ML020720703
| ML020720703 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/27/2002 |
| From: | Montgomery B Constellation Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NMP1L 1647 | |
| Download: ML020720703 (146) | |
Text
P.O. Box 63 Lycoming, New York 13093 Constellation Nuclear Nine Mile Point Nuclear Station February 27, 2002 A Member of the NMP1L 1647 Constellation Energy Group U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE:
Nine Mile Point Unit 1 Docket No. 50-220 DPR-63
Subject:
July - December 2001 Semi-Annual Radioactive Effluent Release Repoil Gentlemen:
In conformance with the Nine Mile Point Unit 1 (NMP1) Technical Specifications, enclosed is the Semi-Annual Radioactive Effluent Release Report for the reporting period July - December 2001. Included in this report is a summary of gaseous, liquid, and solid effluents released from the station during the reporting period (Attachments 1 - 6), a summary of revisions to the Offsite Dose Calculation Manual and the Process Control Program during the reporting period (Attachments 7 and 8), and an explanation as to the cause and corrective actions regarding the inoperability of any station liquid and/or gaseous effluent monitoring instrumentation (Attachment 9). Attachments 10 and 11 provide a summary and assessment of radiation doses to members of the public within and outside the site boundary, respectively, from liquid and gaseous effluents as well as direct radiation in accordance with 40 CFR 190.
The format used for the effluent data is outlined in Appendix B of Regulatory Guide 1.21, Revision 1. Dose assessments were made in accordance with the NMP1 Offsite Dose Calculation Manual. Distribution is in accordance with 10 CFR 50.4(b)(1) and the Technical Specifications. 2 to this report is an update of actual data for the second quarter 2001 used in the January - June 2001 Semi-Annual Radioactive Effluent Release Report.
Page 2 NMP1L 1647 3 is an update of the Abnormal Release for the first half of 2001. 4 is a Summary of Changes to the Environmental Monitoring and Dose Calculation Locations. 5 is a copy of Revision 21 of the Offsite Dose Calculation Manual.
During the reporting period from July - December 2001, NMP1 did not exceed any 10 CFR 20, 10 CFR 50, or Technical Specification limits for gaseous or liquid effluents.
If you have any questions concerning the attached report, please contact Mr. Anthony Salvagno, (315) 349-1456, Engineering Services, Nine Mile Point.
Ver
- tVruy
- ours, ru.M tgomery Gen eral Manager Nucl ar Engineering B SM/CLW/cld Enclosure xc:
Mr. H. J. Miller, Regional Administrator, Region I Mr. G. K. Hunegs, NRC Senior Resident Inspector, Region I Mr. P. S. Tani, Senior Project Manager, NRR (2 copies)
Records Management
Page 3 NMP1L 1647 bcc:
T. Kulczycky (2 copies, without attachment 15)
V. Schuman (without attachment 15)
C. Senska (without attachment 15)
D. Topley (without attachment 15)
C. Widay (without attachment 15)
T. Ringger J. Petro
NINE MILE POINT NUCLEAR STATION - UNIT I SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT July-December 2001 Coenstellat'on Nuclear Nine Mile Point Nudear Station A Mernbfe a
?
Page 1 of 2 NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY - DECEMBER 2001 SUPPLEMENTAL INFORMATION Facility:
Nine Mile Point Unit #1 Licensee:
Nine Mile Point Nuclear Station, LLC
- 1.
TECHNICAL SPECIFICATION LIMITS A)
FISSION AND ACTIVATION GASES
- 1.
The dose rate limit of noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be less than or equal to 500 mrem/year to the total body and less than or equal to 3000 mrem/year to the skin.
- 2.
The air dose due to noble gases released in gaseous effluents from Nine Mile Point Unit 1 to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 milliroentgen for gamma radiation and less than or equal to 10 mrad for beta radiation, and during any calendar year to less than or equal to 10 milliroentgen for gamma radiation and less than or equal to 20 mrad for beta radiation.
B&C) TRITIUM, IODINES AND PARTICULATES, HALF LIVES > 8 DAYS
- 1.
The dose rate limit of Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days, released in gaseous effluents from the site to areas at and beyond the site boundary shall be less than or equal to 1500 mrem/year to any organ.
- 2.
The dose to a member of the public from Iodine-13 1, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days in gaseous effluents released from Nine Mile Point Unit 1 to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrem to any organ and, during any calendar year to less than or equal to 15 mrem to any organ.
D)
LIQUID EFFLUENTS
- 1.
The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 microcuries/ml total activity.
- 2.
The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 1 to unrestricted areas shall be limited during any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and during any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
Page 2 of 2
- 2.
MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents.
A)
FISSION AND ACTIVATION GASES Noble gas effluent activity is determined by on-line gamma spectroscopic monitoring (intrinsic germanium crystal) or gross activity monitoring (calibrated against gamma isotopic analysis of a 4.OL Marinelli grab sample) of an isokinetic stack sample stream.
B)
IODINES Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled from an isokinetic stack sample stream.
C)
PARTICULATES Activity released from the main stack is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from an isokinetic sample stream and composite analysis of the filters for non-gamma emitters.
D)
TRITIUM Tritium effluent activity is measured by liquid scintillation or gas proportional counting of monthly samples taken with an air sparging/water trap apparatus. Tritium effluent activity is measured during purge and weekly when fuel is offloaded until stable tritium release rates are demonstrated.
E)
EMERGENCY CONDENSER VENT EFFLUENTS The effluent curie quantities are estimated based on the isotopic distribution in the Condensate Storage Tank water and the Emergency Condenser shell water. Actual isotopic concentrations are found via gamma spectroscopy. Initial release rates of Sr-89, Sr-90 and Fe-55 are estimated by applying scaling factors to release rates of gamma emitters and actual release rates are determined from post offsite analysis results. The activity of fission and activation gases released due to tube leaks is based on reactor steam leak rates using offgas isotopic analyses.
F)
LIQUID EFFLUENTS Isotopic contents of liquid effluents are determined by isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters. Tritium activity is estimated on the most recent analysis of the Condensate Storage Tank water. Initial release rates of Sr-89, Sr-90, and Fe-55 are estimated by applying scaling factors to release rates of gamma emitters and actual release rates are determined from post offsite analysis results.
G)
SOLID EFFLUENTS Isotopic contents of waste shipments are determined by gamma spectroscopy analysis of a representative sample of each batch. Scaling factors established from primary composite sample analyses conducted off-site are applied, where appropriate, to find estimated concentration of non-gamma emitters. For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.
ATTACHMENT 1 Summary Data Page 1 of 2 Unit 1 X Unit 2 Reporting Period July - December 2001 Liquid Effluents:
10CFR20, Appendix B, Table II, Column 2 Average MPC - uCi/ml (Qtr. 3) = 1.81E-03 Average MPC - uCi/ml (Qtr. 4) = N/A Average Energy (Fission and Activation gases - Mev}:
Qtr. 3_:
Ey
= 0.247
= 0.317 Qtr.4:
Ey
= 0.247
ý= 0.317 Liquid:
Number of batch releases 0
Total time period for batch releases (hrs)
N/A Maximum time period for a batch release (hrs)
N/A Average time period for a batch release (hrs)
N/A Minimum time period for a batch release (hrs)
N/A Total volume of water used to dilute the liquid effluent during release 3rd 4th period (L)
N/A N/A Total volume of water used to dilute the liquid effluent during reporting 3rd 4th period (L) 1.39E+11 1.33E+11 Gaseous - (There were no releases from the operation of the Emergency Condenser Vent):
Number of batch releases 0
Total time period for batch releases (hrsl N/A Maximum time period for a batch release (hrs)
N/A Average time period for a batch release (hrs)
N/A Minimum time period for a batch release (hrs)
N/A Gaseous (Primary Containment Purge):
Number of batch releases 1
Total time period for batch releases (hrs) 5.83E+00 Maximum time period for a batch release (hrs) 5.83E+00 Average time period for a batch release (hrs) 5.83E + 00 Minimum time period for a batch release (hrs) 5.83E+00
ATTACHMENT 1 Summary Data Page 2 of 2 Unit 1 X Unit 2 Reporting Period July - December 2001 Abnormal Releases:
A.
Liquids:
Number of releases 1
Total activity released 2.OOE+01 Ci B. Gaseous:
Number of releases 0
Total activity released N/A Ci UNIT 1 ABNORMAL RELEASE BACKGROUND Cooling for several vital components is provided by the Reactor Building Closed Loop Cooling (RBCLC) System and the Turbine Building Closed Loop Cooling (TBCLC) System.
Both systems have the residual heat removed via the Service Water System.
EVENT On August 8, 2001, it was identified that the makeup flow rate to RBCLC and TBCLC was above normal. The expected makeup to both systems was calculated to be 0.329 gpm while the actual makeup flow rate was estimated at 2.83 gpm based on make-up tank level indications. Action Request (ACR) 01-02661 was written to determine if excess makeup was a result of a leak out of TBCLC. This task was performed on 8/10/01 and the makeup flow rate to TBCLC of 3.28 gpm verified the excess make-up rate. A tube leak in one of the three heat exchangers was immediately suspected due to the loss of plant water inventory. Isolating each heat exchanger and comparing the makeup flow to TBCLC showed that HTX-71-1 2R contained the leak.
Inspection of HTX-71-1 2R showed three tubes along the top row were damaged. The three tubes were plugged as were an additional seven other tubes as a result of eddy current testing and engineering recommendations. HTX-71-12R was brought on line on 8/24/01.
Subsequent Service Water testing did not reveal any additional activity. Furthermore, no activity has been detected in Service Water since HTX-71-12R was repaired. Deviation/Event Report (DER) NM 2001-3756 was generated as a result of this event.
ANALYSIS An offsite vendor analysis of the Service Water samples representing the period July 2, 2001 through August 24, 2001, along with the amount of Service Water released yielded a calculated release of 20 Curies of activity. The nuclides identified are: H-3 (1 5.21 Ci) and Fe-55 (4.74 Ci).
Analysis of the dilution flow for this continuous discharge from 7/2/01 to 8/24/01 resulted in a whole body dose of 1.36E-03 mrem, and a maximum organ dose (Bone) of 8.1 9E-03 mrem. The activity and resulting dose contribution are reflected in Attachment 5.
ATTACHMENT 2 Unit 1 X Unit 2 Reporting Period July - December 2001 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES, ELEVATED AND GROUND LEVEL 3rd 4th EST. TOTAL QUARTER QUARTER ERROR, %
Fission & Activation gases
- 1.
Total release
- 2.
Average release rate A.
B.
C.
Percent of Quarterly Dose Limit (7.5 mrem)
Percent of Annual Dose Limit (15 mrem)
Percent of Organ Dose Rate Limit (1500 mrem/yr)
Ci M.Ci/sec Ci 12Ci/sec Ci juCi/sec Ci Ci
/,Ci/sec 9.21E-01 1.78E-04 1.16E-01 2.24E-05 4.74E-04 6.40E-04 5.97E-05 8.05E-05 3.24E-03 4.08E-04 6.57E-05 2.53E-03 3.18E-04 3.08E-05 1.21E+01 3.58E+01 1.52E+00 4.50E+00 lodines
- 1.
Total Iodine-131
- 2.
Average release rate for period Particulates1
- 1.
Particulates with half-lives >8 days
- 2.
Average release rate for period
- 3.
Gross alpha radioactivity Tritium'
- 1.
Total release
- 2.
Average release rate for period Percent of Tech. Spec. Limits Fission and Activation Gases Percent of Quarterly Gamma Air Dose Limit (5 mR)
Percent of Quarterly Beta Air Dose Limit (10 mrad)
Percent of Annual Gamma Air Dose Limit to Date (10 mR)
Percent of Annual Beta Air Dose Limit to Date (20 mrad)
Percent of Whole Body Dose Rate Limit (500 mrem/yr)
Percent of Skin Dose Rate Limit (3000 mrem/yr)
Tritium, lodines, and Particulates1 (with half-lives greater than 8 days) 1.44E-06 9.19E-07 2.15E-03 8.75E-04 3.75E-08 1.66E-08 6.54E-01 2.08E+00 1.30E-02 1
Tritium, Iron-55, and Strontium results for the second quarter were not received from the off-site vendor at the time of this report. These values include estimates, and actual numbers will be provided in the next Semi-Annual Report.
4.22E-03 1.72E-03 2,14E-03 8.75E-04 1.11E-04 3.90E-05 9.04E-01 1.70E +00 1.80E-02 D.
E.
5.OOE+01 3.OOE +01 3.00E+01 2.50E+01 5.OOE+01
ATTACHMENT 3 Unit 1 X Unit 2 Reporting Period July - December 2001 GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODE3 BATCH MODE There were no batch Releases during the Reporting period.
3rd 4th 3rd 4th Nuclides Released QUARTER QUARTER QUARTER QUARTER 1.
Fission Gases1 Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-1 31m Ci Xenon-133 Ci Xenon-133m Ci Xenon-135 Ci 9.21 E-01 Xenon-1 35m Ci Xenon-137 Ci Xenon-138 Ci
- 2.
lodines1 Iodine-131 Ci lodine-133 Ci Iodine-135 Ci
- 3.
Particulates" 2 Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci Cesium-137 Ci Cobalt-60 Ci Cobalt-58 Ci Manganese-54 Ci Barium-Lanthanum-1 40 Ci Antimony-1 25 Ci Niobium-95 Ci Cerium-141 Ci Cerium-144 Ci Iron-59 Ci Cesium-1 36 Ci Chromium-51 Ci Zinc-65 Ci Iron-55 Ci Molybdenum-99 Ci Neodymium-147 Ci
- 4.
Tritium 2 Ci 4.74E-04 6.40E-04 3.53E-03 3.98E-03 1.17E-04 5.24E-04 6.55E-05 1.69E-03 8.31E-04 3.46E-05 4.53E-04 2.35E-04 1.99E-05 9.07E-04 8.50&E-04 2.66E-05 8.62E+00 3.18E+01 1
Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk. A lower limit of detection of 1.OOE-04 gCi/ml for required noble gases, 1.OOE-11 p1Ci/ml for required particulates, 1.0OE-1 2 pCi/ml for required lodines, and 1.OOE-06 ýCi/ml for Tritium, as required by Technical Specifications, has been verified.
