ML020710735

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2001 Annual Radioactive Effluent Release Report
ML020710735
Person / Time
Site: Rancho Seco
Issue date: 02/27/2002
From: Redeker S
Sacramento Municipal Utility District (SMUD)
To: John Hickman
Document Control Desk, NRC/FSME
References
-RFPFR, MPC&D 02-023
Download: ML020710735 (53)
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Text

SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT 0 P. 0. Box 15830, Sacramento CA 95852-1830, (916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA MPC&D 02-023 February 27, 2002 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-312 Rancho Seco Nuclear Station License No. DPR-54 2001 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Attention: John Hickman In accordance with 10 CFR 50.36a(a)(2) and Rancho Seco Permanently Defueled Technical Specification D6.9.3, the District submits the enclosed Rancho Seco Annual Radioactive Effluent Release Report for the period January 1 through December 31, 2001.

Members of your staff requiring additional information or clarification may contact Walter Partridge at (916) 732-4811.

Sincere.y, Steve J. Redeker Manager, Plant Closure & Decommissioning Attachment cc w/atch: E.W. Merschoff, NRC, Region IV, Arlington

/

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

RANCHO SECO NUCLEAR GENERATING STATION LICENSE NUMBER DPR-54 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 TABLE OF CONTENTS INTRODUCTION .......................................................................................................................................... 1 I. SUPPLEM ENTAL INFORMATIO N ................................................................................................... 2 A. Regulatory Lim its & Guidelines for Effluent Releases ................................................................... 2 B. Maxim um Effluent Concentrations ................................................................................................. 3 C. Measurem ent Methods for Total Radioactivity ............................................................................... 3 D. Batch Releases (via m onitored pathways) ..................................................................................... 4 E. Unplanned Releases ........................................................................................................................... 5 F. Radioactive Effluent Monitoring Instrumentation Inoperable for Greater Than 30 Days ................. 5 II. ESTIM ATION OF ERROR ..................................................................................................................... 6 III. GASEO US EFFLUENTS ....................................................................................................................... 7 Table Ill-A Gaseous Effluents - Sum m ation of All Releases ............................................................ 8 Table III-B Gaseous Effluents - Ground Level Releases ...................................................................... 9 Table Ill-C Gaseous Effluents - Typical Lower Lim its of Detection ................................................ 10 Table III-D Radiological Im pact on Man Due to Gaseous Effluents .............................................. 11 IV. LIQUID EFFLUENTS ........................................................................................................................... 12 Table IV-A Liquid Effluents - Sum m ation of All Releases ............................................................... 13 Table IV-B Liquid Effluents ................................................................................................................. 14 Table IV-C Liquid Effluents - Typical Lower Lim its of Detection ..................................................... 15 Table IV-D Liquid Effluents - Radiological Impact on Man Due to Liquid Effluents ......................... 16 V. SOLID W ASTE ..................................................................................................................................... 17 ATTACHMENTS

1. Radiological Environmental Monitoring Program Manual, Revision 13

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 INTRODUCTION Rancho Seco Nuclear Generating Station (RSNGS) Unit No. 1 is located in Sacramento County, California approximately 25 miles southeast of Sacramento and 26 miles north-northeast of Stockton. Rancho Seco Unit No. 1 began commercial operation on April 17, 1975. The single unit on the Rancho Seco site was a pressurized water reactor supplied by Babcock and Wilcox. The rated capacity was 963 gross megawatts electrical. Because of a public vote on June 6, 1989, the District shutdown the Rancho Seco Nuclear Generating Station and completed defueling operations on December 8, 1989.

This Annual Radioactive Effluent Release Report (ARERR) provides a summary of gaseous and liquid effluent releases made from Rancho Seco during the period January 1 through December 31, 2001. Also presented in this report is the projected radiological impact from these releases and a summary of solid radioactive waste shipments.

This report has been prepared by the Sacramento Municipal Utility District to meet the requirements of Rancho Seco Technical Specification D6.9.3 and Offsite Dose Calculation Manual (ODCM) Step 6.15. It is presented in accordance with the format of USNRC Regulatory Guide 1.21. The radiation doses reported in this ARERR are calculated for a hypothetical individual who receives the maximum possible exposure at or beyond the applicable Site Boundary.

Releases of radioactivity in gaseous and liquid effluents during this report period did not exceed the limits of 10 CFR 20 or the numerical guidelines of 10 CFR 50, Appendix I. A 40 CFR 190 dose evaluation is not required because radioactive effluent releases did not exceed twice the numerical guidelines of 10 CFR 50, Appendix I.

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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY- DECEMBER 2001 SUPPLEMENTAL INFORMATION A. REGULATORY LIMITS & GUIDELINES FOR EFFLUENT RELEASES

1. Gaseous Effluents
a. Noble Gas dose rate limit at or beyond the Site Boundary for Gaseous Effluents (Offsite Dose Calculation Manual (ODCM) Technical Requirement 6.14.6):

500 mrem/year to the total body 3000 mrem/year to the skin

b. Noble Gas air dose limit at or beyond the Site Boundary for Gaseous Effluents (ODCM Technical Requirement 6.14.7, numerical guidelines of 10 CFR 50, Appendix I):

5 mrad per calendar quarter for gamma radiation 10 mrad per calendar quarter for beta radiation 10 mrad per calendar year for gamma radiation 20 mrad per calendar year for beta radiation

c. Dose rate limit at or beyond the Site Boundary for Gaseous Effluents for Tritium and radioactive material in particulate for with half-lives greater than 8 days (ODCM Technical Requirement 6.14.6):

1500 mrem/year to any organ

d. Dose commitment to a member of the public at or beyond the Site Boundary for Gaseous Effluents from Tritium and radioactive material in particulate form with half-lives greater than 8 days (ODCM Technical Requirement 6.14.8, numerical guidelines of 10 CFR 50, Appendix I):

7.5 mrem per calendar quarter to any organ 15 mrem per calendar year to any organ

2. Liquid Effluents
a. The concentration of radioactive material in liquid effluents released beyond the Site Boundary for Liquid Effluents shall not exceed the limits of 10 CFR 20, Appendix B, Table 2, Column 2.

This applies to all radionuclides except dissolved or entrained noble gases (ODCM Technical Requirement 6.14.2).

b. Dose commitment to a member of the public at or beyond the Site Boundary for Liquid Effluents from radioactive materials in liquid effluents shall be limited to (ODCM Technical Requirement 6.14.3, numerical guidelines of 10 CFR 50, Appendix I):

1.5 mrem per calendar quarter to the total body 5 mrem per calendar quarter to any organ 3 mrem per calendar year to the total body 10 mrem per calendar year to any organ 2

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 B. MAXIMUM EFFLUENT CONCENTRATIONS

1. Gaseous Effluents The concentrations listed in 10 CFR 20, Appendix B, Table 2, Column 1 (air) are not directly used in calculations for determining permissible gaseous effluent release rates. The annual dose limits of 10 CFR 20 for unrestricted areas are the doses associated with the concentrations of 10 CFR 20, Appendix B, Table 2, Column 1. ODCM Technical Requirement dose rate limits (mrem/yr) for gaseous effluents are provided to ensure that the dose rate from gaseous effluents at any time at the Site Boundary for Gaseous Effluents will be within the annual dose limits of 10 CFR 20 for unrestricted areas. These dose rate limits (listed above in part A) are used for determining permissible gaseous effluent release rates.
2. Liquid Effluents The concentration values listed in 10 CFR 20, Appendix B, Table 2, Column 2 are used in calculations to determine permissible liquid discharge flow rates. The most conservative Maximum Effluent Concentration (MEC) value for each radionuclide detected in the liquid effluent sample (excluding dissolved or entrained noble gases) is used in the calculations.

