ML081210549

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Annual Radiological Environmental Operating Report for 2007
ML081210549
Person / Time
Site: Rancho Seco
Issue date: 04/21/2008
From: Redeker S
Sacramento Municipal Utility District (SMUD)
To:
NRC/FSME, Region 4 Administrator
References
MPC&D 08-030
Download: ML081210549 (73)


Text

OSMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT The Power To Do More.

P.O. Box 15830, Sacramento, CA 95852-1830; 1-888-742-SMUD (7683)

MPC&D 08-030 April 21, 2008 U.S. Nuclear Regulatory Commission Region IV Administrator 611 Ryan Plaza Drive, Suite 100 Arlington, VA 76011-8064 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2007 Attention: Region IV Administrator In accordance with Rancho Seco Quality Manual, Appendix A, Section 1.5.3, we are submitting the Rancho Seco 2007 Annual Radiological Environmental Operating Report for the period of January 1, 2007 through December 31, 2007.

If you or members of your staff have questions requiring additional information of clarification, please contact Bob Jones at (916) 732-4843.

Sincerely, "Steve Redeker Manager, Plant Closure and Decommissioning Cc: NRC, Document Control Desk

- '2?5

.l RANCHO SECO NUCLEAR PLANT

  • 14440 Twin Cities Road, Herald,CA 95638-9799; (209) 333-2935

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY - DECEMBER 2007 Rancho Seco Nuclear Station Herald, California 10 CFR Part 50 License Number DPR-54 10 CFR Part 72 License Number SNM 2510

2007 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE OF CONTENTS TA BLE OF CO NTENTS ................................................................................................................................. ii LIST O F FIGURES ............. :............................................................................................................................ iii LIST OF TABLES. ............................................................ iv I. EXECUT IVE S UMMARY...........................................................................................................................  :. 1 I1.LA ND US E C ENS US .................................................................................................................................. 3 Ill. RADIO LOG ICAL IMPACT EVALUATIO N............................................................................................ 3 PREDICTED POTENTIAL RADIOLOGICAL IMPACT ................................................................... 3 FU EL CYC LE DO SE EVA LUATIO N ............................................................................................ 4 OBSERVED POTENTIAL RADIOLOGICAL IMPACT .................................................................. 4 IV. PROGRAM ANALYSIS RESULTS

SUMMARY

....................................... 7 IV-A. ATMOSPHERIC MONITORING ............................. 7 IV-B. DIRECT RADIATIO N MO NITO RING ............................................................................... 8 IV-C . TERRESTR IAL MO NITO RING .......................................................................................... 8 IV-D . AQ UATIC LIFE MO NITO RING .......................................................................................... 9 IV-E. WATER MONITORING ............................................ ...9 V. REFERENCES ................................................ . ......... 16 VI. APPENDICES.. .......................... 18 2007 LAND USE CENSUS RESULTS ..................................................................................... A-1 SAM PLE SITE DESCRIPTIO NS AND MAPS ................................................................................ B-1 QUALITY CONTROL SAMPLE ANALYSIS RESULTS ........................................................... C-1 SAMPLE COLLECTION AND ANALYSIS METHODS ............. I...................................... D-1 ENVIRONMENTAL MONITORING PROGRAM DESIGN .......................................................... E-1 2007 SAMPLE ANALYSIS RAW DATA TABLES .................................................................... . F-1 2007 MISSED SAM PLE REPO RT ............................................................................................ G -1 Rancho Seco Nuclear Station ii 2007 AREOR

LIST OF FIGURES FIGURE TITLE PAGE FIGURE B-1 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS ON AND NEAR THE SITE B-3 FIGURE B-2 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS WITHIN 1 MILE FROM THE REACTOR BUILDING -------------------- --------- B-4 FIGURE B-3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS FROM 1 TO 5 MILES FROM THE REACTOR BUILDING ------------------------- B-5 FIGURE B-4 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS 5 TO 25 MILES FROM THE REACTOR BUILDING -------------------------------------------------------- B-6 Rancho Seco Nuclear Station iii 2007 AREOR.

LIST OF TABLES TABLE TITLE PAGE 1 2007 LIQUID EFFLUENT PATHWAY POTENTIAL DOSE COMPARISON 6 2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

11 B-1 RADIOLOGICAL ENVIRONMENTAL MONITORING SITES AND MAP LOCATIONS B-7 C-1 2007 INTERLABORATORY COMPARISON PROGRAM C-4 E-1 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES E-9 E-2 MAXIMUM!(REQUIRED) LLD VALUES FOR ENVIRONMENTAL SAMPLES E-10 F-1 2007 WEEKLY AIR SAMPLE

SUMMARY

F-2 F-2 2007 LUXEL BADGE

SUMMARY

(DIRECT RADIATION) F-4 F-3 2007 GARDEN VEGETABLES F-5 F-4 2007 SEDIMENT F-5 F-5 2007 FISH F-6 F-6 2007 WELL WATER F-6 F-7 2007 RUNOFF WATER F-7 F-8 2007 SURFACE WATER F-8 F-9 2007 DRINKING WATER F-10 Rancho Seco Nuclear Station iv 2007 AREOR

.2007 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT,

1. EXECUTIVE

SUMMARY

This report contains results from the Radiological Environmental Monitoring Program (REMP) for the Rancho Seco Nuclear Station (RSNS) compiled for the period January 1, 2007 through December 31, 2007. The Radiation Protection/ Chemistry Group at RSNS conducts this program in accordance with the REMP manual. This report is compiled and submitted in accordance with the Rancho Seco Quality Manual, Appendix A, Section 1.5.2.3 [RS02].

The results of the 2007 Radiological Environmental Monitoring Program showed that the operation of Rancho Seco Nuclear Station had no significant radiological impact on the environment.

Currently, the Plant is permanently shutdown and undergoing Decommissioning. During 2007 the major project for Decommissioning was the demolition of the concrete walls and floors in the Reactor Building. This project is scheduled for completion in May 2008.

During 2007 the Onsite liquid effluent Retention Basins were removed as part of the Decommissioning process. The Offsite Dose Calculation Manual was revised to indicate that were no longer there was no longer a major liquid source term and the retention basins required to be in place for the discharge of radioactive liquid effluents. The REMP was not revised to eliminate monitoring of the liquid effluent pathway to provide for post- operational data for this pathway.

Currently, the remaining pathways for the Rancho Seco Nuclear Station are:

1. Airborne gaseous pathway from the Reactor Building and Interim Onsite Storage Building (Radwaste storage)
2. Direct radiation pathway, with the primary source being the Independent Spent Fuel Storage Instillation (ISFSI)

During the reporting period, the atmospheric, terrestrial and aquatic environs adjacent to RSNS were monitored. The sample measurements showed that the levels of radioactivity in the sampled media were consistent with previous year's evaluations. All detected nuclides (greater than minimum detected activity) were below the required Nuclear Regulatory commission (NRC) reporting levels. All Lower Limits of Detection (LLD) were at or lower than the maximum required by the NRC.

Doses resulting from ambient exposure to terrestrial and atmospheric direct radiation sources were measured through the placement and retrieval of Luxel monitoring badges. Direct radiation measurements attributable to Station operations, based on control and indicator locations, were indistinguishable above background levels. Two monitoring badge locations, placed in an area near the effluents discharge stream are being used to evaluate the higher than average soil activity.

Rancho Seco Nuclear Station 1 2007 AREOR

I. EXECUTIVE

SUMMARY

(Continued)

This activity is a result of historic monitored liquid effluent releases during Station operation.

One monitoring badge location in this area is indicating dose higher than the indicator average.

The dose at this location does not exceed the regulatory limits of 10 CFR Part 20. Onsite Luxel badge locations near the ISFSI access road show higher readings, attributed to the ISFSI, and are within design calculations.

Isotopic identifications were consistent with known releases of radioactive material from the Station to the atmospheric and aquatic environments. As expected, fish and sediment samples obtained, from the environment of the No Name and Clay Creeks contributed the majority of positive isotopic identifications. Cesium-137 and Cobalt-60 are the predominant nuclides identified in the aquatic environment.

Rancho Seco Nuclear Station 2 2007 AREOR

I1. LAND USE CENSUS The 2006 Land Use Census was conducted in accordance with the Rancho Seco Quality Manual [RS02] Section 1.4.3.2 and the Radiological Environmental Monitoring Program (REMP) manual section 4.0. This evaluation is in accordance with the requirements of 10 CFR Part 50, Appendix I, section IV.B.3. The land use census is performed on a biennial schedule and was performed during 2005/ 2006 and then completed in 2007. See Appendix A for results from this Land Use Census. The next land use census is scheduled to be conducted during 2007/ 2008 and completed in 2009.

I1l. RADIOLOGICAL IMPACT EVALUATION PREDICTED POTENTIAL RADIOLOGICAL IMPACT Gaseous Effluent Exposure Pathways The maximum calculated annual organ dose due to gaseous releases of tritium and particulate isotopes was 1.94 E -02 mRem (as calculated using the Rancho Seco Offsite Dose Calculation Manual (ODCM)). This calculated organ dose was 1.29 E -01% of the associated Rancho Seco Quality Manual (RSQM) [RS02] limit (10CFR50, Appendix I guideline).

Noble gases were not released in 2007 and therefore no dose calculations for noble gases were necessary.

Liquid Effluent Exposure Pathways During 2007, 2.78 E+06 liters of wastewater were released into "No Name" Creek from the two-onsite Retention Basins. This volume of wastewater was dispersed into 1.60 E+10 liters of dilution water. The estimated error associated with determining these volumes were 5% and 20%, respectively.

The Liquid source term resulted in a calculated annual child total body dose of 1.04 E -01 mRem and a calculated child bone dose of 3.96 E -01 mRem (as calculated using the ODCM).

These calculated doses were 3.47% and 3.96%, respectively, of the associated 10 CFR Part 50, Appendix I guidelines. The total body and organ doses reflect the age group(s) that could have received the highest annual dose from the liquid source term.

This information is summarized in Table 1.

Rancho Seco Nuclear Station 3 2007 AREOR

III. RADIOLOGICAL IMPACT EVALUATION (Continued)

FUEL CYCLE DOSE EVALUATION REMP Manual section 8.14 requires each Annual Radiological Environmental Operating Report (AREOR) to include information related to REMP manual section 5.0; Fuel Cycle Dose.

The Fuel Cycle Dose Specification limits the dose or dose commitment to any real member of the public to 25 mRem to the total body or any organ, except the thyroid which is limited to 75 mRem. This specification implements requirements promulgated by the United States Environmental Protection Agency [CFRd].

Consistent with REMP manual section 5.0, no fuel cycle dose evaluation was required to be performed during 2007 since no REMP measurement exceeded the established reporting levels. Additionally, the Station effluent dose predictions did not exceed twice the dose guidelines of 10 CFR Part 50, Appendix I [CFRc]. The station operated within the Appendix I guidelines envelope for radioactive effluents (a condition supported by Program measurements); therefore, determination of an actual dose commitment delivered to a real member of the public was not required.

OBSERVED POTENTIAL RADIOLOGICAL IMPACT Gaseous Effluent Exposure Pathways The calculated gaseous effluent dose of 1.94 E -02 mRem [RS01] is based on tritium and particulate activity. The observed dose calculation, if completed, using the gross beta data (which is primarily due to naturally occurring radioisotopes) would not provide an accurate correlation with the predicted tritium and particulate activity dose calculations. Also, none of the REMP quarterly air filter composite gamma isotopic analysis results for the airborne pathway indicated the presence of nuclides of Station origin. Therefore, no dose comparison was completed.

Direct Radiation Exposure Pathway Based on Luxel control and indicator locations measurement results obtained during 2007, the Station proper did not contribute an observable component to the recorded direct gamma radiation field. This Luxel data supports the Gaseous Effluent Exposure Pathway conclusions and supports the conclusion that the Plant has no direct radiation effect on the environment.

Luxel monitoring badges placed near the effluent stream was used to evaluate the dose from this area. Dose levels at these locations are higher than the mean of the control and indicator locations reported. This above average dose is due to elevated soil activity due to historic liquid effluent releases. Luxel badge locations around the ISFSI outside fence (required by the ISFSI License) show higher readings, attributed to the fuel stored in the ISFSI, and are within design calculations.

Rancho Seco Nuclear Station 4 2007 AREOR

III. RADIOLOGICAL IMPACT EVALUATION (Continued)

OBSERVED POTENTIAL RADIOLOGICAL IMPACT Liquid Effluent Exposure Pathways To evaluate the impact on the environment from the liquid effluent pathway, dose calculations were performed and compared with the annual dose commitment calculations reported in the January -December 2007 Rancho Seco Annual Radioactive Effluent Release Report [RS01].

The observed results presented in Table 1 were obtained using the Cs-137 activity reported for the fish samples from 2007 (Appendix F, Table F-5), default consumption quantities for fish (ODCM), and nuclide-specific dose factors [NRC77].

As in past reports, the observed potential dose commitments listed in Table 1 are subject to uncertainty, principally due to the assumption that the observed radioactivity was due to 2007 Station operations only and was not affected by radioactivity introduced into the environment prior to 2007. A major portion of the activity identified by Program measurements in 2007 is attributable to historical releases documented in previous annual reports. Additionally, the observed dose commitment calculations are based on conservative default consumption factors for fish and garden.

The 2006 Land Use Census indicates the liquid/ fish pathway is a potential exposure pathway.

The fish pathway dose commitment calculation uses conservative default fish consumption factors instead of using actual Land Use Census data. Also, the dose commitment calculation uses fish sample analysis data derived from fish samples collected from the plant effluent stream.