2 Tritium, Iron-55, and Strontium results for the second quarter were not received from the off-site vendor at the time of this report. These values include estimates, and actual numbers will be included in the next Semi-Annual Report.
3 Contributions from purges are included.
ATTACHMENT 4 Unit 1 X Unit 2 Reporting Period July - December 2001 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Ground level releases are determined in accordance with the Off-Site Dose Calculation Manual and Chemistry procedures.
BATCH MODE CONTINUOUS MODE BTHMD There were no batch Releases during the Reporting period.
3rd 4th 3rd 4th QUARTER QUARTER QUARTER QUARTER
- 1.
Fission Gases' Argon-41 Ci Krypton-85 Ci Krypton-85m Ci Krypton-87 Ci Krypton-88 Ci Xenon-127 Ci Xenon-131m Ci Xenon-133 Ci 4.24E-05__
Xenon-133m Ci Xenon-135 Ci 5.29E-05 1.78E-04 Xenon-135m Ci Xenon-1 37 Ci Xenon-138 Ci
- 2.
lodines' Iodine-131 Ci Iodine-133 Ci lodine-135 Ci T
- 3.
Particulates"12 Strontium-89 Ci 2.12E-08 Strontium-90 Ci 2.66E-09 Cesium-134 Ci Cesium-137 Ci 7W Cobalt-60 Ci 7.15E-08 4.59E-08 Cobalt-58 Ci 4.37E-09 Manganese-54 Ci 1.51 E-08 7.03E-09 Barium-Lanthanum-140 Ci Antimony-125 Ci Niobium-95 Ci W7 Cerium-141 Ci WT Cerium-144 Ci ITT Iron-59 Ci Cesium-136 Ci ITT Chromium-51 Ci ITT Zinc-65 Ci IT Iron-55 Ci 4.59E-08 Molybdenum-99 Ci Neodymium-147 Ci ITT
- 4.
Tritium2 Ci 3.49E+O0 3.96E + 00 Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
2 Tritium, Iron-55, and Strontium results for the second quarter were not received from the off-site vendor at the time of this recort. These numbers include estimates and actual numbers will be included in the next Semi-Annual Report.
ATTACHMENT 5 Unit 1 X Unit 2 Reporting Period July - December 2001 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 3rd1 4th EST.
QUARTER QUARTER TOTAL ERROR, %
A.
Fission & Activation Products
- 1.
Total release (not including Tritium, gases, alpha)
- 2.
Average diluted concentration during reporting period B.
Tritium 1.
Total release
- 2.
Average diluted concentration during reporting period C.
Dissolved and Entrained Gases
- 1.
Total release
- 2.
Average diluted concentration during reporting period D.
Gross Alpha Radioactivity
- 1.
Total release E.
Volumes
- 1.
Prior to dilution
- 2.
Volume of dilution water used during release period
- 3.
Volume of dilution water available during reporting period:
F.
Percent of Technical Specification Limits Percent of Quarterly Whole Body Dose Limit (1.5 mrem)
Percent of Quarterly Organ Dose Limit (5 mrem)
Percent of Annual Whole Body Dose Limit to Date (3 mrem)
Percent of Annual Organ Dose Limit to Date (10 mrem)
Percent of 10CFR20 Concentration Limit Percent of Dissolved or Entrained Noble Gas Limit (2.OOE-04 uCi/ml)
Ci jzCi/ml Ci ktCi/ml Ci MuCi/ml Ci Liters Liters Liters 4.74E+00 3.41 E-08 No Releases No Releases 1.52E+01 No Releases 1.09E-07 No Releases No Releases No Releases No Releases No Releases 8.32E+ 10 No Releases 1.39E+ 11 1.33E+ 11 9.07E-02 No Releases 1.64E-01 No Releases 6.19E-02 No Releases 8.19E-02 No Releases 7.91 E-03 No Releases No Releases 5.0OE+01 5.0OE+01 5.0OE+01 5.OOE+01 5.00E+01 5.00E+01 5.00E+01 The activity presented is the abnormal release presented in Attachment 1. Refer to Attachment 1, page 2 for details regarding the abnormal release.
Page 1 of 2
ATTACHMENT 5 Page 2 of 2 Unit 1 X Unit 2 Reporting Period July - December 2001 LIQUID EFFLUENTS RELEASED CONTINUOUS MODE1 3rd 4th Nuclides Released QUARTER QUARTER Strontium-89 Ci No Releases Strontium-90 Ci No Releases Cesium-1 34 Ci No Releases Cesium-1 37 Ci No Releases Iodine-131 Ci No Releases Cobalt-58 Ci No Releases Cobalt-60 Ci No Releases Iron-59 Ci No Releases Zinc-65 Ci No Releases Manganese-54 Ci No Releases Chromium-51 Ci No Releases Zirconium-Niobium-95 Ci No Releases Molybdenum-99 Ci No Releases Technetium-99m Ci No Releases Barium-Lanthanum-140 Ci No Releases Cerium-141 Ci No Releases Tungsten-187 Ci No Releases Iodine-133 Ci No Releases Iron-55 Ci 4.74E + 00 No Releases Neptunium-239 Ci No Releases Iodine-1 35 Ci No Releases Dissolved or Entrained Gases Ci No Releases Tritium Ci 1.52E +01 No Releases No batch mode release occurred during the report period. The activity shown represents an abnormal release. Refer to, page 2.
ATTACHMENT 6 Page 1 of 6 Unit 1 X
Unit 2 Reporting Period July - December 2001 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.1 TYPE Volume Activity1 (m3 )
(Ci0 Class Class A
B C
A B
C
- 1. Spent Resins) 1.11E+01 0
0 3.43E+00 0
0 (Dewatered)
- 2. Dry Active Waste 0
0 0
0 0
0
- 3. Other:
(to vendor for processing or consolidation)
- a.
Dry Active Waste 7.25E+01 0
0 4.73E-02 0
0 (Non-Comp.)
- b.
Misc. Filters and 0
0 0
0 0
0 Equipment
- c.
Resins (Dewatered) 1.26E+01 0
0 3.22E+02 0
0 1
The estimated total error is 5.OOE+01%.
ATTACHMENT 6 Page 2 of 6 Unit 1 X Unit 2 Reporting Period July - December 2001 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.1 TYPE Solidification Container Package Agent
- 1.
Spent Resins (Dewatered)
Poly HIC wl STP None steel shell
- 2.
Dry Active Waste
- 3.
Other: (To Vendor for Processing or Consolidation)
- a.
Dry Active Waste (Non-Compactible)
Metal Box STP None
- b.
Misc. Filters and Equipment
- c.
Resins (Dewatered)
ATTACHMENT 6 Page 3 of 6 Unit 1 X Unit 2 -
Reporting Period July - December 2001 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)
- a.
Spent Resins (Dewatered)
Nuclide (Resins)
Percent (Resins)
(1) Co-60 5.02E+01 (2) Mn-54 2.08E+01 (3) Ce-144 9.31E+00 (4) Cs-137 8.59E+00 (5) Tc-99 2.88E+00 (6) Co-58 2.46E +00 (7) Fe-59 1.32E+00 (8) H-3 1.22E+00 (9) Other 3.22E+00
- b.
Dry Active Waste Nuclide Percent
- c.
Other: (to Vendor for Processing or Consolidation)
- 1.
Dry Active Waste (Non-Compactible)
Nuclide Percent (1) Fe-55 6.77E+ 01 (2) Co-60 2.43E + 01 (3) Cs-137 3.47E + 00 (4) Mn-54 2.57E+00 (5) Ni-63 1.48E+00 (6) Other 2.1OE-01
- 2.
Misc. Filters and Equipment Nuclide Percent
- 3.
Resins (Dewatered)
Nuclide Percent (1) Mn-54 3.87E+01 (2) Co-60 2.94E + 01 (3) Fe-55 2.93E+01 (4) Co-58 1.72E+00 (5) Other 8.80E-01
ATTACHMENT 6 Page 4 of 6 Unit 1 X Unit 2 Reporting Period July - December 2001 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A.3.
SOLID WASTE DISPOSITION:
Number of Shipments Mode of Transportation Destination 3
Truck Studsvik Processing Facility, LLC Erwin, TN 1
Truck US Ecology Oak Ridge, TN 2
Truck Barnwell Waste Management Facility Barnwell, SC B.
IRRADIATED FUEL SHIPMENTS (DISPOSITION):
There were no shipments.
Number of Shipments Mode of Transportation Destination 0
0 0
ATTACHMENT 6 Page 5 of 6 Unit 1 X Unit 2 Reporting Period July - December 2001 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS C.
SOLID WASTE SHIPPED OFF-SITE TO VENDORS FOR PROCESSING AND SUBSEQUENT BURIAL Below is a summary of NMP-1 radwaste buried by vendor facilities during July - December 2001. These totals were reported separately from "10CFR61 Solid Waste Shipped for Burial" since (a) waste classification and burial was performed by the vendors, and (b) Technical Specification 6.9.1 requires reporting of "information for each class of solid waste (as defined by 1 OCFR61 I shipped off-site during the reporting period." The following data represents the actual shipments made from the off-site vendors of our radwaste (e.g., compacted and non-compacted trash, dry non-compressible waste, asbestos, scrap metal, and resins) that was processed and commingled prior to burial.
C.1.
TYPE OF WASTE - Compacted and noncompacted trash, dry non-compressible waste, asbestos, scrap metal, and resins Burial Volume Activity Est. Total processed by vendor facilities prior to burial.
(M
- 3)
(Ci)
Error, %
1.93E+01 3.13E+02 5.OOE+01 C.2.
ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent (1) Mn-54 3.82E+01 (2) Fe-55 2.98E+01 (3) Co-60 2.93E+01 (4) Co-58 1.70E+O0 (5) Other 1.OOE+O0 C.3.
SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 36 Truck Clive, UT 8
Truck Barnwell, SC
ATTACHMENT 6 Page 6 of 6 Unit 1 X Unit 2 Reporting Period July - December 2001 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS D.
SEWAGE WASTES SHIPPPED TO A TREATMENT FACILITY FOR PROCESSING AND BURIAL Below is a summary of the sewage sludge, which was removed from the site sanitary treatment facility and transferred to a municipal sewage treatment facility for subsequent drying and disposal to a landfill. This is a site release and therefore includes the results from Unit 1 and Unit 2 activities.
D.1.
TYPE OF WASTE - Sewage Sludge Burial Volume Activity Est. Total (m 3)
(Ci)
Error, %
2.72E+01 1.72E-03 5.OOE+01 D.2.
ESTIMATE OF MAJOR NUCLIDE COMPOSITION Nuclide Percent (1) H-3 5.63E+01 (2) Ni-63 1.48E+01 (3) C-14 1.31E+01 (4) Tc-99 7.88E+00 (5) 1-129 7.13E+00 (6) Other 7.90E-01 C.3.
SOLID WASTE DISPOSITION Number of Shipments Mode of Transportation Destination 1
Truck Landfill
ATTACHMENT 7 Unit 1 X Unit 2 Reporting Period July - December 2001
SUMMARY
OF CHANGES TO THE OFF-SITE DOSE CALCULATION MANUAL (ODCM)
The Unit 1 Off-Site Dose Calculation Manual (ODCM) Revision 21 was implemented in December 2001.
Administrative changes were made to reflect a change in site ownership and editorial changes for clarification. The ODCM changes do not reduce the overall conformance of existing criteria in accordance with Technical Specifications. A copy of the ODCM, Revision 21 is attached and below is a summary of the changes accepted by the Station Operations Review Committee on December 11, 2001.
New New/Amended ChangeReason for Old Page #
Page #
Section #
Change Iv iv N/A Added "Figure 5.1-2a, Nine Mile Point Offsite Map, Administrative page 69a" to the Table of Contents.
3 3
2.1.3 Revised Note to identify RBCLC rather than RCLC.
Editorial 6
6 2.1.4.5 Replace "10CFR50.59 Safety Evaluation" with Administrative "10CFR50.59 review".
8 8
2.3.1 Corrected the table numbers in the first paragraph and Editorial the next to last paragraph.
9 9
2.3.1 Corrected the designations from Unit I and Unit II to Editorial Unit 1 and Unit 2.
11 11 3.1.2.(5)
Corrected the units in the equation for 1/Ks, at the Typo/Editorial bottom of the page, from "3.7E4 day" to "3.7E4 dis".
13 13 3.1.5.1 Corrected the name of OGESMS from "the old General Editorial Electric Stack Monitoring System" to "the Offgas Effluent Stack Monitoring System".
13 13 3.1.5.1 Corrected the identification of the OGESMS and Clarification RAGEMS overall system schematic from "Figure B-9" to "Figures D-8 through D-11".
13 13 3.1.5.1 Corrected the identification of the simplified view of Editorial RAGEMS from "Figure B-8" to "Figure D-7".
14 14 3.1.5.2 In the first paragraph, corrected "Figure B-9" to Editorial "Figure D-9".
27 27 4.4 Added the units "sec/m 3" to the stack X/Q value.
Editorial 29 29 5.1 Section 5.1, 1s' paragraph: Deleted "Niagara Mohawk Administrative Power Corporation and the New York Power Authority" due to changes in ownership.
29 29 5.1 Section 5.1, 2nd paragraph: Deleted the reference to Editorial Appendix E, which does not exist.
29 29 5.1 Section 5.1, 3 "d & 4 th paragraphs: Revised to refer to Administrative the Technical Specifications and the Radiological Environmental Monitoring Program, DER 2000-4413.
65 65 Table 5.1 The location of Map Location 28 was corrected from Typo "4.7 mi @ 23. SW" to "4.7 mi @ 223' SW".
66 66 Table 5.1 Map Location 45, Milk Location #7 was deleted.
Administrative 66 66 Table 5.1 "e" and the corresponding footnote have been deleted Administrative as they are no longer necessary.
66 66 Table 5.1 Map Location 47, Milk Location #65 was deleted.