C. MEASUREMENT METHODS FOR TOTAL RADIOACTIVITY

1. Fission and Activation Gases Gamma Spectroscopy (HPGe)

Liquid Scintillation (H-3)

2. Particulates Gamma Spectroscopy (HPGe)

Beta Proportional (Sr-90, gross beta)

Alpha Proportional (gross alpha)

3. Liquid Effluents Gamma Spectroscopy (HPGe)

Liquid Scintillation (H-3)

Beta Proportional (Sr-90, gross beta)

Alpha Proportional (gross alpha)

NOTE: HPGe refers to Hyper-Pure Germanium 3

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 D. BATCH RELEASES (via monitored pathways)

1. Liquid (RHUT Releases) Quarter 1 Quarter 2 Quarter 3 Quarter 4
a. Number of batch releases 1 9 6 8
b. Total time period for batch releases (hours) 7.70 34.48 13.80 28.88
c. Maximum time period for a batch release (hours) 7.70 5.82 3.23 5.67
d. Average time period for a batch release (hours) 7.70 3.83 2.30 3.61
e. Minimum time period for a batch release (hours) 7.70 1.43 1.67 1.92
2. Liquid (Retention Basin Discharges)
a. Number of batch releases 0 9 5 6
b. Total time period for batch releases (hours) 128.38 70.95 87.42
c. Maximum time period for a batch release (hours) 16.83 17.22 21.17
d. Average time period for a batch release (hours) 14.26 14.19 14.57
e. Minimum time period for a batch release (hours) 11.70 12.00 9.70
f. Average stream flow during periods of release of effluent into a flowing 17.0 17.2 17.3 stream (cfs)

NOTE: The Regenerant Holdup Tanks (RHUTs) are released to the Retention Basins. The Retention Basins are discharged offsite. All 10 CFR 50, Appendix I dose calculations are based on the RHUT releases. All 10 CFR 20 calculations are based on the Retention Basin discharges.

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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY- DECEMBER 2001 E. UNPLANNED RELEASES This section describes unplanned releases of radioactivity in liquid and gaseous effluent.

Gaseous None None F. RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION INOPERABLE FOR GREATER THAN 30 DAYS None 5

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 II. ESTIMATION OF ERROR The methods for establishing error estimates included review of applicable station procedures, inspection of sampling equipment, engineering estimates, statistical applications, review of calibration setpoint data, and communication with plant personnel. The various sources of error (s) in reported values of gaseous effluents, liquid effluents, and solid waste are assumed to be independent, and thus the total error is calculated according to the formula:

Total Error = VG1 - + (72 + "2+ a1i where: (7 = relative error associated with component i Sources of error for gaseous effluents include fan error (flow), grab sampling, collection, filter efficiency, counting, and calibration.

Sources of error for liquid effluents include RHUT volume, dilution water flow rate, grab sampling, counting, and calibration.

Sources of error for solid waste include offsite lab smear analysis, dose rate meter calibration, dose rate meter reading, computer program dose-to-curie calculation, sample volume measurement, gamma spec counting, gamma spec calibration, and waste volume determination.

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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY- DECEMBER 2001 III. GASEOUS EFFLUENTS Table Ill-A, Gaseous Effluents - Summation of All Releases, provides a detailed summary of gaseous effluent releases per quarter. This table summarizes releases of fission and activation gases, particulates with half-lives greater than 8 days, and tritium. The methodology used to calculate the Percent of ODCM Technical Requirement limit is as follows:

S[(Fj )(Avg Rel Rate)(X I Q)(Dose Factor)]

% Tech Req Limit =(Dose Rate Limit) x 100%

where:

Fi = The fraction of the total number of Curies of nuclide i out of the total curies in that category for that quarter (unitless).

NOTE: Fj always equals 1.0 for H-3 because it is the only nuclide in the category.

(Total Curies per category per quarter)( I E +06 ItCi.

=

Avg Rel Rate (# seconds in the quarter)

X/Q = A default dispersion factor determined to be conservative when compared to the use of actual data (sec/m3).

Dose Factor = The values derived for each nuclide i from NRC Regulatory Guide 1.109 (Ki, Li+1.1 Mi, or Raij). [Units in (mrem/yr)/(pCi/m3)]

Dose Rate Limit = The Technical Requirement (i.e., Regulatory) limits for dose rate listed in Section I of this report (mrem/yr).

NOTE: Particulates with half-lives less than 8 days are not included in this calculation.

The methodology used to calculate the Estimated Total Error (%) in Table III-A is presented in Section II of this report.

Table Ill-B, Gaseous Effluents - Ground Level Releases, provides a complete quarterly summary of the amount of radioactivity (Ci) released per radionuclide in each quarter. Data from continuous and batch releases are provided for fission gases, particulates, and tritium. Data reported for batch releases results only from unplanned releases.

Table Ill-C, Gaseous Effluents - Typical Lower Limits of Detection, provides a listing of the typical lower limit of detection (LLD) concentrations in pCi/cc for various radionuclides.

Table Ill-D, Radiological Impact on Man Due to Gaseous Effluent Releases, provides a summary of calculated radiation doses delivered to a maximum exposed hypothetical individual at the Site Boundary for Gaseous Effluents (actual doses will be assessed in the 2000 Annual REMP Report). The maximum calculated organ dose, gamma air dose, and beta air dose are listed for each quarter along with an annual total. The direct radiation dose results, based on monitoring badge dosimetry, are also listed. Presented in this table for each category is a comparison versus ODCM Technical Requirement dose limits with the exception of direct radiation measurements.

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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 TABLE III-A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Est. Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Error, %

A. Fission & Activation Gases (i.e. Noble Gases)

1. Total Release Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 2-3 E+01
2. Average Release Rate for period pCi/sec 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00
3. Percent of Tech Req limit  % N/A N/A N/A N/A B. Particulates
1. Particulates with half-lives>8 days Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 2.3 E+01
2. Average Release Rate for period pCi/sec 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00
3. Percent of Tech Req limit  % N/A N/A N/A N/A
4. Gross Alpha radioactivitya Ci 1.71 E-07 6.47E-08 1.23E-07 5.36E-07 C. Tritium
1. Total Release Ci 2.32E-01 2.81 E-01 1.52E-01 2.39E-01 2.3 E+01
2. Average Release Rate for period pCi/sec 2.95E-02 3.57E-02 1.91 E-02 3.01 E-02
3. Percent of Tech Req limit  % 2.50E-04 3.03E-04 1.62E-04 2.55E-04 a Gross alpha activity has been determined to be naturally occurring and not the result of the fuel cycle.

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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 TABLE Ii-B GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4

1. Fission Gases (i.e., Noble Gases)

None Ci 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00

2. Particulates None Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00
3. Tritium H-3 Ci 2.32E-01 2.81 E-01 1.52E-01 2.39E-01 9

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 TABLE IIl-C GASEOUS EFFLUENTS - TYPICAL LOWER LIMITS OF DETECTION RADIONUCLIDES LLD (iCi/cc)

1. Tritium (H-3) 2.27 E-10
2. Fission & Activation Gases:

Krypton-85 3.47 E-06

3. Particulates:

Manganese-54 2.08 E-12 Cobalt-58 2.29 E-12 Iron-59 5.89 E-12 Cobalt-60 3.11 E-12 Strontium-89 2.00 E-15 Strontium-90 5.00 E-15 Cesium-134 1.52 E-12 Cesium-137 1.88 E-12 Barium-140 3.06 E-12 Cerium-141 1.15 E-12 Cerium-144 3.69 E-12 10

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 TABLE III-D RADIOLOGICAL IMPACT ON MAN DUE TO GASEOUS EFFLUENT RELEASES CALCULATED RADIATION DOSES AT THE SITE BOUNDARY FOR GASEOUS EFFLUENTS:

2001 Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual A. Tritium, Particulate

1. Maximum Organ Dose mrem 7.51E-03 9.1OE-03 4.94E-03 7.74E-03 3.00E-02 (a) (a) (a) (a) (a)

Percent Tech Req limit  % 1.OOE-01 1.21 E-01 6.59E-02 1.03E-01 2.00E-01 B. Noble Gas

1. Gamma Air Dose mrad 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Percent Tech Req limit N/A N/A N/A N/A N/A
2. Beta Air Dose m rad 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Percent Tech Req limit N/A N/A N/A N/A N/A C. Direct Radiation
1. Dose (Monitoring Badges) mrem 0.00 E+00' 0.00 E+00' 0.00 E+00* 0.00 E+00* 0.00 E+00*
2. Percent of Tech Req limit N/A N/A N/A N/A N/A NOTE: The quarterly doses listed above were calculated using dose factors from GASPAR and default meteorological data for each quarter. Annual doses are the sum of quarterly doses.

