ML20195J057

Annual Radiological Environ Operating Rept,1987

ML20195J057
Person / Time
Site:	Rancho Seco
Issue date:	12/31/1987
From:	Andognini G SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
GCA-88-299, NUDOCS 8806290046
Download: ML20195J057 (142)

Text

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I ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l 1987 RANCHO SECO NUCLEAR GENERATING STATION

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1 ANkUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT I 1987 RANCHO SECO NUCLEAR GENERATING STATION i

i TABLE OF CONTENTS l 1

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I. EXECUTIVE

SUMMARY

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. II.

SUMMARY

OF 1987 RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE ACTIVITIES l t

l III. DATA INTERPRETATION AND CONCLUSIONS A. Air Samples l B. Thermoluminescent Dosimeters (TLD)  ;

i C. Algae  ;

i D. Animal Vegetation l 1

E. Edible Aquatic Fauna  !

F. Milk G. Mud and Silt '

i i H. Rabbits ,

I. Water

J. Human Vegetation

! K. Cow Thyroid L. Beef Tissue M. Honey

'! N. Duck and Pheasant

0. Soil 04-28-88 HP7278P D-01708 i l

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rF ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SECO NUCLEAR GENERATING STATION IV. RADIOLOGICAL ASSESSMENT OF IMPACT ON THE ENVIRONS .

A. ,ladiological Impact - Gaseous Effluents, B. Radiological Impact - Liquid Effluents C. Summary D. References V. APPENDICES A. Land Use Census B. Sampling Program Description and Haps C. Interlaboratory Comparison Program D. Missing Simples E. Missing Data from the 1986 Annual Radiological Environmental Operating Report O

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4 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SECO NUCLEAR GENERATING STATION I. EXECUTIVE

SUMMARY

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The Rancho Seco Nuclear Generating Station Unit One is located approximately 26 miles north-northeast from Stockton and 25 miles southcast from Sacramento in Sacramento County, California. Rancho Seco Unit One began commercial operation on April 17,1975. The single Unit is a pressurized water reactor supplied by Babcock & Hilcox. The rated capacity is 2,772 megawatts thermal and 963 gross megawatts electrical.

This report has been prepared by the Sacramento Municipal Utility District to meet the + .ing requirements of Technical Specification 6.9.2.2, Operating License No. OPR-54. It is transmitted to the U. S. Nuclear Regulatory Commission Region V. Copies are provided to the California Department of Public Health, Sacramento County Health Department, California State University at Sacramento, Central Valley Regional Water Quality Control Board, local libraries, and District offices as a public document.

This report presents several types of related information including:

. Summaries, interpretations, and statistical evaluations of O the results of the radiological environmental surveillance for calendar year 1987.

Comparisons with preoperational and previous years data.

Descriptions of the elements of the radiological environmental monitoring program.

Maps of sampling locations (keyed to tables) which indicate distance and direction from the containment building, Results of the annual land use census.

Results of the interlaboratory comparison program for the District's environmental monitoring contractor (Controls for Environmental Pollution, Inc. [CEP]).

Assessment of the radiological impact based on environmental sample and land use census information.

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ANNUAL pa0IOLOGICAL' ENVIRONMENTAL OPERATING REPORT 1987

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I. .

EXECUTIVE

SUMMARY

(Continued)

. Data for this report were obtained from two main sources:

. CEP, the District's environmental monitoring program contractor.

. Investigations by District staff.

In brief, the results of the 1987 radiological environmental monitoring program indicate the following:

. Land use in the gaseous pathway is essentially unchanged.

. Normal usage of Laguna Creek and Folsom South Canal water for irrigation continued.

Residents who regularly used the liquid effluent pathway for food or recreational purposes stopped using the stream system in late 1984.

. Radiation exposures in the gion are unrelated to plant gaseous effiuent releases and appear to be due to local geology and the Chernobyl accident in the USSR that began April 26, 1986.

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Air sampling data were all negative with respect to contribution by the plant.

Radioactivity in stream bed sediments and aquatic flora and fauna in the Clay-Hadselville-Laguna Creek systems is consistent with previous results. The radioactivity is principally C:-134 and Cs-137. There has been a decrease in radioactivity detected in algae.

No radioactivity in any environmen; . samples could be attributed to releases in the gaseous pathway.

Radiation doses which were calculated for various uses of the liquid pathway totated less than one millirem for 1987.

Results of the interlaboratory comparison were satisfactory. >

The residual radionuclides in the streams downstream from Rancho Seco appear to be mixed to a greater depth in the stream sediments and are more tightly bound and les: available for uptake by the fish.

The levels of radionuclides observed in the fish appear to be related to the levels in the water, not the sediments, and to levels of stable potassium in the water, p)

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Table III-3 sunnarizes the Annual results for all samples and sample locations.

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l 1987 i RANCH 0'SECO NUCLEAR GENERATING STATION i

'O II

SUMMARY

OF 1987 RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE l l

ACTIVITIES l i

The Radiological Environmental Monitoring Program (REMP),

Appendix B, is designed to assMs the impact of Rancho Seco on its environment. To accomplish the objectives of this program, j collection and analysis of environmental samples are performed on a routine basis. The media which .re most likely to first show changes in levels of radioactivity above natural background ,

are sampled most frequently.

The District has committed to condeci the REMP and support measures to upgrade it. The REMP is 'he responsibility of the Health Phy.ics / Chemistry Services (HPCS) group, formerly known 4 as the Health Physics Support and Environmental Programs (HPSEP) group. The program upgrades, initiated in 1986, continued into l 1987, and included the following:

• Revision of the Technical Specifications to be consistent with Standard Radiological Technical Specifications.

. Establishment of additional sampling points for all effluent pathways (see Table 11-1). j

. Adoption of the "control vs. indicator" sample concept for th6 REMP.  ;

. Upgrade of tr.e air sampling program.

3 . Improvement of sample identification and numbering system

. Development and revision of REMP orocedures.

. Establishment of REMP training for associated personnel..

• SMUD made majer changes to the Sampling Program in 1987 intended to assist in the assessment of radioactivity in l the environment due to past effluent releasti. The entire ,

mylual is included in Appendix B. These changes are  !

listed below:

. The sampling sites were evaluated and categorized as

, indicator or control samples.

. The sampling sites were renamed using an alpha-numeric numbering system that designates sample type, .

distance from Rancho Seco, and the Cardinal sector where the sample site is located. j

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V ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 rm RANCHO 3ECO NUCLEAR GENERATING STATION j II. SUMMARv 0F 1987 RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE l ACTIVITIES (Continued)  !

. An additional sampling site for runoff watar was l added to the sampling program. l

• Three additional surface water sample sites were added to the sampling program.

. An additional well water sample site was added to the  !

sampling proaram.  !

. Eight additionel mud and silt sample sites were added to the sampling program to increase the surveillance of the liquid effluent pathway. l

. Five soil sampling sites were added to the sampling program. This is the first time that soil has been routinely collected. Four of the sites are in locations affected by liquid effluent releases. The fifth location is a controi location. l 1

- Five additional fish sampling sites have been added I p to the sampling program. Theses additional locations are the major sampling locations that Lawrence Livermore National Laboratories have monitored as part of special environmental monitoring studies at Rancho Seco. Fish samples will be collected at these sample sites when they are available.

. Two garden sites were constructed on Rancho Seco property to provide human vegetation samples. One site will primarily monitor the gaseous exposure 4 pathway. ihe other site will be watered by the plant i liquid effluent and will provide information about the liquid exposure patnway. )

. Seven additional algae sampling sites were added to the sampling program.

. Four additional pasture vegetation sample sites were added to the program in areas irrigated by the liquid effluent releases.

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II

SUMMARY

OF 1987 RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE ACTIVITIES (Continued)

. Four sample sites were added for the collection of frogs and crawfish when they are available to increase monitoring of the liquid effluent pathway.

. The analyses of several sample types were changed to reflect a more discrete analysis. Gamma scans and specific I-131 analysis replaces some of the gross beta screening methodology.

Section III of this report provides data obtained from the 1987 REMP operation. The data includes interpretation, trending, and conclusions for each sample edia.

Section IV of this report provides an assessment of Rancho Seco's effect on the environment during 1987. The calculation of the radiological impact to man is discussed in this section. I Appendix A presents the results of the 1987 land use census conducted by the District. It includes land use census data expanded to a 50 mile radius. The 50 mile radius land use j (3 census was conducted in support of the Updated Safety Analysis '

() Report (USAR).

Appendix B describes the sampling and analysis program (including maps) that support the REMP.

Appendix C contains the results of CEP's (the District's environmental contractor) participation in the inter aboratory comparison program.

Appendix 0 provides a list of environmental samples that were not collected in 1987 as required by District procedures and/or i Technical Specifications. The samples missed were due to I circumstances beyond the District's control.

Appendix E presents the missing data from the 1986 Annual Radiological Environmental Report.

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

.1987 RANCHO SECO NUCLEAR GENERATING STATION F

Table II-l is a listing of new sample locations -

for samples initiated in 1987.: Forty-seven new locations are identified.

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SEC0 NUCLEAR GENERATING STATION TABLE II-l NEW SAMPLE LOCATIONS Sample Type Sample Collection Description of Location Identification Class

• Freauency Location Name/Dearees/ Miles Fish Samoles RFSO.7N0 IND Quarterly Hater Sump 265* 0.7 RFSl.8N0 IND Quarterly Confluence of Clay and Hadselville Creek 272 1.8 RFS2.2NO IND Quarterly Hadselville Creek above Clay Station Rd 260 2.2 RFSS.4HO IND Quarterly Laguna Creek at Laguna Rd 265 5.4 RFS10.M0 IND Quarterly Laguna Creek at McKenzie Rd 259 10.0 Alcae Samelei RAGO.6MO IND Quarterly Site Boundary 255 0.6 RAGO.7NO IND Quarterly Hater Sump 265 0.7 RAG 1.3F0 CON Quarterly Rancho Seco Reservoir 104 1.3 RAGl.8N0 IND Quarterly Confluence of Clay and Hadselville Creeks 272 1.8 RAG 2.2N0 IND Quarterly Hadselville Creek near Clay Station Rd 260 2.2 RAG 5.4HO IND Quarterly Laguna Creek at Laguna Rd 256 5.4 RAGIOMO IND Quarterly Laguna Creek at McKenzie Rd 259 10.0 l

Rabbit Samole 1

RRBX.XN0 IND Quarterly West of Site Boundary X.X l

• CON = Control

• IND*= Indicator

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l ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT -

1987 RANCHO SECO NUCLEAR GENERATING STATION l TABLE II-1 (Continued)  !

NEH SAMPLE LOCATIONS .

Sample Type Sample Collection Description of Location l Identification Class Frecuency Location Name/Dearees/Hiles Soil Samoles RSLO.6H0 IND Quarterly Site Boundary 255 0.6 RSLO.7NO IND Quarterly Silva Property 250 0.7 1

RSLI.3F0 CON Quarterly Rancho Seco Reservoir 104 1.3 RSLl.5N0 IND Quarterly Silva Property 264 1.5 RSLI.8N0 IND Quarterly Silva Property 268 1.8 Runoff Water

[ RRHO.6H0 IND Biweckly Site Boundary 255 0.6 Surface Water RSWO.7NO IND Honthly Hater Sump 255 0.7 l Rain Water RRNO.800 IND Seasonal Marciel Ranch 75 0.8 l l

RRN23K0 CON Seasonal SHUD Headquarters 315 23.0 Pasturaae i

RPVO.6MO IND Honthly Site Boundary 2.55 0.6 RPV0.8N0 IND Monthly Silva Property 260 0.8 l RPV1.5N0 IND Monthly Silva Property 264 1.5 RPV1.8N0 IND Monthly Silva Property 268 1.8 Hell Water RNHl.6GO IND Quarterly Rancho Seco Reservoir 120 1.6 RWHO.8D0 CON Quarterly Marciel Ranch 75 0.8 l

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SECO NUCLEAR GENERATING STATION TABLE II-1 (Continued)

NEH SAMPLE LOCATIONS Sample Type Sample Collection Description of Location '

Identification Class Freauency Location Name/Dearees/ Miles Mud and Silt RMSO.3M0 IND Quarterly Effluent Discharge 250 0.3 RMSO.7h0 IND Quarterly Hater Sump 265 0.7 RMSl.8HO IND Quarterly Confluence of Clay l

and Hadselville Creeks 272 1.8 RMS2.2N0 IND Quarterly Hadselville Creek above Clay Station Rd 260 2.2 RMS3.7N0 IND Quarterly Laguna Creek at 1 Folsom South Canal 260 3.7 RMSS.4M0 IND Quarterly Laguna Creek at Laguna Rd 265 5.4 RMS10.M0 IND Quarterly Laguna Creek at McKenzie Rd 259 10.0 RMS12.G0 CON Quarterly Comanche Reservoir 130 12.0 Crawfish RCF0.6M0 IND Quarterly Site Boundary 245 0.6 RCF0.7N0 IND Quarterly Hater Sump 265 0.7 RCF3.7N0 IND Quarterly Hadselville Creek at Folsom South Canal 260 3.7 RCF10.M0 IND Quarterly Laguna Creek at McKenzie Rd 259 10.0 l

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• ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 '

RANCHO SECO NUCLEAR GENERATING STATION O '

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l TABLE . I'.-l (Continued)

NEW SAMPLE LOCATIONS Sample Type Sample Collection Description of Location Identification Class Frecuency Location Name/Dearees/ Miles Garden Vecetables: SA - Harvested at least Semi-Annually MTGS - Monthly Throughout the Growing Season RLVO.5A0 IND SA-MTGS Site Garden North 5 0.5 RLV0.6MO IND SA-MTGS Site Garden at Site Boundary, Irrigated with 245 0.6 Clay Creek Hater Honey l

RSHX.XNO IND SA Nearest hives to the West Beef Tissue RBFX.XNO IND SA Beef tissues from cattle raised west of the site Beef Thyroid RBTX.XN0 IND SA Thyroid gland from cattle raised west of the site Pheasant RPHX.XN0 IND Annually Pheasant taken west of the site ILQ Quarterly East of Site, Ione Prison 9.5 O

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SECO NUCLEAR GENERATING STATION V

III. DATA INTERPRETATIONS AND CONCLUSIONS HDTE: Reportable levels are found in Table B-3.

Reportable levels are levels at which the NRC requires notification and at which CEP is required to notify SMUD.

A. Air Samoles Air samp*es were collected weekly from eight fixed monitgr locations. Typical volumes range from 20000 to 24000 ftJ.

The air flow is directed through a particulate filter followed by a radioiodine cartridge (activated charcoal). The volume of air sampled is measured by a dry gas meter attached downstream of each sampler. The purpose of these samples is to monitor the l gaseous effluent pathways for iodine and particulates.  !

Each week the particulate filters are analyzed for gross alpha and beta activity and are composited quarterly and analyzed for gamma isotopes. Additionally, individual samples are analyzed for gamma isotopes when the gross beta levels exceed 10 times ,

the control sample value. The charcoal cartridges are analyzed I for Iodine 131.

Gross Beta Analysis Filter type: Gelman Glass Fiber Filter Type AE #61631 47 mm diameter 99.9% efficiency at 0.3 m  ;

(DOP) l Counting System: Beckman Hide Beta II Thin Hindow Gas Flow I Proportional Counter  ;

or Tennelec LB 5100 Low Background System or Berthold LB 770 Beta Efficiency: (Sr-90) 60% (Beckman)

(Sr-90) 51% (Tennelec)

(Sr-Y-90) 45% (Berthold)

(Cs-137) 43% (Berthold)

Count Time: 100 min.

Sample Period: Heekly (168 hrs.)

Lower Limit of Detection (LLD): 0.002 pCi/m3 0 13

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 p RANCHO SECO NUCLEAR GENERATING STATION L)

III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)  ;

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A. Air Samoles (Continued)

Gross Aloha Analysis i l

Filter type: Gelman Glass Fiber Filter Type AE

1. 61631 47 mm diameter 99.9%

efficiency at 0.3 pm (D0P).

Counting System: Beckman Hide Beta II or Tennelec LB 5100 or Berthold LB 770.

Alpha Efficiency: (Pu-239) 40% Beckman 21% Tennelec l 33% Berthold Count Time: 100 minutes l Sample Period: Heekly (168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />)

Lower Limit of l Detection (LLD): 0.005 pCi/m3, Gamma Soectrometry Analysis Filter type: Gelman Glass Fiber Filter Type AE l

1. 61631 47 mm diameter 99.9%

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efficiency at 0.3 pm (00P).

Counting System: 2 GeLi and 3 intrinsic Germanium detectors Spectroscopy System: Nuclear Data. Computer Based Gamma Spectroscopy System Count Time: 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Sample Period: Quarterly-Composites of.the weekly air particulate filters are counted in a Marinelli beaker, j Lower Limit of Detection (LLD): Cs-137 - 0.001 pCi/m3, Reportable Levels: Cs-107 - 20 pCi/m3 Cs-134 - 10 pCi/m3 O + 14

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l ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l 1987' I p RANCHO SECO NUCLEAR GENERATING STATION  !

III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

A. Air Samoles (Continued)

Iodine - 131 Analysis Method 1 Filter type: Science Applications, Inc.

Radiciodine Sampler BG 300 Impregnated Charcoal 1

Counting System: Intrinsic Germanium and GeLi j Spectroscopy System: Nuclear Data Computer Based Gamma Spectroscopy System Calibration Source: I-131, deposited in the first 5 mm of charcoal cartridge Count Time: 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Sample Period: Heekly  !

Lower Limit of Detection (LLD): 0.01 pCi/m3-0.02 pC1/m3a Reportable Level: 0.9 pCiIm3 Method 2 (Alkaline Leach Concentration)

Filter type: Same as above (Hethod 1)

Counting System: Beckman Low Beta II Thin Hindow Gas Flow Proportional Counter Calibration Source: I-131, deposited in the first 5 mm of charcoal Count Time: 100 min.

Sample Period: Performed on weekly basis. Performed only if method 1 analysis reachas the reportable level of 0.9 pCi/m3 Lower Limit of Detection (LLD): 0.004 pC1/m3,

.s *0.01 pCi/m3 if analysis is performed within 24 to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. 0.02 pCi/m3 if analysis is performed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />.

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1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 es RANCHO SEC0 NUCLEAR GENERATING STATION U

III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

A. Air Samoles: (Continued)

Results Gross Beta Gross Beta activities for the year 1987 ranged from 0.005 '

to 0.055 pCi/m3 Mean quarterly averages were consistent with previous years data.

Gross Beta activities for the year 1986 ranged from 0.006 to 0.142 pCi/m3 The 1986 data reflects the increased activity due to the Soviet Union's Chernobyl accident.

Gross Aloha No gross alpha activities were detected during the year 1987. Gross alpha activities ranged from 0 to 0.007 pC1/m3 during 1986. Hith the exception of one sample in the 4th quarter of 1984 (0.005 pCi/m3), no otiier gross alpha activities have been found in air particulates since the date of initial criticality.