Rancho Seco Nuclear Station 5 2007 AREOR

II1. RADIOLOGICAL IMPACT EVALUATION (Continued)

OBSERVED POTENTIAL RADIOLOGICAL IMPACT TABLE 1 2007 Liquid Effluent Pathway Potential Dose Comparison POTENTIAL DOSE COMMITMENT (Based on the maximally exposed group)

PREDICTED DOSE OBSERVED DOSE PERCENT OF THE 10 CFR COMMITMENT (a) (c) COMMITMENT (b) (c) PART 50 APPENDIX I (mRem) (mRem) DOSE LIMITS 0.104 0.015 0.5 %

(Child total body) (Adult Total Body) Total Body (3 mRem guideline) 0..396 0.024 0.24 %

(Child bone) (Teen liver) Organ (10 mRem guideline)

Notes: (a) Reported in the 2007 Annual Radiological Effluent Release Report (ARERR)

(b) Calculated using Cs-1 37 activity for fish samples (Appendix F, Table F-5); consumption factors form the ODCM, and Regulatory Guide 1.109 dose conversion factors.

(c) The predicted and observed dose commitments reflect the age group that could have received the highest annual dose commitment from the liquid source term Rancho Seco Nuclear Station .6 2007 AREOR

IV. PROGRAM ANALYSIS RESULTS

SUMMARY

This section compiles Program data with corresponding evaluations. Each of the following five subsections presents information about each of the principal environmental exposure pathways monitored by the Program:

=* Atmospheric (Section IV-A)

Direct Radiation (Section IV-B)

Terrestrial (Section IV-C)

=> Aquatic Life (Section IV-D)

Water (Section IV-E)

Each of these sections contains a data evaluation subsection, which provides a summary of the data collected.

Table 2 is a comprehensive, all-media data summary presented in a format considered acceptable by the US Nuclear Regulatory Commission. Information contained in Table 2 was derived from' data presented in Appendix F.

IV-A. ATMOSPHERIC MONITORING DATA EVALUATION No radionuclides attributable to the operation of Rancho Seco were observed in gamma spectrometry analyses of the quarterly composites of the particulate filters.

Therefore, since all data was reported as being below the associated minimum detectable activity (MDA) for the nuclides of interest, no table is presented for the composite air filter data. The data indicates that there was no measurable contribution to the airborne radioactivity inventory that could reasonably be attributable to Station operations.

The results of the gross beta analyses of the particulate samples are given in Appendix F, Table F-I.

Rancho Seco Nuclear Station 7 2007 AREOR

IV-B. DIRECT RADIATION MONITORING DATA EVALUATION A comparison review of all Luxel data for the indicator and control locations during 2007 showed that there was no observable direct radiation component due to Station operations (i.e., storage or utilization of licensed radioactive material within the restricted area.)

Two Luxel locations are being used to evaluate the dose in areas next to the effluent stream.

The data from these locations indicates doses are within regulatory limits of 10 CFR Part 20.

Luxel badge locations on the outside fence of the ISFSI show higher readings, but this is expected due to the spent fuel storage in the ISFSI. The results are within the design criteria and no license or regulatory limits were exceeded.

The summary data for 2007 direct radiation monitoring is presented in Table 2.

Comprehensive data tables are given in Appendix F, Table F-2.

IV-C. TERRESTRIAL MONITORING DATA EVALUATION Garden Vegetation - Three (3) garden vegetation samples were collected and analyzed for nuclides of interest during 2007. Gamma spectrometry analysis of the samples indicated results less than LLD. A site boundary irrigated garden has been utilized as a conservative method for evaluating the liquid effluent pathway. This method meets the requirement of the Land Use Census for monitoring gardens.

The summary data for 2007 terrestrial monitoring is presented in Table 2. Comprehensive data tables are given in the following Appendix F table:

= F-3 (Garden Vegetables)

Rancho Seco Nuclear Station 8 2007 AREOR

IV-D. AQUATIC LIFE MONITORING DATA EVALUATION Sediment - Twelve (12) samples of sediment were collected from the onsite discharge canal during 2007. Gamma spectrometry analysis of these samples indicated the presence of Cs-137 (12 samples, 27.7 to 489 pCi/kg, 171.0 pCi/kg mean), and Co-60 (6 samples, 5.93 to 14.8 pCi/kg, 10.7 pCi/kg mean).

The presence of nuclides of interest in sediments is attributed to historical permitted liquid effluent discharges.

Fish - Two (2) fish samples were collected during 2007 and analyzed for nuclides of interest by gamma spectrometry. Samples were collected in the effluent creek at the Site Boundary.

Gamma spectrometry analysis of these samples indicated the presence of Cs-137 (1 sample, 9.87 pCi/kg).

The summary data for the aquatic life-monitoring program is shown in Table 2.

Comprehensive data tables are given in the following Appendix F Tables:

F-4 Sediment F-5 Fish IV-E. WATER MONITORING DATA EVALUATION Well Water - Eight (8) well water samples were collected at indicator and control locations around the site during 2007. Tritium and gamma spectrometry analysis of the samples indicated results less than LLD. Gross beta activity levels for all samples were within regulatory limits.

Runoff Water - Thirty (30) runoff water samples were collected at the site boundary during 2007. Tritium and gamma spectrometry analysis of the samples indicated results less than LLD.

Surface Water - Five locations (3 indicator and 2 control) were included in the surface water-monitoring program. Composite samplers located at the Plant Intake (Folsom South Canal) and Effluent Discharge provides monthly composite samples. During 2007, 64 samples were collected and analyzed for nuclides of interest. Tritium and gamma spectrometry analysis of the samples indicated results less than LLD Rancho Seco Nuclear Station 6 2007 AREOR

IV-E. WATER MONITORING DATA EVALUATION (continued)

Drinking Water - Water supplied from two site wells is distributed in a potable water supply system for Station personnel consumption and use. On a monthly frequency, samples were collected and analyzed for nuclides of interest. A sample from the Rancho Seco Reservoir Well is collected as a control location. No gamma emitting isotopes were found present in the 36 samples collected in 2007. Gross Beta analysis showed activity within regulatory limits.

The summary data for the water-monitoring program is shown in Table 2. Comprehensive data tables are given in the following Appendix F Tables:

=> F-4 Sediment

= F-6 Well Water

= F-7 Runoff Water

=> F-8 Surface Water

= F-9 Drinking Water Rancho Seco Nuclear Station 10 2007, AREOR

TABLE 2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

(NRC Format)

Rancho Seco Nuclear Station 11 2007 AREOR

TABLE 2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Rancho Seco Nuclear Station Docket No. DPR-54/ SNM 2510 Location of Facility Sacramento, California Reporting Period January - December 2007

. (County, State)

Medium or Type and Lower All Indicator Location with Highest Annual Control locations Number of Pathway Total Limit of Locations MeMean (f) a Nonroutine Sampled Number of Detection Mean (f)a Name . ean-() a- Range Reported (Unit of Analysis (LLD)b Range Distance Range Measurements Measurement) Performed & Direction Air Particulates (pCi/M 3) Gross 1 0.01 0.022 (106/106) RASO.1CO 0.023 (53/53) 0.022 (53/53) 0 (159) (0.004- 0.063) 0.1 miles 450 (0.008-0.063) (0.007-0.066) y,-spec (112) 1Cs 0.01 <LLD <LLD <LLD

'*Cs 0.01 <LLD <LLD <LLD Direct Radiation Luxel NA 19.4 (112-112) RTLO.4NO 26.3(3/3) 19.1 (16/16) 0 (mRem/qtr.) (128) (12-30) 0.4 miles 2700 (20-30) (14-31)

Garden Vegetables y-spec (pCi/kg) (5)

Co 60 <LLD <LLD <LLD 0

_JCs 60 <LLD <LLD <LLD 0

_Cs 60 <LLD <LLD <LLD 0 a Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f) b LLD values from Table E-2. See page E-8, "SENSITIVITY OF THE REMP MEASUREMENT PROCESS", for information on determining LLD and Minimum Detectable Activity (MDA).

Rancho Seco Nuclear Station 12 2007 AREOR

TABLE 2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Rancho Seco Nuclear Station Docket No. DPR-54/ SNM 2510 Location of Facility Sacramento, California Reporting Period January - December 2007 (County, State)

Medium or Type and Lower All Indicator Location with Highest Annual Control locations Number of Pathway Total Limit of Locations Mean Mean (f) a Nonroutine Sampled Number of Detection Mean (f) a Name Mean a Range Reported (Unit of Analysis (LLD) b Range Distance Range Measurements Measurement) Performed & Direction Sediment Y-spec (pCi/kg) (12)

  • uCo 150 10.7 (6/12) RMSO.6MO 10.7 (6/8) NA 0 (5.93-14.8) 0.6 miles 2480 (5.93-14.8)

Cs 150 171 (12/12) RMSO.3MO 180.1 (4/4)

(27.7-489) 0.3 miles 2480 (27.7-489) NA 0

_Cs 150 <LLD <LLD NA 0 Fish (pCi/kg) y-spec

_ _Mn 130 <LLD <LLD NA 0 bUCo 130 <LLD <LLD NA 0

_ _Zn _ _ 260 <LLD <LLD NA 0 13Cs 130 9.87 (1/2) RFSO.6NO 9.87 (1/2)

_____ (<6.03 - 9.87) 0.6 miles 2700 (<6.03-9.87) NA 0

_Cs 130 <LLD <LLD NA 0 aMean and Range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f) bLLD values from Table E-2. See page E-8, "SENSITIVITY OF THE REMP MEASUREMENT PROCESS", for information on determining LLD and Minimum Detectable Activity (MDA).

Rancho Seco Nuclear Station 13 2007 AREOR

TABLE 2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Rancho Seco Nuclear Station Docket No. DPR-54/ SNM 2510 Location of Facility Sacramento, California . Reporting Period January - December 2007 (County, State)

Medium or Type and Lower All Indicator Location with Highest Annual Control locations Number of Pathway Total Limit of Locations Mean Mean (f) a Nonroutine Sampled Number of Detection Me an (f) a RangeReported (Unit of Analysis (LLD) b Range Distance Mean (f)

Range R eeasrte s tName Measurement) Performed & Direction Well Water Gross 43 4.14 (4/4) RWWO.8DO 4.14 (4/4) 3.31 (3/4) 0 (pCi/L) (8) (3.73-4.61) 0.8 miles 67.50 (3.73-4;61) (<2.90-4.81)

Tritium 1000 <LLD <LLD <LLD 0 (8) y-spec 15 <LLD <LLD <LLD 0 Muco 15 <LLD <LLD <LLD 0 b6Zn 30 <LLD <LLD <LLD 0

-1Cs 10 <LLD <LLD <LLD 0 1 Cs 10 <LLD <LLD <LLD 0 Runoff Water Tritium 2000 <LLD <LLD NA 0 (pCi/L) (30) y-spec (30) 5Mn 15 <LLD <LLD NA 0

_0_Co 15 <LLD <LLD NA 0

`bZn 30 <LLD <LLD NA 0

___Cs 18 <LLD <LLD NA 0

_ Cs

_ _ 15 <LLD <LLD NA 0 a Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f) b LLD values from Table E-2. See page E-8, "SENSITIVITY OF THE REMP MEASUREMENT PROCESS", for information on determining LLD and Minimum Detectable Activity (MDA).

Rancho Seco Nuclear Station 14 2007 AREOR

TABLE 2 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM ANNUAL

SUMMARY

Name of Facility Rancho Seco Nuclear Station Docket No. DPR-54/ SNM 2510 Location of Facility Sacramento, California . Reporting Period January - December 2007 (County, State)

Medium or Type and Lower All Indicator Location with Highest Annual Control locations Number of Pathway Total Limit of Locations Mean Mean (f) a Nonroutine Sampled Number of Detection Mean (f) a a MenReported Repored (Unit of (ntRange Analysis (LLD) b an Distance Name Range Mean f) Range Maueet Measurement) Performed & Direction Surface Water Tritium 2000 <LLD <LLD <LLD 0 (pCi/L) (64)

Y-spec (64)

-M-n 15 <LLD <LLD <LLD 0 buco 15 <LLD <LLD <LLD 0 1 Zn 30 <LLD <LLD <LLD 0

,5Cs 18 <LLD <LLD <LLD 0 1ý5Cs 15 <LLD <LLD <LLD 0 Drinking Water Gross 13 4 3.29 (21/24) RDW0.1G0 3.48 (10/12) 4.21 (11/12) 0 (pCi/L) (36) (2.15-4.75) 0.1 miles 1350 (2.15-4.75) (2.44-6.31) -b Tritium 1000 <LLD <LLD <LLD (36) y-spec (36) <LLD_0 4Mn 15 <LLD <LLD , <LLD 0 bUCo 15 <LLD <LLD <LLD 0 b6Zn 30 <LLD <LLD' <LLD 0

-13s 1 10 <LLD <LLD <LLD 0 3Cs 10 <LLD <LLD <LLD 0 Mean and Range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses. (f) b LLD values from Table E-2. See page E78, "SENSITIVITY OF THE REMP MEASUREMENT PROCESS", for information on determining LLD and Minimum Detectable Activity (MDA).

Rancho Seco Nuclear Station 15 2007 AREOR

V. REFERENCES CFRa Code of Federal Regulations, 2007, "National Primary Drinking Water Regulations," Title 40, Part 141.

CFRb Code of Federal Regulations, 2007, "Standards for Protection Against Radiation," Title 10, Part 20.

CFRc Code of-Federal Regulations, 2007, "Domestic Licensing of Production and Utilization Facilities," Title 10, Part 50.

CFRd Code of Federal Regulations, 2007, "Environmental Radiation Protection Standards for' Nuclear Power Operations," Title 40, Part 190.

CFRe Code of Federal Regulations, 2007, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High Level Radioactive Waste, and Reactor-Related Greater than Class C Waste," Title 10, Part 72.

NRC74 United States Nuclear Regulatory Commission, 1974, "Permanently Defueled Technical Specifications for the Rancho Seco Nuclear Station," Appendix A to Facility License No. DPR-54 (as amended).

NRC 00 United States Nuclear Regulatory Commission, 2000, Rancho Seco Nuclear Generating Station, "License for Independent Storage of Spent Nuclear Fuel and High Level Radioactive Waste," SNM-2510. (as amended)

NRC77 United States Nuclear Regulatory Commission, 1977, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Regulatory Guide 1.109, Revision 1.