(a)Child - All Except Bone

" None of the Indicator stations associated with gaseous effluent releases indicate significant radiation attributable to Plant operations.

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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 IV. LIQUID EFFLUENTS Table IV-A, Liquid Effluents - Summation of All Releases, provides a detailed summary of liquid effluent releases per quarter. This table summarizes releases of fission and activation products, tritium, dissolved and entrained gases, and gross alpha radioactivity. Also listed is the volume of waste released prior to dilution and the volume of dilution water used during each quarter.

The following methodology is used to calculate the Average Diluted Concentration and the Percent of ODCM Technical Requirement Limit in Table IV-A:

%Tech Req Limit =  : [,

i LMECi where: n = The total number of radionuclides identified C, = The average diluted concentration of radionuclide i (Total Release per Category per Quarter in ,uCi)

(Total Release Volume (part F in Table IV - A)in ml)

MEC = The MEC of the ith radionuclide, from 10 CFR 20, Appendix B, Table 2, Column 2 The methodology used to calculate the estimated total error in Table IV-A is presented in Section II of this report.

Table IV-B, Liquid Effluents, provides a complete quarterly summary of the amount of radioactivity (Ci) released per radionuclide in each quarter. Data is provided for fission and activation products, and for dissolved and entrained gases. Tritium and gross alpha are not included in this table (they are listed in Table IV-A). Since no continuous releases of liquid radioactive effluent are made from RSNGS, data is provided only for batch releases.

Table IV-C, Liquid Effluents - Typical Lower Limits of Detection, provides a listing of the typical lower limit of detection (LLD) concentrations in pCi/ml for various radionuclides.

Table IV-D, Radiological Impact on Man Due To Liquid Effluent Releases, provides a summary of calculated radiation doses delivered to a maximum exposed hypothetical individual at the Site Boundary for Liquid Effluents (actual doses will be assessed in the 2000 Annual REMP Report). The maximum calculated total body dose and organ dose are listed for each quarter along with an annual total. A comparison versus ODCM Technical Requirement dose limits is also presented.

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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 TABLE IV-A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Est. Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Error, %

A. Fission & Activation Products

1. Total Release (not including tritium, gases, alpha) Ci 4.69E-06 1.85E-05 4.58E-06 1.OOE-04 2.3 E+01
2. Average diluted concentration during period pCi/mI 1.10E-12 4.88E-12 1.18E-12 2.57E-1 1
3. Percent of Tech Req limit  % 1.02E-04 4.36E-04 7.49E-05 2.53E-03 B. Tritium
1. Total Release Ci 5.76E-03 1.51 E+00 9.23E-01 1.08E+00 2.3 E+01
2. Average diluted concentration during period pCi/mI 1.35E-09 3.99E-07 2.38E-07 2.77E-07
3. Percent of Tech Req limit  % 1.35E-04 3.99E-02 2.38E-02 2.77E-02 C. Dissolved and Entrained Gases (i.e., Noble Gases)
1. Total Release Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 N/A
2. Average diluted concentration during period pCi/mI 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 D. Gross Alpha radioactivity
1. Total Release Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 N/A E. Volume of Waste Released Retention Basins (prior to dilution) Liters 0.00 E+00 1.17E+07 5.56E+06 8.02E+06 5.0 E+00 RHUTs (prior to dilution) Liters 1.28E+05 4.35E+06 2.15E+06 3.19E+06 5.0 E+00 F. Volume of dilution water used during period Liters 4.27E+09 3.79E+09 3.88E+09 3.90E+09 2.0 E+01 13

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 TABLE IV-B LIQUID EFFLUENTS Nuclides Released Batch Mode

1. Fission and activation products (excluding tritium, gases alpha) Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Co-60 Ci 4.97E-07 2.97E-06 2.51 E-06 2.46E-06 Cs-1 37 Ci 4.19E-06 1.55E-05 2.07E-06 9.77E-05 Total (for quarter) Ci 4.69E-06 1.85E-05 4.58E-06 1.OOE-04
2. Dissolved and entrained gases None NOTE: No continuous releases of liquid radioactive effluent are made from Rancho Seco Nuclear Generating Station.

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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 TABLE IV-C LIQUID EFFLUENTS - TYPICAL LOWER LIMITS OF DETECTION RADIONUCLIDES BATCH MODE: LLD (wCi/mI) 1 Tritium (H-3) 2.60 E-06

2. Particulates:

Manganese-54 2.11 E-09 Iron-59 3.71 E-09 Cobalt-57 2.12 E-09 Cobalt-58 1.93 E-09 Cobalt-60 1.98 E-09 Zinc-65 4.34 E-09 Strontium-90 5.00 E-10 Ruthenium-1 06 1.79 E-08 Silver-i 1Om 1.94 E-09 Antimony-125 5.78 E-09 Cesium-1 34 1.93 E-09 Cesium-136 2.23 E-09 Cesium-1 37 2.30 E-09 Barium-140 7.75 E-09 Cerium-141 3.60 E-09 Cerium-144 1.59 E-08

3. Dissolved and Entrained Gases:

Krypton-85 4.87 E-07 15

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 TABLE IV-D RADIOLOGICAL IMPACT ON MAN DUE TO LIQUID EFFLUENT RELEASES CALCULATED RADIATION DOSE COMMITMENTS FOR LIQUID EFFLUENTS:

2001 Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual 6.52E-02 A. Maximum Total Body Dose mrem 1.15E-03 1.98E-02 7.61 E-03 3.66E-02 (a) (b) (C) (a) (b)

Percent Tech Req limit  % 7.67E-02 1.32E+00 5.07E-01 2.44E+00 2.17E+00 B. Maximum Organ Dose m rem 2.37E-03 6.28E-03 1.23E-02 7.22E-02 9.32E-02 (d) (e) (f) (0 (M)

Percent Tech Req limit  % 4.74E-02 1.26E-01 2.46E-01 1.44E+f00 9.32E-01 Note: The quarterly doses listed above were calculated using dose factors from LADTAP and the average dilution flow (cfs) for each respective quarter. Annual doses are the sum of quarterly doses.

(a) Adult (b) Child (c) Teen (d) Child - Bone (e) Teen - Bone

( Child - Liver 16

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 V. SOLID WASTE A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of Waste:

Volume Total Est. Total (m3) Activity Error (%)

(Curies)

A. Spent Resins, filter sludges, 2.61 E+01 3.01 E-02 2.5E+01 evaporator bottoms, etc.

B. Dry compressible waste, 4.22E+02 3.99E+00 2.5E+01 contaminated equipment, etc C. Irradiated components, N/A N/A control rods, etc.

D. Other 1.16E+02 1.02E+00 2.5E+01

2. Estimate of major nuclide composition Category A and Category B waste Category A Category B Activity Percentage Activity Percentage Radionuclide (Ci)

(Ci) (%) (%)

H-3 1.68E-02 5.57E+01 1.30E-02 3.27E-01 C-1 4 1.80E-04 5.97E-01 5.76E-02 1.44E+00 Fe-55 3.33E-04 1.11 E+00 2.06E-01 5.17E+00 Co-60 3.06E-04 1.02E+00 3.05E-01 7.65E+00 Ni-63 3.30E-03 1.10E+01 2.23E+00 4.30E+01 Sr-90 3.62E-04 1.20E+00 4.64E-02 1.16E+00 Nb-94 1.23E-03 3.08E-02 Tc-99 0.OOE+00 0.OOE+00 9.19E-05 2.31 E-03 Sb-125 3.24E-03 8.12E-02 Cs-134 6.84E-05 2.27E-01 3.71 E-03 9.31 E-02 Cs-137 8.73E-03 2.90E+01 1.11 E+00 2.78E+01 Pu-238 1.54E-06 5.12E-03 3.37E-04 8.46E-03 Pu-239 1.15E-06 3.80E-03 3.30E-04 8.27E-03 Pu-241 6.OOE-05 1.99E-01 1.44E-02 3.60E-01 Pu-242 6.20E-09 2.06E-05 5.56E-07 1.39E-05 Am-241 3.97E-06 1.32E-02 7.34E-04 1.84E-02 Cm-242 4.44E-12 1.47E-08 4.36E-07 1.09E-05 Cm-244 1.23E-06 4.07E-03 1.56E-04 3.92E-03 17

