labs, among other statistics.
If the resu'ts of a determination by Thermo NUtech in the ICP is outside the specified controllimits or do not pass the outliers test, Thermo NUtech must investigate and, if a problem is identified, take corrective action to prevent problem recurrence.
During 1998, Thermo NUtech analyzed 11 ICP samples related to the current REMP program.
. Thermo NUtech did not submit data for the ICP. sample for Tritium in Water (August 8,1998).
l; Results were obtained (19099.5 pCi/ L), but were not submitted to the EPA by the required due m'
date due to a scheduling error. All other sample results reported by Thermo NUtech were within the controllimits.
The Thermo NUtech measurement results are presented in Table C-1 along with the acceptable i
EPA values for each test.
INTRALABORATORY QUALITY ASSURANCE PROGRAM I'
Thermo NUtech by contract also operate an intralaboratory Comparison Program (Quality Assurance Program) to maintain an acceptable quality level on a routine basis.
I As part of their Quality Assurance Program, the laboratory performs background counts, an analysis of a spiked samples, and duplicate sample counts for every ten Rancho Seco REMP samples analyzed. These quality control procedures are performed for all analyses except l
gamma spectrometry, for which weekly energy and efficiency checks are performed. The spiked and duplicate samples are prepared by personnel not directly involved with the analysis. Spiked samples, as well as the radioactive sources used for the gamma spectrometer checks, are l
traceable to the National Institute for Standards and Technology (NIST).
In all cases during 1998, the duplicate analyses and the tritium spikes were acceptable.
I, i
Rancho Seco Nuclear Station C-2 1998 AREOR l
1 I!
a
L
.I 1
l RANCHO SECO AUDIT AND SURVEILLANCE RESULTS l
The Rancho Seco Quality Program requires periodic audits of REMP activities, including Thermo NUtech. Contract laboratory performance is evaluated by the Rancho Seco QA Department.
I CONCLUSIONS The intralaboratory and Interlaboratory results provided by the EPA and Thermo-NUtech indicate that Thermo-NUtech performance was acceptable.
DIRECT RADIATION (TLD) COMPARISON PROGRAM lI The TLD vendor, ICN Dosimetry Services, participated in a quarterly blind spike comparison-testing program. A review of ICN's results of the participation in this testing program indicates that ICN has satisfactorily completed all of the required tests for the types of environmental radiation monitored at RSNS.
This comparison program satisfies the requirement of the REMP manual section 6.0.
1I 1I 1
'g I
I l
Rancho Seco Nuclear Station C-3 1998 AREOR
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I-I APPENDIX D SAMPLE COLLECTION AND ANALYSIS METHODS I
For each of the sample media collected, the method of collection is documented in Rancho Seco Nuclear Station procedures. Detailed analysis methods are documented in procedures controlled by the contract laboratory, Thermo NUtech. A brief description of these collection and analysis methods is included in this Appendix.
Sample Media Collection / Analysis Method AIR An air samplor continuously moves air through a filter paper designed to capture particulates by filter paper impaction. The air samplers are I
equippd with a flow totalizer, which measures the volume of air that has passed through the filter paper.
I The filter paper is exchanged weekly. At least one day is allowed to elapse between sample collection and counting to reduce the interference of naturally occurring radon and thorium daughters on the sample analysis.
The filter paper is assayed for gross beta radioactivity by placing the filter I
on a stainless steel planchet and counted with an intemal gas flow proportional counter.
The individual particulate filter papers are saved over a calendar quarter and the composite collection is assayed for gamma isotopic radioactivity by gamma spectroscopy.
RADIATION Thermoluminescent dosimeters (TLD's) are located within a ten (10) mile I
radius of the site. TLD's within a five (5) mile radius are conside,ed indicator TLD's. Two (2) TLD's, each containing three CaSO4 Dy phosphors, are placed at each monitoring location to assure adequate data 3
recavery and to improve measurement statistics. The TLD field exposure 3
cycle is approximately ninety (90) days. At the end of the field exposure cycle, the TLD's are exchanged and returned to a contract laboratory for I
processing. The exposure reported by the laboratory is the average of six values, corrected for non-field exposure cycle contributions.
I I
I Rancho Seco Nuclear Station D-1 1998 AREOR I
L
I I
Sample Media Collection / Analysis Method SOIL &
S DilKENT Samples of sediment and soil are collected from the top three inches of the sampled material. Sediment samples are obtained approximately two feet E
from the shoreline. Each sample is assayed directly for gamma isotopic E
radioactivity by gamma spectroscopy.
l GARDEN PRODUCE Samples of vegetables are collected semi-annually from a garden, which is maintained at the Station Site Boundary. Controllocation samples are collected from a local commercial vendor. The vegetables are assayed directly for gamma isotopic radioactivity by gamma spectroscopy.
FISH Fish are collected semi-annually from the Clay Creok system. The dissected (edible) portion of each sample is assayed directly for gamma isotopic radioactivity by gamma spectroscopy.
ALGAE Samples of algae in the Clay Creek system are collected semi-annually and assayed directly for gamma isotopic radioactivity by gamma spectroscopy.
WATER 1 gallon grab samples of water from locations in the liquid effluent pathway and groundwater are collected as follows:
Surface water and Drinking water are collected monthly Runoff water is collected biweekly 3
Well water is collected quarterly.
E At two locations, samples are obtained to provide a monthly composite sample. All samples are assayed for tritium by liquid scintillation counting and fer gamms isotopic radioactivity by gamma spectroscopy. Drinking and Well watu samples are analyzed for Gross Beta activity.
WATER Samples of rainwater are collected on a seasonal basis. All samples are assayed for tritium by liquid scintillation and for gamma isotopic l
radioactivity by gamma spectroscopy.
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I dancho Seco Nuclear Station D-2 1998 AREOR I
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APPENDIX E ENVIRONMENTAL MONITORING PROGRAM DESIGN PROGRAM BASIS The Sacramento Municipal Utility District conducts a continuous Radiological Environmental Monitoring Program (REMP) at the Rancho Seco Nuclear Station to assess the impact of Station operation on the surrounding environment. The current Post-Operation REMP is a continuation of a similar program initiated prior to and during operation of the Station. Samples of the surrounding environment are collected on a routine banis and analyzed to determine the amount of radiation and radioactive materials present in the expcsere pathways.
During 1998 the program was directed and executed by the Radiation Protection / Chemistry Superintendent. Sample collection is performed by the Technical Staff and the Chem / Rad Decommissioning Technicians. Data review and Program ma!ntenance ane performed by the I
Radiological Health Supervisor. The Program is operated with primary accountability and cognizance of the Manager, Plant Closure and Decommissioning.
I The Program is designed consistent with Title 10, Code of Federal Reaulations. Part 50, Appendix 1 - Section IV, B.2, B.3 and C, and Appendix A, " General Design Criteria for Nuclear Power Plants," Criterion 64. The program also complies with Title 10, Code of Federal Reaulations. Part I
20, " Standards for Protection Against Radiation," Section 1302. These federal requirements are cited in the Rancho Seco Permeently Defueled Technical Specifications and the REMP manual.
REMP requirements are implemented through the review, approval and routine use of several documents, namely the REMP Manual, Offsite Doce Calculation Manual, Surveillance Procedures I
and Health Physics implementing Procedures.
The programmatic elements of the REMP are based on "gulatory requirements and associated I
guidelines. The objectives of the Program are to:
1.
Provide the technological basis and the instruction for monitoring the environs for I
radioactivity sources. The radioactive sources, which contribute to detectable radioactivity in the local environs, are comprised of:
= naturally occurring background,
= releases during normal operations, w world-wide weapons testing, and
= major global nuclear accidents I
I Rancho Seco Nuclear Station E-1 1998 AREOR lI
I I
PROGRAM BASIS (Continued) 2.
Provide the means to verify the effectiveness of the Rancho Seco Nuclear Station Radiological Effluents Control Program.
3.
Meet the minimum detactable limits for radioisotopes in environmental samples.
4.
Provide quantitative measurements in the gaseous, liquid and direct radiation exposure pathways for radionuclides.
5.