C'%d Gamma Soectrometry The air particulate composite samples for.the year 1987 showed no gamma activity of interest (i.e., fission-corrosion products). This is consistent with the 1986 results.

Iodine 131 Radiciodine was detected at one air sample location during the fourth guarter of 1987. The indicated activity was 0.009 pCi/m3 During 1986, radioiodine activity ranged from 0 to 0.689 pCi/md.

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ANNUAL PADI0 LOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SEC0 NL' CLEAR GENERATING STATION v

III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

A. Air Samoles (Continued)

Summarv 1st Quarter Gross beta activity during the first quarter 1987 ranged from a low of 0.005 pCi/m3 to a high of 0.043 pC1/m3, The mean gross beta activities during the first quarter ranged from 0.020 to 0.023 pci/m3 The collection period of highest mean gross beta activity during the first quarter of 1987 was 12/29/86 to 01/05/87 (0.039 pCi/m3). The collection period of lowest mean gross beta activity was 3/16/87 to 3/23/87 (0.007 pCi/m3),

i 2nd Quarter Gross beta activity during the second quarter of 1987 l ranged from 0.007 pCi/m3 observed at 5 stations on 1 06/22/87 to a high of 0.035 pCi/m3 on 05/18/87.

(~% The mean quarterly gross beta activitieg during the second

% quarter ranged from 0.014 to 0.19 pCi/m5 The collection periods of highest mean gross beta activity during the second quarter were 04/20/87 to 04/27/87 and 05/04/87 to 05/11/87 (0.025 pCi/m3). The collection period of lowest mean gross beta activity was 06/15/87 to 06/22/87 (0.008 pCi/m3),

3rd Quarter Gross beta activity during the third quarter of 1987 ranged from 0.005 to 0.038 pCi/m3 The mean quarterly gross beta activities during the third guarter ranged from 0.17 pCi/m3 at 3 stations to 0.20 pCi/m3 at 2 stations. The collection period of highest mean gross i beta activity during the third quarter of 1987 was 1 09/14/87 to 09/21/87 (0.031 pCi/m3). The collection period of lowest mean gross beta activity was 06/29/87 to 07/06/87 (0.007 pCi/m3),

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SECO. NUCLEAR GENERATING STATION v I I

III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

A. Air Samoles (Continued) 4th Quarter 1 Gross beta activity during the fourth quarter of 1987 ranged from 0.13 to 0.55 pC1/m3 The mean quarterly gross beta activities during the fourth quarter ranged from 0.029 pCi/m3 at 3 stations to 0.32 pCi/m3 at 3 )

stations. The collection period of highest mean gross l beta activity during the fourth quarter oi 1987 was I 10/12/87 to 10/19/87 (0.050 pCi/m3). The collection l period of lowest mean gross beta activity during the fourth pCi/m3) quarter of 1987 was 12/7/87 to 12/14/87 (0.015 One sample located at SHUD headquarters indicated radiciodine activity of 0.009 pC1/m3 This activity could not be due to Rancho Seco, since the plant was not in operation during 1987.

In summary, the radioactivity detected via the airborne p)

L radioactivity monitoring network at Rancho Seco in 1987 Iwas well below any of the regulatory action levels.

Mean weekly gross beta activity observed during 1987 is consistent with recent historical data with the exception of the second quarter 1986 with increased activity due to the Soviet Union's Chernobyl Accident, and the China weapons fallout detected in late 1981 and early 1983.

Figure i shows the mean weekly gross beta activity from 1980 through 1987. No gross alpha activities have been detected in air particulate samples in 1987.

No gamma activity of interest (corrosion-fission products) was detected in the air particulate quarterly composite samples in 1987. i

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• l ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

! 1987 RANCHO SECO NUCLEAR GENERATING STATION FIGURE II-1 GROSS BETA IN AIR PARTICULATES MEAN HEEKLY ACTIVITY Figure II-1 is a graph of the mean weekly Gross Beta activity in air from 1980 through 1987.

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SECO NUCLEA7 GENERATING STATION f3 U

III. DATA INTERPRETATIONS ANC CONCLUSIONS (Continued)

B. Thermoluminescent Dosimeters (TLD)

Thermoluminescent dosimeters were exchanged on a quarterly basis from 64 fixed monitor locations. Forty three (43) of these locations were established in the fourth quarter of 1980, location 63 was established in the third quarter of 1981, and location 64 was established in the fourth quarter of 1987. Each location has two TLD. badges each with three (3) calcium sulfate chips at each location.

The purpose of these dosimeters is to monitor direct radiation and provide data for analysis for each sample site. The results of the analyses are compared to the effects of Rancho Seco Operations.

TLD Analysis System: Matsushita Electric Industrial  ;

Company (Panasonic Distributor)

System Model: U0-702 Dosimeter Model: 804 Phosphor: CaSO4 :Tm Phosphors / Dosimeter: 3 Dosimeters / Location: 2 Readout Period: Quarterly 26 days Calibration Source: NBS Traceable Cs-137 Statistical Precision: 22o Outlier Rejection: "R" Ratio Technique C

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 i g~s RANCHO SEC0 NUCLEAR GENERATING STATION l

'd III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

B. Thermoluminescent Dosimeters (TLD) (Continued) )

Results i l

TLDs were collected from 63 sample locations during the first three quarters of 1987 and from 64 sample locations during the fourth quarter of 1987. TLD collection from 12 l sample locations were missed in 1987. i The TLD data is consistent with previously accumulated data. Results for the year 1987 show no elevated activity. l Table III-1 shows the sample locations and the actual values of the TLDs for all locations.  ;

The annual mean value is 15.93 mrem. The values ranged ,

from a low of 10.75 mrem at location 43 which is 1.8 miles l southeast of the site to a high of 27.12 mrem at location l 52 which is 19 miles east of the site at the Jackson Civic l Center.

pg The location with the highest annual mean value is at V sample site numbcr 41, which is 1.8 miles northeast of the site. Site 41's mean value was 22.19 mrem.

The mean annual exposure rate for all locations was 6.82 pR/hr.

Quarterly mean exposure rates were:

- 1st quarter 6.80 pR/hr

- 2nd quarter 6.60 pR/hr

- 3rd quarter 6.54 pR/hr

- 4th quarter 7.35 pR/hr Site specific values ranged from 4.8 pR/nr at location 43 to a high of 11.1 pR/hr at location 31, 3.7 miles west of the site.

O 22

• ANNUAL RADIOLOGICAL ENVIRONMENTAL' OPERATING REPORT 1987-RANCHO SECO NUCLEAR GENERATING STATION O

4

. Table III-1 presents the results of the thermoluminescent dosimeters for 'all locations in mrem and also the exposure rate in pR/hr.

W O

3 i

l O

• 23

• i

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-,,-,wn---- ..---wnmr-m~~- - - - -

N ANNUAL RADIOLOGICAL ENVIL U TAL OPERATING REPORT V 1987 RANCHO SECO NUCLEAR GENERATING STATION j

TA8tE III-1 Page 1 of 4 THERM 0 LUMINESCENT DOSIMETER RESULTS 1937 FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER LOCA- Total Exposure Total Exposure Total Exposure' Total Exposure TION DISTANCE Exposure Rate" Exposure Rate" Exposure Rate

• Exposure Rate

• NO. (HILES) DIRECTION LOCATION DESCRIPTION (mren) (pr/hr) (crem) (pr/hr) (mrem) (ur/hr) (mrem) fur /hr) 1 - N Perimeter Fence 18.13 6.8 16.80 7.9 16.67 7.1 16.93 8.0 2 -

E Perimeter Fence 17.42 6.4 12.60 5.9 16.65 7.0 15.73 7.4 3 - W Perimeter Fence 26.22 9.8 17.55 8.3 21.50 9.0 21.83 10.3 4 -

SW Perimeter Fence 20.25 7.6 16.22 7.9 16.15 6.8 16.30 7.7 5 -

SE Perimeter Fence 16.25 6.0 12.35 5.8 14.43 6.1 19.35 9.2 6 -

Visitors Center 15.88 6.0 11.67 5.4 12.76 5.6 13.28 6.3

l 7 Route 104 Entrance Missing 17.68 8.2 14.77 6.2 14.77 6.9 8 6 NW 15.35 5.9 15.90 7.5 15.88 7.0 15.33 7.0 9 22 NE SMUD Headquarters 15.02 5.6 11.70 5.5 14.45 6.5 12.55 5.7 l

10 17 SW Lodi 27.50 10.2 15.60 7.3 17.45 6.5 18.28 8.4 1 11 0.25 S 20.52 7.8 12.90 6.0 17.28 7.7 14.87 6.8 12 11 E Ione 20.30 7.6 11.42 5.3 12.62 5.5 12.67 5.8 13 10 W West Milk Station 16.10 6.0 10.95 5.1 13.82 6.1 Missing 14 11 SW Galt 20.32 7.6 13.38 6.2 14.93 6.6 15.75 7.2 15 11 SW Camanche Reservoir 15.50 5.8 12.92 6.0 14.92 6.6 15.23 7.0 16 0.65 W Clay 14.07 5.4 11.33 5.4 16.27 7.2 16.48 7.7 17 9 SW Southwest Milk Station Missing 14.85 7.3 20.78 9.3 18.93 8.7 18 8 NE 14.60 5.7 10.90 5.1 12.63 5.6 12.35 5.7

• 24

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O ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT O O i

1987 kANCHO SECO NUCLEAR CENERATING STATION TABLE III-1 Page 2 of 4 THERM 0 LUMINESCENT DOSIhcTER RESULTS

- 1987 FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER LOCA- Total Exposure Total Exposure Total Exposure Total Exposure TION DISTANCE Exposure Rate

• Exposure Rate" Exposure Rate

• Exposure Rate

• NO. (MILES) DIRECTION LOCATION DESCRIPTION (arem) fur /hr) (mree) (ur/hr) (mrem) (ur/hy ) (mrem) fur /hr) 19 1 SE 17.8 6.8 14.2 6.6 12.82 5.6 19.63 9.2 20 1.5 WSW 15.1 5.7 13.55 6.2 13.82 6.2 12.18 5.7 21 1.7 SW 15.1 5.7 13.8 6.3 13.13 5.9 12.92 6.0 22 1.8 S 16.3 6.2 17.65 8.1 16.92 7.6 14.9 6.7 23 1.8 SSW 16.3 6.2 13.45 6.2 14.27 6.4 14.15 6.4 24 1.8 SSE 14.6 5.5 11.52 5.3 13.68 6.1 12.08 6.5 25 3.8 SW 16.4 6.3 12.98 6.0 13.8 6.1 14.1 6.5 26 3.9 SSW 14.3 5.5 12.48 5.8 13.05 5.8 Missing 27 3.6 S 15.6 6.0 Missing 12.77 5.7 13.08 6.0 s .

28 3.7 SSE 15.7 6.0 14.27 6.6 16.9 7.5 14.63 6.7 29 4.2 S 16.35 6.3 15.45 7.2 16.33 7.2 16.92. 7.7 30 7.4 WSW Herald Fire Station 16.9 6.3 . 12.4 5.8 15.08 6.6 16.2 7.6 i

31 3.7 W 18.75 7.0 12.02 5.5 14.03 6.3 23.62 11.1 32 4.8 WNW 17.63 6.6 13.13 6.0 14.57 6.5 20.37 9.5 33 3.8 WSW 16.2 6.1 12.5 5.7 13.25 5.9 15.58 7.4 34 3.8 NW 19.62 1.3 13.43 6.4 18.3 7.7 17.47 8.4

35 1.9 W 18.13 6.9 13.53 6.2 20.2 9.1 16.77 7.8 36 1.6 WNW 16.75 6.3 11.82 5.4 17.88 8.0 15.58 7.1

• 25

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l' 1

d ANNUAL RADIOLOGICAL ENVIn...,JTAL OPERATING REPORT 1987 RANCHO SECO NUCLEAR GENERATING STATION TABLE III-1 Page 3 of 4 THERM 0 LUMINESCENT 00SIMETER RESULTS 1987 FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER ,

i LOCA- Total Exposure Total Exposure Total Exposure Total Exposure TION DISTANCE Exposure Rate

• Exposure Rate

• Exposure Rate

• Exposure Rate

• i . NO. (MILES) DIRECTION LOCATION DESC!!IPTION (arem) (pr/hr) (mree) fur /hr) (mrem) (ur/hr) (mrem) (ur/hr) 37 1.9 NW 16.6 6.3 20.25 9.3 16.35 7.3 15.4 7.0 ,

38 1.6 NNW 16.6 6.3 17.8 8.2 15.43 6.6 18.82 8.7 39 1.5 NNE 16.2 6.0 14.8 6.9 14.02 6.0 16.82 7.8 40 1.5 N 14.4 5.4 12.23 5.7 13.27 5.7 14.4 6.7 41 1.8 NE 26 9.7 19.93 9.2 21.92 9.4 20.9 9.7 42 4. 4 SE Missing 14.37 6.6 14.2 6.4 14.73 6.8 43 1.6 SE 14.3 5.5 10.75 4.8 16.58 7.3 12.52 5.9 44 1.4 E 18.7 7.1 14.08 6.5 12.43 5.5 12.87 6.0 45 14 ESE 19.9 7.6 15.37 7.1 13.22 5.8 14.17 6.6 46 1.3 ENE 21.45 8.0 15.77 7.2 15.37 7.0 15.18 7.1 47 3 NE 17 6.3 17.63 8.1 18.3 8.3 15.42 7.1 ,

48 3.5 ENE 16.1 6.0 15.17 6.7 Missing 16.37 7.5 49 3.1 E 21.5 8.0 14.17 6.2 14.67 6.9 14.47 6.6 50 3.5 ESE 25 9.3 15.98 7.0 22.75 10.8 16.57 7.7 51 11 E Preston School of Industry 20.12 7.5 12.12 5.6 13 5.8 12.78 6.0 52 19 E Jackson Civic Center 27.12 10.0 16.75 7.8 19.33 8.5 T9.92 9.2 53 11 SE Camanche Reservoir 21.62 8.0 15.95 7.4 22.17 9.8 17.2 7.9 54 10 S Clements 18.25 6.8 17.82 8.3 Missing 16.45 7.7

• 26

• ANNUAL RADIOLOGICAL ENVI TAL OPERATING REPORT RANCHO SECO NUCLEAR GENERATING STATION TABLE III-I Page 4 of 4 i THERM 0 LUMINESCENT DOSIMETER RESULTS 1987 ,

1 FIRST QUARTER SECOND QUARTER THIRD QUARTER FOURTH QUARTER LOCA- Total Exposure Total Exposure Total Caposure Total Exposure TION DISTANCE Exposure Rate

• Exposure Rate

• Exposure Rate" Exposure Rate" 1

NO. (MILES) DIRECTION LOCATION DESCRIPTION (mrem) (ur/hr) (mrem) (pr/hr) (mrem) (pr/hr) (arem) (ur/h r) 55 8 WNW Dillard School 17.37 6.5 12.3 5.6 14 6.3 16.33 5.8 56 4.6 NNW 16.8 6.3 13.08 6.3 17.77 7.5 16.85 8.1 57 7.6 N 18.98 7.2 13.68 6.6 14.27 6.1 18.03 8.6 i

58 6.6 NNE Missing 18.37 8.4 Missing Missing 59 11.3 NNW Sloughhouse Post Office 21.9 8.1 15.75 7.5 17.2 7.2 15.72 7.4 60 10.6 N Rancho Murieta 21.13 7.9 12.67 6.0 14.42 6.1 14.38 6.8

~

13 WNW Elk Grove Cemetery 17.1 6.3 13.77 6.5 15.05 6.7 14.47 6.7

! 61 62 11 Su Gal t 16.97 6.3 13.68 6.3 14.02 6.2 Missing 63 l' E 15.53 5.8 13.6 6.3 13.52 6.0 13.85 6.3 64 9.5 E Ione Prison 15.45 7.1 I

j

• The exposure rates are expressed in micro-r/hr (pr/hr).

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+ 27 +

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l_ . ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING' REPORT

! 1987 RANCHO SECO NUCLEAR GENERATING STATION

[

l.

e Table III-2 gives the individual locations for all Thermoluminescent Dosimeters.

1 a

1 a

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e *W me w , - n <*er ,s w w - w -w __ww- ,, ,, ., ,

, ANNUAL RADIOLOGICAL ENVI AL OPERATING REPORT RANCHO SECO NUCLEAR GENER% TING STATION TLD LOCATIONS

, TABLE III-2

$ SAMPLE COLLECTION ANALYSIS ANALYSIS REPORTABLE TYPE LOCATION" FREOGENCY ANALYSIS FREQUENCY SENSITIVITY UNITS LEVELS UNITS

]

Direct Radiation TLD's N. Perimeter Q Gamma by Q mrge!

3 Elements per Fence /1 theime- qtr

package, 2 Pkg. E. Perimeter luminescence i per location Fence /2 i W. Perimeter i Fence /3 i SW. Perimeter Fence /4 4

SE. Perimeter Fence /S Visitor Center /6 Route 104 Entrance /7 ,

NW of Site 6 mi/8 NE of Site Sacra. ,

! 22 mi/9 -

l SW of Site Lodi 4 17 mi/10 4 S of Site l .25 mi/11 1 E of Site, Ione 11 mi/12 I

W of Milk Station l 10 mi/13 i SW of Site, Galt

! 11 mi/14 SE of Site, Cowanche Res.

j 11 mi/15

}

W of Site, Clay, i .S mi/16 SW Mill Stat.

j 9 mi/17 y

NE of Site, 8 mi/18

! SE of Site, I cl/19 WSW of Site, 1.5 mi/20

SW of Site, 1.7 mi/21 Q - Quarterly .

l "/n = Map Location 1

]

• 29 +

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l / APMUAL RADIOLOGICAL ENVIRCZ 1987 AL OPERATING REPORT d E

RANCHO SECO NUCLEAR GENERATING STATION TLD LOCATIONS TABLE III-2 l

SAMPLE COLLECTION ANALYSIS ANALYSIS REPORTA8LE TYPE LOCATION

• FRE00CNCY ANALYSIS FRE00ENCY SENSITIVITY UNITS LEVELS UNITS Direct Radiation S of Site.

I TLD's 1.8 mi/22 Continued SSW of Site.

1.8 mi/23

$$E of Site, 1.8 mi/24 5 SW of Site, a 3.8 ml/25 SSW of Site, l 3.9 mi/26 5 of Site, l 3.6 mi/27 &

' SSE of Site, 1 3.7 mi/28 5 of Site.

4.2 mi/29 r WSW of Site, 7.4 mi/30

3. W of Site.

, 3.7 mi/31 l WNW of Site, 4.8 mi/32 '

i WSW of Site, i 3.8 mi/33 1 NW of Site.

3.8 mi/34 W of Site, 1.9 mi/35

• WNW of Site.