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001

3. Estimate of major nuclide composition Category C and Category D waste Category C Category D Activity Percentage Activity Percentage Radionuclide (Ci) (Ci)

(%) (%)

H-3 1.62E-0 3 1.59E-01 C-14 1.75E-0 2 1.72E+00 Fe-55 6.75E-0 2 6.63E+00 Co-60 1.11 E-0 1 1.09E+01 Ni-63 8.09E-0 1 7.96E+01 Sr-90 3.63E-0 4 3.57E-02 Nb-94 5.15E-0 4 5.06E-02 Tc-99 3.86E-0 5 3.79E-03 Sb-125 1.21 E-0 3 1.19E-01 Cs-134 8.63E-0 6 8.48E-04 Cs-1 37 3.95E-0 3 3.88E-01 Pu-238 8.39E-0 5 8.25E-03 Pu-239 9.57E-0 5 9.41 E-03 Pu-241 3.77E-0 3 3.71 E-01 Pu-242 1.45E-0 9 1.42E-07 Am-241 1.61E-0 4 1.58E-02 Cm-242 5.81 E-0 8 5.72E-06 Cm-244 2.04E-0 5 2.00E-03

4. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 37 Highway Envirocare of Utah, Inc.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments None 18

RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2001 ATTACHMENT 1

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 1 OF 31 LEAD DEPARTMENT: EFFECTIVE DATE.

RP/ CHEMISTRY 4-9-01 REVISION

SUMMARY

1. Editorial change to Table 2 (page 23 of 31). Editorially changed the word "position" to "positive", in the first sentence under the text for footnote "a"

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 2 OF 31 TABLE OF CONTENTS SECTION TITLE PAGE 0.0 POLICY..... ..... ......... .............. .............--------------------------------------------

4 1.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM BASES ------------------ 4 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DESCRIPTION ------- 5 2.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PARAMETERS- 5 2.2 ANALYSIS OF EXPOSURE PATHWAYS ----------------------------------------------------------- 7 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING -------------------------------------------- 8 4.0 LAND USE CENSUS ------------------------------------------------------------------------------------ 10 5.0 FUEL CYCLE DOSE ------------------------------------------------------------------------------------- 11 6.0 INTERLABORATORY COMPARISON PROGRAM ---------------------------------------------- 12 7.0 DEFINITIONS --------------------------------------------------------------------------------------------- 13 8.0 RADIOLOGICAL REPORT REQUIREMENTS ---------------------------------------------------- 13 8.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR) ------ 13 8.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR) ---------------------- 14

9.0 REFERENCES

14 10.0 IDENTIFICATION CONVENTION FOR TABLE 6 SAMPLE LOCATIONS ----------------- 16 11.0 REPORTING RESULTS OF RADIOLOGICAL ENVIRONMENTAL DATA ----------------- 17 12.0 SELECTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS---17 13.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) MANUAL CHANGES ------------------------------------------------------------------------------------------------- 18

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 3 OF 31 LIST OF TABLES TABLE TITLE PAG E 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ------------------ 20 2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION, LLD ----------- 22 3 REPORTING LEVELS FOR REMP MEASUREMENTS ------------------------------- 25 4 TWO LETTER DESIGNATION TO IDENTIFY THE TYPE OF SAMPLE --------- 26 5 SECTOR LETTER DESIGNATIONS USED IN SAMPLE IDENTIFICATION ---- 27 6 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS -------------------- 28

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 4 OF 31 0.0 POLICY The Sacramento Municipal Utility District (SMUD) and the Rancho Seco Nuclear Station recognize their responsibility to comply with the Technical Specifications (10 CFR 50 and 10 CFR 72) and the applicable regulations, codes, standards and industry-wide criteria for establishing and maintaining a viable Radiological Environmental Monitoring Program. We are committed to operating the Rancho Seco Nuclear Station in such a manner that will assure proper radiation protection to all employees, contractors and the general public. To this end, we have committed to performing an environmental sampling program, which meets the intent of the applicable regulations while providing an accurate assessment of the radiological environment in and around the environs of the Rancho Seco site.

1.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM BASES The Sacramento Municipal Utility District and the Rancho Seco Nuclear Station have instituted a Radiological Environmental Monitoring Program (REMP) which this manual serves to implement. The REMP is based upon the information contained in Title 10 of the Code of Federal Regulations, Part 20, Section 1302 (10 CFR 20.1302). That Regulatory basis and associated guidelines have been the foundation of the REMP and its programmatic elements which:

1. Provide the technological basis of, and the instruction for, monitoring the site and environs for radioactivity of all sources, including:
a. naturally occurring background
b. releases during normal operations
c. operational occurrences and postulated accidents
d. weapons testing and major nuclear accidents, which contribute to detectable radioactivity in the environs.
1. Ensures the annual dose equivalent to any real individual located outside the Independent Spent Fuel Storage Installation (ISFSI) controlled area does not exceed the annual dose limits in 10 CFR 72.104(a).
3. Provide the means to verify the radiological effluent control program of the Rancho Seco Nuclear Station.
4. Meet minimum limits for detecting radioactive isotopes in samples collected from the environs or direct measurements in the field.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 5 OF 31

5. Provide measurements of radiation and radioactive materials in those exposure pathways, (i.e., liquid, gaseous, and direct radiation), and for those radionuclides, (i.e.,

cesium, and cobalt), which lead to the highest potential radiation exposure of individuals resulting from station operation.

This Manual contains the minimum requirements for the conduct of the Rancho Seco Radiological Environmental Monitoring Program (REMP). The requirements are consistent with USNRC regulations, the Branch Technical Position (BTP), Radiological Effluent Technical Specifications (RETS) for PWRs (NUREG-0472), the Rancho Seco Permanently Defueled Technical Specifications (PDTS), and the ISFSI Technical Specifications as Administrative Controls.

2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DESCRIPTION The Radiological Environmental Monitoring Program is under the cognizance of the Nuclear Plant Closure Manager, with the responsibility for the administration and oversight of the program assigned to the Radiation Protection/ Chemistry Superintendent (RP/ Chem Superintendent).

The design of the program is consistent with the intent of Title 10 Code of Federal Regulations, Part 20, "Standards for Protection Against Radiation" Section 1302. To implement these requirements, the Permanently Defueled Technical Specifications, ISFSI Technical Specifications, Off-site Dose Calculation Manual, Health Physics Implementing Procedures, and Surveillance Procedures have been developed. The implementing procedures address specific areas in the program that require direct attention for completion.

2.1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM PARAMETERS The monitoring and sampling aspects of the program are:

"* Identification of the effluent release pathways,

"* Identification of the human exposure pathways,

"* Identification of the land usage parameters by the population within a two mile radius of the site.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 6 OF 31 Three principal release pathways at Rancho Seco Nuclear Station are:

Gaseous Effluents:

Discharges from the Reactor Building Stack and the Auxiliary Building Stack.

Liquid Effluents:

Discharges which are released from the retention basins via the waste water disposal system [Regenerant Hold Up Tanks (RHUT) A and B].

Direct Radiation:

Radiation that emanates from the ISFSI, plant systems, or radioactive material contained within tanks or other containers, which are within the site boundary to humans outside of the site boundary.

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

Gaseous

"* Inhalation of airborne radioactive material by humans, or by animals that inhale and retain the material in animal products that are consumed by humans, i.e.,

meat or milk.

" Consumption of radioactive particulate material which, although carried by air currents, is deposited onto or is taken up by water sources or plants consumed by humans, or by animals that provide products that are consumed by humans, i.e., milk or meat.

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

" Exposure to the direct radiation from radioactive materials that have been deposited onto surfaces from airborne releases.

Drinking of water from the release pathway by humans, or by animals that are a food source for humans.

The consumption of fish or other animals that have eaten fish or shellfish taken from water within the liquid release pathway.

The consumption of products of animals that have eaten vegetation that has been irrigated with water from the release pathway.

The consumption by humans of fruit or vegetation grown in soil irrigated with water from the release pathway.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 7 OF 31 Direct Radiation

" The exposure to radiation emitted from radioactive materials within the Rancho Seco site boundary. Sources include, but are not limited to, the Borated Water Storage Tank, Demineralized Reactor Coolant Storage Tank, the Interim Onsite Storage Building (IOSB), and the Independent Spent Fuel Storage Installation (ISFSI).