Administrative 66 66 Table 5.1 Map Location 73, Milk Location (Woodworth) was Administrative replaced by Map Location 77, Milk Location Tech Spec. Required (Summerville), as Mr. Woodworth has retired and sold his herd.
69 69 Figure 5.1-2 Figure 5.1-2 was revised to delete Map Location 45.
Administrative N/A 69a Figure 5.1-2a Designated as Figure 5.1-2a. Revised to delete Map Administrative Locations 47 and 73, and add Map Location 77.
70 70 Figure 5.1.3-1 Replace the words "Niagara Mohawk Power Administrative Corporation" and "Power Authority State of New York" with "Nine Mile Point Nuclear Station LLC" and "ENTERGY", respectively. Also, added note:
"Niagara Mohawk Power Corporation retains ownership in certain transmission line and switchyard facilities within the exclusion area boundary. Access and usage are controlled by Nine Mile Point Nuclear Station, LLC by Agreement.
ATTACHMENT 8 Unit 1 X Unit 2 Reporting Period July - December 2001
SUMMARY
OF CHANGES TO THE RADWASTE PROCESS CONTROL PROGRAM (RPCP)
There were no changes to the Unit 1 RPCP during the reporting period.
ATTACHMENT 9 Unit 1 X Unit 2 Reporting Period July - December 2001
SUMMARY
OF INOPERABLE MONITORS There were no required monitors inoperable for more than 30 days at Unit 1.
ATTACHMENT 10 Doses to Members of the Public Due To Their Activities Inside the Site Boundary
Page I of 4 ATTACHMENT 10 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY - DECEMBER 2001 Doses to members of the public (as defined by the Technical Specifications) from the operation of the Nine Mile Point Unit I (NMP1) facility as a result of activity inside the site boundary are based on activities at the Energy Center located approximately one quarter mile west of NMP1.
This facility was open to the public and offered educational information, summer picnicking activities and fishing. However, since the events of September 11, 2001, access has been restricted. Any possible doses received by a member of the public by utilizing the private road that transverses the east and west site boundaries prior to September 11, 2001 are not considered here since it takes a matter of minutes to travel the distance.
The activity at the Energy Center that is used for the dose analysis is fishing near the shoreline adjacent to the NMP site. Although access to this area has been restricted since September 11, 2001, the dose analysis will assume access granted for all of 2001. Dose pathways considered for this activity include direct radiation, inhalation and external ground (shoreline sediment or soil) doses. Other pathways, such as ingestion pathways, are not considered because they are either not applicable, insignificant, or are considered as part of the evaluation of the total dose to a member of the public located off-site. In addition, only releases from the NMP1 stack and vent were evaluated for the inhalation pathway.
The direct radiation pathway is evaluated in accordance with the methodology found in the Off Site Dose Calculation Manual (ODCM). This pathway considers four components: direct radiation from the generating facilities, direct radiation from any possible overhead plume, direct radiation from ground deposition and direct radiation plume submersion. The direct radiation pathway is evaluated by the use of high sensitivity environmental Thermoluminescent Dosimeters (TLDs). Since any significant fishing activity near the Energy Center occurs between April through December, environmental TLD data for the approximate period of April 1 December 31, 2001 were considered. Data from environmental TLDs from the approximate area where the fishing occurs were compared to control environmental TLD locations for the same time period. The average fishing area TLD dose rate was 7.02E-03 mRem per hour for the period. The average control TLD dose rate was 6.02E-03 mRem per hour for the period (approximate second, third and fourth calendar quarters of the year). The average increase in dose as a result of fishing in this area at a conservative frequency of eight hours per week for thirty-nine weeks is 3. 1OE-01 mRem from direct radiation for the period in question. The majority of the dose from this pathway is from the NMP I facility because of its proximity to the fishing area. A small portion may be due to the Nine Mile Point Unit 2 (NMP2) facility.
Page 2 of 4 ATTACHMENT 10 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY - DECEMBER 2001 The inhalation dose pathway is evaluated by utilizing the inhalation equation in the ODCM, as adapted from Regulatory Guide 1.109. The equation basically gives a total inhalation dose in mRem for the time period in question (April - December). The total dose equals the sum, for all applicable radionuclides, of the NMP 1 stack and vent release concentrations, times the average NMPI stack and vent flow rate, times the applicable five-year average calculated X/Q, times the inhalation dose factors from Regulatory Guide 1.109, Table E-7, times the Regulatory Guide 1.109 annual air intake, times the fractional portion of the year in question. In order to be slightly conservative, no radiological decay is assumed.
The 2001 calculation utilized the following information:
NMPI Stack:
- Unit 1 average stack flowrate =
1.13E+02 m3 /sec
- X/Q value = 8.9E-06 (annual NWN sector, historical average)
- Inhalation dose factor = Table E-7 of Regulatory Guide 1.109 0 Annual air intake = 8000 m3 per year (adult) 0 Fractional portion of the year = 0.0356 (312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />)
- H-3 = 4.54E+03 pCi/m 3
- Mn-54= 3.52E-01 pCi/m 3
- Fe-55 = 8.02E-01 pCi/m 3 Co-58 = 1.95E-02 pCi/m 3
- Co-60= 1.25E+00 pCi/m3
- Sr-89 = 2.44E-01 pCi/m 3
- Sr-90 2.36E-02 pCi/m3 0
Ba/La-.140 = 7.17E-03 pCi/m 3
- Nd-147 = 9.67E-03 pCi/m3 1-131 = 5.13E-01 pCi/m3 0
1-133 = 3.04E+00 pCi/m 3
Page 3 of 4 ATTACHMENT 10 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE SITE BOUNDARY JANUARY - DECEMBER 2001 Emergency Condenser Vent:
"* Average vent flowrate = 2.75E-05 m3 /sec
"* X/Q value = 6.63E-06 (conservative ground level value)
"* Inhalation dose factor = Table E-7 of Regulatory Guide 1.109
"* Annual Air intake = 8000 m3 per year (adult)
"* Fractional portion of the year = 0.0356 (312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />)
"* H-3 = 1.31E+10 pCi/m 3
"* Cr-51 6.66E+00 pCi/m3
"* Mn-54 5.90E+01 pCi/m 3
"* Fe-55 = 6.09E+01 pCi/m 3
"* Fe-59 = 3.59E+01 pCi/m3
"* Co-58 = 2.76E+01 pCi/m3
"* Co-60 = 2.69E+02 pCi/m 3
"* Sr-89 = 2.82E+01 pCi/m 3
"* Sr-90 = 3.53E+00 pCi/m 3 The inhalation dose to a member of the public from NMP 1 as a result of activities inside the site boundary is 7.68E-04 mRem to the thyroid (maximum organ dose) and 3.20E-04 mRem to the whole body.
The dose from standing on the shoreline while fishing is based on the methodology in the ODCM, as adapted from Regulatory Guide 1.109. During 2001, it was noted that fishing was performed from the shoreline on many occasions although waders were also utilized. In order to be conservative, it is assumed that the maximum exposed individual fished from the shoreline at all times.
The ODCM equation gives the total dose to the whole body and skin from the sum of all plant related radionuclides detected in shoreline sediment samples. The plant-related radionuclide concentration is adjusted for background sample results, as applicable. The equation, therefore, yields the whole body and skin dose by multiplying the radionuclide concentration adjusted for any background data (as applicable), times a usage factor, times the sediment or soil density in grams per square meter (to a depth of one centimeter), times the applicable shore width factor, times the regulatory guide dose factor, times the fractional portion of the year over which the dose is applicable. In order to be conservative and to simplify the equation, no radiological decay is assumed since the applicable radionuclides are usually long lived.
Page 4 of 4 ATTACHMENT 10 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY JANUARY - DECEMBER 2001 The calculation utilized the following information:
"* Usage factor = 312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />
"* Density in grams per square meter = 40,000
"* Shore width factor = 0.3
"* Whole body and skin dose factor for each radionuclide = Regulatory Guide 1.109, Table E-6
"* Fractional portion of the year = 1 (used average radionuclide concentration over total time period)
"* Average Cs-137 concentration = 0.22 pCi/g The total whole body and skin dose from standing on the shoreline to fish is 3.44E-03 mRem whole body and 4.02E-03 mRem skin dose for the period.
Doses to members of the public relative to activities inside the site boundary from aquatic pathways other than ground dose from shoreline sediment/soil are not applicable.
In summary, the total dose to a member of the public as a result of activities inside the site boundary from the direct radiation, inhalation and shoreline dose pathways is 3. 1OE-0I mRem to the whole body and 7.68E-04 mRem to the maximum exposed internal organ (thyroid). The dose to the skin of an adult is 4.02E-03 mRem. These doses are generally a result of the operation of NMP1. However, a portion of these doses for the direct radiation pathway may be attributable to the NMP2 facility.
ATTACHMENT 11 Doses to Members of the Public Due To Their Activities Outside the Site Boundary
Page 1 of 3 ATTACHMENT 11 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY JANUARY - DECEMBER 2001 Radiation doses to the likely most exposed member of the public outside of the site boundary are evaluated relative to 40 CFR 190 requirements. The dose limits of 40 CFR 190 are 25 mRem (whole body or organ) per calendar year and 75 mRem (thyroid) per calendar year. The intent of 40 CFR 190 also requires that the effluents of Nine Mile Point Unit 1 (NMP1), as well as other nearby uranium fuel cycle facilities, be considered. In this case, the effluents of NMP 1, Nine Mile Point Unit 2 (NMP2) and the James A. FitzPatrick (JAF) facilities must be considered.
Doses to the likely most exposed member of the public as a result of effluents from the site can be evaluated by using calculated dose modeling based on the accepted methodologies of the facilities' Off-Site Dose Calculation Manuals (ODCMs) or may, in some cases, be calculated from the analysis results of actual environmental samples. Acceptable methods of calculating doses from environmental samples are also found in the facilities' ODCMs. These methods are based on Regulatory Guide 1.109 methodology.
Dose calculations from actual environmental samples are, at times, difficult to perform for some pathways. Some pathway doses should be estimated using calculational dose modeling. These pathways include noble gas air dose, inhalation dose, etc. Other pathway doses may be calculated directly from environmental sample concentrations using Regulatory Guide 1.109 methodology.
Since the effluents from the generating facilities are low, the resultant gaseous and liquid effluent doses are anticipated to be low. In view of this, doses can be based on calculated data. Doses are not based on actual environmental data for 2001 with the exception of doses from direct radiation, fish consumption and shoreline sediment. In addition, in order to be conservative and for the sake of simplicity, it is assumed in the dose calculations that the likely most exposed member of the public is positioned in the maximum receptor location for each pathway at the same time. This approach is utilized because the doses are very low and the computations are greatly simplified.
The following pathways are considered:
- 1. The inhalation dose is calculated at the critical residence because of the high occupancy factor. In order to be conservative, the maximum whole body and organ dose assumes no correction for residing inside a residence.
Page 2 of 3 ATTACHMENT 11 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY JANUARY - DECEMBER 2001
- 2. The milk ingestion dose is calculated utilizing the maximum milk cow location. As noted previously, in order to be conservative and for the sake of simplicity, the likely most exposed member of the public is assumed to be at all critical receptors at one time. In this case, the member of the public at the critical residence is assumed to consume milk from the critical milk location.
- 3. The maximum dose from the milk ingestion pathway as a result of consuming goat's milk is based on the same criteria established for item "2" above (ingestion of cow's milk).
- 4. The maximum dose associated from consuming meat is based on the critical meat animal. The likely most exposed member at the critical residence is assumed to consume meat from the critical meat animal location.
- 5. The maximum site dose associated with the consumption of vegetables is calculated from the critical vegetable garden location. As noted previously, the likely most exposed member of the public is assumed to be located at the critical residence and is assumed to consume vegetables from the critical garden location.
- 6. The dose, as a result of direct gamma radiation from the site, encompasses doses from direct "shine" from the generating facilities, direct radiation from any overhead gaseous plumes, plume submersion and from ground deposition. This total dose is measured by environmental TLDs. The critical location is based on the closest year-round residence from the generating facilities as well as the closest residence in the critical downwind sector in order to evaluate both direct radiation from the generating facilities and gaseous plumes as determined by the local meteorology. During 2001, the closest residence and the critical downwind residence are at the same location.
The measured average dose for 2001 at the critical residence was 54.8 mRem. The average control dose was 52.8 mRem. The average dose at the critical residence is slightly greater than the average control location dose. The net increase in dose in due to the differences between doses from naturally occurring radionuclides in the soil and rock at the different locations and due to the standard deviation in TLD measurements. There is not a significant difference between the control and critical resident dose and is within expected normal statistical variation.
Page 3 of 3 ATTACHMENT 11 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (2001)
NINE MILE POINT NUCLEAR STATION UNIT 1 DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES OUTSIDE THE SITE BOUNDARY JANUARY - DECEMBER 2001
- 7. The dose, as a result of fish consumption, is considered as part of the aquatic pathway. The dose for 2001 is calculated from actual results of the analysis of environmental fish samples.
For the sake of being conservative, the average plant-related radionuclide concentrations were utilized from fish samples taken near the site discharge points. No plant related radionuclides were detected in either the control or indicator samples. Therefore, no dose was calculated and was assumed to be zero for this pathway.
- 8. The shoreline sediment pathway is considered relative to recreational activities. The dose due to recreational activities from shoreline sediment is based on the methodology in the ODCM, as adapted from Regulatory Guide 1.109. The ODCM gives the total dose to the whole body and skin from the sum of plant-related radionuclides detected in actual shoreline sediment samples. The plant-related radionuclide concentration is adjusted for background sample results, as applicable. The total whole body and skin dose from shoreline recreational activities are 7.5 1E-04 mRem whole body and 8.77E-04 mRem skin dose for the period.
In summary, the maximum dose to the likely most exposed member of the public is 3.25E-01 mRem to the Thyroid (maximum organ dose) and 2.45E-01 mRem to the whole body. It should be noted that the maximum organ dose and maximum whole body doses are based on the sum of the maximum doses observed for all three facilities regardless of age group. This results in some conservatism. The maximum organ and whole body doses were a result of gaseous effluents.
