ML080950399
| ML080950399 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/31/2008 |
| From: | Redeker S Sacramento Municipal Utility District (SMUD) |
| To: | John Hickman Document Control Desk, NRC/FSME |
| References | |
| MPC&D 08-023 | |
| Download: ML080950399 (156) | |
Text
SACRAMENTO MUNICIPAL UTILITY DISTRICT The Power To Do More.
PO. Box 15830, Sacramento, CA 95852-1830; 1-888-742-SMUD (7683)
MPC&D 08-023 March 31, 2008 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR 2007 Attention: John Hickman In accordance with 10 CFR 50.36(a)(2) and Rancho Seco Quality Manual Appendix A, Section 1.5.3, we are submitting the Rancho Seco 2007 Annual Radioactive Effluent Release Report (ARERR) for the period of January 1 through December 31, 2007. We are also submitting the latest versions of the Offsite Dose Calculation Manual (CAP-0002, Revisions 19 and 20) and the Radiological Environmental Monitoring Program Manual, Revision 14.
If you, or members of your staff, have questions requiring additional information or clarification, please contact Bob Jones at (916) 732-4843.
Si ere ly,
Steve Redeker Manager, Plant Closure & Decommissioning Cc: NRC, Region IV RANCHO SECO NUCLEAR PLANT e 14440 Twin Cities Road, Herald, CA 95638-9799; (209) 333-2935
RANCHO SECO NUCLEAR GENERATING STATION LICENSE NUMBERS DPR-54 and SNM-2510 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 TABLE OF CONTENTS IN T R O D U C T IO N.........................................
1 I.
SUPPLEMENTAL INFORMATION..............................................
2 A. Regulatory Limits & Guidelines for Effluent Releases...................................................................
2 B. Maximum Effluent Concentrations.............
3 C. Measurement Methods for Total Radioactivity-.....................................
3 D. Batch Releases (via monitored pathways)...........
4 E.
U n p la n n e d R e le a s e s...........................................................................................................................
5 F. Radioactive Effluent Monitoring InstrLmentation I'hoperable for Greater Than 30 Days.................
5 I1. E S T IM A T IO N O F E R R O R.......................................................................................................................
6 III. G A S E O U S E F F L U E N T S.........................................................................................................................
7 Table Ill-A Gaseous Effluents - Summation of All Releases............................
8 Table III-B Gaseous Effluents - Ground Level Releases....................................
9 Table Ill-C Gaseous Effluents - Typical Lower Limits of Detection...............................................
10 Table III-D Radiological Impact on Man Due to Gaseous Effluent Releases.................
11 IV. L IQ U ID E F F L U E N T S...................................................................................................
....................... 12 Table IV-A Liquid Effluents - Summation of All Releases..............................
13 T a b le IV -B L iq u id E ff lu e nts..................................................................................................................
14 Table IV-C Liquid Effluents - Typical Lower Limits of Detection..............................
15 Table IV-D Radiological Impact on Man Due to Liquid Effluent Releases......................................
16 V.
S O L ID W A S T E...........................................
17 ATTACHMENTS
- 1. Off-Site Dose Calculation Manual, Revision 19
- 2.
Off-Site Dose Calculation Manual, Revision 20
- 3.
Radiological Environmental Monitoring Program Manual, Revision 14
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 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, Sacramento Municipal Utility District (the District) shutdown the Rancho Seco Nuclear Generating Station and completed defueling operations on December 8, 1989. Transfer of the spent fuel rod assemblies from the Spent Fuel Pool into dry storage at the Interim Spent Fuel Storage Installation (ISFSI) was completed on August 21, 2002. The Retention Basins, which were used to collect, mix, and analyze radioactive liquid waste prior to release to combined effluent, were removed in August 2007. The volume of liquid radioactive waste discharged has been significantly reduced as the radiological dismantlement process nears completion.
This Annual Radioactive Effluent Release Report (ARERR) provides a summary of gaseous and liquid effluent releases made from Rancho Seco during the period of January 1 through December 31, 2007.
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 District to meet the requirements of Rancho Seco Quality Manual (RSQM), Appendix A, Section 1.5.3 and Offsite Dose Calculation Manual (ODCM) Revision 19, Step 6.12.
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.
1
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007
- 1. SUPPLEMENTAL INFORMATION A.
REGULATORY LIMITS & GUIDELINES FOR EFFLUENT RELEASES
- 1. Gaseous Effluents
- a.
Dose rate limit at or beyond the Site Boundary for Gaseous Effluents for Tritium and radioactive material in particulate form with half-lives greater than 8 days (ODCM, Technical Requirement 6.11.5):
1500 mrem/year to any organ
- b.
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 6.11.6, 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 6.11.1).
- 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 6.11.2, numerical guidelines of 10 CFR 50, Appendix I):
1.5 mrem per calendar quarter tothe 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 NOTE: The noble gas source term was removed when spent fuel transfer to the ISFSI was completed in August 2002. Reference to noble gases was completely removed from the ODCM.
2
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 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 C FR 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. Gaseous Effluents Liquid Scintillation (H-3)
Gamma Spectroscopy (HPGe)
Beta Proportional (Sr-90, gross beta)
Alpha Proportional (gross alpha)
- 2.
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 2007 D. BATCH RELEASES (via monitored pathways)
- 1. Liquid (Retention Basin Discharges)
Quarter 1 Quarter 2 Quarter 3 Quarter 4
- a. Number of batch releases 0
3 0
0
- b. Total time period for batch releases (hours)
N/A 41.40 N/A N/A
- c. Maximum time period for a batch release (hours)
N/A 28.33 N/A N/A
- d. Average time period for a batch release (hours)
N/A 13.80 N/A N/A
- e. Minimum time period for a batch release (hours)
N/A 6.00 N/A N/A 4
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 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 R15017A, Retention Basin Effluent Discharge Monitor, was permanently taken out of service and dismantled when the Retention Basins were removed in the summer of 2007.
5
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 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:
2+ 2 2K+
Total Error = I5"
+
("2 (3
K +
i where: ci = 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 retention basin 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.
6
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 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 tritium and particulates with half-lives greater than 8 days. The methodology used to calculate the Percent of ODCM Technical Requirement limit is as follows:.
-[(Fi)(Avg Rel Rate)(X / Q)(Dose Factor)]
% Tech Req Limit =
(Dose x 100%
(oeRate Limit) 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 +06Ci/Ci Avg Rel Rate =
Ci
(# 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.lMi, 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 Ill-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 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 p Ci/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 2007 Annual REMP Report). The maximum calculated organ dose is 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.
7
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 TABLE Ill-A GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Est. Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Error, %
G. Particulates
- 1. Particulates with half-tives>8 days Ci 0.00 E+00
.0.00 E+00 0.00 E+00 2.17 E-06 2.3 E+01
- 2. Average Release Rate for period pCi/sec 0.00 E+00 0.00 E+00 0.00 E+00 2.73 E-07
- 3.
Percent of Tech Req limit N/A N/A N/A 1.65 E-06 Ci 5.97 E-07a 1.57 E-08 9.58 E-08 1.32 E-07
- 4. Gross Alpha radioactivity H.ý Tritium
- 1. Total Release Ci 4.52 E-03 2.81 E-02 6.06 E-02 1.47 E-01 2.3 E+01
- 2.
Average Release Rate for period pCi/sec 5.75 E-04 3.53 E-03 7.71 E-03.
1.85 E-02 4.87 E-06 2.99 E-05 6.53 E-05 1.57 E-04
- 3.
Percent of Tech Req limit a The gross alpha activity for the 1st quarter was from local air samples and not from the Reactor Building stack. The Reactor Building exhaust fan was intermittently out of service during the 1st quarter in 2007. During this condition, alternate local samples were obtained from the building hatches when dismantling activities were being performed.
8
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 TABLE IlI-B GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Nuclides Released
- 1. Particulates(a)
Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Cs-1 37 Ci 0.00 E+00 0.00 E+00 0.00 E+00 2.17 E-06
- 2. Tritium H-3 Ci 4.52 E-03 2.81 E-02 6.06 E-02 1.47 E-01 (a) Trace amounts of Np-237 and Pu-239/240 were identified present in a particulate sample by Alpha Spectroscopy measurement. Their concentrations were slightly above MDA or at MDA values and did not have significant contribution to dose from gaseous releases.
9
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 TABLE II-C GASEOUS EFFLUENTS - TYPICAL LOWER LIMITS OF DETECTION RADIONUCLIDES LLD (wCi/cc)
- 1.
- 2.
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 2007 TABLE III-D RADIOLOGICAL IMPACT ON MAN DUE TO GASEOUS EFFLUENT RELEASES CALCULATED RADIATION DOSES AT THE SITE BOUNDARY FOR GASEOUS EFFLUENTS:
Unit Quarter 1 Quarter 2 2007 Annual Quarter 3 Quarter 4 A. Tritium, Particulate
- 1. Maximum Organ Dose Percent Tech Req limit B. Direct Radiation
- 1. Dose (Monitoring Badges)
- 2.
Percent of Tech Req limit mrem 1.47 E-04 (a) 1.96 E-03 9.12 E-04 1.97 E-03 (a) 1.22 E-02 2.63 E-'02 1.70 E-02 (b) 2.27 E-01 0.00 E+00*
N/A 1.94 E-02 (b) 1.29 E-01 0.00 E+00*
N/A mrem 0.00 E+00*
N/A 0.00 E+00*
N/A 0.00 E+00*
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 (b) Infant - Liver None of the Indicator stations indicate significant radiation attributable to Plant operations.
11
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 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 E
LMECJ 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)
MECj =
The MEC of the ith radionuc!ide, 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 2007 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.
12
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 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)
- 2.
Average diluted concentration during period
- 3.
Percent of Tech Req limit B. Tritium
- 1. Total Release
- 2. Average diluted concentration during period
- 3.
Percent of Tech Req limit C. Dissolved and Entrained Gases (i.e., Noble Gases)
- 1. Total Release
- 2. Average diluted concentration during period Ci pCi/mI Ci pCi/ml Ci pCi/mI 0.00 E+00 0.00 E+00 N/A 0.00 E+00 0.00 E+00 N/A 0.00 E+00 0.00 E+00 7.07 E-05 1.49 E-11 2.28 E-03 7.07 E-04 1.49 E-10 1.49 E-05 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 N/A 0.00 E+00 0.00 E+00 N/A 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 N/A 0.00 E+00 0.00 E+00 N/A 0.00 E+00 0.00 E+00 2.3 E+01 2.3 E+01 N/A D. Gross Alpha radioactivity
- 1. Total Release E. Volume of Waste Released Retention Basins (prior to dilution)
F. Volume of dilution water used during period Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 2.3 E+01 Liters 0.00 E+00 2.78 E+06 0.00 E+00 0.00 E+00 5.0 E+00 Liters 5.08 E+09 3.48 E+09 4.11 E+09. 3.33 E+09 2.0 E+01 13
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 TABLE IV-B LIQUID EFFLUENTS Nuclides Released Batch Mode
- 1. Fission and activation products
- (excludinc tritium, oases alpha)
Co-60 Sr-90 Cs-1 37 Total (for quarter)
Unit
-Quarter 1 Ci 0.00 E+00 Ci 0.00 E+00 Ci 0.00 E+00 Ci 0.00 E+00 Quarter 2 5.23 E-06 4.11 E-05 2.44 E-05 7.07 E-05 Quarter 3 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Quarter 4 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00
- 2.
Dissolved and entrained gases None NOTE: No continuous releases of liquid radioactive effluent are made from Rancho Seco Nuclear Generating Station.
14
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 TABLE IV-C LIQUID EFFLUENTS - TYPICAL LOWER LIMITS OF DETECTION RADIONUCLIDES BATCH MODE: LLD (JCi/ml) 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-106 1.79 E-08 Silver-11Om 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 Bariums140 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 2007 TABLE IV-D RADIOLOGICAL IMPACT ON MAN DUE TO LIQUID EFFLUENT RELEASES CALCULATED RADIATION DOSE COMMITMENTS FOR LIQUID EFFLUENTS:
Unit mrem Quarter 1 0.00 E+00 Quarter2 1.04 E-01 (a)
Quarter 3 Quarter 4 0.00 E+00 0.00 E+00 2007 Annual 1.04 E-01 (a)ý A.
Maximum Total Body Dose Percent Tech Req limit B. Maximum Organ Dose Percent Tech Req limit 0.00 E+00 6.93 E+00 0.00 E+00 0.00 E+00 3.47 E+00' mrem 0.00 E+00 3.96 E-01 0.00 E+00 0.00 E+00 3.96 E-01 (b)
(b) 0.00 E+00 7.92 E+00 0.00 E+00 0.00 E+00 3.96 E+00 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, Child (b) Child - Bone 16
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 V. SOLID WASTE I.
SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)
- 1. Type of Waste:
Volume (m3) 0.00 E+00 Total Activity (Curies) 0.00 E+00 Est. Total Error (%)
N/A A. Spent Resins, filter sludges, evaporator bottoms, etc.
B. Dry compressible waste, 7.26 E+03 2.50 E+01 contaminated equipment, etc C. Irradiated components, 8.92 E+01 5.34 E+01 control rods, etc.
D. Other (primary metals, 8.23 E+02 1.42 E+00 valves, piping)
- 2.
Estimate of major nuclide composition Category A and Category B waste 2.5 E+01 2.5 E+01 2.5 E+01 Radionuclide H-3 C-14 Mn-54 Fe-55 Co-60 Ni-59 Ni-63 Zn-65 Sr-90 Nb-94 Tc-99 Cs-1 37 Pu-238 Pu-239 Pu-241 Pu-242 Am-241 Cm-242 Cm-244 Activity (Ci)
Category A Percentage
(%)
Activity (Ci) 1.01E-0 4.94E-0 4.58E-0 9.51 E-0 8.94E-0 2.02E-0 1.08E+C 4.95E-0 4.60E-0 5.54E-0 8.36E-0 1.12E+
3.76E-0 3.08E-0 1.15E-0 1.45E-0 1.11E-0 2.29E-1 2.31 E-(
Category B Percentage
(%)
)1 4.05E-01 1
1.97E+00 6
1.83E-05 1
3.80E+00
)1 3.57E+00
- 3 8.07E-03 01 4.32E+01 19 1.98E-08
]1 1.84E+00 16 2.21E-05 14 3.34E-03 01 4.47E+01 3
1.50E-02 13 1.23E-02 11 4.59E-01 15 5.80E-05
)2 4.43E-02 11 9.15E-11 03 9.23E-03 17
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007
- 3.
Estimate of major nuclide composition Category C and Category D waste Activity (Ci)
Category C Percentage
(%)
Category D Activity (Ci)
Percentage
(%)
Radionuclide H-3 C-14 Mn-54 Fe-55 Co-60 Ni-59 Ni-63 Zn-65 Sr-90 Nb-94 Tc-99 Cs-1i37 Pu-238 Pu-239 Pu-241 Pu-242 Am-241 Cm-242 Cm-244 2.46E-03 3.75E-03 1.77E-04 2.92E+01 1.51E+01 6.10E-01 8.49E+00 9.50E-07 4.18E-05 2.24E-04 9.08E-04 1.74E-04 2.17E-06 2.09E-06 7.12E-05 8.81 E-06 4.22E-08 1.13E-06 4.61 E-03 7.01 E-03 3.31 E-04 5.46E+01 2.83E+01 1.14E+00 1.59E+01 1.78E-06 7.82E-05 4.19E-04 1.70E-03 3.26E-04 4.06E-06 3.92E-06 1.33E-04 1.65E-05 7.91 E-08 2.12E-06 1,69E-02 2.90E-02 1.49E-02 4.17E-02 7.61E-01 2.19E-02 1.05E-04 5.26E-01 2.03E-04 1,76E-04 6.34E-03 6.81 E-07 5.84E-04 1.14E-04 1.19E+00 2.04E+00 1.05E+00 2.94E+00 5.36E+01 1.55E+00 7.43E-03 3.71E+01 1.43E-02 1.24E-02 4.47E-01 4.80E-05 4.11 E-02 8.01E-03 18
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007
- 4.
Solid Waste Disposition Number of Shipments 189 1
96 Mode of Transportation Highway Rail Rail Destination EnergySolutions, LLC (BWF)(a)
EnergySolutions, LLC (CWF) (b)
EnergySolutions, LLC (BWF)
- 5.
Type of Container
- a.
All shipment containers were "Strong Tight Containers" (STC).
- 6.
Solidification Agent
- a.
Not applicable J. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments None (a) BWF stands for Bulk Waste Facility.
(b) CWF stands for Containerized Waste Facility.
19
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 ATTACHMENT 1
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 1 of 50 LEAD DEPARTMENT:
EFFECTIVE DATE:
512312007 SCOPE OF REVISION:'
- 1. Revision eliminates Retention Basins, associated piping from the power block to the retention basins and the liquid effluent radiation monitor. Any liquid effluent releases will be made using temporary tank(s) and piping.
- 2. Deleted section(s) of procedure, which discusses the liquid effluent monitor and associated surveillance requirements.
3.. Deleted reference to the oily water separator.
- 4. Revised the Purpose section to indicate~that the ODCM complies with the requirements of 10CFR 50.36a. (Audit 05rA-010)
THIS PROCEDURE IS ISSUED F-OR IFORMATiON ONLY AND SHALL NT DE USED FOR WORK -OR DES, N,
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 2 of 50 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE...............
5
3.0 REFERENCES
/COMMITMENT DOCUMENTS..........................................................................
5 3.1 Commitment Documents.........
....................................... 5 3.2 Reference Documents..........................................................
.5 4.0 DEFINITIONS
.................................................................... 7 4.1 M em ber of the Public.............................
7 4.2 Occupational Dose............
I 7
4.3 P ublic D ose.....................................................................................................................
... 7 4.4 B atch R e lea se............................
7 4.5 Continuous Release..........................................................
........ 7 4.6 D ilutio n F low..........
............................ 7 4.7 Maxim um Exposed (Hypothetical) Individual...................................................................
8 4.8 R S N G S..............................................................................
................................................. 8 4.9 S ite B o u n d a rie s............................................................................
8 4.10 Nuisance Pathways 8
4.11 Unplanned Release...................................
8 4.12 Miscellaneous Release................................
8 4.13 S afety F a cto r (S F )...............................................................
................................................... 8 4.14 Ventilation Exhaust Treatment System (VETS).....................................................................
9 4.15 Instrum ent S urve illance..............
9 4.16 S urveillance Intervals.........................................................................................................
9 4.17 Radiological Effluent Information Management System (REIMS)..........................................
10 4.18 O perable/O perability.............................................................................................................
10 5.0 RESPONSIBILITIES..................................................
10 5.1 Radiation Protection/Chemistry Superintendent:..
10 5.2 Commitment Management Review Group (CMRG).............................................................
10
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 3 of 50 TABLE OF CONTENTS (Continued)
SECTION PAGE 6.0 PROCEDURE...................................................................................
11 6.1 General Considerations...................................................................................................
11 6.2 Maxim um Effl uent Concentrations in Liquid Effl uents......................................................
12 6.3 Liquid Dose Calculations......................................................................................................
14 6.4 Liquid Dose Projections..................................................................................................
15 6.5 Maximum Effluent Concentrations (MECs) in Gaseous Effluents...................
16 6.6 Dose Rate Calculations....................................................................................................
17 6.7 Organ Dose Calculations for Gaseous Effluents.................. I...........................................
18 6.8 Gas Dose Projections....................................................................................................
20
.6.9 Fuel Cycle Dose.......................................................................................................
20 6.10 EPA Reporting Requirements...........................................................
.......................... 20 6.11 Technical Requirements.ý...............................................................................................
21 6.11.1 Maximum Effluent Concentrations in Liquid Effluents.................................. 21 6.11.2 Liquid Dose Calculations......................................
22 6.11.3 Radioactive Liquid Effl uent Treatment........................................................
24 6.11.4 Gaseous Effl uent Monitoring.........................................
25 6.11.5 Gaseous Dose Rates....................................................................................
25 6.11.6 Gaseous Organ Dose................................................................................
26 6.11.7 Ventilation Exhaust Treatm ent System...............................
.............................. 27 6.11.8. Fuel Cycle Dose...........................................................................................
29 6.11.9 Quarter/Annual Dose Projections.....................................................................
30 6.12 Reports I..........
31 6.12.1 Annual Radioactive Effluent Release Report (ARERR).................................
31 6.12.2 30 Day Reports................................................
........................................ 32 7.0 RECORDS................................................................................................................................
32
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE' CALCULATION MANUAL PAGE: 4 of 50 TABLE OF CONTENTS (Continued)
ATTACHMENTS ATTACHMENT PAGE 1
DOSE FACTOR PARAMETERS.............................................
33 2
ATMOSPHERIC DISPERSION AND DEPOSITION PARAMETERS........................
36 3
SITE BOUNDARY FOR GASEOUS EFFLUENTS 37 4
SITE BOUNDARY FOR LIQUID EFFLUENTS.........-.................................
