ML20207D465
| ML20207D465 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/31/1998 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20207D447 | List: |
| References | |
| NUDOCS 9903090360 | |
| Download: ML20207D465 (98) | |
Text
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RANCHO SECO r
NUCLEAR GENERATING STATION j
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LICENSE NUMBER DPR-54 I
i ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 1998
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9903090360 99'0301 PDR ADOCK 05000312 R
PDR 3
RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 1998 TABLE OF CONTENTS 1
INTRODUCTION...............
.. 1 l
l.
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. Unplanned Releases...................
...5 F. Radioactive Effluent Monitoring Instrumentation inoperable for Greater Than 30 Days.
... S l
- 11. ESTIMATION OF ERROR.....
..... 6 J
r llL GASEOUS EFFLUENTS..........
..............7 Table ill-A Gaseous Effluents - Summabon of All Releases.....
..... 8 Table ill-B Gaseous Effluents - Ground Level Releases..
.... 9 Table ill-C Gaseous Effluents - Typical Lower Limits of Detection.......
....... 10 j
i Table lil-D Radiological impact on Man Due to Gaseous Effluents.....
. 11 IV. LIQUID EFFLUENTS.................
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Table IV-A Liquid Effluents - Summation of All Releases.....................
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{
Table IV-B Liquid Effluents.
.14 Table IV-C Liquid Effluents - Typical Lower Limits of Detection.............
.15 Table IV-D Liquid Effluents - Radiological Impact on Man Due to Liquid Effluents..
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V. SOLID WASTE.
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4 ATTACHMENTS
- 1. Off-Site Dose Calculation Manual, Revision 9 TC-01 l
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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 1998 l
INTRODUCTION 1
Rancho Seco Nuclear Generating Station (RSNGS) Unit No.1 is located in Sacramento County, Califomia 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 is a pressurized water reactor supplied by Babcock and Wilcox. The rated capacity is 963 gross megawatts I
electrical. Because of a public vote on June 6,1989, the District shutdown the Rancho Seco Nuclear Generating Station and completed defueling operations on December 8,1989.
i This Annual Radioactive Effluent Release Report (ARERR) provides a summary of gaseous and liquid effluent releases made from Rancho Seco during the period January 1 through December 31,1998. Also presented in this report is the projected radiological impact from these releases and a summary of solid radwaste shipments.
This report has been prepared by the Sacramento Municipal Utility District to meet the requirements of Rancho Seco Technical Specification D6.9.3 and Offsite Dose Calculation Manual (ODCM) Step 6,15. It is presented in accordance with the format of USNRC Regulatory Guide 1.21. The radiation doses r900rted in this ARERR are calculated for a hypothetical individual who receives the maximum possible i
e-posure 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 1. A 40 CFR 190 dose evaluation is not required because radioactive effluent releases did not exceed twice the numerical guideline. of 10 CFR 50, Appendix 1.
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RSNGS ANN'JAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 1998 1.
SUPPLEMENTAL INFORMATION l
1 A. REGULATORY LIMITS & GUIDELINES FOR EFFLUENT RELEASES t
1.
Gaseous Effluents
- a. Noblo Gas dose rate limit at or beyond the Site Boundary for Gaseous Effluents (Offsite Dose
. Calculation Manual (ODCM) Technical Requirement 6.14.6):
500 mrem / year to the total body 3000 mrem / year to the skin b.
Noble Gas air dose limit at or beyond the Site Boundary for Gaseous Effluents (ODCM Technical Requirement 6.14.7, numerical guidelines of 10 CFR 50, Appendix I):
5 mrad per calendar quarter for gamma radiation 10 mrad per calendar quartor for beta radiation 10 mrad per calendar year for gamma radiation 20 mrad per calendar year for beta radiation c.
Dose rate limit at or beyond the Site Boundary for Gaseous Effluents for Tritium and radioactive material in particulate for with half-lives greater than 8 days (ODCM Technical Requirement 6.14.6):
1500 mrem / year to any organ
- d. Dose commitment to a member of the public at or beyond the Site Boundary for Gaseous l
Effluents from Tritium and radioactive material in particulate form with half-lives greater than 8 days (ODCM Technical Requirement 6.14.8, numerical guidelines of 10 CFR 50, Appendix l):
7.5 mrem per calendar quarter to any organ 15 mrem per calendar year to any organ 2.
Liquid Effluonts
- a. The concentration of radioactive material in liquid effluents released beyond the Site Boundary
' for Liquid Effluents shall not exceed the limits of 10 CFR 20, Appendix B, Table 2, Column 2.
This applies to all radionuclides except dissolved or entrained noble gases (ODCM Technical Requirement 6.14.2).
b.
Dose commitment to a member of the public at or beyond the Site Boundary for Liquid Effluents from radioactive materials in liquid effluents shall be limited to (ODCM Technical Requirement 6.14.3, numerical guidelines of 10 CFR 50, Appendix I):
1.5 mrem per calendar quarter to the total body 5 mrem per calendar quarter to any organ 3 mrem per calendar year to the total body 10 mrem per calendar year to any organ 2
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- RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l
JANUARY-DECEMBER 1998 1
B. MAXIMUM EFFLUENT CONCENTRATIONS
- 1. Gaseous Effluents The concentrations listed in 10 CFR 20, Appendix B, Table 2, Column 1 (air) are not directly used in calculations for determining permissible gaseous effluent release rates. The annual dose limits of 10 CFR 20 for unrestricted areas are the doses associated with the concentrations of 10 CFR 20, Appendix B, Table 2. Column 1. ODCM Technical Requirement dose rate limits (mremlyr) 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.
s 2.
Liquid Effluents i
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 j
Maximum Effluent Concentration (MEC) value for each radionuclide detected in the 1iquid l
effluent sample (excluding dissolved or entrained noble gases)is used in the calculations.
C. MEASUREMENT METHODS FOR TOTAL RADIOACTIVITY 1.
Fission and Activatior, Gases Gamma Spectroscopy (HPGe)
Liquid Scintillation (H-3) 2.
Particulates Gamma Spectroscopy (HPGe)
Beta Proportional (Sr-90, gross beta) l Alpha Proportional (gross alpha)
- 3. Liquid Effluents
. Gamma Spectroscopy (HPGe) j Liquid Scintillation (H-3)
Beta Proportional (Sr-90, gross beta)
Alpha Proportional (gross alpha) l NOTE:
HPGe refers to Hyper-Pure Germanium 3
P RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 1998 D. BATCH RELEASES (via monitored pathways) 1.
Liquid (RHUT Releases)
Quarter 1 Quarter 2 Quarter 3 Quarter 4 I
a.
Numbe.r of batch releases 1
1.
0 13 b.
Tots! time period for batch releases (hours) 3 3
20 c.
Maximum time period for a batch release (hours).
3 3
4 4
d.
Average time period for a batch release (hours) 3 3
2 e.
Minimum time period for a batch release (hours) 3 3
.5 2.
Liquid (Retention Basin Discharges) a.
Number of batch releases
'2 1
1 12
- b. Total time period for batch releases (hours) 18 8
8 263 c.
Maximum time period for a batch release (hours) 10 8
8 29 6
- d. Average time period for a batch release (hours) 9 8
8 22 e.
Minimum tirne period for a batch release (hours) 8 8
8 18 f.
Average stream flow during periods of release of effluent into a flowing 17.0 16.3 18.7 18.6 stream (cfs) l NOTE:. The Regenerant Holdup Tanks (RHUTs) are released to the Retention Basins. The Retention Basins are discharged offsite. All 10 CFR 50, Appendix I dose calculations are based on the RHUT releases. All 10 CFR 20 calculations are based on the Retention Basin discharges.
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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT j
JANUARY-DECEMBER 1998 E. UNPLANNED RELEASES I
This section describes unplanned releases of radioactivity in liquid and gaseous effluent.
Gaseous None i
Liauid Nono F.
RADIOACTIVE EFFLUENT MONITORING INSTRUMENTATION INOPERABLE FOR GREATER I
THAN 30 DAYS None i
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i RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 1998 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 effluenis, and solid waste are assumed to be independent, and thus the total error is calculated according to the formula:
Total Error =
gi2 + U2 + G3
"+U i
i where: ci = relative error associated with component i t
Sources of error for gaseous effluents include fan error (flow), grab sampling, collection, filter efficle'ncy, counting, and calibration,
' Sources of error for liquid effluents include RHUT volume, dilution water flow rate, grab sampling, counting, and celibration, Sources of error for solid waste include offsite lab smear analysis, dose rate meter calibration, dose rate meter reading, computer program dose-to-curie calculation, sample volume measurement, gamma spec counting, gamma spec calibration, and waste volume determination.
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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 1998 lit. GASEOUS EFFLUENTS Table lil-A, Gaseous Effluents - Summation of All Releases, provides a detailed summary of gaseous effluent releases per quarter. This table summarizes releases of fission and activation gases, particulates with half-lives greater than 8 days, and tritium. The methodology used to calculate the Percent of ODCM Technical Requirement limit is as follows:
](F )(Avg Rel Rate)(X / Q)(Dose Factor))
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% Tech Req Limit =
x 100%
where:
The fraction of the total number of Curies of nuclide i out of the total curies in that Fi
=
l category for that quarter (unitiess).
NOTE: F always equals 1.0 for H-3 because it is the only nuclide in the category.
i (Total Curies per category per quarter)(1 E + 06 Ci Avg Rel Rate =
(# seconds in the quarter)
X/O = 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, Ll+1.1Mi, 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 11 of this report.
Table ill-B, Gaseous Effluents - Ground Level Releases, provides a complete quarterly summary of the amount of radioactivity (Ci) released per radionuclide in each quarter. Data from continuous and batch releases are provided for fission gases, particulates, and tritium. Data reported for batch releases results only from unplanned releases.
Table lil-C, Gaseous Effluents - Typical Lower Limits of Detection, provides a listing of the typical lower limit of detection (LLD) concentrations in pCi/cc for various radionuclides.
Table ill-D, Radiological Impact on Man Due to Gaseous Effluent Releases, provides a summary of calculated radiation doses delivered to a maximum exposed hypotheticalindividual at the Site Boundary for Gaseous Effluents (actual doses will be assessed in the 1998 Annual REMP Report). The maximum calculated organ dose, gamma air dose, and beta air dose are listed for each quarter along with an annual total. The dose due to direct radiation based on Thermoluminescent Dosimeter (TLD) results is also listed. Presented in this table for each category is a comparison versus ODCM Techn cal Requirement dose limits with the exception of direct radiation measurements.
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i RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT -
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JANUARY-DECEMBER 1998 4
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GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES
' Est. Total
- Unit -
Quarter 1 Quarter 2 Quarter 3 Quarter 4 -
Ener.%-
' A. - Fission & Achvation Gases (i.e. Noble Gases)
- 1. Total Release Ci.
' O.00 E+00 - 0.00 E+00 0.00 E+00 ~ 0.00 E+00 N/Ai
- 2. Average Release Rate for penod pCi/sec. 0.00 E+00 0.00 E+00. 0.00 E+00 - 0.00 E+00
- 3. - Percent of Tech Req limit N/A N/A N/A-
.N/A B. Particulates 1.~ ' Partculates with half-livas>8 days -
Ci 0.00 E+00 0.00 E+00 - 0.00 E+00 ' O.00 E+00 ' 2.3 E+01
- 2. Average Release Rate for period pCirsec 0.00 E+00 0.00 E+00 - 0.00 E+00 - 0.00 E+00 -
3 Percent of Tech Req limit N/A.
N/A
'N/A -
-N/A-4.
Gross Alpha radioactmty' Ci 3.71EM i
.0.00E+00 1.89EM 6.71EM 1
C. Tritium '
- 1. Total Release Ci.
6.08E-01 1.06E+00 - - 6.84E-01 5.22E-01 2.3 E+01 2.
Average Release Rate for penod pCi/sec. 7.82E-02 1.35E-01 8,61E-02 6.57E-02.
l 3.
Percent of Tech Req limit
- 6.62E-04; 1.14E-03 7.29E-04 5.56E-04
' Gross alpha actmty has been determined to be naturally occurring and not the result of the fuel cycle.-
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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 1998 TABLE lil-B GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4
- 1. Fission Gases (i.e., Noble Gases)
None
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ll' NOTE: Batch releases of gaseous effluent are no longer planned to be made from Rancho Seco Nuclear Generating Station.
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u RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
. JANUARY - DECEMBER 1998 i
TABLE lil-C i
- GASEOUS EFFLUENTS - TYPICAL LOWER LIMITS OF DETECTION i
RADIONUCLIDES i LLD (uCi/cc) 1.
2.27 E-10 2.'-
. Fission & Activation Gases:
l
, Krypton-85 :
3.47 E,
- 3. '. Particulates:
r Manganese-54 2,08 E-12 Cobalt-58 2.29 E-12 tron-59 5.89 E-12 i
Cobalt 40 -
. 3.11 E-12
- Strontium-89 2.00 E-15 l
~ Strontium-90 5.00 E-15 Cesiura-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 l
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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 1998 TABLE lil-D RADIOLOGICAL IMPACT ON MAN DUE TO GASEOUS EFFLUENT RELEASES CALCULATED RADIATION DOSES AT THE SITE BOUNDARY FOR GASEOUS EFFLUENTS:
1998 Mn_il Quarter 1 Quarter 2 Quarter Q Ouarter 4 Annual A. Tritium, Particulate 1.
Maximum Organ Dose mrem 1.97 E-02 3.45 E-02 2.22 E-02 1.69 E-02 9.33E-02 (a)
(a)
(a)
(a)
(a)
Percent Tech Req limit 2.63 E-01 4.60 E-01 2.96 E-01 2.25 E-01 6.22E-01 B. Noble Gas 1,
Gamma Air Dose mrad 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Percent Tech Reg limit N/A N/A N/A N/A N/A 2.
Beta Air Dose mrad 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Percent Tech Req limit N/A N/A N/A N/A N/A C. Direct Radiation 1.
Dose (TLD results) mrem 0.00 E+00* 0.00 E+00* 0.00 E+00* 0.00 E+00* 0.00 E+00*
2.
Percent of Tech Req I;mit N/A N/A N/A N/A N/A i
NOTE: The quarterly doses listed above were calculated using dose factors from GASPAR and default meteorological data for cach quarter. Annual doses are the sum of quarterly doses.
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- Child - All Except Bone
- None of the indicator stations indicate significant radiation attributable to Plant operations.
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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 1998 IV. LIQUID EFFLUENTS l
Table IV-A, Liquid Effluents - Summation of All Releases, provides'a detailed sum nary of liquid efiluent
[
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 wasto released prior to dilution and the volume of dilution water used during each quarter.
l The following methodology is used to calculate the Average Diluted Concentration and the Percent of ODCM Technical Requirement Limit in Table IV-A:
n C'-
- % Tech Req Limit = [
MECj.
i.
where:
n
=
The total number of radionuclides identified Ci
=
The average diluted concentration of radionuclide i (Total Release per Category per Quarter in pCi)
I (Total Release Volume (part F in Table IV - A)in ml) l MEC =
The MEC of the ith radionuclide, from 10 CFR 20, Appendix B, Table 2, Column 2 i
The methodology used to calculate the estimated total. error in Table IV-A is presented in Section 11 of this i
,eport.
Table IV-B, Liquid Effluents, provides a complete quarteny 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, i
Table IV-C, Liquid Effluents - Typical Lower Limits of Detection, provides a listing of the typical lower limit of detection (LLD) concentrations in pCi/mi for various radionuclides.
)
i 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 1998 Annual REMP Report). The maximum calculated total body dose and organ r'ose are listed for each quarter along with an annual total. A 1
comparison versus ODCM Technical riequirement dose limits is also presented.
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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 1998 TABLE IV-A
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LIQUID EFFLUENTS - SUMWIATION OF ALL RELEASES Est. Total Unit Quarter 1 Quarter 2 Quarter 3 Quarter 4 Error. %
~ A. Fission & Activation Products
- 1. - Total Release (not including tritium, gases, alpha)
Ci-1.89 E-05.1.86 E 0.00 E 5.36 E-05 2.3 E+01
- 2. - Average diluted concentration during period pCi/ml 5.04 E-12
.5.11 E-12 0.00 E-00 1.28 E-11 3.
Percent of Tech Req limit 5.13 E-04 4.56 E-04 N/A 1.19 E-03 B. Tritium 1.
Total Release Ci 1.85 E-03 0.00 E+00 0.00 E+00 5.50 E-00 2.3 E+01
- 2. Average diluted concentration during period pCi/ml 4.93 E-10 0.00 E+00 0.00 E+00 1.32 E-06 3.
Percent of Tech Reg limit 4.93 E-05 N/A N/A 1.32 E-01 C. Dissolved and Entrained Gases (i.e., Noble Gases) 1.
Total Release Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 N/A
' 2.
Average diluted concentration during period pCi/mi 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 D. Gross Alpha radioactivity 2
1.
Total Release Ci 0.00E+00 0.00E+00 0.00E+00 1.30E-06 2.3 E+01 E. Volume of Waste Released
. Retention Basins (prior to dilution)
Liters 4.35 E+05 4.43 E+05 0.00 E+00 2.85 E+06 5.0 E+00 RHUTs (prior to dilution)
Liters 2.22 E+06 9.95 E+05 1.37 E+06 1.81 E+07 5.0 E+00 F. Volume of dilution water used during period Liters 3.75 E+09 3.63 E+09 3.76 E+09 4.18 E+09 2.0 E+01 Gross Alpha activity from December 1998 Regenerant Holdup Tank composite sample. During December 1998 the RHUT releases were I
comprised of approximately 80% Plant Supply Water. The gross alpha activity observed in the sample is consistent with natural activity found in surface water.
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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY DECEMBER 1998 TABLE IV-B l
LIQUID EFFLUENTS j
Nuclides Released Batch Mode
{
1.
Fission and activation products -
(excludina tritium. cases aloha)
Unit Quarter 1 - Quarter 2 Quarter 3 Quarter 4 Co-60 Ci 3.20 E 2.96 E-06 0.00 E+00 5.94 E-06 j
Sr-90 Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Cs-134 Ci 0.00 E+00 0.00 E+00 0.00 E+00 0.00 E+00 Cs-137 Cl 1.57 E-05 1.56 E-05 0.00 E+00 ' 4.77 E-05
. Total for period (above)
Cl 1.89 E-05 1.86 E-05 0.00 E+00 5.36 E-05
]
2.
Dissolved and entrained cases.
-None j
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NOTE: No continuous releases of liquid radioactive effluent are made from Rancho Seco Nuclear Generating Station.
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. RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l
JANUARY-DECEMBER $998
~ TABLE IV C LIQUID EFFLUENTS - TYPICAL LOWER LIMITS OF DETECTION RADIONUCLIDES BATCH MODE: LLD (uCi/ml) 1.
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 l
Strontium-90 5.00 E-10 Ruthenium-106 1.79 E-08 Silver-110m 1.94 E-09 Antimony-125 5.78 E-09 Ceslum-134 1.93 E-09 Cesium-136 2.23 E-09 Cesium-137 2.30 E-09 Barium-140 7.75 E-09 Cerium-141 3.60 E-09 Cerium-144 1.59 E-08 3.