Doses as a result of liquid effluents are secondary. The total whole body and skin dose from shoreline recreational activities are 7.5 1E-04 mRem whole body and 8.77E-04 mRem skin dose for the period. The direct radiation dose to the critical residence from the generating facilities was insignificant or zero. The dose to an individual as a result of fish consumption was also zero.
These maximum total doses are a result of operations at the NMP 1, NMP2 and the JAF facilities.
The maximum organ dose and whole body dose are below the 40 CFR 190 criteria of 25 mRem per calendar year to the maximum exposed organ or the whole body, and below 75 mRem per calendar year to the thyroid.
ATTACHMENT 12 Update of Actual Data for the Second Quarter 2001
Page 1 of 1 Unit 1 X
Unit 2 Reporting Period January - June 2001 UPDATE OF RELEASE AND DOSE DATA FOR GASEOUS (ELEVATED AND GROUND LEVEL) AND LIQUID EFFLUENTS Update of data using actual results from the offsite vendors for Strontium, Tritium, and Iron-55 for the second quarter of 2001.
GASEOUS 2nd QUARTER 2001 Activity (Ci) 2.94E-05 4.97E+00 3.97E-04 LIQUID 2nd QUARTER 2001 Activity (Ci)
No Releases No Releases No Releases No Releases GASEOUS LIQUID Particulates
- 1. Particulates with half-Ci 1.56E-03 No Releases lives > 8 days
- 2. Average release rate pCi/sec (gaseous) 2.01E-04 No Releases for period pCi/ml (liquid)
- 1. Total release Ci 4.97E+O0 No Releases
- 2. Average release rate ZCi/sec (gaseous) 6.39E-01 No Releases for period
[.Ci/ml (liquid)
Tritium, Iodines, and Particulates (with half lives greater than 8 days)
- 1. Percent of Quarterly Dose Limit 2
- 2. Percent of Annual Dose Limit to Date3
- 3. Percent of Organ Dose Rate Limit (Gaseous)(Quarterly)
-Dose Limit (Liquid)
(Quarterly & Annual)
- 4. Percent of 10CFR20 Concentration Limit 2
(Liquid)
- 5.
Percent of Dissolved or Entrained Noble Gas (Liquid)
GASEOUS 4.63E-01 (Quarterly) 1.24E + O0 (Annual) 9.39E-03 (Quarterly)
LIQUID No Releases (Quarterly)
No Releases (Annual)
No Releases (Quarterly)
No Releases (Annual)
No Releases No Releases I Concentrations less than the lower limit of detection of the counting system used are indicated with a double asterisk.
2 The percent of the 1 OCFR20 concentration limit is based on the average concentration during the quarter.
3 The dose is to the whole body for liquid effluents and the maximally exposed organ for gaseous effluents.
Nuclide' Sr-89 Sr-90 H-3 Fe-55
ATTACHMENT 13 Update of Abnormal Release for the First Half of 2001
UPDATED ATTACHMENT 1 Summary Data Page 1 of 2 Unit 1 X Unit 2 Reporting Period January - June 2001 Liquid Effluents:
10CFR20, Appendix B, Table II, Column 2 Average MPC - uCi/ml (Qtr. 1) = 3.OOE-03 Average MPC - uCi/mI (Qtr. 2) = N/A Average Energy (Fission and Activation gases - Mev}:
Qtr. 1_:
Ey
= 0.247 Rý
= 0.317 Qtr. 2:
E-y
= 0.159 Eý
= 0.253 Liquid:
Number of batch releases 0
Total time period for batch releases (hrs)
N/A Maximum time period for a batch release (hrs)
N/A Average time period for a batch release (hrs)
N/A Minimum time period for a batch release (hrs)
N/A Total volume of water used to dilute the liquid effluent during release 1 st 2nd period (L)
N/A N/A Total volume of water used to dilute the liquid effluent during reporting 1 st 2nd period (L) 1.12E+ 11 9.70E+ 10 Gaseous - (There were no releases from the operation of the Emergency Condenser Vent):
Number of batch releases 0
Total time period for batch releases (hrs)
N/A Maximum time period for a batch release (hrs)
N/A Average time period for a batch release (hrs)
N/A Minimum time period for a batch release (hrs)
N/A Gaseous (Primary Containment Purge):
Number of batch releases 1
Total time period for batch releases (hrs) 1.35E+01 Maximum time period for a batch release (hrs) 1.35E+01 Average time period for a batch release (hrs) 1.35E+01 Minimum time period for a batch release (hrs) 1.35E+01
UPDATED ATTACHMENT 1 Summary Data Page 2 of 2 Unit 1 X Unit 2 Reporting Period January - June 2001 Abnormal Releases:
A.
Liquids:
Number of releases 2
Total activity released 5.32E+00 Ci B.
Gaseous:
Number of releases 0
Total activity released N/A Ci BACKGROUND Cooling for several vital components is provided by the Reactor Building Closed Loop Cooling (RBCLC) System and the Turbine Building Closed Loop Cooling (TBCLC) System. Both systems have the residual heat removed via the Service Water (SW) System.
EVENT During July through August 2001, elevated makeup to both Closed Loop Cooling Systems CLCs was identified.
It was determined that a heat exchanger in the TBCLC was leaking into the SW System (refer to Attachment 1, page 2 of the July-December 2001 Semi-Annual Effluent Report).
Vendor results for the year 2001 have indicated a low level discharge of tritium from SW in January and again in March. The concentrations were below the required LLD for tritium (<10%
in January and 15% in March). February and all of the 2nd Quarter results showed no activity in SW. Because of the identification and repair of TBCLC tube leaks in August 2001, the tritium identified in SW from the January 2001 and March 2001 samples are being reported here as abnormal releases since they were unanticipated and unplanned. Internal Deviation/Event Report (DER) NM-2002-310 has been written to address enhancements to the current guidance regarding calculating release rates for non-gamma emitting isotopes that are determined to be present without the occurrence of gamma emitting isotopes or sustained service water rad monitor alarm.
ANALYSIS An offsite vendor analysis of the SW sample along with the amount of SW discharged in January and March yielded a calculated release of 5.32 Ci of tritium. This analysis of the dilution flow for this continuous discharge in January and March resulted in a whole body dose of 4.97E-04 mrem, and a maximum organ dose (Thyroid, Kidney, Liver, GI Tract, and Lung) of 4.97E-04 mrem. The activity and resulting dose contribution are reflected in an updated Attachment 5 (see next page).
UPDATED ATTACHMENT 5 Unit 1 X Unit 2 Reporting Period January -June 2001 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1 st 2nd EST.
QUARTER QUARTER TOTAL ERROR, %
A.
Fission & Activation Products
- 1.
Total release (not including Tritium, gases, alpha)
- 2.
Average diluted concentration during reporting period B.
Tritium1
- 1.
Total release
- 2.
Average diluted concentration during reporting period C.
Dissolved and Entrained Gases
- 1.
Total release
- 2.
Average diluted concentration during reporting period D.
Gross Alpha Radioactivity
- 1.
Total release E.
Volumes
- 1.
Prior to dilution
- 2.
Volume of dilution water used during release period
- 3.
Volume of dilution water available during reporting period:
F.
Percent of Technical Specification Limits Percent of Quarterly Whole Body Dose Limit (1.5 mrem)
Percent of Quarterly Organ Dose Limit (5 mrem)
Percent of Annual Whole Body Dose Limit to Date (3 mrem)
Percent of Annual Organ Dose Limit to Date (10 mrem)
Percent of 10CFR20 Concentration Limit Percent of Dissolved or Entrained Noble Gas Limit (2.OOE- 04 tCi/ml)
Ci gCi/ml Ci uCi/ml Ci
'uCi/ml Ci Liters Liters Liters No Releases No Releases 5.32E+00 No Releases 4.75E-08 No Releases No Releases No Releases No Releases No Releases 7.15E+ 10 No Releases 1.12E+ 11 9.70E+ 10 3.31E-02 No Releases 9.94E-03 No Releases 1.66E-02 No Releases 4.97E-03 No Releases 1.58E-03 No Releases No Releases 1
Tritium is the only isotope that was released during the first half of 2001. Therefore, the isotopic breakdown (Attachment 5, page 2 of 2) is not necessary.
5.OOE+01 5.OOE+01 5.OOE+01 5.OOE+01 5.OOE+01 5.O0E+01 5.OOE+01 T-
ATTACHMENT 14 Summary of Changes to the Environmental Monitoring and Dose Calculation Locations
ATTACHMENT 14 Unit 1 X Unit 2 Reporting Period July - December 2001
SUMMARY
OF CHANGES TO THE ENVIRONMENTAL MONITORING AND CALCULATION LOCATIONS Changes in Environmental Monitoring Locations During the report period, the control location for milk, (Woodworth) map location 73, was replaced by a new control location for milk (Summerville), map location 77, as Mr. Woodworth has retired and sold his herd. Sample location selections are based on the annual land use census. Refer to Attachment 7, changes to the ODCM, for changes in distance and direction.
New Locations for Dose Calculations During the report period, no changes in Dose Calculation Receptor Locations were required based on the results of the land use census.
ATTACHMENT 15 Off-Site Dose Calculation Manual (ODCM) Rev 21
ORIGINAL NINE MILE POINT NUCLEAR STATION NINE MILE POINT UNIT 1 CONTROLLED OFF-SITE DOSE CALCULATION MANUAL (ODCM)
DATE APPROVALS Prepared by:
Reviewed by:
Concurred by:
SIGNATURES G. R. Stinson Health Physicist
/
.r T. M. Kurtz Health Physicist T. G. Kulczycky REVISION 21 12-/1 /0
/22/a
/2// 0/
6' Supervisor, Analysis Services
/ 212 /Z 4e Concurred by:
W. R. Yaeger"'7 V /
Manager, Engineering Services L. A. Hopkins B. S. Montgomery ji
'3 bI Plant General 1Aýnager Unit 1 Genr Manag /uclear Enineering A)k Y
SUMMARY
OF REVISIONS Revision 21 (Effective 11 lar),2Oj) 1
' 0r x.
PAGE 1, 2, 5, 6, 8, 9, 11-13/15-18, 21, 24, 25, 36-44, 47-49, 52-81,86-116 3, 4, 7, 10, 14, 19, 20, 22, 23, 26-35 45, 46, 50, 51, 82-85
- 29
- 64, 77, 78 i, 19, 21, 22A, 22B, 124, 25, 26, 112 i, ii, iii, 12-16, 18, 28-40, 45-47 52, 55, 59-89, 92, 93,97-129 91-93, 95 3, 4, 21, 92, 95a-c 10, 16-20 5, 13, 18, 20, 25-30, 65, 79 66, 69 16, 69 10, 12 10, 18, 67, 69 5, D-1 5, D-1 5, D-1 D-1 iv, 3, 6, 8, 9, 11, 13, 14, 27, 29, 65, 66, 69, 69a i
DATE February 1987 December 1987 January 1988 May 1988 (Reissue)
May 27, 1988 (Reissue)
February 1990 June 1990 June 1992 February 1993 March 1993 June 1993 December 1993 June 1994 February 1995 December 1995 June 1996 June 1997 April 1999 December 1999 December 2001 Unit 1 ODCM Revision 21 December 2001
ODCM - NINE MILE POINT UNIT 1 TABLE OF CONTENTS PAGE
1.0 INTRODUCTION
1 2.0 LIQUID EFFLUENTS..........................................................................
2 2.1 Setpoint Determinations............................................................. 2 2.1.1 B asis.................................................................................. 2 2.1.2 Service Water System Effluent Alarm Setpoint................................ 2 2.1.3 Liquid Radwaste Effluent Alarm Setpoint...................................... 3 2.1.4 Discussion.......................................................................... 4 2.1.4.1 Control of Liquid Effluent Batch Discharges.................................. 4 2.1.4.2 Simultaneous Discharges of Radioactive Liquids................................ 4 2.1.4.3 Sample Representativeness....................................................... 5 2.1.4.4 Liquid Radwaste System Operation............................................. 5 2.1.4.5 Service Water System Contamination............................................. 6 2.2 Liquid Effluent Concentration Calculation.................................... 6 2.3 Dose Determinations.............................................................. 7 2.3.1 Maximum Dose Equivalent Pathway........................................... 7 3.0 GASEOUS EFFLUENTS...................................................................... 10 3.1 Setpoint Determinations......................................................... 10 3.1.1 B asis................................................................................. 10 3.1.2 Stack Monitor Setpoints......................................................... 10 3.1.3 Recombiner Discharge (Off Gas) Monitor Setpoints........................... 12 3.1.4 Emergency Condenser Vent Monitor Setpoint.................................. 13 Unit 1 ODCM Revision 21 ii December 2001
ODCM - NINE MILE POINT UNIT 1 TABLE OF CONTENTS (Cont) 3.1.5 3.1.5.1 3.1.5.2 3.1.5.3 3.1.5.4 3.1.5.5 3.1.5.6 3.2 3.2.1 3.2.1.1 3.2.1.2 3.2.2 3.2.2.1 3.2.2.2 3.2.2.3 3.3 3.4 4.0 40 CFR 4.1 4.2 4.3 PAGE D iscussion.......................................................................... 13 Stack Effluent Monitoring System Description.............................. 13 Stack Sample Flow Path - RAGEMS.......................................... 13 Stack Sample Flow Path - OGESMS............................................. 14 Sample Frequency/Sample Analysis.............................................. 14 1-133 Estimates................................................................... 14 Gaseous Radwaste Treatment System Operation............................. 15 Dose and Dose Rate Determination............................................ 15 D ose R ate..........................................................................
16 N oble G ases........................................................................ 16 Tritium, Iodines and Particulates............................................... 18 D ose................................................................................... 19 N oble G as A ir D ose................................................................. 19 Tritium lodines and Particulates...............................................
20 Accumulating Doses.............................................................. 21 Critical Receptors...............................................................
21 Refinement of Offsite Doses Resulting From Emergency Condenser Vent Releases........................................................... 22 190 REQUIREMENTS...........................................................