" The exposure from being immersed in the release pathway water, to radiation emanating from material contained in the water.

2.2 ANALYSIS OF EXPOSURE PATHWAYS Exposure pathways are analyzed through a systematic process, which identifies a sample medium or organism that is found in the effluent pathways. Usage factors are determined that will suitably represent biological concentration, retention or uptake which may ultimately represent a contribution to human exposure. The pathways to human exposure are evaluated through the analysis of data obtained from the performance of a land use census. The performance of the land use census is required by the Permanently Defueled Technical Specifications Section D6.8.3b.2. The analysis of the effluent and exposure pathways enables the selection of sampling and monitoring locations that fall into one of two classes, those which are, and those which are not, influenced by effluent pathways. Those in the pathways are referred to as indicator locations. Several of the unaffected locations are selected to represent baseline or control locations.

Indicator locations provide data from the surrounding environment that may be influenced by the operation of the plant because they are nearby, downwind or downstream in the release pathway. Such data can be used to calculate doses to verify compliance with 40 CFR 190, using methodology contained in the ODCM. [This is referred to as the MEMBER OF THE PUBLIC. The MEMBER OF THE PUBLIC is defined as any individual except when that individual is receiving an occupational dose. A MEMBER OF THE PUBLIC who, based upon the land use census, is expected to receive the maximum off-site dose to real individuals, may be used to calculate doses to demonstrate compliance with 40 CFR 190.]

Control sample locations are to provide data that should not be influenced by the operations of Rancho Seco. These locations are selected based upon the distance from the plant, being upwind, or upstream of the release pathways. Data from these locations help discriminate between Rancho Seco releases and other natural or manmade events that may impact human exposure.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 8 OF 31 At Rancho Seco, potentially radioactive liquid effluent is discharged into Clay Creek. A continuous flow of Folsom South Canal water is released above the discharge point. The continuous minimum flow and the liquid effluent release are the major effluent release pathway, and thus the exposure pathway for the station during normal operations. Prior to the minimum release rate being established, Clay Creek was a seasonal stream, formed as the confluence of three and one half square miles of drainage runoff upstream of the site. The now continuous flow of Clay Creek intersects Hadselville Creek north and west of California State Highway 104.

Hadselville Creek intersects Laguna Creek just east of the Folsom South Canal. Laguna Creek flows into the Cosumnes River approximately 20 miles from Rancho Seco.

Hadselville and Laguna Creeks are also seasonal streams and also receive irrigation runoff during periods when irrigation is used. These streams are the major release pathways for liquid effluents from the site.

The gaseous pathway analysis is related to the land use census. This pathway is not confined by creek banks, but is subject to the meteorological conditions during the time of the release.

While not a significant release or exposure pathway, weekly air sampling is performed to determine the dose due to radioactive gaseous releases.

The direct radiation exposure pathway is measured with the use of monitoring devices, which monitor continuously and passively. The dose is integrated over three months to accumulate a statistically significant exposure. The vast majority of the dose integrated by these devices is delivered from primordial elements in the geological surface of the Earth, which contain naturally radioactive elements. A smaller fraction of the dose is delivered by cosmic radiation, which has penetrated the Earth's atmosphere.

3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING The REMP shall be conducted AT ALL TIMES as specified in Table 1 3.1 With the REMP not being conducted as specified in Table 1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report (AREOR) required by Section 8.1, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions or seasonal unavailability.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 9 OF 31 3.2 With the level of radioactivity in an environmental sampling medium exceeding the Reporting Level of Table 3 when averaged over any calendar quarter, in addition to complying with the requirements of Section 5.0, FUEL CYCLE DOSE, prepare and submit to the Commission within 30 days after the level of radioactivity has been determined, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the Reporting Levels to be exceeded. This report will define corrective actions to reduce emissions such that potential exposures will meet the 10 CFR 50, Appendix I dose guidelines. When more than one of the radionuclides in Table 3 are detected in the sampling medium, the Special Report shall be submitted if the Reporting Level fraction summation equals or exceeds unity (1.0).

When radionuclides other than those in Table 3 are detected and are the result of plant effluents, this Special Report shall be submitted if the potential annual dose to an individual is greater than or equal to the calendar year guidelines of 10 CFR 50, Appendix I. This Special Report is not required if the measured level of radioactivity was not the result of plant effluents; however, the condition shall be reported and described in the AREOR.

3.3 With fresh vegetation samples unavailable from any of the sample locations required by Table 1, identify the cause of the unavailability of samples and the locations for obtaining replacement samples in the next AREOR. The locations from which samples were unavailable may then be deleted from Table 6 provided the locations from which the replacement samples were obtained are added to Table 6 as replacement locations, if available.

3.4 The radiological environmental monitoring samples shall be collected per Table 1 from the locations shown in Table 6. These samples shall be analyzed to the requirements of Table 1 and Table 2.

3.5 The flow measuring devices on the environmental air monitors used for sampling the Table 1 AIRBORNE EXPOSURE PATHWAY shall be subject to a MONTHLY function check and shall be calibrated ONCE EVERY 12 MONTHS.

3.6 The REMP required by Section 1.0 provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the Station operation. This monitoring program thereby implementsSection IV.B.2 of Appendix I to 10 CFR 50 and supplements the REMP by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and Off-site Dose Calculation Manual (ODCM) modeling of the environmental exposure pathways.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 10 OF 31 Guidance for Section 3.0 was provided by References 9.12 and 9.29. REMP changes may be initiated based on operational experience and changes in the regional population or agricultural practices. The detection capabilities required by Table 2 are state of the art for routine environmental measurements in industrial laboratories. The LLDs for drinking water meet the requirements of 40 CFR 141.

4.0 LAND USE CENSUS A Land Use Census shall be conducted biennially and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden of greater than 500 square feet producing fresh leafy vegetation in each of the 16 meteorological sectors within a distance of two (2) miles. The location of the nearest milk animal is not required if the Offsite Dose Calculation Manual (ODCM) dose calculations are using conservative dose factors which assume the presence of milk animals within the vicinity of Rancho Seco Nuclear Station. Vegetation sampling may be performed at the Station Site Boundary in lieu of the garden census.

The Land Use Census shall also include information relevant to the liquid effluent pathway and gaseous effluent pathway such that the ODCM and the REMP Manual can be kept current with existing environmental and societal use of land surrounding Rancho Seco.

4.1 The Land Use Census shall be conducted biennially by using methods that will provide the best results, such as door-to-door survey, aerial survey, or by consulting local agriculture authorities The Land Use Census, or portions thereof, shall be conducted during the appropriate time of the year to provide the best results. The results of the Land Use Census shall be included in the AREOR covering the census year as required by Section 8.1.2.

4.2 With the Land Use Census identifying a location(s) which yields a calculated dose or dose commitment greater than the values currently being calculated in the ODCM for compliance with 10 CFR 50, Appendix I, identify the new location(s) in the next AREOR.

4.3 With the Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Section 3.0, Radiological Environmental Monitoring, add the new location(s) to Table 6 within 30 days or submit a Special Report to the Commission that identifies the cause(s) for exceeding these requirements and the proposed corrective actions for precluding recurrence.

The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s) [via the same exposure pathway] may be deleted from Table 6 after October 31 of the census year. Identify the new location(s) in the next AREOR including a revised figure(s) and table for the REMP Manual reflecting the new location(s).

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 11 OF 31 4.4 The Section 4.0 requirements are provided to ensure that changes in the use of unrestricted areas are identified and that modifications to the REMP and the ODCM are made if required by the results of the Land Use Census. These requirements also satisfy the requirements of Section IV.B.3 of Appendix I to 10 CFR 50.

Restricting the Land Use Census to gardens of greater than 500 square feet provides assurance that significant exposure pathway via leafy vegetation consumption will be identified and monitored. Gardens of this size are the minimum required to produce the quantity (26 kg/ year) of leafy vegetation assumed (reference 9.14) to be consumed by a child. In specifying this minimum garden size, it was further assumed that 20 percent of the garden was used for growing broad leaf vegetation (e.g./ lettuce or cabbage) and that the productivity was two- (2) kg/ m2 In addition, by gathering information on the liquid effluent pathway and the gaseous effluent pathway, the Land Use Census provides assurance that proper radiological environmental monitoring and radioactive effluent controls are in place for the adequate protection of the health and safety of the general public.