38 5
ORGAN DOSE FACTORS FOR LIQUID EFFLUENTS..................................
39 6
ORGAN DOSE FACTORS FOR GASEOUS EFFLUENTS 41 7
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 42 8
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......................................................................................
43 9
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM................................. 44 10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.................
46 11 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM........-..................
47
.12 ODCM REVISION REVIEW REQUIREMENTS.......
. 50
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 5 of 50 1.0 PURPOSE The Off-site Dose Calculation Manual (ODCM) containsthe methodology and parameters used in the calculation of off-site doses due to radioactive gaseous and liquid effluents.. Methods are described for assessing compliance with the Technical Requirements in the ODCM as they apply to 10 CFR Parts 20.1301 and 20.1302, 10 CFR Part 50, Appendix 1, 10 CFR 50.36a,and.40 CFR 190.10a for liquid and gaseous effluents. Additionally, the ODCM contains the Technical Requirements, which provide the Specifications, Applicability's, Actions, and Surveillance Requirements.
2.0 SCOPE This procedure functions as a manual that provides the basis for development of detailed implementing procedures that address dose calculations for liquid/gaseous releases. Additionally, this manual provides the Technical Requirements that govern releases of liquid and gaseous radioactive releases off-site.
2.1 Currently an installed liquid effluent pathway does not exist. The retention basins, associated valves, controllers and piping, and effluent monitoring instrumentation have been removed, dismantled, or abandoned in place. This was accomplished as part of the Decommissioning process. The main precursor to eliminating the permanently installed equipment and liquid effluent radiation monitor was the eliminationof the major liquid effluent source terms.
3.0 REFERENCES
/COMMITMENT DOCUMENTS 3.1 Commitment Documents 3.1.1 Code of Federal Regulations, Title 10, Chapter 1, Parts 20, 50.36a and Part 50, Appendix I 3.1.2 Rancho Seco Quality Manual (RSQM) 3.1.3 EPA 40 CFR Parts 302, 355 Reporting Requirements 3.1.4. 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Plant Operations 3.2 Reference Documents 3.2.1 USNRC Regulatory Guide 1.109, Rev. !, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1, October 1977
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 6 of 50 3.2.2 W. C. Burke, et. al., Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG-0133, USNRC: NRR, October 1978 3.2.3 ORNL, User's Manual for LADTAP II, NUREG/CR-1276, May 1980 3.2.4 D. L. Strange, et. al., LADTAP-II, Technical Reference and UserGuide, NUREG/CR-4013, Pacific Northwest Laboratory, April 1986 3.2.5 Eckerman, K. F., et. al., User's Guide to GASPAR Code,NUREG-0597, USNRC: NRR, June 1980, in RSIC CCC-463 3.2.6 USNRC Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors 3.2.7 USNRC Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants 3.2.8 USNRC Regulatory Guide 4.1, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants 3.2.9 REIMS Software Life Cycle Documents (Software Requirement Specification, Design Document, Acceptance Test Plan) 3.2.10 USNRC & Pacific Northwest Laboratory, TDMC Computer Code/Data Collections, XOQDOQ-82, Radiological Assessment Code System Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations 3.2.11 2006 Rancho Seco Biennial Land Use Census 3.2.12 RSNGS DSAR Chapters 11.1-1.1.5 3.2.13 RSNGS P&ID Drawing M-563, M-551, M-552 3.2.14 Pacific Northwest Laboratory, XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations 3.2.15 Congel, F. J., Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190), NUREG-0543, USNRC: NRR, February 1980 3.2.16 USNRC Generic Letter, 89-01, Dated January 31, 1989.
3.2.17 Rancho Seco REMP Manual 3.2.18 PDQ 92-063
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19.
TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 7 of 50 3.2.19 RP.312.1.14, Occupational Radiation Exposure Limits and Extensions 3.2.20 DQ 99-0061, 50.59 Rev. 1, Kurtz probe flow out of tolerance.
32.21 DQ-99-0053, SP.625A failed due to excessive system flow.
4.0 DEFINITIONS 4.1 Member of the Public Means any individual except when that individual is receiving an occupational dose.
4.2 Occupational Dose Means the dose received by an individual in the course of employment in which.the individual's assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whetherin the possession of the licensee or other person. Occupational dose does not include dose received from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a memberof the public.
4.3 Public Dose Means the dose received by a Member of the Public from exposure to radiation and/or radioactive material released by a licensee, or to any other source of radiation under the control of a licensee.. It does not include occupational dose or doses received from background radiation, as a patient from medical practices, or from voluntary participation in medical research programs.
4.4 Batch Release:
Liquid Batch Release is a transfer of a discrete volume of radioactive liquid.from a temporary tank to the Waste Water discharge canal (the Environmental Release Point).
A Gaseous Release is the discharge of gaseous radioactive wastes that consist of tritium and/or radionuclides in particulate form.
4.5 Continuous Release A continuous radioactive gaseous release is the discharge of gaseous waste during dismantlement activities.
Continuous radioactive liquid releases, are not planned tobe made from Rancho Seco Nuclear Generating Station (RSNGS).
4.6 Dilution Flow The volume or volume rate of fluid (liquid), which is added to a radiological release stream for the purpose of decreasing the concentration of the stream.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 8 of 50 4.7 Maximum Exposed (Hypothetical) Individual The Maximum Exposed Individual is characterized as "maximum" with regard to food consumption, occupancy, and other usage or exposure pathway parameters in the vicinity of Rancho Seco that would represent an individual with habits greater than usually expected for the average of the population in general.
Maximum dose factor parameters will be determined using site-specific data from the Biennial Land Use Census. If information needed to determine a parameter is not available, RG 1.109 parameters will be used. All dose factor parameters used are listed in Attachment 1.
4.8 RSNGS Rancho Seco Nuclear Generating Station 4.9 Site Boundaries The Site Boundaries are defined by the drawings in Attachments 3 and 4..
4.10 Nuisance Pathways (1)
Secondary system gaseous pathways where the calculated dose totals contribute less than 5% of the annual limits and do.not need to be tracked for dose calculational purposes unless secondary activity reaches a predetermined Action Level..
.(2)
Sources of trace levels of radioactivity in liquid effluents where the calculated dose totals contribute less.than 1% of the annual limits and do not need to be tracked for dose calculational purposes. Trace levels are defined to be less than 1 E-8 ýICi/ml for the nuclides typically released from RSNGS. Examples include the plant effluent inlet, and storm drains.
4.11 Unplanned Release The unexpected release of radioactive materials to unrestricted areas in gaseous and liquid effluent. All unplanned releases shall be discussed in the Annual Radiological Effluent Release Report (ARERR) to the NRC.
4.12 Miscellaneous Release Release pathways, which are considered, planned but are not defined explicitly with monitoring requirements in this procedure. These pathways contribute a relatively small percentage (<5%) to the annual dose limits but shall be tracked for effluent activity accounting and dose calculation purposes. Miscellaneous releases shallnot be reported in the ARERR as abnormal or unplanned releases. The lOS Building is an example of a Miscellaneous Release.
4.13 Safety Factor (SF)
A number greater than unity used in calculations to introduce greater conservatism (larger margin of safety) to offset various uncertainties in instrumentation and methods.
Radiation Protection/Chemistry Supervision based on either analysis or professional judgment sets safety factors. Unless otherwise specified, the default value is two (2).
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION, MANUAL PAGE: 9 of 50 4.14 Ventilation Exhaust Treatment System (VETS)
The Ventilation Exhaust Treatment System is the Reactor Building Purge Exhaust Filtering System. This system is designed and installed to reduce radioactive material in exhaust gases through filters for the purpose of removing particulates from the gaseous exhaust stream prior to the release to the environment.
4.15' Instrument Surveillance (1) Source Check A source check is the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
(2) Channel Test
- A channel test is the injection of an internal or external test signal into the channel to verify its proper response, including alarm and/or trip initiating action, where applicable.
- (3) Instrument Channel Check An instrument channel check is a verification of acceptable instrument performance by observation of its behavior and/or state;, this verification includes comparison of output and/or state 'of independent channels measuring the same variable.
(4) Instrument Channel Calibration*
An instrument channel calibration is a test, and adjustment (if necessary), to establish that the channel output responds with acceptable range and accuracy to known values of the parameter, which the channel measures, or an accurate simulation of these values..
Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include the channel test.
4.16 Surveillance Intervals The Surveillance Interval may be extended to a maximum of +25% to accommodate operations scheduling. The frequency notation (which follows the name of the Surveillance Interval in parenthesis) specified for the performance of Surveillance Requirements shall*
- correspond to the Surveillance Intervals defined below.
(1)
Shift (S):
A time period covering at least once per twelve (12) hours.
(2)
Daily (D):
A time period spaced to occur at least once per twenty four (24) hours.
(3)
Weekly (W):
A time period spaced to occur at least once per seven (7) days.
(4)
Monthly (M):
A time period spaced to occur.at least once per thirty one (3 1) days.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL.
REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 10 of 50 (5)
Quarterly (Q):
A time period spaced to occur at least once per ninety two (92) days.
(6)
Semiannually (SA):
A time period spaced to occur at least once per six (6) months.
(7)
Annually (A):
A time period spaced to occur at least once per twelve (12) months.
(8)
Refueling Interval (R):
A time period spaced to occur at least once per eighteen (18) months.
(9)'
Each Release (P):
This surveillance will be completed prior to each release.
4.17 Radiologqical Effluent Information Manaqement System (REIMS)
The computer software and database that tracks the volume and activity of released radioactive effluents. In addition, the software provides the basis for the permitting process, calculates dose to man, and summarizes data for inclusion into the ARERR.
4.18 Operable/ Operability A component or system is Operable when it is capable of performing its intended function within the required range. The component or system shall be considered to have this capability when: (1) it satisfies the Specifications in Section 6.11,.(2) it has been tested periodically in accordance with the Surveillance Requirement in Section 6.11 and has met its performance requirements, (3) the system has available its source of power, and (4) its required auxiliaries are maintained available and capable of performing their intended function.
5.0 RESPONSIBILITIES 5.1 Radiation Protection/Chemistry Superintendent It is the responsibility of the Radiation Protection/Chemistry Superintendent for the following:
- 1) ODCM Revisions and Reporting the Revisions in the Annual Radioactive Effluent Release Report (ARERR)
- 2) ARERR Preparation and Submittal 3)- REIMS Database
- 4) LADTAP, GASPAR, and XOQDOQ Computer Program Verifications and Changes 5.2 Commitment Manaqement Review Group (CMRG)
The CMRG is responsible for reviewing and accepting all changes to the ODCM with approval by the Plant Manager per the Rancho Seco Quality Manual.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 11 of 50 6.0 PROCEDURE 6.1 General Considerations 6.1.1 Liquid Effluent Pathways The liquid effluent discharge of RSNGS forms the headwaters of Clay Creek.
Dilution of the liquid effluent occurs off-site in the seasonal creek (No Name Creek) just downstream of the Plant Outfall, which then joins Clay and Hadselville Creeks, and of Hadselville and Laguna Creeks, and at the confluence of Laguna Creek and the Cosumnes River.
Planned radioactive liquid releases(if necessary) will be directed through temporary tanks and piping.to give reasonable assurance of compliance with 10 CFR 50 Appendix I prior to their discharge. Prior to discharge from the temporary system to the plant effluent (off-site),
the discharge rate from the temporary system and the amount of dilution from Folsom South Canal are controlled to-ensure compliance with the concentration requirements in 10 CFR 20.
6.1.2 Gaseous Effluent Pathways Airborne radioactive material in the Reactor building at RSNGS is routed and discharged in airborne effluent after passing through filters. Unplanned Releases shall be evaluated on a case-by-case basis. TheInterim On-site Storage (lOS) Building is a Miscellaneous Release.
6.1.3 Meteoroloqical Data The atmospheric dispersion (X/Q) and deposition (D/Q) factors used in calculations involving airborne effluent-are conservative default values. The default X/Q value is 1.0E-4 sec/m3, and the default D/Q value is 1.OE-6 m-2. These factors should be used to determine monitor set points, assess compliance with the gaseous effluent requirements in Section 6.11, and calculate the gaseous effluent dose reported in the ARERR. Attachment 2 shows actual dispersion and deposition factors and is presented for historical information only.
6.1.4 Boundaries The Site Boundary for Gaseous Effluents as shown in Attachment 3 is for all calculations involving gaseous effluents. The Site Boundary for Liquid Effluents as shown in Attachment 4 is for all calculations involving liquid effluents.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 12 of 50 6.1-5 40 CFR 190 Compliance For the purposes of assessing compliance with 40 CFR 190, the MEMBER OF THE PUBLIC which received the most exposure may be determined using actual food consumption, actual occupancy rates, and dilution off-site from additional converging streams (verses assumptions used for a HYPOTHETICAL MAXIMUM EXPOSED INDIVIDUAL based on Biennial Land Use Census data).
6.1.6 Computers vs. Manual Calculations Computer systems such as REIMS should be used for calculations in order to minimize error and hasten the release process. However, in the event computers are not available for calculations, manual pre-release calculations should be done based on the most historically restrictive receptor.
6.2 Maximum Effluent Concentrations in Liquid Effluents The Maximum Effluent Concentration Fraction is calculated to determine compliance with 10 CFR 20 requirements and the Specification in Step 6.11.1. Radioactive liquid effluent discharges normally originate in onsite temporary tank. Samples are collected and analyzed!
from each temporaryTank prior to discharge to ensure that compliance with the Specification in Step 6.11.1 can be achieved.
In addition, calculations to determine the minimum dilution water flowrate and maximum temporary tank discharge flow rate to ensure compliance are provided in this section. Any combination of minimum dilution flow rate and maximum discharge flow rate, which-satisfy the Specification, is acceptable.
6.2.1 Maximum Effluent Concentration Fraction (MECF)
Compliance with the Specification in Step 6.11.1 is anticipated when the MEC.F is less than or equal to 1.0. The MECF is calculated as follows:
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 13 of 50 MECF
[MC]
Fr F0
+ Fr Where:
MECF =
The calculated fraction of Maximum Effluent Concentration in the radioactive liquid effluent discharged beyond the Site Boundary for Liquid Effluents (see Attachment 4).
C
=
The concentration (prior to dilution) of radionuclide i in the batch of liquid effluent in pCi/ml.
MECi
=
The MEC of radionuclide ifrom Appendix B to 10 CFR Part 20, Table 2, Column 2, in pCi/ml. The class with the most restrictive Effluent Concentration will be used for.each isotope.
Fr
=
Discharge flow rate; the flow rate of the radioactive liquid batch release from the temporary tank to the Waste Water Discharge Canal (Plant Effluent) in gpm.
I FC
=
The total available dilution water (Plant Effluent) flow rate at the time of discharge of the radioactive liquid effluent in gpm.
6.2.2 Minimum Dilution Water Flow Rate (Ff__
The minimum dilution water (Plant Effluent) flow rate (Fc 1n) is calculated as follows:
Fcm.
Fr x
[(SF x y{
NOTE SF XZ i(Ci/MECj) must be _ 1.0 Where:
Fr A fixed effluent discharge flow (gpm) (as required by specific release restrictions).
SF A factor which may be applied to incorporate a margin of conservatism (SF > 1).
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 14 of 50 6.2.3 Maximum Effluent Dischargle Flow Rate (FLax)
The maximum effluent discharge flow rate (Frma) is calculated as follows:
Fý Fr_
=
[SF
(
cr]I Where:
F:
= A fixed dilution water flow rate (gpm) (as required by specific release restrictions).
NOTE SF XY (C-lMEC1 ) must be >i 6.3 Liquid Dose Calculations This section provides the methodology to demonstrate compliance with the Specification in Step 6.11.2.
Site-specific organ dose factors for liquid effluents have been determined for the MAXIMUM EXPOSED INDIVIDUAL and are listed in Attachment 5. Dose factors (Aijap) were derived using equations and methods in Regulatory Guide 1.109, Rev. 1 and LADTAP. The dose factor parameters used are listed in Attachment 1. As previously stated, site specific parameters should be used based on the Biennial Land Use Census in'lieu of the values provided in RG 1.109 whenever possible.
The exposure pathways included in the Aijap are those identified by the Biennial Land Use Census. The pathways considered for inclusion are:
Fresh water fish Fresh water invertebrate 0
River shoreline deposits a
Milk from cows that eat fresh or stored forage irrigated with Clay Creek water 0
Meat from cows that eat fresh or stored forage irrigated with Clay Creek water Vegetation'
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 15 of 50 6.3.1 Liquid Effluent Dose Equation
.ZQix Aijap)
D i p
F Daj F
Where:
Daj Annual calculated dose (50 year dose commitment) to the organ (or total body) j of a maximally exposed individual of age group a(mrem/yr).
Q*
=
Activity of isotope i released during the year (Ci/yr).
Aijap.
=
Site-specific dose factor for an organ (or total body) j for a person of age group a via pathway p due to isotope i (mrem-ft3/Ci-sec).
I F
=. Annual average discharge volumetric flow rate (effluent water plus dilution water) in ftW/sec.
Because the dose rate varies linearly with activity release, rate, the dose for a shorter period of time (mrem) may be calculated by substituting the activity released (Ci) during that period for Qi in the above equation. However, volumetric flow rates should not be averaged over a period less than a calendar quarter. More conservative flow rates are acceptable.
6.4 Liquid Dose Projections 31 -day dose projections are calculated to show compliance with the Specification in Step 6.11.3 Quarterly and Annual dose projections are calculated in compliance with the.
Specification in Step 6.11.9.
The following equations shall be used:
31-Day Proiection:
Dp31 = 31 x Dyr tyr Quarterly Proiection:
Dprr = 9.1.3 x Qt tQtr Yearly Proiection:
Dpyr = 365.25 x Dy-tyr
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 16 of 50 Where:
Dp31
=
31-day dose projection.
Dy,
=
Cumulative annual dose to date.
tyr Number of days into the year.
Dpetr
=
Quarterly dose projection.
DQtr
=
Cumulative quarterly dose to date.
tQt
=
Number of days into the quarter.
Dpyr
= Annual dose projection.
6.4.1 Gaseous Effluent Flow Rates Flow rates used in routine gaseous effluent calculations for the pathways listed below are conservative default values. These flow rates should be used to determine monitor set points, assess compliance with the.gaseous effluent requirements in Section 6.11, and calculate the gaseous effluent dose reported in the ARERR.
Gaseous effluent release points and maximum design flow rates used at RSNGS are as follows:
Reactor Building Stack 85,000 CFM Interim On-site Storage Building Ventilation 8,050 CFM
- The Interim On-site Storage (lOS) Building is not subject to continuous discharges of radioactivity. Because of the infrequency of a radioactive release, assessment will be done on each release according to administrative procedures..
6.5 Maximum Effluent Concentrations (MECs) in Gaseous Effluents In. order to demonstrate compliance with 10 CFR 20.1301, which requires that the total MEC fraction not exceed 1 when averaged over an entire year, the calculation is included in the Annual Radioactive Effluent Release Report. In addition, a four hour reporting requirement exists when the total MEC fraction exceeds 20 when averaged over one hour per 10 CFR 50.72. The following provides guidance on how to perform this calculation.
Maximum Effluent Concentration Fraction (MECF) Equation MECF x Fx 4.72E-4 x X/Q x TR
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 17 of 50 Where:
Cj
=
The concentration of nuclide i in mCi/cc..
F
=
Maximum design volumetric flow rate in CFM as indicated in 6.5.1.
X/Q A conservative default atmospheric dispersion factor for a ground level release to a sector at or beyond the Site Boundary for Gaseous Effluents in sec/m 3. The default value in Step 6.1.3 will be used.
MECj The MEC for nuclide ifrom Appendix B to 10 CFR Part 20,.Table 2, Column 2 (pCi/cc). The class with the most restrictive Effluent Concentration will be used for each isotope.
=
If the time of release is less than one hour, then this value is the duration of the transient in minutes divided by sixty. Otherwise, the Time Ratio (TR) is one. Dimensionless.
4.72E.- 4
= The conversion factor in min*m3/sec*ft3.
6.6 Dose Rate Calculations The Specification in.Step 6.11.5 provides a maximum limit on organ dose rate equivalent beyond the Site Boundary for Gaseous Effluents from tritium and all radioactive materials in particulate form with half-lives greater than 8 days. Compliance is determined by calculating the organ dose'rate for the MAXIMUM EXPOSED INDIVIDUAL for the inhalation pathway only.
The organ dose rate resulting from inhalation is calculated with the equation:
Organ:
DOaj (X/Q) x ZZ(Q,, x Raji)
V I
Where:
DO2 j
=
The dose commitment rate to organ j of a person in age group a, (mrem/yr)
Raji The factor to convert air concentration of radionuclide i to organ j dose commitment rate of a person in age group an exposed by inhalation (mrem-m 3/p Ci-yr). See Attachment. 7.