23 Evaluation of Doses From Liquid Effluents..................................... 24 Evaluation of Doses From Gaseous Effluents................................ 25 Evaluation of Doses From Direct Radiation.................................. 26 Unit 1 ODCM Revision 21 iii December 2001
ODCM - NINE MILE POINT UNIT 1 TABLE OF CONTENTS (Cont)
PAGE 4.4 Doses to Members of the Public Within the Site Boundary............ 26 5.0 ENVIRONMENTAL MONITORING PROGRAM...................................... 29 5.1 5.2 5.3 Table 1-1 Tables 2-1 to 2-8 Table 3-1 Table 3-2 Table 3-3 Tables 3-4 to 3-22 Table 3-23 Table 5.1 Figure 5.1-1 Figure 5.1-2 Figure 5.1-2a Figure 5.1.3-1 Appendix A Appendix B Appendix C Appendix D Sam pling Stations............................................................. 29 Interlaboratory Comparison Program.................................. 29 Capabilities for Thermoluminescent Dosimeters Used for Environmental Measurements.................................... 30 Average Energy Per Disintegration..................................... 32 Aj.t Values for the NMP-1 Facility......................................... 33 Critical Receptor Dispersion Parameters for Ground Level and Elevated Releases.................................... 41 Gamma Air and Whole Body Plume Shine Dose Factors for Noble Gases (Bi and V)............................. 42 Immersion Dose Factors for Noble Gases............................. 43 Organ Dose and Dose Rate Factors (R)................................ 44 Parameters for the Evaluation of Doses to Real Members of the Public from Gaseous and Liquid Effl uents............................................................... 63 NMP-1 Radiological Environmental Monitoring Program Sampling Locations.............................. 64 Nine Mile Point On-Site Map..........................................
68 Nine Mile Point Offsite Map............................................. 69 Nine Mile Point Offsite Map.............................................. 69a Site Boundaries............................................................ 70 Liquid Dose Factor Derivation (Aj,,)....................................... 71 Plume Shine Dose Factor Derivation (Bi and V)...................... 74 Organ Dose and Dose Rate Factors for Iodine 131 & 133, Particulates and Tritium (R1)............................... 78 Diagrams of Liquid and Gaseous Radwaste Treatment Systems....... 88 Unit 1 ODCM Revision 21 iv December 2001
1.0 INTRODUCTION
The Offsite Dose Calculation Manual (ODCM) provides the methodology to be used for demonstrating compliance with the Radiological Effluent Technical Specifications (RETS), 10 CFR 20, 10 CFR 50, and 40 CFR 190. The contents of the ODCM are based on Draft NUREG-0472, Revision 3, "Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors," September 1982; Draft NUREG-0473, Revision 2, "Radiological Effluent Technical Specifications for BWR's", "July 1979; NUREG 0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"
October 1978; the several Regulatory Guides referenced in these documents; and, communication with the NRC staff.
Section 5 contains a detailed description of the Radiological Environmental Monitoring (REM) sampling locations.
Should it be necessary to revise the ODCM, these revisions will be made in accordance with Technical Specifications.
Unit 1 ODCM Revision 21 December 2001 1
2.0 LIQUID EFFLUENTS 2.1 Setpoint Determinations 2.1.1 Basis Monitor setpoints will be established such that the concentration of radionuclides in the liquid effluent releases in the discharge canal will not exceed those concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2. Setpoints for the Service Water System Effluent Line will be calculated quarterly based on the radionuclides identified during the previous year's releases from the liquid radwaste system or the isotopes identified in the most recent radwaste release or other identified probable source. Setpoints for the Liquid Radwaste Effluent Line will be based on the radionuclides identified in each batch of liquid waste prior to its release.
After release, the Liquid Radwaste monitor setpoint may remain as set, or revert back to a setpoint based on a previous Semi-Annual Radioactive Effluent Release Report, or install blank flange in the discharge line and declare inoperable in accordance with the technical specification.
Since the Service Water System effluent monitor and Liquid Radwaste effluent monitor can only detect gamma radiation, the alarm setpoints are calculated by using the concentration of gamma emitting isotopes only (or the corresponding MPC values for the same isotopes, whichever are higher) in the Y_ (ýzCi/ml)ij expression (Section 2.1.2, 2.1.3).
The Required Dilution Factor is calculated using concentrations of all isotopes present (or the corresponding MPC values for the same isotopes, whichever are higher) including tritium and other non-gamma emitters to ensure that all radionuclides in the discharge canal do not exceed 10 CFR 20 limits.
2.1.2 Service Water System Effluent Line Alarm Setpoint The detailed methods for establishing setpoints for the Service Water System Effluent Line Monitor shall be contained in the Nine Mile Point Station Procedures. These methods shall be in accordance with the following:
Setpoint (Hi alarm)< 0. 9
, (,uCi / ml )(CF
)TDF /F.
+ background I" [(.Ci /ml),r(/MPC F
]
Setpoint (Alert alarm)< 0.7 -- (uCi+
background S*"[(lUci /ml)j,r/MPC,]
(J.Ci/ml)Iy =
concentration of gamma emitting isotope i in the sample, or the corresponding MPC of gamma emitting isotope i (MPC)i, whichever is higher (units = 1tCi/ml).
(,,Ci/mil)T = concentration of any radioactive isotope i in the sample including tritium and other non-gamma emitters or corresponding MPC of isotope i, MPCI, whichever is higher (units = pCi/ml).
TDF
= Total Dilution Flow (units = gallons/minutes).
Fsw
= Service Water Flow (units = gallons/minutes).
Unit 1 ODCM Revision 21 2
December 2001
2.1.2 Service Water System Effluent Line Alarm Setpoint (Cont'd)
= monitor calibration factor (units = net cpm/rtCi/ml).
MPCQ
= liquid effluent radioactivity concentrations limit for radionuclide i as specified in 10 CFR 20, Appendix B, Table II, Column 2.
Sample
= Those nuclides present in the previous batch release from the liquid radwaste effluent system or those nuclides present in the last Semi-annual Radioactive Effluent Release Report (units = jtCi/ml) or those nuclides present in the service water system.**
(MPC)/
= same as MPCI but for gamma emitting nuclides only.
0.9 and 0.7
= factors of conservatism to account for inaccuracies.
S i [(yCi/ml) 1T/MPCj] = Required Dilution Factor. If MPC values are used in the (ýLCi/ml)*, they must also be used in calculating RDF (numerator).
TDF/F,*
= Actual Dilution Factor 2.1.3 Liquid Radwaste Effluent Line Alarm Setpoint The detailed methods for establishing setpoints for the Liquid Radwaste Effluent Line Monitor shall be contained in the Nine Mile Point Station Procedures. These methods shall be in accordance with the following:
Setpoint (Hi-Hi alarm) < 0.9
[(PCi/ml),(
M
,]
+ background
- --*i[(PO~ / ml 1 MPC ]
+acgon Setpoint (Hi alarm) < 0.7
+(PO
/ml)(/
background
- [(,uCi / MO ir/ MPC ]
+Iakgon (JlCi/ml)jy = concentration of gamma emitting isotope i in the sample or the corresponding MPC of gamma emitting isotope i, (MPC)i whichever is higher.
(jtCi/mi)- = concentration of any radioactive isotope i in the sample including tritium and other non-gamma emitters or the corresponding MPC of isotope i MPG1 whichever is higher. (units = yCi/ml).
TDF
= Total Dilution Flow (units = gallons/minutes).
F.
= Radwaste Effluent Flow (units = gallons/minutes).
= monitor calibration factor (units = net cps/MtCi/ml).
For periods with known reactor water to Reactor Building Closed Loop Cooling (RBCLC) system leakage, RBCLC maximum permissible concentration may be prudently substituted for the above.
Unit 1 ODCM Revision 21 3
December 2001
2.1.3 Liquid Radwaste Effluent Line Alarm Setpoint (Cont'd)
MPCi
= liquid effluent radioactivity concentration limit for radionuclide i as specified in 10 CFR 20, Appendix B, Table II, Column 2, for those nuclides detected by spectral analysis of the contents of the radwaste tanks to be released. (units =,Ci /ml)
(MPC)ý
= same as MPCi but for gamma emitting nuclide only.
0.9 and 0.7
= factors of conservatism to account for inaccuracies.
Y [(Ci/ml)CT/MPCi] = Required Dilution Factor. If MPC values are used in the
(ýtCi/ml),, they must also be used in calculating RDF (numerator).
Notes:
(a)
If TDF/Fre =
Yi I (;Ci/mL)iT/MPCi]
the discharge could not be made, since the monitor would be continuously in alarm. To avoid this situation, Fe will be reduced (normally by a factor of 2) to allow setting the alarm point at a concentration higher than tank concentration. This will also result in a discharge canal concentration at approximately 50% maximum permissible concentration.
(b)
The value used for TDF will be reduced by the fractional quantity (1-FT), where FT is tempering fraction (i.e., diversion of some fraction of discharge flow to the intake canal for the purpose of temperature control).
2.1.4 Discussion 2.1.4.1 Control of Liquid Effluent Batch Discharges At Nine Mile Point Unit 1 Liquid Radwaste Effluents are released only on a batch mode.
To prevent the inadvertent release of any liquid radwaste effluents, radwaste discharge is mechanically isolated (blank flange installed or discharge valve chain-locked closed) following the completion of a batch release or series of batch releases.
This mechanical isolation remains in place and will only be removed prior to the next series of liquid radwaste discharges after all analyses required in station procedures and Technical Specification Table 4.6.15-lA are performed and monitor setpoints have been properly adjusted.
2.1.4.2 Simultaneous Discharges of Radioactive Liquids.
If during the discharge of any liquid radwaste batch, there is an indication that the service water canal has become contaminated (through a service water monitor alarm or through a grab sample analysis in the event that the service water monitor is inoperable) the discharge shall be terminated immediately. The liquid radwaste discharge shall not be continued until the cause of the service water alarm (or high grab sample analysis result) has been determined and the appropriate corrective measures taken to ensure 10CFR20, Appendix B, Table II, Column 2 (Technical Specification Section 3.6.15.a(1)) limits are not exceeded.
Unit 1 ODCM Revision 21 4
December 2001
2.1.4.2 Simultaneous Discharges of Radioactive Liquids (Cont'd)
In accordance with Liquid Waste procedures, controls are in place to preclude a simultaneous release of liquid radwaste batch tanks. In addition, an independent verification of the discharge valve line-up is performed prior to discharge to ensure that simultaneous discharges are prevented.
2.1.4.3 Sampling Representativeness This section covers Technical Specification Table 4.6.15-1 Note b concerning thoroughly mixing of each batch of liquid radwaste prior to sampling.
Liquid Radwaste Tanks scheduled for discharge at Nine Mile Point Unit 1 are isolated (i.e. inlet valves marked up) and at least two tank volumes of entrained fluids are recirculated prior to sampling. Minimum recirculation time is calculated as follows:
Minimum Recirculation Time = 2.0(T/R)
Where:
2.0 = Plant established mixing factor, unitless T = Tank volume, gal R
= Recirculation flow rate, gpm Additionally, the Hi Alarm setpoint of the Liquid Radwaste Effluent Radiation Monitor is set at a value corresponding to not more than 70% of its calculated response to the grab sample or corresponding MPC values. Thus, this radiation monitor will alarm if the grab sample, or corresponding MPC value, is significantly lower in activity than any part of the tank contents being discharged.
2.1.4.4 Liquid Radwaste System Operation Technical Specification 3.6.16.a requires that the liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge, as necessary, to meet the concentration and dose requirements of Technical Specification 3.6.15.
Utilization of the radwaste system will be based on the capability of the indicated components of each process system to process contents of the respective low conductivity and high conductivity collection tanks:
- 1)
Low Conductivity (Equipment Drains): Radwaste Filter and Radwaste Demin.
(See Fig. D-1) or modular waste water technology ("THERMEX")
- 2)
High Conductivity (Floor Drains): Waste Evaporator (See Fig. D-1) or modular waste water technology ("THERMEX") directly to the Waste Collector Tank or the Waste Sample Tanks.
Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined as described in Section 2.3 of this manual prior to the release of each batch of liquid waste. This same dose projection of Section 2.3 will also be performed in the event that untreated liquid waste is discharged, to ensure that the dose limits of Technical Specification 3.6.15.a(2) are not exceeded.
(Thereby implementing the requirements of 10CFR50.36a, General Design Criteria 60 of Appendix A and the Design Objective given in Section II-D of Appendix I to 10 CFR50).
Unit 1 ODCM Revision 21 5
December 2001
2.1.4.4 Liquid Radwaste Systems Operation (Cont'd)
For the purpose of dose projection, the following assumptions shall be made with regard to concentrations of non-gamma emitting radionuclides subsequently analyzed off-site:
a)
[H-3]
- 1 H-3 Concentration found recent condensate storage tank analysis b)
[Sr-89]
< 4 x Cs-137 Concentration c)
[Sr-90]
< 0.5 x Cs-137 Concentration d)
[Fe-55]
- _ 1 x Co-60 Concentration Assumed Scaling Factors used in b, c, and d above represent conservative estimates derived from arialysis of historical data from process waste streams. Following receipt of off-site H-3, Sr-89, Sr-90 and Fe-55 analysis information, dose estimates shall be revised using actual radionuclide concentrations and actual tank volumes discharged.
2.1.4.5 Service Water System Contamination Service water is normally non-radioactive. If contamination is suspected, as indicated by a significant increase in service water effluent monitor response, grab samples will be obtained from the service water discharge lines and a gamma isotopic analysis meeting the LLD requirements of Technical Specification Table 4.6.15-1 completed. If it is determined that an inadvertent radioactive discharge is occurring from the service water system, then:
a)
A 10CFR 50.59 review shall be performed (ref. I&E Bulletin 80-10),
b) daily service water effluent samples shall be taken and analyzed for principal gamma emitters until the release is terminated, c) an incident composite shall be prepared for H-3, gross alpha, Sr-89, Sr-90 and Fe-55 analyses and, d) dose projections shall be performed in accordance with Section 2.3 of this manual (using estimated concentrations for H-3, Sr-89, Sr-90 and Fe-55 to be conservatively determined by supervision at the time of the incident).