5.0 FUEL CYCLE DOSE The dose or dose commitment to any real MEMBER OF THE PUBLIC due to releases of radioactive material in gaseous and liquid effluents and to direct radiation from uranium fuel cycle sources shall AT ALL TIMES be limited to less than or equal to 25 mrem (total body or any organ), and 75 mrem (thyroid), in a calendar year.

5.1 With any of the Reporting Levels of Table 3 being exceeded, calculations shall be made to determine whether the Section 5.0 fuel cycle dose/dose commitment limits have been exceeded. Contributions from direct radiation sources (including outside storage tanks, etc.) shall be included in this calculation.

5.2 If the Section 5.0 limits have been exceeded, prepare and submit to the Commission within 30 days a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the Section 5.0 limits. This Special Report shall also include a schedule for achieving conformance with the Section 5.0 limits.

This Special Report, as defined in 10 CFR 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, in a calendar year that includes the release(s) covered by this Special Report. This Special Report shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 12 OF 31 5.3 If the estimated dose(s) exceeds Section 5.0 limits, and if the release condition resulting in the violation of 40 CFR 190 has not already been corrected, the Special Report shall also include a request for a variance in accordance with the provision of 40 CFR 190.

Submittal of the Special Report is considered a timely request, and a variance is granted until USNRC staff action on the request is complete.

5.4 The Section 5.0 requirements are provided, in part, to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20. For the Rancho Seco site, it is unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the Station remains within twice the numerical guides for design objectives of 10 CFR 50, Appendix I and if direct radiation is kept small.

The Special Report will describe a course of action, which should result in the limitation of the dose to a MEMBER OF THE PUBLIC for a calendar year to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of five (5) miles must be considered.

If the dose to any MEMBER OF THE PUBLIC is evaluated to exceed the requirements of 40 CFR 190, the Special Report along with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected) is considered to be a timely request and fulfills the requirements of 40 CFR 190 until USNRC staff action is completed.

An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she receives an occupational dose.

6.0 INTERLABORATORY COMPARISON PROGRAM The laboratory performing analyses of Table 6 samples pursuant to the requirements of Table 1 shall AT ALL TIMES participate in an Interlaboratory Comparison Program (ICP) approved by the Commission. The ICP approved by the Commission may not always supply tests for the analyses required by Table 6.

Since no Commission approved ICP exists for Monitoring Devices; the laboratory performing analyses of the REMP environmental monitoring devices shall AT ALL TIMES participate in a licensee approved comparison program.

6.1 With ICP analyses not being performed as required in Section 6.0, report the corrective actions taken to prevent a recurrence to the Commission in the AREOR as required by Section 8.1.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 13 OF 31 6.2 A summary of the results obtained, as a participant in the lCP shall be included in the AREOR as required by Section 8.1.

6.3 The requirement to participate in an ICP is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR 50.

7.0 DEFINITIONS 7.1 FORTNIGHTLY - Once per fourteen (14) days 7.2 INDUSTRIAL AREA - That portion of the Station property, access to which is controlled as described in the NRC approved Security Plan by security fencing, equipment and personnel.

7.3 SITE BOUNDARY - That line beyond which the land is neither owned, nor leased, nor otherwise controlled by the licensee.

7.4 RESTRICTED AREA - An area, access to which is limited by the licensee for the purpose of protecting individuals against undue risks from exposure to radiation and radioactive materials. Restricted area does not include areas used as residential quarters, but separate rooms in a residential building may be set apart as a restricted area.

7.5 CONTROLLED AREA - An area, outside of a restricted area but inside the site boundary, access to which can be limited by the licensee for any reason.

7.6 UNRESTRICTED AREA - An area, access to which is neither limited nor controlled by the licensee.

7.7 MEMBER(S) OF THE PUBLIC - Any individual except when that individual is receiving an occupational dose.

8.0 RADIOLOGICAL REPORT REQUIREMENTS 8.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (AREOR) 8.1.1 An AREOR covering the operation of the Station during the previous calendar year shall be submitted to the USNRC prior to May 1 of each year in accordance with Permanently Defueled Technical Specification D6.9.2.3.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 14 OF31 8.1.2 The AREOR shall include summaries and statistical evaluations of the results of the radiological environmental surveillance activities for the report period, including (as appropriate) a comparison with operational controls. The AREOR shall also include the results of the Land Use Census required by Section 4.0, LAND USE CENSUS. In the event a radionuclide concentration should be confirmed in excess of the Reporting Level in Table 3 by environmental measurements, the AREOR shall describe a planned course of corrective action.

8.1.3 The AREOR shall include summarized and tabulated results of all radiological environmental samples taken during the AREOR period. In the event that some results are not available for inclusion, the AREOR shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

8.1.4 The AREOR shall include a summary description of the REMP (including a map of all sampling locations keyed to a table giving distances and directions from the Reactor Building) and the results of participation in the Interlaboratory Comparison Program required by Section 6.0. The AREOR shall also include information related to Section 5.0, Fuel Cycle Dose.

8.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (ARERR)

Any changes made to the REMP MANUAL during the ARERR reporting period shall be included in that ARERR. The complete REMP manual, in its revised form, shall be submitted with the ARERR.

9.0 REFERENCES

The following documents pertain to the design and conduct of radiological environmental monitoring programs:

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

9.2 American Nuclear Insurers and Mutual Atomic Energy Liability Underwriters (ANI/MAELU), Environmental Monitoring Programs, Information Bulletin 86-1 (1986).

9.3 ANI/MAELU, Engineering Inspection Criteria for Radiological Environmental Monitoring, Section 5.2, Revision 2.

9.4 ANI/MAELU, Nuclear Liability Insurance Records Retention, Information Bulletin 80-1 A, Rev. 2 (1986).

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 15 OF 31 9.5 Committee on the Biological Effects of Ionizing Radiations (BEIR), The Effects on Populations of Exposure to Low Levels of Ionizing Radiation: BEIR V Report (1990).

9.6 National Council on Radiation Protection (NCRP), A Handbook of Radioactivity Measurements Procedures, NCRP Report No. 58, Second Edition (1985).

9.7 NCRP, Radiological Assessment: Predicting the Transport, Bioaccumulation and Uptake by Man of Radionuclides Released to the Environment, NCRP Report No. 76 (1984).

9.8 USEPA, Environmental Standards for the Uranium Fuel Cycle, 40 CFR 190, Subpart B (1993).

9.9 USEPA, Upgrading Environmental Radiation Data, Health Physics Society Committee Report HPSR-1, EPA 520/1-80-012 (1980).

9.10 USNRC, Criterion 64 - Monitoring Radioactive Releases, 10 CFR 50, Appendix A (1993).

9.11 USNRC, Numerical Guides for Design Obiectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Is Reasonably Achievable' for Radioactive Material In Light Water Cooled Nuclear Power Reactor Effluents, 10 CFR 50, Appendix I (1993).

9.12 USNRC, An Acceptable Radiological Environmental Monitoring Program, Branch Technical Position, Rev. 1 (November 1979).

9.13 USNRC, Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Off-site Dose Calculation Manual or the Process Control Program, Generic Letter 89-01 (January 31, 1989).

9.14 USNRC, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluatinq Compliance with 10 CFR 50, Appendix I, Regulatory Guide 1.109 (1977).

9.15 USNRC, Estimating Aguatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, Regulatory Guide 1.113 (1977).

9.16 USNRC, Measuring and Reporting of Radioactivity in the Environs of Nuclear Power Plants, Regulatory Guide 4.1 (1973).

9.17 USNRC, Preparation of Environmental Reports for Nuclear Power Stations, Regulatory Guide 4.2, Rev. 2 (1976).

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 16 OF 31 9.18 USNRC, Performance. Testing and Procedural Soecifications for Thermoluminesence Dosimetry: Environmental Aoplications," Regulatory Guide 4.13.

9.19 USNRC, Quality Assurance for Radiological Monitoring Programs (Normal Operations)

Effluent Streams and the Environment, Regulatory Guide 4.15, Rev. 1 (1979).