Dissolved and Entrained Gases:
Krypton-85 4.87 E-07
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RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 1998 TA,BLE IV-D RADIOLOGlCAL IMPACT ON MAN DUE TO LIQUID EFFLUENT RELEASES CALCULATED RADIATION DOSE COMMITMENTS FOR LIQUID EFFLUENTS:
1998-
_ynjt Quarter 1 Qitarter 2 Quarter 3 Ouarter 4 Annual A. Maximum Total Body Dose mrem 6.13 E-03 6.05 E-03 0.00 E+00 9.05 E-02 9.42 E-02 (a)
(a)
(a)
(b)
(b)
Percent Tech Req limit 4.09 E-01 4.04 E-01 N/A 6.03 E+00 3.14 E+00 B. Maximum Organ Cose mrem 1.29 E-02 1.28 E-02 0.00 E+00 1.22 E-01 1.47 E-01 (c)
(c)
(c)
(d)
(d)
Percent Tech Req limit 2.58 E-01 2.56 E-01 N/A 2.45 E+00 1.47 E+00 l
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l Note: The quarterly doses listed above were calculated using dose factors from LADTAP and the j
average dilution flow (cfs) for each respective quarter. Annual doses are the sum of quarterly doses.
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(*) Adult
- ) Child - Total Body (4 Child - Bone (d) Child - Liver 16
e RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY-DECEMBER 1998 V. SOLID WASTE 1
i
.1 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)
)
- 1. Type of Waste:
Volume Total Est. Total (m*)
Activity Error (%)
(Curies) j l
- a. Spent Resins, filter sludges, None N/A N/A evaporator bottoms, etc.
- b. Dry coinpressible waste, ~.
1.96 E+02 2.49 E-02 2.5 E+01 8
contaminated equipment, etc
- c. Irradiated components, None N/A-N/A
]
. control rods, etc.
- d. Other None N/A N/A j
i
- 2. Estimate of major nuclide composition (by type of waste)
- a. N/A b.
Radionuclide Percentage
]
(%)
H-3 0.207 C-14 2.35 Fe-55 10.5
- Co-60 6.27 1
1 Ni-63 44.3 Sr-90 1.36 Sb-125 0.598 Cs-134 0.585 Cs-137 32.8 Pu-238 0.0207 Pu-239 0.0150 Pu-241 0.922 Pu-242 0.0001 Am-241 0.0524 Cm-244 0.0183 l
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- c. N/A j
- d. N/A 8 The volume and activity for this waste type includes 6.7 m' (6.41 E-04 Cl) of waste sent from a waste processor to a disposal site.
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.i RSNGS ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 1998
' 3. Solid Waste Disposition.
Number of Shioments Mode of Transoortation Destination l
25 Highway Envirocare of Utah, Inc.
e t.
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JANUARY'- DECEMBER 1998 i
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I TEMPORARY CHANGE TO BE MADE PERMANLW f? YES X NO IF NOT TO BE MADE PER'MANENT ENTER EXPIRATION DATE:
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4 RECOMMENDED APPROVAL BY MSRC: YES X NO REVIEWED:
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- 013 IIRV. 10 j-t
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 1 of 74 LEAD DEPARTMENT:
EFFECTIVE DATE:
RADIATION PROTECTION / CHEMISTRY 02-10-97 SCOPE OF REVISION:
1.
Changed default flow rate for the ABGLV release pathway to 31,000 cfm, 2.
Changed the total gaseous effluent flow to 152,740 cfm to reflect 1. above; 3.
Added DQ 96-0055 as a reference for the new flow rate; 4
Minor editorial corrections.
8
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MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL e
REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 2 of 74 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE..............
...........................................................................................4 2.0 SCOPE.................
.4
3.0 REFERENCES
/COMMITM. ENT D.OCUMENTS...................................................... 4 o
,J e i 4.0 DEFINITIONS.......
......... 6 5.0 RESPONSIBILITIES........~ :......
.........9 6.0 PROCEDURE....
........ 10 6.1 General Considerations................
. 10 6.2 Liquid Monitor Setpoints.....................................................
........... 12 6.3 Maximum Emuent Concentrations in Liquid Effluents............................
.13 6.4 Liquid Dose Calculations...................
...... 15 6.5 Liquid Dose Projections...........
... 16 6.6 Gaseous Monitor Setpoints...
.17
{
6.7 Maximum Efiluent Concentrations (hECs) in Gaseous Effluents..
.20 6.8 Dose Rate Calculations..................
. 21 1
6.9 Air Dose Calculations.........................
.. 22 i
6.10 Organ Dose Calculations fer Gaseous Effluents..................
........................23 6.I1 Gas Dose Projections....
... 25
{
6.12 Fuel Cycle Dose...................
.. 25 6.13 EPA Reporting Requirements....
. 26 6.14 Technical Requirements..........
.26 6.15 Reports.
.40 i
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7.0 RECORDS..........
...... 41 i
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MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 3 of 74 l
t l
TABLE OF CONTENTS (Continued) 1 1
SECTION PAGE ATTACHMENTS I
LIQUID EFFLUENT FLOW DIAGRAM................................................... 41 l
2 GASEOUS EFFLUENT FLOW DIAGRAM................................................................ 43 3
DOSE FACTOR PARAMETERS..................................................
44 4
ATMOSPHERIC DISPERSION AND DEPOSITION PARAMETERS..........
..47 l
5 SITE BOUNDARY FOR GASEOUS EFFLUENTS.,.
..................................48 6
SITE BOUNDARY FOR LIQUID EFFLUENTS..
...............49 7
HISTORICAL LIQUID SOURCE TERMS...................................
... 50 l
- 8 LIQUID MONITOR DETECTOR EFFICIENCIES..................
............................51 9
ORGAN DOSE FACTORS FOR LIQUID EFFLUENTS...............................
52 4
10 GASEOUS MONITOR DETECTOR EFFICIENCIES.........
.56 11 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS..
..................57 12 - ORGAN DOSE FACTORS FOR GASEOUS EFFLUENTS....
........58 13 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION.................... 60 14 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION
' SURVEILLANCE REQUIREMENTS.....................
......................61 15 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM................. 62 16 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION............ 66 i
17-RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
~
EURVEILLANCE REQUIREMENTS.........
...69 f
18 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM................ 71 l
19 ODCM REVISION REVIEW REQUIREMENTS........................
74 l
4 MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 4 of 74 M
PURPOSE
^
The Off-site Dose Calculation Manual (ODCM) contains the methodology and parameters used in the calculttion ofoff-site doses due to radioactive gaseous and liquid effluents. Also, the ODCM contains the methodology fbr determining effluent monitoring instrumentation alarm / trip setpoints. Methods are described for assessing compliance with the Technical Requirements in the ODCM as they apply to 10 CFR Pans 20.1301 and 20.1302,10 CFR Pan 50, Appendix I, and 40 CFR 190.10a for liquid and gaseous effluents. Additionally, the ODCM contains the Technical Requirements which provide the Specifications, Applicabilities, Actions, and Surveillance Requirements...
- P M
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 and monitor setpoints. Additionally, this manual provides the Technical Requirements that govern releases of Lquid and gaseous radioactive releases off-site.
M REFERENCES / COMMITMENT DOCUMENTS 3.1 Commitment Documents 3.1.1 Code of Federal Regulations, Title 10, Chapter 1, Pans 20,50.36a and Part 50, Appendix I 3.1.2 Rancho Seco Permanently Defueled Technical Specifications (PDTS) 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 svith 10 CFR Pan 50, Appendix I, October 1977 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-U, Technical Reference and User Guide, NUREG/CR-4013, Pacific Nonhwest 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
5 MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 i
PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 5 of 74 3.2.6 USNRC Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Emuents in Routine Releases from Light-Water-Cooled Reactors 3.2.7 USNRC Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity ir. Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Emuents 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 SoRware Life C ci ments (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 Emuent Releases at Nuclear Power Stations 3.2.11 1992 Rancho Seco Land Use Census 3.2.12 RSNGS USAR Chapters 11.1-11.5 3.2.13 RSNGS P&ID Drawing M-563, M-551, M-552, M-503 3.2.14 Pacific Northwest Laboratory, XOQDOQ. Computer Program for the Meteorological Evaluation of Routine Emuent 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 Engineering Calculation Z-RDM-10279, Interim On-site Storage (IOS) Building Emuent Radiation Monitor (R15106) Setpoint Determination 3.2.19 PDQ 92-063 3.2.20 RP.312.I.14, Occupational Radiation Exposure Limits and Extensions 9+
3.2.21 DQ 96-0055, ABGLV flow rate mear.ured above default value
l l
l MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 6 of 74 4A DEFINITIONS 4.1 Member of the Public Member of the Public means any individual except when that individual is receiving an occupational dose.
4.2 Occupational Dose Occuoational Dose nicans the ' dose received by an individual in the course of employment in which the individual's assigriid 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 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 er doses received from background radiation, as a patient from medical practices, or from voluntary participation in medical research programs.
4.4 Batch Release A Liauid Batch Release for 10 CFR 50 Appendix I consideraticas it a transfer of a discrete volume of radioactive liquid from a RHUT to a retention basin. A Liould Batch Release for 10 CFR 20 considerations is a transfer of a discrete volume of radioactive liquid from a retention basin to the Waste Water discharge canal (the Environmental Release Point).
A Gaseous Batch Release is the discharge of gaseous radioactive wastes of discrete volume.
Batch releases for the gaseous pathway are no longer planned.
4.5 Continuous Release A continuous radioactive gaseous release is the discharge of gaseous wastes of a nondiscrete volume from a system the.nay have an input flow during the release. These include the Auxiliary Building Stack (ABS), Auxiliary Building Grade Level Vent (ABGLV), and continuing Reactor Building purges.
Continuous radioactive liquid releases are not planned to be made from Rancho Seco Nuclear Generating Station (RSNGS).
l 4.6 Default Radienuclide Mix A hinorical mixture of radionuclides that may be used to determine monitor setpoints.
l 8
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL L
REVISION: 9 i
L TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 7 of 74 4.7 ' Dilution Flow The volume or volume rate of fluid (liquid or gas) which is added to a radiological release strean for the purpose of decreasing the instantaneous concentration of the stream.
l l
4.8 Maximum Exoosed (Hvoothetical) Individual l
The Maximum Exposed Individual is characterized as " maximum" with regard to food l
consumption, occupancy, and other usage or exposure pathway parameters in the vicinity of l
Rancho Seco that would reprisentAn individual with habits greater than usually expected for l
the average of the popula'tidn in general.
Maximum dose factor parameters will be determined using site specific data from the Land Use
{
Census. Ifinformation needed to determine a parameter is not available, RG 1.109 parameters will be used. All dose factor parameters used are listed in Attachment 3.
4.9 RSNGS -
Rancho Seco Nuclear Generating Station.
. Site Boundaries i
4.10 The Site Boundaries are defined by the drawings in Attachments 5 and 6.
4.11 Nuisance Pathways (1) Secondan/ 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 IE-8 pCi/mi for the nuclides typically released from RSNGS. Examples include the oily water separator, plant effluent inlet, and storm drains.
4.12 Unolanned Release The unexpected release of radioactive materials to unrestricted areas in gaseous and liquid l
effluent. All unplanned releases shall be discussed in the Annual Radiological Effluent Release Report (ARERR) to the NRC.
l i
4 13 Miscellaneous Release I
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%)
l L to the annual dose limits but shall be tracked for effluent activity accounting and dose L
E
.-. _._. _ _._ _._ _.. - - - m _
i l
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 i
PRO'. EDURES MANUAL i
REVISION: 9 TITLE:
, OFF-SITE DOSE CALCULATION MANUAL PAGE: 8 of 74 calculstion purposes. - Miscellaneous releases shall not be reported in the ARERR as abnormal or unplanned releases. The IOS Building is an example of a Miscellaneous Release.
I 4 14 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. Safety factors
,j are set by Radiation Protection / Chemistry Supervision based on either analysis or professional judgment. Unless otherwise specified, the default value is two (2).
i 4 15 Liquid Effluent Radwaste' Treatment System (LERTS)
The Liauid Effluent Radw'aste Treatment System is a system designed to reduce the quantity of radioactive materials in liquid effluents by collecting liquid effluent and providing processing for j
the purpose of reducing the total radioactivity prior to its release to the environment.
4.16 Ventilation Exhaust Treatment System (VETS)
The Ventilation Exhaust Treatment System is the Reactor Building Purge Exhaust Filtering System and Auxiliary and Spent Fuel Building Filter Systems. These systems are designed and installed to reduce radioactive material in exhaust gases through HEPA filters for the purpose of removing particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be Ventilation Exhaust Treatment System components.
4.17 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 l
observation ofits behavior and/or state; this verification includes comparison of output and/or
[
state ofindependent channels measuring the same variable.
1 L
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 i
PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 9 of 74 1
(4) = Instrument Channel Calibration An instrume channel calibration is a test, and adjustment (if necessary), to estabMsh that the channel output reg:nds 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.
1 4.18 Surveillance Intervals 1
The Surveillance Interval $Y 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 l
Surveillance Intervals defined below.
l j
(1) Shift (S): A time period covering at least once per twelve (12) hours.
l (2) Daily (D): A time period spaced to occur at least once per twenty four (24) hours.
l (3). Weekly (%):
A time period spaced to occur at least once per seven (7) days.
I (4) Monthly (M):
A time period spaced to occur at least once per thirty one (31) days.
l (5) Quarterly (Q):
A time period spaced to occur at least once per ninety two (92) days.
i (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) EachRelease(P):
This surveillance will be completed prior to each release.
4.19 Radiolonical Effluent Information Manaaement System (REIMS)
The computer software and database that tracks the volume and activity of released radioactive 3
effluents. In addition, the software provides the basis for the permitting process, calculates dose to man, and summarizes data for inclusion into the ARERR.
'I I
4.20 Operable / Operability
. A component or system is Ooerable when it is capable of performing it's 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 6.14, (2) it has been tested periodically in accordance with the Surveillance Requirement in Section 6.14 and has met its performance i
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.
L 1
7
. - - ~. - -. - - _ _ - -
[ (-
1 MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 i
TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 10 of 74 iQ RESPONSIBILITIES L 5.1 Radiation Protection / Chemistry Superintendent i
L It is the responsibility of the RP/ Chem Superintendent for the following:
1)' ODCM Revisions and Reporting the Revisions in the Annual Radioactive Emuent Release Report (ARERR)
- 2) ARERR Preparation and Submittal i
- 3) REIMS Database *
. ;.'. p
- 4) LADTAP, GASPAR, andKOQDOQ Computer Program Verifications and Changes j
5.2 PRC
\\
The PRC is responsible for reviewing and accepting all changes to the ODCM with approval by i
the Plant Manager per Permanent;y Defueled Technical Specifications.
l l
ftQ PROCEDURE l
6.1 General Considerations i
6.1.1 Liauid Effluent Pathways provides a simplified diagram of the liquid emuent produced by RSNGS. The liquid effluent discharge of RSNGS forms the headwaters of Clay Creek.
. Dilution of the liquid effluent occurs off-site at the confluence of Clay and Hadselville L
Creeks, and of Hadselville and Laguna Creeks, and at the confluence of Laguna Creek and the Cosumnes River.
Planned radioactive liquid releases are directed through the A or B RHUTs to give reasonable assurance of compliance'with 10 CFR 50 Appendix I prior to their discharge to the retention basins (North or South). Prior to discharge from the retention basins to the plant effluent (off-site), the discharge rate from the retention basins 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 l
. Airborne radioactive material in :he various rooms and systems at RSNGS is routed and discharged in airborne effluent as illustrated schematically in Attachment 2. The figure shows l
the functional arrangements of these streams, treatment and controls, radioactivity l
monitoring points, and effluent release points, r-n.
-n
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 11 of 74 Potential release pathways other than those specified in Attachment 2 have been identified.
These release pathways are classified as NUISANCE pathways and include the following:
- 1) Auxiliary Boiler Vents / Reliefs
- 2) Miscellaneous Secondary System Steam Discharges
- 3) Tank Atmospheric Vents l
Past experience his shown'that totals because of the sinall quim,the above release pathways do not tities released and the low concentration of radioactive materials. Therefore, Acti'on Levels may be established for the secondary system concentrations of radio'a'ctive material to trigger when the above routine gaseous emuent releases shall be evaluated for off-site dose impact. The Action Levels shall be based on levels that could contribute more than 5% to the most restrictive yearly dose limit. Action Levels shall be maintained through RSNGS procedures.
Unplanned releases shall be evaluated on a case by case basis.
The Interim On-site Storage (IOS) Building is a miscellaneous release.
p.l.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 sec/m', and the default D/Q value is 1.0E-6 ni. These factors should be used to determine 2
monitor setpoints, assess compliance with the gaseous effluent requirements in Section 6.14, and calculate the gaseous emuent dose reported in the ARERR. contains dispersion and deposition factors calculated using actual meteorological data. These factors should not be used for dose calculations. They are presented for historical information only. The factors are based on a 10-year annual average of meteorological data taken from January 1978 to December 1987. The raw data was converted to X/Q and D/Q factors using the XOQDOQ computer program.
6.1.4' Boundaries The Site Boundary for Gaseous Effluents as shown in Attachment 5 is for all calculations j
involving gaseous effluents. The Site Boundary for Liquid Effluents as shown in Attachment i
6 is for all calculations involving liquid effluents. (Although the RHUTs are used as the dose accountability points for liquid effluents, the dose is considered to be received downstream of the boundary.) _
6.1.5 40 CFR 190 Comoliance 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 4
_~. _ - - - _ _ _ ~ _ _ _ _ _ _ - _. _. - _ _ -
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MANUAL: CHEMISTRY ADMINISTRATIVE -
NUMBER:
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PROCEDURES MANL'AL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 12 of 74 consumption, actual occupancy rates, and dilution off-site from additional converging streams (verses assumptions used for a HYPOTHETICAL MAXIMUM EXPOSED 1
INDIVIDUAL based on Land Use Census data).
6.1.6 Computers vs. Manual Calculations i
h 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. ' ; l 6.2 Liauid Monitor Setooints..
h The High alarm setpoint for the Retention Basin Effluent Discharge Monitor (R15017A) is based upon preventing the limits of the Specification in Step 6.14.2 from being exceeded. When the high alarm level is reached, any effluent discharges in progress are terminated or diverted to the Retention Basins.
A SAFETY FACTOR is included in the setpoint calculations to incorporate a margin of conservatism.
When a batch release is not occurring or the calculated setpoint is so low that it will cause i
spurious alarms, the monitor setpoint should be set close to background without causing 1
spurious alarms or as determined by Radiation Protection / Chemistry Supervision.
)
The conversion factor and setpoint calculations should be performed based on the same
{
radionuclide mix.
J 6.2.1 Conversion Factors for R15017A 1
Provided here is the methodology to determine the conversion factor of counts per minute to i
microcuries per cubic centimeter for the Retention Basin Efiluent Discharge Monitor-i (R15017A). The conversion factor is based on the monitor's efficiency for each nuclide and the abundance of the nuclide. The mix ofisotopes used may be based on the historical mix provided in Attachment 7, current mix in the batch release, or as determined by Radiation Protection / Chemistry Supervision. The mix fraction shall be based on gamma emitting isotopes only.
The following equation shall be used to determine the conversion factor for R15017A:
CF =
[(f, x E )
_i l
Where:
CF =
Ci/cc per cpm
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 13 of 74 fi =
Fraction of nuclide i to total activity of historical mix (Attachment 7) or batch mix E ='
Detector efficiency for nuclide f (cpm /pCi/cc) Attachment 8 i
6.2.2 Hioh Alarm Setooint for R15017A (uCi/ml)
[Cs s
High Alarm (pCi/ ml) =
+ Cbksd e
3 Ci
- i. SF X [ MECp i(
Where:
C, The concentration ofgamma-emitting nuclide g in pCi/ml.
=
Ci The concentration of nuclide i in pCi/ml. This term includes non-
=
gamma emitters MECi = The MEC ofradionuclide 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.
SF A SAFETY FACTOR which may be applied to incorporate a margin of
=
conservatism (SF 21). (Default = 2)
Ca, The background reading of the monitor ( Ci/ml).