NRC79a United States Nuclear Regulatory Commission, 1979, "An Acceptable Radiological Environmental Monitoring Program," Branch Technical Position, Revision 1.

NRC79b United States Nuclear Regulatory Commission, 1979, "Quality Assurance for Radiological Monitoring Programs (Normal Operations) -

Effluent Streams and the Environment," Regulatory Guide 4.15, Revision 1.

NRC92 United States Nuclear Regulatory Commission, "Air Sampling in the Workplace", Regulatory Guide 8.25, June 1992 NUREG79 United States Nuclear Regulatory Commission, 1979, "Radiological Effluent Technical Specifications for PWRs," NUREG-0472, Revision 2.

Rancho Seco Nuclear Station 16 2007 AREOR

V. REFERENCES (continued)

NUREG80a United States Nuclear Regulatory Commission, 1980, "Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190)," NUREG-0543.

RS01 Rancho Seco Nuclear Station, 2007, "Annual Radioactive Effluent Release Report, January -December 2007," Sacramento Municipal Utility District report.

RS02 Rancho Seco Quality Control Manual, Appendix A Rancho Seco Nuclear Station 17 2007 AREOR

VI. APPENDICES Rancho Seco Nuclear Station 18 2007 AREOR

APPENDIX A 2005/2006 LAND USE CENSUS RESULTS In compliance with the Rancho Seco Quality Manual [RS02] and the REMP Manual, section 4.0, "Land Use Census", a land use census was completed in March 2007. The method of conducting the primary survey was to use an aerial survey that was conducted during June 2006. Evaluating the aerial photographs continues to provide an accurate method of determining locations and distances of the nearest residences. The aerial photos also provided a method to identify any changes in the agricultural, commercial, residential, or industrial use of the land surrounding the site. The use of conservative dose factors for the purpose of projected dose calculations still requires that we evaluate the use of the area surrounding the site. The information that is presented is to verify this assumption and validate the process.

The land use census covered an area bounded by each of the sixteen meteorological sectors out to a two-mile radius from the Reactor Building.

The 2005/ 2006 Land Use Census did not identify any changes in the use of the unrestricted areas that would require modifications in the Radiological Environmental Monitoring Program for evaluating doses to individuals from principal pathways of exposure. This evaluation and determination are in accordance with the requirements of 10 CFR Part 50, Appendix I, section IV.B.3.

The Land Use Census is completed on a biennial schedule. Aerial surveys will be conducted during 2008 and the Gait Irrigation report covering 2007 and 2008 will be requested during the last quarter of 2007 and 2008 (respectively). This information will be used to complete the 2007/ 2008 census, which is scheduled to be completed during the first quarter of 2009.

Rancho Seco Nuclear Station Ai20 A-1 RO 2007 AREOR

A. RESIDENT EXPOSURE PATHWAY

SUMMARY

Inhalation, Ground Plane and Water Consumption The 2005/ 2006 census determined that seven of the 16 radial sectors have residences that are within the 2-mile (3219 meters) Land Use Census radius. The closest residence in each of the seven sectors is identified below:

Ranking Sector Distance (Nearest to Farthest)

(meters)

A >3219 NA B >3219 NA C 1432 3 D 1175 1 E >3219 NA F >3219 NA G 2381 6 H >3219 NA J >3219 NA K 2320 5 L 1207 2 M 2028 4 N 3181 7 P >3219 NA Q >3219 NA R >3219 NA It is expected that all seven residences use well water for consumption and other domestic purposes.

Rancho Seco Nuclear Station A-2 2007 AREOR

B. DEPOSITION EXPOSURE PATHWAY

SUMMARY

Beef Consumption Based on conservative dose calculation parameters in use, the following is a summary for the 2003/ 2004 land use census of the potential deposition exposure pathways at the locations listed below:

Sector Distance Consumption Comment (meters) Pathway A 433 Beef Unrestricted Area Boundary B 430 Beef Unrestricted Area Boundary C 531 Beef Unrestricted Area Boundary D 451 Beef Unrestricted Area Boundary E 483 Beef Unrestricted Area Boundary F 499 Beef Unrestricted Area Boundary G 579 Beef Unrestricted Area Boundary H 198 Beef Unrestricted Area Boundary J 195 Beef Unrestricted Area Boundary K 195 Beef Unrestricted Area Boundary L 286 Beef Unrestricted Area Boundary M 404 Beef Unrestricted Area Boundary N 514 Beef Unrestricted Area Boundary P 708 Beef Unrestricted Area Boundary Q 579 Beef Unrestricted Area Boundary R. 448 Beef Unrestricted Area Boundary Due to the revision of the ODCM, which eliminated the gaseous effluent pathway (August 26, 2002), the Deposition Exposure Pathway is not considered a credible evaluation with current plant conditions. Land Use Census use of this evaluation will be considered for revision in

.future surveillances.

Rancho Seco Nuclear Station A-3 2007 AREOR

C. IRRIGATED CROP EXPOSURE PATHWAY

SUMMARY

Laguna Creek Gait Irrigation District The Gait Irrigation District's 2005 Crop Report stated 2470.179 acre-feet of Laguna Creek water was diverted for irrigation purposes during the 2005 crop production season. Crops irrigated were Oats, Corn, Clover, Pasture, Sudan, and Alfalfa over a total of 1021 acres.

The Gait Irrigation District's 2006 Crop Report stated 2438.851 acre-feet of Laguna Creek water was diverted for irrigation purposes during the 2006 crop production season. Crops irrigated were Corn, Clover, Pasture, Sudan, Ryegrass, and Alfalfa over a total of 1190 acres.

Rossini Farming Company In addition to the above, SMUD has contracted with Rossini Farming Co., the owners of the vineyards adjacent to Rancho Seco Station, to supply irrigation water from Clay Creek on an as needed basis.

The following information was reported by the SMUD Water and Power Group, which is responsible for monitoring the usage. For the years of 2005 and 2006 it was reported that

>500 Acre-feet of water was used from the effluent creek for irrigating purposes for the vineyards.

Rancho Seco Nuclear Station A-4 2007 AREOR

D. OTHER EXPOSURE PATHWAYS The 2005/2006 Land Use Census confirmed previous knowledge that the Clay/ Laguna '

Creeks are utilized by the general public for aquatic life -consumption purposes. Based on direct observation cattle consume water from the Clay, Hadselville, and Laguna Creeks.

Past census evaluations have been unsuccessful in determining the usage/ occupancy factors for this consumption. Therefore, insufficient data existed to justify ODCM usage factor modification.

E. REMP EVALUATION An objective of the 2005/ 2006 Land Use Census was to compare census and current REMP Manual locations to ensure consistency exists between monitoring activities and actual land utilization. The following discussion is a summary of the comparison evaluation for each of the four exposure pathways.

Resident Exposure Pathway Luxel dosimetry and air particulate sampling and analysis monitor the inhalation and ground plane exposure pathways, the principal components of the Resident Exposure Pathway, directly and indirectly. Well water was monitored at two locations.

Since the existing REMP was more conservative with respect to Resident Exposure Pathway monitoring, no changes were required.

Deposition Exposure Pathway The Deposition Exposure Pathway is monitored directly within the Station Site Boundary through garden vegetation sampling and analysis. The potential for a deposition pathway has been evaluated by the ODCM and REMP programs and found to have little potential for the current plant status. Since the current REMP was representative and conservative with respect to Deposition Exposure Pathway monitoring, no changes were required.

Irri-iated Crop Exposure Pathway The REMP was effective in monitoring the identified irrigated crop exposure pathways. This conclusion was because the REMP included irrigated vegetation sampling.

REMP surface water surveillance activities monitor irrigation water radiological quality.

Current ODCM calculations are conservative since dilution effects are not included when predicting potential dose delivered through downstream pathways.

Rancho Seco Nuclear Station A-5 2007 AREOR

E. REMP EVALUATION (continued)

Other Exposure Pathways Existing aquatic life, surface water and sediment sampling analysis practices are effective in monitoring potential observable effects associated with recreational activities occurring at the Clay Creek, Hadselville Creek, Laguna Creek, Folsom South Canal and Rancho Seco Lake.

With respect to availability and quantity of food sources, the other identified consumption activities were considered inconsequential for pathway monitoring purposes.

No REMP changes were required to monitor other exposure pathways.

F. ODCM EVALUATION Based on 2005/2006 Land Use Census findings, the following potential exposure pathways exist at the indicated locations:

LIQUID EFFLUENT Exposure Pathway Location Comment Freshwater Fish Clay Creek Recreation beyond the Site Boundary Swimming Clay Creek Recreation beyond the Site Boundary Shoreline Deposits Clay Creek Recreation beyond the Site Boundary Irrigated vegetation Clay Creek Commercial vineyards and potential residences beyond the site boundary Irrigated forage Clay Creek, Cattle grazing beyond the Site Boundary Drinking Water Clay Creek Cattle drinking water beyond the Site Boundary Rancho Seco Nuclear Station A-6 2007 AREOR

F. ODCM EVALUATION (continued)

Specifying the Laguna Creek location also provides additional conservatism since the beneficial effects of downstream dilution are not considered when specifying effluent release restrictions.

As required by the 2005/ 2006 Land Use Census the above information for exposure pathways and locations was submitted for incorporation in the ODCM.

Rancho Seco Nuclear Station A-7 2007 AREOR

APPENDIX B SAMPLE SITE DESCRIPTIONS AND MAPS This appendix provides descriptive information about the sampling locations and maps of all the locations for the Radiological Environmental Monitoring Program sites.

Table B-1 provides information on sample type, identification codes, and map location references. The sample identification code is an alphanumeric string beginning with the prefix "R" (for Rancho Seco Nuclear Station) followed by two letters to identify the sample media:

AS Air MS Mud and Silt RW Runoff Water FS Fish SW Surface Water LV Garden Vegetable DW Drinking Water TL Direct Gamma Radiation (Luxel)

WW Well Water The numeric designations, which follow the letter designations, indicate the straight-line distance (in miles) from the center of the Reactor Building to the monitoring site.

The next letter designates the sector in which the monitoring location is located. The letters A through R are used for sector designators. The letters I and 0 are not used to prevent confusion with the numbers one and zero in the ID codes.

Sector Letter Degrees Azimuth Compass Point

'A 348;75 to 11.25 N B 11.25 to 33.75 NNE C 33.75 to 56.25 NE D 56.25 to 78.75 ENE E 78.75 to 101.25 E F 101.25 to 123.75 ESE G 123.75 to 146.25 SE H 146.25 to 168.75 SSE J 168.75 to 191.25 S K 191.25 to 213.75 SSW L 213.75 to 236.25 SW M 236.25 to 258.75 WSW N 258.75 to 281.25 W P 281.25 to 303.75 WNW Q 303.75 to 326.25 NW R 326.25 to 348.75 NNW Rancho Seco Nuclear Station B-1 2007 AREOR

SAMPLE SITE DESCRIPTIONS AND MAPS (Continued)

The final letter designation indicates if the location is part of the operational REMP program

("0") or post-operational REMP program ("P").

Table B-1 Lists each location referencing the sample type and the location ID code to the map site number on one of the four Radiological Environmental Monitoring Site Maps included in this Appendix.

Figure B-1 Site Location Map: Shows the locations of the sample locations on and/or near the Site (including Storm Drain locations).

Figure B-2 I Mile Radius map: Sampling locations within one mile of the Reactor Building centerline are shown on this map.

Figure B-3 5 Mile Radius map: Sampling locations -between one and five miles from the Reactor Building centerline are shown on this map.

Figure B-4 25 Mile Radius map: Sampling locations between five to 25 miles from the Reactor Building centerline are shown on this map.

Rancho Seco Nuclear Station B-2 2007 AREOR

--- 2'\#

  1. 3) (#2 (98) (#5) (44)

Figure B-I Radiological Environmental Sampling Locations on and near the Site (Storm Drain location numbers are in parenthesis)

Rancho Seco Nuclear Station B-3 2007 AREOR

N S

Figure B-2 Radiological Environmental Sampling Locations within I mile from the Reactor Building Rancho Seco Nuclear Station B-4 2007 AREOR

SMUD pROPERTY DOUNWRY Figure B-3 Radiological Environmental Sampling Locations from 1 to 5 miles from the Reactor Building Rancho Seco Nuclear Station B-5 2007 AREOR

SLOM PROPERTY GOUNGRY Figure B-4 Radiological Environmental Sampling Locations 5 to 25 miles from the Reactor Building Rancho Seco Nuclear Station B-6 2007 AREOR

Table B-1 Radiological Environmental Monitoring Sites and Map Locations Sample Type IDCode Class Map Location Collection Frequency Description. of Location Miles Sector No.