Qv*
=
The release rate of radionuclide i (not including Noble Gas nuclides), via effluent vent v during the time of the release'(pCi/sec)
X/Q
=
A conservative default atmospheric dispersion factor for a ground level release to a sector at or beyond the Site Boundary for Gaseous Effluents in sec/m3. The default value in Step 6.1.3 will be used.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL.
REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 18 of 50 Exposure to dose rate factors, Raji, for using equation 13 in RG 1.109, Rev. 1, derives inhalation. Tables E-5, E-7, E-8, E-9, and E-10 are assumed to represent the Maximum Exposed Individual in the equation to derive Raji.
6.7 Organ Dose Calculations for Gaseous Effluents" The Surveillance Requirement in Step 6.11.6 requires the radiation dose or dose commitment to the Maximum Exposed (Hypothetical) Individual accumulated.from exposure to tritium and radioactive materials in particulate form having half-lives greater than 8.0 days, that originate in effluent air, be determined at least every month. The radiation dose or dose commitment accumulated during a.calendar quarter and a year may not exceed values stated in the Specification in Step 6.11.6.
A person may be exposed to effluent radioactive material of this type in air by inhalation or indirectly via environmental pathways that involve deposition Onto vegetation and the ground.
The exposure pathways evaluated will include the following:
p Exposure Pathway 1
Air - inhalation 2
Deposition onto ground - irradiation 3
Deposition onto vegetation - ingestion 4
Deposition onto forage - cow - milk - ingestion 5
Deposition onto forage - meat animal - meat - ingestion 6.
Deposition onto forage - goat - milk - ingestion The equation used to calculate the dose commitment to the Maximum Exposed (Hypothetical).
Individual from radionuclidesother than tritium is:
Daj =Z (X/Q)p x Qvi X Rajip
+ I
/Q)p x JI Qvi x Rijp p=l Iv i
I p2L V
i
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 19 of 50 Where:
p = 1, i.e., air-inhalation, in the first term, and p = 2, 3, 4, 5, and 6 in the second term of.
the equation excludes H-3.
Daj
=
- The dose commitment to organ j of a person in age group a (mrem)
Qv
-=
The quantity of each radionuclide i, in particulate form having a half-life greater than 8.0 days, in air discharged via effluent stream v (pCi)
X/Q
=
A conservative default atmospheric dispersion.factor for a ground level release to a sector at or beyond the Site Boundary for Gaseous Effluents in sec/m 3. The default value in Step 6.1.3 will be used.
D/Q
=
A conservative default deposition faetor. A Factor converting a ground-level or building wake discharge in air to deposition on land (m-2). The D/Q value in Step 6.1.3 will be used.
Rajip A factor converting time integrated concentration of radionuclide i in. air or deposited on vegetation and/or ground to radiation dose commitment to organ j, including total body, of a person in age group a who is exposed via pathway p.
When p = 1, representing air-inhalation, Rajip has units. of mrem-m 3/[Ci-yr. When p=2,3,4,5 or 6 in the second term of the: equation above, representing pathways involving deposition., Rajip has units of mrem-m 2-sec/yr-4Ci. When the radionuclide is H-3, Rajpp has units of mrem-m3/tCi-yr.
Tritium is assumed not to deposit onto vegetation or the ground. Hence, the concentration in vegetation is assumed to be related to the local atmospheric concentration as described in RG 1.109, Rev. 1,Appendix C. The dose commitment to the Maximum Exposed (Hypothetical).
Individual from tritium in gaseous effluent is calculated with the equation:
Daj = 3.17E-8 x I (X/Q)p X Y-X(Q'i x Raji)
Where:
p = 1, 3, 4, 5, and 6 i includes H-3 only X/Q
=
A conservative default atmospheric dispersion factor for a ground level
- release to a sector at or beyond the Site Boundary for Gaseous Effluents in sec/rm3. The default value in Step 6.1.3 will be used.
3.17E-8 years/sec Other terms as defined in previous section.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 20 of 50 Dose factors Rajip for RSNGS are derived using the equations and methods in RG 1.109, Rev.
1, Appendix C. Values of parameters in RG 1.109, Rev. 1, Table E-5 are assumed to represent the Maximum Exposed (Hypothetical) Individual unless Land Use Census data justify a different value. Any different values from default values will be justified and added as a table to the ODCM. Values of other parametersrecommended in RG 1.109, Rev. 1, including those, recommended in the absence of site-specific data, are used in the equationsto derive the dose factors. (GASPAR or REIMS may be used to perform the calculations.)
6.8 Gas Dose Proiections 31-Day Dose projections are calculated to show compliance with Step 6.11.9. Quarterly and Annual dose projections are calculated in compliance with the Specification in Step 6.11.9.
The dose projection equations are the same as used for-liquid per Step 6.4.
6.9 Fuel Cycle Dose If a calculated dose exceeds twice the limit of the Specification in Step 6.11.2 and 6.11.6 or a level in Table 3 of the REMP Manual is exceeded, an assessment of compliance with the Specification in Step 6.11.8 must be made.
Liquid dose calculations shall be made using the general methodology of Step 6.4. Gas dose calculations shall be made using the general methodology of Steps 6.6 and 6.7. These methodologies are to be used as a guide and strict adherence is not required because the Fuel Cycle Dose Calculation is done to determine the actual dose received, not a hypothetical maximum. Therefore, parameters such as dilution beyond the siteboundary and residential shielding may be factored into the calculation.
The total body and organ doses shall be the result of summing the individual contributions from liquid, gas, and direct radiation sources for the affected Member of the Public.
Irradiation, i.e., exposure to an external source of radiation, directly from the RSNGS normally will be evaluated with the aid of environmental monitoring dosimetry.
6.10 EPA Reporting Requirements If a calculated dose exceeds the Specification limit of Step 6.11.1, 6.11.2, 6.11.5, or 6.11.6, an assessment of compliance with 40 CFR Parts 302 and 355, Reportable Quantity Adjustment -
Radionuclides, must be made.
- This involves determining the maximum quantity of radionuclides released in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and comparing the quantities to the values listed in 40 CFR'302 Appendix B. The "sum of the
.ratios" method shall be used to determine compliance. If the "sum of the ratios" is greater than one, the National Response Center shall-be notified.
Since Rancho Seco's systems and procedures are set up to normally operate within the above limits, this condition is not expected to occur, therefore, specific implementation procedures to determine compliance are not required.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 21 of 50 6.11 Technical Requirements
.6.11.1 Maximum Effluent Concentrations in Liquid Effluents Specifications:
The concentration of radioactive material released in liquid effluents at any time beyond the Site Boundary for Liquid Effluents (see Attachment 4) shall, be limited to the concentrations specified in Appendix B to 10 CFR Part 20, Table 2, Column 2.
Applicability:
This is applicable at all times.
Action:
With the concentration of radioactive material released from the site to areas beyond the Site Boundary for Liquid Effluents exceeding the above Specifications, immediately restore concentration within the required limits and report the event in the nextAnnual Radioactive Effluent Release Report.
Surveillance Requirements:
The radioactivity concentration of each temporary tank to be discharged shall be determined prior to release by sampling and analysis in acpordance with Attachment 9.
The results of the temporary tank pre-release sample analyses shall be used with~the calculational methods described in Step 6.2 to ensure that the concentration at the point of release is within the limits of the above Specification.
Bases:
This Specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to areas beyond the Site Boundary For Liquid Effluents (see Attachment 4) will be less than the concentration levels specified in Appendix B to 10 CFR Part 20, Table 2, Column 2. This limitation provides additional.
assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within the limits of 10 CFR Part 20.1301 to a MEMBER OF THE PUBLIC.
There are no continuous releases of radioactive material in liquid effluents from the plant.
All radioactive liquid effluent releases from the plant are by batch method.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 22 of 50 6.11.2 Liquid Dose Calculations Specifications:
The dose or dose commitment to a MAXIMUM EXPOSED (HYPOTHETICAL) INDIVIDUAL from radioactive materials in liquid effluents released beyond the Site Boundary for Liquid Effluents (see Attachment 4) shall be limited to:
- 1)
Less than or equal to 1.5 mrem to the total body and to less than or equal to 5.0 mrem to any organ during. any calendar quarter; and,
- 2)
Less than or equal to 3 mrem to the total body and to less than or equalto 10 mrem to any organ during any calendar year.
Applicability:
At all times.
-Action:
With the calculated dose or dose commitment from the release of radioactive materials in liquid effluents exceeding any of the above Specifications, prepare and submit to the Commission within 30 days a Special Report. This Report will identify the cause(s) for exceeding the limit(s) and define the corrective actions to be taken to reduce the releases of radioactive material in liquid effluents and the proposed corrective actionsto be taken to assure that subsequent releases will be in compliance with the above Specifications.
Surveillance Requirements:
Cumulative dose assessments associated.with the release of radioactive liquid effluent shall be determined by sampling and analysis in accordance with Attachment 9, and calculations performed in accordance with the methodology describedin Step 6.4 at the following frequencies:
- 1)
Prior to the initiation of a release of radioactive liquid effluent-from the temporary tank(s); and,
- 2)
Upon verification of monthly composite analysis results for radioactive liquid effluent released from the temporary tank(s).
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 23 of 50 A dose tracking system and administrative dose limits shall be established and maintained.
With the 31-day dose projection in excess of the limits in Step 6.11.2, adjust liquid effluent operating parameters to give reasonable assurance of compliance with the dose limits of this Specification (10 CFR 50, Appendix I dose guidelines) and maintain radioactiveliquid releases'as low as is reasonably achievable.
Bases:
ODCM Step 6.11.2 is provided to implement the requirements of Sections IIA, III.A,and IV.A of Appendix 1, 10 CFR Part 50. This step implements the guides set forth in Section lI.A of 10 CFR 50, Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of 10 CFR 50, Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." The dose calculation methodology in this manual implement the requirements in Section III.A of 10 CFR 50,Appendix I that conformance with the guides of 10 CFR 50, Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.
The equations specified in this manual for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "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," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. There is reasonabl6 assurance thatthe operation of the facility will not result in radionuclide concentrations in finished drinking water that are in excess of the requirements of 40 CFR 141.
The Lower Limits of Detection established in Attachment 9 are based on an estimated
- maximum annual effluent outflow of 2 million gallons with a minimum annual average flow rate in the plant effluent stream of 6,000 gallons per minute., The temporary tank pre-release and monthly composite Lower Limits of Detection equate to an off-site dose of less than 10 percent of the 10 CFR 50, Appendix I guidelines. These Lower Limits of Detection, along with the dose tracking system, give reasonable assurance that the dose limits.
prescribed in ODCM Step 6.11.2 (the 10 CFR 50, Appendix I dose guidelines) will be met.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 24 of 50 6.11.3 Radioactive Liquid Effluent Treatment Specifications:
A radioactive liquid effluent treatment process shall be used to reduce the quantity of radioactive materials in liquid effluent prior to their discharge when projected doses due to the liquid effluent beyond the Site Boundary for Liquid Effluents (see Attachment 4), when averaged over 31 days, would exceed 0.25 mrem to the total body or 0.83 mrem to any organ (8.33% of the 10 CFR 50, Appendix I annual guidelines).
Applicability:
At all times.
Action:
With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days a Special Report, which includes the following information:
- 1)
Explanation of why liquid Radwaste was being discharged without treatment,
.2)
Action(s) taken to restore. treatment capability and,
- 3)
Summary description of action(s) taken to prevent a recurrence.
Surveillance Requirements:
Doses due to liquid releases to areas beyond the Site Boundary for Liquid Effluents shall be projected prior to each temporary tank release in accordance with the methodology described.in Step 6.4.
Bases:
The liquid effluent source term and time constraints for releases have been significantly.
reduced with the current plant configuration. Use. of a radioactive liquid effluent treatment process whenever liquid effluent requires treatment prior to release to the environment, provides reasonable assurance that the releases of radioactive materials in liquid effluent are maintained "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section liD of Appendix I to 10 CFR 50. The specified dose limits are the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 25 of 50 6.11-4 Gaseous Effluent Monitoring Instrumentation requirements for gaseous effluent monitoring are presented in Attachment 10.
Th uildinghas a ventilation system. in which the effluent release is sampled during work events that generate airborne particulate activity. Operation of the ventilation system produces a negative pressure in the building. Although no planned airborne radioactive releases are anticipated from this pa thway, refer to Attachment 11 when sampling the ventilation exhaust.
6.11.5 Gaseous Dose Rates Specifications:
The dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the Site Boundary for Gaseous Effluents (see Attachment 3) shall be limited to the following values:
- 1)
The dose rate limit for tritiumand for all radioactive materials in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mrem/yr to any organ.
Applicability:
This is applicable at all times.
Action:
With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the limit(s) specified and report the event in the next Annual Radioactive Effluent.
Release Report.
Surveillance Requirements:
Obtaining representative samples and performing analyses in accordance with the sample analyses. program specified in Attachment 11 shall determine the release rate of radioactive materials in gaseous effluents.
The dose rate due to tritium and all radioactive material in particulate form with half-lives greater than 8 days, released in gaseous effluents, shall be determined to be Within the limits of this Specification by using the results of the sampling and analysis program specified in Attachment 11 and the methodology described in Step 6.6.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002
.MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 26 of 50 Bases:
Step 6.11.5 is provided to ensure that the dose rate from gaseous effluents due to inhalation at any time at the Site Boundary for Gaseous Effluents (see Attachment 3) will be within the annual dose limits of 10CFR Part 20 for MEMBERS OF THE PUBLIC. The annual dose limits are the doses associated with the concentrations of Appendix B to 10 CFR Part 20, Table 2, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual at or beyond the Site Boundary for Gaseous Effluents to annual average concentrations exceeding the dose rate equivalent, on which the limits specified in Appendix B, Table 2 of 10 CFR Part 20 were derived. For individuals who may at times be within the Site Boundary for Gaseous Effluents, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the boundary.
6.11.6 Gaseous Organ Dose Specifications:
The dose or dose commitment to a MAXIMUM EXPOSED (HYPOTHETICAL) INDIVIDUAL from tritium and radioactive materials in particulate form with half-lives greater than eight days in gaseous effluents released to areas at.or beyond the Site Boundary for Gaseous Effluents (see Attachment 3) shall be limited to the following:
- 1) During any calendar quarter, to less than or equal to 7.5 mrem to any organ; and,
- 2) During any calendar year, to less than or equal to 15 mrem to any organ.
Applicability:
This is applicable at all times.
Action:
With thecalculated dose. or dose commitment from the release of tritium and radioactive materials inparticulate form with half-lives greater than eight days in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report. This Report will identify the cause(s) for exceeding the limit and define the corrective actions to be taken to reduce the releases and the proposed corrective action(s) to be taken to assure that subsequent releases will be in compliance, with the above annual limits.
Surveillance Requirements:
Cumulative dose contributions forthe current calendar quarter and calendar year period shall be determined in accordance with the methodology described in Step 6.7 at least monthly.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE:* 27 of 50 Bases:
Step 6.11.5 is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix., 10 CFR Part 50. The Specifications are the guides set forth in Section lI.C of 10 CFR 50, Appendix I. The Action statements provide the required operating flexibility and at.the same time implement the guides set forth in Section IV.A of 10 CFR 50, Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "As Low
.As is Reasonably Achievable (ALARA)." The calculational methods specified inthe Surveillance Requirements implement the requirements in Section III.A of 10 CFR 50, Appendix I that conformance with the guides of 10 CFR 50, Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. For individuals who may at times be within the Site Boundary for Gaseous Effluents, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric dispersion factor above that for the boundary.
The calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory'Guide 1.109,
""Calculating of Annual Doses to Man from Routine Releases Qf Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111, ""Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,""
Revision 1, July 1977. These equations also provide for estimating doses based upon the historical average atmospheric conditions.
The release rate specifications for radioactive materials in particulate form are dependent on the existing radionuclide pathways to man in areas at or beyond the Site Boundary for Gaseous Effluents (see Attachment 3). The pathways which were examined in the development of these calculations are: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
6.11.7 Ventilation Exhaust Treatment System Specifications:
The VENTILATION EXHAUST TREATMENT SYSTEM shall be sampled during dismantlement activities.
The following two conditions shall not exist simultaneous:
(1)
Gaseous waste is being discharged without treatment, and (2)
The projected doses due to gaseous effluent releases from the site (see ), when averaged over 31 days, would exceed 2% of the 10 CFR 50, Appendix I annual dose guidelines (0.3 mrem to any organ, or air doses of 0.2 mrad from gamma radiation or.0.4 mrad from beta radiation).
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 28 of 50 Applicability:
This is applicable at all times.
Action:
If both parts 1) and 2) of the Specification are satisfied, prepare and submit to the Commission within 30 days a Special Report pursuant to Appendix A of the RSQM, which includes the following information:
- a. Explanation of why gaseous Radwaste was being discharged without treatment, and identification of the equipment or subsystems not OPERABLE and.the reason for inoperability.
- b. Action(s) taken to restore the inoperable equipment to OPERABLE STATUS.
- c. Summary description of action(s) taken to prevent a recurrence.
Surveillance Requirements:
Doses due to gaseous releases to areas at and beyond the Site Boundary for Gaseous Effluents (see Attachment 3) shall be projected at least once per 31 days in accordance with the methodology and parameters in Step 6.8.
Aerosol particulate testing will be performed on the filters in the Ventilation Exhaust Treatment Systems every 18 months, or after any work has been performed on the filter systems, which could alter their integrity. For minor filter integrity repairs (up to - 0.1% of filter bank surface area), immediate testing is not required. Filter integrity is ensured through visual observations and effluent sampling Bases:
The operation of the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems are available for use whenever gaseous effluents require treatment prior to release to the environment..The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents are maintained "as low as is reasonably achievable". The specified limits governing the use of appropriate portions of the systems and the dose design objectives set forth in Sections lI.Band II.C of Appendix I, 10 CFR 50, for gaseous effluents.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 29 of 50 6.11.8 Fuel Cycle Dose Specification:
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 be limited to less than or equal to 25 mrem to the total body or any organ in a calendar year.
Applicability:
At all times.
Action:
- 1)
With the calculated doses from.the release of radioactive material in liquid or gaseous effluents exceeding twice the limits of Specifications in Steps 6.11.2 and 6.11.76 or exceeding the reporting levels in Table 3 of the REMP Manual, calculations shall be made including direct radiation contributions (including outside storage tanks, etc.) to determine whether the above specifications have been exceeded.
- 2)
If the above 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 above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(a)(4), 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 report. It shall also describe levels of radiation. and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.
- 3)
If the estimated dose(s) exceed the above limits, and if the release condition resulting in the violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provision of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
Surveillance Requirements:
Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Step 6.11.2 and 6.11.5 Surveillance Requirements.
Cumulative dose contributions from direct radiation (including outside storage tanks, etc.).
shall be determined in accordance with Step 6.9. This requirement is applicable only under the conditions set forth in the above Action statements.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 30 of 50 Bases:
Step 6.11.8 is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the numerical guides for design objective doses of 10 CFR 50, Appendix I or exceeds the reporting levels of the Radiological Environmental Monitoring Program. 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 plant remains within twice the numerical guides for design objectives of 10 CFR 50, Appendix I and if direct radiation (outside storage tanks, etc.) 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 5 miles must be considered. If the dose to any MEMBER OF THE PUBLIC is evaluated to exceed the requirements of 40CFR 190, the Special Report with a request for a variance (providedthe release. conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190 is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. An individual is not considered a MEMBER OF THE.PUBLIC during any period in which he/she is engaged in carrying out any operation, which is part of the uranium fuel cycle.
6.11.9 Quarter/Annual Dose Projections Specifications:
The projected dose contributions from liquid and gaseous effluents for the current calendar quarter and current calendar year shall be calculated according to the methodology in Steps 6.4 and 6.8 at least every 31 days.
Applicability:
At all times.
Action:
With the required dose calculations not being performed, best effort will be exerted to perform the calculations once the deficiency has been identified. Corrective actions will be taken and documented to prevent reoccurrence.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 31 of 50 Surveillance Requirements
- 1)
Liquid Effluents:
Projected dose contributions shall be determined at least every 31 days.
- 2)
Gaseous Effluents:
Projected dose contributions shall be determined at least every 31 days.
Bases:.
This step is provided to implement Appendix A of the Rancho Seco Quality Manual. Dose-projections provide a means of determining if current release practices will be within the dose limits of 10 CFR 50, Appendix I. Calculating projected dose totals every 31 days provides information, which can be used to keep effluent releases "as low as is reasonably achievable".
Calculations performed during the first 15 days of the calendar year or calendarquarter will result in artificially high dose projections, which provide no usable information.
6.12 Reports 6.12.1 Annual Radioactive Effluent Release Report (ARERR)
The ARERR covering the activities of the unit during the previous 12 months shall be submitted within 90 days after January 1 of each year. The report shall include the following:
(1)
Summary of the quantities of radioactiveliquid and gaseous effluents released from the unit.
(2)
Summary of solid waste shipped from the unit.