=
6.3 Maximum Effluent Concentrations in Liquid Effluents The Maximum Effluent Concentration Fraction is calculated to determine compliance with 10 CFR 20 requirements and the Speci6 cation in Step 6.14.2. Radioactive liquid effluent discharges normally originate in the RHUTs and are discharged into a retention basin. Samples are collected and analyzed from each retention basin prior to discharge to ensure that compliance with the Specification in Step 6.14.2 can be achieved.
In addition, calculations to determine the minimum dilution water flow rate and maximum retention basin discharge flow rate to ensure compliance are provided in this section. Any combination ofminimum dilution flow rate and maximum discharge flow rate which satisfy the Specification is acceptable.
6.3.1 Maximum Effluent Concentration Fraction (hECF)
Compliance with the Specification in Step 6.14.2 is anticipated when the MECF is less than I-or equal to 1.0. The MECF is calculated as follows:
f
e MANUAL: CHEMISTRY ADMINISTRATIVE-NUMBER:
CAP-0002 PROCEDURES MANUAL i
REVISION: 9 TITLE:
OFF SITE DOSE CALCULATION MANUAL PAGE: 14 of 74 i
-y C' 3 F,
MECF.= [
j x
, i (MECis,
F + F, j
i Where:
MECF = The calculated fraction of Maximum Effluent Concentration in the radioactive liquid effluent discharged beyond the Site Boundary for Liquid Effluents (see Attachment 6).
..p Cr
= The concentration (prior to dilution) of radionuclide i in the batch of liquid effluent in Ci/ml.
j MEC; = The MEC 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.
F,
= Discharge flow rate; the flow rate of the radioactive liquid batch release
}
from the retention basin to the Waste Water Discharge Canal (Plant Effluent)in gpm.
F.
The total available dilution water (Plant Effluent) flow rate at the time
=
of discharge of the radioactive liquid effluent in gpm.
__q l
!._ _ _ _ _ _ _ _ _ s n xtCp_(Eg mu st,be_2 Lp_ _ _ _ _ _ _ _ _,j
- 6.3.2 Minimum Dilution Water Flow Rate (F, : )
The minimum dilution water (Plant Effluent) flow rate (Fe) is calculated as follows:
r n
Ci F,, = F, x SF < [,
.s i
, M E Ci,s l
I Where:
F, A fixed effluent discharge flow (gpm)(as required by specific release i
=
restrictions).
SF A factor which may be applied to incorporate a margin of conservatism
=
_(SF21).
L L-p V
1-
L MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
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r r------------------
NOTE i
i l
l' I
l l
SF x IfC;/MECQmust be 21
\\
l 6.3.3 Maximum Effluent Discharne Flow Rate (F - )
The maximum effluent discharge flow rate (F-) is calculated as follows:
p
,r
. lP F. :.
r r.
3 Ci-
,SF x { MECv.
,g is Where:
A fixed dilution water flow rate (gpm)(as required by specific release F.
=
restrictions).
6.4 Liauid Dose Calculations i
This section provides the methodology to demonstrate compliance with the Specification in Step 6.14.3.
Site specific organ dose factors for liquid effluents have been determined for the MAXIMUM EXPOSED INDIVIDUAL and are listed in Attachment 9. Dose factors (Ag.,) were derived using equations and methods in Regulatory Guide 1.109, Rev. I and LADTAP. The dose factor parameters used are listed in Attachment 3. As previously stated, site specific parameters should be used based on the Land Use Census in lieu of the values provided in RG 1.109 whenever possible.
The exposure pathways included in the A;;., are those identified by the Land Use Census. The pathways considered for inclusion are:
e fresh water fish fresh water invertebrate river shoreline deposits e
milk from cows that eat fresh or stored forage irrigated with Clay Creek water e
meat from cows that eat fresh or stored forage irrigated with Clay Creek water Vegetation 6.4.1 Liauid Effluent Dose Eauation I
(((Q x Av.p)
D.; =
F w-,
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
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Annual calculated dose (50 year dose commitment) to the organ (or total D.;
=
body)J of a maximally exposed individual of age group a (mrem /yr).
Qi Activity ofisotope i released during the year (Ci/yr).
=
Site specific dose factor for an organ (or total body)j for a person of age A;;.,
=
group a via pathwayp due to isotope f (mrem-ft'/Ci-sec).
Annual'a'v'erage discharge volumetric flow rate (effluent water plus dilution F
=
water) in ft'/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 n the above equation..However, volumetric flow rates should not be averaged over a i
period less than a calendar quarter. More conservative flow rates are acceptable.
6.5 Liquid Dose Projectio.ns 31-day dose projections are calculated to show compliance with the Specification in Step 6.14.4. Quarterly and Annual dose projections are calculated in compliance with the Specification in Step 6.14.11.
The following equations shall be used:
31-Day Projection:
D' Y
D,y = 31 x I
t y, Quarterly Projection:
D*
D,, = 91.3 x tg Yearly Projection:
D,y, = 365.25 x br.
ty, Where:
D,n 31-day dose projection.
=
Cumulative annual dose to date.
Dy,
=
Number of days into the year.
t y,
=
D,,
=. Quarterly dose projection.
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Cumulative quarterly dose to date.
l Do,
=
Number ofdays into the quarter.
to.
=
i
' Annual dose projection.
D,w.
=
6.6 Gaseous Monitor Setooints i
This step does not apply to the IOS Building vent monitor (R15106). The calculations used to determine the setpoints for,this monitor are contained in Reference 3.2.18.
The Gaseous Effluent Radiation Monitors have the capability to monitor gaseous effluents over three general ranges (high,' middle and low) using four channels. In the perrnanently defueled mode, the middle and high ranges (Channels 2 and 3) are no longer necessary, and are no longer
)
used or maintained. Channels 1 and 4 both operate in the low range and are the monitor channels which are considered in this procedure.
The Specification in Step 6.14.5 states that the gaseous effluent monitors shall have their
- alarm / trip setpoints set to ensure the limits of the Specification in Step 6.14.6 are not exceeded.
The conservative default atmospheric dispersion (X/Q) factor from S:ep 6.1.3 is used.
Compliance with the dose rate limits for noble gases specified in Step 6.14.6 is demonstrated by setting each gaseous effluent monitor alarm / trip setpoint so that an alarm / trip will occur at or before the dose rate limit is reached.
A SAFETY FACTOR is included in the setpoint calculations to incorporate a margin of conservatism.
Maximum design flow rates for each release point will be used to calculate setpoints.
6.6.1 Conversion Factors for R15044. R15045. and R15546A Provided here is the methodology to determine the conversion factor of counts per minute to microcuries per cubic centimeter for the Auxiliary Building Stack Monitor (R15045),
Reactor Building Stack Monitor (R15044), and the Auxiliary Building Grade Level Vent Monitor (R15546A). The conversion factor is based on the monitor's efficiency of detection 1
for each nuclide and the mix of the nuclide. The mix ofisotopes used should be based on Kr-
{
85, but may be based on the current mix in the continuous release, or as determined by Radiation Protection / Chemistry Supervision. The mix used for setpoint calculations and i
conversion factor calculations should be the same.
,_m.
y.
^
(
)Lp ;L S.3
~
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[
The following equation shall be used to determine the conversion factor for R15044, R15045-s._
2.
and R15546A:
l
..n
-CF.= [(fi x Ei)
.1 Where:
pCi/cc per cpm CF
=
a(..P f;
' Fraction ornuclide i to total activity of the mix used
.=
Dhector efficiency for nuclide i, in cpm per pCi/cc, Attachment 10 E;
=
6 6.2 - Gaseous Effluent Flow Rates Flow rates used in routine gaseous effluent calculations for the pathways listed below are conservative default values.1 These flow rates should be used to determine monitor setpoints, assess compliance with the gas.cous effluent requiremerits in Section 6.14, 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:
, 7 ft.e I Reactor Building Stack 74,000 CFM
.--> p 9
,90,ce.o,,740 CFM Auxiliary Building Stack i
9-+ *-
Auxiliary Building Grade Level Vent 31,000 CFM
' Interim On-site Storage Building Ventilation
- 8,050 CFM l
- The Interim On-site Storage (IOS) 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.
l i
l 6.6.3 Determination 'of Partition Factor &J The Specification in Step 6.14.6 applies to the entire site, not just one vent or monitor.
i i
Consequently, the total release rate must be partitioned among the three major vents (ABS, j
L
.ABGLV, RBS). For routine operations, the partition factor may be calculated by assuming i
! : -n.ep that the effluent concentration is the same for all pathways and using a ratio of flow rates.
[
9-+ r N-The total volume flow rate for all three vents is M9;NO CFM. Therefore:
6S)oco 74,000 CFM b " 152,740 CFM O'
dI Ii1S, ore 1
'L L
g,,
Tc.ob
=..
l
(.
jLye s 43 MANUAL. CHEMISTRY ADMINISTRATIVE NUMBER:
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~ PROCEDURES MANUAL 3:
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fc; A
.9-+.
9 49;940CFM
.P,t,, = 152,70 CFM
= 4+1 c.6 j
/7$ cor-31,000 CFM -
Patisiv: =
= DJO o./ / --
i 452;940 CFM If(oc6 x
(_.-.-
Radiation Protection / Chemistry Supervision may elect to use a diff'erent set of panition factors based on plant conditions. However, the sum of all the panition factors for the site.
must be less than or equal to unity (1).
{
.y p
\\
6.6.4 Channel 4 Noble Gas Setsoint for R15044. R15045. and R15546A in uCi/see
- 30h0 x" Pv x E Ci=
I i
My
=
, + Bkgd.
. SF x (X/Q) x ' 1 C : x (LI + 1.1 x Mi) i Where:
Monitor setpoint for ven't v (i.e., RBS,' ABS, or ABGLV) in pCi/sec -
' M.
=-
- 3000-
- = - Step 6.14.6 Specification limit for skin dose rate in ' mrem /yr P.
Partition factor for vent v, dimensionless, which distributes the total site
=
release rate among the three vents C;
- =
Concentration ofisotope f in gaseous effluent in pCi/cc. The mix ofisotopes used may be based on Kr-85, the current mix, or as determined by Radiation L-Protection / Chemistry Supervision.
a LSafety Factor, dimensionless, (SF 21)
. SF.
=-
- 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'. The default value in Step 6.1.3 will be used.
'A factor convening gamma radiation from noble gas radionuclide i to skin Li
=
dose (mrem-m'/pCi-yr). See Attachment i1.
c Mi
'A factor convening gamma radiation from noble gas radionuclide i to air dose
=
(mrad-m'/pCi-yr). See Attachment 11.
'Bkgd:
Monitor background reading in pCi/sec
=
l r
~
_.___.._._._..__.m_._-
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615 Channel'1 Noble Gas Setooint for R15044. R15045. and R15546A in uCi/cc MC, = 472 x F, + Bkgd i
Where:
I MC, = Monitor setpoint for vent v based on concentration in pCi/cc l
Monitof set' point for vent v based on release rate in pCi/sec excluding
- MR,
=
the background term. That is, M - Bkgd i
3 Maximum design volumetric flow rate for vent v in CFM as indicated in i
F.
=
Step 6.6.2.
28317 ml/ft'
- 1 min /60 sec 472
=
Bkgd = Monitorbackground readingin Ci/cc c----------------
NOTE f
i i
I I
l Channel 1 does not cause any automatic terminations or l
{.audib,le_ alarms._ _ _,, _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ j 6.7 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 I 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 r
s Ci MECF = [ MECsx F x 4.72E -4 x X / Q x TR is Where:
1 The concentration of nuclide lin mci /cc.
Ci
=
Maximum design volumetric flow rate in CFM as indicated in 6.6.2.
{
F~
=
A conservative default atmospheric dispersion factor for a ground level X/Q-
=
release to a sector at or beyond the Site Boundary for Gaseous Effluents in sec/m'. The default value in Step 6.1.3 will be used.
'~
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. 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.
l TR If the time of release is less than one hour, then this value is the duration of
=
the transient in minutes divided by sixty. Othenvise, the Time Ratio (TR) is one. Dimensionless.
4.72E-4 =
The conversion factor in min *m'/sec*ft'.
'~
6.8 Dose Rate Calculations Compliance with the doseYate limits for noble gases in the Specification in Step 6.14.6 is demonstrated by setting each gaseous effluent monitor alarm setpoint so that an alarm will occur at or before either dose rate limit Specification in Step 6.14.6 is reached. In addition, the
{
l Specification in Step 6.14.6 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.
i i
The dose rate due to noble gas is evaluated as follows:
i l
Total Body:
- 6. = (X / Q) x ' (((Q,i x Ki)
,i l
Skin:
b, = (X / Q) x (( Q,i x (Li + 1.lMi)
, i Where:
l The total body dose rate from noble gases (mrem /yr)
[
D.
=
t D,
The skin dose rate from noble gases (mrem /yr)
=
i X/Q A conservative default atmospheric dispersion factor for a ground level j
=
release to a sector at or beyond the Site Boundary for Gaseous Effluents in sec/m'. The default value in Step 6.1.3 will be used.
j Qa The release rate of noble gas radionuclide i from effluent vent v during the
=
time of the release ( Ci/sec) i l
K; A factor converting time integrated, ground-level concentration of noble gas
=
radionuclide i to total body dose from its gamma radiation (mrem-m'/pCi-yr).
See Attachment 11.
_ _... _ _ _. ~. _ _ _ _ _. _. _. _. _ _ _..
d L
MANUAL CHEMISTRY ADMINISTRATIVE NUMBER:
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' A factor converting gamma radiation from noble gas radionuclide i to skin
=
dose (mrem-m'/ Ci-yr). See Attachment 11.
i Mi A factor converting gamma radiation from noble gas radionuclide i to air dose
=
(mrad-m'/ Ci-yr). See Attachment 11.
i 1.1 A factor converting air dose from gamma radiation to skin dose equivalent
=
(mrem / mrad)
The organ dose rate resulting from inhalation is calculated with the equation:
Organ:
DO,j = (X/Q) x (((Qy Raji) x v i Where:
The dose commitment rate to organj of a person in age group a (mrem /yr) l DO.)
=
i-i R.ji The factor to convert air concentration of radionuclide i to organj dose
=
commitment rate of a person in age group a exposed by inhalation l
(mrem-m'/ Ci-yr). See Attachment 12.
l l
Qw The release rate of radionuclide f (not including Noble Gas nuclides), via
=
l effluent vent y during the time of the release (pCi/sec) i Exposure to dose rate factors, R.ji, for inhalation are derived by using equation 13 in RG 1.109, L
Rev. l. Tables E-5, E-7, E-8, E-9, and E-10 are assumed to represent the Maximum Exposed l
Individual in the equation to derive R.;;.
l L
6.9 Air Dose Calculations i
The Surveillance Requirement in Step 6.14.7 requires cumulative dose to air from radioactive effluent noble gases to be determined in order to assess compliance with the Specification in Step 6.14.7. The air dose is evaluated in the sector of the maximum exposure at or beyond the Site Boundary for Gaseous Effluent.
1 Air dose from noble gas gamma radiation is calculated cumulatively with the equation:
l Dg = 3.17E-8 x '[ (X/Q)x (((Qyni x Mil v_
i n Air dose from noble gas beta radiation is calculated cumulatively with the equation:
Db - 3.17E-8 x [ (X/Q) x (((Qvni x Ni) i y
in
l MANUAL: CHEMISTRY ADMINISTRATIVE
. NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 23 of 74 Where:
D, The noble gas gamma dose to air (mrad)
=
D6 The noble gas beta dose to air (mrad)
=
j-X/Q A conservative default atmospheric dispersion factor for a ground level
=
release to a sector at or beyond the Site Boundary for Gaseous Emuents in l
sec/m'. The default value in Step 6.1.3 will be used.
t A fact,o'r'conve'rting ground-level concentration to ganuna radiation from M4
=
noble gas radionuclide i to air dose (mrad-m'/ Ci-yr)
Ni A factor converting ground-level concentration to beta radiation from noble
=
gas radionuclide i to air dose (mrad-m'/pCi-yr)
Qw The quantity of each noble gas radionuclide iin batch a released via emuent
=
stream v(pCi) 3.17E-8 =
1 yr/3.156E+7 sec l
Factors Mi and Ni are 10' pCi/pCi times the values in RG 1.109, Rev.1, Table B-1, Columns 4 and 2, respectively. The computer codes GASPAR and REIMS may be used to perform these calculations.
6.10 Organ Dose Calculations for Gaseous Effluents -
The Surveillance Requirement in Step 6.14.8 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 i
emuent 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 Speci6 cation in Step 6.14.8.
A person may be exposed to emuent radioactive material of this type in air by inhalation or indirectly via environmental pathways that involve deposition onto vegetation and the ground.
l The exposure pathways evaluated will include the followmg:
i p
Exposure Pathway i
1-Air -inhalation l
2
. Deposition onto ground - irradiation l
3 Deposition onto vegetation - ingestion 4-Deposition onto forage - cow - milk - ingestion L
5-Deposition onto forage - meat animal - meat - ingestion
- 6 Deposition onto forage '- goat - milk - ingestion a
a
+
-y--,
,,.y
-9s u
9,.gi w-----
MANUAL CHEMISTRY ADMINISTRATIVE NUMBER:
CAP 0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 24 of 74 The equation used to calculate the dose commitment to the Maximum Exposed (Hypothetical) l Individual from radionuclides other than tritium is:
o-I (x/o), x II(ou x R.) +E (D/o), x II(ow x R. )
u p=1 v i p=2 v i Where:
p = 1, i.e., air-inhalation,in,theifirst term, and p = 2, 3,4, 5, and 6 in the second term of the equation 5
r i excludes H-3 D.;
The dose commitment to organj of a person in age group a (mrem)
=
Qw The quantity of each radionuclide i, in particulate form having a half-life
=
greater than 8.0 days, in air discharged via effluent stream y( Ci)
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'. The default value in Step 6.1.3 will be used.
t A conservative default deposition factor. A Factor converting a ground-level D/Q
=-
or building wake discharge in air to deposition on land (m 2). The D/Q value in Step 6.1.3 will be used.
A factor converting time integrated concentration of radionuclide f in air or R,j;,
=
deposited on vegetation and/or ground to radiation dose commitment to organJ, including total body, of a person in age group a who is exposed via j
pathwayp.
When p=1, representing air-inhalation, R.;;, has units of mrem-m'/pCi-yr. When p=2,3,4,5 or 6 j
in the second term of the equation above, representing pathways involving deposition, R.ji, has l
units of mrem-m -sec/yr-pCi. When the radionucMe is H-3, R.j;, has units ofmrem-m'/pCi-yr.
2 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:
k L
MANUAL: CHEMISTRY ADM;MISTRATIVE NUMBER:
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D4 = 3.17E-8 x [ (X / Q), x [(Q,; x R i, 4
P.
v Where; p = 1, 3, 4, 5, and 6 Iincludes H-3 only A consedative' dhault atmospheric dispersion factor for a ground level X/Q
=
release' to a sector at or beyond the Site Boundary for Gaseous Effluents in j
sec/m'. The default value in Step 6.1.3 will be used.
l 3.17E-8 =
years /sec l'E Other terms as defined above.
Dose factors R.ji, 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 bejustified 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.)
6.11 Gas Dose Proiections 31-Day Dose projections are calculated to show compliance with Step 6.14.9. Quarterly and Annual dose projections are calculated in compliance with the Specification in Step 6.14.11.
The dose projection' equations are the same as used for liquid per Step 6.5.
6.12 Fuel Cycle Dose If a calculated dose exceeds twice the limit of the Specification in Step 6.14.3,6.14.7,6.14.8, or
. a level in Table 3 of the REMP Manual is exceeded, an assessment of compliance with the Specification in Step 6.14.10 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 6.9 and 6.10. These methodologies are to be used as a guide and strict adherence is not required because the Fuel l:
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.
i 4
4
~
l MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
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?