AIR RASO.1CO IND. 1 Weekly On Site-PAP BLDG. 0.1 C AIR RASO.7EO CON 2 Weekly Meteorological Tower 0.7 E AIR RAS0.3MO IND. 3 Weekly Effluent Discharge 0.3 M RUNOFF WATER RRWO.6MO IND. 5 Biweekly Site Boundary 0.6 M SURFACE WATER RSWO.7NO IND. 6 Monthly Water Sump 0.7 N SURFACE WATER RSW1.3FO CON 7 Monthly Rancho Seco Reservoir 1.3 F SURFACE WATER RSW3.7NO CON 8 Monthly Composite ISCO Composite Sampler at Folsom South Canal 3.7 N SURFACE WATER RSWO.3MO IND. 3 Monthly Composite ISCO Composite Sampler at Effluent Discharge 0.3 M SURFACE WATER RSW1.8NO IND. 9 Monthly Confluence of Clay and Hadselville Creeks 1.8 N DRINKING WATER RDW0.1GO IND. 10 Monthly Rancho Seco Site 0.1 G DRINKING WATER RDW1.8FP CON 30 Monthly Rancho Seco Lake Well 1.8 F DRINKING WATER RDWO.2PP IND 65 Monthly SAS Well 0.2 P WELL WATER RWWO.3EO IND. 11 Quarterly Site Well 0.3 E WELL WATER RWW0.8DO CON 12 Quarterly Marciel Ranch . 0.8 D Rancho Seco Nuclear Station B-7 2007 AREOR

Table B-1 (Continued)

Radiological Environmental Monitoring Sites and Map Locations Sample Type ID Code Class Map location No. Collection Frequency Description. of Location Miles Sector MUD AND SILT RMS0.3MO IND. 3 Quarterly Effluent Discharge 0.3 M MUD AND SILT RMSO.6MO IND. 5 Quarterly Site Boundary 0.6 M FISH RFS0.3MO IND. 3 Semi-Annual Effluent Discharge 0.3 M FISH RFS0.6MO IND. 5 Semi-Annual Site Boundary 0.6 M FISH RFSO.7NO IND. 6 Semi-Annual Water Sump 0.7 N FISH RFS1.5FO CON 7 Semi-Annual Rancho Seco Reservoir 1.5 F FISH RFS1.8NO IND. 9 Semi-Annual Confluence of Clay and Hadselville Creeks 1.8 N GARDEN RLV0.6MO IND. 5 Semi-Annual Site Boundary Garden irrigated with No-Name Creek 0.6 M VEGETABLES water GARDEN RLVXX.XX CON NA Semi-Annual Truck Garden which provides local produce from the NA NA VEGETABLES local area Rancho Seco Nuclear Station B-8 2007 AREOR

Table B-1 (Continued)

Radiological Environmental Monitoring Sites and Map Locations Sample Type ID Code Class Map Location No. Collection Description of Location Miles Sector Frequency LUXEL RTLO.3RO IND. 31 Quarterly NNW @ Perimeter Fence N/O Spray Ponds; #1 0.3 R LUXEL RTLO.3C0 IND. 32 Quarterly NE Perimeter Fence/ parking lot NE corner; #2 0.3 C LUXEL RTLO.3NO IND. 17 Quarterly W Perimeter Fence road/ pole/ top of hill; #3 0.3 N LUXEL RTLO.3LO IND. 20 Quarterly SW Perimeter Fence road near RS lake filters; #4 0.3 L LUXEL RTL0.3HO IND. 33 Quarterly Perimeter Fence/ S/O of Admin. Bldg.; #5 0.3 H LUXEL RTLO.4F0 IND. 34 Quarterly Photovoltaic Facility/ North Fence (NRC); #6 0.4 F LUXEL RTLO.5CO IND. 35 Quarterly Rt. 104 entrance to Rancho Seco; #7 0.5 C LUXEL RTLO.6KO IND. 36 Quarterly Tokay Substation; #11 0.8 K LUXEL RTL2.7MO IND. 14 Quarterly In Clay at Tipling's Residence 11633 Clay Station Rd; 2.1 M

  1. 16 (See note below)

LUXEL RTL8.2KO CON. 37 Quarterly Elliott Cemetery Near Angelo Dairy; #17 8.2 K LUXEL RTL7.8CO CON. 38 Quarterly Sam Jaber Residence/ 601 Carbondale Rd/lone; #18 7.8 C LUXEL RTLO.7GO IND. 30 Quarterly Well pump fence @ reservoir; #43 1.7 G LUXEL RTLI.5MO IND. 40 Quarterly Clay East & Kirkwood (NRC); #20 1.5 M_

LUXEL RTL3.9KO IND. 41 Quarterly SSW of Site on Borden Rd; #26 3.9 K LUXEL RTL7.4MO CON. 42 Quarterly Herald Fire Station #87/ 12746 Ivie Rd; #30 7.4 M Note: Badge at map location 14 (Tippling residence # 16 was moved to power pole outside of property due to inaccessibility, on July 27, 2005.

Rancho Seco Nuclear Station B-9 2007 AREOR

Table B-1 (Continued)

Radiological Environmental Monitoring Sites and Map Locations Sample Type ID Code Class Map Location No. Collection Frequency Description of Location Miles Sector LUXEL RTL3.7NO IND . . 43 Quarterly Folsom South Canal near Hobday Rd; #31 - 3.7 N LUXEL RTL3.8MO IND. 44 Quarterly BLM entrance to Folsom South Canal Pumping Station; #33 3.8 M LUXEL RTL1.9NO IND. 9 Quarterly Hadselville Cr. & Clay Cr.; #35 1.9 N LUXEL RTLI.8F0 IND. 45 Quarterly Rancho Seco Lake Maintenance Building, #19 1.8 F LUXEL RTL1.4DO IND. 46 Quarterly 0.9 Miles E/O Site on Twin Cities Road/ Rt. 104; #46 1.4 D LUXEL RTL8.0PO CON. 47 Quarterly Dillard School; #55 8.0 P LUXEL RTLO.8DO IND. 12 Quarterly Marciel Ranch; 14626 Twin Cities Rd; #63 0.8 D LUXEL RTL0.6MO IND. 5 Quarterly Site Boundary Irrigated Garden; #65 0.6 M LUXEL RTLO.4NO IND. 29 Quarterly Depression @ Clay Creek; #66 0.4 N LUXEL RTLO.4N01 IND. 29 Quarterly Soil Pile @ Clay Creek; #67 0.4 N LUXEL RTLO.3PO IND. 48 Quarterly West Fence; #68 0.3 P LUXEL RTLO.3NP IND., 53 Quarterly West Garden, #88 0.3 N LUXEL RTLO.4NP IND. 54 Quarterly Southwest ISFSI, #89 0.4 N LUXEL RTLO.5NP IND. 55 Quarterly Northwest ISFSI, #90 0.5 P LUXEL RTLO.3QP IND. 56 Quarterly Northeast ISFSI, #91 0.3 Q LUXEL RTLO.7QP IND. 59 Quarterly Highway 104 at the rail spur on pole, #92 0.7 Q LUXEL RTLO.7JP IND. 61 Quarterly Clay East Road on pole south of site boundary, #93 0.7 J LUXEL RTLO.4PP IND. 62 Quarterly ISFSI ALARA fence north side, #94. 0.4 P Rancho Seco Nuclear Station B-1 0 2007 AREOR

APPENDIX C QUALITY CONTROL SAMPLE ANALYSIS RESULTS QUALITY ASSURANCE AND CONTROL Implementation of the Radiological Environmental Monitoring Program (REMP) consists of a number of discrete steps including:

= Sample collection,

= Packaging, Shipment'and receipt,

= Measurements of radioactivity,

= Data evaluation, and

= Reporting.

These program elements are performed according to approved, written procedures to assure the validity of REMP results. This section discusses the internal quality control measurements made by the analysis laboratory, Eberline Services, and the results of their participation in the Interlaboratory Comparison Program implemented by the National Institute of Standards Testing (NIST). The Interlaboratory Comparison Program and the analysis laboratories Quality Assurance Programs provide information on the validity (accuracy and precision) of the REMP implementation steps listed above.

Because REMP measurement validity is important for evaluating protection of the health and safety of the public, RSNS has established an Environmental Quality Assurance Program (EQAP) for radiological environmental measurements. The Environmental QA Program implements the guidance provided in Regulatory Guide 4.15, (NRC79a).

INTERLABORATORY COMPARISON PROGRAM The ICP is a radiological analysis quality control program implemented by NIST and provided by vendor laboratories. Eberline Services participates in an ICP provided by Environmental Resources Associates (ERA). Eberline Services also participates in the Department of Energy (DOE) Mixed Analyte Performance Evaluation Program (MAPEP). Participation in an ICP is a requirement of the Rancho Seco Quality Manual (RS02), section 1.4.3.2. It provides for an independent check of the proficiency of the laboratory. It also provides information on the precision and accuracy of measurements of radioactive material in REMP samples by Eberline Services. The extent of Eberline Services participation in this program includes all of the environmental radioactivity determinations that are related to the analyses required by the REMP manual.

Rancho Seco Nuclear Station C-1 2007 AREOR

INTERLABORATORY COMPARISON PROGRAM (Continued)

The Intercomparison Program consists of sample media spiked with known quantities of specific radioactive materials at levels normally found in environmental samples. Most samples require long counting times to determine if any activity is present, and the results may have large deviations from the mean. 'When the samples are distributed, there is an implied precision requirement given in terms of the analysis requested to be performed. After the labs provide the results of their analyses, an ERA laboratory provides a statistical summary of all the results by the participating laboratory. This report includes the acceptance control limits, the mean of all laboratories and the standard deviation of the results by all labs, among other statistics. The same process is applicable for the MAPEP samples.

If the results of a determination by Eberline Services in the ICP are outside the specified control limits or do not pass the outliers test, Eberline Services must investigate, evaluate why the outlier occurred, and take appropriate corrective action to prevent problem recurrence.

During 2007, Eberline Services analyzed 13 ICP samples (ERA RAD-68) related to the current REMP program. One analysis for Gross Alpha in Water was above the upper control limit and was reported by ERA as "not acceptable". Eberline initiated a Corrective Action Request (CAR 07-04) and determined the corrective action which was related to the efficiency curve used for the analysis. Eberline Services completed a ERA QUIK Response Performance Evaluation for Gross Alpha in Water with acceptable results. In addition to the ERA study, Eberline Services participated in the MAPEP series07-017 study conducted in May 2007. Eberline Services failed the Zinc 65 in Vegetation, Cobalt 57 in Air Filter, and Iron 55 in Soil analysis. All three results for these analyses were higher than allowed by the acceptable range. Corrective action requests CAR 07-08 (Zinc 65 in vegetation, CAR 07-09 (Cobalt 57 in air filter), and CAR 07-10 (Iron 55 in soil) were initiated. SP.805, Annual Interlaboratory Comparison Program Data Review will document the completed corrective action for these CAR's.

The Eberline Services measurement results are presented in Table C-1 along with the acceptable values for each test.

INTRALABORATORY QUALITY ASSURANCE PROGRAM Eberline Services, by contract, also conducts an Intralaboratory Comparison Program (Quality Assurance Program) to maintain an acceptable quality level on a routine basis.

As part of their Quality Assurance Program, the laboratory performs background counts, an analysis of spiked samples, and duplicate sample counts for every ten Rancho Seco REMP samples analyzed. These quality control procedures are performed for all analyses except gamma spectrometry, for which weekly energy and efficiency checks are performed.

Personnel not directly involved with the analysis prepare the spiked and duplicate samples.

Spiked samples, as well as the radioactive sources used for the gamma spectrometer checks, are traceable to the National Institute for Standards and Technology (NIST).

Rancho Seco Nuclear Station C-2 2007 AREOR

RANCHO SECO AUDIT AND SURVEILLANCE RESULTS The Rancho Seco Quality Program requires periodic audits of REMP activities, including Eberline Services. Contract laboratory performance is evaluated by the Rancho Seco QA Department and an "Approved Vendor List" is created from these audits. Audits are either conducted by Rancho Seco QA staff or by reviewing audits conducted by other facilities (NUPIC audit review). Eberline Services is currently on the approved suppliers list.

CONCLUSIONS The Intralaboratory and Interlaboratory results provided by Eberline Services indicate that Eberline Services performance was acceptable.

DIRECT RADIATION (Luxel) COMPARISON PROGRAM The monitoring badge vendor, Landauer participates in a comparison program provided by the Idaho National Environmental Laboratory (INEL). INEL did not conduct this comparison program in 2007; therefore no results from that program are available for this report. Landauer also maintains NVLAP certification with NIST. A review of Landauer's NVLAP certification results indicates that Landauer has satisfactorily completed all of the required tests for the types of environmental radiation monitored at RSNS and is certified through December 31, 2008.

This comparison program satisfies the requirement of the REMP manual section 6.0.

Rancho Seco Nuclear Station C-3 2007 AREOR

TABLE C-1 2007 INTERLABORATORY COMPARISON PROGRAM Sample Type Report Date Assay Type ERA Result Eberline Result Control Limits (ERA RAD-68) (pCi/L) (pCi/L) (pCi/L)

Water 3/21/07 Sr-89 60.8 60.9 52.1-69.5 Water 3/21/07 Sr-90 28.1 25.9 19.4-36.8 Water 3/21/07 Ba-1 33 90.5 81.0 74.8-106 Water 3/21/07 Cs-134 88.9 95.2 80.2-97.6 Water 3/21/07 Cs-137 231 234 211-251 Water 3/21/07 Co-60 101 102 92.2-110 Water 3/21/07 Zn-65 350 384 289-410 Water ~3/21/~07 Gros~sAlpha. 12.7~ 24.0* 4.04-21.4 Water 3/21/07 Gross Beta 36.2 35.1 27.5-44.9 Water 3/21/07 Radium-226 19.4 20.3 14.4-24.4 Water 3/21/07 Radium-228 13.4 12.0 7.65-19.3 Water 3/21/07 Uranium(Nat) 35.9 34.7 29.7-42.1 Water 3/21/07 Uranium 52.8. 46.8 43.7-61.9 (Nat) mass Water 4/27/07 Gross Alpha 23.3 21.8 13.2-33.4 Water 4/27/07 Gross Beta 39.1 34.6 30.4-47.8

  • ERA QUIK check completed with acceptable results Rancho Seco Nuclear Station C-4 2007 AREOR

TABLE C-1 (cont.)

2007 INTERLABORATORY COMPARISON PROGRAM Sample Type Report Date Assay Type INEL Result Eberline Result Control Limits (MAPEP-07) (pCi/L) (pCi/L) (Bq/sample)

Vegetation 5/07 Cs-134 6.2101 7.03 4.3471-8.0731 Vegetation 5/07 Cs-137 6.9949 7.40 4.8964-9.0934 Vegetation 5/07 Co-57 8.1878 8.1 5.7315-10.6441 Vegetation 5/07 Co-60 5.8215 5.88 4.0751-7.7.5680 Vegetation 5/07 Mn-54 8.4492 8.87 5.9144-10.9840 Air Filter 5/07 Gross Alpha 0.601 0.7 >0.0-1.202 Air Filter 5/07 Gross Beta 0.441 0.478 0.221-0.662 Air Filter 5/07 Cs-134 4.1960 5.09 2.9372-5.4548 Air Filter 5/07 Cs-137 2.5693 2.95 1.7985-3.3401 Air Filter 5/07 Co-57 2.8876 3.92* 2.0213-3.7539 Air Filter 5/07 Co-60 2.9054 3.92 2.0213-3.7539 Air Filter 5/07 Mn-54 3.5185. 4.11 2.4630-4.5741 Air Filter 5/07 Zn-65 2.6828 2.98 1.8780-3.4876

TABLE C-1 (cont.)