Provide indications of the lergest potential radiation exposure for individuals as a result of radionuclides in the principle exposure pathways.
The Program is developed and conducted using recognized standards end practices NRC79a, NRC79b, NUREG79, and NUREG80a.
REMP CHANGES The Permanently Defueled Technical Specifications administrative requirements for the REMP program were not revised during 1998. The REMP manual was not revised during 1998 EXPOSURE PATHWAYS The fundamental parameters, which have been defined prior to monitoring the environs, are:
1.
Identification of,the effluent release pathways 2.
Identification of the human exposure pathways 3.
Identification of the land use parameters by the population within a two-mile radius of the plant site.
Each of these three parameters is discussed below.
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I Rancho Seco Nuclear Station E-2 1998 AREOR I
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EXPOSURE PATHWAYS Effluent Release Pathways There are three principal pathways, which may result in human exposure to radiation and radioactive material originating from Station operation:
1
- 1. Gaseous effluents I
I
- 2. Liquid eftruents and l
5
- 3. Direct radiation from these effluents and onsite sources.
Gaseous Effluents Gaseous ventilation and process effluents are released, through particulate filtration units to the
- 3 environment from the Reactor Building, Auxiliary Building, and Auxiliary Building Grade Level Vent
- E stacks.
in the gaseous pathway, airborne radioactive materials can be inhaled or ingested by humans.
I Animals can inhale or ingest radioactive material present in the atmosphere, which are retained in animal food products (meat or milk). Radioactive materials, which are carried by air currents, can also be deposited on vegetation or water sources, which are in turn directly consumed by humans
- l or animals.
Liauid Effluents in the liquid exposure pathway, radioactive materials in surface waters can be ingested by E
humans directly or indirectly through the consumption of aquatic foods such as fish and shellfish.
T Humans can consume vegetation, which is irrigated with Clay Creek water, which may contain radioactive material. Another exposure pathwayimm liquid effluents results from the
- E consumption of animal products such as meat and milk from animals which have fed upon
- E irrigated vegetation and/ or consumed Clay Creek water.
Direct Radiation
!m' In the direct radiation pathway, potential radiation exposure may occur from radioactive material j
storage vessels, which are contained within the site boundary such as the Borated Water Storage Tank. People can potentially be exposed to direct radiation from gaseous effluents or from ground deposition of particulates deposited on the ground from gaseous or liquid effluents. When l
the fuel off-load is completed, the ISFSI will become part of the direct radiation pathway.
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!I Rancho Seco Nuclear Station E-3 1998 AREOR
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I I
LAND USE CENSUS On a biennial basis, a land use census is conducted within a two-mile radius to identify any changes in the human exposure pathways. The Land Use Census is used to determine the changes needed for REMP monitoring activities. The results of the land use census conducted during 1998 are presented in Appendix A of this Report. The next scheduled land use census will be condu# % o000 and reported in the 2000 AREOR. From data obtained from the Land Use Census,f athways are analyzed through a systematic process which identifies a sample rnediur
. tat is found to potuntially contribute to an individual's radiation exposure.
Usage-u-
lulation factors (NRC77) are then specif'ed which represent the magnitude of -
cansfer through the food chain to a receptor. The analysis of the effluent and radioat w
exposu.,,
, o enables monitoririg sites to be identified as " indicator" (for sites at which the q
potential v..ds of Station effluents would be read;ly detected) or " control" (for those sites which
)
are not expected to be influenced by Station operation). The analysis results of samples obtained at indicator and control sites are routinely compared to ;dentify potential axposures above background levels.
MONITORING LOCATION SELECTION The REMP maintains the monitoring sites required by the REMP manual, Table 6. This program is supplemented with additional samples to compensate for changes in the radiological E
environment surrounding Rancho Seco. Some of the monitoring sites were also selected by the g
United States Nuclear Regulatory Commission and the Califomia Department of Health Services as part of their monitoring programs. Indicator sites are placed in areas, which would be most a
sensitive to the effects of Station effluents such as downwind, or downstream areas near the g
Station. If radioactive material is detected above background at any of these indicator sites, observed potential exposure and dose to humans can be estimated to verify the effectiveness of the Offsite Dose Calculation Manual in predicting potential exposures or doses. It is important to
]
note that the detection of radioactive rnaterial in indicator samples does not necessarily mean that its presence can be attributed to Rancho Seco operations. Moreover, especially with liquid effluent pathway samples, the detection of radioactive material is difficult to interpret since it is j
unknown when the material was deposited. In many instances, the observed radioactive material
{
could correctly be ascribed to historical (pre-1998) depositions.
l Control locations provide data that should not be influenced by the operation of Rancho Seco.
These locations are selected based upon distance from the Station in the upwind or upstream j
direction of the effluent release pathways. Samples obtained from control locations should, upon E'
analysis, reveal information about the presence and distribution of naturally occurring and man-3 made radioactive materials. Data from these locations are used to aid in the discrimination j
between the effects of Rancho Seco releases and other natural phenomena or accidental releases, which may result in human exposure.
i Rancho Seco Nuclear Station E-4 1998 AREOR i
I,
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. l.
I MONITORING LOCATION SELECTION l
(continued)
Gaseous effluent indicator monitoring sites are generally placed in areas, which receive prevailing l
winds crossing the Rancho Seco site. Liquid radioactive effluents are discharged in batches from two onsite Retention Basins into "No Name" Creel. exated southwest of the Station. Dilution water, obtained from the Folsom South Canal, is discharged into "No Name' Creek to give reasonable assurance of compliance with the 10CFR50, Appendix I dose guidelines. "No Name" Creek flows southerly into the Clay Creek. Without this dilution water flow, the Clay Creek would be in a dry state for most of the year.
Beyond the Site Boundary at a point north of Highway 104, the Clay Creek empties into the Hadselville Creek. Hadselville Creek then empties into the Laguna Creek at a point west of North
'g Clay Station Road near the Folsom South Canal. Finally, Laguna Creek flows into the Cosumnes E
River at a point located approximately 20 straight-line miles west of llancho Seco. Since this stream system is the only routine release pathway for liquid radioactive and non-radioactive
.g effluents from the Station, the liquid exposure pathway indicator sites are located along these l
creeks and nearbyland.
g The direct radiation pathway is monitored principally through a network of passive devices
- 5 (thermoluminescent dosimeters - TLD's) at monitoring sites distributed in sectors centcred on the Station. The TLD's are located primarily at the site, residential, and recreational areas around the Rancho Seco location. This design provides the capability to easily detect Station-induced direct radiation contributions to the observed terrestrial and cosmic direct radiation background.
Some TLD's have been sited in special locations to record direct radiation resulting from known
.I depositions of radioactive material and to provide pre-operational data for the Interim Spent Fuel Storage Installation (ISFSI).
- E Appendix B contains a detailed description and illustration of the REMP sample and monitoring
.E locations.
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lI Rancho Seco Nuclear Station E-5 1998 AREOR il
I SAMPLE MEDIA Samples are collected from predetermined monitoring sites at a specified frequency. The sample media chosen is a function of the type of monitoring desired and coincides with one of the following exposure pathways:
o Atmospheric o
Direct radiation o
Terrestrial o
Aquatic life o
Water Atmospheric monitoring is accomplished by filtering a volume of air using a mechanical air pump to collect particulates with a particulate filter paper. Four air sampler locations are used to collect weekly air samples. Two locations (Meteorological Tower and Rancho Seco Reservoir) are control locations and the remaining two locations are indicator locations on the plant site.
Direct radiation monitoring is achieved by placing TLD's at aboveground sites. TLD's respond to, and record the amount of, gamma radiation exposure. The source of this gamma radiation 3
exposure is varied and includes potential Stanon effluents, naturally occurring terrestrial, and 3
cosmogonic radionuclides. The TLD's are also influenced by seasonal and global (fallout) radiation sources. Almost all the exposure recorded by a TLD could be traced to terrestrial radionuclides.
There are 35 sites, which are monitored by thermoluminesence dosimetry within a 10-mile radius M the Station. The TLD's are placed at the Station Industrial Area Boundary, near the property WJndary, locations of interest such as nearby residences, and at control locations located beyond five miles of the Station.