9.20 USNRC, Radiological Assessment: A Textbook on Environmental Dose NUREG/CR 3332 (1983).

9.21 USNRC, Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements, NUREG/CR-4007 (1984).

9.22 USNRC, Radiological Effluent Technical Specifications for PWRs, NUREG-0472, Rev. 2 (July 1979).

9.23 USNRC, Radiological Monitoring by NRC Licensees for Routine Operations of Nuclear Facilities, NUREG-0475 (1978).

9.24 USNRC, Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40 CFR 190), NUREG-0543 (1980).

9.25 USNRC, Dose Limits for individual members of the public, 10 CFR 20.1301 (1993).

9.26 USNRC, Reports of exposures, radiation levels, and concentrations of radioactive material exceeding the limits, 10 CFR 20.2203 (1993).

9.27 Merril Eisenbud, Environmental Radioactivity From Natural, Industrial. and Military Sources, Third Edition (1987).

9.28 Rancho Seco Permanently Defueled Technical Specifications.

9.29 USNRC, Technology, Safety and Costs of Decommissioning a Reference Pressurized Water Reactor Power Station, NUREG/CR-0130 (June 1978) 9.30 USNRC, Air Sampling in the Workplace, Regulatory Guide 8.25, Rev. 1 (June 1992) 9.31 Rancho Seco Independent Spent Fuel Storage Installation Technical Specifications.

10.0 IDENTIFICATION CONVENTION FOR TABLE 6 SAMPLE LOCATIONS Sampling and monitoring sites designated in Table 6 are identified using the following convention:

10.1 To establish the fact that the Table 6 samples originate from the Rancho Seco REMP, the letter "R" precedes every sample site designator.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 17 OF 31 10.2 The next two (2) letters are selected to identify SAMPLE TYPE. Refer to Table 4 for a listing of the SAMPLE TYPES and the associated two-letter abbreviation.

10.3 The numbers following the SAMPLE TYPE abbreviation reflect the straight-line distance (miles) to the sample site, referenced to the center of the Reactor Building.

10.4 Following the distance, a SECTOR DESIGNATOR letter is included to specify which of the 16 meteorological sectors the sample site is encompassed. Refer to Table 5 for a listing of the sector designators.

10.5 The final character in the sample site designation is the letter "0"or the letter "P". The letter "0"designates the sample as one being added to the REMP following Station initial criticality. The letter "P" designates the sample as one being added during the post operational period following the issuance of the Possession Only License.

10.6 The present identification convention has been selected in preference to the system originally used to identify samples and sites. Since it is desirable to retain the ability to identify, and continue to use data from, previously collected samples, the former identification convention is also shown parenthetically in Table 6.

11.0 REPORTING RESULTS OF RADIOLOGICAL ENVIRONMENTAL DATA The requirements for reporting radiological environmental data are specified in Section 8.0 of this manual. Those subsections which require supporting data from the Radiological Environmental Monitoring Program address the Annual Radiological Environmental Operating Report and the Annual Radioactive Effluent Release Report.

Special Reports are made specific in HPIP-2050, Radiological Environmental Monitoring Program Reports. Specified therein are conditions requiring special reports, and reporting requirements in days for submittal. This includes those calculations to provide rapid assurance of the degree of compliance with 10 CFR 50 Appendix I, and 40 CFR 190 calculations after releases of any origin.

12.0 SELECTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS In conjunction with the data base established from the land use census, the requirements of the Permanently Defueled Technical Specifications, and the guidance described in Section 2.0 of this Manual, the selection of sampling and monitoring sites is performed. These selected locations provide at least the minimum number of locations specified in Table 1.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 18 OF 31 Data was gathered from the land use census, Lawrence Livermore National Laboratory Rancho Seco Study Reports, Oak Ridge National Laboratory Study Reports, and from additional sampling sites from which materials have been collected. The information gathered was used to determine indicator sites. Presently, a number of control sites have been selected and are not anticipated to be increased in number.

The second column of Table 6 identifies the Sample Class of a particular sample as either an Indicator (IND) or a Control (CON) Sample. Additional sample locations designated as Special (Spec) are used to perform initial radiological evaluations.

Environmental monitoring devices are placed in the environs around the site. These devices passively monitor radiation in the immediate environs. Data from monitoring devices is trended to establish variations, which are influenced by seasonal, meteorological, local and global sources. The monitoring devices will also respond to radiation in the effluents of the plant if they pass in near proximity. The data is included in each quarterly environmental report.

Sample locations for the collection of the flora and fauna are concentrated in the liquid effluent pathway to the West. Representative samples of all the pathways and suitable locations are established in all directions. Air samplers are distributed to achieve a sampling of air from major wind directions across the site.

The Radiological Environmental Monitoring Program maintains at least those minimum sampling locations and type of samples to meet the requirements listed in Table 1.

A site has been established for a vegetable garden. The garden is at the site boundary alongside Clay Creek, and irrigated with water from the effluent stream. This data is considered essential for comparisons to vegetation not irrigated with effluent stream water for determination of bioaccumulation for soil types common to the environs.

All of the environmental sample locations required for the Radiological Environmental Monitoring Program are designated in Table 6. Additional sampling locations are listed in HPIP-2070, REMP Routes and Sample Locations.

13.0 Radiological Environmental Monitoring Program (REMP) Manual Changes As required by the Permanently Defueled Technical Specifications (PDTS) section D6.14.3, changes to the REMP manual shall be documented and the records of the reviews performed for the changes shall be retained as required by the PDTS section D6.10.2.o. The documentation shall contain sufficient information to support the change together with the appropriate analyses or evaluations justifying the change.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 19 OF31 The documentation shall also contain a determination that the change will maintain the level of radioactive effluent control that is required by 10 CFR 20.1302, 40CFR190, 10 CFR 50.36a, and Appendix I to 10CFR50 and not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.

Changes to the REMP manual shall become effective after review and acceptance by the PRC and approval by the Plant Manager.

Changes to the REMP manual shall be submitted to the Nuclear Regulatory Commission in the form of a complete, legible copy of the entire REMP Manual as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the REMP Manual was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changes, and shall indicate the date (e.g., month/ year) the change was implemented.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 20 OF 31 Table 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Sampling and Type and Frequency of Analysis and/ or Sample Samples* Collection Frequency

1. AIRBORNE 3 Continuous operation Particulate sampler. Analyze for Gross Beta of sampler with sample radioactivity at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change.

collection as required Perform gamma isotopic analysis on each sample where by dust loading but at gross beta activity is greater than 10 times the yearly least once per week mean of control samples for the same sample period.

Perform gamma isotopic analysis on composite (by location) sample at least once per quarter.

2. DIRECT At least 25 locations At least once per Gamma dose. At least once per quarter RADIATION with 2 monitoring quarter devices at each location
3. WATERBORNE
a. Surface 2 Composite sample Gamma isotopic and tritium analysis of each composite collected monthly 3 Grab sample collected Gamma isotopic and tritium analysis of each sample monthly
b. Runoff 1 Grab sample collected Gamma isotopic and tritium analysis of each sample fortnightly I Sample locations are shown in Table 6

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 21 OF 31 Table 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Number of Sampling and Type and Frequency of Analysis and/ or Sample Samples* Collection Frequency

3. WATERBORNE 2 Grab sample collected Gross Beta, Gamma isotopic, and Tritium analysis of
c. Ground quarterly each sample
d. Drinking 2 Grab sample collected Gross Beta, Gamma isotopic, and Tritium analysis of monthly each sample.
e. Mud and 2 At least quarterly. Gamma isotopic analysis of each sample.

Silt Sample collected of the top 3" of material 2 ft. from shoreline.

4. INGESTION
a. Fish 1 At least semiannually. Gamma isotopic analysis of the edible portion of each At least one sample of sample.

either of the species listed in Table 6

b. Food 1 At least semiannually. Gamma isotopic analysis of the edible portion of each One sample of sample.

vegetable(s) as shown I _ _ in Table 6 1 Sample locations are shown in Table 6

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 22 OF 31 Table 2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION, LLD a,c Airborne Analysis Water Particulate or Fish Food Products Mud and Silt (pCi/ I) Gases (pCi/m 3) (pCi/ kg-wet) (pCi/ kg-wet) kg-wet)_

_(p~k Gross Beta 4b 0.01 H-3 2000 (1000b)

Mn-54 15 130 Co-60 15 130 150(e)

Zn-65 30 260 Cs-134 15 ( 1 0 b) 0.01 130 60 150 Cs-137 18(10 0.01 130 60 150

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 23 OF 31 Table 2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION, LLD a,c The Low Limit of Detection (LLD) values for the radionuclides presented in Table 2 are those recommended in Reference 9.12 (BTP) and Reference 9.22 (RETS).