Irradiation, i.e., exposure to an external source of radiation, directly from the RSNGS normally -
will be evaluated with the aid of environmental dosimetry such as thermoluminescent dosimetry (TLD) or portable ion chamber (PIC) measurements.
6.13 EPA Reoortina Reauirements l
If a calculated dose exceeds the Specification limit of Step 6.14.2, 6.14.3, 6.14.6, 6.14.7, or 6.14.8, an assessment of compliance with 40 CFR Parts 302 and 355, Reportable Quantity l
Adjustment - Radionuclides, must be made.
i i
,l This involves determining (ths 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 I
and comparing the quantitie.s'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.
l 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 i
determine compliance are not required.
l 6.14 Technical Reauirements l
6.14.1 Liauid Emuent Monitoring Instrumentation Specifications:
l The radioactive liquid effluent monitoring instrumentation channels shown in Attachment 13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Step j
6.14.2 are not exceeded. The alarm / trip setpoints of these channels shall be determined in j
accordance with Step 6.2.
)
Aeolicability:
During releases via the retention basin emuent discharge.
Action:
- 1) With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than a value which will ensure that the limits of Step 6.14.2 are met, immediately suspend the release of radioactive emuents monitored by the affected channel, or declare the channelinoperable, or change the setnst so it is acceptably conservative.
t i
- 2) With less than the minimum number of radioactive liquid emuent monitoring i
instrumentation channels OPERABLE, take the Action shown on Attachment 13.
i
. _ _. _ _ _ _ _ _ _ _. ~... _
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l Surveillance Reauirements:
l l
- 1) The maximum setpoint shall be determined in accordance with methodology as described L
in Step 6.2 and shall be recorded on the release permits.
- 2) Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the INSTRUMENT CHANNEL CHECK, SOURCE CHECK, INSTRUMENT CHANNEL CALIBRATION, AND CHANNEL TEST at the i
frequencies shown in Attaciunent 14.
'l'
- 3) Records shall be maihtained in accordance with the Process Standards of all radioactive liquid effluent monitoring instrumentation alarm / trip setpoints. Maximum setpoints and calculations shall be available for review to ensure that the limits of Step 6.14.2 are met.
Bases.
During continuing operations leading to decontamination and decommissioning of the site, radioactively contaminated water will be processed, as necessary, to remove the activity according to the Process Control Program (PCP). After being processed as necessary, the water may be transferred to the 'A' and 'B' Regenerant Holdup Tanks (RHUTs). Pathways for water to reach the RHUTs are shown in Attachment 1, Liquid Effluent Flow Diagram.
Administrative controls provide reasonable assurance that any waste water that is radioactive is processed through the RHUTs prior to their release.
Water which is in the 'A' and 'B' RHUTs is transferred to the North or South Retention Basin. The water in a Retention Basin is released off-site as a batch release. These releases are monitored by the Retention Basin Effluent Discharge Monitor.
Radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of radioactive liquid effluents. The alarm / trip setpoints for these instruments shall be calculated in accordance with the methodology contained in this manual to ensure that the alarm / trip will occur prior to exceeding the limits of Step 6.14.2. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60,
~ 63, and 64 of Appendix A to 10 CFR Part 50.
6.14.2 Maximum Efiluent Concentrations in Liauid Effluents Soecifications:
The concentration of radioactive material released in liquid effluents at any time beyond the Site Boundary for Liquid Effluents (see Attachment 6) shall be limited to the concentrations specified in Appendix B to 10 CFR Part 20, Table 2, Column 2.
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TITLEi OFF-SITE DOSE CALCULATION MANUAL PAGE: 28 of 74 Aeolicability:
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 j
concentration within the required limits and report the event in the next Annual Radioactive j
Emuent Release Repon
,7 Surveillance Requirements:
The concentration of radioactive material at any time in liquid effluents released from the site to areas beyond the Site Boundary for Liquid Effluents shall be continuously monitored in accordance with Attachment 13.
The liquid effluent continuous monitor having provisions for automatic termination ofliquid releases, as listed in Attachment 13, shall be used to limit the scentration of radioactive material released at any time from the site to areas beyond the Site Boundary for Liquid Effluents to the limits given in the above Specifications.
The radioactivity concentration of each Retention Basin to be discharged shall be determined prior to release by sampling and analysis in accordance with Attachment 15, Item A. The results of Retention Basin pre-release sample analyses shall be used with the calculational methods described in Step 6.3 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 radioacive materials released in liquid waste emuents from the site to areas beyond the Site Boundary For Liquid i
Effluents (see Attachment 6) 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.
6.14.3 Liauid 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 6) shall be limited to:
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- 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 equal to 10 mrem to any organ during any calendar year.
Apolicability:
At all times.
.p
^
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 emuents and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above Specifications.
Surveillance Reauirements:
Cumulative dose assessments associated with the release of radioactive liquid effluent shall be determined by sampling and analysis in accordance with Attachment 15, Item B or Item C, 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 emuent from the A or B RHUT; and, 2)~
. Upon verification of monthly composite analysis results for radioactive liquid emuent released from the A and B RHUTs.
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 6.14.4, adjust liquid ef9uent 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 6.14.3 is provided to implement the requirements of Sections II.A, III.A, and IV. A of Appendix I,10 CFR Part 50. This step implements the guides set forth in Section II.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 emuents 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
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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 j
is unlikely to be substant' ally underestimated. The equations specified in this manual for 1
calculating the doses due to the actual release rates of radioactive materials in liquid effluents
(
are consis*ent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual cas to Man from Routine Releases ofReactor Effluents for the Purpose of I
Evaluatics Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and j
Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases fbr,the. Purpose ofImplementing 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 ia excess of the requirements of 40 CFR 141.
The Lower Limits of Detection established in Attachment 15, Item B are based on an estimated maxitum annual emuent outflow of 2 million gallons with a minimum annoal average flow rate in the piant emuent stream of 6,000 gallons per minute. The RHUT pre-release and monthly composite Lower Limits of Detection equate to an off-site dose ofless 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 6.14.3 (the 10 CFR 50, Appendix I dose guidelines) will be met.
6.14.4 Liauid Effluent Radwaste Treatment i
Specifications:
The LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM shall be OPERABLE.
The appropriate portions of the system shall be used to reduce the quantity of radioactive materials in liquid emuents prior to their discharge whe. projected doses due to the liquid
. emuent beyond the Site Boundary for Liquid Emuents (see Attachment 6), 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).
j Anolicability:
At all times.
l Action-i With the LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM inoperable for more than 31 days or with radioactive liquid waste being discharged without treatment and in
)
excess of the above limits, prepare and subma to the Commission within 30 days a Special Repon which includes the following information.
- 1) Explanation ofwhy liquid radwaste was being discharged without treatment, identification i
of any inoperable equipment or subsystems, and the reason for the inoperability; and, i
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- 2) Action (s) taken to restore the inoperable equipment to OPERABLE status; and,
- 3) Summary description of action (s) taken to prevent a recurrence.
Surveillance Recuirements:
Doses due to liquid releases to areas beyond the Site Boundary for Liquid Effluents shall be projected prior to each RHUT release in accordance with the methodology described in Step l
6.5 when LIQUID EFFLUENT RADWASTE TREATMENT SYSTEMS are not being fully utilized. The installed L1, QUID EFFLUENT RADWASTE TREATMENT SYSTEM shall be considered OPERABLE by meeting the Specifications in Steps 6.14.2 and 6.14.3.
Bases.
l r
The OPERABILITY of the LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this l
system be used, when specified, provides reasonable assurance that the releases of radioactive materials in liquid effluents 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 limits governing the use of appropriate portions of the LIQUID EFFLUENT RADWASTE TREATMENT SYSTEM are the dose
' design objectives set forth in Section II.A of Appendix I,10 CFR Part 50, for liquid effluents.
6,14.5-Gaseous Effluent Monitorinu Instrumentation Specifications:
The radioactive gaseous effluent monitoring instrumentation channels shown in Attachment 16 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Step 6.14.6 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the methodology contained in this procedure. Continuous samples of the gaseous effluent for radioactive particulate material shall be taken as indicated in Attachment
-- 16.
Aeolicability:
- This is applicable at all times.
Action:
i
- 1) With a radioactive gaseous effluent monitoring instnamentation channel alarm / trip setpoint less conservative than a value which will ensure that the limits of Step 6.14.6 are met, l
immediately suspend the release of radioactive gaseous efflue tn s monitored by the affected l
channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
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- 2) With less than the minimum number of radioactive gaseous emuent monitoring instrumentation channels OPERABLE, take the Action shown in Attachment 16. Exert best efforts to return the instrument to OPERABLE status within 30 days and ifunsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner, Surveillance Reauirements:
The maximum setpoints shall be determined by procedures implementing the methodology presented in this procedste add shall be recorded on release permits.
Each gaseous emuent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the INSTRUMENT CHANNEL CHECK, SOURCE CHECK, INSTRUMENT CHANNEL CALIBRATION, AND CHANNEL TEST at the frequencies shown in Attachment 17.
Records shall be maintained in accordance with the Process Standards of all radioactive gaseous effluent monitoring instrument alarm / trip setpoints. Maximum setpoints and setpoint calculations shall be available for review to ensure that the limits of Step 6.14.6 are met.
Bases:
The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of radioactive gaseous effluents. The alarm / trip setpoints f~ these instruments, except for the Interim On-site Storage (IOS) Building vent monitor (R15106),
shall be calculated in accordance with the methodologv contained in this manual to ensure that the alarm / trip will occur prior to exceeding the limits of ODCM Step 6.14.6. The monitor setpoints for R15106 are set statistically high enough above background to prevent spurious alarms, yet stop potential radioactive releases when detected (Aeference 3.2.18).
l The OPERABILITY and use of this instrumentation is consistent with the requirements of j
General Design Criteria 60,63, and 64 of Appendix A to 10 CFR Part 50.
j The IOS Building has a ventilation system which provides protection against radioactive airborne releases. Operation of the ventilation system produces a negative pressure in the building. During operation, the ventilation exhaust flow is continuously monitored for particulate activity. Upon an alarm, the exhaust duct closes and the supply and exhaust fans stop, minimizing any chance of an airborne release. Although no planned airborne radioactive releases are anticipated from this pathway, the ventilation exhaust monitor is includedin Attachment 16.
Fuel Storage Building exhaust is directed to the Auxiliary Building Stack where the exhaust is filtered and monitored for any activity prior to release to the atmosphere.
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6.14.6 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 Efiluents (see Attachment 5) shall be limited to the following values:
- 1) The dose rate limit for noble gases shall be less than or equal to 500 mrem /yr to the total body and less than or equal to 3.000 mrem /yr to the skin; and,
- 2) The dose rate limit f,o.r tritium and for all radioactive materials in particulate form with i
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 Efiluent Release Report.
Surveillance Reauirements:
The noble gas effluent continuous monitors, as listed in Attachment 16, shall use monitor setpoints to limit the dose rate in unrestricted areas to the limits in the above Specification.
In the event a noble gas effluent exceeds the setpoint ofits monitor, an assessment of compliance with the Specification above shall be made in accordance with the methodology contained in this manual.
The release rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined by obtaining representative samples and performing analyses in accordance with the sampling analyses program specified in Attachment 18.
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
' 8 and the methodology described in Step 6.8.
Bases.
Step 6.14.6 is provided to ensure that the dose rate from gaseous effluents due to immersion or inhalation at any time at the Site Boundary for Gaseous Efiluents (see Attachment 5) will be within the annual dose limits of 10 CFR Part 20 for hEMBERS OF THE PUBLIC. The
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' annual dose limits are the doses associated with the concentrations of Appendix B to 10 CFR 1
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 G===>s Effluents to annual.verage 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. The specified
)
release rate limits restrict, at all times, the corresponding gamma and beta dose rates above j
background to an individual n't or beyond the Site Boundary for Gaseous Effluents to less than or equal to 500 inrem/yr to the total body or to less than or equal to 3,000 mrem /yr to the skin. These release' rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a person of any age group via the inhalation pathway to less than
' or equal to 1,500 mrem /yr, 6.14.7 Gamma and Beta Air Dose Specifications:
The air dose due to noble gases released in gaseous effluents to areas at or beyond the Site Boundary for Gaseous Effluents (see Attachment 5) shall be limited to the following:
- 1) During any calendar quarter, to less than' or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation; and,
- 2) During any calendar year, to less than or equal to 10 mrad for gamma radiation and to less than or equal to 20 mrad for beta radiation.
Applicability:
This is applicable at all times.
i Action:
With the calculated air dose from radioactive noble gases 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 (s) and define the corrective action (s) tsken to reduce the release of radioactive noble gases on gaseous effluents, and the corrective action (s) to be taken to assure that subsequent releases wii! be in compliance with the above limits.
Surveillance Requirements:
Cumulative air dose contributions for the current calendar quarter and calendar year shall be determined in accordance with the methodology in Step 6.9 at least monthly.
MANU/i: CHEMISTRY ADMINISTRATIVE HUMBER:
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Appendix I,10 CFR Part 50. This step implements the guides set fonh in Section II.B of i
Appendix I. The Action statemente provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable."
The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance yvith the guides of Appendix I be shown by calculational procedures based
. on models and data such.that thsactual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in this manual for calculating the doses due to the actual release rates of radioactive noble gases i
in gaseous 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 Pan 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transpon and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled I
Reactors," Revision 1, July 1977. The equations in this manual provide for determining that
)
the air doses at the Site Boundary for Gaseous Effluents (see Attachment 5) are based upon the historical average atmospheric conditions.
]
6.14.8 Gaseous Ornan Dose Soecifications:
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 5) 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.
Aoolicability:
l This is applicable at all times.
j 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 j
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 i
--m;
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n y
l l
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l Surveil'ance Requirements:
Cumulative dose contributions for the current calendar quaner and calendar year period shall be determined in accordance with the methodology described in Step 6.10 at least monthly.
Bases.
Step 6.14.8 is provided't'a impfeinent the requirements of Sections II.C, III.A and IV.A of Appendix I,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 i
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." 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 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, i
" Calculating of Annual Doses to Man from Routine Releases of Reactor Efiluents for the j
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 Efiluents in Routine Releases from Light-Water-Cooled Reactors,"
Revision 1, July 1977. These equations also provide for estimating deses 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 Efiluents (see Attachment 5). 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 l
subsequent exposure of man.
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6.14.9 Ventilation Exbanet Treatment System f
Snecifications:
}
I The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The j
. installed VENTILATION EXHAUST TREATMENT SYSTEM shall be considered -
OPERABLE by meeting the Specifications in Steps 6.14.6, 6.14.7, and 6.14.8.
l Also, the following two conditions shall not exist simultaneously:
j i
- 1) Gaseous waste is beinig discharged without treatment, and; J
' 2) The projected doses'due to gaseous effluent releases from the site (see Attachment 5),
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).
Anolicability:
This is applic' able at all times.
1 Action:
If both parts 1) and 2) of the Specification are satisfied, prepare and submit to the Commission within 30 days a Special Repon pursuant to Technhal Specification D6.9.7 which includes the following information:
- a. Explanation ofwhy 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 Reauirements:
Doses due to gaseous releases to areas at and beyond the Site Boundary for Gaseous Effluents (see Attachment 5) shall be projected at least once per 31 days in accordance with the methodology and parameters in Step 6.11..
DOP tests will be performed on the HEPA filters in the Ventilation Exhaust Treatment
- Systems every 18 months, or after any work has been performed on the HEPA filter systems which could alter their integrity.
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. The OPERABILITY 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 l
be used, when specified, provides reasonable assurance that the releases of radioactive materiale da gaseous effluents are maintained "as low as is reasonably achievable." Step i
6.14.9 implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of j
Appendix A to 10 CFR 50, and the design objectives given in Section II.D of Appendix I to
.10 CFR 50. The specified lintitsjoverning the use of appropriate portions of the systems i
and the dose design objectives set fonk in Sections II.B and II.C of Appendix 1,10 CFR 50,
~
for gaseous effluents..'
6.14.10 Frel Cycle Dose Soccification:
l 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 (except the thyroid, which is limited to less than or equal to 75 mrem) in a calendar year.-
Apolicability:
At all times.
l Action.
i j
-1)
With the calculated doses from the release of radioactive material in liquid or j
gaseous effluents exceeding twice tlie limits of Specifications in Steps 6.14.3, 6.14.7,
)
6.14.8'or exceeding the reponing levels in Table 3 of the REMP Manual, i
calculations shall be made includin~g direct radiation contributions (including outside storage tanks, etc.) to determine whether the above specifications have been i
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 j
reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Repon, 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 j
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.
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If the estimated dose (s) exceed the above limits, and if the release condition resulting I
in the violation of 40 CFR Pan 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provision of 40 L
CFR Pan 190. _ Submittal of the report is considered a timely request, and a vanance is granted until staff action on the request is complete.
)
Surveillance Reauirements-
. Cumulative dose contributipns from liquid and gaseous effluents shall be determined in accordance with the Step,6.14.3,'6.14,7, and 6.14.8 Surveillance Requirements.
Cumulative dose contri,butions from direct radiation (including outside storage tanks, etc.)
shall be determined in accordance with Step 6.12. This requirement is applicable only under j
the conditions set forth in the above Action statements.
1 i
Bases.
Step 6.14.10 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 reponing 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 Repon 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 Repon with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already beer, 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 pan of the uranium fuel cycle.
l, 6.1411 Ouaner/ Annual Dose Proiections L
' Soecifications:
The projected dose contributions from liquid and gaseous effluents for the current calendar quaner and current calendar year shall be calculated according to the methodology in Steps 6.5 and 6.11 at least every 31 days.
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i Applicability.
t i
At all times.
i
. Action.
I i
With the required dose calculations not being performed, best effort will be exerted to I
perform the calculations once the deficiency has been identified. Corrective actions will be taken and documented to p,revent reoccurrence.
Sury.in.nce p.mde,nede.
e
[
i
- 1) Liquid Effluents l
Projected dose contributions shall be determined at least every 31 days.
ll
- 2) Gaseous Emuents l
Projected dose contributions shall be determined at least every 31 days.
i Bases:
This step is provided to implement the requirement of Technical Specification D6.8.3.a.5.
Dose projections provide a means of determining if current release practices will be within the dose limits of 10 CFR 50, Appendix 1. Calculating projected dose totals every 31 days provides information which can be used to keep emuent 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.
6.15 Reoorts 6 15.1 Annual Radioactive Effluent Release Report (ARERR)
The ARERR covering the activities of the unit during the previous 12 months shall be submitted within 60 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.
l (2) Summary of solid waste shipped from the unit.
]
(3) All unplanned releases of radioactive m aterials in gaseous and liquid effluents to L
unrestricted areas shall include a description of the event and equipment involved, j
cause(s), action (s) taken to prevent recurrence, and consequences.
l;
~
l MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOdE CALCULATION MANUAL PAGE: 41 of 74 (4) Dose or dose commitment assessments to ensure compliance with the specifications in 6.14.3,6.14.7, and 6.14.8.
(5) Complete, legible copy of the entire ODCM and/or REMP 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 6.14.2,6.14.5, and 6.14.6.