2007 INTERLABORATORY COMPARISON PROGRAM Sample Type Report Date Assay Type INEL Result Eberline Result Control Limits (MAPEP-07) (pCilL) (pCi/L) (Bq/sample)

Water 5/07 Gross Alpha 0.327 0.278 >0.0-0.654 Water 5/07 Gross Beta 0.851 0.89 0.426-1.277 Water 5/07 Cs-134 83.5 91.4 58.5-108.6 Water 5/07 Cs-137 163.0 179.4 114.1-211.9 Water 5/07 C6-57 143.7 152.0 100.6-186.8 Water 5/07 Co-60 26.9 28.4 18.8-35.0 Water 5/07 Tritium 283.0 312.6 198.1-367.9 Water 5/07 Fe-55 129.3 141.0 90.5-168.1 Water 5/07 Ni-63 130.4 121.0 91.3-169.5 Water 5/07 Tc-99 10.5 10.5 7.4-13.7 Water 5/07 Zn-65 114.8 121.6 80.4-149.2 4 4 Rancho Seco Nuclear Station C-6 2007 AREOR

TABLE C-1 (cont.)

2007 INTERLABORATORY COMPARISON PROGRAM Sample Type Report Date Assay Type INEL Result Eberline Result Control Limits (MAPEP-07) (pCilL) (pCi/L) (Bqlkg)

Soil 5/07 Cs-134 34.8 32.7 24.4-45.2 Soil 5/07 Cs-137 799.7 754.1 559.8-1039.6 Soil 5/07 Co-57 471.2 447.2 329.8-612.6 Soil 5/07 Co-60 274.7 269.2 192.3-357.1 Soil > 7 5/07 Fe-55 ~ 807.6 1300* 5~65.31049.9 Soil 5/07 Mn-54 685.2 663.6 479.6-890.8 Soil 5/07 Ni-63 585.0 496 409.5-760.5 Soil 5/07 K-40 602 593.8 421-783 Soil 5/07 Tc-99 6.24 Soil 5/07 Zn-65 536.8 550.3 375.8-697-8

APPENDIX D SAMPLE COLLECTION AND ANALYSIS METHODS For each of the sample media collected, the method of collection is documented in Rancho Seco Nuclear Station procedures. Detailed analysis methods are documented in procedures controlled by the contract laboratory, Eberline Services. A brief description of these collection and analysis methods is included in this Appendix.

Sample Media Collection/Analysis Method AIR An air sampler continuously moves air through a filter paper designed to capture particulates by filter paper impaction. The air samplers are equipped with an elapsed time meter and flow gauge, which are used to calculate the volume of air that has passed through the filter paper.

The filter paper is exchanged weekly. At least one day is allowed to elapse between sample collection and counting to reduce the interference of naturally occurring radon and thorium daughters on the sample analysis. The filter paper is assayed for gross beta radioactivity by placing the filter on a stainless steel planchet and counted with an internal gas flow proportional counter.

The individual particulate filter papers are saved over a calendar quarter and the composite collection is assayed for gamma isotopic radioactivity by gamma spectroscopy.

DIRECT RADIATION Monitoring badges, (Luxels), are located within a ten (10) mile radius of the site. The badges within a five (5) mile radius are considered indicator badges. Two (2) badges are placed at each monitoring location to assure adequate data recovery and to improve measurement statistics. The badge field exposure cycle is approximately ninety (90) days. At the end of the field exposure cycle, the badges are exchanged and returned to the contract laboratory for processing.

Rancho Seco Nuclear Station D-1 2007 AREOR

Sample Media Collection/Analysis Method SEDIMENT Samples of sediment are collected from the top three inches of the sampled material on a quarterly schedule. Sediment samples are obtained approximately two feet from the shoreline. Each sample is assayed directly for gamma isotopic radioactivity by gamma spectroscopy.

GARDEN PRODUCE Samples of vegetables are collected semi-annually from a garden, which is maintained at the Station Site Boundary. Control location samples are collected from a local commercial vendor. The vegetables are assayed directly for gamma isotopic radioactivity by gamma spectroscopy.

FISH Fish are collected semi-annually from the Clay Creek system. The dissected (edible) portion of each sample is assayed directly for gamma isotopic radioactivity by gamma spectroscopy.

WATER 1-liter grab samples of water from locations in the liquid effluent pathway and groundwater are collected as follows:

  • Surface water and Drinking water are collected monthly
  • Runoff water is collected biweekly 0 Well water is collected quarterly.

At two locations, samples are obtained to provide a monthly composite sample. All samples are assayed for tritium by liquid scintillation counting and for gamma isotopic radioactivity by gamma spectroscopy.

Drinking and Well water samples are analyzed for Gross Beta activity.

Rancho Seco Nuclear Station D220 D-2 RO 2007 AREOR

APPENDIX E ENVIRONMENTAL MONITORING PROGRAM DESIGN PROGRAM BASIS The Sacramento Municipal Utility District conducts a continuous Radiological Environmental Monitoring Program (REMP) at the Rancho Seco Nuclear Station to assess the impact of Station operation on the surrounding environment. The current Post-Operational REMP is a continuation of a similar program initiated prior to and during operation of the Station. Samples of the surrounding environment are collected on a routine basis and analyzed to determine the amount of radiation and radioactive materials present in the exposure pathways.

During 2007 the program was directed and executed by the Radiation Protection/ Chemistry Superintendent. Decommissioning Chemistry/ Radiation Protection Technicians perform sample collection. The Radiological Health Supervisor performs data review and Program maintenance/ oversight. The Program is operated with primary accountability and cognizance of the Manager, Plant Closure and Decommissioning.

The Program is designed consistent with Title 10, Code of Federal Regulations, Part 50, Appendix I - Section IV, 8.2, B.3 and C, and Appendix A, "General Design Criteria for Nuclear Power Plants," Criterion 64. The program also complies with Title 10, Code of Federal Re-gulations, Part 20, "Standards for Protection Against Radiation," Section 1302. These federal requirements are cited in the Rancho Seco Quality Manual, Appendix A, and the REMP manual. REMP requirements are implemented through the review, approval and routine use of several documents, namely the REMP Manual, Offsite Dose Calculation Manual, Surveillance Procedures and'Health Physics Implementing Procedures.

The programmatic elements of the REMP are. based on regulatory requirements and associated guidelines. The objectives of the Program are to:

1. Provide the technological basis and the instruction for monitoring the environs for radioactivity sources. The radioactive sources, which contribute to detectable radioactivity in the local environs, are comprised of:

=> Naturally occurring background,

= Releases during normal operations,

= World-wide weapons testing, and

=> Major global nuclear accidents Rancho Seco Nuclear Station E-1 2007 AREOR

PROGRAM BASIS (Continued)

2. Provide the means to verify the effectiveness of the Rancho Seco Nuclear Station Radiological Effluents Control Program.
3. Meet the minimum detectable limits for radioisotopes in environmental samples.
4. Provide quantitative measurements in the gaseous (airborne particulate), liquid, and direct radiation exposure pathways for radionuclides.
5. Provide indications of the largest potential radiation exposure for individuals as a result of radionuclides in the principal exposure pathways.

The Program is developed and conducted using recognized standards and practices NRC79a, NRC79b, NUREG79, and NUREG80a.

REMP CHANGES The REMP manual and sampling program was not revised during 2007.

EXPOSURE PATHWAYS The fundamental parameters, which have been defined prior to monitoring the environs, are:

1. Identification of the effluent release pathways
2. Identification of the human exposure pathways
3. Identification of the land use parameters by the population within a two-mile radius of the plant site.

Each of these three parameters is discussed below.

Effluent Release Pathways There are two principal pathways, which may result in human exposure to radiation and radioactive material originating from Station operation:

1. Liquid effluents and
2. Direct radiation from these effluents and onsite sources.

Rancho Seco Nuclear Station E-2 2007 AREOR

Liquid Effluents In the liquid exposure pathway, humans can ingest radioactive materials in surface waters directly or indirectly through the consumption of aquatic foods such as fish and shellfish.

Humans can consume vegetation, which is irrigated with Clay Creek water, which may contain radioactive material. Another exposure pathway from liquid effluents results from the consumption of animal products such as meat and milk from animals, which have fed upon irrigated vegetation and/ or consumed Clay Creek water.

Direct Radiation In the direct radiation pathway, potential radiation exposure may occur from radioactive material storage areas, which are contained within the site boundary. People can potentially be exposed to direct radiation from ground deposition of particulates deposited on the ground from liquid effluents. With the off-loading of spent fuel to the ISFSI, the ISFSI has become part of the direct radiation pathway.

LAND USE CENSUS On a biennial basis, a land use census is conducted within a two-mile radius to identify any changes in the human exposure pathways. The Land Use Census is used to determine the changes needed for REMP monitoring activities. The results of the land use census conducted

.during 2005/ 2006 are presented in Appendix A of this Report. The next scheduled land use census will be conducted in 2007/ 2008 and reported in the 2008 AREOR. From data obtained from the Land Use Census, exposure pathways are analyzed through a systematic process, which identifies a sample medium, or organism that is found to potentially contribute to an individual's radiation exposure. Usage and bioaccumulation factors (NRC77) are then specified which represent the magnitude of radioactive material transfer through the food chain to a receptor. The analysis of the effluent and exposure pathways enables monitoring sites to be identified as "indicator" (for sites at which the potential effects of Station effluents would be readily detected) or "control" (for those sites which are not expected to be influenced by Station operation). The analysis results of samples obtained at indicator and control sites are routinely compared to identify potential exposures above background levels.

Rancho Seco Nuclear Station E-3 '2007 AREOR

MONITORING LOCATION SELECTION The REMP maintains the monitoring sites required by the REMP manual, Table 6. This program is supplemented with additional samples to compensate for changes in the radiological environment surrounding Rancho Seco. The California Department of Health Services also selected some of the monitoring sites as part of their monitoring programs.

Indicator sites are placed in areas, which would be most sensitive to the effects of Station effluents such as downwind or downstream areas near the Station. If radioactive material is detected above background at any of these indicator sites, observed potential exposure and dose to humans can be estimated to verify the effectiveness of the Offsite Dose Calculation Manual in predicting potential exposures or doses. It is important to note that the detection of radioactive material in indicator samples does not necessarily mean that its presence can be attributed to Rancho Seco operations. Moreover, especially with liquid effluent pathway samples, the detection of radioactive material is difficult to interpret since it is unknown when the material was deposited. In many instances, the observed radioactive material could correctly be ascribed to historical (pre-2007) depositions.

Control locations provide data that should not be influenced by the operation of Rancho Seco.

These locations are selected based upon distance from the Station in the upwind or upstream direction of the effluent release pathways. Samples obtained from control locations should, upon analysis, reveal information about the presence and distribution of naturally occurring and man-made radioactive materials. Data from these locations are used to aid in the discrimination between the effects of Rancho Seco releases and other natural phenomena or accidental releases, which may result in human exposure.

Liquid radioactive effluents are discharged in batches from two onsite Retention Basins into "No Name" Creek located southwest of the Station. Dilution water, obtained from the Folsom South Canal, is discharged into "No Name" Creek to give reasonable assurance of compliance with the 10CFR50, Appendix I dose guidelines. "No Name" Creek flows southerly into the Clay Creek. Without this dilution water flow, the Clay Creek would be in a dry state for most of the year.

Beyond the Site Boundary at a point north of Highway 104, the Clay Creek empties into the Hadselville Creek. Hadselville Creek then empties into the Laguna Creek at a point west of North Clay Station Road near the Folsom South Canal. Finally, Laguna Creek flows into the Cosumnes River at a point located approximately 20 straight-line miles west of Rancho Seco.

Since this stream system is the only routine release pathway for liquid radioactive and non-radioactive effluents from the Station, the liquid exposure pathway indicator sites are located along these creeks and nearby land.

Rancho Seco Nuclear Station E-4 2007 AREOR

MONITORING LOCATION SELECTION (continued)

The direct radiation pathway is monitored principally through a network of monitoring badges at sites distributed in sectors centered on the Station. The badges are located primarily at the site, residential, and recreational areas around the Rancho Seco location. This design provides the capability to easily detect Station-induced direct radiation contributions to the observed terrestrial and cosmic direct radiation background.

Some badges have been sited in special locations to record direct radiation resulting from known depositions of radioactive material and to provide 10 CFR Part 72 license required data for the Interim Spent Fuel Storage Installation (ISESI).

Appendix B contains a detailed description and illustration of the REMP sample and monitoring

.locations.

SAMPLE MEDIA Samples are collected from predetermined monitoring sites at a specified frequency. The sample media chosen is a function of the type of monitoring desired and coincides with one of the following exposure pathways:

o Atmospheric 0 Direct radiation 0 Terrestrial 0 A~quatic life 0 Water

,Atmospheric. monitoring is accomplished by filtering a volume of air using a mechanical air pump to collect. particulates with a particulate filter paper. Three air sampler locations are used to collect weekly air samples. One location (Meteorological Tower) is a control location and the remaining two locations are indicator locations on the plant site..

Direct radiation monitoring is achieved by placing monitoring badges at aboveground sites.

The monitoring badges respond to, and record the amount of, gamma radiation exposure. The source of this gamma radiation exposure is varied and includes potential Station effluents, naturally occurring terrestrial, and cosmogonic radionuclides. The monitoring badges are also influenced by seasonal and global (fallout) radiation sources.

Rancho Seco Nuclear Station E520 E-5 RO 2007 AREOR

SAMPLE MEDIA (Continued)

There are 33 sites, which are monitored within a 10-mile radius of the Station. The monitoring badges are placed at the Station Industrial Area Boundary, near the property boundary, locations of interest such as nearby residences, and at control locations located beyond five miles of the Station.