Terrestrial monitoring is accomplished by obtaining samples of sediment, soil, and garden vegetation to measure the quantity of radioactive material deposited from gaseous and liquid effluents. There are five mud and silt,27 soil, and 2 garden vegetation locations.
Aquatic monitoring includes the sampling of fish and algae. Algae is an excellent concentrator of radioactivity contained in water and is sampled to provide an early indication of increased liquid E
radioactive material concentration. There are four fish and five algae sample locations.
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I Rancho Seco Nuclear Station E-6 1998 AREOR I!
E
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l SAMPLE MEDIA (continued)
Water monitoring includes samples of surface, runoff, drinking, and well sources from locations in the liquid effluent pathway and from area wells. The six surface water sampling locations monitor site supply water (Folsom South Canal), runoff water and water discharged from the Station. Drinking water is sampled from six groundwater wells and two drinking water taps. A lE new Drinking Water location was added (1997) to sample a residence located near the Clay
!E Creek system. This location was added to reflect the change is agricultural use of the 1
surrounding area. Rainwater 's also collected at one location on a seasonal basis.
SAMPLE ANALYSIS & DATA HANDLING The laboratory, which provides radio-analytical services for the Program, is Thermo NUtech located in Richmond, California. Sample analysis results submitted by Thermo NUtech are
- a reviewed for accuracy and completeness and then entered into a computerized database for
- g evaluation and trending.
Data comparisons are made between individual control and indicator sample sites to isolate potential Station influences on the measurement results.
The summarized results of the 1998 Radiological Environmental Monitoring Program are presented in Table 2.
Individual (raw data) results are presented in Appendix F, Tables F 1 through F-11.
REGULATORY REPORTING LEVELS Sample analysis data is reviewed and evaluated by the Radiological Health Supervisor as the results are received. All sample analytis results are reviewed for correct sensitivity and
- a anomalies.
- g The activity concentration values listed in Table E-1 are the environmental Fuel Cycle Dose quantities that, if exceeded, require a Special Report to be submitted to the USNRC. In accordance with the REMP Manual (Section 5, Fuel Cycle Dose), the Special Report must include an evaluation of any release conditions, environmental factors or other aspects which caused the reporting limits to be exceeded.
E lI Rancho Seco Nuclear Station.
E-7 1998 ARECH i
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I REGULATORY REPORTING LEVELS (continued)
In addition to the Fuel Cycle Dose reporting requirements, a Special Report is required to be submitted to the USNRC whan more than one of the radionuclides in Table E-1 are detected in the sampling medium and the summed ratio of detected activity concentration to the respect!ve Reporting Level concentration is greater than, or equal to, unity (1). When radionuclides other than those listed in Table E-1 are detected which are a result of Station effluents, a Special Report is required to be submitted if the potential annual dose commitment exceeds the 10 CFR 50, Appendix l guidelines.
No reports of the types described above were required to be submitted during 1998.
' SENSITIVITY OF THE REMP MEASUREMENT PROCESS All Program measurements must be performed at a sensitivity, which meets USNRC g
requirements. This sensitivity is determined "before the fact" (a prion) for each radionuclide of g
interest and sample analysis type. Typical controllable sensitivity parameters include:
=> Sample volume or mass e
=> Sampling efficiency
=> Time from sample collection tG measurement
=o Instrument detection efficiency for the nuclides (energies) of interest
=> Background radiation levels I.
=> Chemicalrecoveryfactors i
i By adjusting and controlling each of these parameters to maximize measurement process efficiency, a maximum sensitivity level (activity concentration) can be specified for each nuclide of interest and analysis type while maintaining an economic measur.ement process. The maximum.
sensitivities in the REMP are specified by the USNRC in the REMP Manual approved for Rancho Seco. These sensitivities are referred to as "LLD's", an acronym for " Lower Limit of Detection".
LLD's are specified on an "a priorf basis and apply to routine measurement process capabilities i
when no other interfering radioactivity is present. The word " routine" is emphacized since E!
occasional circurnstances, such as limited sample mass, elevated levels of background radiation 5
and interfering nuclides can contribute to sensitivity degradation.
Such occurrences are normally noted and reported during the conduct of REMP activities.
1I Rancho Seco Nuclear Station E-8 1998 AREOR I:
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- I SENSITIVITY OF THE REMP MEASUREMENT PROCESS
,I (continued)
Meeting the LLD requirements is a quality control function shared by both REMP and the analytical laboratory personnel. Once the laboratory establishes values for the controllable parameters for each analysis type, sample chain of custody controls ensure that these parameters are upheld. If all parameters are upheld, then compliance with the LLD requirements has been demonstrated. The specific LLD values for Program measurements are included in Table E-2.
I Since most u the samples analyzed result in the detection decision " activity not identified", a Minimurn Detectable Activity (MDA) concentration value is calculated and reported. This value can be thought of as the LLD-at-the-time-of-counting since it is calculated using an equation, i
- E which is similar to the one, used to establish LLD parameters. The biggest difference is that 5
actual (not "a pr/orr) parameters are used, including interference from natural radioactive material in the sample. It is important to note that MDA's are reported on!v for those measurements where the " activity not identified" decision has already been made.
MDA values are used primarily to identify changes in the measurement process and to convey a
more information about the measurement itself. Without the use of the MDA concept, most ig-Program measurements would be reported simply as "<LLD". With MDA used, Program measurements are reported as "< xxx " where "xxx" is the calculated MDA concentration.
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Rancho Seco Nuclear Station E-9 1998 AREOR I
I TABLE E-1 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Water Airborne Food (pCl/L)
Particulate or (pCl/kg, wet)
Products Analysis Gases (pCl/m')
(pCl/kg, wet)
H-3 20000*
Mn-54 1000 30000 Co-60 300 10000 Zn-65 300 20000 Cs-134 30 10 1000 1000 Cs-137 50 20 2000 2000 b
Gross Beta 40 2*
t Notes:
- For drinking water samples, this is a 40 CFR Part 141 value D Gross Beta activity in water of ten times the yearly mean of the control samples is indicated as the level that gamma isotopic analysis should be performed on the individual sample (NRC79a). ' Gamma isotopic analysis on each water sample is required by the REMP and therefore this requirement does not apply.
I
- Gross Beta activity is air of ten times the yearly mean of the control samples is indicated as the level that gamma isotopic analysis should be performed on the individual sample. The value indicated is Site specific.
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I l Rancho Seco Nuclear Station E-10 1998 AREOR i
3
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TABLE E-2 I
MAXIMUM (REQUIRED) LLD VALUES FOR ENVIRONMENTAL SAMPLES **
(NRC79A)
Airborne Fish Food Sediment I
Analysis Water Particulate (pCl/kg, Products (pCl/kg, dry)
(d)
(pCl/L) or Gases wet)
(pCl/kg, dry)
(pCl/m')
l Gross Beta 4
0.01 H-3 2000 (1000, D)
Mn-54 15 130 l
Co-60 15 130 150*
Zn-65 30 260 Cs-134 15(10 )
d 0.01 130 SO 150 D
Cs-137 18(10 )
0.01 130 60 150 d
Notes:
I (a)
Ana!ysis requirements are those reoammended in the BTP [NRC79A] and RETS
[NUREG79].
(b)
LLD for water samples utilized for human consumption only [NUREG79].
(c)
Other peaks, which are measurable and identifiable, together with the nuclides in Table E-2, shall be identified and reported.
(d)
Composite analysis LLD is Shown; individual sample LLD is 0.05 pCi/m'(Site specific value).
(e)
LLD for Mud and Silt Co-60 is not required by RETS [NUREG79]. This value is consistent with the RETS required value for Cs-134 and Cs-137.
I h
g
_ S.__ _
m,,
w
I ArgeNoix e 1998 SAMPLE ANALYSIS RAW DATATABLES I
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Rancho Seco Nuclear Station F-1 1998 AREOR
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TABLE F-1 1998 WEEKLY AIR SAMPLE
SUMMARY
Gross Beta Activity in Air Particulates (pCi/m )
Collection RASO.1CO 2 sigma RASO.3MO 2 sigma RASO.7EO.