6.15.2 30 Day Reoorts ~
'.lt The following 30 day reports should be submitted if the criteria are met as stated in the following areas:
(1) 6.14.3 - Liquid Dose Calculations (2) 6.14.4 - Liquid Dose Projections (3) 6.14.7 - Gamma and Beta Air Dose (4) 6.14.8 - Gaseous Organ Dose (5) 6.14.9 - Gaseous Dose Projections (6) 6.14.10 - Fuel Cycle Dose 20 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 i
Records Management in accordance with RSAP-0601, Nuclear Records Management.
l
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL l
REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 42 of 74 1
~
LIOUID EFFLUEhiT FLOW DIAGRAM UQUID EFFLUENT FLOW DIAGRAM
[O OvtRFL0w FRoM CONDEN5IR ORC BASIN, SPRAY gg
, wgg Pf7 $ UMP PONDS E *"
O BACKWASH FROM SW5, i
bE "NE RESERWMR, NRW FILTERS
- ,I C 5 EWER PLANT EFFLUENT
]
j V
5 BATTERY ROOM DRMN5 P005HER E CHEM MIEN i
DEMINERAUZER pump DRA NS O TANK FARM i
SUMP 85AMPt E DRMMS (COLD 8 %
STO W DRAIN 5 1
ETURWNE DECK (O ANUT VAtyt GALLaRY 4
A STORM DRAIN 5*
SUMP 5 l
f O EX COOLANT DEMIN STORAGE TANK j
4 O TANK FARM SUMP 5 (3) 1 O AuxtuARY so4Lra i
s BLOWDOWN I-Y Y
T ARHUT 8RMUT r O TUR9NE DECK 04LY STORM DRMM5*
WATER W
O TRAN5FORMER l
SEPERATOR ALLEY STORM V Y
(
DRAINS SLUICE EFFLUENT MIXING DEMINS STRMNERS DOX 4
H R 150170)
FN MH W l l n.s.
vv v v MISC RETENTION I Ic R.15017A) y RADWA;TE BA5W5 l
^
SYSTEM
> PLANT EFFLUEP(T v
TO CLAY CREEK f'
Flow TOTAUZER/
F *F r s FLOW RATE METER
- TUR$1NE DECK STORM DRAIN 5 CAN N DIRECTED TO THE CtLY WATER SEPERATOR (NORMAL) OR THE POU5HER DEMIN SUMP Attachment I Page1of1 I
r I
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 43 Of 74 GASEOUS EFFLUENT FLOW DIAGRAM
)
l l
GASEOUS EFFLUENT FLOW PATH PLANT VENTS
==
e g l AUX BLDG EXHAUST PLENUM l
^
4 g - - - -
^
^
,CR15045}
RxBLDG AUX BLDG-( e COMPACTOR ROOM STACK p ]j uDECON AREA STACK A
v aCHEMICAL STORAGE
)
R15040 SPENT FUEL
( BALCONY BUILDING mumm
(~ s MISC WASTE TANK RM eVALVE GALLERY s*A' HPIP ROOM HOT LAB l;
a EAST / WEST DH 2
[
]
j' PUMP ROOM Y
m DECAY HEAT SUMP VENTS CTMT BLDG
( a RCDT ROOM INLET AIR
's MAKEUP PUMP ROOM g
s*B* HPIP ROOM j
4 s SPENT RESIN TANK RM 5
=
m SEAL RETURN b COOLER ROOMS
/-
( e BA CONC ROOM AUX BLDG s MW EVAP ROOM E
AUX BLDG 4_
GRADE AREA a EAST / WEST DH GRADE LEVEL l
VENTS COOLER ROOMS VENT 4]Ed aION EXCHANGE ROOM aWASTE GAS COMP ROOM i
(a UNDERGROUND TNKS f aMISCWASTE STRIPPER l J (MISC WASTE EVAP)
. 2 (RIS106) l l m RC WASTE GAS
( STRIPPER (BAC)
/
INTERIM ONSITE 4.
RADWASTE j
STORAGEBLDG IOS VENT (POTENTIAL RELEASE PATHWAY)
= HEPA FILTER Page1 of1
.~
i MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 44 of 74
'~
DOSE FACTOR PARAMETER _S CONSUMPTION AND USAGE PARAMETERS PATHWAY Afd 1.109 DEFAULT RSNGS Irrigated Stored Vegetables Adult 520 kg/yr 520 kg/yr Teen 630 kg/yr 630 kg/yr Child 520 kg/yr 520 kg/yr
, hifant;i 0 kg/yr 0 kg/yr Irrigated Fresh Vegetables Adult 64 kg/yr 64 kg/yr
- ' Teen 42 kg/yr 42 kg/yr Child 26 kg/yr 26 kg/yr Infant 0 kglyr 0 kg/yr Irrigated Milk Adult 310 kg/yr 310 kg/yr Teen 400 kg/yr 400 kg/yr Child 330 kg/yr 330 kg/yr Infant 330 kglyr 330 kg/yr Irrigated Meat & Poultry Adult i10 kg/yr 110 kglyr Teen 65 kg/yr 65 kg/yr Child 41 kg/yr 41 kg/yr Infant 0 kg/yr 0 kg/yr Fish Adult 21 kg/yr 21 kg/yr Teen 16 kg/yr 16 kg/yr Child 6.9 kg/yr 6.9 kg/yr Infant 0 kglyr 0 kg/yr Other Seafood Invenebrate Adult 5.0 kg/yr 6.9 kg/yr (Crayfish)
Teen 3.8 kg/yr 5.2 kg/yr Child 1.7 kg/yr 2.2 kg/yr Infant 0kr/yr 0 kg/yr Algae Adult None 0 kg/yr Teen None 0 kg/yr l
Child None 0 kg/yr Infant None 0 kg/yr Water Usage (Drinking Water)
Adult 7301/yr 01/yr i
Teen 5101/yr 01/yr Child 5101/yr 01/yr Infant 3301/yr 01/yr Page1of3
MANUAL-CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 45 of 74
~ DOSE FACTOR rARAMETERS (Continued) l CONSUMPTION AND USAGE PARAMETERS (continued)
PATHWAY AGE 1.109 DEFAULT RSNGS Shoreline Recreation Adult 12 hr/yr 200 hr/yr Teen 67 hr/yr 100 hr/yr Child 14 hr/yr 14 hr/yr
- Infant p 0 hr/yr 0 hr/yr Swimnung Adult None 100 hr/yr
- ~ Teen None 100 hr/yr Child None 14 hr/yr Infant None 0 hr/yr Boatmg Adult None 0 hr/yr 1
Teen None 0 hr/yv Child None 0 hr/yr
{
Infant None 0 hr/>T Inhalation Adult 8000 m' 8000 m' Teen 8000 m' 8000 m' Child 3700 m' 3700 m' Infant 1400 m' 1400 m' IRRIGATION RATES AND FRACTION OF IRRIGATION 1
1.109 DEFAULT RSNGS Irrigation Rate 2631/m'/ month 2631/m / month 2
. Time field has been irrigated prior to crop of 15 years 15 years interest Fraction of the year field is irrigated None None Fraction of animal water intake not obtained from None 0
. the irrigation system (Irrigated Meat)
Fraction of animal water intake not obtained from None 1
the irrigation' system (Irrigated Milk)
Page 2 of 3
r l
I MANUAL: CHEMISTFtY ADMINISTRATIVE NUMBER:
CAP-0002 l
PROCEDURES MANIJAL l
REVISION: 9 TITLE:
OFF-SITE DOSE CALCULAHON MANUAL PAGE: 46 of 74 QOSU FACTOR PARAMETERS (Continued) i TRANSIT. TRANSFER. AND I!OLDUP TIMES 1.109 DEFAULT RSNGS j
l Irrigated Stored Vegetables Holdup Time 1440 hrs 1440 hrs i
Irrigated Fresh Vegetables Holdup Tune 24 hrs 24 hrs Irrigated Milk Holdup Time 48 hrs 48 hrs Irrigated Meat Holdup Time 480 hrs 480 hrs Transit Time From Time Of Sample To Time Of None 72 hrs Release Transit Time To Drinking Water None 0 hrs DILUTIONS 1.109 DEFAULT RSNGS All Pathways None 1
(None)
Shore-Width Factor 0.2 0.2 i
MISCELLANEOUS l.109 DEFAULT RSNGS Fraction Of Leafy Vegetables Grown In Garden 1.0 1.0 OfInterest Fraction Of Produce Ingested Grown In Garden 0.76 0.76 OfInterest Crop Growing Time For Leafy Vegetables 60 Days 30 Days Ingested By Man Crop Growing Time For Pasture Grass 30 Days 30 Days l
Crop Yield For Leafy Vegetables Ingested By 2.0 kg/m 2.0 kg/m 2
2
{
Man l
i Crop Yield For Pasture Grass 0.7 kg/m 2.0 kg/m 2
2 l
l Page 3 of 3
M' MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 47 of 74 ATMOSPHERIC DISPERSION AND DEPOSITION PARAMETERS
~
~
GASEOUS EFFLUENT PATHWAYS 1994 CO~NTROLLING LOCATIONS **
l PATHWAY DIRECTION DISTANCE XLQ*
Dl.Q*
(sec/m')
(m-2)
Inhalation ENE 1038 M 8.lE-06 I
1038 M 4.8E-08 Ground ENE
,l.
Vegetation SSW 670 M 1.4E-05 2.8E-08 Cow Milk ENE 1038 M 8.lE-06 4.8E-08 Meat Animal S
195 M 1.2E-04 Meat Animal SSE 198 M 3.4E-07 Goat Milk SSW 2500 M 1.0E-06 1.7E-09 Site Boundary NNW 670 M 2.1E-05 for Gaseous Effluents g
l' i
' Based on meteorological data from January 1978 to December 1987.
- Based on 1994 Land Use Census.
l_
Page1of1 i
MANUAL CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 48 of 74
. SITE BOUNDARY FOR GASEOUS EFFLUENTS t
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MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 i
PROCEDURES MANUAL REVISION: 9 l
TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 49 of 74
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SITE BOUNDARY FOR LIOUID EFFLUENTS s
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MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 50 of 74
~
- ^ ~
~ HISTORICAL LIOUID SOURCE TERMS 1
OfGamma Emitters Of AllNuclides Ci Relative Relative Relative Relative Nuclide (pCi/ml)
Fraction Fraction H-3 4.45 E-04 n/a n/a 100.00 1.00 Cs-137 1.23 E-08
'1,00.00 1.00 2.76 E-05 2.76 E-05 TOTAL 4.45 E-04 100.00 1.00 100.00 1.00 Note Based on Retention Basin Effluent History of Rancho Seco from January 1,1993 through December 31,1994 i
4 Page1of1
. =
i MANUAL CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 51 of 74
-.- ~ 'LIOUID' MONITOR DETECTOR EFFICENCES R15017A & R15017B*
(Detector Model RD-53)
,I,
- l' Efficiency Nuclide epm /pCi/cc MO-99 3.47 EM7 I-l31 1.90 E+08 I-132 4.17 E+08 I-133 1.53 E+08 I-135 1.74 E+08 CS-134 3.25 E+08 CS-137 1.28 E+08 CR-51 1.85 E+07 MN-54 1.30 E+08 FE-59 1.26 E+08 CO-58 1.85 E+08 CO-60 2.40 E+08 ZN-65 6.49 EM7 SB-124 2.66 E+08 BA-140 8.98 E+07 LA-140 2.69 E+08 CE-141 7.68 E+07 j
CE-144 1.80 E+07 j
i
- From Calculation Z-RDM-10261 l
l l
I Page1of1
MANUAL CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 52 of 74 i
' ORGAN DOSE FACTORS FOR L10UID EFFLUENTS DOSE FACTOR TABLE 1 A(1) - Adult Units are mrem /hr per pC1/ml Nuclide Bone L!ver Tbody Thyroid Kidney 1,ung Gitract N-3 0.00E*00 1.215+01 1.215+01 1.218*01 1.21E*01 1.21E+01 1.215+01 C-14 3.82E*06 7.63E+04 7.638+04 7.635*04 7.634+04 7.633*04 7.638+04 NA-24 4.328+01 4.32s+01 4.323+0! 4.32E+01 4.32E+01 4.32t+01 4.32E+01 P-32 4.078+07 2.53E*06 1.57t+06 6.318-02 6.315-02 6.315-02 4.585+06 CR-51 3.00E*00 3.00E*00 8.998+00 6.66E*00 4.368*00 1.00E*01 1.468+03 MM-54 8.23E+02 3.31t*05 6.30Ee04 0.233+02 9.905+04 8.238*02 1.018606 MM-56 0.008*00 2.135-04 3.795-05 0.00B+00 2.705-04 0.005*00 6.795-03 FI-SS 1.108+04 8.173+03 1.91s*03 7.29E-04 7.298-04 4.568*03 4.698+03 FE-59 1,478+04 3 428*04 1.328*04 1.77s*02 1.77E*02 9.698+03 1.143+0S CD-58 2.368*02 ; 9.91E+02 a el.935*03 2.365*02 2.368+02 2.365+02 1.55E+04 j
CD-60 1.268+44 1.61B**04 3 2.025*04 1.26E*04 1.268+04 1.265*04 7.138*04 N1-63 3.42E+0S *2.37E*04 1.158*04 0.005 00 0.00E+00 0.00s 00 4.955+03 M1-65 8.668-04 1.125-04 S.135-05 0.00s 00 0.00E*00 0.00s+00 2.065 03 CU-64 8.905-02 7.028-01 3.775-01 0.905-02 1.645*00 8.908-02 S.24E+01 EM-65 7.63t+04 2.4 2E+0S 1.10E*06 4.463+02 1.623*05 4.465*02 1.52E+0S EN-69 0.00t*00 0.00E+00 0.00E+00 0.00E*00 0.00E*00 0.005*00 0.00E+00 BR-83 0.00E*00 0.00$*00 4.045-06 0.008*00 0.00E+00 0.00E*00 4.985-05 WR-04 0.00$*00 0.00E*00 0.008 00 0.00E*00 0.005 00 0.005*00 0.00E+00 1
SR-06 0.00E*00 0.005 00 0.008*00 0.00E+00 0.00E+00 0.00E*00 0.00B+00 RS-06 6.468+00 1.21E*05 S.628 04 6.465 00 6.468*00 4.465*00 2.345*04 l
KB-OS 0.00B+00 0.00E*00 0.00E+00 0.00E+00 0.00E*00 0.003+00 0.00E*00 KB-09 0.00E*00 0.00E*00 0.00E*00 0.00t*00 0.00t*00 0.00E*00 0.00E+00
$R-09 2.015+0S 6.252-02 S.7S8*03 6.251-02 6.258-02 6.2SB-02 3.225 04 80-90 S.715*06 6.163-03 1.S3t+06 6.168-03 4.165-03 6.16E-03 3.26E*0$
SR-91 S.598+00 1.193-01 3.408-01 1.195-01 1.195-01 1.198-01 2.628*01
)
SR-92 S.955-03 0.00E*00 2.588-04 0.00E*00 0.00E*00 0.005*00 1.185-01 Y-90 3.15E+00 6.943-02 1.525-01 6.948-02 6.943-02 6.943-02 3.275+04 Y-91M 0.00E+00 0.00E*00 0.00r+00 0.00s+00 0.00s+00 0.005 00 0.00s+00 Y-91 1.0SE*02 6.825-01 S.P.E*00 6.825-01 6.828-01 6.82E-01 1.07E+0S Y-92 1.728-05 4.248-06 4.625-06 4.24E-04 4.248-06 4.24E-04 2.208 01 Y-93 2.168-02 1.613-02 1.638-02 1.618-02 1.615-02 1.413 02 1.73t+02 22-95 1.821*02 1.64t+02 1.62t+02 1.668+02 1.698+02 1.568+02 2.675+04 3R-97 9.878-01 9.83E-01 9.025-01 9.028-01 9.03E-01 9.828-01 3.265+02 NS-95 S.168+02 3.275+02 2.17t+02 0.928*01 3.24t+02 0.028 01 1.448+06 MD-99 1.27E*00 1.04E+02 S.895+01 1.275+00 6.07E*02 1.27t*00 1.03Et02 TC-99M 0.238 04 1.031-03 s.741-03 7.11E-04 S.515-03 9.665-04 1.088-01 TC-101 0.002*00 0.00E*00 0.00E*00 0.00E*00 0.00E*00 0.005 00 0.00E*00 RU-103 6.765*02 7.021*01 3.31E*02 1.025*01 2.30E*03 7.02E+01 1.068+04 RU-10%
9.3SE-04 1.838-04 4.80E-04 1.835-04 9.913-03 1.038-04 4.60E-01 RU-106 1.618*04 2.953 02 2.30E*03 2.95E+02 3.045*04 2.95E+02 1.02E*06 AG-130M 2.63E+03 2.59E*03 2.37E*03 2.065*03 3.10E*03 2.065*03 2.1*E*05 TE-12SM 1.865+04 6.75E*03 2.49E*03 S.40E+03 7.578+04 9.215-01 7.435+04 TE-12?M S.268*04 1.88t*04 6.41t*03 1.345*04 2.145 05 S.S7E-02 1.16E*06 T5-127 6.068-01 2.103-01 1.318-01 s,493-01 2.47E*00 1.62E-04 4.99E*01 TE-129M 7.198+04 2.648&04 1.145*04 2.47E*04 3.00E*0S 1.31E*01 3.62t+0S TE-129 0.00E*00 0.00E+00 0.00t*00 0.005 00 0.00E*00 0.00E*00 0.00E*00 TE-131M 1.115 03 S.44t*02 4.548+02 8.688*02 S.4SE*03 S.645 00 S.34E+04 TE-131 0.00E+00 0.00g*00 0.00t+00 0.00E*00 0.00t+00 0.008+00 0.00E+00 78-132 6.30E+03 4.078 03 3.828*03 4.50s*03 3.928*04 3.138 00 1.938*05
. 130 3.148*00 1.625*00 3.51E*00 S.765*02 1.14E+01 0.313-01 6.448+00 1-131 7.068+02 1.00t*03 S.825*02 3.245*0$
1.718+03 1.47E*01 2.765*02 1-132 1.608-04 4.293-04 1.605-04 1.605 02 6.835-04 0.00E*00 8.055-05 l
1-133 1.60$+01 2.84t+01 9.452+00 4.01E*03 4.00E*01 1.135 00 2.$1E+01 1
1-134 0.005 00 0.00E*00 0.00E+00 0.00t*00 0.00E*00 0.001 00 0.00E*00 1-135 1.591-01 4.145 01 1.53E-01 2.13E+01 6.638-01 0.911 04 4.685-01 C5-134 4.448+0S 1.0SE*06 6.595 0%
4.03t.03 3.43E*06 1.16E*0$
2.235*04 c5-134 3.16t*04 1.245*06 0.95E+04 1.15s+02 6.92E*04 9.59E*03 1.428*04 c5-137 S.86t+0S 7.90E*05 S.2SE*05 6.06E+03 2.75t*05 9.54E 04 2.14E+04 Cs-130 0.00E*00 0.00E*00 0.005 00 0.00E*00 0.00E*00 0.005 00 0.00E+00 SA-131 0.005 00 0.00t*00 0.005 00 0.00Ee00 0.00Ee00 0.00E*00 0.00E*00 SA-140 4.90$*03 2.115+01 3.358*02 1.50E*01 1.715*01 1.0$8*01 1.01E*04 SA-141 0.008*00 0.00E*00 0.00E+00 0.00g*00 0.00E*00 0.005 00 0.00E+00 SA-142 0.00E+00 0.00E*00 0.00E*00 0.00g*00 0.00t*00 0.00E*00 0.00E*00 l
LA-140 4.14E*00 3.928*00 3.76t+00 3.71t+00 3.71E*00 3.71E*00 1.61E+04
(
LA-142 0.00E*00 0.00E*00 0.00E*00 0.00E*00 0.00E*00 0.003 00 6.295-06 CS-141 1.875+01 1.665+01 9.66E*00 0.905 00 1.20E*01 8.90E*00 2.548*04 I
CE-143 1.93E+00 1.428+02 1.16I*00 1.74t+00 1.01E+00 1.145*90 S.24E+03
(
CE-144 0.99E*02 4.00t*02 9.765*01 4.1SE*01 2.54E*02 4.1SE*01 2.90E*06 PR-143 7.308*00 2.96E*00 3.661-01 0.00t*00 1.115+00 0.00E*00 3.23t*04 P9-144 0.00E*00 0.00E*00 0.00t+00 0.00$*00 0.00t*00 0.00E+00 0.00E 00 ND-147 9.628*00 1.038 01 S.27t+00 4.958*00 0.11E*00
- 4. 96 t *00 2.598*04 W-101 2.03E+01 1.725 01 6.095*00 1.36t+00 1.3SE*00 1.358 00 S.20E*03 NP-239 3.70$*00 1.568 00 1.568*00 1,$55 00 1.59E*00 1.555 00 2.92t+03 Page1of4 1
i
" MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL i
REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 53 of 74 ORGAN DOSE FACTORS FOR LIOUID EFFLUENTS (Continued) -
+
DOSE FACTOR TABLE: A(i) - Teen Units are mrem /hr per WCi/ml Nuclide tone Liver Thedy Thyroid Kidney _
Lung G1 tract M-3 0.00E*00 1.375+01 1.378+01 1.378+0!