Additionally, service water effluent monitor setpoints may be recalculated using the actual distribution of isotopes found from sample analysis.
2.2 Liquid Effluent Concentration Calculation This calculation documents compliance with Technical Specification Section 3.6.15.a (1).
The concentration of radioactive material released in liquid effluents to unrestricted areas (see Figure B-7) shall be limited to the concentrations specified in 10CFR20, Appendix B, Table II, Column 2, for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited to 2 E-4 microcurie/milliliter (1zCi/mi) total activity.
Unit 1 ODCM Revision 21 6
December 2001
Liquid Effluent Concentration Calculation (Cont'd)
The concentration of radioactivity from Liquid Radwaste batch releases and, if applicable, Service Water System and emergency condenser start-up vent discharges are included in the calculation. The calculation is performed for a specific period of time. No credit taken for averaging over the calendar year as permitted by 10CFR20.106. The limiting concentration is calculated as follows:
MPC Fraction C.F.) / (MPC[(i F. I Where:
MPC Fraction
= The limiting concentration of 10 CFR 20, Appendix B, Table II, for radionuclides other than dissolved or entrained noble gases.
For noble gases, the concentration shall be limited to 2 E-4 microcurie/ml total activity.
Ci,=( 1LCi/ml)j,
= The concentration of nuclide i in particular effluent stream s,
,,Ci/ml.
F,
= The flow rate of a particular effluent stream s, gpm.
MPCG
= The limiting concentration of a specific nuclide i from 10CFR20, Appendix B, Table II, Column 2 (noble gas limit is 2E-4 PCi/ml).
Y_
(uCi/ml)jsFs) = The total activity rate of nuclide i, in all effluent streams s.
S (F5)
= The total flow rate of all effluent streams s, gpm (including those S
streams which do not contain radioactivity).
A value of less than one for MPC fraction is considered acceptable for compliance with Technical Specification Section 3.6.15.a.(1).
2.3 Dose Determinations 2.3.1 Maximum Dose Equivalent Pathway A dose assessment report was prepared for the Nine Mile Point Unit 1 facility by Charles T. Main, Inc., of Boston, MA. This report presented the calculated dose equivalent rates to individuals as well as the population within a 50-mile radius of the facility based on the radionuclides released in liquid and gaseous effluents during the time periods of 1 July 1980 through 31 December 1980 and from January 1981 through 31 December 1981.
The radwaste liquid releases are based on a canal discharge rate of 590 ft3/sec which affects near field and far field dilution; therefore, this report is specific to this situation.
Utilizing the effluent data contained in the Semi-Annual Radioactive Effluent Release Reports as source terms, dose equivalent rates were determined using the environmental pathway models specified in Regulatory Guides 1.109 and 1.111 as incorporated in the NRC computer codes LADTAP for liquid pathways, and XOQDOQ and GASPAR for gaseous effluent pathways. Dose equivalent rates were calculated for the total body as well as seven organs and/or tissues for the adult, teen, child, and infant age groups.
From the standpoint of liquid effluents, the pathways evaluated included fish and drinking water ingestion, and external exposure to water and sediment.
Unit 1 ODCM Revision 21 2.2 7
December 2001
Maximum Dose Equivalent Pathway (Cont'd)
The majority of the dose for a radwaste liquid batch release was received via the fish pathway. However, to comply with Technical Specifications for dose projections, the drinking water and sediment pathways are included. Therefore, all doses due to liquid effluents are calculated monthly for the fish and drinking water ingestion pathways and the sediment external pathway from all detected nuclides in liquid effluents released to the unrestricted areas to each organ. The dose projection for liquid batch releases will also include discharges from the emergency condenser vent as applicable, for all pathways.
Each age group dose factor, Ai., is given in Tables 2-1 to 2-8. To expedite time the dose is calculated for a maximum individual instead of each age group. This maximum individual will be a composite of the highest dose factor of each age group for each organ, hence Af. The following expression from NUREG 0133, Section 4.3 is used to calculate dose:
Dt=
Ai, (ATLCiLFL) I L
Where:
Dt
= The cumulative dose commitment to the total body or any organ, from the liquid effluents for the total time period (ATL) mrem.
= The length of the L th time period over which CiL and FL are averaged for all liquid releases, hours.
C11
= The average concentration of radionuclide, i, in undiluted liquid effluents during time period ATL from any liquid release, p.Cilml.
Af
= The site related ingestion dose commitment factor to the total body or any organ t for each identified principal gamma or beta emitter for a maximum individual, mrern/hr per
/.Ci/ml.
FL
= The near field average dilution factor for CL during any liquid effluent release. Defined as the ratio of the maximum undiluted liquid waste flow during release to the average flow from the site discharge structure to unrestricted receiving waters, unitless.
At values for radwaste liquid batch releases at a discharge rate of 295 ft1/sec (one circulating water pump in operation) are presented in tables 2-1 to 2-4. Ak, values for an emergency condenser vent release are presented in tables 2-5 to 2-8. The emergency condenser vent releases are assumed to travel to the perimeter drain system and released from the discharge structure at a rate of.33 ft3/sec. See Appendix A for the dose factor A. derivation. To expedite time the dose is calculated to a maximum individual. This maximum individual is a composite of the highest dose factor Akt of each age group a for each organ t and each nuclide i. If a nuclide is detected for which a factor is not listed, then it will be calculated and included in a revision to the ODCM.
All doses calculated in this manner for each batch of liquid effluent will be summed for comparison with quarterly and annual limits, added to the doses accumulated from other releases in the quarter and year of interest. In all cases, the following relationships will hold:
Unit 1 ODCM Revision 21 8
December 2001 2.3.1
2.3.1 Where
D,
= total dose received to the total releases.
body or any organ due to liquid effluent If these limits are exceeded, a special report will be submitted to the NRC identifying the cause and proposed corrective actions. In addition, if these limits are exceeded by a factor of two, calculations shall be made to determine if the dose limits contained in 40 CFR 190 have been exceeded. Dose limits, as contained in 40 CFR 190 are total body and organ doses of 25 mrem per year and a thyroid dose of 75 mrem per year.
These calculations will include doses as a result of liquid and gaseous pathways as well as doses from direct radiation. The liquid pathway analysis will only include the fish and sediment pathways since the drinking water pathway is insignificant. This pathway is only included in the station's effluent dose projections to comply with Technical Specifications. Liquid, gaseous and direct radiation pathway doses will consider the James A. FitzPatrick and Nine Mile Point Unit 2 facilities as well as Nine Mile Point Unit 1 Nuclear Station.
In the event the calculations demonstrate that the 40 CFR 190 dose limits, as defined above, have been exceeded, then a report shall be prepared and submitted to the Commission within 30 days as specified in Section 3.6.15.d of the Technical Specifications.
Section 4.0 of the ODCM contains more information concerning calculations for an evaluation of whether 40 CFR 190 limits have been exceeded.
Unit 1 ODCM Revision 21 December 2001 Maximum Dose Equivalent Pathway (Cont'd)
For a calendar quarter:
D, < 1.5 mrem total body Dt < 5 mrem for any organ For the calendar year:
D, < 3.0 mrem total body D, < 10 mrem for any organ
3.0 GASEOUS EFFLUENTS 3.1 Setpoint Determinations 3.1.1 Basis Stack gas monitor setpoints will be established such that the instantaneous release rate of radioactive materials in gaseous effluents does not exceed the 10 CFR 20 limits for annual release rate. The setpoints will be activated if the instantaneous dose rate at or beyond the (land) site boundary would exceed 500 mrem/yr to the whole body or 3000 mirem/yr to the skin from the continuous release of radioactive noble gas in the gaseous effluent.
The offgas (condenser air ejector activity) monitor setpoints provide assurance that the total body exposure to an individual at the exclusion area boundary does not exceed a small fraction of the dose guidelines of 10 CFR 100.
Emergency condenser vent monitor setpoints will be established such that the release rate for radioactive materials in gaseous effluents do not exceed the 10 CFR 20 limits for annual release rate over the projected longest period of release.
Monitor setpoints from continuous release points will be determined once per quarter under normal release rate conditions and will be based on the isotopic composition of the actual release in progress, or an offgas isotopic distribution or a more conservative default composition specified in the pertinent procedure. If the calculated setpoint is higher than the existing setpoint, it is not mandatory that the setpoint be changed.
Monitor setpoints for emergency condenser vent monitors are conservatively fixed at 5 mr/hr for reasons described in Sections 3.1.4 and therefore do not require periodic recalculations.
Under abnormal site release rate conditions, monitor alarm setpoints from continuous release points will be recalculated and, if necessary, reset at more frequent intervals as deemed necessary by Chemistry Supervision. In particular, contributions from both JAF and NMP-2 and the Emergency Condenser Vents shall be assessed.
During outages and until power operation is again realized, the last operating stack and off gas monitor alarm setpoints shall be used.
Since monitors respond to noble gases only, monitor alarm points are set to alarm prior to exceeding the corresponding total body dose rates.
The skin dose rate limit is not used in setpoint calculations because it is never limiting.
3.1.2 Stack Monitor Setpoints The detailed methods for establishing setpoints shall be contained in the station procedures. These methods shall apply the following general criteria:
(1) Rationale for Stack monitor settings is based on the general equation:
release rate, actual
=
release rate, max. allowable corresp. dose rate, actual corresp. dose rate, max. allowable
,i Qi (Q)max Q, (V, +(SF)K, (X/Q).)
500mremlyr Unit 1 ODCM Revision 21 10 December 2001
3.1.2 Stack Monitor Setpoints (Cont'd)
Where:
Qi=
release rate for each isotope i, ACi/sec.
Vi=
gamma whole body dose factor in units of mremlyr per /Ci/sec. (See Table 3-2).
(Q)n
=
instantaneous release rate limit /-Ci/sec.
SF, Ki, X/Q =
See Section 3.2.1-1.
(2)
To ensure that 10 CFR 20 and Technical Specifications dose rate limits are not exceeded, the Hi Hi alarms on the stack monitors shall be set lower than or equal to (0.9) (Q).. Hi alarms shall be set lower than or equal to (0.5) (Q)..
(3)
Based on the above conservatism, the dose contribution from JAF and NMP-2 can usually be ignored. During Emergency Classifications at JAF or NMP-2 due to airborne effluent, or after emergency condenser vent releases of significant proportions, the 500 mrem/yr value may be reduced accordingly.
(4)
To convert monitor gross count rates to yCi/sec release rates, the following general formula shall be applied:
(Cm-B) K, = Q = uCi/sec, release rate Where:
Cm
= monitor gross count rate in cps or cpm B
= monitor background count rate K,
= stack monitor efficiency factor with units of yCi/sec-cps or puCi/sec-cpm (5)
Monitor K, factors shall be determined using the general formula:
K,
=
Q-J(C-B)
Where:
Qj
= individual radionuclide stack effluent release rate as determined by isotopic analysis.
K, factors more conservative than those calculated by the above methodology may be assumed.
Alternatively, when stack release rates are near the lower limit of detection, the following general formula may be used to calculate k,:
E (2: i FZ k Yk Ek ) (3.7E4 dis) f f
sec - gCi Where:
f
= stack flow in cc/sec.
E
= efficiency in units of cpm-cc//.zCi or cps-cc/MCi (cpm = counts per minute; cps counts per second).
E,
= cpm-cc/bps or cps-cc/yps.
From energy calibration curve produced during NIST traceable primary gas calibration or transfer source calibration (bps = beta per second; yps = gammas per second).
Unit 1 ODCM Revision 21 11 December 2001
3.1.2 Stack Monitor Setpoints (Cont'd)
Yk
= b/d (betas/disintegration) or y/d (gammas/disintegration).
F,
= Activity fraction of nuclide i in the mixture.
i
= nuclide counter.
k
= discrete energy beta or gamma emitter per nuclide counter.
s
= seconds.
This monitor calibration method assumes a noble gas distribution typical of a recoil release mechanism. To ensure that the calculated efficiency is conservative, beta or gamma emissions whose energy is above the range of calibration of the detector are not included in the calculation.
3.1.3 Recombiner Discharge (Off Gas) Monitor Setpoints (1)
The Hi-Hi alarm points shall activate with recombiner discharge rates equal to or less than 500,000 pCi/sec. This alarm point may be set equal to or less than 1 Ci/sec for a period of time not to exceed 60 days provided the offgas treatment system is in operation. According to the Unit 1 Technical Specifications, Note (C) to Table 4.6.14 2, the channel functional test of the condenser air ejector radioactivity monitor shall demonstrate that automatic isolation of this pathway occurs if either of the following conditions exist:
i)
Instruments indicate two channels above the Hi-Hi alarm setpoint, ii)
Instruments indicate one channel above Hi-Hi alarm setpoint and one channel downscale.
This automatic isolation function is tested once per operating cycle in accordance with station procedures.
(2)
The Hi alarm points shall be set to activate at equal to or less than five (5) times normal full power background.
If the monitor alarms at this setpoint, the offgas will be immediately sampled and analyzed, followed by an analysis of reactor coolant sample.
(3)
To convert monitor mR/hr readings to uCi/sec, the formula below shall be applied:
(R)(KR
= QR gCi/sec recombiner discharge release rate Where:
R
= mR/hr monitor indicator.
KR
= efficiency factor in units of 1 Ci/sec/mR/hr determined prior to setting monitor alarm points.
(4)
Monitor KR factors shall be determined using the general formula:
KR
_. QiR Where:
Qi
= individual radionuclide recombiner discharge release rate as determined by isotopic analysis and flow rate monitor.
KR factors more conservative than those calculated by the above methodology may be assumed.
Unit 1 ODCM Revision 21 12 December 2001
Recombiner Discharge (Off Gas) Monitor Setpoints (Cont'd)
(5)
The setpoints chosen provide assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a very small fraction of the limits of 10CFR Part 100 in the event this effluent is inadvertently discharged directly to the environment without treatment (thereby implementing the requirements of General Design Criteria 60 and 64 of Appendix A to 10CFR Part 50). Additionally, these setpoints serve to limit buildup of fission product activity within the station systems which would result if high fuel leakage were to be permitted over extended periods.