2 sigma RAS 1.BFP 2 sigma Date 01/05/98 0.052 0.003 0.048 0.002 0.047 0.004 0.049 0.002 01/12/98 0.018 0.001 0.017 0.002 0.016 0.001 0.015 0.002 01/20/98 0.011 0.001 0.01 0.001 0.011 0.001 0.012 0.001 01/27/98 0.026 0.002 0.024 0.002 0.024 0.001 0.025 0.001 02/02/98 0.017 0.002 0.015 0.001 0.014 0.001 0.016 0.001 02/09/98 0.009 0.001 0.008 0.001 0.008 0.001 0.008 0.001 02/17/98 0.014 0.001 0.012 0.001 0.013 0.001 0.013 0.001 02/24/98 0.01 0.001 0.01 0.001 0.008 0.001 0.009 0.001 03/03/98 0.011 0.001 0.01
.0.001 0.01 0.001 0.01 0.001 03/10/98 0.016 0.001 0.015 0.001 0.013 0.001 0.015 0.001 03/17/98 0.018 0.002 0.018 0.001 0.017 0.001 0.018 0.002 03/24/98 0.022 0.001 0.021 0.001 0.023 0.001 0.021 0.001 03/31/98 0.01 0.001 0.01 0.001 0.011 0.001 0.01 0.001 04/06/98 0.012 0.001 0.01 0.001 0.009 0.001 0.01 0.001 04/13/98 0.014 0.001 0.013 0.001 0.011 0.001 0.012 0.001
~
04/21/98 0.016 0.001 0.015 0.001 0.016 0.001 0.017 0.001 04/28/98 0.022 0.001 0.026 0.002 0.023 0.001 0.023 0.001 05/05/98 0.019 0.002 0.022 0.002 0.02 0.001 0.02 0.001 05/11/98 0.011 0.001 0.012 0.001 0.011 0.001 0.011 0.001 05/19/98 0.009 0.001 0.01 0.001 0.009 0.001 0.008 0.001 05/2S/98 0.01 0.001 0.012 0.001 0.011 0.001 0.01 0.001 06/02/98 0.009 0.001 0.01 0.001 0.009 0.001 0.009 0.001 06/08/98 0.014 0.002 0.015 0.002 0.014 0.001 0.013 0.001 06/16/98 0.013 0.001 0.016 0.001 0.014 0.001 0.013 0.001 06/23/98 0.012 0.001 0.013 0.001 0.011 0.001 0.012 0.001 06/30/98 0.011 0.0G
- 0.011 0.001 0.012 0.001 0.012 0.001 I
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Rancho Seco Nuclear Station F-2 1998 AREOR I
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' I TABLE F-1 1997 WEEKLY AIR SAMPLE GUMMARY (continued)
Gross Beta Activityin Air Particulatc; (pCi/m')
Collection RASO.1CO 2 sigma RASO.3MO 2 sigma RASO.7EO 2 sigma RAS 1.8FP 2 sigma I
Date 07/06/98 0.016 0.001 0.016 0.001 0.016 0.001 0.017 0.001 07/15/98 0.02 0.001 0.018 0.002 0.02 0.001 0.018 0.001 I
07/21/98 0.023 0.001 0.022 0.001 0.022 0.001 0.021 0.001 07/28/98 0.02 0.001 0.019 0.001 0.018 0.001 0.019 0.002 08/03/98 0.022 0.001 0.022 0.001 0.02 0.001 0.022 0.002 I
08/10/98 0.025 0.002 0.024 0.002 0.026 0.002 0.025 0.002 08/18/98 0.024 0.002 0.024 0.002 0.024 0.002 0.026 0.002 08/25/98 0.022 0.002 0.02 0.001 0.019 _
0.001 0.018 0.001 I~
09/01/98 0.028 0.002 0.025 0.002 0.026 0.002 0.025 0.002 09/08/98 0.039 0.002 0.037 0.002 0.037 0.002 0.041 0.002 l
09/15/98 0.029 0.003 0.029 0.001 0.029 0.002 0.029 0.002 I
09/22/98 0.018 0.001 0.017 0.001 0.017 0.001 0.017 0.001 09/29/98 0.022 0.002 0.021 0.001 0.02 0.001 0.021 0.001 10/05/98 0.018 0.002 0.018 0.002 0.018 0.002 0.016 0.001 I
10/12/98 0.025 0.002 0.024 0.002 0.026 0.002 0.025 0.002 10/20/98 0.024 0.001 0.024 0.001 0.023 0.002 0.024 0.002 10/27/98 0.041 0.002 0.039 0.002 0.038 0.002 0.035 0.002 I
11/03/98 0.026 0.002 0.027 0.002 0.026 0.002 0.024 0.002 11/10/98 0.014 0.001 0.015 0.001 0.014 0.001 0.014 0.001 11/17/98 0.026 0.002 0.026 0.002 0.025 0.002 0.024 0.002 l
I 11/24/98 0.029 0.002 0.031 0.002 0.03 0.002_
0.029 0.002 11/30/98 0.014 0.001 0.015 0.001 0.014 0.002 0.015 0.001 12/07/98-0.011 0.001 0.012 0.001 0.011 0.001 0.012 0.001 I
12/15/98 0,033 0.001 0.029 0.002 0.029 0.002 0.031 0.002 12/22/98 -
0.024 0.002 0.024 0.002 0.027 0.002 0.026 0.002 L
12/29/98 0.069 0.003 0.064 0.003 0.067 0.003 0.067 0.005 I
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JI R2ncho Seco Nuclear Station F-3 1998 AREOR I
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Table F-2 1998 TLD Summary (Direct Radiation)
Quarterly (mrem)
Location ID Type 98-1 98-2 98-3 98-4 RTLO.3RO INDICATOR 18.80 14.20 14.80 18.40 RTLO.3CO INDICATOR 14.90 14.40 13.40 17.30 RTLO.3NO INDICATOR 17.60 14.40 14.50 17.00 RTLO.3LO INDICATOR 15.70 14.20 16.00 17.50 g
RTLO.3HO INDICATOR 8.00 14.40 14.20 14.80 E
RTLO.4FO INDICATOR 13.20 13.30 13.60 13.80 RTLO.5CO INDICATOR 14.10 13.40 14.40 Missing RTLO.6KO INDICATOR 13.70 13.70 14.20 14.10 RTL10.0HP CONTROL 15.40 17.20 13.90 14.30
_ RTL2.7MO INDICATOR 13.60 12.30 12.60 16.40 RTL8.2KO CONTROL 17.20 16.30 19.30 16.50 RTL7.8CO CONTROL 12.40 13.80 12.80 13.30 RTL1.8FO INDICATOR 11.60 14.80 11.60 15.40 RTL1.5MO INDICATOR 15.40 14.40 17.50 14.80 RTL3.9KO INDICATOR 14.20 12.80 13.80 13.60 RTL7.4MO CONTROL 15.70 14.30 14.00 15.40 RTL3.7NO INDICATt * ' 12.80 13.60 14.50 14.80 RTL3.8MO INDICAT..