1.6 mi/36 i

NW of Site,

, 1.9 mi/37 NNW of Site,

, 1.6 mi/38 NNE of Site, i 1.5 mi/39 4 N of Site,

) 1.5 mi/40 j NE of Site.

4 2 mi/41 SE of Site,

) 4.4 mi/42 j SE of Site, 1.6 mi/43 J

j Q - Quarterly

• /n - Monthly .

• 30 --

I

ANNUAL RADIOLOGICAL ENVIRC( AL OPERATING REPORT 1987 " f RANCHO SECO NUCLEAR GENERATING STATION i

TLD LOCATIONS TABLE III-2 COLLECTION ANALYSIS ANALYSIS REPORTABLE 4 SAMPLE LOCATION" FRE00ENCY ANALYSIS FRE0VENCY SENSITIVITY UNITS LEVELS UNITS TYPE Direct Radiation E of Site.

TLD's 1.4 al/44 Continued ESE of Site, 1.4 mi/45

) ENE of Site,

1.3 mi/46 NE of Site, 3 mi/47

• ENE of Site,

! 3.5 mi/48 E of Site, 3.1 mi/49 ESE of Site, '

3.5 mi/50 E of Site, 11 mi/51 E of Site,

' 19 mi/52 i SE of Site, 11 mi/53

S of Site, 1- 10 mi/54

! WNW of Site, 4

8 mi/55 NNW of Site, 4.6 mi/56 N of Site, 7.6 mi/57 NNE of Site, 6.6 mi/58 '

NW cf Site, l 11.3 mi/59 N of Site, 10.6 mi/60 WNW of Site, 13 mi/61 4

SW of Site, i

11 mi/62 E of Site, I mi/63 2 ~ E of Site, c

9.5 ml/64 Q - Quarterly

• /n - Map Location

• 31

• ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING kEPORT l 1987 l RANCHO SECO NUCLEAR GENERATING STATION O

III. DATA INTERPRETATIONS AND CONCLUSIONS (Continuedi C. Alcae l In 1987 algae samples were taken from eight locations chosen to ,

reflect liquid effluent releases to the environment. The locations are at the liquid effluent outfall at the site boundary west of the plant, Hadselville Creek near the Folsom South Canal, the site reservoir, Laguna Creek, the confluence of Clay and Hadselville Creeks, and a sump 0.7 miles west of .

I containment.

Samples are scheduled on a quarterly basis but are obtained on an as available basis.

Grab samples of algae are a mixture of algaes including but not limited to the following:

Diatoma, Gonphoenema, Nitzschia, Spirogyra, Synedra, Fragelaria, Navicula, Microspora, Chlorococeum, Vethrix, Zygnema, and i Tabillaria Varies.

Algae samples are analyzed for gamma emitting nuclides.

Gamma Soectromettv Analysis Method: Wet sample, Marinelli Beaker Counting System: Intrinsic Germanium and GeLi  ;

Spectroscopy System: Nuclear Data Computer based Gamma Spectroscopy System l

Results  :

i During 1987, thirty six (36) samples were collected.

Algae samples are collected and analyzed because they have the l ability to concentrate radionuclides such as Cs-137 and Cs-134. I Algae are sensitive indicators of stream effluents even though they are not part of the direct food chain.

l O + 32

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, .__ - - m. ,, ,_ . - . - . - - , , . - _ - - , . , -

.w-

l ANNUAL RADICLOGICAL ENVIRONMENTAL OPERATING REPORT ^ '

1987

/l RANCHO SECO NUCLEAR GENERATING STATION NJ ,

III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

C. Algae (Continued)  !

l Gamma :pectroscopy of algae samples resulted in identifying the following gamp'r emitters: Cs-134 with a range of less than detectable to 0.441 pC1/g, Cs-137 with a range of less than the lower limit of detection (LLD) to 2.06 pCi/g, arid Co-60 with a range of less than detectable l to 0.433 pC1/g. l l

Gamma spectroscopy of algae samples during 1986 showed '

levels of gamma emitters which are greater than those l fourid in 1987. In 1987 the Cs-134 levels ranged from i i 0.545 to 4.78 pCi/g, Cs-137 levels ranged from 3.11 pCi/g l to 18.2 pCi/g (dry), and Co-60 levels ranged from 1.01 to ,

6.59 pCi/g. l

. Conclusion Radioactivity detected in algae samples continu9d to l decrease but was still measurable in 1987. l O  !

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t ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 -

RANCHO SECO NUCLEAR' GENEf!ATING STATION l d,G  !

i III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

D. Animal Vegetation  !

Animal vegetation was collected from eight locations on a I monthly basis. The vegetation sampled is representative of the variety of grasses found on local-putures where .

milk and beef animals feed. The samples are analyzed for i gamma emitting nuclides. ,

Gamma Soectrometry Analysis  !

Sample Type: Dry sample in Marinelli Beaker i

Detector: Intrinsic Germanium and GeLi  :

Spectroscopy System Nuclear Data Computer Based Spectroscopy-System Results i O. During 1987, 96' routine animal vegetation samples were V collected and analyzed by gamma spectrometry.

Gamma activities ranged from less than the lower limit of j detection (LLD) to 1.724 pCi/5 (wet) during 1987. The  :

only isotope identified was Cs-137 with a maximum value of ,

1.724 pCi/g (wet).  ;

In 1986, gamma activities ranged from sess than the lower l limit of detection (LLD) to 3.60 pCi/g (dry). The  !

isotopes indicated in 1986 and their maximum values were as follows: i Cs-134 0.95 pCi/g (dry)  :

3.60 pCi/g (dry)

Cs-137

, Co-60 0.72 pC1/g (dry)

Conclusion Routine sample analyses indicate activities which are less than previous years data. Analysis of samples from the Clay Creek area indicate the uptake of radionuclides from 3

past plant releases which were exnected based on the previous LLNL studies.

O b

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l ANNUAL RADIOLOGICAL ENVIRONMENTA1. OPERATING REPORT l

~

1987-RANCHO SEC0 NUCLEAR GENERATING STATION (s

.]

III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued) i E. Edible Aauatic Fauna '

E11t1 Fish samples are tak.en at nine locations.

Samples were collected by net at quarterly intervals. I Samples are analyzed routinely for gross beta,  !

potassium-40 and gamma emitting nuclides.

Gross Beta Analysis Method: Dried at 110*C for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, ashed, dissolved in dilute HNO3-Counting System: Beckman Hide Beta II Thin Hindow Gas Flow Proportional Counter. j Lower Limit of Detection (LLD): 0.02 pCi/g K-40 is subtracted.

3 (V Potassium-40 (K-40) Analysis Method: Dried at 110*C for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, ashed, dissolved in dilute HNO3 .

Analyzed by atomic absorption, K-40 taken as 1.7 dpm per mg K.

Lower Limit of Detection (LLD): 0.001 pCi/gm.

Gamma Soectrometry Analysis Method: Dried at 110*C for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, ashed, dissolved in dilute HNO3-Counting System: Intrinsic Germanium and GeLi Spectroscopy System: Nuclear Data Computer Based l Spectroscopy System O

35 *

, - . . - _ _.- ,_ -,.-.__v.. __ . _ - - l

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 '

RANCHO SECO NUCLEAR GENERATING STATION f

III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

E. Edible Aauatic Fauna (Continued)

Results ELsh The routine collection of fish from the Clay Creek effluent stream was initiated in 1985.

Preoperational data are too heavily influenced by atmospheric weapons testing to allow meaningful comparison. During 1987 thirty-nine fish samples were collected and analyzed.

During 1987 the gross beta less potassium-40 concentration ranged from 0.89 pCi/g to 9.36 pCi/g. The concentrations are consistent with the past few years.

Potassium-40 concentrations in fish ranged from 2.94 to 21.32 pC1/g (dry) in 1987. During 1986 these levels ranged 2.76 to 15.4 pCi/g.

Gamma spectrometry resulted in identifying the folic, wing '

gamma emitters: Cs-134 with a range of less than detectable to 0.93 pC1/g, and Cs-137 with a range of less than the lower limit of detection (LLD) to 5.94 pC1/g.

ELQ91 1

Six (6) frog samples were collected during the first thre; j quarters of 1987. Samples were analyzed for gamma emitting nuclides. i Samma Soectrometry Analysis Methed: Dried at 110*C for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, ashed, dissolved in dilute HNO3-Counting System: Intrinsic Germanium and GeLi ,

Spectroscopy System: Nuclear Dita Computer Based <

Spectroscopy System l

O

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i ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SECO NUCLEAR GENERATING STATION III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

E. Edible Aauatic Fauna (Continued)

Results One frog sample collected on August 20, 1987 showed Cs-134 and Cs-137 activi ty. The levels were Cs-134 at 0.13 pC1/g (dry) and Cs-137 at 0.57 pCi/g (dry).

Cr,nclusion The concentrations of radionuclides in edible aquatic fauna are still evident from previous plant releases. The levels are less than detected in 1985 and 1986 and should continue to decrease in 1988.

O i

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

, 1987 T<ANCHO SECO NUCLEAR GENERATING STATION ~

III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

F. Bl.lt

. Fresh milk samples were collected on a weekly basis from four dairies during 1987. The samples were analyzed for iodine-131 and, commencing with the 1st quarter (OT./24/87), gamma emitting nuclides.

Monthly analysis of milk samples for Sr-90 was discontinued in the first quarter to conform with Technical Specification requirements.

Radiciodine Analysis Analysis Period: Weekly (within 48 hrs, of collection) l Method: Anion Exchange, Count AgI beta Carrier: Standardized iodine Resin: Amberlite (IRA-400) Anion O

V Exchange Time: I hour Counting System: Beckman Hide Beta II Thin Hindow Gas Flow Proportional Counter Efficiency: 43% Beta Count Time: 100 min 1 l

Lower Limit of I Detection (LLD): 0.5 pCi/l Strontium-90 (Sr-90)

Analysis Period: Monthly (January and February only)

Method: Cation Exchange, Count Yttrium Oxalate for Y-90 Carrier: Standardized Yttrium Resin: Dowex (50W-V8) Cation i O 38 l

l i

i ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SECO NUCLEAR GENERATING STATION III. DATA IN1F.RPRETATIONS AND CONCLUSIONS (Continued)  ;

F. tillh (Continued)

Exchange Time: 30 minutes Counting System: Beckman Hide Beta II Thin Hindow Gas Flow Proportional Counter Efficiency: 601. Beta (Sr-Y)

Count Time: 100 min Lower Limit of Detection (LLD): 0.05 pCi/g Results During 1987, 208 milk samples were collected.

I-131 and gamma emitting nuclides were not detected in samples collected during 1987.

Samples collected in January and February for Sr-90  ;

analysis indicated no activity above the lower limit of detection.

Conclusions Milk samples in 1987 did not show any effect from Rancho Seco.

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ANNUAL RADIOLO3ICAL ENVIRONMENTAL OPERATING REPORT "

1987 O

Q RANCHO SECO NUCLEAR GENERATING STATION III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

G. Mud and Silt Samples were routinely taken at ten different locations on a quarterly basis. Seven additional mud and silt locations were added to the sampling program to. increase the surveillance of the liquid effluent pathway.- Samples '

were analyzed for gross beta and gamma emitting nuclides.

Gross Beta Analysis Sample Preparation: Samples are dried at 110'C and leached with nitric acid, then ashed and placed in a 2 inch stainless steel planchet for counting.

Counting Systea: Beckman Wide. Beta II Thin Hindow Gas i Flow Proportional Counter or a Tennelec LB 5100-low background j simultaneous counter.

Efficiency: 60% Beta, Sr-Y (Beckman)

O 51% Beta, Sr-Y (Tennelec)

Lower Limit of Detection (LLD): 0.05 pC1/g Gamma soectrometry Analysis Sample Preparation: Same as gross beta analysis above Counting System: Intrinsic Germanium and GeLi Spectroscopy System: Nuclear Data Computer Based i Spectroscopy System l

I 1

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• ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987

/ RANCHO SECO NUCLEAR GENERATING STATION

. V) .

III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

G. Hud and Silt (Continued)

Results During 1987, forty seven (47) mud and silt samples were taken.

Gross Beta ranged from 0.19 to 8.41 pCi/g (dry). Gamma activities observed included Cs-134, Cs-137, Co-60, and Hn-54. - Cs-137 activities (the primary gamma emitter) ranged from less than detectable to 15.8 pC1/g (dry). The range of Cs-134 was from less than the lower' limit of detection (LLD) to 2.16 pCi/g (dry) and Co-60 ranged from less than detectable to 2.74 pC1/g (dry). Four samples had concentration levels of Mn-54 ranging from 0.024 to 0.109 pCi/g (dry).

Conclusions Levels during 1987 were comparable to samples from 1985 and 1986. The low levels combined with limited preoperational data make S comparison unmeaningful. This O- is especially true since the preoperational data had high St-90 level due to nuclear weapons testing. I-131, Nb-95, Cr-51, Ag-110m, Zn-65. Rh-106, Be-7, Zr-95 were observed in 1984 but were not detected during 1985 and 1986.

l 4

l l

41

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l ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ,

1987 l Q

v RANCHO SECO NUCLEAR GENERATING STATION l i

III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued) )

H. Rabbits ,

i Two rabbit samples were collected for each of the first three quarters in the vicinity of Rancho Seco. The ,

samples were disected and analyzed for gamma emitting l nuclides.

Gamma Soectrometry Analysis ':

Method:- Ory sample, Marinelli Beaker Counting System: Intrinsic Germanium and Geli Spectrometry System: Nuclear Data Computer Based Spectroscopy System Results No evidence of radionuclide concentrations were detected  :

in the 6 rabbit samples during 1987.

Conclusion i Based on limited data, it does not appear radionuclide concentrations in rabbits are affected by Rancho Seco Operations. I 1

l l

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1 1

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 O

V RANCHO SEC0 NUCLEAR GENERATING STATION III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

I. Hater Hater samples were collected both on site and in the vicinity of Rancho Seco. Sample types include surface, runoff, well, and drinking water.

Runoff water was collected biweekly and was analyzed for Gross Beta (dissolved and suspended), Tritium, Iodine-131, and gamma emitting nuclides.

Surface water was collected monthly and was analyzed for Gross Beta (dissolved and suspended), Tritium Iodine-131, and gamma emitting nuclides.

Well water was collected quarterly and drinking water was collected monthly. Both are analyzed for Gross Beta, Tritium, Iodine-131, and gamma emitting nuclides.

One liter samples are counted in a Marinelli Beaker. The ,

sample is then put through a membrane filter. The filtrate is then recounted to determine dissolved gamma activity. The suspended gamma activity is determined by subtraction of the dissolved activity from the total activity.

The membrane filter is then counted for gross beta. The gamma filtrate is evaporated and counted for dissolved gross beta.

Tritium is determined by liquid scintillation counting of 3 ml of water.

Iodine is determined by carbon tetrach'ioride extraction using standardized iodine carrier. The iodine is then back extracted using hydrazine. A precipitate of AgI is then formed and counted.

Gamma Soectromtttry Sample Type: 1 liter Marinelli Beaker.

Sample Period: monthly (except biweekly for mixed effluent)

O

.c.

2

- . - . -- - . - - - - ~ -..~.~n., - , . .

, . - - . ..- . . . =. - . . .. -.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

.1987

_ /+ RANCHO SECO NUCLEAR GENERATING STATION III. DATA INTERPRETATIONS AND CONCLUSIONS- (Continued)

I. Water (Continued)  ;

Counting System: Intrinsic Germanium and Geli Spectroscopy System: Nuclear Data Computer Based Spectroscopy System Lower Limits of Detection (LLD): Cs-137: 10 pCi/1 Radiciodine 131 Sample. Type: 1 liter water processed to create AgI precipitate.

. Sample Period: See above.

Counting Instrument: Beckman Hide Beta II Thin Hindow Gas .

Flow Proportional Counter.

Efficiency: 41% I-131 Counting Time: 100 mi'nutes Lower Limits of Detection (LLD): 0.5 pCi/l Gross Beta Sample Type: 1 liter sample filtered on stainless  :

steel planchet i

Counting Instrument: Beckman Hide Beta II Thin Hindow Flow i Proportional Counter or Tennelec LBN j

5100 t

i O

3

+ 44 e o w - - --- w nw, a < , r-. .,,=n, -

---.-----m.- - - , - , , , , - - - , ,v--.+-,,,r.mp,,,-.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 i RANCHO SECO NUCLEAR GENERATING STATION III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

I. Etter (Continued)

Beckman efficiency: 60% (Sr-Y)

Tennelec efficiency: 51% (Sr-Y)

Counting Time: 100 mir.utes Lower Limits of Detection (LLD) 0.5 pCi/L Tritium Sample Volume: 3 ml Counting Instrument: Liquid Scintillation Model: Beckman LS100 Cocktail: Aquasol NEF 934 (New England Nuclear) 1 Calibration: Set of 6 NBS standards.

f Efficiency: 30%

Lower Limits of Detection (LLD) 250 pCi/L Results During 1987 fifty-six run off water samples, forty-nine surface water samples, thirty-two well water samples and twelve drinking water samples were collected.

Runoff water during 1987 showed no detectable levels of Iodine-131, or gamma emitting nuclides. No iodine was detected in 1986.

1 1

O j 45 *

. _ _ _ . .-...._f._.. . _. - _ . . . _ _

l l

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SECO NUCLEAR GENERATING STATION III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

I. Etter (Continued)

Suspended gross beta and dissolved gross beta ranged from less than the detection limit of 0.5 pCi/L to 2.7 pC1/L.

This compares with the 1986 concentration range of less than the detection limit to 5.2 pCi/L. Concentrations in 1985 ranged from 0 to 4.5 pCi/L.

All samples collected during 1987 were less than the lower limit of detection for tritium.

Surf _4fJL water __ Samples during 1987 ranged from less than The lower limit of detection (LLD) to 4.9 pCi/L for dissolved-gross beta. These values compare with 1986 and 1985 concentrations of 0 to 5.6 pCi/L and 0 to 2.8 pCi/l respectively. Suspended gross beta concentrations ranged from less than the lower limit of detection (LLD) to 8.2 pCi/L.

Tritium activity was detected in one sump sample taken on 01/14/87. This activity was at a level of 475 2 256 pCi/L.

Iodine-131 was not detected in any of the samples.

Well water gross beta activity ranged from .6 pCi/L to 3.1 pCi7C This compares to 1986 levels of 0 to 4.9 pCi/L and ,

1985 levels of 0 to 3.5 pCi/L. No tritium was detected in  ;

any samples.

.Drjnking water concentrations ranged from 1.3 pCi/L to 3.3 l pCi/L for gross beta. This compares to 1986 levels of 0 to 5.9 pCi/L and 1985 levels of 0 to 3.5 pCi/L.

_ Gamma _ac_tivity,_Id31_.and tritium were not detected in drinking water sa.aples during 1.e37.

Conclusions I l

Levels observed during 1987 were comparable to samples i from 1985 and 1986. Activity observed in surface water ,

samples was residual activity from controlled plant releases.