(3)
All unplanned releases of radioactive materials in gaseous and liquid effluents to unrestricted areas shall include a description of the event and equipment involved, cause(s), action(s) taken to prevent recurrence, and consequences.
(4)
Dose or dose commitment assessments to ensure compliance with the specifications in 6.11.2, 6.11.6.
(5)
Complete, legible copy of the entire ODCM and/or REMP Manualif changes occurred during the ARERR reporting period. The copy may be part of the ARERR or sent concurrently.
(6)
The ARERR shall also include events described in 6.11.1, 6.11.3, and 6.11.4.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGEý 32 of 50 6.12.2 30 Day Reports The following 30-day reportsshould be submitted if the criteria are met as stated in the following areas:
(1) 6.11.2 - Liquid Dose Calculations (2) 6.11.9 - Liquid Dose Projections (3) 6.11.6 - Gaseous Organ Dose (4) 6.11.9 - Gaseous Dose Projections (5) 6.11.8 - Fuel Cycle Dose 7.0 RECORDS The individual/packaged documents and related correspondence completed as a result of the performance or implementation of this procedure are records. They shall be transmitted to Records Management in accordance with RSAP-0601 Nuclear Records Management.
MANUAL:.
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 33 of 50 DOSE FACTOR PARAMETERS CONSUMPTION.AND USAGE PARAMETERS PATHWAY Irrigated Stored Vegetables Irrigated Fresh Vegetables Irrigated Milk Irrigated Meat & Poultry Fish.
Other Seafood Invertebrate (Crayfish)
Algae AGE 1.109 DEFAULT Adult 520 kg/yr Teen 630 kg/yr Child 520 kg/yr Infant 0 kg/yr Adult 64 kg/yr Teen 42 kg/yr Child 26 kg/yr Infant 0 kg/yr Adult 310 kg/yr Teen 400 kg/yr Child 330 kg/yr Infant 330 kg/yr Adult 110 kg/yr Teen 65 kg/yr Child 41 kg/yr Infant 0 kg/yr Adult 21 kg/yr Teen 16 kg/yr Child 6.9 kg/yr Infant 0 kg/yr Adult 5.0 kg/yr Teen 3.8 kg/yr Child 1.7 kg/yr Infant 0 kg/yr Adult None Teen None Child None Infant None RSNGS 520 kg/yr 630 kg/yr 520 kg/yr 0 kg/yr 64 kg/yr 42 kg/yr 26 kg/yr 0 kg/yr 310 kg/yr 400 kg/yr 330 kg/yr 330 kg/yr 110 kg/yr 65 kg/yr 41 kg/yr 0 kg/yr 21 kg/yr
.16 kg/yr 6.9 kg/yr 0 kg/yr 6.9 kg/yr 5.2 kg/yr.
2.2 kg/yr 0 kg/yr 0 kg/yr 0 kg/yr 0 kg/yr 0 kg/yr Water Usage.(Drinking Water)
Adult Teen Child Infant 730 i/.yr 510 I/yr 510 'l/yr 330.1 /yr 0 I/yr 0 I/yr 0 I/yr 0 I/yr Page 1 of 3
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 34 of 50 DOSE FACTOR PARAMETERS (Continued)
CONSUMPTION AND USAGE PARAMETERS (continued)
PATHWAY Shoreline Recreation AGE 1.109 DEFAULT Swimming Adult Teen Child Infant Adult Teen Child Infant Adult Teen Child Infant Adult Teen Child Infant 12 hr/yr 67 hr/yr 14 hr/yr 0 hr/yr None None None None None None None None 8000 m3 8000 m3 3700 m3 1400 m3 RSNGS 200 hr/yr 100 hr/yr 14 hr/yr 0 hriyr 100 hr/yr 100 hr/yr 14 hr/yr 0 hr/yr 0 hr/yr 0 hr/yr 0 hr/yr 0 hr/yr 8000 m3 8000 m3 3700 m3 1400 m3 Boating Inhalation IRRIGATION RATES AND FRACTION OF IRRIGATION 1.109 DEFAULT 263 liters/m2 /month RSNGS Irrigation Rate 263 liters/m2 /month Time field has been irrigated prior to crop of interest Fraction of the year field is irrigated Fraction of animal water intake not obtained from the irrigation system (Irrigated Meat)
Fraction of animal water intake not obtained from the irrigation system (Irrigated Milk)
Page 2 of 3 15 years None None None 15 years None 0
1*
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 35 of 50 DOSE FACTOR PARAMETERS (Continued)
TRANSIT. TRANSFER. AND HOLDUP TIMES Irrigated Stored Vegetables Holdup Time Irrigated Fresh Vegetables Holdup Time Irrigated Milk Holdup Time Irrigated Meat Holdup Time Transit Time From Time Of Sample To Time Of Release Transit Time To Drinking Water DILUTIONS All Pathways Shore-Width Factor MISCELLANEOUS Fraction Of Leafy Vegetables Grown In
.Garden Of Interest Fraction Of Produce Ingested Grown In Garden Of Interest Crop Growing Time For Leafy Vegetables Ingested By Man Crop Growing Time For Pasture Grass Crop Yield For Leafy Vegetables Ingested By Man Crop Yield For Pasture Grass 1.109.DEFAULT 1440 hrs 24 hrs 48 hrs 480 hrs None None 1.109 DEFAULT None
- 0.2 1.109 DEFAULT 1.0 0.76 60 Days 30 Days 2.0 kg/m 2
0.7 kg/M 2
RSNGS 1440 hrs 24.hrs 48 hrs 480 hrs 72 hrs 0 hrs RSNGS 1 (None) 0.2 RSNGS 1.0
.0.76 30 Days 30 Days 2.0 kg/M 2
2.0 kg/m 2
Page 3of 3
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 36'of 50 ATMOSPHERIC DISPERSION AND DEPOSITION PARAMETERS PATHWAY Inhalation Ground Vegetation Cow Milk Meat Animal Meat Animal Goat Milk Site Boundary for Gaseous Effluents DIRECTIOI ENE ENE SSW ENE S
SSE SSW NNW GASEOUS EFFLUENT PATHWAYS 1998 CONTROLLING LOCATIONS**
A DISTANCE X/Q*
(sec/m3) 1038 M 8.1E-06 1038 M 670 M 1038 M 195 M 198 M 2500 M 670 M 1.4E-05 8.1 E-06 1.2E-04 1.OE-06 2.1 E-05 D/Q*
(m-2) 4.8E-08 2.8E-08 4.8E-08 34E-07 1.7E-09 Based on meteorological data from January 1978 to December 1987.
- Based on 1998 Land Use Census.
Page 1 of 1
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 37 of 50 SITE BOUNDARY FOR GASEOUS. EFFLUENTS Page 1 of I
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 38 of 50 SITE BOUNDARY FOR LIQUID EFFLUENTS Page 1 of 1
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 39 of 50 ORGAN DOSE FACTORS FOR LIQUID EFFLUENTS DOSE FACTOR TABLE: A(if - Adult Units are mrem/hr per pCi/mI Nuclide Bone
-Liver Tbody Thyroid Kidney Lung GI tract H-3 C-14 FE-55 CO-60 NI-63 CS-134 CS-137 0.OOE+00 3.82E+05 1.18E+04 1.26E+04 3.42E+05 4.44E+05 5.85E+05 1.21 E+01 7.63E+04 8.17E+03 1.61 E+04 2.37E+04 1.05E+06 7.98E+05 1.21E+01 7.63E+04 1.91E+03 2.02E+04 1.15E+04 8.59E+05 5.25E+05 1.21 E+01 7.63E+04 7.29E-04 1.26E+04 0.00E+00 4.03E+03 6.06E+03 1.21 E+01 7.63E+04 7.29E-04 1.26E+04 0.OOE+00.
3.43E+05 2.75E+05 1.21E+01 7.63E+04 4.56E+03 1.26E+04 0.OOE+00 1.16E+05 9.54E+04 1.21E+01 7.63E+04 4.69E+03 7.73E+04 4.95E+03 2.23E+04 2.14E+04 DOSE FACTOR TABLE: A(i) - Teen.
.Units are mremlhr per uCi/ml Nuclide Bone Liver Tbody Thyroid Kidney Lung GI tract H-3 C-14 FE-55.
CO-60 NI-63 SR-90 CS-134 CS-1 37 0.OOE+00 5.64E+05 1.37E+04 6.35E+03 4.50E+05 7.40E÷06 5.04E+05 6.99E+05 1.37E+01 1.13E+05 9.69E+03 1.10E+04 3.18E+04 6.16E-03 1.18E+06 9.30E+05 1.37E+01 1.13E+05 2.26E+03 1.69E+04 1.53E+04 1.98E+06 5.50E+05 3.26E+05 1.37E+01 1.13E+05 7.29E-04 6.35E+03 0.00E+00 6.16E-03 2.03E+03 3.03E+03 1.37E+01 1.13E+05 7.29E-04 6.35E+03 0.OOE+00 6.16E-03 3.77E+05 3.18E+05 1.37E+01 1.13E+05 6.15E+03 6.35E+03 0.OOE+00 6.16E-03 1.45E+05 1.26E+05 1.37E+01 1.13E+05 4.19E+03 6.71 E+04 5.06E+03 3.85E+05 1.67E+04 1.62E+04 DOSE FACTOR TABLE: A(iM - Child Units are mrem/hr oer uCi/ml
-Nuclide Bone Liver.
Tbody Thyroid Kidney Lung GI tract H-3 FE-55 CO-60 SR-90 CS-134 CS-137 0.OOE+00 2.40E+04 8.89E+02 1.47E+07 7.61 E+05 1.12E+06 2.1OE+01 1.27E+04 7.51 E+03 8.62E-04.
1.25E+06 1.07E+06 2.10E+01 3.94E+03 2.04E+04
- 3.93E+06 2.64E+05 1.59E+05 2.1OE+01 1.02E-04 8.89E+02 8.62E-04 2.85E+02 4.25E+02 2.10E+01 1.02E-04 8.89E+02 8.62E-04 3.87E+05 3.50E+05 2.10E+01 7.19E+03 8.89E+02 8.62E-04 1:39E+05 1.26E+05 2.10E+01 2.35E+03 3.76E+04 2.97E+05 7.02E+03 7.15E+03 Page 1 of 2
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 40 of 50 ORGAN DOSE FACTORS FOR LIQUID EFFLUENTS (Continued)
DOSE FACTOR TABLE: A(i) - Infant Units are mrem/hr Der uCi/ml Nuclide Bone Liver Tbody Thyroid Kidney Lung GI tract H-3 FE-55 CO-60 NI-63 SR-90 CS-134 CS-137 0.OOE+00 5.61 E+02 0.OOE+00 1.72E+05 3.91 E+05 1.55E+05 2.32E+05
- 1. 14E+01 3.63E+02 3.81 E+02 1.06E+04 0.OOE+00 2.89E+05 2.71E+05 1.14E+01 9.69E+01 8.99E+02 5.97E+03 1.05E+05 2.92E+04 1.92E+04 1-14E+01 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 1.14E+01 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 7.43E+04 7.27E+04 1.14E+01 1.77E+62 0.OOE+O0 0.00E+00 0.OOE+O0 3.05E+04 2.94E+04 1.14E+01 4.61E+01 9.06E+02 5.29E+02 7.22E+03 7.84E+02 8.47E+02 Page 2 of 2
MANUAL:
CHEMISTRY ADMINISTRATIV
E. PROCEDURE
S NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 41 of 50 ORGAN DOSE FACTORS FOR GASEOUS EFFLUENTS DOSE FACTOR TABLE: R(i) -Adult, inhalation Units are mrem/vr oer uCi/m 3.
Nuclide Bone Liver Tbody Thyroid Kidney Lung GI tract H-3 0.00E+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 FE-55 2.46E+04 1.70E+04 3.95E+03 0.OOE+00 0.00E+00 7.21 E+04 6.03E+03 CO-60 O.OOE+00 1.15E+04 1.48E+04 0.OOE+00 0.OOE+00 5.97E+06 2.85E+05 SR-90 9.92E+07 0.OOE+00 6.1OE+06 O.OOE+00 0.OOE+00 9.60E+06 7.22E+05 CS-134 3.73E'+05 8.48E+05 7.28E+05 0.OOE+00 2.87E+05 9.76E+04 1.04E+04 CS-1 37 4.79E+05 6.21E+05 4.28E+05 0.OOE+00 2.23E+05 7.52E+04 8.40E+03 DOSE FACTOR TABLE: R(i) - Teen, inhalation, Units are mrem/yr per pCi/m 3 Nuclide Bone Liver Tbody Thyroid Kidney Lung GI tract H-3 0.OOE+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 FE-55 3.35E+04 2.39E+04 5.55E+03 -0.00E+00 0.OOE+00 1.24E+05 6.39E+03 CO-60 0.OOE+00 1.51E+04 1.98E+04 0.OOE+00 0.OOE+00 8.72E+06 2.59E+05 SR-90 1.08E+08 0.OOE+00 6.68E+06 0.0OE+00 0.OOE+00 1.65E+07 7.65E+05 CS-134 5.03E+05 1.13E+06 5.49E+05 0.OOE+00 3.75E+05 1.46E+05 9.76E+03 CS-137 6.71E+05 8.48E+05 3.11E+05 0.OOE+00 3.04E+05 1.21E+05 8.48E+03 DOSE FACTOR TABLE: R(i) - Child, inhalation Units are mrem/yr per uCi/m 3 Nuclide Bone Liver Tbody Thyroid Kidney Lung GI tract H-3 0.OOE+00 1.13E+03 1.13E+03 1.13E+03 1.13E+03 1.13E+03 1.13E+03 FE-55 4.74E+04 2.52E+04 7.77E+03 0.OOE+00 0.OOE+00 1.11E+05 2.87E+03 CO-60 0.OOE+00 1.31E+04 2.27E+04 0.OOE+00 0.OOE+00 7.07E+06 9.62E+04 SR-90 1.01E+08 0.OOE+00 6.44E+06 0.OOE+00 0.OOE+00 1.48E+07 3.44E+05 CS-134 6.51E+05 1.01E+06 2.25E+05 0.OOE+00 3.31E+05 1.21E+05 3.85E+03 CS-1 37 9.07E+05 8.25E+05 1.28E+05 0.OOE+00 2.82E+05 1.04E+05 3.62E+03 DOSE FACTOR TABLE: R(i) - Infant, inhalation Units are mrem/yr per uCi/m 3 Nuclide
'Bone Liver Tbody Thyroid Kidney Lung GI tract
.H-3 FE-55 CO-60 SR-90 CS-134 CS-137 0.OOE+ý00 1.97E+04 0.OOE+O0 4.09E+07 3.96E+05 5.49E+05 6.47E+02 1.18E+Q4 8.03E+03 0.00E+00 7.03E+05 6.12E+05 6.47E+02 3.33E+03 1.18E+04 2.59E+06 7.45E+04 4.55E+04 6.47E+02 O.OOE+00 0.OOE+00 0.OOE+00 01.OOE+00 0.OOE+00 6.47E+02 0.OOE+00 O.OOE+00 0.OOE+00 1.90E+05 1'.72E+05 6.47E+02 8.70E+04 4.51 E+06 1.12E+07 7.97E+04 7.13E+04 6.47E+02 1.1OE+03 3.19E+04 1.31 E+05 1.33E+03 1.33E+03 Page 1 of 1
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19.
TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 42 of 50 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Number of Channels Instrument Operable Action
- 1. Flow Measurement Devices Waste Water Flow Rate and Totalizer (FIRQ95108)
Temporary Tank Discharge Flow Rate device to be installed prior to release I
1 With the flow measurement device inoperable, effluent releases via this pathway may.
continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during temporary tank releases by a level device in the discharge stream.
With the flow rate measurement device inoperable, effluent releases via this pathway may continue provided that the temporary tank discharge flow rate is estimated using the Waste Water Flow Rate instrument.
Page 1 of 1
MANUAL:,
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 43 of 50 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.
Instrument Channel Check Instrument Channel Calibration I
Instrument Channel Test I 1 Flow Monitors Waste Water Flow Rate and Totalizer (FIRQ95108)
Temporary Tank Discharge Flow Rate R
R Q.
Q Table Notation (1) The Instrument Channel Check shall consist of verifying indication of flow during periods of release. The Instrument Channel Check shall be made at least once daily on any day in which batch releases are made.
Page 1 of 1
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19
- TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 44 of 50 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit of Liquid Release Sampling Minimum Analysis Detection (LLD)(a)
Type Frequency Frequency Type of Activity
(
)Ci/ml)*
Each Batch Each Batch H-3 1.00 E-05 Temporary P
P Co-60 4.00 E-09 Tank(b'c'd)
Cs-134, Cs-137 3.00 E-09 Each Batch Composite(e)
Sr-90 1.00 E-09 P
M Gross Alpha 1.00 E-07 Table Notation (a)
- 1. The Lower Limits of Detection (LLDs) for the radionuclides presented in this table are the smallest concentrations (expressed in microcuries. per milliliter) which are required to be, detected, if present, in order to achieve compliance with the limits of Step 6.11.2 (10 CFR 50, Appendix I) and assurance of compliance with the limits of Step 6.11.1 (10 CFR 20, Appendix B, Table 2, Column 2) for a Temporary TankDischarge.
- 2. The LLD of aradioanalysis 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 are taken as equal at 0.05. The general equation for estimating the maximum LLD in microcuries per milliliter is given by the following:
271
+ 3.29 X Sb'
/ts LLD=
Where:
(3.70 E + 04)(Y x E x V)e(-Xtc) 2.71 3.29 factor to account for Poisson statistics at very low background count rates two times the constant used to establish the one sided 0.95 confidence interval 3.70 E+04 =
disintegrations/second/microcurie Y
yield of radiochemical process, i.e., the product of all factors such as emission fraction, chemical yield, etc.
E c.ounting efficiency (count/disintegrations)
Page 1 of 2
MANUAL:
CHEMISTRY-ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 45 of 50 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)
Table Notation (Continued)
V
.= sample volume (milliliters) 2,
=
the radioactive decay constant for the particular nuclide (seconds1)
- t.
=
the elapsed time from midpoint of collection to the midpoint of counting Sb the standard deviation of the background counting rate B
B Sb
=
+
- Ytbt, tb Where:
B.
background counts tb
=
background counting interval (seconds) t,
=
sample counting interval (seconds)
- 3. The LLD is defined as an a priori (before the fact) estimate and is not to be calculated for each sample analyzed on an a posteriori (after the fact) basis.
(b)
A batch release is the discharge of liquid wastes of discrete volume from the temporary tank(s).
(c)
A Temporary Tank will be isolated and its contents thoroughly mixed to assure representative sampling.
(d)
Isotopic peaks which are measurable and identifiable from a temporary tank sample analysis shall be reported and included in ODCM evaluations. Nuclides which are not observed in the analysis shall be reported as "less than" the nuclide's a. posteriori minimum detectable concentration and shall not be reported as being' present. The "less than" results shall be considered "zero" for the purposesof ODCM evaluations; however, if a nuclide is measured and identified at a value less than the Attachment 9 LLD value, it shall be reported and entered in ODCM evaluations.
(e)
A composite sample shall be obtained by mixing liquid aliquot volumes in proportion to the volume of liquid released from each temporary tank.
Page 2 of 2
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE:.46 of 50 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Instrument
- 1.
IOSB Reactor Building
- a. Particulate Sampler
- b. Sampler Flow Rate Measurement Device Action These samples are analyzed in accordance with 1.
Only samplers with a calibrated flow-measuring device may be used. 0 Page 1 of 1
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19.
TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 47 of 50 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit of Detection Gaseous Release Sampling Minimum Analysis Type of Activity (LLD) (a)
Type Frequency (b)
Frequency Analysis (jCi/cc)
M (0 Principal Gamma 1.00 E-11 Continuous Particulate Sample Emitters(c)
Reactor Building Continuous M M Gross Alpha (e) 1.00 E-1 1
_ Particulate Sample Sr-90 1.00 E-1 1 1.00 E-6
_Grab Sample M
M (
IOSB Continuous Particulate Sample Principal Gamma 1.00 E-11 Emitters(c)
Table Notation (a), 1. The Lower Limits of Detection (LLDs) for the. radionuclides presented in this table are the smallest concentration (expressed in microcuries per unit volume) which are required to be detected, if present, in order to achieve compliance with the limits of the Specifications in Steps 6.11.5, and 6.11.6.
- 2. 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 are taken as equal at 0.05. The general equation for estimating the maximum LLD in microcuries per cubic centimeter (pCi/cc) is given by the following:
2.7*1
+ 3.29 x S,
/s
. 9 S
LLD =
(3.70 E + 04)(Y x E x V)e(-Xtc) 1
- Page 1 of 3
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 48 of 50 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)
Where:
2.71
=
factor to account for Poisson statistics at very low background count rates 3.29
=
two times the constant used to establish the one sided 0.95 confidence interval 3.70'E+04 =
disintegrations/second/microcurie Y
yield of radiochemical process, i.e., the product of all factors such as emission fraction, chemical yield, etc.