1.378+01 1.375+01 1.375*01 C-14 S.64s+0S 1.138+0S 1.13E+0S 1.138+0S 1.13E+0S 1.135*06 1.13E+0S
- NA-2 4 6.36E+01 6.368+01 6.365+01 6.368+01 6.365+01 6.368*01 6.368+01 P-32 4.44E*07 2.758+06 1.725+06 6.318-02 6.318-02 6.318-02 3.738+06 CR-51 1.02E+00 1.028+00 0.10E*00 S.31E+00 3.19E*00 1.00E+01 1.065+03 MM-54 4.20E+02 3.245*05 6.4S8*04 4.20E+02 9.69E*04 4.20E+02 6.635605 MH-56 0.00E+00 1.928-04 3.438-05 0.00E*00 2.43E-04 0.008+00 1.268-02 FI-SS 3.378+04 9.698*03 2.268+03 7.298-04 7.295-04 6.15E+03 4.198+03 FE-59 1.558*04 3 618+04 1.40E*04 1.00E+02 1.00E*02 1.15E+04 0.538+04
!!008+04 g CO-58 1.285+02 2.32E+03 1.28E*02 1.28E+02 1.20E+02 1.338+04 00-60 6.35E+03 1.10E*04 1.698+04 6.35E+03 6.3SE*03 6.3SE+03 6.71E*04 N!-63 4.50840S ' 3.188+04 1.53E+04 0.00E+00 0.008+00 0.008*00 S.068+03 N1-6S 3.195-04 1.058-04 4.775-OS 0.00E+00 0.00E+00 0.003+00 S.675-03 CU-64 0.6S8-02 9.2SE-01 4.00E-01 8.S$8-02 2.218+00 0.555-02 6.52E+01 EM-65
- 1. 568+ p4 2.625+05 1.228*06 2.29t+02 1.60t+0S 2.298+02 1.115+0S ZN-49 0.00E+00 0.00s+00 0.00E+00 0.00E*00 0.00E+00 0.00E+00 0.008+00
?
BR-03 0.00E*00 0.00s+00 4.935-05.0.00E*00 0.00E*00 0.00E+00 0.00E+00 AR-04 0.00E+00 0.00E+00 0.00E*00 0.003*00 0.00E+00 0.008+00 0.00E+00 SR-05 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E*00 0.00E*00 0.00E*00 RS-06 4.10E+00 1.40t+0S 6.568+04 4.108+00 4.10E+00 4.10E+00 2.075+04 Ra-08 0.00E*00 0.008*00 0.00E+00 0.00t+00 0.008*00 0.008*00 0.00E*00 RS-09 0.00E*00 0.00t+00 0.00E+00 0.00E+00 0.00E*00 0.00E*00 0,00E+00 SR-09 2.938+05 S.64E-02 8.30E+03 S.64I-02 S. 44 E.02 S.648-02 3.40E*04 3R-90 7.40E*06 6.165-03 1.90t*06 6.165-03 6.165-03 6.165-03 3.058*05 3R-91 S.73t+00 1.168-01 3.393-01 1.168-01.1.16E-01 1.165-01 2.565+0!
3R-92 S.SSE-03 0.00E+00 2.375-04 0.00s+00 0.00E+00 0.00E+00 1.428-01 Y-90 3.358+00 6.878-02 1.51E-01 6.075-02 6.075-02 6.475-02 2.71E+04 Y-91M 0.00t+00 0.00E+00 0.00E*00 0.00E+00 0.00t+00 0.00E+00 0.00E*00 Y-91 2.465+02 3.70E-01 6.91E*00 3.785-01 3.701-01 3.70E-01 1.01E*05 Y-92 1.648-05 4.20E-06 4.565-06 4.20E-06 4.20E-06 4.208-06 3.358-01 Y-93 2.138-02 1.578-02 1.595-02 1.575-02 1.575-02 1.575-02 1.70E+02 i
2R-95 1.198+02 9.678*01 9.348+01 0.625*01 1.028+02 8.62B+0!
2.42E+04 IR-97 9.415-01 9.378-01 9.378-01 9.368-01 9.308-01 9.365-01 2.63B+02 NS-95 4.73E+02 2.52E+02 1.755+02 4.468+01 2.75E+02 4.468+01 1.025+06 MD-99 6.368-01 4.328*02 0.20E+01 6.36E-01 9.07t+02 6.368-01 7.738+02 TC-99M t.S45-04 1.138-03 6.355-03 6.905-04 7.20E-03 9.40E-04 2.075-01 TC-101 0.00E+00 0.00E+00 0.00E+00 0.001*00 0.00E*00 0.008+00 0.00E+00 RU-103 5.868+02 3.515+01 2.715+02 3.51E*01 1.9tE*03 3.515+0!
4.61E*04 RU-10$
0.005-04 1.818-04 4.S25-04 1.015-04 9.005-03 1.81E-04 S.6SE-01 RU-106 1.69E+04 1.4B5+02 2.14E+03 1.4 0t +02 3.06t+04 1.48E+02 7.57E+0S AG-110M 1.078+03 1.03E.03 1.53E+03 1.06t+03 2.53E+03 1.06E*03 2.178+0S TE-12SM 2.065*04 1.42E+03 2.75E*03 S.755+03 4.81E-01 4.818-01 6.075*04 1E-127M S.93E*04 2.10E*04 7.05E+03 1.41t*04 2.40E+0S 2.938-02 1.40E*05 T5-127 6.631-01 2.125-01 1.41E-01 4.515-01 2.64E+00 1.475-04 S.048+01 T8-129M 7.76E*04 2.88E*04 1.23E+04 2.50t+94 3.24E*05 1.70E*00 2.91E+0S75-129 0.00B+00 0.00t*00 0.00E+00 0.00t+00 0.00E+00 0.008*00 0.00E*00 75-131M 1.10E*03 S.675+02 4.74t*02 0.50$+02 S.06E*03 S.20t+00 4.51E+04 T5-131 0.00E*00 0.00E*00 0.00E*00 0.00E*00 0.00E*00 0.00E+00 0.00E*00 T5-132 6.585+03 4.171*03 3.928*03 4.40E+03 4.00E*04 3.07E*00 1.325+05 I-130 3.40t+00 9.85t+00 4.268+00 7.06t+02 1.41E*01 0.005-01 7.4SE*00 1-131 9.72E+02 1.368+03 7.335*02 3.938*05 2.33E+03 1.068*01 2.775+02 1-132 1.465-04 3.018-04 1.378-04 1.29E-02 6.015-04 0.00E+00 1.668-04
]
1-133 2.275+01 3.77E*01 1.22E*01 S.12B+03 6.545 01 1.068+00 2.80E+01 I-134 0.00E*00 0.00E*00 0.00E+00 0.00t*00 0.00E*00 0.005*00 0.008+00 1-136 1.051-01 4.768-01 1.718-01 3.06E+01 7.625-01 4.45E-04 S.265-01 C3-134 S.045*05 1.188+06 S.50E*05 2.03I*03 3.778+0S 1.45E+0S 1.67E*04 C3-136 3.278+04 1.20E+0S 0.625*04 1.755+01 6.99E*04 1.11E*04 1.048+04 i
C3-137 4.99E*06 9.30E*05 3.265*05 3.03E+03 3.188+0S 1.268+0S 1.62s+04 C3-130 0.00E+00 0.00E*00 0.00E*00 0.00E+00 0.002+00 0.00E*00 0.008+00 DA-139 0.00E*00 0.00t+00 0.00E*00 0.00E*00 0.005+00 0.005+00 2.948-06 BA-14 0 -
S.34t*03 1.64E*01 3.63E*02 9.07E+00 1.21E*01 1.43E+01 4.23E+03 BA-141 0.00E*00 0.00E+00 0.00E+00 0.00E*00 0.005*00 0.00E*00 0.00E*00 SA-142 0.00E+00 0.00E+00 0.00t*00 0.00t*00 0.00$+00 0.003 00 0.00B+00 LA-140 2.30E*00. 2.00E*00 1.91E*00 1.0St*00 1.055*00 1.055*00 1.278*04 LA-142 0.00E*00 0.00E*00 0.00E*00 0.00t+00 0.00E*00 0.00E+00 2.358-0$
CE-141
. 3.69E+01 1.30t+01 6.0SE*00 S.1SE*00 0.045*00 S.15E+00 2.25t*04 l
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I l
Page 2 0f 4 l
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MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 54 of 74 ORGAN DOSE FACTORS FOR LIOUID EFFLUENTS (Continued)
DOSE FACTOR TABLES A(1) - Child Units are mrem /hr per pCi/ml Nucinde Bone Liver Tbody,,,_Thyoid Kidne,y, 1.ung Gittact N-3 0.008*00 2.10E+01 2.108+01 2.10E*01 2.118*01 2.10E+01 2.10E+01 C-14 1.298+06 2.565+0S 2.$68+0S 2.$68+0S 2.S63+0S 2.565*05 2.568+0S NA-24 1.165+02 1.16E+02 1.165*02 1.16B+02 1.168*02 1.16E+02 1.165+02 P-32 S.748*07 2.695+06 2.21E+06 - 8.84 8-03 8.848-03 0.848-03 1.595+0?
CR-61 2.548 01 2.545-01 7.95E+00 4.S2E+00 1.42t+00 0.05E+00 4.08t+02 MW 54 S.84t*01 2.S38*05 6.74E+04 S 888+01 7.10E*04 S.89t+01 2.128+0S MN-56 0.008 00 2.518-04 S.685-05 0.00E+00 3.043-04 0.005+00 3.648-02 FI-SS 2.40E*04 1.273+04
- 3. 94 s+03 1.023-04 1.028-04 7.195+04 2.35t+03 FI-59 2.21E*04 3.588+04 1.788+04 1.405 01 1.40S*01 1.048+04 3.728+04 CO-50 1.79t+01 1.285*03 3.888*03 1.79E*01 1.198+01 1.79E*01 7.388+03 CD-60
- 8. 89E*02 ' 7. 518+03 ',2.04 E+04 0.898+02 8.86E+02 8.898+02 3.765+04 NI-63 1.022+04'.S.'4 85+04 ' 3. 40E*04 0.00t+00 0.00E+00 0.00E*00 3.695+03 NI-65 1.52E-03 1.435-04 0.355-05 0.00t+00 0.00$+00 0.00E+00 1.758-02 CU-64 1.208-02 1.278+00 7.705-01 1.20E-02 3.0$E+00 1.20E-02 S.89t+01 EW-65 9.538*04 2.54t*05 1.588 0%
3.218+01 1.60t+0S 3.218*01 4.46t*04 2N-69 0.00t+06 ' O.00t+00 0.00t+00 0.00s*00 0.00s+00 0.00t+00 0.00E+00 BR-83 0.008+00 0.00t+00 9.588-05 0.00E*00 0.00$*00 0.00E*00 0.008+00 BR-84 0.00E*00 0.008+00 0.00E*00 0.00E*00 0.008*00 0.00E+00 0.00E+00 SR-85 0.00t+00 0.00t+00 0.00E*00 0.00E+00 0.008*00 0.008+00 0.00E+00 RS S 748-01 1.618+0S 9.80s*04 S.74E-01 S.745-01 S.748 01 1.03E+04 RS-80 0.00E*00 0.00E*00 0.00E+00 0.00t+00 0.00E*00 0.00E+00 0.00t*00 R8-89 0.00t+00 0.00E*00 0.00E*00 0.00s+00 0.00E+00 0.00E*00 0.00E+00 SR-89 6.488+0S 7.905 03 1.8SE+04 7.908-03 1.903-03 7.908-03 2.S1E+04 3R-90 1.47E*07 8.625-04 3.935 06 0.625-04 0.428-04 8.62E-04 2.978+0S 5R-91 1.048+01 1.625 02 4.065-01 1.623-02 1.628-02 1.625-02 2.28t+01
$R-92 1.02E-02 0.00E+00 4.095-04 0.00E+00 0.00E*00 0.00s+00 1.93E-01 Y-90 4.28t+00 9.628-03 1.245-01 9.625-03 9.628-03 9.628-0J 1.22E*04 Y-91M 0.00t+00 0.00E*00 0.00t*00' O.00s*00 0.00E*00 0.00t*00 0.005+00 Y-91 4.49E*02 S.293-02 1.21E*01 S.295-02 S.298-02 S.298 02 S.988*04 Y-92 2.315-06 0.00E+00 1.235-06 0.00E+00 0.008+00 0.00t+00 6.508-01 Y-93 1.055-02 2.201-03 2.435-03 2.20E-03 2.20E-03 2.205-03 1.24s+02 29-95 8.32E*01 2.77t+01 2.60E*01 1.21E*01 3.458+01 1.21t*01 1.63E+04 ER-97 1.40E-01 1.328-01 1.325-01 1.313-01 1.338-01 1.31E-01 1.90E+02 NS-95 S.20E+02 2.065+02 1.49E*02 6.25s+00 1.945*02 6.2SE+00 3.705*06 MO-99 I.90E-02 7.015+02 1.73E*02 8.903-02 1.60E*03 8.908-02 S.00t+02 TC-99M 4.345-04 7.545-04 1.108-02 9.778-05 9.698-03 4.338 04 3.768-01 TC-101 0.00E+00 0.00E+00 0.00t+00 0.00E*00 0.00E*00 0.00E*00 0.008+00 RU-103 1.02E+03 4.925*00 3.96E*02 4.925*00 2.57E*03
- 4. 92 E *00 2.63E+04 RU-105 1.313-03 2.533-05 4.903-04 2.53E-05 1.135-02 2.S33-05 8.35E-01 RU-106 3.188+04 2.078+01 3.988+03 2.01E*01 4.298+04 2.07E*01 4.948*05 AG-110M 1.79E+03 1.26s+03 1.04s+03
- 1. 4 0 t *02 2.22E*03 1.488+02 1.32E+0S TE-12SM 3.04E*04 8.258*03 4.068 03 8.54t*03 4.738-02 6.735-02 2.94t+04 ft-127M 9.30E*04 2.50t+04 1,10E*04 2.22E+04 2.64E+0S 4.106-03 7.531 04 TI-127 8.943-01 2.41E-01 1.925-01 6.195 01 2.548*00 2.201-05 3.498+01 TE-129M 1.095+0S 3.0$E+04 1.70E*04 3.528 04 3.213 05 1.09t+00 1.338+0S TI-129 0.00t+00 0.00E*00 0.00E*00 0.005+00 0.00t+00 0.00E*00 1.145-06 78-131M 1.40t+03 S.13t+02 S.468 02 1.0$5+03 4.96t+03 7.283-01 2.088+04 T5-131 0.00t+00 0.00E+00 0.00E*00 0.00E*00 0.003 00 0.00E*00 0.00E+00 75-132 8.15E+03 3.41E*03 4.365+03 S.268*03 3.3SE*04 4.308-01 3.638*04 1-130 6.365*00 1.278+01 6.625*00 1.39E+03 1.90t+01 1.135-01 6.02E*00 I-131 2.06E+03 2.07t*03 1.185 03 6.845*05 3.40E+03 1.51E+00 1.865+02 1-132 2.60s-04 4.78E-04 2.208-04 2.225-02 7.328 04 0.00E*00 S.43E-04 1 333 4.6St+01 S.74E+01 2.198+01 1.065+04 9.56t*01 1.495-01 2.32E+01 1-134 0.005*00 0.008*00 0.00t+00 0.00E+00 0.70t*00 0.00E+00 0.00E*00 1-135 3.193-01 6.82E-01 3.235 01 6.04t*01 1.05E+00 6.248-05 S.205-01 CS-134 7.61E*05 1.2SE*06 2.64t+0S 2.95t+02 3.87E*06 1.39E*05 7.028*03 CS-136 4.145*04 1.14E+0S 7.375 04 1.09t*01 6.06t+04 9.05t+03 4.01E+03 C5-137 1.12E+06 1.07E*06 1.598*05 4.2SE*02 3.50t+0S 1.268+0S 1.155*03 C3-138 0.00E*00 0.00E+00 0.00t+00 0.00t+00 0.008+00 0.00E*00 0.00E+00 EA-139 0.00E+00 0.00E*00 0.00E*00 0.00t+00 0.00E+00 0.00E*00 3.518 0S BA 140 0.64E+03 8.95E+00 6.0SE*02 1.388+00 3.8St+00 S.09E+00 4.385+03 BA-141 0.00E*00 0.00t*00 0.00t+00 0.00E*00 0.008*00 0.00E*00 0.00t*00 SA-142 0.008*00 0.00t*00 0.00t+00 0.00E+00 0.00E+00 0.00E*00 0.00E*00 LA 140 8.308-01 4.598-01 3.278-01 2.69E-01 2.598-01 2.595-01 S.565+03 LA-142 0.00k*00 0.00t+00 0.00E*70 0.00E*00 0.00E*00 0.00E+00 1.99E-04 CE-141 2.048+01 1.0St+01 2.18t+00 7.218-01 S.03t+00 7.21E-01 1.23E*04 rg-141 4,858-01 1.428+02 2.441-01 2.238-01 2.038-01 2.231-01 2.088+03 C5-144 '
2.398 03 7.91E*02 1.30E+02 2.971 00 4,178+02 2.978+00 1.95t*05 l
PR-143 1.11t*01 3.33E*00 S.51E-01 0.00E*00 1.80E+00 0.00s+00 1.205+04 PR-144 0.00E*00 0.00E+00 0.00E*00 0.00E*00 0.00E+00 0.00E*00 0.00t*00 ND-147 7.38E*00 6.04t.00 7.868-01 3.47E-01 3.4?t*00 3.477-01 9.02t+03 W-147 2.65E+01 1.588+01 7.171+00 1.775 01 1.771-01 1.771-01 2.19E*03 NP-239 4.001-01 2.031-01 1.998-31 1.68t-01 2.328-01 1,985-01 1.138*01 t
l Page 3 of 4 L
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{
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 55 of 74
' ORGAN DOSE FACTORS FOR LIOUID EFFLUENTS (Continued)
DOSE FACTOR TABLE: A(1) - Infant Units are mrem /hg per WC1/ml
..Nuclide Bone 1.1ver tbody Thyroid Kidney 1,ung G1 tract N-3 0.00B+00 1.14t*01 1.14E+01 1.14t*01 1.148*01 1.148*01 1.148+01 C-14 5.80t+0S 1.245*05 1.24E+05 1.24s+0S 1.248*05 1.24t+0S 1.24t+0S NA-24 1.74E+02 1.76E*02 1.765+02 1.76E+02 1.768+02 1.76E+02 1.768+02 P-32 9.00t+05 S.298+04 3.495+04 0.00t+00 0.00t+00 0.00B+00 1.225*04 CR-51 0.00E+00 0.00B+00 7.825 01 S.108-01 1.128-01 9.938-01 2.20E+01 i
MN-54 0.00s+00 1.68t*02 3.02t+01 0.008600 3.73E+01 0.00E+00 6.10t+01 MN-56 0.008+00 1.225 06 0.00E*00 0.00E*00 1.058-06 0.008+00 1.115-04 FI-55
$.61E+02 3.63t+02 9.69t*01 0.008*00 0.00E+00 1.77E*02 4.61E*01 FS-69 1.04E+03 1.$18+03 7.14E+02 0.00E+00 0.00t+00 S.365*02 0.665+02 Co-58 0.008+00, 1.00B+02. 2.705+02 0.008*00 0.00E*00 0.00t+00 2.70E*02 CO-60 0.008+00,
- 3. 818'+ 02. 8.998+02 0.00B+00 0.00E+00 0.00t+00 9.068+02 N!-63 1.72t+0S *1.06t+04 S.97E*03 0.00t+00 0.00E+00 0.00E+00 S.293*02 NT-65 1.478-04 1.665-05 7.565-06 0.00B+00 0.00t+00 0.00E*00 1.273-03 CU-64 0.00E+00 2.29t*00 1.068*00 0.008*00 3.87t+00 0.00E*00 4.70E+01 1N-65 3.028+0) 1.038*06 4.775+04 0.00E*00 5.028*04 0.005+00 8.743*04 ZM-69 0.00E+00 0.00C+00 0.00E*00 0.00E*00 0.008+00 0.00E*00 0.008*00 BR-61 0.00E+00 0.00E*00 4.158-01 0.008+00 0.00E*00 0.00E+00 0.00t*00 BR-84 0.00E*00 0.00E*00 0.00E*00 0.00E*00 0.00E*00 0.00t+00 0.00g*00 BR-85 0.00l+00 0.00t*00 0.00E+00 0.00E*00 0.00t*00 0.00E*00 0.008*00 Ra-86 0.008*00 1.14t*06 S.6SE*04 0.00t*00 0.00$*00 0.00$+00 2.92E+03 RS-84 0.00E*00 0.00E*00 0.00E*00 0.00E*00 0.008*00 0.00t+00 0.00E*00 RS-89 0.00t*00 0.00t*00 0.00E*00 0.00E+00 0.00E+00 0.00t+00 0.00t+00 SR-89 5.578*04 0.00t*00 1.66E+03 0.00E*00 0.00E*00 0.00t+00 1.19t*03 SR-90 3.91t*05 0.00t*00 1.0SE*05 0.00$+00 0.00E+00 0.00E*00 7.228*03 3R-91 4.01E*00 0.00E+00 1.451-01 0.00S+00 0.008+00 0.00$+00 4.758*00