1

. 46

• 1

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987

() RANCHO SECO NUCLEAR GENERATING STATION III. DATA INTERPRETATIONS AND CONCLUSIONS (Contitiued)

J. Human Veaetation Seven samples are obtained quarterly when available. They are routinely counted for Gross Beta, Potassiuns40, and gamma emitting nuclides.

Gross Bet 3 less K-40 Method: Samples are dried at 110*C for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, ashed, and dissolved with dilute acid.

Counting System: Beckman Wide Beta II Thin Hindow Gas Flow Proportional Counter Calibration Source: CS 137 Efficiency: 43%

! Count Time: 100 min

() Lower Limit of Detection (LLO): 0.2 pCi/g Potassium-40 (K-40) Anal"111 .

a Method: Dried at 110*C for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, ashed,

dissolved in dilute HNO3-Analyzed by atomic absorption, K-40 taken as 1.7 dpm per mg K.

Lower Limit of Detection (LLD): 0.001 pCi/gm ,

1 i

I J l

' i 1

. 47

• l

., _.. , , , . - , .,,.,..,,,..n,-.. .q. n.,-n.,-,-y., .

_ . . . , . = -. . - . - - . .-. . _ _ . . . . . . . _ - . . , - . - . . - .

I ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT '

1987- .

RANCHO SECO NUCLEAR GENERATING STATION III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued) ,

J. Human Veaetation (Continued)

Gamma Soectrometry 1

i Method: Dried at 110'C for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, ashed, dissolved in dilute HNO3 .

Counting System:- Intrinsic Germanium and'Geli l Spectroscopy. System: Nuclear Data Computer Based Spectroscopy System 1

Results Twenty-seven samples were collected during the second,. )

, third and fourth quarters of 1987. Gross Beta activity ranged from a low of 5.41 pCi/g in the third quarter to a high of 19.75 pCi/g in the second quarter. K-40 activity ranged from a low of 12.24 pCi/g in the third quarter to a high of 29.35 pCi/g in the third quarter.

4 No gamma emitting nuclides were detected in any of the I samples.

Conclusions l It does not appear that human vegetation samples are-affected by Rancho Seco Operations.

i r

r i

I l

I e 48 l

F

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SECO NUCLEAR-GENERATING STATION III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

K. Cow Thyroid Cow thyroid samples are collected once a year when available from animals that graze on Rancho Seco property. (Availability usually depends on special studies being conducted or animals dying on the property.)

10.d10!L13.1 Method: The sample is placed in a Marinelli Beaker and analyzed for I-131.

Sample Type: Marinelli Beaker Counting System: Intrinsic Germanium and Geli Spectroscopy System: Nuclear Data Computer Based Spectroscopy System Results O No cow thyroid samples were collected'in 1987. The samples collected in 1984, 1985 and 1986 did not have any detectable activity. This is consistent with preoperational data obtained in 1971 and 1973.

Conclusions Based on the three samples analyzed from 1984-1986, it  !

does not appear that the uptake of I-131 in animals grazing on Rancho Seco property is affected by Rancho Seco operations. l i

\

O 1 49 l

- . . . . =

- - _ . .. - ~ -. . . - . . .- .

P r

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SECO NUCLEAR GENERATING STATION ,

1 III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

I L. Beef Tissue Beef tissue samples are collected once a year when ,

available from animals that graze on Rancho Seco property '

(availability usually depends on special studies being conducted or-animals dying). The samples are analyzed-for gamma emitting nuclides.

Gamma Soectrometry Method: Sample is dried at Il0*C for 24  ;

hours, the sample is then reweighed i

and ground and blended into powder for analysis. Samples prepared are then reweighed.

Sample Type: Marinelli. Beaker Counting System: Intrinsic Germanium and Geli ,

Spectroscopy System: Nuclear Data Computer Based Spectroscopy System ,

Results No activity above the lower limit of detection was found

in the one cow tissue sample collected in February 1987.

< Conclusions j i Based on limited sample data, it does not appear that radionuclide concentrations in animal tissue are affected by Rancho Seco operations.

t 4

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n,aw.v--,~r,

ANNUAL RADIOLOGICA'l ENVIRONMENTAL OPERATING REPORT 1987 *

(]

v RANCHO SECO NUCLEAR GENERATING STATION  ;

III. DATA INTERPRETATI0l:S AND CONCLUSIONS (Continued)

H. Honey Semi-annual honey samples are collected from hives located in the vicinity of Rancho Seco. The samples are analyzed for gamma emitting nuclides Gamma Soectrometry Sample Type: Marinelli Beaker Counting System: Intrinsic Germanium and Geli Spectroscopy System: Nuclear Data Computer Based  :

Spectroscopy System Results A honey sample was obtained in the second and third ,

quarter of 1987. The samples were counted by gamma spectrometry. No detectable gamma nuclides were observed.

O During 1986 and 198S no detectable gamma activity was present in samples collected.

Conclusions Based on limited sample data, it does not appear that radionuclide concentrations in honey are affected by Rancho Seco operations.

e 1

l

. S1 m e - --

y-- m+- %v -m y %7 g1 ,'qM4

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SECO NUCLEAR GENERATING STATION III. *0ATA INTERPRETATIONS AND CONCLUSIONS (Continued)

N. Duck and Pheasant One duck and one pheasant sample were collected from the vicinity of Rancho Seco. The flesh was analyzed for gamma ,

emitting nuclides.

Gamma Soectrometry Method: The sample is dried at 110*C for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, weighed, ground and blended into powder for analysis. Prept. red samples are reweighed. ,

Counting System: Intrinsic Germanium and Geli Spectroscopy System: Nuclear Data Computer Based

- Spectroscopy System Results The collection of duck or pheasant samples was initiated  !

in 1986. The duck and pheasant samples vare obtained on O- November 4, 1987, and no radionuclide concentrations were 1

detected in the samples.

i Conclusions Based on this limited sample data, it does not appear that radionuclide concentrations in duck and pheasant are affected by Rancho Seco operatior,s.

l 1

i t

l i

O

• 52

• l j

L ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SECO NUCLEAR GENERATING STATION

. III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued) l

0. 1011.

In 1987, five soil sampling sites were added to the sampling program.- Fou'r of.the sites are in locations.of known contamination due to previous liquid effluent  ;

releases, and one of the sites is a control location.

Samples were analyzed for Gross Beta activity and gamma emitting nuclides. .

Gross Beta Analysis Method: Dried at 110*C for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, <

dissolved in dilute HNO3 .

Counting System: Beckman Hide Beta II Thin Hindow Gas Flow Proportional Counter.

Calibration Source: Cs-137 Efficiency: 43%

Count Time: 100 min

(} '

Lower Limit of l

Detection: 0.2 pC1/g l Gamma Soectrometry 4

Method: Dried at 110'C for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 1 dissolved in dilute HNO,3 l Counting System: Intrinsic Germanium and Geli Spectroscopy System: Nuclear Data Computer Based Spectroscopy System o

i n

O

• 53 e i

f

2 _ . _ . . -

,w ANNUAL RADIOLOGICAL ENVIRONHENTAL OPERATING REPORT 1987 RANCHO SECO NUCLEAR GENERATING STATION III. DATA INTERPRETATIONS AND CONCLUSIONS (Continued)

0. S. oil (Continued)

Results During 1987, thirty-one soil samples were taken. Gross Beta ranged from .18 to 42.97 pCi/g (dry).

Gamma activities observed included Cs-134. Cs-137, and Co-60. Cs-134 levels ranged from less than the lower limit of detection (LLD) to 5.58 pCi/g (dry). The range of Cs-137 was from less than detectable to 31.95 pCi/g (dry), and Co-60 ranged from less than detectable to 4.69 pC1/g (dry).

One sample taken 0.8 miles west of the site on January 6, 1987, contained Gross Beta activity of 42.97 pCi/g, and the presence of Cs-134 (5.58 pC1/g), Cs-137 (31.95 pCi/g) and Co-60 (4.69 pC1/g).

Conclusions O Based on initial samples taken, radionuclide V concentrations in soil indicate effects of previous releases.

O 54

ANNUAL RADIOLOGICAL ENVIRONMENTAL s % M:'. R t. !

1987

..N RANCHO SECO NUCLEAR GENERATT l 1

d Table III-3 represents the summary of all sample locations and sample types. Data on gross beta, iodine, K-40, and gamma spectrometry are given. The mean values and the range of values for all locations, for the location with

- the highest values, and the control locations are '

4 reported.

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ENVIRONMLdTAL RADIOLOGICAL MC::ITCaid PROGRM ANNLEL SUN %RY P' '

RANCHO SECO NUCLEAR GENERATING STATION SACRAMENTO COUNTY. CALIFORNIA

]

TABLE III-3 Medium or Type and Total Lower Limit All Indicator Location w/ Highest Control Locations No. of Non-Pathway Sampled Number of Analys. ')f Detect. Locations Annual Mean Me#4 Routine (units) Perfomed (LLD) mean. name mean Range Reported rance dir & d*st rance Meas.srements Air Particulates Gross Beta 416 0.002 P.022(260/260) Ione .023(52/52) .021(155/156) 0 (pCi/m ) (.005 .055) 88* 9ml (.008 .048) (.007 .055) j Airborne Iodine I 416 0.0(,4 <tLD (0/260) $MJD Ndq. .009(1/52) .009 (1/156) 0  ;

l 315* 23 mi .009 .009  !

I sample 1 sample Direct Radiation TLDs 241 N/A 15.83 (144/144) 1.8 mi E 22.19 (4/4) 16.35(47/47) 0 (mR/Otr.) (2 per loc 3ticn-482) (10.75-26.0) of site (19.93-26.0) (11.4-27.1) 1 .

} Algae (pCi/g wet) Gamma Spec: 36 1

j CR-51 0.246 <LLD <tLD < L9 0 I-131 0.025 sLLD <LtD <LLD 0 a

pa-140 0.075 <tLD <LLO <ttD 0 La-140 0.465 <tLD <tLD <tLD 0 Cs-134 0.079 0.198(12/32) Hadselville 0.428(1/4) <LLD 0

(.049 .441) Creek @ Folsom 0.428 S. Canal 260* 3.7mi i sample l

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ENVIRONMENTAL RADIOLOGICAL MONITORu PRCGRAM ANNUAL SUPMARY RANCHO SECO MILEAR GENERATING STATION ,

SACRAMENTO COUNTY, CALIFORNIA

, TABLE III-3 (Continued)

Medium or lype and Total Lower Limit All Indicator Location w/ Highest Control Locations No. of Non-Pathway Jampled Number of Analys. Of Detect. Locations Annual Mean Mean Routine Performed mean Range Reported (units) (LLD) mean name rance dir & dist rance Measurements Pm4 & Silt (Continued) -

(*LLD based on 2509) Cs-137 0.056* 2.503 (36/43) Effluent 12.71 (4/5)

(0.050-15.8) Discharge (5.633-15.8) 0.160(/4) 1 (0.158-0.1611 Cr-51 0.246* <tLD <tLD <LLD 1 Co-58 0.017* <LLD <LLD <tLD 1 -

Co-60 0.058 0.717 (16/43) Effluent 1.49 (4/5) ,

(0.070-2.740 Discharge (0.417-2.74) 1 7

250*. 0.3 mi <tLD 1 Co-57 0.004* <tLD <tLD <tLD 1 Nt>-95 0.034" (LLD <tLD <tLD 1 Mn-54 0.021" 0.080 (3/43) R.S. Reservoir 0.10') (1/4) 0.034 (1/4) 1 (0.024-0.1091 104*. 1.3 mi 1 readina 1 re+dino Fe-59 ,

0.024* <tLD <LLD <tLD 1 Zn-65 0.060* <tLD <tLD <tLD 1 Zr-95 0.066* <LLD <tLD <LLD 1 __

Soll(pCl/g dry) Gross Beta: 31 3.914 (26/26) Silva Property' 42.97 1.388 (5/5) 0.05 (0.51-42.971 250*. 0.8 mi (1 sample) (0.81-2.461 0 5 of 12

• 60

• _ _ _ _ _ _ _ . _ _ _ _ ~ . _ _ _ _ _ _ _ _ _ . . _ . _ . m _ - _ _ _ . _ . . _ . _ _ = _.. . _ . __ .

s 1

ENVIRONMECTAL RE10 LOGICAL 90NITL PfiOGRAM AleRRL SUPMA2Y

! RANCHO SECO NUCLEAR GENERATING STATION SACRAMENTO C0'JNTV CALIFORNIA TAELE III-3 (Continued)

. Medium or Type and Total Lower Limit All Indicator Location w/ Highest Control Locations No. of N -

Pathway Sampled Number of Analy . Of Detect. Locations Anacal Mean  !!r.ee._ Routi e PHtag_ Range Reported (units) Performed (LLD) mean. name

.anoe dir & Jist rance Measurements l Soil Gamma Spec: 31 i.411 (6/26) Silva Property 5.58 Cs-134 0.079 (0.053-5.5E", 250*. 0.8 el (1! sasele) <tLD 0 2.323 (23/26) Silva property 31.53 0.151 (5/5)

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1.2% (4/26) Silva property 4.69 1.38 T VS)

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(pCi/g dry) 0.02 (5.41-16.85) 90*. 9.5 mi 16 32-16.85 1 control 0 i

20.758(26/25) Sloughhouse area 34.62 22.3 1

K-43 27 0.001 (7.3-34.62) 341*. 11 al (I readina) (2 readinos) 0

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ENVIRONMENTAL RADIOLOGICAL MONIT0in.d PROGRAM ANNUAL SUP9%RY RANCHO SECO NUCLNR GENERATING STATION SACRAMENTO COUNTY, CALIFORNIA TABLE III-3 (Continued)

Medium or Type and Total Lower Limit All Indicator Location w/ Highest Control Locations No. of Non-Pathway Sampled Number of Anal 5. Of Detect. Locations Annual Mean Mean Routine name mean Range Reported (units) Performed (LLD) mean rance dir & dist rance Measurements Honey (Continued)

Mn-54 0.056 (LLD utD <LLD 0 _ _ _

Fe-59 0.187 <LLD <tLD <LLD 0 Zn-65 0.028 <LLD <LLD <LLD 0 Co-60 0.060 <tLD (LLD <LLD 0 La-140 0.108 <tLD <tLD <tLD 0 Co-57 0.018 <tLD <tLD <tLD 0 Surface Water (pCi/1) I-131 49 0.5 <tLD (LLD <tLD 0 250 479 (1/49) Water sump 475 (1/13)

T ri tium 265* 0.7 mi i sample <LLD 0 _

Beta 0.5 0.919 (11/25) Water sump 1.05 (8/13) 1.57(13/24)

Suspended (0.5 1.8) ,265* 0.7 mi (0.5-1.8) (0.6-8.2) 0 Beta 0.5 1.259 (22/25) Water sump 1.43 (11/11) 1.378(18/24)

Dissolved (0.6-3.0) 265* 0.7 mi (0./-3.0) (0.5-4.9) O Surface water Gamma Spec: 49 (pCi/1) Mn-54 2 (LLD <tLD <LLD 0 Fe-59 3 <LLD <!.LD <LLD 0 Co-58 3 <tLD <tLD <tLD 0 8 of 12

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ENVIRONMENTAL RADIOLOGICAL MONITdin.J3 PROGRAM ANNUAL SUMARY RANCHO SECO NUCLEAR GENERATING STATION SACRAMENTO COUNTY, CALIFORNIA TABLE III-3 (Continued)

Medium or Type and Total Lower Limit All Indicator Location w/ Highest Control Locations No. of Non-4 Pathway Sampled Number of Analys. Of Detect. Locatipos- Annual Mean Mean Routine (units) Performed (LLD) mean name mean Range Reported 6 rance dir & dist rance Measurenents Runoff water (Continued)

Gross Beta 1.29 (40/56) Site Boundary 1.432(19/29) -

Dissolved 56 0.5 (0.5-2.7) 255*. 0.6 mi (0.6-2.7) <tLD 14 Gamma Spec: 56 Mn-54 2 <tLD <tLD <tLD 14 Fe-59 3 <LLD <LLD <LLD 14 Co-58 3 (LLD <tLD <tLD 14 Co-60 5 <tLD <tLD <tLD 14 Zn-65 16 <LLD <tLD <tLD 14 Z r-Nb-95 8 <tLD <tLD <tLD 14 Cs-134 10 <tLD <tLD <tLD 14 Cs-137 2 <tLD <LLD <LLD 14 Ba.La-140 4 <LLD <tLD <LLD 14 Well water (pCi/li ter) I-131 36 0.5 <tLD <LLD <LLD 13 Tritium 36 250 <LLD <tLD <LLD 13

, 1.567 (28/28) Site well 2.375 (4/4) 2.413 (8/S) j Gross Beta 36 0.5 (0.6-2.8) 138*. 0.1 mi (2.1-2.7) (1.8-3.1) 13 Gamma Spec: 32 Mn-54 2 <LLD (LLD <LLD 13

• 11 of 12

• 66

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1

1987 '

RANCHO SEC0 NUCLEAR GENERATING STATION

(

IV. RADIOLOGICAL ASSESSMENT OF IMPACT ON THE ENVIRONS A. Radioloaical Imoact - Gaseous Effluent,.1 No measurable activities due to the toutine operation of the Rancho Seco Nuclear Generating Station have been observed by the air sampling program during 1987. As a result, no radiological impact can be inferred from the measur,ements. This is supported by the following:  ;

1. No directly detectable activities above background have been correlated with plant operation. All measurements for gross beta, gross alpha, radiciodine, and gamma spectroscopy have not been able to detect quantities above normal background, except as associated with the Chernobyl event.

2. Actual plant release data indicate on a calculational basis (i.e., X/Q calculations) that current plant l releases are unlikely to be detected with the current !

X/Q values, plant releases, and system sensitivities i for lower limits of detection.

3. Results below system detectabilities have been consistent with plant history. Positive levels of radionuclides associated with nuclear weapons testing i and the Chernobyl event have been observed.

4. The proper operation and detectability for the air sampling systems can be inferred from the good  ;

aareement of natural background measurements. j B. Radioloaical Imoact - Licuid Effluents The potential radiological impact of_the liquid effluents i from Rancho Seco is traced to 4 paths:

. consumption of aquatic foods

. swimming and shoreline usage of the streams i e irrigation of crops with subsequent ingestion by humans

. irrigation of food crops or pasture with subsequent consumption of meat by humans.

68

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

, 1987 RANCHO SEC0 NUCLEAR GENERATING STATION IV. RADIOLOGICAL ASSESSMENT OF IMPACT ON THE ENVIRONS (Continued)

Consumotion of Aauatic Foods and Swimmina and Shoreline Usage Estimates of the impact of this path are derived by evaluation l of doses for a hypothetical family with freshwater aquatic food  ;

intake in the range of previous studies for persons in the Pacific region (Ru80) and modified with the results of the 1987 Land Use Census (Nu 87). Results of the liquid effluent land t e survey indicate that no Rancho Seco area residents use the C ar and Hadselville stream system, but allowance for farmers neai 7e shoreline is included. Consequently, it is inapp.opr bte to assess dose for these residents.