The LLD of a radioanalysis system is that value which will indicate the presence or absence of radioactivity in a sample when the probability of a false positive and of a false negative determination is stated. The probabilities of the false positive and false negative determinations are taken as equal to 0.05. The equation for estimating the maximum LLD is given by the following equation:

LLD = 2.71/t., + 3.29Sb1 3.7E - 2(YEV) exp(-2t:)' pCi/I, pCi/kg-wet, or pCi/M 3 where:

2.71 = factor to account for Poisson statistics at very low background count rate 3.29 = twice the constant used to establish the one-sided 0.95 confidence interval Sb = standard deviation of the background count rate

[B / (tbts) + B / tb2] 0.5 B = background counts tb = background count interval, sec ts = sample count interval, sec 3.7E-2 = conversion factor, dis/ sec/ pCi Y = radiochemical process yield (product of all factors such as abundance, chemical yield, etc.)

E = counting efficiency, cts/ dis V = sample volume or mass, I or kg

= radioactive decay constant for the associate nuclide

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 24 OF 31 Table 2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION, LLD a~d tc = elapsed time from the midpoint of sample collection to the midpoint of counting, sec The LLD is defined as an a 2riori (before the fact) estimate and is not to be calculated for each sample analyzed on an a posteriori(after the fact) basis.

Occasionally, unavoidably small sample sizes or other uncontrollable circumstances may result in a priori LLD values not being met. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

b LLD for Drinking Water samples from Reference 9.22 (RETS).

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

d Composite analysis LLD from Reference 9.22 (RETS) is shown; individual sample LLD 3

is 0.05 pCi/m . This LLD (0.05 pCi/m 3) is a site specific value.

LLD for Mud and Silt Co-60 is not required by Reference 9.22 (RETS). This value is consistent with the RETS required LLD for Cs-1 34 and Cs-1 37.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 25 OF 31 Table 3 REPORTING LEVELS FOR REMP MEASUREMENTS Analysis Water Airborne Particulate or Fish Food Products (pCi/I) Gases (pCi/ 3) (pCi/ kg-wet) (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-1 37 50 20 2000 2000 Gross Beta 4 0 b 2c a Applies to water samples utilized for human consumption only. This value is as specified in 40 CFR 141.

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 [Reference 9.12 (BTP)]. Gamma isotopic analysis on each water sample is required by Table 1 and therefore this reporting requirement does not apply.

c Gross Beta activity in air of ten (10) 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.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 26 OF 31 Table 4 TWO LETTER DESIGNATION TO IDENTIFY THE TYPE OF SAMPLE a Letter Desiqnation Type of Sample Reoresented AG Algae Sample AS Air Sample FS Fish Sample LV Garden Vegetation MS Mud & Silt (Sediment)

RW Runoff Water SW Surface Waterb TL Direct Radiation (Monitoring Badge)

WW Ground (Well) Water DW Drinking Water SL Soil a

Additional letter designation may be added as sample designators if additional sample types are collected for analysis.

b The portion of precipitation on the land that ultimately reaches streams is considered to be surface water.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 27 OF 31 Table 5 SECTOR LETTER DESIGNATIONS USED IN SAMPLE IDENTIFICATION True North Compass Sector Sector Degrees Sector A 348.75 to 11.25 N B 11.25 to 33.75 NNE C 33.75 to 56.25 NE D 56.25 to 78.75 ENE E 78.75 to 101.25 E F 101.25 to 123.75 ESE G 123.75 to 146.25 SE 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 a 303.75 to 326.25 NW R 326.25 to 348.75 NNW

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 28 OF 31 Table 6 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Sample ldentificatio n Sample Collection Location Identification (Former ID) Class Frequency AIR (Particulate. s)

RASO. 1CO IND Weekly On Site (PAP Build ling Carport)

(RAHO)

RASO.3M0 IND Weekly On Site (Effluent Discharge)

RASO.7EO IND Weekly Meteorological Toyver RUNOFF WATE ER RRWO.6MO IND Biweekly Site Boundary SURFACE WATFER RSWO.7N0 IND Monthly Water Sump RSW1.3F0 IND Monthly Rancho Seco Reservoir (RSWCO)

RSW3.7N0 CON Monthly Folsom South Canal (Composite Sample)

(RSWBO)

RSW1.8N0 IND Monthly Confluence of Clay and Hadselville Creeks RSWO.3M0 IND Monthly Effluent Discharge (Composite Sample)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 29 OF 31 Table 6 (continued)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Sample Identification Sample Collection Location Identification (Former ID) Class Frequency GROUND (Well)

WATER RWWO.3EO IND Quarterly Site Well (RWWAO)

RWW0.8DO CON Quarterly Marciel Ranch DRINKING WATER RWDO.1 GO IND Monthly Industrial Area Drinking Water Source RDW1.8FP CON Monthly Rancho Seco Lake Drinking Water Source MUD AND SILT (Sediment)

RMSO.3MO IND Quarterly Effluent Discharge RMSO.6MO IND Quarterly Site Boundary (RMSEO)

FISH

  • RFSO.6MO IND Semiannually Clay Creek near the Site Boundary NOTE: Include predator (e.g., bass, sunfish) or scavenger (e.g., catfish, sucker) species, as available.
  • Other downstream locations may be substituted to meet sampling requirements.

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 30 OF 31 Table 6 (Continued)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Sample Identification Sample Collection Location Identification (Former ID) Class Frequency GARDEN VEGETABLES RLVO.6MO IND Semiannually Site Boundary Vegetable Irrigation Garden (vegetable samples, depending on availability)

RLVXX.XX CON Semiannually Truck Farm, outside 5 mile radius. (locally (RLVFO) grown vegetable samples, depending on availability)

MONITORING DEVICE RTL0.3RO IND Quarterly #1 Rancho Seco Site RTLO.3CO IND Quarterly #2 Rancho Seco Parking Lot RTLO.3NO IND Quarterly #3 Rancho Seco Site RTL0.3LO IND Quarterly #4 Rancho Seco Site RTL0.3HO IND Quarterly #5 Rancho Seco Site RTLO.4FO IND Quarterly #6 SMUD Photovoltaic Facility RTLO.5CO IND Quarterly #7 Rancho Seco Entrance RTLO.6KO IND Quarterly #11 Tokay Substation/ Clay East Rd.

RTL2.7MO IND Quarterly #16 Tipling Residence RTL8.2KO CON Quarterly #17 Elliot Cemetery RTL7.8CO CON Quarterly #18 Sam Jaber Residence

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 13 PAGE 31 OF 31 Table 6 (Continued)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Sample Identification Sample Collection Location Identification (Former ID) Class Frequency MONITORING DEVICE RTL1.8F0 IND Quarterly #19 Rancho Seco Lake RTL1.5MO IND Quarterly #20 Clay East Road & Kirkwood RTL3.9KO IND Quarterly #26 Borden Road RTL7.4MO CON Quarterly #30 Herald Fire Department RTL3.7NO IND Quarterly #31 Hobay Road RTL3.8MO IND Quarterly #33 Folsom South Canal Pumping Station RTL1.9NO IND Quarterly #35 Hadselville Creek and Plant Effluent Water RTL1.7F0 IND Quarterly #43 Rancho Seco Reservoir RTL1.4DO IND Quarterly #46 Twin Cities Road (Highway 104)

RTL8.OPO CON Quarterly #55 Colony Road RTLO.8DO IND Quarterly #63 Marciel Ranch RTLO.6MO IND Quarterly #65 Site Boundary Irrigated Garden RTLO.3PO IND Quarterly #68 West Fence, adjacent to ISFSl RTL0.3NP IND Quarterly #88 ISFSI outer Security fence, near inactive West Garden RTLO.4NP IND Quarterly #89 ISFSI outer Security fence, SW corner RTLO.5NP IND Quarterly #90 ISFSI outer Security fence, NW corner RTL0.3QP IND Quarterly #91 ISFSI outer Security fence, NE corner

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