Terrestrial monitoring is accomplished by obtaining samples of sediment and garden vegetation to measure the quantity of radioactive material deposited from liquid effluents.

There are two mud and silt (sediment) and 2 garden vegetation locations.

Aquatic monitoring includes the sampling of fish. There are four fish sample locations that can be selected for sampling.

Water monitoring includes samples of surface, runoff, drinking, and well sources from locations in the liquid effluent pathway and from area wells. The six surface water sampling locations monitor site supply water (Folsom South Canal), runoff water and water discharged from the Station. Drinking water is sampled from two groundwater wells and three drinking water taps.

SAMPLE ANALYSIS & DATA HANDLING The laboratory, which provides radio-analytical services for the Program, is Eberline Services located in Richmond, California. Sample analysis results submitted by Eberline Services are reviewed for accuracy and completeness and then entered into a computerized database for evaluation.

Data comparisons are made between individual control and indicator sample sites to isolate potential Station influences on the measurement results.

The summarized results of the 2007 Radiological Environmental Monitoring Program are presented in Table 2.

Individual (raw data) results are presented in Appendix F, Tables F-i through F-9.

REGULATORY REPORTING LEVELS Sample analysis data is reviewed and evaluated by the Radiological Health Supervisor as the results are received. All sample analysis results are reviewed for correct sensitivity and anomalies.

Rancho Seco Nuclear StationE-.20ARR E-6. 2007 AREOR

REGULATORY REPORTING LEVELS (Continued)

The activity concentration values listed in Table E-1 are the environmental Fuel Cycle Dose quantities that, if exceeded, require a Special Report to be submitted to the USNRC. In accordance with the REMP Manual (Section 5, Fuel Cycle Dose), the Special Report must include an evaluation of any release conditions, environmental factors or other aspects, which caused the reporting limits to be exceeded.

In addition to the Fuel Cycle Dose reporting requirements, a Special Report is required to be submitted to the USNRC when more than one of the radionuclides in Table E-1 are detected in the sampling medium and the summed ratio of detected activity concentration to the respective Reporting Level concentration is greater than, or equal to, unity (1). When radionuclides other than those listed in Table E-1 are detected which are a result of Station effluents, a Special Report is required to be submitted if the potential annual dose commitment exceeds the 10 CFR 50, Appendix I guidelines.

No reports of the types described above were required to be submitted during 2007.

SENSITIVITY OF THE REMP MEASUREMENT PROCESS All Program measurements must be performed at a sensitivity, which meets USNRC requirements. This sensitivity is determined "before the fact" (a priori)for each radionuclide of interest and sample analysis type. Typical controllable sensitivity parameters include:

= Sample volume or mass

= Sampling efficiency

= Time from sample collection to measurement Instrument detection efficiency for the nuclides (energies) of interest

= Background radiation levels

= Chemical recovery factors Rancho Seco Nuclear Station E-7 2007 AREOR

SENSITIVITY OF THE REMP MEASUREMENT PROCESS (continued)

By adjusting and controlling each of these parameters to maximize measurement process efficiency, a maximum sensitivity level (activity concentration) can be specified for each nuclide of interest and analysis type while maintaining an economic measurement process. The maximum sensitivities in the REMP are specified by the USNRC in the REMP Manual approved for Rancho Seco. These sensitivities are referred to as "LLD's", an acronym for "Lower Limit of Detection". LLD's are specified on an "a priori' basis and apply to routine measurement process capabilities when no other interfering radioactivity is present. The word "routine" is emphasized since occasional circumstances, such as limited sample mass, elevated levels of background radiation and interfering nuclides can contribute to sensitivity degradation.

Such occurrences are normally noted and reported during the conduct of REMP activities.

Meeting the LLD requirements is a quality control function shared by both REMP and the analytical laboratory personnel. Once the laboratory establishes values for the controllable parameters for each analysis type, sample chain of custody controls ensure that these parameters are upheld. If all parameters are upheld, then compliance with the LLD requirements has been demonstrated. The specific LLD values for Program measurements are included in Table E-2.

Since most of the samples analyzed result in the detection decision "activity not identified", a Minimum Detectable Activity (MDA) concentration value is calculated and reported. This value can be thought of as the LLD-at-the-time-of-counting since it is calculated using an equation, which is similar to the one, used to establish LLD parameters. The biggest difference is that actual (not "a priori') parameters are used, including interference from natural radioactive material in the sample. It is important to note that MDA's are reported only for those measurements where the "activity not identified" decision has already been made.

MDA values are used primarily to identify changes in the measurement process and to convey more information about the measurement itself. Without the use of the MDA concept, most Program measurements would be reported simply as "<LLD". With MDA used, Program measurements are reported as "< xxx "where "xxx" is the calculated MDA concentration.

Rancho Seco Nuclear Station E-8 2007 AREOR

TABLE E-1 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Water Airborne Fish Food (pCi/L) Particulate or (pCi/kg, wet) Products Analysis Gases (pCi/m 3 ) (pCi/kg, wet)

H-3 20000a Mn-54 1000 30000 Co-60 300 10000 Zn-65 300 20000 Cs-134 30 10 1000 1000 Cs- 37 50 20 2000 2000 Gross Beta 40 b 2C a

Notes: For drinking water samples, this is a 40 CFR Part 141 value b Gross Beta activity in water of ten times the yearly mean of the control samples is indicated as the level that gamma isotopic analysis should be performed on the individual sample (NRC79a). Gamma isotopic analysis on each water sample is required by the REMP and therefore this requirement does not apply.

cGross Beta activity is air of ten times the yearly mean of the control samples is indicated as the level that gamma isotopic analysis should be performed on the individual sample. The value indicated is Site specific.

Rancho Seco Nuclear Station E-9 2007 AREOR

TABLE E-2 MAXIMUM (REQUIRED) LLD VALUES FOR ENVIRONMENTAL SAMPLESac (NRC79A)

Airborne Fish Food Sediment Analysis Water Particulate (pCi/kg, Products (pCi/kg, dry)

(d) (pCi/L) or Gases wet) (pCilkg, dry)

(pCi/m3)

Gross Beta 0.01 H-3 2000 (1000, b Mn-54 15 130 Co-60 15 130 15 0 e Zn-65 30 260 Cs-134 15 (10b) 0.01 d 130 60 150 Cs-137 18(10 0.01 130 60 150 Notes:

(a) Analysis requirements are those recommended in the BTP [NRC79A] and RETS [NUREG79].

(b) LLD for water samples utilized for human consumption only [NUREG79].

(c) Other peaks, which are measurable and identifiable, together with the nuclides in Table E-2, shall be identified and reported.

(d) Composite analysis LLD is Shown; individual sample LLD is 0.05 pCi/m 3 (Site-specific value).

(e) LLD for Mud and Silt Co-60 is not required by RETS [NUREG79]. This value is consistent with the RETS required value for Cs-1 34 and Cs-1 37.

Rancho Seco Nuclear Station E-10 2007 AREOR

APPENDIX F 2007 SAMPLE ANALYSIS RAW DATA TABLES Rancho Seco Nuclear Station F-1 2007 AREOR

TABLE F-1 2007 WEEKLY AIR SAMPLE

SUMMARY

Gross Beta Activity in Air Particulates (pCi/m 3)

Collect Date RAS01CO 2 sigma~ RAS03MO 2 sigma RAS07EO 2 sigmna 1/3/2007 0.036 0.002 0.033 0.002 '0.036 0.002 1/9/2007 0.023 0.002 0.021 0.001 0.023 0.001 1/16/2007 0.026 0.001 0.026 0.002 0.027 0.002 1/23/2007 0.054 0.002 0.052 0.002 0.056 0.002 1/30/2007 0.055 0.002 0.051 0.002 0.053 0.002 2/6/2007 0.063 0.002 0.055 0.002 0.066 0.002 2/13/2007 0.028 0.001 0.028 0.001 0.028 0.002 2/20/2007 0.024 0.002 0.022 0.003 0.018 0.001 2/27/2007 0.009 0.001 0.008 0.001 0.008 0.001 3/6/2007 0.018 0.001 0.017 0.001 0.017 0.001 3/13/2007 0.025 0.001 0.025 0.002 0.019 0.004 3/20/2007 .0.026 0.001 0.023 0.001 0.025 0.001 3/28/2007 0.024 0.004 0.012 0.001 0.012 0.001 4/3/2007 0.020 0.002 0.019 0.001 0.018 0.001 4/10/2007 0.014 0.001 0.014 0.001 0.014 0.001 4/17/2007 0.013 0.001 0.011 0.011 0.009 0.002 4/25/2007 0.011 0.001 0.010 0.001 0.009 0.001 5/1/2007 0.019 0.001 0.018 0.001 0.018 0.001 5/8/2007 0.014 0.001 0.014 0.001 0.014 0.001 5/15/2007 0.018 0.001 0.017 0.002 0.017 0.001 5/22/2007 0.016 0.002 0.013 0.001 0.013 0.000 5/29/2007 0.016 0.001 0.014 0.001 0.015 0.001 6/5/2007 0.013 0.001 0.012 0.001 0.011 0.001 6/12/2007 0.011 0.001 0.004 0.001 0.011 0.001 6/19/2007 0.017 0.001 0.015 0.001 0.016 0.001 6/26/2007 0.015 0.001 0.016 0.001 0.015 0.001 Rancho Seco Nuclear Station F-2 2007 AREOR

TABLE F-1 2007 WEEKLY AIR SAMPLE

SUMMARY

(Continued)

Gross Beta Activity in Air Particulates (pCi/m 3)

CollectDat~e RAS01CO 2 sigma ~RAS03MO* 2 sigma RAS07E9 2sigma 7/2/2007 0.012 0.001 0.013 0.001 0.011 0.001 7/10/2007 0.015 0.001 0.015 0.001 0.015 0.001 7/17/2007 0.009 0.001 0.010 0.001 0.008 0.001 7/24/2007 0.008 0.001 0.008 0.001 0.007 0.001 7/31/2007 0.014 0.001 0.013 0.001 0.013 0.001 8/7/2007 0.014 0.001 0.013 0.001 0.013 0.001 8/14/2007 0.015 0.001 0.013 0.002 0.015 0.001 8/21/2007 0.012 '0.001 0.012 0.001 0.014 0.001 8/28/2007 0.017 0.001 0.015 0.001 0.018 0.001 9/4/2007 0.022 0.001 0.020 0.002 0.022 0.002 9/10/2007 0.019 0.001 0.017 0.001 0.019 0.001 9/17/2007 0.021 0.001 0.021 0.002 0.022 0.002 9/25/2007 0.021 0.001 0.020 0.001 0.021 0.001 10/2/2007 0.022 0.001 0.021 0.001 0.024 0.001 10/8/2007 0.017 0.001 0.015 0.001 0.018 0.001 10/15/2007 0.022 0.002 0.020 0.001 0.021 0.001 10/23/2007 0.014 0.001 0.014 0.001 0.014 0M001 10/30/2007 0.038 0.002 0.038 0.002 0.041 0.002 11/6/2007 0.044 0.002 0.040 0.002 0.047 0.002 11/13/2007 0.038 0.002 0.038 0.002 0.041 0.002 11/20/2007 0.020 0.001 0.020 0.001 0.021 0.002 11/27/2007 0.043 0.002 0.043 0.002 0.042 0.002 12/4/2007 0.036 0.002 0.037 0.020 0.035 0.002 12/11/2007 0.021 0.001 0.020 0.002 0.019 0.001 12/18/2007 0.045 0.001 0.041 0.002 0.040 0.002 12/24/2007 0.019 0.002 0.017 0.003 0.017 0.001 12/31/2007 0.019 0.001 0.019 0.002 0.019 0.002 Rancho Seco Nuclear Station F-3 2007 AREOR

Table F-2 2007 Luxel Summary (Direct Radiation)

Quarterly (mRem)

e tence norm ot spray por 2 RTLO.3CO NE corner of parking lot 19 19 23 18 3 RTL0.3NO Site fence west near south of rail spur I 20 25 30 22 4 RTL0.3LO0 Site fence south of canal pumps I 18 18 20 16 5 RTL0.3HO Site south of Admin Bldg. I 17 17 28 19 6 RTLO.4FO NE corner of PV-1 I 17 14 23 15 7 RTLO.5CO Rancho Seco entrance sign I 19 17 23 17 11 RTL0.6KO Tokay substation I 18 Lost in 24 19 Shipping 16 RTL2.7MO Tippling's residence I 16 15 21 15 17 RTL8.2KO Elliott Cemetery C 23 18 31 19 18 RTL7.8CO Sam Jaber residence C 17 16 21 15 19 RTL1.8FO Rancho Seco Lake Maint. Bldg. I 16 14 23 14 20 RTL1.5MO Clay/ Kirkwood streets I 17 18 20 17 26 RTL3.9KO Borden Road I 18 16 21 14 30 RTL7.4MO Herald Fire Station C 20 15 24 15 31 RTL3.7NO Folsom South Canal back entrance I 19 14 24 19 33 RTL3.8MO Folsom South Canal/ Hwy 104 I 19 15 28 17 35 RTL1.9NO Hadselville/ Clay Creeks I 20 Lost in 28 21 Shipping 43 RTL1.7FO Rancho Seco Lake Well Enclosure I 17 14 23 15 46 RTL1.4DO Hwy 104 mile marker 13.15 I 19 Lost in 27 18 Shipping 55 RTL8.OPO Dillard School C 17 18 22 14 63 RTLO.8DO Marcial Ranch I 17 12 21 14 65 RTLO.6MO Site Boundary Garden I 14 14 24 15 66 RTLO.4NO Soil depression area I 30 29 Missing 20 collection 67 RTLO.4N01 Dredge pile I 19 17 30 18 68 RTLO.3PO Site fence west by IOSB I. 19 15 27 20 88 RTLO.3NP ISFSI south fence, I 22 16 26 17 89 RTLO.4NP ISFSI south fence I 18 16 28 20 90 RTLO.5NP ISFSI west fence I 20 20 27 19 91 RTLO.3QP Site fence NW corner I 17 16 26 16 92 RTLO.7QP Railroad spur I 18 16 26 17 93 RTLO.7JP Clay Rd east south of site I 18 14 23 15 94 RTLO.4PP ISFSI fence north . I 21 18 27 20 I = Indicator Location / C = Control Location Rancho Seco Nuclear Station F-4 2007 AREOR