E
=
counting efficiency (count/disintegrations)
V
=
sample volume (cubic centimeters)
X
= the radioactive decay constant for the particular nuclide (seconds-1)
=
the elapsed time from midpoint of collection to the midpoint of counting Sb the standard deviation of the background counting rate 0.5 rB B
Sb
=
Where:
B
=
background counts tb
=
background counting interval (seconds) t,
=
sample counting interval (seconds) 1 Page 2 of 3
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 49 of 50 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)
Table Notation (Continued)
- 3. The LLD is defined as an a priori (before the fact) estimate and is not to be calculated.for each sample analyzed on an a posteriori (after the fact) basis.
(b)
Sample during Dismantlement activities.
(c)
Principal gamma emitters for which the LLD applies are: Co-60, Cs-1 34, and Cs-1 37 for particulate samples. This does not mean only these nuclides will be detected and reported.
Other peaks that are measurable and identifiable shall be reported in the Annual Radioactive Effluent Release Report, pursuant to Step 6.12.1. All peaks, which are measurable and identifiable, shall be reported and entered into the ODCM evaluations. Nuclides, which are not observed for the analysis shall be reported as "less, than" the nuclide's a posteriori minimum detectable concentration and shall not be reported as being present. The "less than" results shall be considered "zero' for the ODCM evaluations; however, if a nuclide is measured and identified at a value less than the Attachment 11 LLD value, it shall be reported and entered into ODCM evaluations.
(d)
A gross beta analysis is performed on a monthly basis for each environmental release particulate sample. If any one. of these samples indicates greater than 1.0 E-1 1 pCi/cc gross beta activity, then an Sr90 analysis will be performed on those samples exceeding this value.
(e)
A gross alpha analysis is performed on a monthly basis for each environmental release particulate sample. This fulfills the requirements of performing a monthly composite.
(f)
Sample during Dismantlement activities.
(g)
This analysis shall be performed until such time that all plant origin liquid sources of Tritiated water have been eliminated. i.e. Radwaste Tanks have been emptied. 1 Page 3 of 3
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 19 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 50 of 50 ODCM REVISION REVIEW REQUIREMENTS ODCM REVISION REVIEW REQUIREMENTS Whenever the ODCM is revised, no matter what the changes are, several reviews must be performed. These reviews must also be documented. The documentation is often included as an attachment to the 50.59 Safety Determination. This form lists the minimum reviews and documentation required for each change. Initial each requirement as it is completed.
Sign the bottom of the form when all review requirements are'completed.
Initials I.
Determination that the level of control of radioactive effluents is being maintained.
This determination is made by review of the following documents:
10 CFR 20.1301 and 20.1302 10 CFR 50.36a
- AppendixIto IOCFR50 40 CFR 190 II.
Determination that the change(s) will not adversely affect the accuracy or reliability of effluent dose calculations or effluent monitor setpoint determinations.
This determination is made by directly reviewing each change to the ODCM. Although each change must be evaluated, changes that directly involve culatio s should be more c a r e f u l l y c o n s i d e r e d.
n 5 i.oo
- 11.
Supporting information.
Full justification including analyses and evalu ens t o\\pp 'rt the change(s) must be included in the review and approval packa IV.
Notification of NRC.
X TeNCis notified ofalchanges C~
by including a complete, legible copy as part of, or concurrent with, the
- nu Rad'l~tive Effluent Release Report (ARERR). To.
ensure inclusion in the ARE ta Iem s'hould be initiated whenever the ODCM is revised.,__
V.
Implementing Th flowing docJ hould reviewed for impact whenever the ODCM is revised:
CAP-0008, QCffit~jases of Radio act ivity in Liquid Effluents CAP-0009, Qiffite Re ts of Radio act iviry in Liquid Effluents CAP-0013, Preparation of the Annual RadioactiveEffluent Release Report CHM-5107, Compositing of Liquid Samples ClAM-5109, Effluent Monitor Alarm Response Procedure VI.
Multidiscipline Review Ensure all areas that may be affected by the revision, or have an interest in the changes made in the rCvisiond are included in the multidiscipline review. Areas that are affected by the 0eCM and could be included in this review arc: Technical Services, Surveillance Scheduler;-Quality Assurance,' Licensing, and Operations.
revieReviewer Signature Date 0HM-122 (Rev. 0)
Page 1 of 1 2 Page.1 of 1
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 ATTACHMENT 2
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES MANUAL TITLE OFFSITE DOSE CALCULATION MANUAL LEAD DEPARTMENT:
NUMBER: CAP-0002 REVISION: 20 PAGE: 1 of 50 EFFECTIVE DATE:
8/15/20.07 SCOPE OF REVISION:
- 1. Eliminate requirement to DP test the Reactor Building filters after maintenance or replacement. Integrity will be verified with effluent sampling
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 2 of 50 TABLE OF CONTENTS SECTION PAGE 1.0 P U R P O S E................................................................................................................................
5 2.0 SCOPE....................................................
......................................................... 5
3.0 REFERENCES
/COMM ITM ENT DOCUM ENTS......................................................................
5 3.1 Comm itment Documents....
5 3.2 Reference Documents.................. :.......................................................................
5 4.0 D E F IN IT IO N S............................................................................................................................
7 4.1 Member of the Public....................................................................................................
7 4.2 Occupational Dose.................................................................................................................
7 4.3 P u b lic D o s e...........................................................................................................................
. 7 4.4 Batch Release..................................................................
................................................ 7 4.5 Continuous Release..................................
........................................................................... 7 4.6 D ilu tio n F lo w................................................................................................
7 4.7 Maxim um Exposed (Hypothetical) Individual..........................................................................
8 4.8 R S N G S..................................................
8 4.9 S ite B o u n d a rie s.........................................................
8 4.10 Nuisance Pathways...........................................................................
. 8 4.11 Unplanned Release........................................................................................................
8 4.12 M iscellaneous Release..........................................................................................................
8 4.1 3 S a fe ty F a cto r (S F )....................................................................................................................
8 4.14 Ventilation Exhaust Treatment System (VETS)...................................................................
9 4.15 Instrument Surveillance.......................................................................................................
9 4.16 Surveillance Intervals......................................................................................................
9
'4.17 Radiological Effluent Information Management System (REIMS).........................................
10 4.18 Operable/Operability............................................................................................................
10 5.0 RESPONSIBILITIES..................................................................................................................
10 5.1 Radiation Protection/Chemistry Superintendent..............................
10 5.2 Comm itment Management Review Group (CM RG).............................................................
10
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 3 of 50 TABLE OF CONTENTS (Continued)
SECTION PAGE 6.0 PROCEDURE.........................................................................................
11 6.1 General Considerations...........................................................................
11 6.2 Maximum Effluent Concentrations in Liquid Effluents...........................
12..........
6.3 Liquid Dose Calculations...........................................................................
14 6.4 Liquid Dose Projections...........................................................................
15 6.5 Maximum Effluent Concentrations (MECs) in Gaseous Effluents..............................
16 6.6 Dose Rate Calculations...........................................................................
17 6.7 Organ Dose Calculations for Gaseous Effluents................................................
18 6.8 Gas Dose Projections..............................................
I.......................
20 6.9 Fuel Cycle Dose....................................................................................
20 6.10 EPA Reporting Requirements...............I......................................................
20 6.11 Technical Requirements..........................................................................
21 6.11.1 Maximum Effluent Concentrations in Liquid Effluents.............................
21 6.11.2 Liquid Dose Calculations.............................................................
22 6.11.3 Radioactive Liquid Effluent Treatment............................................
.-24 6.11.4 Gaseous Effluent Monitoring...........................K............................. 25 6.11.5 Gaseous Dose Rates................................................................ 25 6.11.6 Gaseous Organ Dose.................................................................
26 6.11.7 Ventilation Exhaust Treatment System..............................................
27 6.11.8 Fuel Cycle Dose......................................................................
29 6.11.9 Quarter/Annual Dose Projections...................................................
30 6.12 Reports
.................................................................................... I......31 6.12.1 Annual Radioactive Effluent Release Report (ARERR)...........................
31 6.12.2 30 Day Reports.......................................................................
32 7.0 RECORDS.................................................
I.......... 32
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 4 of 50 TABLE OF CONTENTS (Continued)
ATTACHMENTS ATTACHMENT PAGE 1
DOSE FACTOR PARAMETERS 33 2
ATMOSPHERIC DISPERSION AND DEPOSITION PARAMETERS......................................
36 3
SITE BOUNDARY FOR GASEOUS EFFLUENTS..................................................................
37 4
SITE BOUNDARY FOR LIQUID EFFLUENTS...........................................................................
38 5
ORGAN DOSE FACTORS FOR LIQUID EFFLUENTS........................................................... 39 6
ORGAN DOSE FACTORS FOR GASEOUS EFFLUENTS 41 7
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION......................... 42 8
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SU RV EILLA NC E REQ UIREM ENTS............................................................................. 43 9
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM...........................
44 10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 46 11 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM..........................
47 12 ODCM REVISION REVIEW REQUIREMENTS 50
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 5 of 50 1.0 PURPOSE The Off-site Dose Calculation.Manual (ODCM) contains the methodology and parameters used in the calculation of off-site doses due to radioactive gaseous and liquid effluents.. Methods are described for assessing compliancewith the Technical Requirements in the ODCM as they apply to 10 CFR Parts 20.1301 and 20.1302, 10 CFR Part 50, Appendix 1, 10 CFR 50.36a,and 40 CFR 190.1Oa for liquid and gaseous effluents. Additionally, the ODCM contains the Technical Requirements, which provide the Specifications, Applicability's, Actions, and Surveillance Requirements.
2.0 SCOPE This procedure functions as a manual that provides the basis for development of detailed implementing procedures that address dose calculations for liquid/gaseous releases. Additionally, this manual provides the Technical Requirements that govern releases of liquid and gaseous radioactive releases off-site.
2.1 Currently an installed liquid effluent pathway does not exist. The retention basins, associated valves, controllers and piping, and effluent monitoring instrumentation have been removed, dismantled, or abandoned in place. This was accomplished as part of the Decommissioning process. The main precursor to eliminating the permanently installed equipment and liquid effluent radiation monitor was the elimination of the major liquid effluent source terms.
3.0 REFERENCES
/COMMITMENT DOCUMENTS 3.1 Commitment Documents 3.1.1 Code of Federal Regulations, Title 10, Chapter 1, Parts 20, 50.36a and Part 50, Appendix I 3.1.2 Rancho Seco Quality Manual (RSQM) 3.1.3 EPA 40 CFR Parts 302, 355 Reporting Requirements 3.1.4 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Plant Operations 3.2 Reference Documents 3.2.1 USNRC Regulatory Guide 1.109, Rev. 1, 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, October 1977
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 6 of 50 3.2.2 W. C. Burke, et. al., Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG-0133, USNRC: NRR, October 1978 3.2.3 ORNL, User's Manual for LADTAP II, NUREG/CR-1 276, May 1980 3.2.4 D. L.'Strange, et. al., LADTAP-II, Technical Reference and User Guide, NUREG/CR-4013; Pacific Northwest Laboratory, April 1986 3.2.5 Eckerman, K. F., et. al., User's Guide to GASPAR Code, NUREG-0597, USNRC: NRR, June 1980, in RSIC CCC-463 3.2.6
. USNRC Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors 3.2.7 USNRC Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants 3.2.8 USNRC Regulatory Guide 4.1, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants 3.2.9 REIMS Software Life Cycle Documents (Software Requirement Specification, Design Document, Acceptance Test Plan) 3.2.10 USNRC & Pacific Northwest Laboratory, TDMC Computer Code/Data Collections, XOQDOQ-82, Radiological Assessment Code System Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations 3.2.11 2006 Rancho Seco Biennial Land Use Census 3.2.12 RSNGS DSAR Chapters 11.1-11.5 3.2.13 RSNGS P&ID Drawing M-563, M-551, M-552 3.2.14 Pacific Northwest Laboratory, XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations 3.2.15 Congel, F. J., Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190), NUREG-0543, USNRC: NRR, February 1980 3.2.16 USNRC Generic Letter, 89-01, Dated January 31, 1989.
3.2.17 Rancho Seco REMP Manual 3.2.18 PDQ 92-063
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 7 of 50 3.2.19 RP.312.1.14, Occupational Radiation Exposure Limits and Extensions 3.2.20 DQ 99-0061, 50.59 Rev. 1, Kurtz probe flow out of tolerance.
3.2.21 DQ-99-0053, SP.625A failed due to excessive system flow.
4.0 DEFINITIONS 4.1 Member of the Public Means any individual except when that individual is receiving an occupational dose.
4.2 Occupational Dose Means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose received from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public.
4.3 Public Dose Means the dose received by a Member of the Public from exposure to radiation and/or radioactive material released by a licensee, or to any other source of radiation under the control of a licensee. It does not include occupational dose or doses received from background radiation, as a patient from medical practices, or from voluntary participation in medical research programs.
4.4 Batch Release:
Liquid Batch Release is a transfer of a discrete yolume of radioactive liquid from a temporary tank to the Waste Water discharge canal (the Environmental Release Point).
A Gaseous Release is the discharge of gaseous radioactive wastes that consist of tritium and/or radionuclides in particulate form.
4.5 Continuous Release A continuous radioactive gaseous release is the discharge of gaseous waste during dismantlement activities.
Continuous radioactive liquid releases are not planned to be made from Rancho Seco Nuclear Generating Station (RSNGS).
4.6 Dilution Flow The volume or volume rate of fluid (liquid), which is added to a radiological release stream for the purpose of decreasing the concentration of the stream..
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 8 of 50 4.7 Maximum Exposed (Hypothetical) Individual The Maximum Exposed Individual is characterized as "maximum" with regard to food consumption, occupancy, and other usage or exposure pathway parameters in the vicinity of Rancho Seco that would represent an individual with habits greater than usually expected for the average of the population in general.
Maximum dose factor parameters will be determinedi using site-specific data from the Biennial Land Use Census. If information needed to determine a parameter is not available, RG 1.109 parameters will be used. All dose factor parameters used are listed in Attachment 1.
4.8 RSNGS Rancho Seco Nuclear Generating Station 4.9 Site Boundaries The Site Boundaries are defined by the drawings in Attachments 3 and 4.
4.10 Nuisance Pathways (1)
Secondary system gaseous pathways where the calculated dose totals contribute less than 5% of the annual limits and do not need to be tracked for dose calculational purposes unless secondary activity reaches a predetermined Action Level.
(2)
Sources of trace levels of radioactivity in liquid effluents where the calculated dose totals contribute less than 1% of the annual limits and do not needto be tracked for dose calculational purposes. Trace levels are defined to be less than 1 E-8 pLCi/ml for the nuclides typically released from RSNGS. Examples include the plant effluent inlet, and storm drains.
4.11 Unplanned Release The unexpected release of radioactive materials to unrestricted areas in gaseous and liquid effluent. All unplanned releases shall be discussed inthe Annual Radiological Effluent Release Report (ARERR) to the NRC.
4.12 Miscellaneous Release Release pathways, which are considered planned but are not defined explicitly with monitoring requirements in this procedure. These pathways contribute a relatively small percentage (<5%) to the annual dose limits but shall be tracked for effluent activity accounting and dose calculation purposes. Miscellaneous releases shall not be reported in the ARERR as abnormal or unplanned releases. The lOS Building is an example of a Miscellaneous Release.
4.13 Safety Factor (SF)
A number greater than unity used in calculations to introduce greater conservatism (larger margin of safety) to offset various uncertainties in instrumentation and methods.
Radiation Protection/Chemistry Supervision based on either analysis or professional judgment sets safety factors. Unless otherwise specified, the default value is two (2).
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 9 of 50 4.14 Ventilation Exhaust Treatment Systemn (VETS)
The Ventilation Exhaust Treatment System is the Reactor Building Purge Exhaust Filtering System. This system is designed and installed to reduce radioactive material in exhaust gases through filters for the purpose of removing particulates from the gaseous exhaust stream prior to the release to the environment.
4.15 Instrument Surveillance (1) Source Check A source check is the qualitative assessment, of channel response when the channel sensor is exposed to a radioactive source.
.(2) Channel Test A channel test is the injection of an internal or external test signal into the channel to verify its proper response, including alarm and/or trip initiating action, where applicable.
(3) Instrument Channel Check An instrument channel check is a verification of acceptable instrument performance by observation of its behavior and/or state; this verification includes comparison of output and/or state of independent channels measuring the same variable.
(4) Instrument Channel Calibration An instrument channel calibration,* is a test, and adjustment (if necessary), to establish that the channel output responds with acceptable range and accuracy to known values of the parameter, which the channel measures, or an accurate simulation of these values.
Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include the channel test..
4.16 Surveillance Intervals The Surveillance Interval may be extended to a maximum of +25% to accommodate operations scheduling. The frequency notation (which follows the name of the Surveillance Interval in parenthesis) specified for the performance of Surveillance Requirements shall correspond to the Surveillance Intervals defined below.
(1) Shift (S):
A time period covering at least once per twelve (12) hours.
(2) Daily (D):
A time period spaced to occur at least once per twenty four (24) hours.
(3) Weekly (W):
A time period spaced to occur at least once per seven (7) days.
(4)
Monthly (M):
(4) Mnthly(M):
A time period spaced to occur at least once per thirty one (31) days.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 10 of 50 (5)
Quarterly (Q):
A time period spaced to occur at least once per ninety two (92) days.
(6)
Semiannually (SA):
A time period spaced to occur at least once per six (6) months.
(7)
Annually (A):
A time period spaced to occur at least once per twelve (12) months.
(8)
Refueling Interval (R):
A time period spaced to occur at least once per eighteen (18) months.
(9)
Each Release (P):
This surveillance will be completed prior to each release.
4.17 Radiological Effluent Information Management System (REIMS)
The computer software and database that tracks the volume and activity of released radioactive effluents. In addition, the software provides the basis for the permitting process, calculates dose to man, and summarizes data for inclusion into the ARERR.
4.18 Operable/ Operability A component or system is Operable when it is capable of performing its intended function within the required range. The component or system shall be considered to have this capability when: (1) it satisfies the Specifications in'Section 6.11, (2) it has been tested periodically in accordance with the Surveillance Requirement in Section 6.11 and has met its performance requirements, (3) the system has available its source of power, and (4) its required auxiliaries are maintained available and capable of performing their intended function.
5.0 RESPONSIBILITIES 5.1 Radiation Protection/Chemistry Superintendent It is the responsibility of the Radiation Protection/Chemistry Superintendent for the following:
- 1) ODCM Revisions and Reporting the Revisions in the Annual Radioactive Effluent Release Report (ARERR)
- 2) ARERR Preparation and Submittal
- 3) REIMS Database
- 4) LADTAP, GASPAR, and XOQDOQ Computer Program Verifications and Changes 5.2 Commitment Management Review Group (CMRG)
The CMRG is responsible for reviewing and accepting all changes to the ODCM with approval by the Plant Manager per the Rancho Seco Quality Manual.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 11 of 50 6.0 PROCEDURE 6.1 General Considerations 6.1.1 Liquid Effluent Pathways The liquid effluent discharge. of RSNGS forms the headwaters of Clay Creek.
Dilution of the liquid effluent occurs off-site in the seasonal creek (No Name Creek) just downstream of the Plant Outfall, which then joins Clay and Hadselville Creeks, and of Hadselville and Laguna Creeks, and at the confluence of Laguna Creek and the Cosumnes River.
Planned radioactive liquid releases (if necessary) will be directed through temporary tanks and piping to give reasonable assurance of compliance with 10 CFR 50 Appendix I prior to their discharge. Prior to discharge from the temporary system to the plant effluent (off-site),
the discharge rate from the temporary system and the amount of dilution from Folsom South Canal are controlled to ensure compliance with the concentration requirements in 10 CFR 20.
6.1.2 Gaseous Effluent Pathways Airborne radioactive material in the Reactor building at RSNGS is routed and discharged in airborne effluent after passing through filters. Unplanned Releases shall be evaluated on a case-by-case basis. The Interim On-site Storage (lOS) Building is a Miscellaneous Release.
6.1.3 Meteorological Data The atmospheric dispersion (X/Q) and deposition (D/Q) factors used in calculations involving airborne effluent are conservative default values. The default X/Q value is 1.0E-4 3
-2 sec/m, and the default D/Q value is 1.0E-6 mi. These factors should be used to determine monitor set points, assess compliance with the gaseous effluent requirements in Section 6.11, and calculate the gaseous effluent dose reported in the ARERR. Attachment 2 shows actual dispersion and deposition factors and is presented for historical information only.
6.1.4 Boundaries The Site Boundary for Gaseous Effluents as shown in Attachment 3 is for all calculations involving gaseous effluents. The Site Boundary for Liquid Effluents as shown in Attachment 4 is for all calculations involving liquid effluents.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 12 of 50 6.1.5 40 CFR 190 Compliance For the purposes of assessing compliance with 40 CFR 190, the MEMBER OF THE PUBLIC which received the most exposure may be determined using actual food consumption, actual occupancy rates, and dilution off-site from additional converging streams (verses assumptions used for a HYPOTHETICAL MAXIMUM EXPOSED INDIVIDUAL based on Biennial Land Use Census data).