3.1.4 Emergency Condenser Vent Monitor Setpoint The monitor setpoint was established by calculation ("Emergency Condenser Vent Monitor Alarm Setpoint", January 13, 1986, NMPC File Code #16199). Assuming a hypothetical case with (1) reactor water iodine concentrations higher than the Technical Specification Limit, (2) reactor water noble gas concentrations higher than would be expected at Technical Specification iodine levels, and (3) leakage of reactor steam into the emergency condenser shell at 300 % of rated flow (or 1.3 E6 lbs/hr), the calculation predicts an emergency condenser vent monitor response of 20 mR/hr. Such a release would result in less than 10 CFR 20 dose rate values at the site boundary and beyond for typical emergency condenser cooldown periods.
Since a 20 mR/hr monitor response can, in theory, be achievable only when reactor water iodines are higher than permitted by Technical Specifications, a conservative monitor setpoint of 5 mr/hr has been adopted.
3.1.5 Discussion 3.1.5.1 Stack Effluent Monitoring System Description The NMP-1 Stack Effluent Monitoring System consists of two subsystems; the Radioactive Gaseous Effluent Monitoring System (RAGEMS) and the Offgas Effluent Stack Monitoring System (OGESMS). During normal operation, the OGESMS shall be used to monitor station noble gas effluents and collect particulate and iodine samples in compliance with Technical Specification requirements.
The RAGEMS is designed to be promptly activated from the Main Control Room for use in high range monitoring during accident situations in compliance with NUREG 0737 criteria.
Overall system schematic for the OGESMS and RAGEMS are shown on Figure D-8 through D
- 11. A simplified view of RAGEMS Showing Unit 0, 1, 2, 3 and 4 can be found on Figure D-7.
The RAGEMS can provide continuous accident monitoring and on-line isotopic analysis of NMP-1 stack effluent noble gases at Lower Levels of Detection less than Technical Specification Table 4.6.15-2 limits. Activities as low as 5.OE-8 and as high as 2.0E5 kiCi/cc for noble gases are detectable by the system.
3.1.5.2 Stack Sample Flow Path - RAGEMS The effluent sample is obtained inside the stack at elevation 530' using an isokinetic probe with four orifices. The sample line then bends radially out and back into the stack; descends down the stack and out of the stack at approximately elevation 257'; runs horizontally (enclosed in heat tracing) some 270' along the off gas tunnel; and enters the RAGEMS located on the Turbine Building 250' (Dilution cabinet - Unit 0) and Off Gas Building 247' (Particulate, Iodine, Noble Gas stations - Units 1-3).
Unit 1 ODCM Revision 21 13 December 2001 3.1.3
3.1.5.2 Stack Sample Flow Path - RAGEMS (Cont'd)
In the Dilution cabinet of the RAGEMS, the stack gas may be diluted during accident situations approximately 100-200X (first stage) or 10000-40000 X (first and second stage) with gaseous nitrogen supplied from an on-site liquid nitrogen storage tank (see Figure D-9).
From Unit 0, the sample gas enters Unit 1-3 of RAGEMS and flows thru in-line particulate and iodine cartridges and then thru either a 6 liter (low range) or 30 cc (high range) noble gas chamber. The sample gas next flows back thru Unit 0 and the off gas tunnel; and back into the stack.
3.1.5.3 Stack Sample Flow Path - OGESMS The OGESMS sample is obtained from the same stack sample probe as the RAGEMS. From the exit of the stack at elevation 257', the sample line runs east approximately 20' and then vertically approximately 8' to the OGESMS skid. In the OGESMS, sample flows thru a particulate/iodine cartridge housing and four noble gas scintillation detectors (i.e., 07 and 08 low range beta detectors and RN-03A and RN-03B high range gamma detectors). From OGESMS, the stack sample flows back into the stack at approximately elevation 257'.
All OGESMS detector outputs are monitored and recorded remotely in the Main Control Room.
Alarming capabilities are provided to alert Operators of high release rate conditions prior to exceeding Technical Specification 3.6.15.b (1) a dose rate limits.
Stack particulate and iodine samples are retrieved manually from the OGESMS and analyzed in the laboratory using gamma spectroscopy at frequencies and LLDs specified in Table 4.6.15-2 of the Technical Specifications.
3.1.5.4 Sampling Frequency/Sample Analysis Regardless of which stack monitoring subsystem is utilized, radioactive gaseous wastes shall be sampled and analyzed in accordance with the sampling and analysis program specified in Technical Specification Table 4.6.15-2. Particulate samples are saved and analyzed for principal gamma emitters, gross alpha, Fe-55, Sr-89, Sr-90 at monthly intervals minimally.
The latter three analyses are performed off-site from a composite sample. Sample analysis frequencies are increased during elevated release rate conditions, following startup, shutdown and in conjunction with each drywell purge.
Consistent with Technical Specification Table 4.6.15-2, stack effluent tritium is sampled monthly, during each drywell purge, and weekly when fuel is off loaded until stable release rates are demonstrated. Samples are analyzed off-site.
Line loss correction factors are applied to all particulate and iodine results. Correction factors of 2.0 and 1.5 are used for data obtained from RAGEMS and OGESMS respectively. These correction factors are based on empirical data from sampling conducted at NMP-1 in 1985 (memo from J. Blasiak to RAGEMS File, 1/6/86, "Stack Sample Representativeness Study:
RAGEMS versus In-Stack Auxiliary Probe Samples").
3.1.5.5 1-133 Estimates Monthly, the stack effluent shall be sampled for iodines over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and the 1-135/1-131 and the 1-133/1-131 ratios calculated. These ratios shall be used to calculate 1-133, 1-135 release for longer acquisition samples collected during the month.
Unit 1 ODCM Revision 21 14 December 2001
3.1.5.5 1-133 Estimates (Cont'd)
Additionally, the 1-135/1-131 and 1-133/1-131 ratios should also be determined after a significant change in the ratio is suspected (eg, plant status changes from prolonged shutdown to power operation or fuel damage has occurred).
3.1.5.6 Gaseous Radwaste Treatment System Operation Technical Specification 3.6.16.b requires that the gaseous radwaste treatment system shall be operable and shall be used to reduce radioactive materials in gaseous waste prior to their discharge as necessary to meet the requirements of Technical Specification 3.6.15.b.
To ensure Technical Specification 3.6.15.b limits are not exceeded, and to confirm proper radwaste treatment system operation as applicable, cumulative dose contributions for the current calendar quarter and current calendar year shall be determined monthly in accordance with section 3.2 of this manual. Initial dose calculations shall incorporate the following assumptions with regard to release rates of non-gamma emitting radionuclides subsequently analyzed off-site:
a)
H-3 release rate
< 4 1gCi/sec b)
Sr-89 release rate
< 4 x Cs-137 release rate c)
Sr-90 release rate
- 0.5 x Cs-137 release rate d)
Fe-55 release rate
< 1 x Co-60 release rate Assumed release rates represent conservative estimates derived from analysis of historical data from effluent releases and process waste streams (See NMP 34023, C. Ware to J. Blasiak, April 29, 1988, "Dose Estimates for Beta-Emitting Isotopes"). Following receipt of off-site H-3, Sr-89, Sr-90, Fe-55 analysis information, dose estimates shall be revised using actual radionuclide concentrations.
3.2 Dose and Dose Rate Determinations In accordance with specifications 4.6.15.b.(l), 4.6.15.b.(2), and 4.6.15.b.(3) dose and dose rate determinations will be made monthly to determine:
(1)
Total body dose rates and gamma air doses at the maximum X/Q land sector site boundary interface and beyond.
(2)
Skin dose rates and beta air doses at the maximum X/Q land sector site boundary interface and beyond.
(3)
The critical organ dose and dose rate at the maximum X/Q land sector site boundary interface and at a critical receptor location beyond the site boundary.
Average meteorological data (ie, maximum five year annual average X/Q and D/Q values in the case of elevated releases or 1985 annual average X/Q and D/Q values, in the case of ground level releases) shall be utilized for dose and dose rate calculations. Where average meteorological data is assumed, dose and dose rates due to noble gases at locations beyond the site boundary will be lower than equivalent site boundary dose and dose rates. Therefore, under these conditions, calculations of noble gas dose and dose rates beyond the maximum X/Q land sector site boundary locations can be neglected.
The frequency of dose rate calculations will be upgraded when elevated release rate conditions specified in subsequent sections 3.2.1.1 and 3.2.1.2 are realized.
Unit 1 ODCM Revision 21 15 December 2001
Dose and Dose Rate Determinations (Cont'd)
Emergency condenser vent release contributions to the monthly dose and dose rate determinations will be considered only when the emergency condenser return isolation valves have been opened for reactor cooldown, if Emergency Condenser tube leaks develop with or without the system's return isolation valve opened, or if significant activity is detected in the Emergency Condenser Shell.
Without tube leakage dose contributions from emergency condenser vent releases are to be determined based on condensate storage tank and emergency condenser shell isotopic distributfions.
When releases from the emergency condenser have occurred, dose rate and dose determinations shall be performed using methodology in 3.2.1 and 3.2.2. Furthermore, environmental sampling may also be initiated to refine any actual contribution to doses. See Section 3.4.
Critical organ doses and dose rates may be conservatively calculated by assuming the existence of a maximum individual. This individual is a composite of the highest dose factor of each age group, for each organ and total body, and each nuclide. It is assumed that all pathways are applicable and the highest X/Q and/or D/Q value for actual pathways as noted in Table 3-1 are in effect. The maximum individual's dose is equal to the same dose that person would receive if they were simultaneously subjected to the highest pathway dose at each critical receptor identified for each pathway. The pathways include grass-(cow and goat)-milk, grass-cow-meat, vegetation, ground plane and inhalation. To comply with Technical Specifications we will calculate the maximum individual dose rate at the site boundary and beyond at the critical residence.
If dose or dose rates calculated, using the assumptions noted above, reach Technical Specification limits, actual pathways will be evaluated, and dose/dose rates shall be calculated at separate critical receptor locations and compared with applicable limits.
3.2.1 Dose Rate Dose rates will be calculated monthly, at a minimum, or when the Hi-Hi stack monitor alarm setpoint is reached, to demonstrate that dose rates resulting from the release of noble gases, tritium, iodines, and particulates with half lives greater than 8 days are within the limits specified in 10CFR.20. These limits are:
Noble Gases Whole Body Dose Rate:
500 mrem/yr Skin Dose Rate:
3000 mrem/yr Tritium, Iodines and Particulates Organ Dose Rate: 1500 mrem/yr 3.2.1.1 Noble Gases The following noble gas dose rate equation includes the contribution from the stack (s) elevated release and the emergency condenser vent (v) ground level release when applicable (See section 3.2).
To ensure that the site noble gas dose rate limits are not exceeded, the following procedural actions are taken if the offsite dose rates from Unit 1 exceed 10% of the limits:
- 1)
Notify the Unit 1 SSS (Station Shift Supervisor) and Unit 1 Supervisor Chemistry.
Unit 1 ODCM Revision 21 16 December 2001 3.2
3.2.1.1 Noble Gases (Cont'd)
- 2)
Notify the Unit 2 SSS and Unit 2 Supervisor Chemistry and request the Unit 2 contribution to offsite dose.
- 3)
Notify the SSS of the James A. Fitzpatrick Nuclear Plant and request the Fitzpatrick contribution to offsite dose.
- 4)
Increase the frequency of performing noble gas dose calculations, if necessary, to ensure Site (Nine Mile Point Units 1 and 2 and Fitzpatrick) limits are not exceeded.
Additionally, alarm setpoints are set at 50% of the dose rate limit to ensure that site limits are not exceeded. This alarm setpoint is adjusted if the noble gas dose rate from Unit 1 is greater than 10% of the limit.
For total body dose rates (mrem/sec):
DRy (mrem/sec) = 3.17E-8y.. [(Vi + (SF)Ki(X/Q)s)Qis + (SF)Ki (X/Q)vQivl For skin dose rates (mrem/sec):
DR,+p(mrem/sec)= 3.17E-8Ei [(Li(X/Q)s + 1.11(SF) (Bi + Mi(X/Q).))QQi
+
... (Li + 1.11(SF)Mi) (X/Q)Qiv]I Where:
DRY
= total body gamma dose rate (mrem/sec).
Dly +1O = skin dose rate from gamma and beta radiation (mrem/sec).
Vi
= the constant accounting for the gamma whole body dose rate from stack radiation for an elevated finite plume releases for each identified noble gas nuclide, i. Listed on Table 3-2 in mrem/yr per yCi/sec.
K,
= the constant accounting for the gamma whole body dose rate from immersion in the semi-infinite cloud for each identified noble gas nuclide,
- i. Listed in Table 3-3 in mrem/yr per 1 Ci/m3 (from Reg. Guide 1.109)
Qi,,Qi,
= the release rate of isotope i from the stack(s) or vent(v); (/MCi/sec)
SF
= structural shielding factor.
X/Q
= the relative plume concentration (in units of sec/m3) at the land sector site boundary or beyond. Average meteorological data (Table 3-1) is used.
"Elevated" X/Q values are used for stack releases (s = stack); "Ground" X/Q values are used for Emergency Condenser Vent releases (v = vent).
Li
= the constant accounting for the beta skin dose rate from immersion in the semi-infinite cloud for each identified noble gas nuclide, i. Listed in Table 3-3 in mrem/yr per ACi/m3 (from Reg. Guide 1.109)
Bi
= the constant accounting for the air gamma radiation from the elevated Finite plume resulting from stack releases for each identified noble gas nuclide, i. Listed in Table 3-2 in mrad/yr per yCi/sec.
Unit 1 ODCM Revision 21 17 December 2001
3.2.1.1 Noble Gases (Cont'd)
Mi
= the constant accounting for the gamma air dose rate from immersion in the semi-infinite cloud for each identified noble gas nuclide, i. Listed in Table 3-3 in mrad/yr per yCi/m3 (from Reg. Guide 1.109)
See Appendix B for derivation of Bi and Vi.