14.80 14.20 14.30 14.80 RTL1.9NO INDICATUn 16.80 16.20 16.10 16.70 l
RTL1.7FO INDICATOR 15.80 13.70 13.60' 15.10 W
RTL1.4DO INDICATOR 17.60 16.00 14.70 16.40 RTL10.0EP CONTROL 13.70 13.50 13.10 13.60 RTL8.0PO CONTROL 11.80 13.80 14.20 14.60 RTLO.8DO INDICATOR 14.60 14.10 13.70 14.40 RTLO.6MO INDICATOR 19.30 14.20 12.90 13.50 RTLO.4NO INDICATOR 29.40 22.70 23.50 24.30 I
RTLO.4NO1 INDICATOR 16.60 15.40 17.10 16.00 RTLO.3PO INDICATOR 13.60 14.10 14.20 15.60 l
RTLO.3NP INDICATOR 13.60 14.10 16.80 15.40 RTLO.4NP INDICATOR 14.40 14.00 15.00 15.40 RTLO.5NP INDICATOR 20.70 14.60 14.30 15.20 RTLO 30P INDICATOR 14.10 17.40 14.20 15.70 RTLO.70P INDICATOR 13.70 14.10 14.30 13.80 RTLO.7JO INDICATOR 13.70 14.10 13.50 13.20 RTLO.4PP INDICATOR 15.90 14.60 15.20 15.60 I
Rancho Seco Nuclear Station F-4 1998 AREOR I
I Table F-3 1998 Garden Vegetables Semi-annual (pCi/kg, wet)
I Sample ID Collection Date Mn-54 Co40 Zn-65 Cs 134 Cs 137 RLVO.6MO 01/27/98
<6.00
<6.00
<15.0
<8.00
<6.00 I
RLV18.0KO 01/27/98
<17.0
<18.0
<41.0
<18.0
<16.0 j
RLVO.6MO 06/23/98
<23.0
<30.0
<58.0
<25.0
<21.0 i
RLV18.0KO 06/23/98
<8.00
<7.00
<17.0
<9.00
<7.00 RLVO.6MO 09/16/98
<12.0
<13.0
<30.0
<14.0
< 11.0 RLV18.0KO 09/16/98
<12.0
<15.0
<34.0
<15.0
<12.0 Table F-4 1998 SEDIMENT I
Quarterly (pCi/kg)
I Co-60 Cs-137 Sample ID Collection date Mn-54 Co-60 2 sigma 2n-65 Cs-134 Cs-137 2 sigma RMSO.3MO 02/12/98
<11.0
<12.0
<28.0
<13.0 143 13 RMSO.6MO 02/12/98
<4.0 7.00 4.0
<9.00
<5.00 221 7.0 RMSO.6MOQ 02/12/98
<5.0 15.0 7.0
, 12.0
<7.0 300 10 RMS1.8NO 02/12/98
<6.00
<9.00
<16.0
<9.00 156 9.0 RMS3.7NO 02/12/98 11.0+-5.0
<4.00
<13.0
<7.00 30.0 3.0 RMSO.7NO 02/12/98
<11.0
<12.0
<28.0
<14.0 102 14 RMS1.8NO 05/11/98
<7
<7
<18
<10 92 9
RMS3.7NO 05/11/98
<12
<13
<29
<15 42 12 RMSO.6MOQ 05/11/98
<6 16 6
<13
<10 614 11 RMSO.6MO
. 05/11/98
<18
<26
<38
<36 944 34 RMSO.7NO 05/11/98
<9
<12
<20
<13 268 15 RMSO.3MO 05/11/98
<6
<6
<13
<B 108 5
RMS3.7NO 08/10/98
<16
<17
<45
<19 65 18 RMSO.6MO 08/10/98
<9
<11
<25
<12 304 14 RMSO.6 MOO 08/10/98
<5 7
5
<11
<7 237 8
RMSO.7NO 08/10/98
<13
<14
<33
<16 74 15 RMS1.8NO 08/10/98 12+-5
<8
<19
<12
<7 RMSO.3MO 08/10/98
<7
<10
<16
<10 145 7
RMSO.3MO 11/17/98
<23
<25
<54
<29 385 29
.RMS3.7NO 1.!17/98
<15
<16
<39
<18 66 14 RMSI.BNO 11/17/98
<7
<7
<21
<10 314 8
RMSO.7NO 11/17/98
<14
<14
<35
<16 121 10 RMSO.6 MOO 11/17/98
<4 38 6
<12
<9 298 8
.I RMSO.6MO 11/17/98
<9 39 10
<20
<10 305 14 R:ncho Seco Nuclear Station F-5 1998 AREOR I
I I
TABLE F-4 (continued)
-g, 1998 SOIL AND SEDIMENT Effluent Creek Soil Semi-Annual (PCi/kg)
Sample ID Description Collection Date Mn-54 Co-60 Zn-65 ' Cs-134 Cs-137 RSLO.6MO Site Boundary 03/02/98
<13 187
<25
<11 1538 RSLO.6MO Site Boundary 09/10/98
<7 48
<16
<5 396 RSLO.7NO Water Sump 03/02/98
<8
<8
<21
<6 32 RSLO.7NO Water Sump 09/10/98
<7
<5
<16
<5 134 RSL1.5NO Silva Property 03/02/98
<13 77
<30
<13 1101 g
RSL1.5NO Silva Property 09/10/98
<8 29
<26
<8 501 g
RSL1.8NO Hadselville/ Clay Creeks 03/02/98
<15
<17
<36
<12 329 RSL1.8NO Hadselville/ Clay Creeks 09/10/98
<9
<9
<21
<6 56 I
TABLE F-4 (continued) 1998 SOIL AND SEDIMENT Characterization Site Boundary / Depression Areas Serni-Annual (pCi/kg)
Sample ID Description Collection Date Mn-54 Co-60 Zn-65 Cs-134 Cs 137 RSLO.4MP1 Depression 03/02/98
<27 2358
<57 414 61770 RSLO.4MP1 Depression 09/10/98
<19 1395
<47 180 39480 g
RSLO.4MP2 Depression 03/02/98
<14 380
<33 146 19500 g
RSLO.4MP2 Depression 09/10/98
<14 552
<33 112 21120 RSLO.4MP3 Depression 03/02/98
<15 54
<34
<18 5137 RSLO.4MP3 Depression 09/10/98
<10 94
<27 48 7834 RSLO.5MPAK Site Boundary 03/02/98
<14
<17
<30
<15 350 RSLO.5MPAK Site Boundary 09/10/98
<15
<16
<35
<13 308 l
RSLO.5MPAL Site Boundary 03/02/98
<16
<17
<34
<13 492 RSLO.5MPAL Site Boundary 09/10/98
<16
<23
<42
<17 571 m
RSLO.5MPAM Site Boundary 03/02/98
<12 411
<28 40 5003 RSLO.5MPAM Site Boundary 09/10/98
<10 55
<23
<8 1360 RSLO.5MPAN Site Boundary 03/02/98
<9
<10
<24
<7 128 RSLO.5MPAN Site Boundary 09/10/98
<7
<8
<15
<6 73 I
I Ranc'ao Seco Nuclear Station F-6 1998 AREOR I
TABLE F-4 (continued) 1998 SOIL AND SEDIMENT Storm Drain Soil Semi-Annual (pCi/kg)
Sample ID Description Collection Date Mn-54 Co-60 Zn-65 Cs-134 Cs-137 l
RSLO.2HO1 Storm Drain #1 02/26/98
<9
<7
<19
<6 9
I RSLO.2HO1 Storm Drain #1 09/10/98
<6
<5
<15
<5 51 RSLO.2HO2 Storm Drain #2 02/26/98
<12
<10
<26
<8 33 RSLO.2HO2 Storm Drain #2 09/10/98
<8
<7
<20
<6 25 RSLO.2JO Storm Drain #3 02/26/98
<7
<7
<19
<7 14 I
RSLO.2JO Storm Drain #3 09/10/98
<7
<8
<18
<5
<21 RSLO.2KO Storm Drain #4 02/26/98
<10
<11
<22
<8 51 RSLO.2KO Storm Drain #4 09/10/98
<6
<7
<16
<6 32 I
RSLO.3LO Storm Drain #5 02/26/98
<7
<9
<19
<7 26 RSLO.3LO Storm Drain #5 09/10/98
<8
<6
<17
<5 44 RSLO.2HO Storm Drain #6 02/26/98
<12
<13
<28
<8
<12 RSLO.2HO Storm Drain #6 09/10/98
<7
<8
<17
<6 44 I
RSLO 3MO7 Storm Drain #7 02/26/98
<8
<9
<21
<6 54 RSLO,3MO7 Storm Drain #7 09/10/98
<6
<7
<16
<6
<21 RSLO.3MO8 Storm Drain #8 02/26/98
<9
<10
<24
<7 35 RSLO.3MO8 Storm Drain #8 09/10/98
<4
<7
<16
<6 45 RSLO.3MO9 Storm Drain #9 02/26/98
<11
<10
<28
<8
<11 RSLO.3MO9 Storm Drain #9 09/10/98
<7
<6
<16
<5 40 I
RSLO.3AO Storm Drain #10 02/26/98
<9
<7
<25
<7 33 RSLO.3AO Storm Drain #10 09/10/98
<6
<6
<14
<5 39 RSLO.3OO Storm Drain #11 02/26/98
<11
<9
<23
<7
<11 RSLO.3OO Storm Drain #11 09/10/98
<6
<8
<18
<6
<27 RSLO.3NO Storm Drain #12 02/26/98
<10
<8
<24
<7
<10 RSLO.3NO Storm Drain #12 09/10/98
<4
<8
<17
<6
<19 RSLO.3NP1 ISFSI#1 02/26/98
<9
<9
<27
<8
<9 I
<8
<8
<20
<7
<28 RSLO.3NP2 ISFSI#2 02/26/98
<9
<9
<20
<7
<10 RSLO.3NP2 ISFSI#2 09/16/98
<9
<9
<19
<6
<27 RSLO.3NP3 ISFSI #3 02/26/98
<12
<11
<29
<9
<11 I
<7
<7
<18
<6
<23 II ll h
y _._ _
1 i
I !