Swimmina and Shoreline Usaae of the Streams The stream usage factors for the hypothetical family are presented in Table IV-1. This table uses the land use census data for consumption of freshwater fish and stream usage from Nu

87. Crayfish and frog legs were not identified, and are consequently not used. The remaining source terms were derived from data presented in Regulatory Guide 1.109, b)

V The source terms for the hypothetical family were obtained by using the average values for sections of the stream system downstream from 3.0 km. The length of the stream from the site boundary out to 4.6 km has been posted with "No Hunting, No Fishing, No Trespassing" signs and usage has been significantly reduced since 1984. Observations indicate that there has been a significant reduction in the fish populations, as reported by personnel with scientific cellection permits.

Table IV-2 presents source terms for the hypothetical family.

Doses were calculated in accordance with the Offsite Dose Calculation Manual. The doses are presented in Table IV-3.

Irrication of Croos with Subseauent Inaestion In the downstream distance beyond 4.6 km, crops are irrigated from the stream system by subscribers of the Galt Irrigation District. Some crops such as wheat and rice, could be directly ingested by humans. Although unlikely, because the crops are raised for market, the dose to an individual whose grain intake is composed solely from these fields is evaluated. Usage is shown in Table IV-1.

3 (V

69 1

• ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT' n 1987 RANCHO SEC0 NUCLEAR GENERATING STATION IV. RADIOLOGIC 8L ASSESSMENT OF IMPACT ON THE ENVIRONS (Continued)

The Galt Irrigation District keeps accurate records of water usage and acreage irrigated. The average rate of irrigation in 1987 was 130 liters per square meter per month, assuming six month.

irrigation. The source term was obtained from the average of water concentrations at Folsom South Canal and downstream. The source terms are presented in Table IV-2. All other factors are taken from the Offsite Dose Calculation Manual. The resulting dose equivalent estimates are presented in Table IV-3.

Irriaation of Pasture With Subseauent Inaestion of Meat Beef cattle are pastured on land formerly irrigated by Clay Creek between the plant outfall and the site boundary. One sample was taken from a beef pastured in this area. Radionuclide concentrations are presented in Table IV-2.

The usage parameters shown in Table IV-1 are taken from the Offsite Dose Calculation Manual for the maximally exposed individual.

O In the unlikely event that this individual's entire ingestion of

(' meat were from this beef, the body and organ doses which would result are presented in Table IV-3. 1 1

1 O

+ 70

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 3 1987 RANCHO SECO NUCLEAR GENERATING STATION 1

i Tables IV-1 through.IV-3 give data necessary for evaluating the impact on the environment by Rancho Seco. This includes stream usage ,

factors, source terms, and' calculated dose equivalents.

O O

71

• e

---

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1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 198,

• RANCHO SECO NUCLEAR GENERATING STATION IV. RADIOLOGICAL ASSESSMENT 0F IMPACT ON THE ENVIRONS (Continued)

TABLE IV-1 STREAM USAGE FACTORS - HYPOTHETICAL FAMILY Aquatic Foods (kg/yr) ADULT . TEEN CHILO Fish 0.49 0.11 0.24 Shoreline (hrs /yr) 65 NA NA Swimming (hrs /yr)(posted) NA NA NA Irrigated Vegetation (Grains) 520 630 520 (kg/yr)

O Meat (kg/yr) 110 65 41 l

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- - . - . . -. . .. __. . - . . . - - . ._ _.-.~ .~ . - = . - .

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SEC0 NUCLEAR GENERATING STATION-IV. RADIOLOGICAL ASSESSHENT OF IMPACT ON THE ENVIRONS (Continued)

TABLE IV-2 SOURCE TERHS Cs 134 Cs 137 Co 60 Hn 54 Aquatic Foods (pCi/gm)

Fish (all species) 0.042 1.23 - -

Shoreline (pCi/m2) 6.39E+3 2.5E+4 7.37E+3 8.0E+2 Swimming (pCi/1) - - - -

Irrigated Vegetation (pCi/1) - - - -

O Heat (pCi/g) - - - -

O

. ,2

- - , . - - . . _-- -,-_--....-....-_. _ ._ - ---.-___._-__.--.- -_=_- . _...... - - .- -.

. ~ -

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l 1987 RANCHO SECO NUCLEAR GENERATING STATION IV. RADIOLOGICAL ASSESSMENT OF IMPACT ON THE ENVIRONd (Continued)

TABLE IV-3 CALCULATED DOSE EQUIVALENT (mrem) FOR 1987 BASED ON ENVIRONMENTAL SAMPLES WHOLE BODY ADULT TEEN CHILD Aquatic Foods 0.023 0.006 0.QO33 Shoreline 0.016 NA NA Swimming NA NA NA i

Irrigated Vegetation 0.0 0.0 0.0 Heat 0.0 0.0 0.0 '1 TOTAL 0.039 0.006 0.033 MAXIMUM ORGAN (Liver)

Aquatic Foods 0.048 0.013 0.016 Shoreline 0.019 NA NA i Swimming NA NA NA Irrigated Vegetation 0.0 0.0 0.0 Heat 0.0 0.0 0.0 l l

TOTAL 0.067 0.013 0.016 I

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ANNUAL RADIOLOGICAL' ENVIRONMENTAL OPERATING REPORT 1987 Oi RANCHO SECO NUCLEAR GENERATING STATION V j IV. RADIOLOGICAL ASSESSMENT OF IMPACT ON THE ENVIRONS (Continued)

C. Summary During 1987 any impact on the environment possibly from Rancho Seco operaticed fontinues to be overshadowed by the contamination associated with the 1985 Chernobyl event.

Additionally Rancho Seco was in cold shutdown during all of 1986 and 1987. The results of analyses indicated ,

compliance with 40CFR190, Fuel Cycle Dose.

Gaseous Effluents j The results from the TLD program indicate that no correlation can be made with respect to sector-weighted releases even at close distances. The conclusions from analysis of the air sample results are similar, although the air sample coverage is much less than the TLD coverage.

Anomalies occur in the TLD readings. Anomalies at the l protected area boundary have been traced to storage of (

radioactive waste in the vicinity. The geology of the area leads to the hypcthesis that distant anomalies are p) y due to naturally-occurring radic3ctive materials, as shown by E. G. & G. fly-overs in 1974 and 1986.

l Licuid Effluents '

The results of end renmental samples taken in this pathway l indicate that a total body dose equivalent of less than 0.5 mrem could se received by a hypothetical individual who occasionally eats aquatic fauna from the stream. A hypothetic11 maximum individual who obtains all his grain intake from irrigated crops would have received a dose equivalent of less thsn 0.5 mrem during 1987. An individual whose sole meat intake is from beef with radionuclide concentrations similar to the sample might receive a dose to the tc.aximum organ of less than 1.0 mrem per year. The land use census clearly demonstrates that the grain crops are processed and distributed via cooperatives, wholesalers and retail grocery chains. Few local residents consume these grains exclusively, m

• 75 I

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.

1987 RANCHO SECO NUCLEAR GENERATING STATION IV. RADIOLOGICAL ASSESSMENT OF IMPACT ON THE ENVIRONS (Continued)

D. References Ru80 Rupp, Elizabeth, M. Forest, L. Miller and C. F. Baes III, "Some Results of Recent Surveys'of Fish and Shellfish Consumption by Age and Region of U.S. Residents, Health Physics, 39:2, August 1980 Nu87 NUS Land Use Data Base for Rancho Seco Nuclear Generating Station, August 1987 O

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHOSECdNUCLEARGENERATINGSTATION APPENDIX A LAND USE CENSUS f

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SECO NUCLEAR GENERATING STATION LAND USE CENSUS The land use census is currently composed of:

. Identification of the nearest milk animal, nearest residence and nearest garden of greater than 500 square feet in each of the 16 sectors within a five-mile radius (in accordance with Technical Specification 3.23).

. Interviews of residents living near Rancho Seco who use the Clay-Hadselville-Laguna Creek system to determine extent of use of this stream system.

. Review of documents to determine items such as irrigation water obtained from the Clay-Hadselville-Laguna Creek system.

. Review of county population projections.

The results of the first element are presented in Table A-1. These data indicate that changes during 1987 principally involve residences which are a greater distance from Rancho Seco.

Interviews to implement the second element continued into 1987 to obtain information on the 1986 usage. Information into May 1986 indicates that residents in the Rancho Seco area stopped using the stream system for fishing, frogging, swimming, and other recreational purposes in November-December 1984.

With the cooperation of local landowners, Clay and Hadselville Creeks were posted with "N0 HUNTING, NO FISHING, NO TRESPASSING" signs in December 1984. Access is limited in the areas of downstream distances less than 4.6 km. The District continued the program to inspect the Clay /Hadselville Creek areas on a limited basis. The purpose of the inspection is to determine whether persons are trespassing on posted private property, particularly to fish.

During 1987, no anglers were observed in the posted area, but on several occasions litter was found which suggests anglers may hele been in the area indicating limited use of the stream.

From the interviews and inspections, it appears at the time of this report that no regular use is made of the stream system by residents near Rancho Seco. Any use of the stream system (at less than 4.5 km) is confined to occasional users who stop at the California State Route 104 bridge.

Data were obtained from the Galt Irrigation District for all irrigation users along Laguna Creek. These users, identified by alphabet code, quantities of water, areas irrigated, and crops are in Table A-2.

l ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l

- 1987  ;

RANCHO SECO NUCLEAR GENERATING STATION i

Tables A-1 and A-2 present data obtained during the land use' census for the gaseous pathway (Table A-1) and the Galt Irrigation District water usage (Table A-2).  ;

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT p 1987 (j RANCHO SECO NUCLEAR GENERATING STATION LAND USE CENSUS TABLE A-1 Results of 1987 Gaseous Pathway Census Within 5 Hiles 1 (All values are distances in meters to nearest subject in the sector)

NEAREST MILK ANIMAL NEAREST NEAREST NEAREST MEAT ANIMAL SECTOR GOAT COH RESIDENT GARDEN

• BEEF *** H0G POULTRY SHEEP N None** None None None 436 None None None NNE None None None None 433 None None None NE None None 4830 4830 433 None None 4830 ENE None 1140 1140 1140 448 None 1140 1140 E None None None Hone 472 None None None

("T ESE None None None None 668 None None None G) SE None None 2560 2560 235 None None None SSE None None 7800 None 198 None None None S None None 6490 6490 195 None 6490 None  !

SSH None None 5330 5330 198 None 6340 None SW None 6380 3190 3190 287 3190 3190 3190 4 1

HSH None 3620 1830 2380 405 3230 3620 3230 l H 3230 7740 3230 3230 506 None 5820 3230 l l

HNH None None 4390 4390 436 None None None NH None None 6750 6750 497 6750 6750 6750 NNH None None 7250 None 445 None None None l

Defined as greater than 500 square feet with edible. green leafy vegetables.

• • None within a five mile radius from the R.incho Seco Containment Building.

,Q V *** Beef do not graze in these locations for the entire year.

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 A RANCHG SECO NUCLEAR GENERATING STATION V

TABLE A-2 GALT IRRIGATION DISTRICT HATER USAGE 1987 Hater Usage Croos (acres) usar (liters) Con 1 Bica Clover Sud.an Pasture L4hfutt Total A 1.62E+9 180 170 100 450 B 1.02E+8 42 18 60 C 1.72E+8 60 40 100 D NONE N/A E 8.88E+7 30 30 l F 5.47E+8 190 190 l G 9.48E+8 140 120 260 H 2.11E+8 50 20 20 90 I NONE N/A J 1.67E+8 100 100 Total 3.86E+9 122 310 170 310 308 -

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I . ANNUAL RADIOLOGICAL-ENVIRONMENTAL OPERATING REPORT 1987

. RANCHO SECO NUCLEAR GENERATING STATION i

AP.'> ENDIX B SAMPLING PROGRAM DESCRIPTIONS AND MAPS i

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SEC0 NUCLEAR GENERATING STATION l

l Appendix B contains the following Tables and Figures:

l Table B-1 Lower Limits of Detection by Other Than Gamma Spectrometry ,

1 Table B-2 Lower Limits of Detectic.1 by Gamma Spectrometry Table B-3 Radiological Environmental Reporting Levels Table B-4 Collection Schedule Table B-5 Sample Counting Tirnes Table B-6 Aliquot Used for Detection Limit Calculation and .

Actual Analysis l Figure B-1 Environmental Sample Locations - General Figure B-2 Environmental TLD Locations for 5 Mile Radius Figure B-3 Environmental TLD Locations for 20 Mile Radius 1

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(, RA0iOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1 PAGE 1 0F 27  ;

LEAD DEPARTMENT Effective date: 03-24-88 Environmental Protection I

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o THIS PROCEDURE IS ISSUED FOR I.WORl1AT10N ONLY AND SHALL NOT BE USED FOR WORX OR DESIGN. j l

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O' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1 PAGE 2 0F 27 l

l TABLE OF CONTENTS 1

SECTION TITLE PAGE 0.0 Rancho Seco REMP Policy 3 1.0 Radiological Environmental Monitoring Program Bases 4  ;

2.0 Radiological Environmental Monitoring i Program Description 5 l

2.1 Radiological Environmental Monitoring Program Parameters 8 2.2 Analysis of Exposure Pathways 10 2.3 Identification of Sampling and Monitoring 0 Sites and Samples 11 2.4 Reporting Results of Radiological Environmental Data 13 2.5 Selection of Radiological Environmental Monitoring Locations 13 TABLE TITLE PAGE j 1 Two Letter Designation to Identify ,

the Type of Sample 15 )

1 2 Sector Letter Designations Used in Sample Identification 16 l 3 Radiological Environmental Sampling i Locations 17 4 Environmental Thermoluminescent Dosimeter Locations 26 8

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1 PAGE 3 0F 27 0.0 EELLGl.

The Sacramento ' Municipal Utility District (SMUD) and the Rancho Seco Nuclear Generating Station recognize their responsibility to l comply with the Technical Specifications and the applicable regulations. codes, standards and industry-wide criteria for  ;

establishing and maintaining a viable Radiological Environmental l Monitoring Program. We are committed to operating.the Rancho Seco l Nuclear Generating Station in such a manner that will assure proper radiation protection to all employees, contractors and the general public. To this end, we have committed to performing an l environmental sampling program which meets the intent of the I applicable regulations while providing an accurate assessment of the radiological environment in and around the environs of the Rancho Seco site.

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Chi Exe ive Officer, Nuclear I

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1 PAGE 4 0F 27 1.0 RADIOLOGICAL ENVIRONMENTAL MeifT0 RING PROGRAM BASES The Rancho Seco Unit One Technical Specifications, Section 4.26, state in part that:

"The Radiological Environmental Monitoring Program required by this specification provides measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from station operation. This monitoring program thereby supplements the radiological e f fl uen t monitoring program by ve ri fyi ng that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected."

The Sacramento Municipal Utility District and the Rancho Seco Nuclear Generating Station, to ensure that this O'd requirement is met, have instituted a Radiological Environmental Monitoring Program (REMP) which this manual serves to implement. The REMP is based upon the guidelines of Title 10 of the Code of Federal Regulations, Part 20, i Section 106 (10 CFR 20.106). That R e g u l a t o r.r basis and associated guidelines have been the foundation of the REMP and its programmatic elements which:

1. Provide the technological basis of, and the_ instruction for, monitoring the site and environs for radioactivity of all sources, including;

a. naturally occurring background

b. releases during normal operations

c. operational occurances and postulated accidents

d. weapons testing and major nuclear accidents which contribute to detectable radioactivity in the environs.

2. Provide the means to verify the effluent control ,

program of the Rancho Seco Nuclear Generating Station. l

3. Meet minimum limits for detecting radioactive elements in samples collected from the environs, or direct 1 measurement s in the field.

4 Provide measurements of radiation and radioactive materials in those exposure pathways, i.e., liquid,

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V RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL RPISION: 1 PAGE 5 0F 27 gaseous, and direct radiation, and for those radionuclides, i.e., iodine, cesium, and cobalt, which lead to the highest potential radiation exposure of individuals resulting from station operation.

2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DESCRIPTION  ;

The Radiological Environmental Monitoring Program is under i the cognizance of the Chief Executive Officer, Nuclear, witn '

the responsibility for the administration and oversight of the program assigned to the Manager, Environmental l Protection. I The design of the program is consistent with the intent of Title 10 Code of Federal Regulations, Part 20, Section 106, "Standards for. Protection Against Radiation". To implement these requirements, the Technical Specifications, Offsite Dose Calculation Manual and Health Physics Implementation Procedures have been developed. The implementing procedures address specific areas of emphasis in the program that l O- require direct attention and/or specified step-wise progress for completion. The following is a list of those types and numbers of those documents used for the implementation of

)

the REMP: 1 Rad'ological Effluent Technical Specification, Appendiy A, Sections 3.22, 3.22-1, 3.22 2, 3.23, 3.25, 3.26, i 4.26, 4.26-1, 4.27, 4.29, 6.5.1.8.b,c,d,k,n, 6.9.2, .

6.9.5. I Offsite Oose Calculation Manual. 1 Health Physics implementing Procedures listed below; HPIP.2001 R a d i o l o g i c a l Environme .al Mon toring Operations, HPIP.2010 Training and Qualification of Radiological Environmental Personnel, HPIP.2021 Interlaboratory Comparison of Radiological Environmental Monitoring Analysis, HPIP.2025 Q u al i t y Review of the Radiological e

Environmental TLD System, HPIP.2040 Radiological Environmental Trend Analysis, l

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1

. PAGE 6 0F'27 HPIP.2050 Radiological Environmentai Reports, HPIP.2051 Annual Radiological Environmental Operating '

Reports, HPIP.2060 Radi ological Environmental Records and Documentation, HPIP.2080 Radiological Environmental Surveillances, HPIP.2130 P r e p a r a t i o n s Prior to Performing Environmental Sampling, HPIP.2131 Handling and Preparations of Radiological Environmental Samples for Shipment, hPIP.2140 land Use Census, HPIP.2201 S a m p l i n g of Water for P.adiological Environmental Monitoring, HPIP.2260 Preparation of the ISCO Composite Water Sampler for Use:

i HPIP.2261 Inspection and Maintenance of the ISCO Composite Water Sampler, HPIP.2310 Algae Sampling for Radiological Environmental Monitoring, F PIP.2401 A i r b o r n e Radiological Environmental Monitoring, H P I P . ?. 501 T e r r e s t r i a l Sampling for Radiological Envlionmental Mar.itoring,

, HPIP.2610 Posting and Rett, eval of Environmental Thermoluminescent Dosimeters, HPIP.2611 Analysis of Thermoluminescent Dosimeter Data, HPIP.263C Irradi a tion of Test and Calibration Thermoluminescent Oosimeters, HPIP.7.611 Acceptance Criteria and Periodic Testing of a

Environmenta' Thermoluminescent Dosimeters, HP!P.2650 Op e r a t i o n of the U0 702 Panasonic Themoluminescent Dosimetry Reader, t--- ,,-----w- .,,m,, p . - , . . -  ; -v- , , . , -,.--,.-.,..--,-,e- .