Table F-3 2007 Garden Vegetables Semi-annual (pCi/kg, wet)

Sapl CllctMn-54 Co-60~ Zn-65~ Cs-134 Cs4137 Comment RLVO.6MO 4/5/2007 <12.8 <14.4 <34.2 <17.4 <13.3 Herbs RLVO.6MO 4/9/2007 <8.77 <9.815 <23.5 <11.7 <13.3 Vegetables RLV18.OKO 4/10/2007 <4.08 <4.55 <10.7 <5.38 <4.32 Vegetables RLVO.6MO 8/20/2007 <8.88 <4.30 <26.6 <11.0 <3.94 RLV18.OKO 19/25/2007 <12.2 <7.03 <35.5 <9.21 <5.65 Table F-4 2007 SEDIMENT Quarterly (pCi/kg)

(Sample Collect Mn-54 Co'-i0 Zn-65 Cs4134 Cs-137~ sigma I_____ _ Date_ _ _

RMSO.6MO 1/23/2007 <4.56 7.57 <12.1 <6.16 99.0 5.9 RMSO.6MOQ 1/23/2007 <4.29 14.8 <9.89 <20.2 95.1 5.8 RMSO.3MO 1/23/2007 <5.32 <5.81 <15.2 <6.81 98.6 8.5 RMSO.6MOQ 4/25/2007 <3.46 11.7 <8.92 <7.02 274 6.8 RMSO.3MO 4/25/2007 <4.88 <13.3 <13.4 <6.32 105 7.4 RMSO.6MO 4/25/2007 <4.53 14.4 <12.8 <5.91 386 7.7 RMSO.6MO 7/24/2007 <6.32 <6.46 <19.4 <8.82 46.0 8.1 RMSO.6MOQ 7/24/2007 <9.92 <9.87 <31.2 <13.8 30.5 10 RMSO-3MO 7/25/2007 <6.13 <6.90 <13.0 <7.12 489 9.2 RMSO.3MO 10/15/2007 <6.16 <6.98 <17.1 <7.88 27.7 4.9 RMSO.6MO 10/15/2007 <3.50 5.93 <8.72 <4.96 195 6.6 RMS0.6MOQ 10/15/2007 <5.00 9.60 <14.7 <6..83 206 8.7 Rancho Seco Nuclear Station F-5 2007 AREOR

TABLE F-5 2007 FISH Semi-Annual (pCi/kg, wet)

RFS0.6M() 9/17/20071<5.87 1<6.23 1<15.7 <7.77 <6.03 Note: (1) =Predator Species TABLE F-6 2007 WELL WATER Quarterly (pCi/L)

Sample~ Collect Date ~Gross Beta Tritium Mn-54 Co-60 Zn-65. Cs-4 34~ Cs-~137J RWWO.8DO 2/6/2007 2.60 <157 <17.0 <9.92 <55.6 <15.2 <8.19 RWWO.3EO 2/6/2007 4.33 <156 <9.65 <6.10 .<22.9 <7.34 <4.19-RWW0.3EO 5/7/2007 4.61 <173 <7.76 <7.68 <15.7 <8.98 <7.68 RWW0.8DO 5/7/2007 4.81 <169 <7.97 <9.00 <20.1 <10.1 <9.03 RWWO.8DO 8/7/2007 2.53 <171 <4.14 <4.72; <9.17 <5.76 <4.18 RVWVO.3EO 8/7/2007 3.88 <171 <9.17 <9.21 <23.1 <11.6 <9.09 RWWO.8DO 11/5/2007 <2.90 <159 <10.8 <11.2 <29.3 <14.0 <11.4 RWWO.3EO 11/5/2007 3.73 <161 <5.98 <5.96 <13.9 <7.21 <5.46 Rancho Seco Nuclear Station F-6 2007 AREOR

TABLE F-7 2007 RUNOFF WATER Biweekly (pCi/L)

Samrple iollect C Date Tritium~ Mn-54 CO-60 Zn-65 Cs-1I34 Cs-I 37 RRWO.6MO 1/9/2007 <367 <8.81 <9.43 <22.7 <11.8 <9.10 RRWO.6MO 1/23/2007 <178 <8.13 <8.98 <16.7 <8.11 <8.16 RRWO.6MO 2/6/2007 <149 <6.86 <8.48 <16.4 <8.46 <7.40 RRWO.6MO 2/20/2007 <146 <8.72 <9.45 <22.7 <11.9 <9.44 RRW0.6MO 3/6/2007 <172 <8.89 <9.67 <22.9 <11.8 <10.2 RRWO.6MO 3/20/2007 <176 <7.53 <8.41 <15.7 - <8.06 <7.60 RRWO.6MOQ 3/20/2007 <175 <8.61 <9.43 <21.6 <16.3 <9.14 RRW0.6MO 4/3/2007 <168 <10.5 <11.0 <26.5 <14.5 <11.0 RRWO.6MO 4/16/2007 <179 <7.07 <7.70 <14.3 <8.03 <7.15 RRWO.6MO 4/30/2007 <171 <8.06 <8.40 <19.4 <11.1 <8.80 RRWO.6MO 5/15/2007 <174 <7.90 <8.22 <19.6 <10.8 <8.59 RRWO.6MO 5/29/2007 <164 <6.31 <6.86 <15.3 <8.64 <7.56 RRWO.6MOQ, 6/12/2007 <164 <5.64 <6.49 <12.7 <7.85 <5.98 RRWO.6MO 6/12/2007 <164 <8.92 <10.2 <23.4 <11.9 <9.36 RRWO.6MO 6/26/2007 <160 <5.97 <6.74 <15.2 <7.85 <5.99 RRWO.6MO 7/12/2007 <172 <9.03 <9.68 <23.6 <15.4 <9.42 RRWO.6MO 7/24/2007 <170 <4.67 <3.89 <11.0 <5.35 <4.60 RRWO.6MO 8/7/2007 <172 <7.43 <7.38 <17.7 <8.42 <6.82 RRWO.6MO 8/21/2007 <164 <6.50 <7.66 <14.9 <8.33 <7.73 RRWO.6MOQ 9/4/2007 <167 <5.71 <5.94 <13.7 <6.87 <6.20 RRWO.6MO 9/4/2007 <167 <9.56 <10.4 <25.9 <12.8 <10.2 RRWO.6MO 9/18/2007 <162 <8.60 <9.84 <21.6 <11.8 <8.99 RRWO.6MO 10/1/2007 <153 <7.14 <7.57 <16.8 <8.60 <7.44 RRWO.6MO 10/15/2007 <91.7 <4.72 <5.26 <10.3 <6.09 <4.56 RRWO.6MO 10/29/2007 <154 <4.97 <5.38 <11.4 <8.51 <6.00 RRWO.6MO 11/12/2007 <156 <11.3 <11.4 <31.4 <14.9 <12.1 RRWO.6MO 11/27/2007 <168 <5.95 <6.83 <11.9 <7.17 <5.92 RRWO.6MO 12/11/2007 <160 <7.40 <8.57 <19.4 <9.77 <7.76 RRWO.6MOQ 12/11/2007 <157 <5.70 <5.94 <13.2 <7.34 <6.38 RRWO.6MO 12/24/2007 <155 <7.90 <8.70 <19.9 <10.7 <8.56 Rancho Seco Nuclear Station F-7 2007 AREOR

TABLE F-8 2007 SURFACE WATER Monthly Grab / Monthly Composite (pCi/L)

Sample< Collect Date Tritiuim Mn-54 Co-6'0 ~Zri65 Cs-134 Cs-1 37 RSW1.3FO 1/23/2007 <174 <9.66 <9.54 <24.3 <12.6 <9.72 RSW0.3MO 1/23/2007 <179 <9.86 <9.95 <25.4 <12.8 <10:1 RSW1.8NO 1/23/2007 <176 <8.09 <9.85 <19.0 <10.2 <9.36 RSW3.7NO 1/23/2007 <183 <10.9 <11.1 <26.9 <13.8 <12.0 RSWO.7NO 1/23/2007 <177 <9.12 <9.27 <22.7 <12.2. <9.54 RSW1.8NOQ 1/23/2007 <177 <4.88 <5.86 <11.1 <5.91 <5.68 RSW1.8NO 2/27/2007 <175 <8.48 <8.75 <21.6 <11.0 <8.75 RSW3.7NO 2/27/2007 <172 <7.73 <7.91 <20.2 <9.95 <7.57 RSWO.3MO 2/27/2007 <173 <6.99 <8.18 <14.7 <8.44 <7.28 RSW1.3FO 2/27/2007 <172 <7.99 <8.88 <20.7 <10.6 <9.25 RSWO.7NO 2/27/2007 <176 <8.54 <9.72 <21.6 <11.4 <9.74 RSW1.3FO 3/26/2007 <178 <6.76 <7.79 <14.6 <8.19 <7.48 RSW1.8NO 3/26/2007 <171 <8.88 <9.68 <22.4 <11.8 <9.53 RSW3.7NO 3/26/2007 <170 <7.97 <8.14 <19.6 <10.3 <7.94 RSWO.7NO 3/26/2007 <174 <7.82 <8.29 <18.9 <11.0 <8.24 RSWO.3MO 3/29/2007 <172 <9.35 <10.1 <24.1 <12.5 <10.5 RSWO.3MO 4/25/2007 <165 <7.18 <7.56 <14.5 <8.60 <7.66 RSW3.7NO 4/25/2007 <172 <8.76 <9.01 <22.3 <11.8 <9.05 RSW1.8NO 4/25/2007 <168 <4.94 <4.95 <9.38 <5.57 <5.35 RSW1.3FO 4/25/2007 <168 <5.81 <6.18 <14.6 <15.8 <5.87 RSW1.8NOQ 4/25/2007 <172 <5.48 <5.84 <13.8 <7.65 <6.32 RSWO.7NO 4/25/2007 <166 <8.11 <8.79 <20.6 <10.7 <8.29 RSW1.8NO 5/29/2007 <165 <8.42 <8.63 <21.9 <11.0 <8.45 RSW1.3FO 5/29/2007 <165 <8.59 <9.34 <21.8 <11.1 <9.28 RSWO.7NO 5/29/2007 <162 <4.05 <4.91 <9.09 <5.24 <4.13 RSWO.3MO 5/29/2007 <165 <6.07 <6.39 <14.6 <14.9 <7.12 RSW3.7NO 5/29/2007 <167 <6.69 <7.65 <15.1 <8.34 <7.44 RSW3.7NO 6/25/2007 <160 <9.12 <9.63 <24.5 <11.9 <9.30 RSWO.3MO 6/25/2007 <161 <7.81 <7.98 <16.7 <8.02 <7.48 RSWO.7NO 6/25/2007 <164 <11.9 <13.3 <31.8 <15.9 <12.9 RSW1.3FO 6/25/2007 <163 <8.51 <9.45 <20.4 <11.4 <10.6 RSW1.8NO 6/25/2007 <161 <12.8 <12.7 <31.3 <15.4 <12.7 Rancho Seco Nuclear Station F-8 2007 AREOR

TABLE F-8 (Continued) 2007 SURFACE WATER Monthly Grab/ Monthly Composite (pCi/L)

RSW3.7NO 7/24/2007 <176 <7.38 <8.05 <15.8 <8.79 <7.60 RSW1.8NO 7/24/2007 <170 <4.48 <4.87 <9.16 <5.62 <4.78 RSW1.8NOQ 7/24/2007 <176 <6.36 <6.08 <14.1 <7.72 <7.11 RSWO.7NO 7/25/2007 <174 <7.89 <8.45 <20.9 <10.3 <8.21 RSWO.3MO 7/25/2007 <173 <8.22 <9.33 <22.1 <11.5 <9.11 RSW1.3FO 7/25/2007 <176 <3.93 <4.59 <8.64 <5.48 <4.20 RSWO.3MO 8/27/2007 <164 <8.86 <9.54 <23.6 <12.2 <9.60 RSW1.3FO 8/27/2007 <163 <4.41 <4.87 <9.44 <5.30 <4.48 RSW1.8NO 8/27/2007 <168 <4.74 <5.08 <10.4 <5.62 <4.86 RSWO.7NO 8/27/2007 <166 <5.85 <6.25 <13.1 <6.03 <5.70 RSW3.7NO 8/27/2007 <161 <7.02 <8.27 <15.5 <8.60 <8.37 RSW1.3FO 9/24/2007 <162 <5.84 <6.06 <13.2 <8.89 <6.90 RSW1.8NO 9/24/2007 <166 <4.28 <4.89 <9.90 <6.17 <4.84 RSW3.7NO 9/24/2007 <163 <8.01 <9.26 <20.2 <10.6 <8.31 RSWO.3MO 9/24/2007 <162 <7.03 <8.05 <15.5 <8.77 <7.57 RSWO.7NO 9/24/2007 <160 <4.14 <5.40 <9.09 <6.31 <4.74 RSW1.3FO 10/22/2007 <151 <4.14 <5.16 <9.94 <6.22 <5.35 RSWO.3MO 10/23/2007 <158 <4.59 <4.83 <9.68 <5.38 <4.74 RSW0.7NO 10/23/2007 <157 <6.46 <7.08 <15.7 <9.20 <7.54 RSW1.8NOQ 10/23/2007 <156 <9.58 <10.6 <25.6 <13.2 <9.93 RSW3.7NO 10/23/2007 <159 <6.08 <6.63 <16.2 <8.14 <6.42 RSW1.8NO 10/23/2007 <154 <6.79 <7.88 <16.6 <8.66 <7.85 RSW1.3FO 11/21/2007 <165 <8.25 <7.70 <16.2 <9.23 <7.94 RSW1.8NO 11/21/2007 <165 <3.87 <3.58 <7.70 <4.95 <3.92 RSW3.7NO 11/21/2007 <164 <7.01 <7.69 <18.8 <9.26 <7.36 RSWO.3MO 11/21/2007 <165 <4.59 <5.39 <10.7 <6.21 <5.60 RSW0.7NO 11/21/2007 <165 <9.08 <9.70 <22.2 <12.1 <9.79 RSW3.7NO 12/20/2007 <158 <9.53 <9.84 <22.4 <12.1 <9.77 RSWO.3MO 12/20/2007 <155 <3.70 <3.89 <7.43 <5.15 <4.32 RSW0.7NO 12/20/2007 <156 <9.05 <9.76 <23.1 <12.0 <9.39 RSW1.3FO 12/20/2007 <158 <4.65 <4.96 <10.3 <5.47 <4.60 RSW1.8NO 12/20/2007 <158 <6.70 <7.83 <15.9 <8.41 <7.24 Rancho Seco Nuclear Station F-9 2007 AREOR