$R-92
- 1. 8 4 E-04 0.00E*00 6.838-06 0.00E+00 0.00l+00 0.00E+00 1.908-03 Y 90 4.555-03 0.00I+00 1.228-04 0.00t+00 0.00E+00 0.002*00 6.28E+00
" 91M 0.00t+00 0.00B+00 0.00E+00 0.00E*00 0.00t+00 0.005+00 0.00E+00 Y-91 3.325-01 0.00$*00 S.838-03 0.00E+00 0.00E+00 0.00E+00 2.388+01 Y-92 0.00$+00 0.00t+00 0.005+00 0.008*00 0.00t+00 0.00E*00 3.318-04 Y-93 3.065-05 0.00t+00 0.00E+00 0.00t+00 0.00s+00 0.00E+00 2.428-01 2R-95 3.068-02 1.458-03 S.285-03 0.00t+00 0.038-03 0.005+00 3.71E+00 ER-97 4.315-0S 7.40E-06 3.385-06 0.008+00 1.465-06 0.005+00 4.725-01 NS-95 2.815+00 1.168*00 6.70s-01 0.00t+00 0.115-01 0.008+00 9.705+02 MO-99 0.00t+00 1.388+03 2.698*02 0.00E+00 2.068+03 0.00E*00 4.5SE+02 TC-99M S.618-04 1.168-03 1.49E-02 0.00E+00 1.258-02 6.05E-04 3.368-01 TC-101 0.00E+00 0.003+00 0.00E+00 0.00t+00 0.00t*00 0.00t+00 0.00E+00 RU.103 4.08E-02 0.00t+00 1.378-02 0.00E*00 8.60E-02 0.00s+00 4.978-01 RU-105 0.00E*00 0.00t*00 0.00E*00 0.00t*00 1.525-06 0.00E*00 8.258-05 RU-106 8.40E-01 0.00E*00 1.05E-01 0.00E*00
- 9. 94 E-01 0.00t*00 6.385+00 M-110M 1.01E*03 1.32E*03 8.74t+02 0.00E+00 1.89E*03 0.00t*00 6.85E+04 i
TE 125M t.481*02 2.83E*02 1.15t+02 2.tSt+02 0.00E+00 0.00E+00 4.04t*02 1
75-127M 2.628 03 8.69t*02 3.17E*02 7.57E*02 6.45t*03 0.00E*00 1.06t*03 1
TE-127 9.618-02 3.22E-02 2.078-02 7.822 02
- 2. 3 4 E -01 0.00s+00 2.025*00 TE 129M
).058+03 1.058*03 4.10E*02 1.175+03 7.63E*03 0.00t*00 1.028*03 i
TE-129 0.00t*00 0.00E+00 0.00E*00 0.00t+00 0.00E+00 0.00t*00 0.00E+00 TE-131M 2.87t+01 1.16E*01 9.658 00 2.34t+01 7.965*01 0.00E+00 1.968+02 1
75-131 0.00E+00 0.00E+00 0.00$+00 0.00E+00 0.00E+00 0.006*00 0.008+00 78-132 1.41t*02 6.90E+01 6.61E*01 1.03E+02 4.365*02 0.00t+00 2.581*02 I-130 8.92E+00 1.968*01 1.00I+00 2.20t+03 2.168*01 0.00E+00 4.218+00 i
1-131 3.075*03 3.61R*03 1.$98+03 1.19t*06 4.22t+03 0.00t+00 1.298+02 I
1-132 1.308-05 2.643-06 9.415-06 1.245-03 2.958-05 0.00s+00 2.144-05 1-133 6.998+01 1.028*02 2.98t+01 1.05E+04 1.20E*02 0.00E*00 1.72E+01 1-134 0.00$*00 0.00t*00 0.00f*00 0.00t*00 0.00E*00 0.00E+00 0.008+00 1-13S 4,238-01 E.41E-01 3.075-01 7.54t+01 9.308-01 0.00t*00 3.048-01 C3-134 1.55E+05 2.898+0% 2.925*04 0.00t*00 1.43t+04 3.05E+04 7.84t*02 CS-136 1.05E*04 3.00E*04 1.1$$*04 0.00t+00 1.23E+04 2.51E*03 4.67t*02 CS-137 2.328*05 2.71t*05 1.92E+04 0.005 00 1.27E*04 2.94E*04 8.473+02 C3-130 0.00E+00 0.00t+00 0.008*00 0.00t*00 0.00E*00 0.00E*00 0.00t+00 BA-139 0.00E*00 0.00E*00 0.00E*00 0.00E+00 0.00t+00 0.008*00 0.00E*00 BA-140 1.268+03 1.288 00 6.61E*01 0.00t*00 3.058-01 1.005-01 3.16t+02 SA-141 3.00E+00 0.00t*00 0.00B*00 0.00E+00 0.00$*00 0.008*00 0.00t+00 SA 142 0.00E+00 0.00E+00 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00t+00 LA-140 3.05E 04 1.20E-04 3.09E-06 0.005 00 0.00t+00 0.005+00 1.41t*00 LA-142 0.00E*00 0.00$+00 0.00E*00 0.00E*00 0.00E*00 0.005 00 0.00E*00 CE-141 2.078-01 1.265+01 1.49E-02 0.008+00 3.093-02 0.00t+00 6.628+01 CE-143 3.20E-03 2.12E*00 2.42E-04 0.00t+00 6.195-04 0.00E*00 1.24E+01 l
CE-14 4 -
9.825+00 4.025*00 5.505-01 0.00s 00 1.628*00 0.00E+00 S.63E+02 PR-143 7.865-03 2.948-03 3.90E-04 0.00s+00 1.095-03 0.00E*00 4.168+00 PR-144 0.00E+00 0.00E*00 0.00$+00 0.00E*00 0.00E+00 0.00t*00 0.00B+00 ND-147 4.815-03 4.948-03 3.025-04 0.00t+00 1.908-03 0.00E+00 3.135+00 W6187 5.$58-01 3.848-01 1.338-01 0.00E+00 0.00t+00 0.00E*00 2.275+01 NP 239 2.518-04 2.248-0S 1.275-05 0.00E*00 4.475-05 0.008+00 6.40E-01 Page 4 of 4 I
MANUAL
- CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9
- TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 56 of 74
.. - GASEOUS MONITOR DETECTOR EFFICIENCIES R15044, R15045, and R15546A (Detector Model RD-52) 1
'.l5 Efficiency
- cpm /pCi/cc l
Nuclide KR-83M 0.0 KR-85M 7.30 E+07 KR-85 7.19 E+07 KR-87 8.70 E+07 KR-88 8.70 E+07 KR-89 8.70 E+07 KR-90 8.70 E+07 XE-131M 0.0 XE-133M 0.0 XE-133 2.94 E+07 XE-135M 0.0 XE-135 7.75 E+07 XE-137.
8.70 E+07 XE-138 8.70 E+07 AR-41 7.80 E+07
- From Calculation Z-RDM-10261 4
i l 0 j
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MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 57 of 74 l
_: DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS s'
FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES Dose to Peoplet Dose to Air
- Gansna-Body Beta-Skin Gansna Beta Nuclide K(i)
L(1)
M(i)
N(i)
AR-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 KR-83M 7.56E-02 0.00E+00 1.93E+01 2.88E+02 KR-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 KR-85M 1.17E+03 1.46E+03 1.23E+03 1.97E+03 KR-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 KR-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 KR-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 KR-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 XE-131M 9.15E+01 4.76E+02 1.56E+02 1.11E+03 XE-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 XE-133M 2.51E+02 9.94E+02 3.27E+02 1.48E+03 XE-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 i
XE-135M 3.12E+03 7.11E+02 3.36E+03 7.39E+02 XE-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 XE-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 t -- mrem /yr per pCi/m'
- -- mrad /yr per pCi/m' i
I 1 Page1of1
l l
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 l
TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 58 of 74
. ORGAN DOSE FACTORS FOR GASEOUS EFFLUENTS l
Adt11t, inhalation DOSE FACTOR TABLE: R(i)
Units are mrem /yr per pCi/m' Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.00E+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 CR-51 0.00E+00 0.00E+00 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 MN-54 0.00E+00' 3.96E+0'4, 6<30E403 0.00E+00 9.84E+03 1.40E+06 7.74E+04 FE-55 2.46E+04 1.70E+04 3.95E+03 0.00E+00 0.00E+00 7.21E+04 6.03E+03 II-59 1.18E+04 2.78E+04 1.06E+04 0.00E+00 0.00E+00 1.02E+06 1.88E+05 CO-58 0.00E+00 1.58E+03 2.07E+03 0.00E+00 0.00E+00 9.28E+05 1.06E+05 CO-60 0.00E+00
-1.T5E+04 1.48E+04 0.00E+00 0.00E+00 5.97E+06 2.85E+05 ZN-65 3.24E+04 1.03E+05 4.66E+04 0.00E+00 6.90E+04 8.64E+05 5.35E+04 J
SR-89 3.04E+05 0.00E+00 8.72E+03 0.00E+00 0.00E+00 1.40E+06 3.50E+05 SR-90 9.92E+07 0.00E+00 6.10E+06
- 0. 00E+ 00 0.00E+00 9.60E+06 7.22E+05
)
ZR-95 1.07E+05 3.44E+04 2.33E+04 0.00E+00 5.42E+04 1.77E+06 1.50E+05 I-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 0.00E+00 6.28E+03 I-133 8.64E+03 1.40E+04 4.52E+03 2.15E+06 2.59E+04 0.00E+00 8.88E+03 CS-134 3.73E+05 8.40E+05 7.2EE+05 0.00E+00 2.87E+05 9.76E+04 1.04E+04 CS-136 3.91E+04 1.46E+05 1.10E+05 0.00E+00 8.56E+04 1.20E+04 1.17E+04 CS-137 4.79E+05 6.21E+05 4.28E+05 0.00E+00 2.23E+05 7.52E+04 8.40E+03 BA-140 3.91E+04 4.91E+01 2.57E+03 0.00E+00 1.67E+01 1.27E+06 2.18E+05 CE-141 1.99E+04 1.35E+04 1.53E+03 0.00E+00 6.27E+03 3.62E+05 1.20E+05 CE-144 3.43E+06 1.43E+06 1.84E+05 0.00E+00 8.48E+05 7,78E+06 8.16E+05 DOSE FACTOR TABLE: R(i)
Teen, inhalation, Units are mrem /yr per pCi/m' Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.00E+00 1.27E+03 1.27E+03 1.27E+33 1,27E+03 1.27E+03 1.27E+03 CR-51 0.00E+00 0.00E+00 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03 MN-54 0.00E+00 5.11E+04 8.40E+03 0.00E+00 1.27E+04 1.98E+06 6.68E+04 FE-55 3.35E+04 2.39E+04 S.55E+03 0.00E+00 0.00E+00 1.24E+05 6.39E+03 FE-59 1.59E+04 3.70E+04 1.43E+04 0.00E+00 0.00E+00 1.53E+06 1.78E+05 CO-58 0.00E+00 2.07E+03 2.78E+03 0.00E+00 0.00E+00 t 34E+06 9.52E+04 Co-60 0.00E+00 1.51E+04 1.98E+04 0.00E+00 0.00E+00 8.72E+06 7.59E+05 ZN-65 3.86E+04 1.34E+05 6.24E+04 0.00E+00 8.64E+04 1.24E+06 4.67E+04 SR-89 4.35E+05 0.00E+00 1.25E+04 0.00E+00 0.00E+00 2.42E+06 3.71E+05 SR-90 1.08E+09 0.00E+00 6.68E+06 0.00E+00 0.00E+00 1.65E+07 7.65E+05 l
l ZR-95 1.46E+05 4.59E+04 3.15E+04 0.00E+00 6.74E+04 2.69E+06 1.;9E+05 I-131 3.55E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 0.00E+00 6.49E+03 1-133 1.22E+04 2.05E+04 6.23E+03
- 2. 92E+ 06 3.59E+04 0.00E+00 1.03E+04 CS-134 5.03E+05 1.13E+06 5.49E+05 0.00E+00 3.75E+05 1.46E+05 9.76E+03 i
CS-136 5.15E+04 1.94E+05 1.37E+05 0.00E+00 1.10E+05 1.78E+04 1.09E+04 CS-137 6.71E+05 8.4eE+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 j
BA-140 5.47E+04 6.71E+01 3.C2E+03 0.00E+00 2.28t+01 2.03E+06 2.29E+05 CE-141 2.84E+04 1.90E+04 2.17E+03 0.00E+00 0.88E+03 6.14E+05 1.26E+05 CE-144 4.89E+06 2.02E+06 2.63E+05 0.00E+00 1.21E+06 1.34E+07 8.64E+05
- 2 i
Page1of2
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MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL t
i REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 59 of 74 ORGAN DOSE FACTORS FOR GASEOUS EFFLUENTS (Continued) 2 DOSE FACTOR TABLE: R(i)
Child, inhalation 3
Units ar_ mrem /yr per pCi/m Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.00E+00 1.13E+03 1.13E+03 1.13E+03 1.13E+03 1.13E+03 1.13E+03 CR-51 0.00E+00, 0.00E+0,0 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 HN-54 0.00E+00 4.29E+04 9.51E+03 0.00E+00 1.00E+04 1.58E+06 2.29E+04 FE-55 4.74E+04 2.52S+04 'T.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87t+03 FE-59 2.07E+04 3.35E+04 1.67E+04 0.00E+00 0.00E+00 1.27E+06 1.07E+04 CO-58 0.00E+00 1.77E+03 3.16E+03 0.00E+00 0.00E+00 1.11E+06 3.44E+04 Co-60 0.00E+00 1.J1E+04 2.27E+04 0.00E+00 0.00E+00 7.07E+06 9.62E+04
)
ZN-65 4.26C+04 1.13E+05-7.03E+04 0.00E+00 7.14E+04 9.96E+05 1.63E+04 SR-89 6.00E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 l
SR-90 1.01E+08 0.00E+00 6.44E+06 0.00E+00 0.00E+00 1.48E+07 3.44c+05 ZR-95 1.90E+05 4.18E+04 3.'0E+04 0.00E+00 5.96E+04 2.23E+06 6.11E+04 I-131 4.81E+04 4.81E+04 2.e3E+04 1.63E+07 7.88E+04 0.00E+00 2.84E+03 I-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.00E+00 5.48E+03 CS-134 6.51E+05 1.01E+06 2.25E+05- 0.00E+00 3.31E+05 1.21E+05 3.85E+03 CS-136 6.51E+04 1.71E+05 1.16E+05 0.00E+00 9.55E+04 1.45E+04 4.18E+03 CS-137 9.07E+05 8.25E+05 1.28E+05 0.00E+00 2.82E+05 1.04E+05 3.62E+03 BA-140 7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.11E+01 1.74E+06 1.02E+05 CE-141 3.92E+04 1.95E+04 2.90E+03 0.00E+00 8.55E+03 5.44E+05 5.66E+04 CE-144 6.77E+06 2.12E+06 3.62E+05 0.00E+00 1.17E+06 1.20E+07 3.89E+05 DOSE FACTOR TABLE: R(i)
Infant, inhalation i
Units are mrem /yr per pCi/m' Nuclide Bone Liver Tbody Thyroid Kidney Lung Gitract H-3 0.00E+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 CR-51 0.00E+00 0.00E+00 8.95E+01 5.76E+01 1.32E+01 1.28E+04 3.57E+02 HN-54 0.00E+00 2.54E+04 4.99E+03 0.00E+00 4.99E+03 1.00E+06 7.06E+03 FE-S$
1.97E+04 1.18E+04 3.33E+03 0.00E+00 0.00E+00 8.70E+04 1.10E+03 FE-59 1.36E+04 2.35E+04 9.48E+03 0.00E+00 0.00E+00 1.02E+06 2.48t+04 Co-58 0.00E+00 1.22E+03 1.82E+03 0.00E+00 0.00E+00 7.77E+05 1.11E+04 Co-60 0.00E+00 8.03E+03 1.18E+04 0.00E+00 0.00E+00 4.51E+06 3.19E+04 i
EN-65 1.93E+04 6.26E+04 3.11E+04 0.00E+00 3.25E+04 6.47t+05 5.14E+04 SR-89 3.98E+05 0.00E+00 1.14E+04 0.00E+00 0.00E+00 2.03E+06 6.40E+04 SR-90 4.09E+07 0.00E+00 2.59E+06 0.00E+00 0.00E+00 1.12E+07 1.31E+05 ZR-95 1.15E+05 2.79E+04 2.03E+04 0.00E+00 3.11E+04 1.75E+06 2.17E+04 I
I-131 3.80E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.00E+00 1.06E+03 I-133 1.32E+04 1,92E+04
- 60E+03 3.56E+06 2.24E+04 0.00E+00 2.16E+03 CS-134 3.96E+05 7.03E+05 7.45E+04 0.00E+00 1.90E+05 7.97E+04 1.33E+03 CS-136 4.83E+04 1.35E+05 5.29E+04 0.00E+00 5.64E+04 1.18E+04 1.43E+03 CS-137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+05 7.13E+04 1.33E+03 BA-140 5.60E*0(
5.60E+01
- 2. 90E'. 03 0.00E+00 1.34E+01 1.60E+06 3.84E+04 CE-141 2.77E+04 1.67E+04 1.99E+03 0.00E+00 5.25E+03 5.17E+05 2.16E+04 CE-144 3.19E+06 1.21E+06 1.76E+05 0.00E+00 5.38E+05 9.85E+06 1.48E+05 l
' 2 Page 2 of 2
.-.-. - -. - - - - - - - ~ ~. - -
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 60 of 74 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION -
>u Minimum Number of Channels Instrument Operable Action i
1.