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1 PAGE 7 0F 27 HPIP.2651 C a l i b r a t i o n of the UD-702 Panasonic Thermoluminescent Dosimetry Reader, HPIP.2652 Main tenance of the UD'-702 Panasonic Thermoluminescent Dosimetry Reader, HPIP. 2710 S a m p l i n g of Milk for Radiological Environmental Monitoring, HPIP.2720 Sampling of Aquatic Life For Radiological Environmentai Munitoriag, HPIP.2730 S ampl i ng of Botanical Specimens for Radiological Environmental Monitoring, HPIP.2740 Sampling of Animal Tissues for Radiological  ;

Environmental Monitoring, e

HPIP.2750 S a mp l i n g of Honey for Radiological Environmental Monitoring.

Several' documen t s that were used as guidance, but were not necessarily strictly adhered to as absolute standards, during the developmenta? phases of the program are:

American National Standards Institute Standard ANSI N545-1975, Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry (Environmental Applications),

ANI/MAELU Information Bulletin 86-1, Regulatory Guide 4.1 Programs for Monitoring -

Radioactivity in the Environs of Nuclear Power Plants,  ;

Regulatory Guide 4.15, Rev. 1, 1979, Quality  !

Assurance for Radiological Monitoring Programs (Normal Operations) -

Effluent Streams and the Environment.

NUREG-0472, Rev. 2, Radiological Effluent Technical Specifications for PWR's, July 1979, NUREG 0543, Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part  !

190),

Branch Technical Position, Rev. 1, November 1979, i

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! ,/ RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1 PAGE 8 0F 27 NCRP' Report No. 50 -

Environmental Radiation Measurements.

2.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PARAMETERS The monitoring and sampling aspects of the program-have been established after three major factors were determined, which are:

Identification of the effluent release pathways, Identification of the human exposure pathways, Identification of the land usage parameters by the population within a ten mile radius of the site.

Three principal .elease pathways exist at Rancho Seco Nuclear Generating Station, which are:

Gaseous Effluents discharges from the waste gas system for the reactor building stack, auxiliary building stack, miscellaneous water evaporator stack and the auxiliary grade level vent.

Liouid Ef fluents di scharges which are released from the retention basins via the waste water disposal system (regenerant hold up tanks (RHUT) A and B].

Direct Radiation radiation that enanates from radioactive material contained within tanks other containers which are within the site coundary to humans outside o f the site boundary.

The pathways to human exposure :o radioactive materials in the effluent release pathways from Rancho Seco are:

Gaseous Inhalation humans, of airborne radioactive material by or by animals that inhale and retain the material in animal products eaten 3 by the public, i.e. meat or milk.

l Consumption of radioactive particulate material which, although carried by air l

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1 PAGE 9 0F 27 cur. rents, is deposited onto or is taken up by water sources or plants consumed by humans, or by animals that provide products that are consumed by humans, i.e... milk or. meat.

Exposure from being immersed in . air containing radioactive materials a s. a gas and/or particulates.

Exposure to the direct radiat-ion from radioactive materials that have been deposited onto surfaces from airborne releases.

Liouid Drinking of water from the release pathway by humans, or by animala that are a food source for humans. l The consumption of fish, shellfish or other O

animals t '.i a t have eaten fish or shellfish ,

taken from water 'within the liquid release pathway.

The consumption of animal meats or products of animals that have eaten vegetation that have been irrigated with water from the I release pathway.

The consumption by humans of fruit or 4

vegetation grown in soil irrigated with water from the release pathway.

Direct ,

Radiation The exposure to radiation emitted from i radioactive materials within the Rancho Seco sire boundary. Sources include, but are not limited to, the Borated Water Storage Tank,

Reactor Coolant St rage Tank, and the  ;

Radioactive Waste Storage Area. '

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The Exposure from being immersed in the  :

release pathway water, to radiation emanating l i

from material contained in the water. I l

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q RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL V REVISION:

PAGE 1

10 0F 27 2.2 ANALYSIS OF EXPOSURE PATHWAYS Exposure pathways are analyzed through a systematic process which identifies a sample medium or organism that is found in the effluent pathways, for which usage factors can be determined and will suitably represent biological concentration, retention or uptake which may u l t _i m a t e l y represent a contribution to human exposure. The pathways to human exposure are evaluated through the analysis of data obtained from the performance of a land use census. The performance of the land use census is required by the Technical Specifications Section 4.27. The analysis of the e f fluen t and exposure pathways enables the selection of sampling and monitoring locations that fall into one of two classes, those which are, and those which are not, influenced by e f fl uent pathways. Those in the pathways are referred to as indicator locations. Several of the unaffected locations are selected to represent baseline or control locations.

Indicator locations provide data from the surrounding O'

environment that may be influenced by the operation of the plant because they are nearby, downwind or downstream in the release pathway. Such data can be used to calculate doses to humans to verify t i, e degree of compliance with 40 CFR 190, using methodology contained in the 00CM. (This is referred to as the Real Individual Exposure. The Real Individual is defined as any person who participates in activities that result in that person being in the actual pathways for offsite dose. A Real Individual who, based upon the land use census, is expected to receive the maximum offsite dose to real individuals, may be used to calculate doses to demonstrate compliance with 40 CFR 190).

Control sample locations are to provide data that should not be influenced by the operations of Rancho Seco. These locations are selected based upon the distance from the plant, being upwind, or upstream of the release pathways.

Data from these locations help discriminate between Rancho l Seco releases and other natural or manmade events that may  !

impact human exposure.

At Rancho Seco, potentially radioactive liquid e f fl uen t is i discharged into Clay Creek, Continuously, a minimum flow of

, 5000 gallo.1s per minute of non-radioactive water is released  !

above the discharge point. The continuous minimum flow and  !

A the liquid radicactive effluent release are the major V ef fluent release pathway, and hence exposure pathway for the l

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l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1 PAGE 11 0F 27 station during normal operations. Prior to the minimum release rate being established, Clay Creek was a seasonal stream, formed as the c o n fl u e nc e of three and one half square miles of drainage runoff upstream of the site. The-now continuous flow of Clay Creek intersects Hadselville Creek North and West of California State Highway 104.

Hadselville Creek intersects Laguna Creek just East of the Folsom Canal. Laguna Creek flows into the Consumnes River approximately 20 miles from Rancho Seco. Hadselville and Laguna Creeks are also seasonal streams and also receive irrigation runoff during periods when irrigation is used.

Because these streams are the major release pathway for liquid e f fl uen t s from the site, the majority of recent program enhancements have focused on this effluent pathway.

The gaseous pathway analysis is also related to the land use census. This pathway is not confined by creek banks, but is subject of the meteorological conditions during the time of the release. This presents the requirements of having indicator and control sampling stations more evenly distributed with particular attention to those areas of s greater population dansity. While not the major release nor  ;

exposure pathway, recent improvements in monitoring this i s pathway have been instituted.

The direct radiation exposure pathway is the least likely l pathway for the exposure to plant radiation by humans. It is the most easily measured with the use of thermoluminescence dosimeters, which monitor continuously and passively. The dose is integrated over three months to accumulate a statistically significant exposure. The vast majority of the dose integrated by these detectors is aelivered from primordial elements in the geological surface of the Earth, which happen to contain naturally radioactive elements. A l smaller fraction af the dose is delivered by cosmic radiation which has penetrated the Earth's atmosphere.

2.3 IDENTIFICATION OF SAMPLING AND MONITORING SITES AND SAMPLES Sampling and monitoring sites and the samples collected from them, must be identified with a concise designation. This has been accomplished using the following methodology:

To establish the Utility identification, the letter "R" has been chosen. Therefore all samples from the Rancho Seco begin with the letter "R".

e N Next, that portion of the identification related to the type of sample is made with a two letter designation, 1

u

RA010 LOGICAL UVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1 PAGE 12 0F 27 i.e., AS = Air Sample. A complete list is contained in Table 1.

A group of digits follows the Sample type. These indicate the straight line distance from the center of containment. For distances less than ten miles, the figure is to the nearest tenth of one mile. For distances ten or more miles the figure is to the nearest mile. Distances are measured with the use of U.S. Geodetic Survey maps.

Following that is a letter designation which specifies the identification letter corresponding with one of the 16 wind sectors as identified in the Emergency Response Plan, i.e., "H". Emergency Response Plan Wind Sectors are defined in Table 2.

The final character is the letter "0" which designates the sample as being one collected after the p l a r. t was declared operational.

O Thus, a Rancho Seco Air Sample, collected at ten miles from the plant in Emergency Plan Wind Sector "H" after operational status was established would be identified as:

RAS 10H0.

To complete t1e identification process, each sample label has a date as part of the sample number, followed by 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time, written as:

MM/DD/YYYY-HHmm, or specifically, if the sample was collected in December, on the 15th day in 1987 at 5:15PM, then the above sample would be identified as:

RAS 10H0-12/15/1988-1715.

The present system of identification has been incorporated in preference to the system originally used to identify samples and sites. There is a necessity to retain the ability to identify, and continue to use data from, previously collected samples. The former identification O designation is shown in parenthesis under the currently used one.

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1 PAGE 13 0F 27 2.4 REPORTING RESULTS OF RADIOLOGICAL ENVIRONMENTAL DATA The requirements for reporting radiological envi_ronmental  !

data are specified in the Technical Specifications, Section j 6.9.2, Environmental Reports. Those subsections- which require supporting data from the Radiological Environmental  ;

Monitoring Program Address the Annual Radiological Environmental Operating Report and the Semi-annual Radioactive Effluent Release Report. Technical Specification Section 6.9.5, Special Reports, is made specific in HPIP l 2050, Radiological Environmental Reports. Specified therein l are conditions requiring special reports, and reporting i requirements in days for submittal. This includes those .l calculations to provide rapid assurance of the degree of compliance with 10CFR50 Appendix I, and 40CFR190 i calculations after releases of any_ origin. l l

2.5 SELECTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS l a  !

In conjunction with the data base established from the land I use eensus, the requirements of the Technical Specifications, and the guidance described in Section.2.0 of this Manual, the selection of sampling and monitoring sites was performed. These were chosen to provide for at least the minimum number of indicator locations specified in Technical Specifications, Section 3.22, Table 3.22-1.

For those locations to be classified as indicator sites, data is gathered from the land use census, Lawrence Livermore National Laboratory Ranch- Seco Study Reports, Oak Ridge National Laboratory Study Re, ts, and from additional sampling sites from which materials have been collected and determined to be candidate sites. Presently, a sufficient number of control sites have been selected and are not anticipated to be increased in number.

Environmental themoluminescence dosimeters are placed more uniformly around the environs of the site. These devices passively monitor radiation in the immediate environs. Data from TL0s is trended to establish variations which are influenced by seasonal, meteorological, local and global sources. TL0s will also respono to radiation in the effluents of the plant if they pass in near proximity.

, The TLD Program is operated entirely by Rancho Seco. The data is included in each Quarterly Envirar,mentel Report.

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RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1 PAGE 14 0F 27, Sample locations for the collection of the flora and fauna are concentrated in the liquid effluent pathway to the West.

Representative samples of all the pathways and . suitable locations are established in all directions. Air samplers are distributed to achieve a sampling of air from major wind directions across the site.

The Radiological Environmental Monitoring Program maintains at least those minimum sampling locations and type' of samples as required to' meet the Technical Specification requirements listed in Table 3.22-1. Many sample types and locations have been added to enhance characterizing the radiological environmental impact of Plant operations. The increased sampie locations and types in this manual, will be will be maintained unless it is determined that they are no longer useful or necessary data sites. The number and type will not be reduced below those stated in T.S. 3.22-1.

Two special sites that have been established are vegetable gardens maintained by site personnel. One is established at q the site boundary alongside the Clay Creek, and irrigated Q with water considered from the essential ef fluent for stream.

comparisons These data to' vegetation are not irrigated with effluent stream water for determination of bioaccumulation for soil types common to the environs. The second garden is at the North of the site, and is irrigated with domestic water. Washed vegetable from this sight will be compared to the Lite l,oundary washed vegetables for the comparison studies. Linwashed Samples will be taken from this garden to evaluate possible airborne materials to the North of the site via the gaseous ef fluent exposure pathway.

All of the locations s e '. e c t e d for the Radiological Environmental Monitoring Program, present and future, are  ;

designated in Table 3 for environmental samples. Health '

Physics Implementing Procedure HPlP.2001, Radiological Environmental Monitoring Operations, contains detailed maps  ;

on which the sampling and monitoring locations are marked.

l Table 4 lists the locations selected for the environmental thermoluminescence dosimeters. HPIP.2001 Radiological Environmental Monitoring Operations, contains detailed maps on which the sampling and monitoring locations are marked.

O v i

() -

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1

, PAGE 15 0F 27

' TABLE I TWO LETTER DESIGNATION TO IDENTIFY THE TYPE OF SAMPLE LETTER DESIGNATION TYPE-0F SAMPLE REPRESE1TEQ AS Air Sample RW Runoff Water SW Surface Water OW Drinking Water WW Well Water MS Mud and Silt MF Milk Sample (Cow)

RB Rabbit SL Soil HS Honey Sample BF Beef Tissue BT Beef Thyroid Fish Sample O. FS LV . Garden Vegetation AG Algae Sample PV Pasturage TL Thermoluminescense Oosimetry SG Small Game FG Frog CF Crawfish PH Pheasant DU Ouck RI Rice Additional letter designation may be added as sample designators

, if additional sample types are collected for analysis.

1 I

l l

4 i

O l

I

. _ . - ~ - , .. - . _ _ , _ , _ __ - - _ . . . _ . . . - . . _. . - - - .

._,I

('^')

\m '

' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1 PAGE 16 0F 27 TABLE 2 SECTOR LETTER DESIGNATIONS USED IN SAMPLE IDENTIFICATION SECTOR LETTER LELTOR DEGREES AND TRUE NORTH COMPASS SECTOR 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

/

(_)N- H 146.25 T0 168.75 SSE J 168.75 T0 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 0 303.75 TO 326.25 NW R 326.25 TO 348.75 NNW The letters "I" and "0" are not utilized. This reduces the chances for mistaking them as numbers one and zero respectively.

l 1

(~h V

l A

( RADIOLOGICAL ENVIRONME2 AL MONITORING PROGRAM MANUAL REVISION: 1

__ PAGE 17 CF 27 7ABLE 3 RADIOLOGICAL ENVIF0UMENTAL SAMPLING LOCATIONS SAMPl.E TYPE SAMPLE COLL EC TION DESCRIPTION OF LOCATION IDEN"IFICATION CLASS FRECUENCY Location Name/ Degrees /Mi

__LQ111 IOd) _

AIR SAMPLES RAen.lC0 INO Weekl,/ On Site / 54 /0.1 (AA80)

RASO.6K0 INO Weekly Tokay Substation /192 /0.6 (RA00)

RAS 6.200 INO Weekly Miller Residence /310 /6.2 (RAA0)

RAS 7.8C0 IND Weekly Carbondale / 53 /7.8

(~'/)

\_ (RAF0)

FAS9.0E0 INO Weekly Ione / 88 /9.0 (RAE0)

RAS 10.H0 CON Weekly Fish Hatchery /149 /10. l (RAG 0) l l

RAS 18.K0 CON Weekly Lodi Substation /212 /18.  !

(RAC0) 1 RAS 23.00 CON Weekly SMVD Headquarters /315 /23.

(RAB0)

MILK SAMPLES RMFO.800 INO Weekly Marciel Ranch / 75 /0.8 (RMF00)

RMF5.8P0 INO Weekly Mederios Dairy /298 /5.8 (RMFAO)

, RMF8.2K0 IND Weekly Angelo Dairy /204 /8.2 g-) (RMFBO) v

) aA010 LOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1 PAGE 18 0F 27 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION 10ENTIFICATION CLASS FREQUENCY location Name/ Degrees /Mi

_[0LO 108)

RMF10.N0 INO Weekly Warmerdam Dairy /260 /10.

(RMFBO)

RVN0FF WATER RRWO.3M0 IND Biweekly- Ef fluent Discharge /250 /0.3 (RRWCO)

RRW0.6M0 IND Biweekly Site Boundary /255 /0.6 (NEW)

SURFACE WATER RSW0.7hu (ND . Monthly Water Sump /265 /0.7

(NEW)

RSW1.3F0 IND Monthly Rancho Seco Reserv. /104 /1.3 (RSWCO)

RSW3.7NO CON Monthly Folsom South Canal /262 /3.7 (RSWBO) 1 RSW12.G0 CON Monthly Camanche Reservoir /130 /12.

(RSWAO)

! i 1

ORINKING WATER RDWO.lGO INO Monthly Rancho Seco Site /NA /0.1 (RWWCO)

RAIN WATER 4

RRN0.800 th0 5easonal Marciel Ranch / 75 /0.8 '

, (NEW) i

( ]) RRN23.K0 CON Seasonal SMUD Headquarters /315 /23 (NEW) i

() RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 'l PAGE 19 0F 27 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION IDENTIFICATION CLASS FREQUENCY location Name/ Degree:/H1 (0LD 10#)

PASTURAGE RPVO.6MO IND Monthly Site Boundary /255 /0.6 (NEW)

RPVO.8N0 INO Monthly Silva Property /260 /0.8 (NEW)

RPV0.800 IND Monthly Marciel Ranch / 75 /0.8 (RLVHO)

RPV1.5N0 IND Monthly Silva Property /264 /1.5 (NEW)

O RPV1.8N0 (NEW)

IND Monthly Silva Property /268 /1.8 RPV5.8P0 IND Monthly Mederios Osiry /298 /5.8 (RLVFO)

, RPV8.2K0 IND Monthly Angelo Dairy /204 /8.2 (RLVGO)

RPV10.N0 IND Monthly Warmerdam Dairy /260 /10.