Ii l
TABLE F-S 1998 F1SH Semi-Annual (pClikg, wet)
Sample ID Collection Date Mn-54 Co-60 ! 2n-65 Cs-134 Cs-137 gigj RFSO.6MO(1) 05/28/98
<138
<176
<307
<149
<361 RFSO.6MO(1) 11/23/98
<188
<193
<466
<240
<225 I
TABLE F-6 1998 ALGAE Semi-annual j
I]j (pCi/kg, wet)
Sample ID Collection Date Mn-54 Co-60 Zn-65 Cs 134 Cs-137 RAGO.3NO 06/16/98
<230
<276
<505
<283
<235 i
RAGO.7NO 06/16/98
<240
<299
<604
<274 709+-230 RAGO.6NO 06/16/98
<245
<260
<518
<256
<317 RAG 1.8NO 06/16/98
<97
<78
<202
<114 1200+-120
_RAGO.3NO 09/02/98
<99
<104
<226
<118 649+-100 RAGO.7NO 09/02/98
<285
<295
<645
<331 411+-300 RAG 1.8NO 09/02/98
<118
<118
<255
<148 488+-130
)
RAG 3.7NO 09/02/98
<124
<128
<262
<141 283+-110 I
I I
I I
l I
Rancho Seco Nuclear Station F-8 1998 AREOR I'
I TABLE F-7 1998 WELL WATER Ouarterly (pCi/L)
I Sample ID Collection Gross Tritium Mn-54 Co-60 Zn-65 Cs-134 Cs-137 Data Beta I
RWW0.3EO 03/23/98 4.65
<183
<8.97
<11.6
<19.0
<10.6
<9.17 R,WWO.3EO 06/23/98 5.34
<216
<9.18
<10.1
<16.3
<10.7
<8.75 RWW0.3EO 09/15/98 2.70
<205
<9.98
<19.4
<25.0
<12.2
<10.1 I
RWW0.3EO 12/15/98 3.66
<226
<12.7
<14.0
<26.7
<13.2
<11.2 RWW0.8DO 03/23/98 2.15
<184
<9.88
<12.2
<20.2
<11.3
<9.02 RWWO.8DO 06/23/98 4.56
<211
<9.23
<13.6
<21.7
<12.2
<9.51 I
RWWO.8DO 09/15/98 1.97
<218
<4.26
<4.79
<8.83
<5.88
<4.19 RWWO.8DO 12/15/98 1.97
<226
<11.3
<11.6
<21.8
<10.7
<9.45 RWWO.8LO 03/23/98 4.15
<185
<9.21
<10.4
<20.2
<11.2
<9.15 I
RWWO.8LO 06/23/98 4.43
<213
<9.08
<11.4
<20.6
<12.2
<9.65 RWWO.8LO 09/15/98 2.36
<201
<11.1 30.6 +-14
<24.8
<12.1
<10.5 RWWO.8LO(recount) 09/15/98 2.36
<201
<5.41 24.7+-5.7
<6.24
<4.51 I
RWWO.8LO(in house) 11/18/98
<2.54
<2.49
<5.70
<2.44
<2.88 RWWO.8LO(resample) 11/18/98
<9.11
<10.8
<20.6
<10.2
<9.21 RWWO.8LO 12/15/98
<2.47
<228
<10.0
<10.4
<22.2
<11.8
<8.88 I
RWW1.5MP 03/23/98 2.90
<180
<3.52
<4.44
<7.64
<4.36
<3.73 RWW1.5MP 06/23/98 3.02
<210
<4.19
<4.88
<8.82
<5.40
<4.26 RWW1.5MP 09/15/98
<1.52
<208
<4.99
<6.47
<9.58
<6.54
<4.94 I
RWW1.5MP 12/15/98
<2.41
<233
<10.0
<10.2
<24.8
<10.7
<8.73 RWW2.1MO 03/23/98 2.71
<183
<3.88
<4.38
<8.33
<4.35
<3.83 RWW2.1MO 06/23/98 2 28
<215
<9.84
' 13.4
<24.3
<12.2
<9.67 I
RWW2.1MO 09/15/98 1.47
<202
<10.8
<10.4
<23.5
<11.8
<9.42 RWW2.1MO 12/15/98
<2.59
<228
<4.43
<4.72
<10.4
<5,11
<4.00 RWW3.7MO 03/23/98 3.48
<187
<2.98
<3.69
<7.06
<3.89
<3.40 RWW3.7MO 06/23/98 3.47
<215
<10.3
<12.0
<18.8
<12.7
<15.9 RWW3.7MO 09/15/98 1.39
<206-
<4.46
<4.67
<9.87
<5.56
<4.51 RWW3.7MO 12/15/98
<2.12
<228
<3.46
<3.74
<8.70
<4.49
<3.72 I
I
{I l
Rancho Seco Nuclear Station F-9 1998 AREOR
i iIl l
I!