Gross Radioactivity Monitors Providing AutomaticTermination ofRelease
'u Retention Basin Emuent Discharge -
Monitor (R15017A) 1 With the monitor inoperable, emuent releases may be resumed provided that prior to initiating a release from the retention basin:
- 1) At least two independent samples are analyzed in accordance with Step 6.14.2.
- 2) At least two technically qualified members of the Facility Staffindependently verify the release rate calculations and discharge line valving.
Otherwise, suspend release of radioactive emuents via the pathway. Exert best efforts to return the monitor to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Emuent Release Repon why the inoperable monitor was not restored in a timely manner.
. 2.
Flow Measurement Devices t
i Waste Water Flow Rate and With the flow measurement device inoperable, emuent t
Totalizer (FIRQ95108)
I 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 retention basin releases by a level device in the discharge stream.
Retention Basin Discharge Flow With the flow rate measurement device inoperable, Rate (F195001)
I emuent releases via this pathway may continue provided that the Retention Basin discharge flow rate is estimated using the Waste Water Flow Rate instrument. 3 Page1of1
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 61 of 74 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE -
i REOUIREMENTS Instrument Instrument Channel Source Channel j
Instrument Ch-ck Check Calibration Channel Test
- 1. Gross Radioactivity Monitors Providing Alarm and Automatic Termination Isolation Retention Basin Effluent D*
P R*
QS Discharge Monitor (R15017A).
- 2. Flow Monitors Waste Water Flow Rate and Totalizer (FIRQ95108)
D")
N/A R
Q Retention Basin Discharge Flow Rate (FI95001)
D")
N/A R
Q Table Notation (1) During releases via this pathway, a check shall be pedormed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Normally, checks are automatically performed once every eight (8) hours.
(2)- The Instmment Channel Calibration for radioactivity measurement instrumentation shall be pedormed using one or more reference standards.
(3) The Channel Test shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist.
A.-
Instrumentation indicates measured Svels above the alarm / trip setpoint.
B.
Circuit failure.
I C.
Instrument indicates a downscale failure.
D.
Instrument controls not set in operate mode.
-(4) The Instrument Channel Check shall consist of verif ing indication of flow during periods of f
release. The Instmment Channel Check shall be made at least once daily on any day in which batch
- releases are made. 4 Page1ofI e
(
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 62 of 74 RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM l
l Lower Limit of Liquid Release Sampling Minimum Analysis Detection (LLD)(*)
Type Frequency Frequency Type of Activity (pCi/ml) l A. Retention Each Batch Each Batch Mn-54, Co-60, Zn-65, Basin (N/S)*)
Cs-134, Cs-137, Ce-144 3.00 E-07 P
P H-3 1.00 E-05 B. Regenerant Each Batch -
.Each, Batch Mn-54, Co-60 4.00 E-09 P'
Zn-65 6.00 E-09 Holdup Tank P
(A/B)(#)
Cs-134, Cs-137 3.00 E-09 Standard Ce-144 6.00 E-08 Release H-3 1.00 E-05 Scenario
- Each Batch Composite")
Sr-90 1.60 E-09 P
M Gross Alpha 1.00 E-07 C. Regenerant Each Batch Each Batch Mn-54, Co-60, Zn-65, Holdup Tank Cs-134, Cs-137 2.00 E-08 (A/B)(*)
P P
Ce-144 6.00 E-08 Rapid H-3 1.00 E-05 Release Each Batch Composite"'
Mn-54, Co-60 4.00 E-09 Scenario
- P M
Zn-65 6.00 E-09 Cs-134, Cs-137 3.00 E-09 Sr-90 1.00 E-09 Gross Alpha 1.00 E-07
(
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MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 l
TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 63 of 74 l
RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM (Continued) 1 Table Notation (a)
L-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 6.14.3 (10 CFR 50, Appendix I) for a RHUT transfer to a retention basin and assurance of compliance with the limits of Step 6.14.2 (10 CFR '20, Appendix B, Table 2, Column 2) for a Retention Basin 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:
2.7
+ 3.29 x S b LLD =
5 (3.70 E + 04)(Y x E x V)eW')
)
Where:
i 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 i
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 (milliliters) i the radioactive decay constant for the particular nuclide (seconds)
A,
=
the elapsed time from midpoint of collection to the midpoint of counting t.
= 5 Page 2 of 4
i l-MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9
~ TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 64 of 74 l
L
, RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)
-l TableNotation (Continued) l l
S.
the standard deviation 'of the background counting rate
=
r 3 0.5 B +B L
S.
=
t$j (t tbs l
Where:
!~
B= bacicground counts background counting interval (seconds) t6
=
t.
= sample countinginterval(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.
l
'(b) A batch release is the discharge ofliquid wastes of discrete volume from the north or south l-Retention Basin. The Retention Basins are the maximum permissible concentration accountability points for 10 CFR 20, Appendix B compliance.
f (c) A RHUT will be isolated and its contents thoroughly mixed to assure representative sampling prior to transferring the contents to a Retention Basin. The A and B RHUTs are the dose equivalent accountability points for 10 CFR 50, Appendix I compliance.
(d) Isotopic peaks which are measurable and identifiable from a RHUT 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 be;ng present. The "less than" results shall be considered "zero" for the purposes of ODCM evaluations; however, if a nuclide is measured and identified at a value less than the 5 LLD value, it shall be reported and entered in ODCM evaluations.
l l
(e) A composite sample shall be obtained by mixing liquid aliquot volumes in proportion to the volume L
- ofliquid released from each RHUT. Preparation of the composite is identical no matter which release scenario, or combination of scenarios, was used to release the RHUTs. If any RHUT which is part of the composite was released using the Rapid Release Scenario, the composite will be analyzed accordmg to the Rapid Release Scenario.
- 5 Page 3 of4 i
MANUAL
- CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 65 of 74 i
RADIOACTIVE LIOUID WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)
Table Notation (Continued) u (f)- Release of each RHUT may proceed along either of two separate scenarios depending on operational requirements. Normally, the Standard Release Scenario will be used for RHUT releases The Rapid Release Scenario will be used when operational requirements dictate expediting the release process. In either scenario, the sample must eventually be analyzed to an LLD level which equates to an off-site dose ofless that 10 percent of the 10 CFR 50, Appendix I L
guidelines. ' Preparation of the Monthly. Composite is independent of the scenario used to release l
each RHUT during a calendarlm' nth: the composite must be prepared for either scenario, only the i
o i
analysis requirements differ. These Lower Limits of Detection for either or both scenario may l
L change as the maximum annual effluent outflow or the minimum annual average flow rate in the i
plant effluent stream changes.
l
- 1. Standard Release Scenario. This scenario uses the lower LLDs on a pre-release basis, resulting in correspondingly longer analysis intervals. In this scenario, the monthly composite does not i
need to be analyzed for gamma emitters. The pre-release and post-release (monthly composite)
LLDs equate to an off-site dose ofless than 10 percent of the 10 CFR 50, Appendix I guidelines.
- 2. Ranid Release Scenario. This scenario allows the use of higher LLDs for pre-release dose
{
calculations, resulting in correspondingly shoner analysis intervals. The pre-release LLDs l=
equate to an off-site dose ofless than 20 percent of the 10 CFR 50, Appendix I guidelines. The i
post-release (monthly composite) LLDs equate to an off-site dose ofless than 10 percent of the l
10 CFR 50, Appendix I guidelines. H-3 and Cc-144 analyses are specifically required only on a 1
- pre-release basis. The LLDs for H-3 and Ce-144 are required for the pre-release analysis only, however, these LLDs were included in the determination of post-release LLDs which meet the 10 percent criteria.
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1-5 Page 4 of 4 1
-. - - ~. - -
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 66 of 74 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION i
Minimum Number of Channels Instrument Ooera%c Action 1.
Reactor Building Stacig
- P
- a. Noble Gas Activity. -
1 With the monitor channel alarm / trip setpoint less Monitor providing conservative than the setpoint calculated as alarm and automatic described in Step 6.6, immediately suspend the termination of release.
release or declare the channel inoperable.
With the monitor inoperable, effluent releases via this pathway may continue provided grab samples are taken at least daily and these samples are analyzed in accordance with Attachment 18.
Increase grab sample frequency as necessary during unusual plant conditions.
- b. Particulate Sampler 1
With the collection device inoperable, effluent releases via this pathway may continue provided continuous samples are taken within I hour after j
the monitor is declared inoperable and these samples are analyzed in accordance with 8*.
l
- c. Sampler Flow Rate 1
With the flow rate device inoperable, effluent Measurement Device releases via this pathway may continue provided the flow rate is estimated and recorded daily.
l
- Intermption of continuous sampling is allowed for periods not to exceed I hour.
~ 6 Page1of3
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1 MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 s
l PROCEDURES MANUAL j
REVISION: 9 i
TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 67 of 74 L-RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l
(Continued)
Minimum Number of Channels Instrument
. Ooerable Action 2.
Auxiliary Building Stac,k
- l.
- ?
- a. Noble Gas Activity 1
With the monitor alarm / trip setpoint less Monitor-conservative tir.n the setpoint calculated as described in Step 6.6, immediately suspend the release or declare the channel inoperable.
With the monitor inoperable, effluent releases via this pathway may continue provided grab samples are taken at least daily (every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during fuel handling activities) and these samples are analyzed in accordance with Attachment 18. Increase grab sample frequency as necessary during unusual plant conditions.
- b. Particulate Sampler 1
With the collection device inoperable, effluent
)
releases via this pathway may continue provided
.{
continuous samples are taken within I hour after 1
the monitor is declared inoperable and these samples are analyzed in accordance with 8*.
- c. Sampler Flow Rate 1-With the flow rate device inoperable, effluent Measurement Device releases via this pathway may continue provided the flow rate is estimated and recorded daily.
i
- Interruption of continuous sampling is allowed for periods not to exceed I hour. 6 '
Page 2 of 3 i
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL I.
REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 68 of *,*
i
-" ~ RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION -
'i (Continued)
Minimum i
Number of Channels i
Instrument Operable Action 3.
Auxiliary Building Grade Level Vent -
- l,
)
i
- a. Noble Gas Activity 1
With the monitor alarm / trip setpoint less Monitor conservative than the setpoint calculated as described in Step 6.6, immediately suspend the release or declare the channel inoperable.
With the monitor inoperable, effluent releases via this pathway may continue provided grab samples i
)
- are taken at least daily and these samples are analyzed in accordance with Attachment 18.
Increase grab sunple frequency as necessary during unusual plant conditions.
.b.
Particulate Sampler 1
With the collection device inoperable, effluent releases via this pathway may continue provided continuous samples are taken within I hour after
~
the monitor is declared inoperable and these samples are analyzed in accordance with
, 8*.
- c. Sampler Flow Rate 1
With the flow rate device inoperable, effluent Measurement Device releases via this pathway may continue provided the flow rate is estimated and recorded daily.
4.
- IOS Building Vent
- a. Particulate Monitor i
Eth the monitor inoperable, ventilation flow shall be halted or continuous particulate samples shall be taken in accordance with Attachment 18, Section D, for particulate samples.
- Interruption of continuous sampling is allowed for periods not to exceed I hour. 6 Page 3 of 3
i MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 69 of 74 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE -
o REOUIREMENTS Instrument Instrument Channel Source Channel Channel l
Instrument Check Check Clibration Test
- 1. Reactor Building Stack D
RW Qm
- a. Noble Gas Activity Monitor W
NA NA NA
- b. Particulate Sampler' l,
D NA R
Q
- c. Sampler Monitor Flow ~ Rate Measurement Device 1
- 2. Auxiliary Building Stack D
M RW Q
- a. Noble Gas Activity Monitor W
NA NA NA
- b. Particulate Pampler D
NA R
Q j
- c. Sampler Monitor Flow Rate Measurement Device
- 3. Auxiliary Building Grade Level Vent D
M R*
QS
- a. Noble Gas Activity Monitor W
NA NA NA-
- b. Particulate Sampler D
NA R
Q
- c. Sampler Monitor Flow Rate Measurement Device 4iIOS Building Vent M
NA R
- a. Particulate Sampler 1
1:
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-.=_-
MANUAL: CHEMISTRY ADMINISTRATIVE -
NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 70 of 74 c,...
... RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEHLANCE REOUIREMENTS (Continued)
Table Notation (1)
The CHANNEL TEST shall also demonstrate that automatic termination of the purge and control room alarm annunciation occurs if any of the follow;ng conditions exist:
Instrument indicates measured levels above the alarm / trip setpoint.
- Circuit failure.
',j Instrument indicates a downscale failure.
e Instrument controls not set'in operate mode.
(2)
The CHANNEL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
- Instrument indicate measured levels above the alarm / trip setpoint.
- Circuit failure.
- Instrument indicates a downscale failure.
- Instrument controls not set in operate mode.
(3)
The INSTRUMENT CHANNEL CALIBRATION shall be performed using one or more reference standards.
]
(4)
A check shall be performed prior to each release and monthly during periods of continuous purging.
i 4
i 7 Page 2 of 2
y.
- i4 i
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL REVISION:
9-
)
TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 71 of 74 RADIOACTWE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit ofDetection Sampling Minimum Analysis Type of Activity (LLD)(')
Gaseous Release Type Frecuency Frequency Analysis (gCi/ml)
A. ReactorBuilding M
M Kr-85 1.00 E-04 Stack Grab Sample H-3 1.00 E-06 B. Auxiliary Building
. M*
M Kr-85 1.00 E-04 Stack Grab Sample' H-3 1.00 E-06 C. Auxiliary Building M
M Kr-85 1.00 E-04 Grade Level Vent Grab Sample H-3 1.00 E-06 D. All Release Continuous M
Principal Gamma 1.00 E-11 Types as listed in Particulate Sample Emitters (*)
A, B, C above Continuous M
Gross Alpha (
l.00 E-11 j
Particulate Sample Sr-90")
1.00 E-11 l
Continuous Continuous Noble Gases, Gross 1.00 E-04 j
(Noble Gas Monitor)
Beta and Gamma as Xe-133 i
j 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 i
detected, if present, in order to achieve compliance with the limits of the Specifications in Steps 6.14.6,6.14.7, and 6.14.8.
j j
- 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 nege.tive i
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:
2.7% + 3.29 x S b
' 5 LLD =
(3.70 E + 04)(Y x E x V)e@'*)
i i
, 8 o
Page1 of3
f:
]
l MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 5
i l
PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 72 of 74 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM (Continued)
Where:
2.71
'=
factor to account for Poisson statistics at very low background count rates f
3.29 two times the constant used to establish the one sided 0.95 confidence
=
interval
.'. lt l
3.70 E+04 = disintegritions/second/ microcurie Y
= yield ofradiochemical process, i.e., the product of all factors such as I
emission fraction, chemical yield, etc.
E counting efficiency (count / disintegrations)
=
V sample volume (milliliters)
=
A
= the radioactive decay constant for the particular nuclide (seconds)
l the elapsed time from midpoint ofcollection to the midpoint ofcountmg j
t.
=
the standard deviation of the background counting rate I
S6
=
e 3 0.5 B
B S6
+h
=
(t tbs t
Where:
B=
background counts t6 = background counting interval (seconds) sample counting interval (seconds) t.
=
i
, 8 Page 2 of 3 I^
MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP OOO2 l
PROCEDURES MANUAL REVISION: 9 TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 73 of 74
]MQlOACTIVE GASEOUS WASTE SAMPLING AND ~ ANALYSIS PROGRAM (
Table Notation (Continued) 1
- 3. The LLD is defined as an a pdori (before the fact) estimate and is not to be calculated for each sample analyzed on an a posteriori (after the fact) basis.
(b) ~ Tritium grab samples shall be taken at ut once per seven days from the ventilation exhaust from the auxiliary building stack anytime ft a is in the spent fuel pool and the pool temperature exceeds '
110*F. Below 110*F there is essentially'no evaporation from this source; (c) - Principal gamma emitters for vyhich the LLD applies are: Kr-85 for gaseous samples and Mn-54, Co-60,2n-65, Cs-134, Cs-137, and Ce-144 for particulate samples. This does not mean only these nuclides will be detected and reponed. Other peaks that are measurable and identifiable shall be reported in the Annual Radioactive Effluent Release Report, pursuant to Step 6.15.1. 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 18 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 j
sample. If any one of these samples indicates greater than 1.0E-Il pCi/cc gross beta Sr-90 activity, then an 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.
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Page 3 ~of 3 4
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l MANUAL: CHEMISTRY ADMINISTRATIVE NUMBER:
CAP-0002 PROCEDURES MANUAL l
REVISION: 9 l
TITLE:
OFF-SITE DOSE CALCULATION MANUAL PAGE: 74 of 74 l
ODCM REVISION REVIEW REOUIREMENTS l
ODCM REVISION REVIEW REQUIREMENTS Whenever the ODCM is revised, no matter what the changes are, sevceal reviews must be perforrned. These reviews must also be documented. The documentation is oRen inckded as an attachment to the 50.59 Safety Determination. This form lists the minimum reviews and documentation required for each change. Initial each requirenwnt as it is compicted.
Sign the bottom of the forrn when a0 review requiremmts are completed.
j Initials i
L Determination that the Ic' vel ofcontrol of radioactive effluents is being mahtained.
l This determination is 'made by review of the foDowing documents 10 CFR 20.130I and 20.1302 10 CFR 50.36a
{
+
Appendix I to 10 CFR 50 40 CFR 190
+
Determination that the change (s) win not adversely affect the accuracy or reliability ofefDuent dose calculations or effluent monitor setpoint determinations.
This determination is made by directly reviewing each change to the ODCrd. Although each change must be evaluated, changes that directly involve Iculatio s should be more carefully considered.
Supporting information.
Fuujustification including analyses and evalu ns a p rt the change (s) rnust be included in the review and approval packa l
IV.
Noti 6 cation ofNRC.
The NRC is notified ofaD changes h M by includirig a complete, legible copy as part oC or concurrent with, the nu a tive Effluent Release Report (ARERR). To ensure inclusion in the ARE a stem Id be initiated whenever the ODCM is revised.
/
V.
Implementing The following docu ents should reviewed for impact whenever the ODCM is revised:
- CAP-0008. sits ses of Radioactivity in Liquid Effluents CAP-0009, Offsite Re ses of Radioactivity in Liquid E!11uents CAP-0013 Preparation of the Aranual Radioactive EfDuent Release Report CllM 5107, Compositing ofLiquid Samples CHM 5109, EfDuent Monitor Alarm Response Procedure VI.
Multidisciphne Review Ensure an areas that may be affected by the revision, or have an eterest in the changes made in the revision, are included in the multidiscipline review. Areas that are affected by the ODCM and coukt be included in this review are: Technical Services Survei!!ance Scheduler, Quahty Assurance, Licensing, and Operations.
All Reviews Complete:
Reviewer Signature Date CHM 122 (Rev,0)
Page 1 of 1 l
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