(RLVE0)

WELL WATER RWW0.lG0 IND Quarterly Site Well /138 /0.1 (RWWAO)

RWWO.800 CON Quarterly Marciel Tsanch / 75 /0.8 (NEW)

RWWO.8L0 IND Quarterly Clay Cattle Feedlot /215 /0.8 (RWWE0)

, RWW1.6G0 IND Quarterly Rancho Seco Reserv /120 /1.6 L (NEW) l

(~N RA010 LOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL

's ,) REVISION: 1 PAGE 20 0F 27 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS

~

-SAMPLE TYPE SAMPLE . COLLECTION DESCRIPTION OF LOCATION IDENTIFICATION CLASS FREQUENCY location Name/ Degrees /Mi (OLO 1081

• RWW1.8F0 CON Quarterly Rancho Seco Reserv /114 /1.8 (RWWE0)

RWW2.lM0 IND Suarterly Clay Area Well /254 /2.1 (RWW80)

MUD AND SILT RMSO.3M0 IND Quarterly Ef fluent Discharge /250 /0.3 (NEW)

RMSO.6M0 INO Quarterly Site Boundary /255 /0.6 (RMSE0)

I\- RMS0.7N0 IND Quarterly Water Sump /265 /0.7 (NEW)

RMSI.3F0 IND Quarterly Rancho Seco Reserv /104 /1.3 (RMSCO)

RMS1.8N0 INO Quarterly Confluence of Clay /272 /1.3 (NEW) and Hadselville Creeks RMS2.2N0 IND Quarterly Hadselville Creek /260 /2.2 (NEW) above Clay Station Road RMS3.7N0 IND Quarterly Laguna Creek at /260 /3.7 (NEW) Folsom South Canal RMSS.4M0 IND Quarterly Laguna Creek at /256 /5.4 (NEW) Laguna Rrad RMS10.M0 IND Quarterly Laguna Creek at /259 /10.

j (NEW) McKenzie Road RMS12.G0 CON Quarterly Camanche Reservoir /130 /12.

(NEW)

,, , , . , - . , ,e. - - - ~

/~'\ RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL

\~) REV-ISION: 1-..

PAGE 21 0F 27 RADIOLOGICAL ENVIRONMENTAL SAMPllNG LOCATIONS SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION IDENTIFICATION. CLASS FREQUENCY location Name/ Degrees /Mi (OLO 10#)

FISH SAMPLES RFSO.3M0 INO Quarterly Effluent Discharge /250 /0.3 (RFBO)

RFS0.6M0 IND Quarterly Site Boundary /255 /0.6  ;

(RF00)

RFSO.7N0 li!D Quarterly Water Sump /265 /0.7 (NEW)

RFSl.3F0 CON Quarterly Rancho Seco Reserv /104 /1.5 (RFAO)

() RFSl.8NO (NEW)

IND Quarterly Confluence of Clay and Hadselville Creek

/272 /1.8 RFS2.2N0 IND Quarterly Hadselville Creek /260 /2.2 (NEW) above clay Station Road.

RFS3.7NO IND Quarterly laguna Creek Near /260 / 3 . 7 Folsom South Canal RFS5.4M0 IND Quarterly Laguna Creek at /256 /5.4 (NEW) Laguna Road RFS10.M0 IND Quarterly Laguna Creek at /259 /10 McKenzie Road (NEW)

ALGAE SAMPLES RAGO.3M0 IND Quarterly Ef fluent Discharge /250 /0.3 (RBAO) l RAGO.6MO IND Quarterly Site Boundary /255 /0.6 )

4 (NEW)  ;

RAGO.7N0 INO Quarterly Water Sump /265 /0.7

!() (NEW) i l

, , , , ,,n-

O -RADIOLOGICAL ENVIRONVENTAL MONITORING PROGRAM MANilAL REVISION:

PAGE 1

22 0F 27 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION IDENTIFICATION CLASS FREQUENCY Location Name/ Degrees /Mi (0LO [08)

RAGl.3F0 CON Quarter'ly Rancho Seco Reserv /104 /1.3 (NEW)

RAGl.8N0 INO Quarterly Conf 1'ence u of Clay /272 /1.8 (NEW) and Hadselville Creek RAG 2.2N0 IND Quarterly Hadselville Creek /260 /2.2 (NEW) near Clay Station Road RAG 3.7NO IND Quarterly Hadselville Creek. /260 /3.7 (RBB0) at Folsom South Canal RAG 5.4M0 INO Quarterly Laguna Creek at /256 /5.4 (NEW) Laguna Road

() RAG 10.M0 (NEW)

IND Qu a r t e rl y Laguna Creek at McKenzie Road

/259 /10.

RABBIT l

RRBX.XN0 IND Quarterly West of the Site Boundary /X.X l (NEW)

SALL RSLO.6M0 IND Quarterly Site Boundary /255 /0.6 (NEW)

RSLO.7N0 IND Quarterly Silva Property /250 /0.7 (NEW)

RSLl.3F0 CON Quarterly Rancho Seco Reserv /104 /1.3 (NEW)

I

! RSI.l.5N0 IND Quarterly Silva Property /264 /1.5

',, (NEW) h s/

RSLI.8N0 (NEW)

IND Quarterly Silva Property /268 /1.8 I

/^\ RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL (m / REVISION: 1 PAGE 23 0F 27 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION IDENTIFICATION CLASS FREQUENCY Location Name/ Degrees /Mi (0LD 108)

CRAWFISH RCFO.6M0 IND Quarterly Site Boundary /245 /0.6 (NEW)

RCF0.7N0 IND Quarterly Water Sump /265 /0.7 (NEW)

RCF3.7N0 INO Hadselville Creek Quarterly /260 /3.7 (NEW) at Folsom South Canal ex RCF10M0 IND Quarterly Laguna Creek at /259 /10

() (NEW) McKenzie Road GARDEN VEGETABLES HARVESTED AT LEAST SEM!-ANNUALLY (= SA),

MONTHLY THROUGHOUT THE GROWING SEASON) (= MTGS)

RLV0.5A0 IND SA-HTGS Site Garden North / 5 /0.5 i (NEW)

RLV0.5E0 IND SA-MTGS Site Garden East / 92 /0.5 (NEV 1988) l RLV0.5J0 IND SA-MTGS Site Garden South /182 /0.5 (NEW 1988) l RLV0.5N0 IND SA-MTGS Site Garden West /275 /0.5 l (NEW 1988)  !

RLVO.6M0 IND SA-MTGS Site Garden at Site /245 /0.6 (NEW) Boundary, irrigated with l

Clay Creek Water j l

RLV2.lM0 IND SA Clay Staiion Area /250 /2.1

, (RLVAO)

{

(~3 RLV9.5E0 IND SA lone Area / 90 /9.5

'N_/ (RLVCV0) l l

1

O RADIOLOGICAL ENVIRONMENTAL M0dITORING PROGRAM MANUAL REVISION:

PAGE 1

24 0F 27 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION IDENTIFICATION CLASS FREQUENCY location Name/ Degrees /Mi (0LD 108)

RLVll.J0 IND SA Clements Area /171 /11.

(RLVCO)

RLV11.R0 IND SA Sloughhouse Area /341 /11 (RLV00)

RLV18.K0 CON SA Lodi Area /212 /18 (RLVFO)

HONEY RSHX.XN0 IND SA NEAREST HIVES TO THE WEST (NEW)

O BEEF TISSVE RBFX.XN0 IND SA BEEF TISSVES FROM CATTLE (NEW) RAISED WEST OF THE SITE BEEF THYR 010 RBTX.XN0 IND SA THYROID GLAND FROM CATTLE THAT (NEW) WERE RAISED WEST OF THE SITE PHEASANT RPHX.XN0 IND ANNUALLY PHEASANT TAKEN WEST OF THE (NEW) SITE S0VIRREL RSQX.XN0 INO AS NEEDED COLLECT FROM WEST OF THE PLANT (NEW 1988) NEAR SITE B0UNDARY GARDEN To be collected if squirrel

, meat enters food chain

4 RADIOLOGICAL ENVIRONMENTAL MONITOR'NG PR0' GRAM MANUAL O. _

REVISION:

PAGE 25 0F 27 1

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS SAMPLE TYPE SAMPLE COLLECTION DESCRIPTION OF LOCATION IDENTIFICATION CLASS FREQUENCY - Location Name/ Degrees /Mi '

(0LD 108)

FROGS RFG0.6M0 IND Quarterly Site Boundary / 255 /0.6 RFG2.2N0 IND Quarterly Hadselville Creek / 260 /2.2 L at Clay Station Road -;

RFG3.7NO IND Quarterly Hadselville Creek /260 /3.7 at.Folsom South Canal RFG10.M0 IND Quarterly Laguna Creek at / 259 /10.

McKenzie Road O

i i

l I

\ l e

i 2

- y J - - - -

r--, -- -

c-- ..e,,,-,-.,..,,,,rm, . , , ,,,....,y--,r c---.-.7- r-,-w-c-e,.,,,,_+g-,-r -

• w v- v-y-.g,y--- -y.evny-=--

l l ). RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL i REVISION: 1 PAGE 26 0F 27 )

TABLE 4 ENVIRONMENTAL THERM 0 LUMINESCENT 00SIMETER LOCATIONS i IDENT/DESIG CLASS TLD MAP

• IDENT/DESIG CLASS TLD MAP #

NUMBER IND/ CON NUMBER IN0/ CON RTLO.3R0 IND 1 RTLI 7LO -IND 21 RTLO.3E0 IND 2 RTL1.6JO IND 22  ;

$ RTLO.3NO IND 3' RTLI.8KO IND 23

, RTLO.3LO IND 4 RTLI.7HO IND 24

RTLO.3H0 IND 5 RTL3.8LO IND 25 RTLO.4E0 INO 6 RTL3.9K0 INO 26 RTLO.500 IND 7 RTL3.6J0 IND 27 ,

O RTL6.200 IND 8 RTL3.7H0 IND 28 RTL23.00 CON 9 RTL4.2J0 INO 29 RTL18.K0 CON 10 RTL7.4M0 IND 30 i RTLO.6K0 IND 11 RTL3.7NO IND 31-i RTL9.0E0 CON 12 RTL4.8P0 IND 32  !

RTL10.N0 IND 13 RTL3.8M0 INO 33 i RTL11.M0 CON 14 RTL3.8QO IND 34

RTL10 H0 CON 15 RTLI.9N0 IND 35 RTL2.7LO IND 16 RTLI.6P0 IND 36 RTL8.2KO IND 17 RTLI.900 IND 37 i l j RTL7.8CO IND 18 RTLI 6RO IND 38

RTLO.7G0 IND 19 RTLI.580 IND 39 RTLI.5M0 INO 20 RTLI.5A0 IND 40 i

-,7-- , ,-- -

_ . . . , - . . , . , . -~, - - , . ,,..-r- --n , , _ - , , , , .---,~~~wx,-

i i

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION: 1 PAGE 27 0F 27 ENVIRONMENTAL THERM 0 LUMINESCENT 00SIMETER LOCATIONS l IDENT/DESIG CLASS TLD MAP # IDENT/DESIG CLASS TLD MAP #

NUMBER IND/ CON NUMBER IND/ CON RTLI.8C0 IND 41 RTLl4.P0 CON 61 RTL4.4G0 IND 42 RTLll.M0 CON 62 RTL1.8F0 IND 43 RTLO.800 IND 63 RTLI.6E0 IND 44 RTL9.5E0 IND 64 RTLI.8F0 INO 45 RTLI.400 IND 46 RTL3.0C0 IND 47 RTL3.700 48

() IND RTL3.2E0 IND 49 RTL3.5F0 IND 50 RTL10.E0 CON 51 RTL19.E0 CON 52 RTL12.GO CON 53 RTL11.J0 IND 54 RTL8.0P0 IND 55 RTL4.600 IND 56 RTL7.6A0 IND 57 RTL6.6B0 IND 58 RTL11.R0 CON 59 RTLil.A0 CON 60 O

V

l ANNUAL RADIOLOGICAL u RONMENTAL OPERATING REPORT -

1987 RANCHO SECO NUCLEAR GENERATING STATION l

TABLE B-1 LONER LIMITS OF DETECTION BY OTHER THAN GADMA SPECTROMETRY l Sample Tvoe ,_

Gross Aloha Gross Beta Sr-91_ H-3 K-40 I-131 Air Particulates 0.005 pC1/m3 0.002 pC1/m3 Vegetation 0.02' pCi/g Miik 1.0 pC1/1 0.5 pCi/1 F1sh (Flesh) 0.02' pCi/g 0.001' pC1/g Silt. Soil, Mud 0.05 pC1/g

, Hater 1.0 pCi/1 0.05 pCi/1 0.5 pCi/1 250 pCi/1 0.5 pCi/1

Algae 0.02' pCi/g Airborne Radiolodine 0.004 pC1/m3

'As dry weight.

P l

l 5 _ _ __ _ . _ _ _ - . . .-__ - ____- --_ - - ___ _ - - -._ _ _ _ -. - ..

O- ANNUALRADIOLOGICALENVIRATALOPERATINGREPORT O 1987 RANCHO SECO NGCLEAR GENERATING STATION I

TABLE B-2 i

i LOWER LIMITS OF DETECTION BY GAMMA SPECTROMETRY l

Milk & Air Animal Energy Algae Water Particulate Vegetation Tissue Mud / Silt MeV* Isotope oCi/am" DCl/1*** oC1/m3**** oC1/a(b) oCi/athl pCl/q(bl 0.122 Cobalt-57 0.004 2 0.001 0.004 0.01 0.004 0.134 Cerium-144 0.121 17 0.005 0.121 0.08 0.080 0.186 Radium-226 0.200 84 0.073 0.200 0.20 0.200 0.239 Lead-212 0.040 20 0.016 0.040 0.04 0.040 0.295 Lead-214 0.060 38 0.004 0.060 0.06 0.060 0.320 Chromium-51 0.246 18 0.010 0.246 0.02 0.246 0.344 Actinium-228 0.140 50 0.104 0.140 0.14 0.140 0.364 Iodine-131 0.025 1 (a) 0.030 0.03 0.025 0.476 Bery111um-7 0.236 40 0.01 0.750 0.75 0.,750 0.537 Barium-140 0.075 4 0.030 0.075 0.04 0.040 0.583 Thallium-208 0.060 16 0.018 0.060 0.06 0.060 0.605 Cesium-134 0.079 10 0.010 0.029 0.04 0.079 0.609 Bismuth-214 0.100 40 0.030 0.100 0.10 0.100 0.622 Ru,Rh--106 0.143 10 0.001 0.143 0.04 0.040 0.662 Cesium-137 0.056 2 0.001 0.040 0.04 0.056

'Id energy for the nuclide - other energy lines exist.

• • Based on 100 grams (wet weight).

• • • Based on 1 litgr.

• • • • Based on 265m5 volume of air, (a)0.01 pC1/m3 If CEP receives charcoal cartridges within 24 to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and 0.02 pCi/m3 for a tridges received 48 to 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> after collection.

(b[> Based on 250 grams.

.. . = -_. . . . _ _ _ -. ._

ANNUAL RADIOLOGICAL ENVIR NTAL OPERATING REPORT 1987 RANCHO SECO NUCLEAR GENERATING STATION TABLE B-2 (Continued)

LOHER LIMITS OF DETECTION BY GAMMA SPECTROMETRY Milk & Air Animal Energy Algae Water Particulate Vegetation Tissue Mud / Silt' MeV' Isotope DC1/am** oCi/1*** oC1/m3'*** DC1/a(b) oC1/a(b) oC1/a(b) 0.756 Zirconium-95 0.041 8 0.0' s 0.041 0.04 0.066 4

0.765 Niobium-95 0.034 8 0.026 0.034 0.03 0.034 0.765 Zirconium, Niobium-95 0.066 8 0.026 0.066 0.08 0.066 0.810 Cobalt-58 0.017 3 0.001 0.020 0.06 0.017 0.835 Manganese-54 0.021 2 0.001 0.021 0.06 0.021 1.095 Iron-59 0.024 3 0.006 0.021 0.10 0.024 1.115 Zinc-65 0.060 16 0.045 0.060 0.10 0.0f3 1.173 Cobalt-60 0.058 5 0.019 0.063 0.03 0.058

. 1.460 Potassium 1.600 662 1.172 1.60 1.60 1.60 1.596 Lanthanum-14C 0.465 4 0.030 0.075 0.04 0.040

• Id energy for the nuclide - other energy lines exist.

• • Based on 100 grams (wet weight).

Based on 1 liter.

1 **** Based on 265m3 volume of air.

1 (a)0.01 pC1/m3 if CEP receives charcoal cartridges within 24 to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and 0.02 pC1/c3 for cartridges received 48 to 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> after collection.

(b) Based on 250 grams.

___ _ _ _ - _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ . - _ . - ~.. _ _ __

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

() UNCHO SECO NUCLEA ENERATING STATION TABLE B-3 RADIOLOGICAL ENVIRONMENTAL REPORTING LEVELS Airborne Particulate Water or Ggses Fish Milk Food Products Analvsis Ioci/1) (oCi/m3 B Ci/am drv) (oCi/1) (oCi/am drv) ___

4 H-3 2x10 3

Mn-54 lx10 2

Fe-59 4x10 3

Co-58 1x10 2

Co-60 3x10 2

Zn-65 3x10 2

Zr-No-95 4x10 I-131 2 0.9 3*

Cs-134 30 10 00 O Cs-137 50 20 70 V Ba-La-140 2x10 2

300 Gross Beta 40 2 10**' 10**

• Full gamma isotopic analysis if I-131 exceeds reporting level of 3 pCi/1.

• • Edible food must have gamma isotopic analysis if Gross Beta minus K-40 exceeds 10.

• • • Fish is required to have full gamma isotopic analysis if the Gross Beta minus K-40 exceeds 10 pCi/g (dry).

.O V

.. . .-- .- .- . - ~ . . -- - -

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 RANCHO SEC0 NUCLEAR GENERATING STATION [

TABLE B-4  :

COL', 'CTION SCHEDULE >

Sample Letter Collection. Number Tvoe Desianation Freauency of Locations i Runoff Hater RH Twice-Monthly 2 Surface Hater SH Monthly 4 Drinking Hater DH Monthly 1 Hell Hater HH Quarterly 5 Mud and Silt MS Quarterly 10 Soil SL Quarterly 5 .

Fresh Milk MF Heekly 4 j l

y Fish FS Quarterly 9 Human Vegetation LV Quarterly 7  ;

Algae AG Quarterly 8 Pasturage PV Monthly 8

Frog FG Quarterly

• 3 i Crawfish CF Quarterly

• 3 )

Air Sample AS Heekly 8 I Honey HS Semi-yearly

• 1 Beef Tissue BF Semi-yearly

• 1 l Beef Thyroid BT Semi-yearly

• 1 Small Game SG Quarterly

• 1 l

j Rabbit RB Quarterly

• 2

! TLD TL Quarterly 64 i i

• Sampled when available l

1

1 ANNUAL RADIOLOGICAL EN MENTAL OPERATING REPORT i 1987 RANCHO SECO NUCLEAR GENERATING STATION TABLE B-5 SAMF.E COUNTING TIMES i

Garma Sample Tvoe Gross Alpha GreAs Beta Spec. I-131 Sr-90 Sr-89 Tritium j Air Particulate 100 min. 100 min. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

.j Algae 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Vegetation 100 min. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 100 min.

I Animal Tissue 100 min 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Milk (Fresu) 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 100 min.

I Mud and Silt, Soll 100 min. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Water 100 min. E hours 100 min. 100 min. 100 min. 540 min.

Airborne Radiolodine 100 min.

3 i

i i

i l

f l

i.