TABLE F-8 1998 RUNOFF WATER Biweekly (PCi/L)
Sample ID Collection Date Tritium Mn-54 Co-60 Zn-65 Cs-134 Cs-137 RRWO.6MO 01/12/98
<200
<8.28
<8.11
<18.3
<9.06
<9.06 g
RRWD.6MO 01/27/98
<200
<9.75
<10.3
<20.4
<11.6
<9.27 g
RRWO.6 MOO 01/27/98
<194
<3.29
<3.69
<6.87
<4.22
<2.99 RRWO.6MO 02/09/98
<206
<3.65
<4.37 c8.46
<5.00
<4.03 g
RRWO.6MO 02/24/98
<199
<4.07
<4.19
<8.19
<4.89
<3.98 gj RRWO.6MO 03/10/98
<198
<10.0
<12.6
<24.8
<13.5
<11.6 gl' RRWO.6MO 03/24/98
<189
<3.82
<4.07
<8.21
<4.56
<3.81 RRWO.6MO 04/06/98
<188
<3.34
<3.66
<6.94
<4.19
<3.27 3
RRWO.6MO 04/21/98
<189
<9.32
<10.5
<19.1
<10.5
<8.87 RRWO.6MOQ 04/21/98
<187
<3.60
<4.21
<7.43
<4.33
<4.00 g
RRWO.6MO 05/05/98
<279
<3.31
<3.74
<7.10
<4.46
<3.46 3
RRWO.6MO 05/19/98
<276
<9.64
<11.5
<19.4
<11.7
<9.22 RRWO.6MO 06/02/98
<192
<8.78
<28.5
<17.2
<11.3
<9.54 g
RRWO.6MO 06/16/98
<216
<9.69
<11.5
<20.0
<10.2
<216 g
RRWO.6MO 06/30/98
<239
<4.17
<4.92
<9.87
<5.35
<3.91 RRWO.6MO 07/15/98-
<237
<4.05
<4.41
<8.38
<5.22
<4.11 g
RRWO.6 MOO 07/15/98
<245
<10.7
<12.3
<24.6
<12.4
<10.2 E
RRWO.6MO 07/28/98
<239
<9.75
<11.5
<18.7
<11.1
<8.96 RRWO.6MO 08/10/98
<184
<11.0
<11.7
<28.2
<12.5
<10.2 g
RRWO.6MO 08/25/98
<188
<4.05
<4.92
<8.96
<5.42
<4.38 5
RRWO.6MO 09/08/98
<217
<10.3
<9.37
<21.4
<11.0
<9.04 RRW0.6MO 09/22/98
<217
<4.58
<4.45
<8.55
<5.74
<4.28 g
RRWO.6MO 10/05/98
<218
<9.42
<9.76
<19.5
<11.4
<7.89 5
RRWO.6MOQ 10/05/98
<222
<4.05
<4.24
<8.55
<5.42
<4.05 RRWO.6MO 10/20/98
<171
<2.50
<2.78
<5.76
<3.19
<2.28 g
RRWO.6MO 11/03/98
<173
<5.80
<12.8
<13.0
<6.63
<6.22 5
RRWO.6MO 11/17/98
<224
<4.36
<4.74
<9.85
<5.12
<3.89 RRWO.6MO 11/30/98
<224
<4.11
<4.42
<8.90
<5.15
<3.99 RRW0.6MO 12/15/98
<222
<3.86
<3.62
<8.97
<4.97
<3.94 RRWO.6 MOO 12/29/98
<189
<8.08
<9.54
<16.4
<10.1
<9.35 RRWO.6MO 12/29/98
<184
<9.51
<11.9
<22.6
<10.8
<9.12 I
Rincho Seco Nuclear Station F-10 1998 AREOR I1 J
II I
TABLE F-9
{
1998 SURFACE WATER Monthly Grab / Monthly Composite (pCi/L)
Sample ID Collection Date Tritium Mn-54 Co.60 Zn-65 Cs-134 Cs-137 RSW3.7NO 01/27/98
<196
<3.78
<3.68
<7.39
<4.45
<3.58
{
RSWO.7NO 01/27/98
<195
<3.91
<4.10
<8.92
<4.92
<4.08
+
RSW1.3FO 01/27/98
<198
<7.28
<8.31
<16.0
<9.03
<6.09 RSW1.8NO 01/27/98
<196
<6.31
<7.10
<14.7
<8.01
<7.22
)
RSW1.8NOO 01/27/98
<202
<10.5
<12.0
<20.4
<11.4
<9.03
{
RSWO.3MO 01/27/98
<198
<8.49
<10.4
<18.8
<10.9
<7.63 j
RSW1.3FO 02/24/98
<196
<3.17
<3.72
<6.78
<3.96
<3.38 RSW1.8NO 02/24/98
<200
<9.83
<10.2
<22.1
<11.8
<9.91 RSWO.7NO 02/24/98
<197
<9.96
<13.6
<22.2
<12.0
<9.14 RSW3.7NO 02/24/98
<201
<9.20
<10.2
<21.2
<11.2
<9.49 i
RSW0.3MO 02/24/98
<201
<3.73
<4.53
<8.50
<4.93
<3.68 RSW1.8NO 03/24/98
<191
<7.83
<10.0
<19.3
<8.62
<8.37 RSW3.7NO 03/24/98
<186
<4.16
<4.12
<9.67
<4.62
<3.87 RSWO.7NO 03/24/98
<197
<9.14
<11.6
<21.2
<10.3
<9.70 RSW1.3FO 03/24/98
<192
<4.32
<4.50
<8.08
<5.40
<4.45 i
RSW0.3MO 03/24/98
<189.
<9.12
<12.5
<21.8
<12.4
<10.3 RSW1.8NO 04/21/98
<185
<10.4
<12.4
<21.2
<11.4
<10.1 RSW1.3FO 04/21/98
<182
<9.82
<11.7 '
<20.1
<11.2
<9.47 RSWO.7NO 04/21/98
<187
<10.4
<12.8
<23.6
<11.5
<10.4 I
RSW3.7NO 04/21/98
<184
<9.12
<10.9
<16.1
<11.4
<8.68 RSW1.8NOO 04/21/98
<183
<9.34
<11.5
<18.2
<11.9
<9.16 RSWO.3MO 04/21/98
<187
<4.14
<4.36
<8.06
<5.04
<4.19 RSW1.8NO 05/26/98
<.198
<10.8
<13.5
<23.0 '
<11.9
<10.3 RSWO.3MO 05/26/98
<190
<3.96
<4.66
<9.96
<5.05
<3.92 RSW1.3FO 05/26/98
<191
<9.40
<11.9
<18.5
<10.4
<9.82 I
RSWO.7NO 05/26/98
<190
<3.89
<4.47
<8.70
<4.98
<4.27 RSW3.7NO 05/26/98
<191
<10.0
<12.6
<20.0
<11.2
<10.4 RSW1.8NO 06/23/98
<213
<9.36
<11.7
<21.5
<10.7
<9.62 I
RSW0.3MO 06/23/98
<212
<4.31
<4.61
<8.77
<S.26
<3.58 RSW3.7NO 06/23/98
<217
<3.50
<3.74
<7.79
<4.68
<3.45 RSWO.7NO 06/23/98
<211
<10.6
<11.8
<22.9
<10.6
<9.79 RSW1.3FO 06/23/98
<211
<3.95
<4.00
<8.23
<4.96
<3.66 I
. I R2ncho Seco Nuclear Station F-11 1998 AREOR
I TABLE F-9 l'
(continued) 5 1998 SURFACE WATER E
Monthly GratV Monthly Composite E'
(pCl/L)
Sample ID Collection Date Tritium Mn-54 Co-60 Zn 65 Cs-134 Cs-137 RSW1.8NO 07/28/98
<240
<8.86
<10.6
<19.8
<10.3
<9.92 RSW1.3FO 07/28/98
<240
<8.09
<10.4
<17.7
<11.9
<8.56 gl RSW1.8NOO 07/28/98
<239
<3.76
<4.28
<8.52
<4.60
<3.77 W
RSWO.3MO 07/28/98
<240
<11.0
<11.6
<23.0
<12.3
<9.56 RSW3.7NO 07/28/98
<235
<8.99
<12.0
<19.8
<12.1
<8.97 g
RSWO.7NO 07/28/98
<228
<4.04
<4.16
<8.85
<5.26
<3.87 5
RSWO.3MO 08/25/98
<219
<10.1
<10.9
<21.6
<12.0
<9.19 RSWO.7NO 08/25/98
<209
<4.39
<4.62
<8.89
<5.62
<4.45 RSW1.3FP 08/25/98
<206
<10.1
<12.6
<23.8
<12.0
<10.8 RSW1.8i'J) 08/25/98
<205
<9.64
<9.44
<21.3
<11.8
<9.35 RSW3.~ AIO 08/25/98
.<217
<4.09
<4.43
<9.29
<5.56
<4.39 RSW0.7NO 09/22/98
<218
<9.21
<12.4
<20.3
<10.7
<8.84 -
RSWO.3MO 09/22/98
<226
<8.62
<9.63
<20.6
<10.3
<8.07 RSW3.7NO 09/22/98
<229
<4.21
<4.35
<8.54
<4.97
<3.65 RSW1.8NO 09/22/98
<216
<10.6
<11.8
<22.1
<12.0
<10.0 RSW1.3FO 09/22/98
<216
<5.4
<5.95
<11.7
<6.85
<4.82 RSW0.7NO 10/27/98 358+-130
<10.2
<9 03
<21.9
<11.2 <
<9.35 RSWO.3 MOO 10/27/98 363+-140 RSW3.7NO 10/27/98
<207
<4.29
<4.62
<9.13
<5.33
<4.21 RSWO.3MO 10/27/98 355+-140
<9.88
<11.3
<23.4
<11.9
' 8.69 RSW1.8NOO 10/27/98 9780+-330
<11.6
<11.7
<26.0
<12.2
<9.72 RSW1.3FO 10/27/98
<205
<8.83
<9.86
<21.5
<9.70
<8.33 RSW1.8NO 10/27/98 9520+-320
<4.56
<4.83
<12.2
<5.75
<4.49 RSW1.8NO 11/24/S8
'<222