6.1.6 Computers vs. Manual Calculations Computer systems such as REIMS should be used for calculations in order to minimize error and hasten the release process. However, in the event computers are not available for calculations, manual pre-release calculations should be done based on the most historically restrictive receptor.
6.2 Maximum Effluent Concentrations in Liquid Effluents The Maximum Effluent Concentration Fraction is calculated to determine compliance with 10 CFR 20 requirements and the Specification in Step 6.11.1. Radioactive liquid effluent discharges normally originate in onsite temporary tank. Samples are collected and analyzed from each temporary tank prior to discharge to ensure that compliance with the Specification in Step 6.11.1 can be achieved.
In addition, calculations to determine the minimum dilution water flow rate and maximum temporary tank discharge flow rate to ensure compliance are provided in this section. Any combination of minimum dilution flow rate and maximum discharge flow rate, which satisfy the Specification, is acceptable.
6.2.1 Maximum Effluent Concentration Fraction (MECF)
Compliance with the Specification in Step 6.11.1 is anticipated when the MECF is less than or equal to 1.0. The MECF is calculated as follows:
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 13 of 50 LC \\.ME-i' Fc + Fr Where:
MECF =
The calculated fraction of Maximum Effluent Concentration in the radioactive liquid effluent discharged beyond the Site Boundary for Liquid Effluents (see Attachment 4).
Ci
=
The concentration (prior to dilution) of radionuclide i in the batch of liquid effluent in pCi/ml.
MECi
= The M EC of radionuclide i from Appendix B to 10 CFR Part 20, Table 2, Column 2, in pCi/ml. The class with the most restrictive Effluent Concentration will be used for each isotope.
Fr
= Discharge flow rate; the flow rate of the radioactive liquid batch release from the temporary tank to the Waste Water Discharge Canal (Plant Effluent) in gpm.
Fc
=
The total available dilution water (Plant Effluent) flow rate. at the time of discharge of the radioactive liquid effluent in gpm.
6.2.2 Minimum Dilution Water Flow Rate (Fcmin.
The minimum dilution water (Plant Effluent) flow rate (Fcmin) is calculated as follows:
F r,
= Fx SF x
{MEQCi} )
i]
NOTE SF X Z i(Ci/MEC,) must be _> 1.0 Where:
Fr
= A fixed effluent discharge flow (gpm) (as required by specific release restrictions).
SF
=
A factor which may be applied to incorporate a margin of conservatism (SF > 1).
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 14 of 50 6.2.3 Maximum Effluent Discharge Flow Rate (Frrna The maximum effluent discharge flow rate (Frmax) is calculated as follows:
F,._ =
[SF 5< yCED Where:
F,
=
A fixed dilution water flow rate (gpm) (as required by specific release restrictions).
NOTE SF X Y_
i(C,/MECi) must be >Ž 6.3 Liauid Dose Calculations This section provides the methodology to demonstrate compliance with the Specification in Step 6.11.2.
Site-specific organ dose factors for liquid effluents have been determined for the MAXIMUM EXPOSED INDIVIDUAL and are listed in Attachment 5. Dose factors.(Aijap) were derived using equations and methods inRegulatory Guide 1.109, Rev. 1 and LADTAP. The dose factor parameters used are listed in Attachment 1. As previously stated, site specific parameters should be used based on the Biennial Land Use Census in lieu of the values provided in RG 1.109 whenever possible.
The exposure pathways included in the Aijap are those identified by the Biennial Land Use Census. The pathways considered for inclusion are:
Fresh water fish Fresh water invertebrate
° River shoreline deposits Milk from cows that eat fresh or stored forage irrigated with Clay Creek water
" Meat from cows that eat fresh or stored forage irrigated with Clay Creek water Vegetation
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 15 of 50 6.3.1 Liquid Effluent Dose Equation Z Z(Qi x Aijap)
Daj i
p F
Where:
Daj Annual calculated dose (50 year dose commitment) to the organ (or total body)j of a maximally exposed individual of age group a (mrem/yr).
Q
=
Activity of isotope i released during the year (Ci/yr).
Aijap
=
Site-specific dose factor for an organ (or total body) j for a person of age group a via pathway p due to isotope i (mrem-ft3/Ci-sec).
F
=
Annual average discharge volumetricflow rate (effluent water plus dilution water) in ft3/sec.
Because the dose rate varies linearly with activity release rate, the dose for a shorter period of time (mrem) may be calculated by substituting the activity released (Ci) during that period for Qi in the above equation. However, volumetric flow rates should not be averaged over a period less than a calendar quarter. More conservative flow rates are acceptable.
6.4 Liquid Dose Proiections 31-day dose projections arecalculated to show compliance with the Specification in Step 6.11.3 Quarterly and Annual dose. projections are calculated in compliance with the Specification in Step 6.11.9.
The following equations shall be used:
31-Day Prooection:
D Y D p3
=31 x Yr tyr Quarterly Proiection:
D Qtr DpQtr = 91.3 x t.Qtr Yearly Projection:
Dpyr = 365.25 x DYr tyr
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 16 of 50 Where:
Dp3l=
31-day dose projection.
Dyr
=
Cumulative annual dose to date.
tyr Number of days into the year.
DpQtr
=
Quarterly dose projection.
DQtr
= Cumulative quarterly dose to date.
tQtr
=
Number of days into the quarter.
DpYr
=
Annual dose projection.
6.4.1 Gaseous Effluent Flow Rates Flow rates used in routine gaseous effluent calculations for the pathways listed below are conservative default values. These flow rates should be used to determine monitor set points, assess compliance with the gaseous effluent requirements in Section 6.11, and calculate the gaseous effluent dose reported in the ARERR.
Gaseous effluent release points and maximum design flow rates used at RSNGS are as follows:
Reactor Building Stack 85,000 CFM Interim On-site Storage Building Ventilation 8,050 CFM
- The Interim On-site Storage (lOS) Building is not subject to continuous discharges of radioactivity. Because of the infrequency of a radioactive release, assessment will be done on each release according to administrative procedures.
6.5 Maximum Effluent Concentrations (MECs) in Gaseous Effluents In order to demonstrate compliance with 10 CFR 20.1301, which requires that the total MEC fraction not exceed 1 when averaged over an entire year, the calculation is included in the Annual. Radioactive Effluent Release Report. In addition, a four hour reporting requirement exists when the total MEC fraction exceeds 20 when averaged over one hour per 10 CFR 50.72.. The following provides guidance on how to perform this calculation.
Maximum, Effluent Concentration Fraction (MECF) Equation MECE
=
x F x 4.72E -4. x X/Q x TR~
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 17 of 50 Where:
C
=
The concentration of nuclide i in mCi/cc.
F
=
Maximum design volumetric flow rate in CFM as indicated in 6.5.1.
X/Q
=
A conservative default atmospheric dispersion. factor for a ground level release to a sector at or beyond the Site Boundary for Gaseous Effluents in sec/m 3. The default value in Step 6.1.3 will be used.
MECi
=
The MEC for nuclide i from Appendix B to 10 CFR Part 20, Table 2, Column 2 (pCi/cc). The class with the most restrictive Effluent Concentration will be used for each isotope.
=
If the time of release is less. than one hour, then this value is the duration of the transient in minutes divided by sixty. Otherwise, the Time Ratio (TR) is one. Dimensionless.
4.72E - 4
= The conversion factor in min*m 3/sec*ft3.
6.6 Dose Rate Calculations The Specification in Step 6.11.5 provides a maximum limit on organ dose rate equivalent beyond the Site Boundary for Gaseous Effluents from tritium and all radioactive materials in particulate form with half-lives greater than 8 days. Compliance is,determined by calculating the organ dose rate for the MAXIMUM EXPOSED INDIVIDUAL for the inhalation pathway only.
The organ dose rate resulting from inhalation is calculated with the equation:
Organ:
6-aj (X/Q) x ZZ(Qvi x Raji) v i Where:
DOaj The dose commitment rate to organ j of a person in age group a (mrem/yr)
Raji
=
The factor to convert air concentration of radionuclide i to organ j dose commitment rate of a person in age group an exposed by inhalation (mrem-m 3/pCi-yr). See Attachment 7.
Qv
=
The release rate of radionuclide i (not including Noble Gas nuclides), via effluent vent v during the time of the release (pCi/sec)
X/Q
=
A conservative default atmospheric dispersion factor for a ground level release to a sector at or beyond the Site Boundary for Gaseous Effluents in sec/m3. The default value in Step 6.1.3 will be used.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002.
MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 18 of 50 Exposure to dose rate factors, Raji, for using equation 13 in RG 1.109, Rev. 1, derives inhalation. Tables E-5, E-7, E-8, E-9, and E-10 are assumed to represent the Maximum Exposed Individual in the equation to derive Raji.
6.7 Organ Dose Calculations for Gaseous Effluents The Surveillance Requirement in Step 6.11.6 requires the radiation dose or dose commitment to the Maximum Exposed (Hypothetical) Individual accumulated from exposure to tritium and radioactive 'materials in particulate form having half-lives greater than 8.0 days, that originate in effluent air, be determined at least every month. The radiation dose or dose commitment accumulated during a calendar quarter and a year may not exceed values stated in the Specification in Step 6.11.6.
A person may be exposed to effluent radioactive material of this type in air by inhalation or indirectly via environmental pathways that involve deposition onto vegetation and the ground.
The exposure pathways evaluated will include the following:
p Exposure Pathway 1
Air - inhalation 2
Deposition onto ground - irradiation 3
Deposition ontovegetation - ingestion 4
Deposition onto forage - cow - milk - ingestion 5
Deposition onto forage - meat animal - meat - ingestion 6
Deposition onto forage - goat - milk - ingestion
\\
The equation used to calculate the dose commitment to the Maximum. Exposed (Hypothetical)
Individual from radionuclides other than tritium is:
Daj (X
zx/Q)p x< ZZ(Qv1 x Rajip)l +
'LD./Q~p x Z(Q x
Raijp p=1IL v
j p=2L Ij
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 19 of 50 Where:
p = 1, i.e., air-inhalation, in the first term, and p = 2, 3, 4, 5, and 6 in the second term of the.equation excludes H-3.
Daj
=
The dose commitment to organ j of a person in age group a (mrem)
Qvi The quantity of each radionuclide i, in particulate form having a half-life greater than 8.0 days, in air discharged via effluent stream v (pCi)
X/Q A conservative default atmospheric dispersion factor for a ground level release to a sector at or beyond the Site Boundary for Gaseous Effluents. in sec/m3. The default value in Step 6.1.3 will be used.
D/Q
=
A conservative default deposition factor. A Factor converting a ground-level or building wake discharge in air to deposition on land (m-2). The D/Q value in Step 6.1.3 will be used.
Rajip
=
A factor converting time integrated concentration of radionuclide i in air or deposited on vegetation and/or ground to radiation dose commitment to organ j, including total body, of a. person in age group a who is exposed via pathway p.
When p = 1, representing air-inhalation, Rajip has units of mrem-m 3/4Ci-yr. When p=2, 3, 4, 5 or 6 in the second term of the equation above, representing pathways involving deposition, Rajip has units of mrem-m 2-sec/yr-.tCi. When the radionuclide is H-3, Rajip has units of mrem-m3/4Ci-yr.
Tritium is assumed not to deposit onto vegetation or the ground. Hence, the concentration in vegetation is assumed to be related to the local atmospheric concentration as described in RG 1.109, Rev. 1, Appendix C. The dose commitment to the Maximum Exposed (Hypothetical)
Individual from tritium in gaseous effluent is calculated with the equation:
Daj =3.17E-8 x r(X/Q)P x jQv x Raji,)j Where:
p= 1, 3, 4, 5, and 6 i includes H-3 only X/Q
=
A conservative default atmospheric dispersion factor for a ground level release to a sector at or beyond the Site Boundary for Gaseous Effluents in sec/m 3. The default value in Step 6.1.3 will be used.
3.17E-8 =
years/sec Other terms as defined in previous section.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 20 of 50 Dose factors Rajip for RSNGSare derived using the equations and methods in RG 1.109, Rev.
1, Appendix C. Values of parameters in RG 1.109, Rev.1, Table E-5 are assumed to represent the Maximum Exposed (Hypothetical) Individual unless Land Use Census data justify a different value. Any different values from default values will be justified and added as a table to the ODCM. Values of other parameters recommended in RG 1.109, Rev. 1, including those recommended in the absence of site-specific data, are used in the equations to derive the dose factors. (GASPAR or REIMS may be used to perform the calculations.)
6.8 Gas Dose Proiections 31-Day Dose projections are calculated to show compliance with Step 6.11.9. Quarterly and Annual dose projections are calculated in compliance with the Specification in Step 6.11.9.
The dose projection equations are the same as used for liquid per Step 6.4.
6.9 Fuel Cycle Dose If a calculated dose exceeds twice the limit of the Specification in Step 6.11.2 and 6.11.6 or a level in Table 3 of the REMP Manual is exceeded, an assessment of compliance with the Specification in Step 6.11.8 must be made.
Liquid dose calculations shall be made using the general methodology of Step 6.4. Gas dose calculations shall be made using the general methodology of Steps 6.6 and 6.7. These methodologies are to be used as a guide and strict adherence is not required because the Fuel Cycle Dose Calculation is done to determine the actual dose received, not a hypothetical maximum. Therefore, parameters such as dilution beyond the site boundary and residential shielding may be factored into the calculation.
The total body and organ doses shall be the result of summing the individual contributions from. liquid, gas, and direct radiation sources for the affected Member of the Public.
Irradiation, i.e., exposure to an external source of radiation, directly from the RSNGS normally will be evaluated with the aid of environmental monitoring dosimetry.
6.10 EPA Reportinq Requirements If a calculated dose exceeds the Specification limit of Step 6.11.1, 6.11.2, 6.11.5, or 6.11.6, an assessment of compliance with 40 CFR Parts 302 and 355, Reportable Quantity Adjustment -
Radionuclides, must be made.
This involves determining the maximum quantity of radionuclides released in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and comparing the quantities to the values listed in 40 CFR 302 Appendix B. The "sum of the ratios" method shall be. used to determine compliance. If the "sum of the ratios" is greater than one, the National Response Center shall be notified.
Since Rancho Seco's systems and procedures are set up to normally operate within the above limits, this condition is not expected.to occur, therefore, specific implementation procedures to determine compliance are not required.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 21 of 50 6.11 Technical Requirements 6.11.1 Maximum Effluent Concentrations in Liquid Effluents Specifications:
The concentration of radioactive material released in liquid effluents at any time beyond the Site Boundary for Liquid Effluents (see Attachment 4) shall be limited to the concentrations specified in Appendix B to 10 CFR Part 20, Table 2, Column 2.
Applicability:
This is applicable at all times.
Action:
With the concentration of radioactive material released from the site to areas beyond the Site Boundary for Liquid Effluents exceeding the above. Specifications, immediately restore concentration.within the required limits and report the event in the next Annual Radioactive Effluent Release Report.
Surveillance Requirements:
The radioactivity concentration of each temporary tank to be discharged shall be determined prior to release by sampling and analysis in accordance with Attachment 9.
The results of the temporary tank pre-release sample analyses shall be used with the calculational methods described in Step 6.2 to ensure that the concentration at the point of release is within the limits of the above Specification..
Bases:
This Specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to areas beyond the Site Boundary For Liquid Effluents (see Attachment 4) will be less than the concentration levels specified in Appendix B to 10 CFR Part 20, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures-within the limits of 10 CFR Part 20.1301 to a MEMBER OF THE PUBLIC.
There are no continuous releases of radioactive material in liquid effluents from the plant.
All radioactive liquid effluent releases from the plant are by batch method.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 22 of 50 6.11.2 Liquid Dose Calculations Specifications:
The dose or dose commitment to a MAXIMUM EXPOSED (HYPOTHETICAL) INDIVIDUAL from radioactive materials in liquid effluents released beyond the Site Boundary for Liquid Effluents (see Attachment 4) shall be limited to:
- 1)
Less than or equal to 1.5 mrem to the total body and to less than or equal to 5.0 mremn to any organ during any calendar quarter;, and,
- 2)
Less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ during any calendar year.
Applicability:
At all times.
Action:
With the calculated dose or dose commitment from the release of radioactive materials in liquid effluents exceeding any of the above Specifications, prepare and submit to the Commission within 30 days a Special Report. This Report will identify the cause(s) for exceeding the limit(s) and define the corrective actions to be taken to reduce the releases of radioactive material in liquid effluents and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above Specifications.
Surveillance Requirements:
Cumulative dose assessments associated with the release of radioactive liquid effluent shall be determined by sampling and analysis in accordance with Attachment 9, and calculations performed in accordance with the methodology described in Step 6.4 at the following frequencies:
.1)
Prior to the initiation of a release of radioactive liquid effluent from the temporary tank(s); and,
- 2)
Upon verification of monthly composite analysis results for radioactive liquid
.effluent released from the temporary tank(s).
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 23 of 50 A dose tracking system and administrative dose limits shall be established and maintained.
With the 31-day dose projection in excess of the limits in Step 6.11.2, adjust liquid effluent operating parameters to give reasonable assurance of compliance with the dose limits of this Specification (10 CFR 50, Appendix I dose guidelines) and maintain radioactive liquid releases as low as is reasonably achievable.
Bases:
ODCM Step 6.11.2 is provided to implement the requirements of Sections lI.A, Ill.A, and IV.A of Appendix I, 10 CFR Part 50. This step implements the guides set forth in Section ILA of 10 CFR 50, Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.Aof 10 CFR 50, Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." The dose calculation methodology in this manual implement the requirements in.Section III.A of 10 CFR 50, Appendix I that conformance with the guides of 10 CFR 50, Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated.
The equations specified in this manual for calculatingthe doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "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," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. There is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in finished drinking water that are in excess of the requirements of 40 CFR 141.
The Lower Limits of Detection established in Attachment 9 are based on an estimated maximum annual effluent outflow of 2 million gallons with a minimum annual average flow rate in the plant effluent stream of 6,000 gallons per minute. The temporary tank pre-release and monthly composite Lower Limits of Detection equate to an off-site dose of less than 10 percent of the 10 CFR 50, Appendix I guidelines. These Lower Limits of Detection, along with the dose tracking system, give reasonable assurance that the dose limits prescribed in ODCM Step 6.11.2 (the 10 CFR 50, Appendix I dose guidelines) will be met.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 24 of 50 6.11.3 Radioactive Liquid Effluent Treatment Specifications:
A radioactive liquid effluent treatment process shall be used to reduce the quantity of radioactive materials in liquid effluent prior to their discharge when projected doses due to the liquid effluent beyond the Site Boundary for Liquid Effluents (see Attachment 4), when averaged over 31 days, would exceed 0.25 mrem to the total body or 0.83 mrem to any organ (8.33% of the 10 CFR 50, Appendix I annual guidelines).
ApplicabilitV:
At all times.
Action:
With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days a Special Report, which includes the following information:
- 1)
Explanation of why liquid Radwaste was being discharged without treatment,
- 2)
Action(s) taken to restore treatment capability and, 3).
Summary description of action(s) taken to prevent a recurrence.
Surveillance Requirements:
Doses due to liquid releases to areas beyond the Site Boundary for Liquid Effluents shall be projected prior to each temporary tank release in accordance with the methodology described in Step 6.4.
Bases:
The liquid effluent source term and time constraints for releases have been significantly reduced with the current plant configuration. Use of a radioactive liquid effluent treatment process whenever liquid effluent requires treatment prior to release to the environment, provides reasonable assurance that the releases of radioactive materials in liquid effluent are maintained "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design Objectives given in Section II.D of Appendix I to 10 CFR 50. The specified dose limits are the dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 25 of 50 6.11.4 Gaseous Effluent Monitorinq Instrumentation requirements for gaseous effluent monitoring are presented in Attachment 10.
The lOS Building has a ventilation system in which the effluent release is sampled during work events that generate airborne particulate activity. Operation of the ventilation system produces a negative pressure in the building. Although no planned airborne radioactive releases are anticipated from this pathway, refer to Attachment 11 when sampling the ventilation exhaust.
6.11.5 Gaseous Dose Rates Specifications:
The dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the Site Boundary for Gaseous Effluents (see Attachment 3) shall be limited to the following values:
- 1)
The dose rate limit for tritium and for all radioactive materials in particulate form
-with-half-lives greater than-8days shall be-less than or equal to 1500 mrem/yr to
- any organ.
Applicability:
This is applicable at all times.
Action:
With the dose rate(s) exceeding the above limits, immediately restore the release rate to within the limit(s) specified and report the event in the next Annual Radioactive Effluent Release Report.
Surveillance Requirements:
Obtaining representative samples and performing analyses in accordance with the sample analyses program specified in Attachment 11 shall determine the release rate of radioactive materials in gaseous effluents.