___.__-___-----_-_______.__.___._____.________.____a_ _ _ _ _ _ _ _ __ _ _ - _ _ _ _ _ __m-ww.--

reus-_ _ w----_ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ . _ _ _ _ _ - _ _ _ _ _

_ . = . _ _ . _ _ . _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ . . . . - . ~ _ .

ANEUAL RADIOLOGICAL ENV HENTAL' OPERATING REPORT

~

1987 RANCHO SECO NUCLEAA GCNERATING STA1 ION I

TABLE B-6 i

ALI000T USED FOR DETECTION LIMIT CALCULA. TION AND ACTUAL ANALYSIS Gross Alpha Samole Type and Beta Sr-89. Sr-90 Gammt. H-3 K-40 I-131

] __

Air Particulate 265 m3 Vegetation, Food Products 10.0 g 250 g 0.! g

] 2.01

Milk 1.01 Water 1.01 1.01 1.01 0.0031 1.01 i Silt. Sail and Mud 10.0 g 250 g Animal Tissue, Fish 10.0 g 250 g 0.1 g Algae 100 g Airborne Radleiodine 265 m3 4

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 l RANCHO SECO NUCLEAR GENERATING STATION 1

l l

l l

I l

i I

APPENDIX C INTERIABORATORY COMPARISON PROGRAM O

RN o , __ e

. b==de amd Controls for Environmental Pollution, Inc. -

1925 Aosina . P. O. Box 5351' . Santa Fe, New Mexico 87502 . Teleonons 505 982-9841' February 12,1988 Mr. Donald W. Martin Manager, Environmental Protection Department Rancho Seco Nuclear Generating Station 14440 Twin Cities Road Herald, CA 95638-9799

Dear Mr. Martin:

In response to your letter (EP88-0253) of January 27, 1988, the following information is provided.

We have no problem conforming to your new required Lower Limits of Detection (LLD's).

og Our LLD's are still less than or equal to the new levels, The reporting limits vill be incorporated into our program for the Rancho Seco Nuclear Generating Station and will replace any previous lists.

The types of analvsis to be performed by us have been changed to reflect those lit.ted in your techt ital specifications on Tai >1e 3.22-1. Reports of analysi., e :li also change to reflect '/our requirements.

Enclosed you will find a repc" of our 1987 EPA Cross-Check results.

On February 3,1988, we sent to Bill Wadman the draft copies of your fourth quarter 1987 REM P report. They were forwarded by overnight courier.

Call me if you have any questions.

Very trulv-yours,

"~ CONTROLS FOR ENVIRONMENTAL PO L LUTION, INC.

^

/ /

$ ,.Ylb(IDD g\ Bob Bates Contracts Administration Manager BB/pp Enclosure cc: James J. Mueller, CEP E ).w 1:$Q Cu Rt :- ::-- :.'.s a  ;

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EPA CROSS-ClfECK PROGR AM 1937 l

l Radionuclides in Air Filters EPA CEP Date Known Value Reported Value j

Parameter pCi/ filter 11 o l pCi/ filter 12 a i 4/37 Gross Alpha !4 + 5 20 + 1 IS 1 17 1 Gross Beta 43 2 5 63+2 6472 66[2 Strontium-90 17 + 1.5 19 + 10 23 ~+ 10 ,

24 10 Cesium-137 8+5 17 + 5

, 19 + 5 20 I 5 8/37 Cross Alpha l

10 1 5 10 + 1 12 7 !-

! 3 .' '

Cross Beta 30 + 5 '9+2 31 _! 2 33: 2 S tron tium-90 10 l.5 3+1 9+1~

9;1 Cesium-137 10 5 3+5 ~

10 _+ 5 10 5

. .._-.. - . . . . . . - - . _ . . . . . _ . . . . . _ - _ _ _ _ . ~ . _ _ _ . _ _ - . ._ ._ _ . . . _ -

4 l'

EPA CROSS-CI(ECK'PflOCR AAj i 1987 Cross Alpha and Gross Beta in Water EPA- CEP

_ Date Known Value Reported Yalue Parameter pCi/l11 o oCi/112 0 1/37 Gross Alpha

!! 1 5 12 + 2 1272'

~

12+2-Gross Beta 10 1 5 22 + 6 25 _: 6' .

27 1 7 3/87 Gross A;pha 313 4+2 4!2 452 .

Gross Beta 13 + 5 ~

l< 12+4 '

, 9+4 i

-374 -

5/37 Gross Alpha 11 2 5 1I + 2

!! 2 2 .!

12 - 2

~

Gross Beta 7 _, , -

17 + 6 13 + 6 7/S7 1926 Gross Alpha 5:5 4+2 5.52 6+2 ~

Gross Beta 5 35 6+3 7-~ 3 973

~

9/37 Gross Alpha

• tS 3+1 3!!

3 ~ !-

Gross Beta 12 + 5 -

L3 _+ 1 13 ~+ 1 l

5 1 1 l

=----y w e . =--=w===rrwww evy-- w w w a ww -ve-,t---wrw-r-e+,s.w-w--w i =w w - w -

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EPA CROSS-CHECK PROGR AM 1987 Gross Alpha and Cross Beta in Water (Cont.)

EPA CEP Known Value Reported Value Date Parameter pCi/l 1 I a i pCi/l 12 a l 11/37 Gross Alpha 715 62 712 312 Cross Beta 19 1 5 16 3 13 3 3 20 1 3 U l l

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l EPA CROSS-CHECK PROGR AM 1987

\

Gamma in Water I

EPA CEP Known Value Reperted Value Date ' Parameter pC!/l1 I o pCl/l12 a 2/87 Cobalt-60 30 15 55 , 5 55 '1'5, 56 _+ 5-Zinc-65 102 + 7 91 1 5 ~

114 + 6-103 + 6 Ruthenium-106 ~ 100 1 5 93 ~+ 5 105 + 5 103[5 Cesium-134 59+5 61 + 3 -

57+2 60 + 3 Cesium-137 '

37 1 5 109 + 6

~

93 _+ 6 102 -

5

) 6/37 Cobalt-60 64 1 5 69 + 5 6925 71 _+ 5 .

Zinc-65 10 1 5 12 + 3 14 _73 t6 _+ 1 Ruthenium-106 75 1 5 30 + 5 75 5 7173 Cesium-134 40 1 5 40 + 3 39 + 3 3S _+ 3 Cesium-137 30 1 5 '32 + 5

~

34 + 5

~ 35 1 5 Chromium-51 41 1 5 46 + 3

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i EPA CROSS.Clf Ep.K PROGR AM 1937 Gamma in Water (Cont.)

EPA CEP Known Value Reported Value Date Parameter pCi/l 11 a pCi/112 e i

10/87 C'hromium-51 70 + 5 66 + 3 67 1 3 l 73 3 8 i Cobalt-60 l5 3 5 :7 1 2 13 1 2 19 3 2 Zinc-65 46 + 3 55 + 15 57 15 61 15 Ruthenium-106 61 5 7I 10 g'%  ;

V I5 1 10 79 10 i

Cesium-134 25 + 5 26 + 3 l 26 - 3 ,

27 - '.  !

Cesium-137 51 + 5 56 5 56; 5 SS 5 l

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r 4 V EPA CROSS-Cl{ECK PROGR AM l 1937 Tritium in Water EPA CEP Known Value Reported Value

_Da te Parameter pCi/l1 I a pCi/l12 a 2/37 Tritium 4209 + 421 4600 + 500 4510 1 500, 4330 300 6/37 Tritium 2393 2 357 2366 3 235 2331 1 233 2792 1 233 10/37 Tritium 4492 + 449 3367 + 300 3925 1 300 4211 1 300 1

V 1 1

1

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EPA CROSS-CllECK PROGR AM 1987 Strontium In Water EPA CEP Date Known Value Reported Value Parameter pCi/l1 ! a pCi/l 12 o 1/87 Strontium-89 25 + 5 15 + 5 17 1 6 20 1 5 Strontium-90 25 1 1.5 1

22 1 5 {

24 1 6  ;

24 1 5 \

$/37 S tron tium-39 i 41+5

~ 26 + 5 I 34 ; 5 '

\

34 1 5 Strontium-90 20 + !.5 14+3 15 + 3 <

17 ; 3 '

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(D sg EPA CROSS-CHECK PROGR AM 1937 lodine-131 in Water I

1 l

EPA CEP Known Value Reported Value

__ Da te Parameter pCi/11 I a pCi/112 0 3/37 Low Level

• 7.0 1 0.7 2+i

~

2 4 214 3/37 High Level 43 1 6 43 3 5 41 1 4 i 39 1 3 10/37 Mid Level 26 + 6

- l9+4 20 ~14 -

22 1 4 O ' Unable to reanalyze due to half-life decay.

e se

l.

EPA CROSS-CliECK PROGR AM 1987 Radionuclides in Milk ,

EPA CEP Known Value Reported Value l Date Parameter pCi/l1 to pCi/li 2 a 6/37 S tron tium-90 ' 35 + 1.5 29 + 3 23 3 3 32 1 3 Cesium-137 74 + 5

~

75 + 2 77[2 70 1 2 Strontium-89

• 69 5 5+2 5+2 472 lodine-131 59 6 63 3 2 64 3 2 60 1 2 Potassium 125

! r> l 7 + ! $0 mg/!

1643 150 mg/l 1643 ISO mg/l 10/37 EPA cancelled Milk Study due to EPA facility being reroofed.

' Unable to reanalyze due to limited sample.

O

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EPA CROSS-CitECK PROG!t \M 1937 lodine-131 In Milk .

I EPA CEP Known Value Reported Value Date Parameter pCi/l i 10 pCi/l 12 0 2/37 Low Level 9.0 + 0.9 9.0 + 1.0 '

3.0 + 0.5 i 3.010.5 O

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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1987 O RANCHO SECO NUCLEAR GENERATING STATION l

I APPENDIX D l

HISSING SAMPLES 1

1 i

5 0

I l

AN';UAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT f

l 1987 RANCHO SECO NUCLEAR GENERATING STATION l

l 1

l l

Table D-1 give the locations at which samples were missing i

O l

1 i

l O

F-l ANNUAL RADIOLOGICAL ENVIRONHENTAL OPERATING REPORT

- 1987

( RANCHO SECO NUCLEAR GENERATING STATION TABLE D-1 HISSING SAMPLES Samole Tvoe Samole Date Samole location -Reason TLD 1st Quarter Route 104 Entrance (0.5 miles) Missing TLD lst Quarter S.H. Hilk Station (8.2 miles) Missing TLD 1st Quarter S.E. of Site (4.4 miles) Missing TLD 1st Quarter N.N.E. of Site (6.6 miles) Missing TLD 2nd Quarter S. of Site (3.6 miles) Missing TLD 3rd Quarter E.N.E. of Site (3.7 miles) Missing TLD 3rd Quarter S. of Site, Clements (11 miles) Missing TLD 3rd Quarter N.N.E. of Site (6.6 miles) Missing TLD 4th Quarter H. Hilk Station (10 miles) Missing TLD 4th Quarter S.S.E. of Site (3.6 miles) Missing TLD 4th Quarter N.N.E. of Site (6.6 miles) Missing TLD 4th Quarter S.W. of Site, Galt (11 miles) Missing Missing samples appear to have been stolen. Investigation of areas where samples were missing indicated evidence of vandalism and theft. Cages and samples were entirely removed. There was no evidence of weather, or other causes which could have resulted in missing TLDs. Missing sampling equipment has been replaced.

O

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT' 1987. 'l i O RANCHO SECO NUCLEAR GENERATING STATION I

t 3

l l

t APPENDIX E HISSING DATA FROM THE O ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1986

l O -

e - - = - ~ # w re - - e %e- ww- w wwm,--_,_ m,s.-.yry,w .mm, w wwwny ,g_. . mm, _ . . wwy ewwwg , ym-

Lawrence Livermore National Laboratory March 30, 1987 Mr. E.W. Bradley -

Health Physics Support

& Environmental Programs Mail Stop 292 Sacramento Municipal Utility District '

Sacramento, CA 95813 j w.

Dear Ed,

N Enclosed is a Table of data, just completed, showing a comparison of radionuclide results in cores collected in August 1986 and Octocer 1984. The w cores were collected from an irrigation pond off Hadselville Creek on the property of G. Silva, 6.0 km from Cancho Seco. A diagram showing the location ,

of the pond relative to other geographical features is enclosed. The analysis of the sediment was completed too late for inclusion in _the recent UCIO Report (UCIO-20963). The results from the 1984 corc were published in UCID-20298, p. '

34. Note, however, there was an error in the reported area (0.001257 sq. m) of the core. The correct value should be 0.002425 sq. m.

I show this comparison to support several points raised and discussed in UCIO-20963. The' concentrations (pCi/g/ of 137Cs and 134Cs in the surface 10 cm of sediment cecreased (as they did everywhere in sediments from 'tne creek.s) between 1984 and 1986. The sediment column inventory (PCl/m2) however, changed only slightly during the 1.83 year period between the two collections. If the 1984 results are decay corrected to Augutt 1986 (values snown in the Table), the inventories of 137Cs, 134Cs, and 60Co are nearly identical to the measured inventories. The surf ace concentrations decreased

~N as a result of mixing niin lesser contaminated sediments bu: there has been

[b little riet cnange in the total sediment inventory. This reinforces the need to comolete some detailed analysis on sections of cores fr09 the cifferent creeks.

v. !<;s , u -

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• Page two Ed Bradley ,

3/30/87 More important, howevEr,'is the fact that concentrations of 137Cs in the_ flesh of catfish from this pond decreased from 5.1 -pCi/g in Feb. 85 to 0.18 pCi/g in Aug. 86 (see Table 5, UCIO 20963, data f rom Station R 52; labelled incorrectly as Station RS-52.) The concentration of 137 C s in fish in most direct contact with thz sediments decreased oy over an order of magnitude while the sedimen.

inventories essentially remained unchanged. This suggests the concentrations bound to the sediments (and food components deriving I37Cs from sediments) are playir.g much less a role in maintaining fish body burdens 'an previously assumed. If true, the source of 137Cs accumulated by fish must bebhewater (and/or the food organisms deriving body burdens from the water). Therefore, if low concentrations can be maintained in water, the concentrations of I37 Cs in fish will b( l o'w'regardless of the levels and inventories in the sediments. He will try to reinforce this finding with the appropriate data from our sampling program this year.

Also, thank you for the July-Dec. 86 semi annual report. Using the data in the above and in your Jan.-June 1986 report, I compute that the mean ,

concentration of 137Cs in water released frota the plant over the year was 0.08 pCi/1. Note on page 27 of UCID 20963 Part 1, the mean concentration we determined in solution it Station RS-17 over the period sampled in 1986 was 0.05 0.04 pCi /1. I consider these values to be in good agreement. The )

results again confirm the ef fectiveness of the liquid-ef fluent control program.

Sincerely, Yb Victor E. Noshkin  !

Section Leader 4 Aquatic Sciences 4

VN/mt encls.

l

O O O .

Table 1. Concentrations of radionuclides in scdiment core samples from station It-52*.

(Number in parenthesis is the 1 sigma counting error expressed as percentage of the value listed; "<d!' means less than detection limits.)

Depth Sample Sample Sample interval dry wt g/sq. cm Concentration (pCi/g dry wt) Concentration (pCi/sq. cm)

ID (cm) (g) 1370s 134Cs 60Co 137Cs 134Cs 60Co Core collected 14 August 1986; Cross sectional area-24.25 sc. cm. #

687 0-2 19.94 0.82 12.6(1) 3.01(8) 0.87(7) 10.3 2.50 0.69 688 2-4 13.82 0.57 12.7(2) 2.96(4) 1.44(6) 7.7 1.69 0.82' 689 4-6 14.28 0.59 14.1(1) 3.18(5) 0.40(15) 8.3 1.88 0.24 690 6-8 17.58 0.72 14.8(1) 3.19(7) 0.61(12) 10.7 2.30 0.44 691 8-10 17.28 0.71 16.8(1) 4.02(3) 0.87(7) 11.9 2.85 0.62 692 10-12 18.64 0.77 13.0(1) - 3.00(7) 0.87(10) 10.0 2.31 0.67 693 12-14 17.01 0.70 5.95(4) 0.87(23) 0.79(8) 4.2 0.61 0.55 694 14-19 29.63 1.22 2.54(2) 0.29(24) <dl 3.1 0.35 < di Total 65.7 14.5 4.1 Core collected 17 October 1984; Cross sectional area-24.25 sq. cm. (see UCID-20298).

J304 0-2 9.06 0.37 21.0(1) 8.40(2) 0.97(11) 7.77 3.11 0.36 J305 2-4 11.66 0.48 20.6(2) 8.80(2) 0.94(15) 9.89 4.22 0.45 J306 4-6 14.61 0.60 21.5(1) 8.90(2) 0.99(7) 12.90 5.34 0.59 J307 6-8 10.43 0.43 22.2(1) 8.30(3) 0.76(17) 9.55 3.57 0.33 ,

J308 8-10 18.19 0.75 17.6(1) ' 7.10(2) 0.83(9) 13.20 5.33 0.62 J309 10-12 15.41 0.64 8.56(3) 3.10(5) 1.31(10) 5.48 1.98 0.84 J310 12-14 17.14 0.71 4.60(6) 1.43(9) 1.33(13) 3.27 1.02 0.94 J311 14-16 14.87 0.61 4.68(5) 0.99(13) 0.99(13) 2.85 0.60 0.60 J312 16-20 53.50 2.21 4.03(2) 0.87(5) 0.56(10) 8.90 1.92 1.24 Total '73.8 27.1 6.0 Decay corrected to 14 Aug 86-- 70.5 14.4 4.7

• Irrigation pond off Iladselville Creek; 6 km from llancho Seco.

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• l V("% SMUD ucavro SACRAMENTO MUNICIPAL UTluTY DISTRICT O P. O. Box 15830, Sacramento CA SbSB;2-1830, (916) 452-3211 I AN ELECTRIC SYSTEM SERVINGTTMI5 H'6 ART OF CALIFORNIA m3 i;M -3 A 11: 01 MAY 0 21988 l l

GCA 88-299 I l

l l

U. S. Nuclear Regulatory Commission l Attn: J. B. Martin, Regional Administrator l Region V l 1450 Maria Lane, Suite 210 l Walnut Creek, CA 94596 l l

Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 )

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l

Dear Mr. Martin:

l The Sacramento Municipal Utility District hereby transmits two copies of the Annual Radiological Environmental Operating Report for 1987. The report is submitted to meet the requirement of Technical Specification 6.9.2.2 Annual Radiological Environmental Operating Report.

• Please contact me if you have any questions. Members of your

, staff with questions requiring additional information or clarification may contact Mr. Paul Lavely at (209) 333-2935, extension 4824.

Sincerely, G. Carl Andognin Chief Executive Officer, Nuclear cc: F. J. Miraglia, NRR, Rockville A. D'Angelo, NRC, Rancho Seco C. Hooker, NRC, Walnut Creek p4 4i _

RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Cities Road, Herald, CA 95638 9799;(209) 333-2935