<4.53
<5.06
<8.98
<5.61
<4.09 RSW1.3FO 11/24/98
<217
<8.87
<10.4
<19.9
<11.0
<10.6 RSWO.7NO 11/24/98 896+-160
<9.45
<11.4
<20.8
<11.8
<10.1 RSW3.7NO 11/24/98
<214
<3.73
<4.46
<9.57
<5.16
<3.58 RSWO.3MO 11/24/98 622+-150
<8.71
<9.50
<19.3
<10.3
<9.39 RSWO.7NO 12/29/98 959+-140
<10.7
<11.9
<25.2
<11.2
<9.87 RSW3.7NO 12/29/98
<186
<9.66
<12.2
<24.4
<12.0
<9.25 RSWO.3MO 12/29/98 638+-130
<8.69
<9.68
<18.0
<10.1
<9.79 RSW1.3FO 12/29/98
<194
<4.66
<5.00
<10.1
<5.84
<4.60 RSW1.8NO 12/29/98
<188
<3.42
<3.48
<8.46
<5.00
<3.66 I
Rancho Seco Nuclear Station F-12 1998 AREOR
I I
TABLE F-10 1998 Drinking Water i
Monthly (pCi/L)
Sample ID Collection Date Grois Beta Tritium Mn-54 Co-60 Zn-65 Cs-134 Cs 137 RDWO.1GO 01/27/C8 9;28
<198
<3.40
<3.58
<6.97
<4.00
<3.18 RDWO.1GO 02/24/98 1120
<194
<3.55
<4.15
<7.10
<4.50
<3.49 RDWO.1GO 03/24/98 4.34
<186
<3.53
<4.09
<7.92
<4.93
<3.46 RDWO.1GO 04/21/98 7.89
<201
<3.42
<3.65
<7.51
<4.28
<3.59 RDWO.1GO 05/26/98 (i.15
<210
<3.91
<4.49
<8.40
<4.71
<3.99 RDWO.1GO 06/23/98 fi.74
<216
<4.61
<4.91
<9.66
<5.67
<4.20 RDWO.1GO 07/28/98 7.16
<224
<10.0
<17.5
<18.2
<10.7
<9.55 RDWO.1GO 08/25/98 3.97
<186
<4.47
<4.69
<9.55
<5.66
<4.52 RDWO.1GO 09/22/98 2.t34
<223
<9.83
<12.0
<22.2
<11.6
<9.27 RDWO.1GO 10/27/98 1}.8
<223
<4.15
<4.16
<8.43
<4.73
<3.25 RDWO.1GO 11/24/98 3.28
<251
<9.69
<11.9
<22.6
<11.8
<8.62 j
RDW0.1GO 12/29/98 3p2
<188
<3.73
<4.21
<7.62
<4.81
<3.75 RDW1.8FP.
01/27/98 6114
<202
<2.80
<2.86
<5.96
<3.58
<2.87 RDW1.8FP 02/24/98 7.36
<193
<9.31
<11.3
<19.2
<10.6
<8.39 RDW1.8FP 03/24/98 6.26
<184
<4.13
<4.52
<8.82
<4.88
<3.94 RDW1.8FP 04/21/98 5.11
<201
<3.19
<3.86
<6.36
<4.08
<3.59 RDW1.8FP 05/26/98 6.02
<207
<10.2
<11.7
<21.0
<11.4
<9.35 RDW1.8FP 06/23/98 2.$7
<214
<9.99
<12.5
<22.9
<11.1
<8.89 RDW1.8FP 07/28/98 5.34
<224
<3.79
<4.35
<8.78
<5.15
<3.74 RDW1.8FP 08/25/98
<2 42
<185
<10.7
<10.5
<20.1
<11.5
<9.74 RDW1.8FP 09/22/98 2.11 3
<218
<10.4
<14.0
<25.1
<14.8
<10.8
_RDW1.8FP 10/28/98 42!9
<232
<4.63
<4.95
<11.4
<8.79
<4.33 RDW1.8FP 11/24/98 2.!p
<233
<8.63
<9.66
<19.6
<12.3
<9.12 RDW1.8FP 12/29/98 3.79
<188
<10.6
<13.4
<23.9
<11.9
<9.22 I
j-RIncho Seco Nuclear Station F-13 1998 AREOR I
q TABLE F-11 I
1998 Rain Water Seasonal (pCi/L)
Sample ID Collection date Tritium Mn-54 Co-60 Zn-65 Cs-134 Cs-137 l
RRNO.8DO 01/12/98
<199
<3.15
<3.46
<7.03
<3.85
<3.14 5
RRNO.8DO 01/27/98
<196
<7.88
<8.88
<17.7
<9.30
<8.29 RRNO.8DO 02/09/98
<192
<9.13
<11.1
<20.8
<11.2
<9.09 RRNO.8DO 02/24/98
<204
<3.61
<4.14
<7.83
<4.84
<3.56 f
RRNO.tsuO 03/10/98
<202
<8.74
<10.3
<19.8
<9.90
<8.86 RRNO.8DO 03/23/98
<190
<8.34
<11.3
<18.8
<10.5
<8.57 lI RRNO.8DO 04/06/98
<183
<8.39
<10.0
<17.0
<9.48
<7.93 Wl RRNO.8DO 04/21/98
<182
<9.18
<11.3
<20.0
<10.7
<10.3 RRNO.8DO 05/05/98
<287
<9.68
<11.1
<20.4
<10.9
<9.58 l
RRNO.8DO 05/26/98
<189
<10.3
<12.9
<22.3
<11.5
<9.69 m
RRNO.8DO 06/08/98
<190
<3.64
<4.26
<7.77
<4.91
<3.76 RRNO.8DO 09/29/98
<225
<4.72
<5.06
<9.70
<5.38
<4.37 RRNO.8DO 10/27/98
<214
<11.1
<12.6
<22.3
<12.3
<9.08 RRNO.8DO 11/17/98
<219
<8.67
<11.4
<19.6
<10.3
<8.54 RRNO.8DO 11/30/98
<215
<9.73
<12.0
<21.0
<12.1
<9.62 RRNO.8DO 12/15/98
<235
<8.88
<11.4
<18.1
<9.77
<8.58 I
I' I
I' R:ncho Seco Nuclear Station F-14 1998 AREOR I:
f I
l i
APPENDIX G 1998 MISSED SAMPLE REPORT in accordance with the requirements REMP manual section 3.1, the following samples are being I
reported as not being collected for the reasons indicated during 1998. Corrective action as required by the REMP manual is as indicated.
I TLD (Direct radiation oathway)
I Location # 7 RTLO.5CO, Rancho Seco Entrance Sign (indicator) - On January 4,1999, the TLD's at this location were missing during the routine changeout. First Quarter 1999 TLD's were restored at this location. No TLD data will be available for this location for the fourth quarter 1998.
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i l-Rancho Seco Nuclear Station G-1 1998 AREOR I
L
APPENDIX G ADDENDUM TO 1997 AREOR REPORT 1.
During an intemal OA audit it was found that the second quarter 1997 Mud and Silt (Sediment) data was not included in the 1997 AREOR. The missing data is provided in the following table:
1997 Mud and Silt Data Second Quarter 1997 Co-60 Cs-137 Sample ID Collection date Mn-54 Co-60 2 sigma Zn-65 Cs-134 Cs-137 2 sigma RMS3.7NO 05/12/97
<10
<10
<28
<12 27 9.0 RMSO.3MO 05/12/97
<10
<10
<25
<12 100 11 RMSO.7NO 05/12/97
<6.0
<8.0
<16
<12 220 11 RMSO.6MO 05/12/97
<8.0 14 10
<20
<17 230 10 RMSO.6 MOO 05/12/97
<3.0 9.0 5.0
<8.0
<5.0 170 4.0 RMS1.8NO 05/19197
<5.0
<5.0
<13
<7.0 74 4.0 2.
During an NRC sudit conducted during July 6-9,1998, the following discrepancies were noted in the 1997 AREOR:
a)
Page E-6, fourth paragraph indicates that there are 34 TLD locations. Page F-4, Table F-2 indicates there are 35 TLD locations. The correct number of locations is 35.
b)
Page 1, paragraph 5 states that there are two TLD locations, placed as part of the characterization program, which indicates higher than the indicator average. The correct statement should be one location is higher than the indicator average.
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Rancho Seco Nuclear Station H-1 1998 AREOR
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