The dose rate due to tritium and all radioactive material in particulate form with half-lives greater than 8 days, released in gaseous effluents, shall be determined to be within the limits of this Specification by using the results of the sampling and analysis program.
specified in Attachment 11 and the methodology described in Step 6.6.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 26 of 50 Bases:
Step 6.11.5 is provided to ensure that the dose rate from gaseous effluents due to inhalation at any time at the Site Boundary for Gaseous Effluents (see Attachment 3) will be within the annual dose limits of 10 CFR Part 20 for MEMBERS OF THE PUBLIC. The annual dose limits are the doses associated with the concentrations of Appendix B to 10 CFR Part 20, Table 2, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual at or beyond the Site Boundary for Gaseous Effluents to annual average concentrations exceeding the dose rate equivalent, on which the limits specified in Appendix B, Table 2 of 10 CFR Part 20 were derived. For individuals who may at times be within the Site Boundary for Gaseous Effluents, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the boundary.
6.11.6 Gaseous Organ Dose Specifications:
The dose or dose commitment to a MAXIMUM EXPOSED (HYPOTHETICAL) INDIVIDUAL from tritium and radioactive, materials in particulate form with half-lives greater than eight days in gaseous effluents released to areas at or beyond the Site Boundary for Gaseous Effluents (see Attachment 3) shall be limited to the following:
- 1) During any calendar quarter, to less than or equal to 7.5 mrem to any organ; and,
- 2) During any calendar year, to less than or equal to 15 mrem to any organ.
Applicability:
This is applicable at all times.
Action:
With the calculated dose or dose commitment from the release of tritium and radioactive materials in particulate form with half-lives greater than eight days in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days a Special Report. This Report will identify the cause(s) for exceeding the limit and define the corrective actions to be taken to reduce the releases and the proposed corrective action(s) to be taken to assure that subsequent releases will'be in compliance with the above annual limits.
Surveillance Requirements:
Cumulative dose contributions for the current calendar quarter and calendar year period shall be determined in accordance with the methodology described in Step 6.7 at least monthly.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 27 of 50 Bases:
Step 6.11.5 is provided to implementthe requirements of Sections II.C, III.A and IV.A of Appendix 1, 10 CFR Part 50. The Specifications are the guides set forth in Section. II.C of 10 CFR 50, Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of 10 CFR 50, Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "As Low As is Reasonably Achievable (ALARA)." The calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of 10 CFR 50, Appendix I that conformance with the guides of 1.0 CFR 50, Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. For individuals who may at times be within the Site Boundary for Gaseous Effluents, the occupancy of the individual will be sufficientlylow to compensate for any increase in the atmospheric dispersion factor above that for the boundary.
The calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109,
"'Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, RevisionI, October 1977 and Regulatory Guide 1.111, ""Methods-for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,""
Revision 1, July 1977. These equations also provide for estimating doses based upon the historical average atmospheric conditions.
The release rate specifications for radioactive materials in particulate form are dependent on the existing radionuclide pathways to man in areas at or beyond the Site Boundary for Gaseous Effluents (see Attachment 3). The pathways which were examined in the development of these calculations are: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
6.11.7 Ventilation Exhaust Treatment System Specifications:
The VENTILATION EXHAUST TREATMENT SYSTEM shall be sampled during dismantlement activities.
The following two conditions shall not exist simultaneous:
(1)
Gaseous waste is being discharged without treatment, and (2)
The projected doses due to gaseous effluent releases from the site (see ), when averaged over 31 days, would exceed 2% of the 10 CFR 50, Appendix I annual dose guidelines (0.3 mrem to any organ, orair doses of 0.2 mrad from gamma radiation or 0.4 mrad from beta radiation).
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 28 of 50 Applicability:
This is applicable at all times.
Action:
If both parts 1) and 2) of the Specification are satisfied, prepare and submit to the Commission within 30 days a Special Report pursuant to Appendix A of the RSQM, which includes the following information:
- a. Explanation of why gaseous Radwaste was being discharged without treatment, and identification of the equipment Or subsystems not OPERABLE and the reason for inoperability.
- b. Action(s) taken to restore the inoperable equipment to OPERABLE STATUS.
- c. Summary description of action(s) taken to prevent a recurrence.
Surveillance Requirements:
Doses due to gaseous releases to areas at and beyond the Site Boundary for Gaseous.
Effluents (see Attachment 3) shall be projected at least once per 31 days in accordance with the methodology and parameters in Step 6.8.
Filter integrity is ensured through effluent sampling Bases:
The operation of the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems are available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents are maintained "as low as is reasonably achievable". The specified limits governing the use of appropriate portions of the systems and the dose design objectives set forth in Sections II.B and II.C of Appendix 1, 10 CFR 50, for gaseous effluents.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 29 of 50 6.11.8 Fuel Cycle Dose Specification:
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 be limited to less than or equal to 25 mrem to the total body or any organ in a calendar year.
ApplIica bil ity:
At all times.
Action:
- 1)
With the calculated doses from the release of radioactive material in liquid or gaseous effluents exceeding twice the limits of Specifications in Steps 6.11.2 and 6.11.76 or exceeding the reporting levels in Table 3 of the REMP Manual,
- calculations shall be made including direct radiation contributions (including outside storage tanks, etc.) to determine whether the above specifications have been exceeded.
- 2)
If the above 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 above limits and includes the schedule for achieving conformance with the above limits. This
- Special Report, as defined in 10 CFR Part, 20.2203(a)(4), 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 r eport. It shall also describe levels of radiation and concentrations of radioactive material involved, and the.cause of the exposure levels or concentrations.
- 3)
If the estimated dose(s) exceed the above limits, and if the release condition resulting in the violation of 40 CFR Part 190 has not already, been corrected, the Special Report shall include a request for a variance in accordance with the provision of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
Surveillance Requirements:
Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Step 6.11.2 and 6.11.5 Surveillance Requirements.
.Cumulative dose contributions from direct radiation (including outside storage tanks, etc.)
shall be determined in accordance with Step 6.9. This requirement is applicable only under the conditions set forth in the above Action statements.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 30 of 50 Bases:
Step 6.11.8 is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the numerical guides for design objective doses of 10 CFR 50, Appendix I or exceeds the reporting levels of the Radiological Environmental Monitoring Program. 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 plant remains within twice the numerical guides for design objectives of 10 CFR 50, Appendix I and if direct radiation (outside storage tanks, etc.) 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 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 with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190 is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation, which is part of the uranium fuel cycle.
6.11.9 Quarter/ Annual Dose Proiections Specifications:
The projected dose contributions from liquid and gaseous effluents for the current calendar quarter and current calendar year shall be calculated according to the methodology in Steps 6.4 and 6.8 at least every 31 days.
Applicability:
At all times.
Action:
With the required dose calculations not being performed, best effort will be exerted to perform the calculations once the deficiency has been identified. Corrective actions will be taken and documented to prevent reoccurrence.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 31 of 50 Surveillance Requirements
- 1)
Liquid Effluents:
Projected dose contributions shall be determined at least every 31 days.
- 2)
Gaseous Effluents:
Projected dose contributions shall be determined at least every 31 days.
Bases:
This step is provided to implement Appendix A of the Rancho Seco Quality Manual. Dose projections provide a means of determining if current release practices will be within the dose limits of 10 CFR 50, Appendix I. Calculating projected dose totals every 31 days.
provides information, which can be used to keep effluent releases "as low as is reasonably achievable".
Calculations performed during the first 15 days of the calendar year or calendar quarter will result in artificially high dose projections, which provide no usable information.
6.12 Reports 6.12.1 Annual Radioactive Effluent Release Report (ARERR)
The ARERR covering the activities of the unit during the previous 12 months shall be submitted within 90 days after January 1 of each year. The report shall include the following:
(1)
Summary of the quantities of radioactive liquid and gaseous effluents released from the unit.
(2)
Summary of solid waste shipped from the unit.
(3)
All unplanned releases of radioactive materials in gaseous and liquid effluents to unrestricted areas shall include a description of the event and equipment involved, cause(s), action(s) taken to prevent recurrence, and consequences.
(4)
Dose or dose commitment assessments to ensure compliance with the specifications in 6.11.2, 6.11.6.
(5)
Complete, legible copy of the entire ODCM and/orREMP Manual if changes occurred during the ARERR reporting period. The copy may be part of the ARERR or sent concurrently.
(6)
The ARERR shall also include events described in 6.11.1, 6.11.3, and 6.11.4.
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 32 of 50 6.12.2 30 Day Reports The following 30-day reports should be submitted if the criteria are met as stated in the following areas:
(1) 6.11.2 - Liquid Dose Calculations (2) 6.11.9 - Liquid Dose Projections (3) 6.11.6 - Gaseous Organ Dose (4) 6.11.9 - Gaseous Dose Projections (5) 6.11.8 - Fuel Cycle Dose 7.0 RECORDS The individual/packaged documents and related correspondence completed as a result of the performance or implementation of this procedure are records. They shall be transmitted to Records Management in accordance with RSAP-0601, Nuclear Records Management.
MANUAL:
CHEMISTRY ADMINISTRATIVE, PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 33 of 50 DOSE FACTOR PARAMETERS CONSUMPTION AND USAGE PARAMETERS PATHWAY Irrigated Stored Vegetables Irrigated Fresh Vegetables Irrigated Milk
,Irrigated Meat & Poultry Fish Other Seafood Invertebrate (Crayfish)
Algae AGE 1.109 DEFAULT Adult Teen Child Infant Adult Teen Child Infant Adult Teen Child Infant Adult Teen Child Infant Adult Teen Child Infant Adult Teen Child Infant Adult Teen Child Infant Adult Teen Child Infant 520 kg/yr 630 kg/yr 520 kg/yr 0 kg/yr 64 kg/yr 42 kg/yr 26 kg/yr 0 kg/yr 310 kg/yr 400 kg/yr 330 kg/yr 330 kg/yr 110 kg/yr 65 kg/yr 41 kg/yr 0 kg/yr RSNGS 520 kg/yr 630 kg/yr 520 kg/yr 0 kg/yr 64 kg/yr 42 kg/yr 26 kg/yr 0 kg/yr 310 kg/yr 400 kg/yr 330 kg/yr 330 kg/yr 110 kg/yr 65 kg/yr 41 kg/yr 0 kg/yr 21 16 6.9 0
kg/yr kg/yr kg/yr kg/yr 5.0 kg/yr 3.8 kg/yr 1.7 kg/yr 0 kg/yr None None None None 730 I/yr 510 I/yr 510 I/yr 330 I/yr 21 kg/yr 16 kg/yr 6.9 kg/yr 0 kg/yr 6.9 kg/yr 5.2 kg/yr 2.2 kg/yr 0 kg/yr 0 kg/yr 0 kg/yr 0 kg/yr 0 kg/yr Water Usage (Drinking Water) 0 I/yr 0 I/yr 0 I/yr 0 I/yr Page 1 of 3
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 34.of 50 DOSE FACTOR PARAMETERS (Continued)
CONSUMPTION AND USAGE PARAMETERS (continued)
PATHWAY Shoreline Recreation Swimming Boating Inhalation AGE 1.109 DEFAULT Adult Teen Child Infant Adult Teen Child Infant Adult Teen Child Infant Adult Teen Child Infant 12 hr/yr 67 hr/yr 14 hr/yr 0 hr/yr None None None None None None None None 8000 m3 8000 m3 3700 m3 1400 m3 RSNGS 200 hr/yr 100 hr/yr 14 hr/yr 0 hr/yr 100 hr/yr 100 hr/yr 14 hr/yr 0 hr/yr 0 hr/yr 0 hr/yr 0 hr/yr
.0 hr/yr 8000 m3 8000 m3 3700 m3 1400 m3 IRRIGATION RATES AND FRACTION OF IRRIGATION 1.109 DEFAULT RSNGS Irrigation Rate 263 liters/m2 /month 263 liters/m2 /month Time field has been irrigated prior to crop of interest Fraction of the year field is irrigated Fraction of animal water intake not obtained from the irrigation system (Irrigated Meat)
Fraction of animal.water intake not obtained from the irrigation system (Irrigated Milk)
- 15 years None None None 15 years None 0
1 Page 2 of 3
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 35 of 50.
DOSE FACTOR PARAM TRANSIT, TRANSFER, A Irrigated Stored Vegetables Holdup Time Irrigated Fresh Vegetables Holdup Time Irrigated Milk Holdup Time Irrigated Meat Holdup Time Transit Time From Time Of Sample To Time Of Release Transit Time To Drinking Water DILUTIONS All Pathways Shore-Width Factor MISCELLANEOUS Fraction Of Leafy Vegetables Grown In Garden Of Interest Fraction Of Produce Ingested Grown In Garden Of Interest Crop Growing Time For Leafy Vegetables Ingested By Man Crop Growing Time For Pasture Grass Crop Yield For Leafy Vegetables Ingested By Man Crop Yield For Pasture Grass ETERS (Continued)
ND HOLDUP TIMES 1.109 DEFAULT 1440 hrs 24 hrs 48 hrs 480 hrs None None 1.109 DEFAULT None 0.2 1.109 DEFAULT 1.0 0.76 60 Days 30 Days 2.0 kg/m 2 0.7 kg/m 2 RSNGS 1440 hrs 24 hrs 48 hrs 480 hrs 72 hrs 0 hrs RSNGS 1 (None)
. 0.2 RSNGS 1.0 0.76 30 Days 30 Days 2.0 kg/M 2 2.0 kg/m 2
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MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 36 of 50 ATMOSPHERIC DISPERSION AND DEPOSITION PARAMETERS GASEOUS EFFLUENT PATHWAYS 1998 CONTROLLING LOCATIONS**
DIRECTION DISTANCE X/Q*
(sec/m 3)
ENE 1038 M 8.1E-06 PATHWAY Inhalation Ground Vegetation Cow Milk Meat Animal Meat Animal Goat Milk Site Boundary for Gaseous Effluents ENE SSW ENE S
SSE SSW NNW 1038 M 670 M 1038 M 195 M 198 M 2500 M 670 M 1.4E-05 8.1 E-06 1.2E-04 1.OE-06 2.1 E-05 D/Q*
(m-2) 4.8E-08 2.8E-08 4.8E-08 3.4E-07 1.7E-09 Based on meteorological data from January 1978 to December 1987.
- Based on 1998 Land Use Census.
Page 1 of 1
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 37 of 50 SITE BOUNDARY FOR GASEOUS EFFLUENTS Page 1 of 1
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 38 of 50 SITE BOUNDARY FOR LIQUID EFFLUENTS Page 1 of 1
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 39 of 50 ORGAN DOSE FACTORS FOR LIQUID EFFLUENTS DOSE FACTOR TABLE: A(i) - Adult Units are mrem/hr ner uCi/ml Nuclide H-3 C-14 FE-55 CO-60 N 1-63 CS-1 34 CS-137 Bone 0.00E+00 3.82E+05 1.18E+04 1.26E+04 3.42E+05 4.44E+05 5.85E+05 Liver 1.21E+01 7.63E+04 8.17E+03 1.61E+04 2.37E+04 1.05E+06 7.98E+05 Tbody 1.21E+01 7.63E+04 1".91 E+03 2.02E+04 1.15E+04 8.59E+05 5.25E+05 Thyroid 1.21 E+O1 7.63E+04 7.29E-04 1.26E+04 O.OOE+00 4.03E+03 6.06E+03 Kidney 1.21E+01 7.63E+04 7.29E-04 1.26E+04 0.00E+00 3.43E+05 2.75E+05 Lung 1.21 E+01 7.63E+04 4.56E+03 1.26E+04 0.00E+00 1.16E+05 9.54E+04 GI tract 1.21E+01 7.63E+04 4.69E+03 7.73E+04 4.95E+03 2.23E+04 2.14E+04 DOSE FACTOR TABLE: A(i) - Teen Units are mrem/hr oer uCi/mI Nuclide H-3 C-14.
FE-55 CO&60 NI-63 SR-90 CS-1 34 CS-1 37 Bone O.OOE+00 5.64E+05 1.37E+04 6.35E+03 4.50E+05 7.40E+06 5.04E+05 6.99E+05 Liver 1.37E+01 1.13E+05 9.69E+03 1.10E+04 3.18E+04 6.16E-03 1.18E+06 9.30E+05 Tbody 1.37E+01 1.13E+05 2.26E+03 1.69E+04 1.53E+04 1.98E+06 5.50E+05 3.26E+05 Thyroid
.1.37E+01 1.13E+05
.7.29E-04 6.35E+03 0.00E+00 6.16E-03 2.03E+03 3.03E+03 Kidney 1.37E+01 1.13E+05 7.29E-04 6.35E+03 0.OOE+00 6.16E-03 3.77E+05 3.18E+05 Lung 1.37E+01 1.13E+05 6.15E+03 6.35E+03 0.00E+00 6.16E-03 1.45E+05 1.26E+05 GI tract 1.37E+01 1.13E+05 4.19E+03 6.71 E+04 5.06E+03 3.85E+05 1.67E+04 1.62E+04 DOSE FACTOR TABLE: A(i) - Child Units are mrem/hr oer uCi/mI Nuclide H-3 FE-55 CO-60 SR-90 CS-134 CS-1 37 Bone O.00E+00 2.40E+04 8.89E+02 1.47E+07 7.61 E+05 1.12E+06 Liver 2.10E+01 1.27E+04 7.51E+03 8.62E-04 1.25E+06 1.07E+06 Tbody 2.10E+01 3.94E+03 2.04E+04 3.93E+06 2.64E+05 1.59E+05 Thyroid 2.1OE+01 1.02E-04 8.89E+02 8.62E-04 2.85E+02 4.25E+02 Kidney 2.10E+01 1.02E-04 8.89E+02 8.62E-04 3.87E+05 3.50E+05 Lung 2.10E+01 7.19E+03 8.89E+02 8.62E-04 1.39E+05 1.26E+05 G I tract 2.10E+01 2.35E+03 3.76E+04 2.97E+05 7.02E+03 7.15E+03 Page 1 of 2
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 40 of 50 ORGAN DOSE FACTORS FOR LIQUID EFFLUENTS (Continued)
DOSE FACTOR TABLE: A(i) - Infant Units are mrem/hr per uCi/ml Nuclide H-3 FE-55 CO-,60 NI-63 SR-90 CS-134 CS-1 37
. Bone 0.OOE+00 5.61 E+02 0.00E+00 1.72E+05 3.91 E+05 1.55E+05 2.32E+05 Liver 1.14E+01 3.63E+02 3.81 E+02 1.06E+04 0.OOE+00 2.89E+05 2.71 E+05 Tbody 1.14E+01 9.69E+01 8.99E+02 5.97E+03 1.05E+05 2.92E+04 1.92E+04 Thyroid 1.14E+01 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 Kidney 1.14E+01 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 7.43E+04 7.27E+04 Lung 1.14E+01 1.77E+02 0.OOE+00 0.OOE+00 0.OOE+00 3.05E+04 2.94E+04 GI tract 1.14E+01 4.61E+01 9.06E+02 5.29E+02 7.22E+03 7.84E+02 8.47E+02 Page 2 of 2
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 41 of 50 ORGAN DOSE FACTORS FOR GASEOUS EFFLUENTS DOSE FACTOR TABLE: R(i) - Adult, inhalation Units are mrem/yr per JCi/m 3 Nuclide Bone Liver Tbody Thyroid Kidney Lung GI tract H-3 O.OOE+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 FE-55 2.46E+04 1.70E+04 3.95E+03 0.OOE+0O 0.00E+00 7.21E+04 6.03E+03 CO-60 0.OOE+00 1.15E+04 1.48E+04 0.OOE+00 0.00E+00 5.97E+06 2.85E+05 SR-90 9.92E+07 0.OOE+00 6.10E+06 0.OOE+00 O.OOE+00 9.60E+06 7.22E+05 CS-134 3.73E+05 8.48E+05 7:28E+05 O.00E+00 2.87E+05 9.76E+04 1.04E+04 CS-137 4.79E+05 6.21E+05 4.28E+05 0.OOE+00 2.23E+05 7.52E+04 8.40E+03 DOSE-FACTOR TABLE: R(i) - Teen, inhalation, Units are mrem/yr per jCi/m3 Nuclide Bone Liver Tbody Thyroid Kidney Lung GI tract H-3 0.00E+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 FE-55 3.35E+04 2.39E+04 5.55E+03 0.OOE+0O 0.OOE+00 1.24E+05 6.39E+03 CO-60 0.OOE+00 1.51E+04 1.98E+04 0.OOE+00 O.OOE+00 8.72E+06 2.59E+05 SR-90 1.08E+08 0.OOE+00 6.68E+06 0.OOE+00 0.OOE+00 1.65E+07 7.65E+05 CS-134 5.03E+05 1.13E+06 5.49E+05 0.OOE+00 3.75E+05 1.46E+05 9.76E+03 CS-137 6.71E+05 8.48E+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 DOSE FACTOR TABLE: R(i) - Child, inhalation Units are mrem/yr per JCi/m 3
- Nuclide Bone Liver Tbody Thyroid Kidney Lung GI tract H-3 0.OOE+00 1.13E+03 1.13E+03 1.13E+03 1.13E+03 1.13E+03 1.13E+03 FE-55 4.74E+04 2.52E+04 7.77E+03 0.OOE+00 O.OOE+00 1.11E+05 2.87E+03 CO-60 0.OOE+00.1.31E+04 2:27E+04 0.00E+00 O.OOE+00 7.07E+06 9.62E+04 SR-90 1.01E+08 0.OOE+00 6.44E+06 0.OOE+00 0.OOE+00 1.48E+07 3.44E+05 CS-134 6.51E+05 1.01E+06 2.25E+05 0.00E+00 3.31E+05 1.21E+05 3.85E+03 CS-137 9.07E+05 8.25E+05 1.28E+05 0.OOE+00 2.82E+05 1.04E+05 3.62E+03 DOSE FACTOR TABLE: R(i) - Infant, inhalation Units are mrem/yr per IJCi/m 3 Nuclide Bone Liver Tbody Thyroid Kidney Lung GI tract H-3 FE-55 CO-60 SR-90 CS-1 34 CS-1 37 0.OOE+00 1.97E+04 0.OOE+00 4.09E+07 3.96E+05 5.49E+05 6.47E+02 1.18E+04 8.03E+03 0.00E+00 7.03E+05 6.12E+05 6.47E+02 3.33E+03 1.18E+04 2.59E+06 7.45E+04 4.'55E+04 6.47E+02 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 6.47E+02 0.OOE+00 0.OOE+00 0.OOE+00 1.90E+05 1.72E+05 6.47E+02 8.70E+04 4.51 E+06 1.12E+07 7.97E+04 7.13E+04 6.47E+02 1.10E+03 3.19E+04 1.31 E+05 1.33E+03 1.33E+03 Page 1 of 1
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 42 of 50 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Number of Channels Instrument Operable Action
- 1. Flow Measurement Devices Waste Water Flow Rate and Totalizer (FIRQ95108)
Temporary Tank Discharge Flow Rate device to be installed prior to release 1
1 With the flow measurement device inoperable, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during temporary tank releases by a level device in the discharge stream.