TABLE F-9 2007 Drinking Water Monthly (pCi/L)

Sample ID 'Collect Date Gross Beta Tritium Mn-54~ Co-60 Zn-65 ~Cs-134 Cs-i 37 RDW0.1G0 1/23/2007 4.75 <180 <4.84 <7.47 <10.2 <6.29 <5.43 RDWO.2PP 1/23/2007 4.10 <180 <9.55 <10.3 <24.0 <12 8 <10.2 RDW1.8FP 1/23/2007 4.68 <176 <8.31 <10.0 <19.1 <8.91 <8.03 RDWO.2PP 2/27/2007 2.85 <176 <9.30 <9.09 <22.8 <11.1 <9.37 RDW1.8FP 2/27/2007 6.31 <170 <8.99 <8.86 <22.7 <11.2 <8.57 RDWO.IGO 2/27/2007 3.86 <175 <9.42 <9.42 <25.1 <12.2 <9.02 RDWO.2PP 3/26/2007 3.70 <168 <7.45 <7.79 <18.0 <9.61 <7.84 RDW1.8FP 3/26/2007 4.85 <170 <5.88 <6.42 <14.0 <6.92 <6.61 RDW0.1GO 3/26/2007 3.98 <173 <6.77 <7.21 <16.9 <8.89 <7.08 RDW0.1GO 4/25/2007 4.50 <167 <8.34 <8.74 <21.0 <10.9 <8.55 RDWO.2PP 4/25/2007 3.06 <167 <4.20 <4.78 <8.40 <5.22 <4.21 RDW1.8FP 4/25/2007 5.10 <169 <7.77 <8.30 <19.1 <10.6 <8.65 RDWO.2PP 5/30/2007 2.85 <166 <4.95 <4.59 <10.5 <5.80 <5.16 RDW1.8FP 5/30/2007 5.14 <162 <8.79 <8.77 <22.4 <11.0 <8.50 RDW0.1GO 5/30/2007 2.15 <163 <10.3 <10.3 <26.2 <13.1 <10.3 RDW0.1GO 6/25/2007 3.13 <162 <7.12 <7.44 <15.2 <8.69 <7.26 RDWO.2PP 6/25/2007 3.45 <163 <9.02 <9.38 <23.9 <11.6 <9.26 RDW1.8FP 6/25/2007 3.57 <160 <8.64 <8.86 <19.8 <9.40 <8.48 RDWO.2PP 7/25/2007 <3.02 <174 <5.50 <5.94 <11.7 <7.45 <6.58 RDWO1GO 7/25/2007 <2.91 <174 <8.60 <9.26 <22.3 <11.5 <9.10 RDW1.8FP 7/25/2007 3.16 <171 <6.69 <6.53 <14.8 <7.27 <6.66 RDW1.8FP 8/27/2007 2.44 <166 <9.03 <9.68 <22.5 <15.0 <9.41 RDWO.1GO 8/27/2007 2.74 <168 <4.31 <4.86 <9.30 <5.13 <4.25 RDWO.2PP 8/27/2007 2.46 <165 <5.81 <6.18 <13.0 <8.08 <6.42 RDWO.2PP 9/24/2007 2.44 <162 <7.47 <7.27 <15.0 <8.04 <7.85 RDW1.8FP 9/24/2007 3.76 <167 <8.54 <9.21 <20.8 <23.5 <8.45 RDW0.1GO 9/24/2007 2.86 <163 <5.82 <6.15 <12.2 <9.20 <6.63 RDW0.1GO 10/22/2007 3.83 <155 <2.73 <3.09 <6.18 <3.93 <3.27 RDWO.2PP 10/22/2007 2.77 <161 <5.80 <6.31 <13.3 <7.20 <6.67 RDW1.8FP 10/22/2007 4.14 <158 <3.86 <4.07 <8.68 <5.23 <4.62 RDW0.1GO 11/21/2007 3.00 <166 <6.45 <6.94 <15.7 <8.23 <6.76 RDWO.2PP 11/21/2007 3.67 <167 <3.63 <4.19 <7.68 <4.79 <3.85 RDW1.8FP 11/21/2007 <2.92 <166 <2.82 <2.92 <6.51 <3.96 <3.12 RDWO.2PP 12/20/2007 2.85 <157 <3.51 <3.30 <6.46 <10.5 <3.91 RDW1.8FP 12/20/2007 3.16 <158 <6.27 <6.60 <14.0 <7.43 <6.29 RDWO.1GO 12/20/2007 <3.04 <158 <4.14 <4.88 <8.54 <5.04 <4.24 Rancho Seco Nuclear Station F-1 0 2007 AREOR

APPENDIX G 2007 MISSED SAMPLE REPORT In accordance with the requirements REMP manual section 3.1, the following samples are being reported as not being collected for the reasons indicated. Corrective action as required by the REMP manual is as indicated.

Air Sampler (Airborne Pathway)

RASO.1CO PAP Building (indicator)/ RASO.3MO, Plant Effluent (indicator) / RASO.7EO, Rancho Seco Meteorological Tower (control) - On February 6, 2007, during routine change out of the air samplers, it was found that 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> sample time had been lost from the sample period for all three samplers due to a power outage. Air sampler run time was 10127.5, 10154.5, and 10446.0 minutes, respectively. The minimum sample volume was achieved for all three air samples.

RASO.1CO PAP Building (indicator)/ RASO.3MO, Plant Effluent (indicator) - On February 15, 2007 the air filters at the two locations were removed and new filters were put in place.

The reason the filters were removed was for an evaluation of the Site airborne activity after a contamination event during the Reactor vessel cut up project. The sample period for the locations was covered by two filters instead of one. Minimum sample volume was achieved for both locations. PDQ 07-004 was written to cover the incident.

RASO.1CO PAP Building (indicator) - On March 28, 2007, during normal change out, the air sampler was found not running. The air sampler was replaced and restarted. Evaluation of the failed air sampler found a electrical failure of the motor possibly due to a power spike on March 21, 2007. Conservative volume was calculated using that information and a comparison of the dust loading on the other two locations.

RASO.3MO, Plant Effluent (indicator) - On June 12, 2007, air sampler was found not running during normal change out. Power had been lost for the air sampler due to water spray from a piping system to cause the air sampler to short out and trip the supply breaker. The power was rerouted and the air sampler was restarted. Minimum sample volume was not achieved for this location for this sample period. Air filter was sent in for analysis.

RASO.3MO, Plant Effluent (indicator) - Air sampler power was not available for this location for three hours during the sample period of August 14, 2007 to August 21, 2007 due to electrical maintenance. Air sample was collected and minimum volume was achieved.

RASO.3MO, Plant Effluent (indicator) / RASO.7EO, Rancho Seco Meteorological Tower (control) - Power outage for these two locations resulted in a loss of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> for location RASO.3MO and 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for location RASO.7EO for the sample period of December 11, 2007 to December 18, 2007. Air samples were collected and minimum volume was achieved.

Rancho Seco Nuclear Station G-1 2007 AREOR

APPENDIX G 2005 MISSED SAMPLE REPORT (Continued)

Direct Monitoring Pathway (Luxel Badge))

RTL0.4NO Soil Depression Area (Indicator) - On July 25, 2007 (3rd Quarter 2007 results) the location for this direct radiation monitoring location was moved to a new location in the same general area to facilitate soil remediation based on MARSSIM survey results. Data for this location will be collected for the 3 rd quarter monitoring period.

RTL0.6K0 Tokay Substation Indicator/ RTLI.9NO Hadselville Creek/ Clay Creek (indicator)/ RTLI.4DO East of Site, Twin Cities Road (Indicator) - Badges for these three locations were lost in shipment. Badges were shipped on July 19, 2007 and were received at the processing vendor (Landauer) on July 27, 2007. No discrepancies were noted by the shipping company (UPS) or the analysis vendor. Results were received and logged in and the discrepancy was discovered during data review. Landauer was contacted and indicated no report was made of damage to the shipment. UPS was contacted and they reported no damage was indicated for the shipment. Results for these locations will not be available for the 2 nd quarter 2007 report. Corrective action was to place on the badges in a zip lock bag for additional protection from loss/ damage and to insure the shipment to hopefully instill accountability in the shipping process.

RTLO.4NO Soil Depression Area (Indicator) - During badge change out for the 3rd quarter 2007, the monitoring badges at this location were not found. The cricket cage was also missing. A search of the area was conducted and no evidence of the badges or cricket cage was found. This is the location that was moved for soil remediation, so the MARSSIM staff was contacted to see if they had any information regarding the location of the badges. 4th quarter badges were placed at the location. No data will be available for this location for the 3 rd quarter 2007 results..

Rancho Seco Nuclear Station G-2 2007 AREOR

Personnel- Name and RP #

NAME RP # NAME RP #

Alderman, Wayne RPl17 Edwards, Leon RP113 Allen, James H. RP078 Eilering, Jim RP026 Anderson, Dee An RP036 Field, James J. RP028 Ashby, William F. RP096 Fore, Dorrel RPl14 Astronomo, Jose V RP031 Frank, Gary RP013 Averette, Earl A. RP060 Gacke, Brad A. RP083 Barba, Jesus G. RP032 Gaines, Rebecca E RP091 Barnes, Vernon G. RP128 Garcia, Emilio NRC07 Barnreiter, Karl V. RP087 Garcia, Tomas E. RP132 Boland, Terry L. RP156 Gilson, David G. RP049 Bourn, Michael RP062 Goetsch, Ronald RP040 Bridger, Philip T. RP044 Gonzales, David G RP246 Brown, Douglas RP140 Gonzales, Ramon RP247 Brown, Erin L. RP112 Griffin, Charles W. RP134 Bua, Michael J. RP137 Grinley, John L. RP033 Burnett, Andre J. RP061 Haley, Aaron J. RP054 Burrell, Ronald E. RP075 Harris, Craig V. RP109 Byrd, Edwin RP057 Hart, David RP038 Carder, Clayton W. RP037 Hawkins, Janice RP214 Cathey, LarryRP023 Hawley, Wayne H. RP009 Caudell, Thomas RP146 Hayes, Michael RP034 Chachere, Arnold RP158 Healy, Mike S. RP027 Clark, Dickson A. RP099 Hernandez, Fernan RP135 Clarke, Thomas RP133 Herrera, "Andy" Fr RP142 Cook, Edward RP072 Herrera, Frank RP085 Crandall, Rickey E. RP076 Hill, Thomas C. RP098 Cuadras, Eli E. RP020 Howard, Pamela R RP068 Decker, Robert RP018 Imura, Tom RP154 D'Este, Samuel T. RP131 Iverson, John W. RP127 Devine, Tim RP110 Iverson, Lillian 0. RP071 Dodero, Mike RP107 James, Reginald RP206 Dolezal, Edward RP015 Jensen, Michael RP041 Easley, Paul A. RP008 Johnson, Karl C. RP104 Eder, Gabriel J. RP007 Johnson, Matthew RP010 Wednesday, April 16, 2008 Page I of 2

NAME RP # NAME RP #

Jones, Robert E. RP095 Share, Tim RP090 Koontz, David E. RP030 Sholes, Terry RP174 Kovach, George J. RP046 Snyder, Michael RP141 Kreeger, Keith RP178 Sparks, Stephen A RP022 Kubic, Daniel J. RP052 Star, Mark RP139 Lasavio, Mark RP165 Stark, Larry RP164 Lee, Ronda RP148 Stayner, George H. RP067 Leggett, Johnnie RP077 Stein, Michael RP004 Lieneck, Walter RP123 Steinbacher, Micha RP111 Luce, Penny RP039 Stephenson, Dougl RP212 Luna, Juan RP121 Swiger, Stanley W. RP024 Marble, James RP014 Tallman, Dan RP201 McChesney, John RP116 Terry, Philip RP005 McMurtry, Joe D. RP012 Tewsley, Alan D. RP025 Mennella, Michael RP124 Trujillo, Richard RP1,45 Mote, Caroline E. RP019 Warmuth, Jeff RP190 Murdock, Michael RP074 Welch, David, J. RP102 Nichols, Rob J. RP001 Wilson, Brian RP035 Nicolls, Steven A. RP064 Witczak, Justin RP016 Norris, Joseph RP244 Woolman, William RP108 Pacheco, Jeff RP185 Zambrano, Olvin E. RP094 Parkhurst, Glenn 0 RP150 Zlotnick, Lucien RP003 Pillsbury, George RP101 Zwierzynski, Antho RP047 Pimentel, Emanuel RP103 Porteous, Launie RPO11 Porterfield, Steven RP065 Rabb, Ivan C. RP080 Ramirez, Joaquin RP088 Redeker, Steven J. RP050 Reeves, Michael RP021 Renteria, Maria E. RP100 Ridley, Roy F. RP063 Roberts, George F. RP017 Rodriguez, Daniel RPl15 Ronningen, Einar T RP002 Russell, Donald RP055 Wednesday, April 16, 2008 Page 2 of 2