With the flow rate measurement device inoperable, effluent releases via this pathway may continue provided that the temporary tank discharge flow rate is estimated using the Waste Water Flow Rate instrument.
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MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 43 of 50 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Channel I
Instrument Check Instrument Channel Calibration Channel Test 1
Flow Monitors Waste Water Flow Rate and Totalizer (FIRQ95108)
Temporary Tank Discharge Flow Rate D(1)
R Q
Q R
Table Notation (1) The Instrument Channel Check shall consist of verifying indication of flow during periods of release. The Instrument Channel Check shall be made at least once daily on any day in which batch releases are made.
Page 1 of 1
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 44 of 50 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit of Liquid Release Sampling Minimum Analysis Detection (LLD)(a)
Type Frequency Frequency Type of Activity (pCi/ml)
Each Batch Each Batch H-3 1.00 E-05 Temporary P
P Co-60 4.00 E-09 Tank(b'c'd)
Cs-134, Cs-137 3.00 E-09 Each Batch Composite(e)
Sr-90 1.00 E-09 P
M Gross Alpha 1.00 E-07 Table Notation (a)
- 1. The Lower Limits of Detection (LLDs) for the radionuclides presented in this table are the smallest concentrations (expressed in microcuries per milliliter) which are required to be detected, if present, in order to achieve compliance with the limits of Step 6.11.2 (10 CFR 50, Appendix I) and assurance of compliance with the limits of Step 6.11.1 (10 CFR 20, Appendix B, Table 2, Column 2) for a Temporary Tank Discharge.
- 2. 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 are taken as equal at 0.05. The general equation for estimating the maximum LLD in microcuries per milliliter is given by the following:
2-71t
+ 3.29 x Sb LLD=
Where:
(3.70 E + 04)(Y x E x V)e(-Xtc) 2.71 3.29
= factor to account for Poisson statistics at very low background count rates
=
two times the constant used to establish the one sided 0.95 confidence interval 3.70 E+04 =disintegrations/second/microcurie Y
=
yield of radiochemical process, i.e., the product of all factors such as emission fraction, chemical yield, etc.
E counting efficiency (count/disintegrations)
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CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE-OFFSITE DOSE CALCULATION MANUAL PAGE: 45 of 50 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)
Table Notation (Continued)
V
=
sample volume (milliliters)
- 2.
= the radioactive decay constant for the particular nuclide (seconds 1) to
the elapsed time from midpoint of collection to the midpoint of counting Sb
the standard deviation of the background counting rate 0.5 (B
B Sb
=
+-
Where:
B
=
background counts tb
=
background counting interval (seconds) ts
=
sample counting interval (seconds)
- 3. The LLD is defined as an a priori (before the fact) estimate and is not to be calculated for each sample analyzed on an a posteriori (after the fact) basis.
(b)
A batch release is the discharge of liquid wastes of discrete volume from the temporary tank(s).
(c)
A Temporary Tank will be isolated and its contents thoroughly mixed to assure representative sampling.
(d)
Isotopic peaks which are measurable and identifiable from a temporary tank sample analysis shall be reported and included in ODCM evaluations. Nuclides which are not observed in the analysis shall be reported as "less than" the nuclide's a posteriori minimum detectable concentration and shall not be reported as being present. The "less than" results shall be considered "zero" for the pyrposes of ODCM evaluations; however, if a nuclide is measured and identified at a value less than the Attachment 9 LLD value, it shall be reported and entered in ODCM evaluations.
(e)
A composite sample shall be obtained by mixing liquid aliquot volumes in proportion to the volume of liqbid released from each temporary tank.
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MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 46 of 50 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Instrument
- 1.
IOSB Reactor Building Action
- a. Particulate Sampler
- b. Sampler Flow Rate Measurement Device These samples are analyzed in accordance with 1.
Only samplers with a calibrated flow-measuring device may be used. 0 Page 1 of 1
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE:, 47 of 50 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit of Detection Gaseous Release Sampling Minimum Analysis Type of Activity (LLD) (a)
Type
- Frequency (b)
Frequency Analysis (PCi/cc)
M (0 Principal Gamma 1.00 E-11 Continuous Particulate Sample Emitters(c)
Reactor Building Continuous M (7 Gross Alpha (e) 1.00 E-1 1 I Particulate Sample Sr-90 1.00 E-1 1 1.00 E-6 Grab Sample M
)
M (0 IOSB Continuous Particulate Sample Principal Gamma 1.00 E-1 1 Emitterscc)
Table Notation (a)
- 1. The Lower Limits of Detection (LLDs) for the radionuclides presented in this table are the smallest concentration (expressed in microcuries per unit volume) which are required to be detected, if present, in order to achieve compliance with the limits of the Specifications in Steps 6.11.5, and 6.11.6.
- 2. 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 are taken as equal at 0.05. The general equation for estimating the maximum LLD in microcuries per cubic centimeter (pCi/cc) is given by the following:
2.71*
+ 3.29 x Sb ts LLD =
(3.70 E + 04)(Y x E X V)e(-ktc) 1 Page 1 of 3 d
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL.
REVISION: 20 TITLE OFFSITE DOSE CALCULATION. MANUAL PAGE: 48 of 50 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)
Where:
2.71
=
factor to account for Poisson statistics at very low background count rates 3.29
=
two times the constant used to establish the one sided 0.95 confidence interval 3.70 E+04 =
disintegrations/second/microcurie Y
= yield of radiochemical process, i.e., the product of all factors such as emission fraction, chemical yield, etc.
E
= counting efficiency (count/disintegrations)
V
=
sample volume (cubic centimeters)
- 2.
the radioactive decay constant for the particular nuclide (seconds-1) to
the elapsed time from midpoint of collection to the midpoint of counting Sb=
the standard deviation of the background counting rate 0.5.
Sb
+
týs Where:
B
=
background counts tb
=
background counting interval (seconds) ts
=
sample counting interval (seconds) 1 Page 2 of 3
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 49 of 50 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)
Table Notation (Continued)
- 3. The LLD is defined as an a priori (before the fact) estimate and is not to be calculated for each sample analyzed on an a posteriori (after the fact) basis.
(b)
Sample during Dismantlement activities.
(c)
Principal gamma emitters for which the LLD applies are: Co-60, Cs-134, and Cs-137 for particulate samples. This does not mean only these nuclides will be detected and reported.
Other peaks that are measurable and identifiable shall be reported in the Annual Radioactive Effluent.Release Report, pursuant to Step 6.12.1. All peaks, which are measurable and identifiable, shall be reported and entered into the ODCM evaluations. Nuclides, which are not observed for the analysis shall be reported as "less than" the nuclide's a posteriori minimum detectable concentration and shall not be reported as being present. The "less than" results shall be considered "zero" for the ODCM evaluations; however, if a nuclide is measured and identified at a value less than the Attachment 11 LLD value, it shall be reported and entered into ODCM evaluations..
(d)
A gross beta analysis is performed on a monthly basis for each environmental release particulate sample. If any one of these samples indicates greater than 1.0 E-1 1 pCi/cc gross beta activity, then a Sr90 analysis will be performed on those samples exceeding this value.
(e)
A gross alpha analysis is performed on a monthly basis for each environmental release particulate sample. This fulfills the requirements of performing a monthly composite.
(f)
Sample during Dismantlement activities.
(g)
This analysis shall be performed until such time that all plant origin liquid sources of Tritiated water have been eliminated. i.e. Radwaste Tanks have been emptied. 1 Page 3 of 3
MANUAL:
CHEMISTRY ADMINISTRATIVE PROCEDURES NUMBER: CAP-0002 MANUAL REVISION: 20 TITLE OFFSITE DOSE CALCULATION MANUAL PAGE: 50 of 50 ODCM REVISION REVIEW REQUIREMENTS ODCM REVISION REVIEW REQUIREMENTS Whenever the ODCM is revised, no matter what the changes are, several reviews must be performed. These reviews must also be documented. The documentation is often included as an attachment to the 50.59 Safety Determination. This form lists the minimum reviews and documentation required for each change. Initial each requirement as it is completed.
Sign the bottom of the form when all review requirements are completed:
Initials I.
Determination that the level of control of radioactive effluents is being maintained.
This determination is made by review of the following documents:
10 CFR 20.1301 and 20.1302 I0CFR5036a Appendix I to 10 CFR 50 40 CFR 190 II.
Determination that the change(s) will not adversely affect the accuracy or reliability of effluent dose calculations or effluent monitor setpoint determinations.
This determination is made by directly reviewing each change to the ODCM. Although each change must be evaluated, changes that directly involve Iculatiosn should be more carefully considered.
III.
Supporting information.
Full justification including analyses and evalu ns t pp rt the change(s) must be included in the review and approval packa IV.
Notification of NRC.
A The NRC is notified of all changes/t~hf-*CM by including a complete, legible copy as part of; or concurrent with, the u Ra ctive Effluent Release Report (ARERR). To ensure inclusion in the ARE a
item should be initiated whenever the ODCM is revised.
V.
Implementing The following docutnt-s should *e reviewed for impact whenever the ODCM is revised:
" CAP-0008, itleases of Radioactivity in Liquid Effluents
- CAP-0009, Offsite Relses of Radioactivity in Liquid Effluents CAP-0013, Preparation of the Annual Radioactive Effluent Release Report CHIM-5107, Compositing of Liquid Samples
" CHM-5109, Effluent Monitor Alarm Response Procedure VI.
Multidiscipline Review Ensure all areas that may be affected by the revision, or have an interest in the changes made in the revision, are included in the multidiscipline review. Areas that are affected by the ODCM and could be included in this review are: Technical Services, Surveillance Scheduler, Quality-Assurance, Licensing, and Operations.
All Reviews Complete:
Reviewer Signature Date CHM-122 (Rev. 0)
Page 1 of I Attachment.12 Page 1 of 1
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 2007 ATTACHMENT 3
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL LEAD DEPARTMENT:
RP/ CHEMISTRY REVISION 14 PAGE 1 OF 31 EFFECTIVE DATE:
6/05/2007 REVISION
SUMMARY
- 1.
Removed reference to Retention Basins and R15017A as part of liquid effluent pathway.
They have been removed from the system as part of the Decommissioning process and Final Site Survey.
ý...................-.3Wrc44p>.~
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 14 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 14 PAGE 3 OF 31 LIST OF TABLES TABLE TITLE PAGE 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 14 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 themeans 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 14 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 tw6 mile radius of the site.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 14 PAGE 60OF 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 Site. Currently they is no permanently installed liquid. effluent discharge system.
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 donsumed by humans, or by animals that provide products that are consumed by humans, i.e., milk or meat.
" Exposure from being immersed in air containing radioactive materials as a gas and! or particulates.
" Exposure to the direct radiation from radioactive materials that have been deposited onto surfaces from airborne releases.
0 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.
0 The, consumption by humans of fruit or vegetation grown in soil irrigated with water from the release pathway.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 14 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 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 14 PAGE 8 OF 31 At Rancho Seco, potentially radioactive liquid effluent may be 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 14 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 1. 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 I 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 environm~ental 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 14 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' lieuof 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 1, 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 14 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 ODOM 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 expos ure 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 14 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 PUBLICwill 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 siteor 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 14 PAGE 13 OF 31 6.2 A summary of the results obtained, as a participant in the ICP 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 14 PAGE 14 OF 31 8.1.2 The AREOR shall include summaries and statistical evaluations of the results of the radiological environmental surveillance activities forthe 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 thý 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, Testin.0 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 14 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 1 (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 Evaluating Compliance with 10 CFR 50, Appendix I, Regulatory Guide 1.109 (1977).
9.15 USNRC, Estimating Aquatic 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 14 PAGE 16 OF 31 9.18 USNRC, Performance. Testing and Procedural Specifications for Thermoluminesence Dosimetry: Environmental Applications," 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, Technoloqy, Safety and Costs of Decommissioning a Reference Pressurized Water Reactor Power Station, NUREG/CR-013.0 (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 14 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 Annu~al 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 1, and 40 CFR 190 calculations after releases of any origin.
112.0 SELECTION OF RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS In conjunction with the data base established from the land use census, the requirements of the Perman ently 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 14 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 w.ind 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 thePermanently 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 14 PAGE 19 OF 31 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 14.
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 Grass 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 onc e per Gamma dose. At least once per quarter RADIATION with 2 monitoring quarter devices at-each location
- 3.
'WATERBORNE
- a.
Surface 2Composite 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 collectedý Gamma isotopic and tritium analysis of each sample
_________________fortnightly___________________________
Sample locations are shown in Table 6
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 14 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" ofmaterial 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 in Table 6 Sample locations are shown in Table 6
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 14 PAGE 22 OF 31 Table 2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION, LLD ac.
Airborne Analysis Water Particulate or Fish Food Products Mud and Silt (pCi/I )
Gases (pCi/m 3)
(pCi/ kg-wet)
(pCi/ kg-wet)
(pCi/ kg-wet)
Gross Beta 4
0.01 H-3 2000
.(1000b Mn-54 15 130 Co-60 15 130 1 5 0(e)
Zn-65 30 260 Cs-134 15 (1 0 b) 0.01d 130 60 150 Cs-137 18(1 lb 0.01d 130 60 150
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 14 PAGE 23 OF 31 Table 2 MAXIMUM VALUES FOR THE LOWER LIMIT OF DETECTION, LLD a,c a
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 theprobability 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 =
2.7/t 3.29Sb
, pCi/ I, pCi/kg-wet, or pCi/M 3 3.7E - 2(YEV) exp(-dtc) 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 X
=
radioactive decay constant for the associate nuclide
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 14 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 priori (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.
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
3 is 0.05 pCi/rn. This LLD (0.05 pCi/m ) is a site specific value.
e 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-134 and Cs-137.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 14 PAGE 25 OF 31 Table 3 REPORTING LEVELS FOR REMP MEASUREMENTS Analysis Water Airborne Particulate or Fish Food Products (pCi/I )
Gases (pCi/m n3)
(pCi/ kg-wet)
(pCi/ kg-wet)
H-3 20000 Mn-54 1000 30000 Co-60 300 10000 Zn-65 300 20000 Cs-134 30 10 1000 1000 Cs-137 50 20 2000 2000 Gross Beta 40b 2c Applies to water samples utilized for human consumption only. This value is as specified in 40 CFR 141, 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 s'ample. The value indicated is site specific.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 14 PAGE 26 OF 31 Table 4 TWO LETTER DESIGNATION TO IDENTIFY THE TYPE OF SAMPLE a Letter Designation AG AS FS LV MS RW SW TL WW DW SL Type of Sample Represented Algae Sample Air Sample Fish Sample Garden Vegetation Mud & Silt (Sediment)
Runoff Water Surface Water'b Direct Radiation (Monitoring Badge)
Ground (Well) Water Drinking Water Soil a
b Additional letter designation may be added as sample designators if additional sample types are collected for analysis.
Theportion of precipitation on the land that ultimately reaches streams is considered to be surface water.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 14 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 Q
303.75 to 326.25 NW R
326.25 to 348.75 NNW
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 14 PAGE 28 OF 31 Table 6 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Sample Identification (Former ID)
AIR (Particulates)
RASOlCO (RAHO)
RASO.3MO RASO.7EO RUNOFF WATER RRWO.6MO SURFACE WATER RSWO.7NO RSW1.3F0 (RSWCO)
RSW3.7N0 (RSWBO)
RSW1.8N0 RSWO.3M0 Sample Collection Location Identification Class Frequency IND IND IND IND IND IND CON IND IND Weekly Weekly Weekly Biweekly Monthly Monthly Monthly Monthly Monthly On Site (PAP Building Carport)
On Site (Effluent Discharge)
Meteorological Tower Site Boundary Water Sump Rancho Seco Reservoir Folsom South Canal (Composite Sample)
Confluence of Clay and Hadselville Creeks Effluent Discharge (Composite Sample)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 14 PAGE 29 OF 31 Table 6 (continued)
RADIOLOGICAL ENVIRONMENTALSAMPLING LOCATIONS Sample Identification Sample Collection Location Identification (FormerlID)
Class Frequency GROUND (Well),
WATER RWWO.3EO (RWWAO)
RWWO.8DO IND Quarterly Quarterly Site Well CON Marciel Ranch DRINKING WATER RWD0.1GO RDW1.8FP IND CON Monthly Monthly Industrial Area Drinking Water Source Rancho Seco Lake Drinking Water Source MUD AND SILT (Sediment)
RMSO.3MO RMSO.6MO (RMSEO)
IND IND Quarterly Quarterly Effluent Discharge Site Boundary 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 14 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 RLVXX.XX (RLVFO)
IND CON Semiannually Semiannually Site Boundary Vegetable Irrigation Garden (vegetable samples, depending on availability)
Truck Farm, outside 5 mile radius. (locally grown vegetable samples, depending on availability)
MONITORING DEVICE RTLO.3RO RTLO.3CO RTLO.3NO RTL0.3L0 RTLO.3HO RTLO.4FO RTLO.5CO RTLO.6KO RTL2.7MO RTL8.2KO RTL7.8CO IND IND IND IND IND IND IND IND IND CON CON Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly
- 1
- 2
- 3
- 4
- 5
- 6
- 7
- 11
- 16
- 17
- 18 Rancho Seco Site Rancho Seco Parking Lot Rancho Seco Site Rancho Seco Site Rancho Seco Site SMUD Photovoltaic Facility Rancho Seco Entrance Tokay Substation/ Clay East Rd.
Tipling Residence Elliot Cemetery Sam Jaber Residence
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUAL REVISION 14 PAGE 31 OF 31 Table 6 (Continued)
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Sample Identification Sample Collection Location Identification (Former ID)
Class Frequency MONITORING DEVICE RTL1.8FO RTL1.5MO RTL3.9KO RTL7.4MO RTL3.7NO RTL3.8MO RTL1.9NO RTL1.7FO RTL1.4DO RTL8.OPO RTLO.8DO RTL0.6MO RTL0.3PO RTLO.3NP RTL0.4NP RTL0.5NP RTLO.3QP IND IND IND CON IND IND IND IND IND CON IND IND IND IND IND IND IND Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly Quarterly
- 19 Rancho Seco Lake
- 20 Clay East Road & Kirkwood
- 26 Borden Road
- 30 Herald Fire Department
- 31 Hobay Road
- 33 Folsom South Canal Pumping Station
- 35 Hadselville Creek and Plant Effluent Water
- 43 Rancho Seco Reservoir
- 46 Twin Cities Road (Highway 104)
- 55 Colony Road
- 63 Marciel Ranch
- 65 Site Boundary Irrigated Garden
- 68 West Fence, adjacent to ISFSI
- 88 ISFSI outer Security fence, near inactive West Garden
- 90 ISFSI outer Security fence, NW corner
- 91 ISFSI outer Security fence, NE corner