3.2.1.2 Tritium, Iodines and Particulates To ensure that the 1500 mrern/year site dose rate limit is not exceeded, offsite dose rates for tritium, iodine and particulates with half lives greater than 8 days shall be calculated monthly and when release rates (Q) exceed 0.34 MCi/sec using the following equation.
Dak (mrem/sec)
= 3.17E-8y i [i.
Rijak
[Ws Qis + WV Qiv))
Where:
DAk Total dose rate to each organ k of an individual in age group a (mrem/sec).
Wi dispersion parameter either X/Q (sec/m 3) or D/Q (1/m2) depending on pathway and receptor location assumed. Average meteorological data is used (Table 3-1). "Elevated" Wj values are used for stack releases (s = stack); "Ground" Wj values are used for Emergency Condenser Vent releases (v = vent).
Q-
= the release rate of isotope i, from the stack (s) or vent(v); (gCi/sec).
Rijak
= the dose factor for each isotope i, pathway j, age group a, and organ k (Table 3-4, through 3-22; m2-mrem/yr per zCi/sec for all pathways except inhalation, mrem/yr per MCi/m 3. The R values contained in Tables 3-4 through 3-22 were calculated using the methodology defined in NUREG-0 133 and parameters from Regulatory Guide 1.109, Revision 1; as presented in Appendix C.
3.17E-8 =
the inverse of the number of seconds in a year.
When the release rate exceeds 0.34 MCi/sec, the dose rate assessment shall also include JAF and NMP-2 contribution.
The use of the 0.34 MCi/sec release rate threshold to perform dose rate calculations is justified as follows:
(a)
The 1500 mremlyr organ dose rate limit corresponds to a minimum release rate limit of 0.34 MCi/sec calculated using the equation:
1500 = (Q, MCi/sec) x (RijWj)max Where:
1500
= site boundary dose rate limit (torem/year).
(RjjWj)max
= the maximum curie-to-dose conversion factor equal to 4.45E3 mrem-sec//,Ci-yr for Sr-90, child bone at the critical residence receptor location beyond the site boundary.
Unit 1 ODCM Revision 21 18 December 2001
3.2.1.2 Tritium, lodines and Particulates (Cont'd)
(b)
The use of 0.34 MCi/sec release rate threshold and the 4.45E3 mrem-sec//k.Ci-yr curie-to-dose conversion factor is conservative since curie-to-dose conversion factors for other isotopes likely to be present are significantly lower.
In addition, if the organ dose rate exceeds 5 % of the annual limit, the following procedural actions will be taken:
- 1)
Notify the Unit 1 SSS (Station Shift Supervisor) and Unit 1 Supervisor Chemistry.
- 2)
Notify the Unit 2 SSS and Unit 2 Supervisor Chemistry and request the Unit 2 contribution to offsite dose.
- 3)
. Notify the SSS of the James A. Fitzpatrick contribution to offsite dose.
- 4)
Increase the frequency of performing dose calculations if necessary to ensure site (Nine Mile Point Units 1 and 2 and Fitzpatrick) limits are not exceeded.
3.2.2 Dose Calculations will be performed monthly at a minimum, to demonstrate that doses resulting from the release of noble gases, tritium, iodines, and particulates with half lives greater than 8 days are within the limits specified in 10 CFR 50, Appendix I. These limits are:
Noble Gases 5 m.R gamma/calendar quarter 10 mrad beta/calendar quarter 10 mR gamma/calendar year 20 mrad beta/calendar year Tritium, Iodines and Particulates 7.5 mrem to any organ/calendar quarter 15 mrem to any organ/calendar year 3.2.2.1 Noble Gas Air Dose The following Noble Gas air dose equation includes contributions from the stack (s) elevated release and the emergency condenser vent (v) ground level release when applicable (see section 3.2):
For gamma radiation' (mrad):
DY (mrad) = 3.17E-8z* (Mi(X/Q)v Qj, + (Bi + Mi(X/Q)s) Qis] 0 t For beta radiation (mrad):
Dp(mrad) = 3.17E-8y,* Ni[(X/Q)v Qjv + (X/Q)s Qis]
t Where:
DY
=
gamma air dose (mrad)
Do
= beta air dose (mrad).
Note that the units for the gamma air dose are in mrad compared to the units for the limits are in mR. The NRC recognizes that 1 mR= 1 mrad, for gamma radiation.
Unit 1 ODCM Revision 21 19 December 2001
3.2.2.1 Noble Gas Air Dose (Cont'd)
Bi the constant accounting for the air gamma radiation from the elevated finite plume resulting from stack releases for each identified noble gas nuclide, i. Listed in Table 3-2 in mrad/yr per pCi/sec.
Ni the constant accounting for the air beta dose from immersion in the semi-infinite cloud for each identified noble gas nuclide, i.
Listed on Table 3-3 in mrad/yr per kzCi/m 3 (from Reg. Guide 1.109).
Qi, Qiv the release rate of isotope i, from the stack (s) or vent (v);
(jzCi/sec).
3.17E-8
=
the inverse of the number of seconds in a year.
Mi the constant accounting for the air gamma dose from immersion in the semi-infinite cloud for each identified noble gas nuclide, i. Listed on Table 3-3 in mrad/yr per 1 Ci/m3 (from Reg. Guide 1.109).
t total time during release period, sec.
All other parameters are as defined in section 3.2.1.1.
3.2.2.2 Tritium, Iodines and Particulates To ensure that the 15 mrem/yr facility dose limit is not exceeded, offsite doses for tritium, iodines, and particulates with half lives greater than 8 days shall be calculated monthly using the following equation:
Dak (mrem) 3.17E-8E Y, i Rijak
[W.
Qi.
+ Wv QiI]
I
- t Where:
DD-total dose to each organ k of an individual in age group a(mrem).
W-dispersion parameter either X/Q (sec/m3) or D/Q (1 /m2) depending on pathway and receptor location assumed. Average meteorological data is used (Table 3-1). "Elevated" Wj values are used for stack releases (s = stack); "Ground" Wj values are used for Emergency Condenser Vent releases (v = vent).
Qi,=V the release rate of isotope i from stack(s) or vent (v); (PtCi/sec).
Rij*,
the dose factor for each isotope i, pathway j, age group a, and organ k (Tables 3-4, through 3-22; m2-mrem/yr per PCi/sec).
R values contained in Tables 3-4 through 3-22 were calculated using the methodology defined in NUREG-0133 and parameters from Regulatory Guide 1.109, Revision 1; as presented in Appendix C.
3.17E-8
=
the inverse of the number of seconds in a year.
t total time during the release period, sec.
Unit 1 ODCM Revision 21 20 December 2001
3.2.2.3 Accumulating Doses Doses will be calculated monthly, at a minimum, for gamma air, beta air, and the critical organ for each age group. Dose estimates will, also, be calculated monthly prior to receipt of any offsite analysis data i.e., strontium, tritium, and iron-55. Results will be summed for each calendar quarter and year.
The critical doses are based on the following:
noble gas plume air dose direct radiation from ground plane deposition inhalation dose cow milk ingestion dose goat milk ingestion dose cow meat ingestion dose vegetation (food crops) ingestion dose The quarterly and annual results shall be compared to the limits listed in paragraph 3.2.2.
If the limits are exceeded, special reports, as required by Section 6.9.3 of the Technical Specification, shall be submitted.
3.3 Critical Receptors In accordance with the provisions of 10 CFR 20 and 10 CFR 50, Appendix I, the critical receptors have been identified and are contained in Table 3-1.
For elevated noble gas releases the critical receptor is the site boundary.
When 1985 average annual X/Q values are used for ground level noble gas releases, the critical receptor is the maximum X/Q land sector site boundary interface.
For tritium, iodines, and particulates with half lives greater than eight days, the critical pathways are grass-(cow and goat)-milk, grass-cow meat, vegetation, inhalation and direct radiation (ground plane) as a result of ground deposition.
The grass-(cow and goat)-milk, and grass-cow-meat pathways will be based on the greatest D/Q location. This location has been determined in conjunction with the land use census (technical specification 3.6.22) and is subject to change. The vegetation (food crop) pathway is based on the greatest D/Q garden location from which samples are taken. This location may also be modified as a result of vegetation sampling surveys.
The inhalation and ground plane dose pathways will be calculated at the critical residence.
Because the Technical Specifications state to calculate "at the site boundary and beyond",
the doses and/or dose rates must be calculated for a maximum individual who is exposed to all pathways at the site boundary and at the critical residence. The maximum individual is a composite of the highest dose factor of each age group, for each organ and total body, and each nuclide. Since the critical residence location has the greatest occupancy time, the resultant dose at the residence including all pathways is limiting.
However, due to the Technical Specification wording, the inhalation and ground plane dose at the site boundary along with all other pathways, will be calculated assuming a continuous occupancy time.
Unit 1 ODCM Revision 21 21 December 2001
3.3 Critical Receptors (Cont'd)
In lieu of correcting land site boundary ground plane and inhalation dose factors for occupancy time, a Technical Specification change will be submitted to change the requirement from calculating "at the site boundary and beyond" to "at the site boundary or beyond". Unit 1 will then calculate at the critical residence since this should be the limiting dose. Until this change is effective, the dose and/or dose rate calculations for tritium, iodines, and particulates with half lives greater than 8 days will conservatively assume that the ground plane and inhalation pathway critical receptors are at the site boundary, i.e., X/Q and D/Q, respectively, are calculated at the site boundary.
3.4 Refinement of Offsite Doses Resulting from Emergency Condenser Vent Releases The doses resulting from the operation of the emergency condensers and calculated in accordance with 3.2.2 may be refined using data from actual environmental samples.
Ground deposition samples will be obtained from an area or areas of maximum projected deposition. These areas are anticipated to be at or near the site boundary and near projected plume centerline. Using the methodology found in Regulatory Guide 1.109, the dose will be calculated to the maximum exposed individual. This dose will then be compared to the dose calculated in accordance with 3.2.2. The comparison will result in an adjustment factor of less than or greater than one which will be used to adjust the other doses from other pathways. Other environmental samples may also be collected and the resultant calculated doses to the maximum exposed individual compared to the dose calculated per 3.2.2. Other environmental sample media may include milk, vegetation (such as garden broadleaf vegetables), etc. The adjustment factors from these pathways may be applied to the doses calculated per 3.2.2 on a pathway by pathway basis or several pathway adjustment factors may be averaged and used to adjust calculated doses.
Doses calculated from actual environmental sample media will be based on the methodology presented in Regulatory Guide 1.109. The regulatory guide equations may be slightly modified to account for short intervals of time (less than one year) or modified for simplicity purposes by deleting decay factors. Deletion of decay factors would yield more conservative results.
Unit 1 ODCM Revision 21 22 December 2001
4.0 40 CFR 190 REQUIREMENTS The "Uranium Fuel Cycle" is defined in 40 CFR Part 190.02 (b) as follows:
"Uranium fuel cycle means the operations of milling of uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but excludes mining operations, operations at waste disposal sites, transportation of any radioactive material in support of these operations, and the reuse of recovered non-uranium special nuclear and by-product materials from the cycle."
Section 3.6.15.d of the Technical Specifications requires that when the calculated doses associated with -the effluent releases exceed twice the applicable quarter or annual limits, the licensee shall evaluate the calendar year doses and, if required, submit a Special Report to the NRC and limit subsequent releases such that the dose commitment to a real individual from all uranium fuel cycle sources is limited to 25 mrem to the total body or any organ (except the thyroid, which is limited to 75 mrem). This report is to demonstrate that radiation exposures to all real individuals from all uranium fuel cycle sources (including all liquid and gaseous effluent pathways and direct radiation) are less than the limits in 40 CFR Part 190. If releases that result in doses exceeding the 40 CFR 190 limits have occurred, then a variance from the NRC to permit such releases will be requested and if possible, action will be taken to reduce subsequent releases.
The report to the NRC shall contain:
- 1)
Identification of all uranium fuel cycle facilities or operations within 5 miles of the nuclear power reactor units at the site that contribute to the annual dose of the maximum exposed member of the public.
- 2)
Identification of the maximum exposed member of the public and a determination of the total annual dose to this person from existing pathways and sources of radioactive effluents and direct radiation.
The total body and organ doses resulting from radioactive material in liquid effluents from Nine Mile Point Unit 1 will be summed with the maximum doses resulting from the releases of noble gases, radioiodines, and particulates for the other calendar quarters (as applicable) and from the calendar quarter in which twice the limit was exceeded. The direct dose components will be determined by either calculation or actual measurement.
Actual measurements will utilize environmental TLD dosimetry. Calculated measurements will utilize engineering calculations to determine a projected direct dose component. In the event calculations are used, the methodology will be detailed as required in Section 6.9.1.e of the Technical Specifications.
Unit 1 ODCM Revision 21 23 December 2001
40 CFR 190 REQUIREMENTS (Cont'd)
The doses from Nine Mile Point Unit 1 will be added to the doses to the maximum exposed individual that are contributed from other uranium fuel cycle operations within 5 miles of the site. Other uranium fuel cycle facilities within 5 miles of the Site include Nine Mile Point Nuclear Station Unit 2 and the James A. Fitzpatrick Nuclear Power Plant. Doses from other facilities will be calculated in accordance with each facilities' ODCM.
For the purpose of calculating doses, the results of the Radiological Environmental Monitoring Program may be included for providing more refined estimates of doses to a real maximum exposed individual. Estimated doses, as calculated from station effluents, may be replaced by doses calculated from actual environmental sample results. Reports will include all significant details of the dose determination if radiological sampling and analyses are used to determine if the dose limits of 40CFR190 are exceeded.
4.1 Evaluation of Doses From Liquid Effluents For the evaluation of doses to real members of the public from liquid effluents, the fish consumption and shoreline sediment ground dose will be considered. Since the doses from other aquatic pathways are insignificant, fish consumption and shoreline sediment are the only two pathways that will be considered. The dose associated with fish consumption may be calculated using effluent data and Regulatory Guide 1.109 methodology or by calculating a dose to man based on actual fish sample analysis data.
Because of the nature of the receptor location and the extensive fishing in the area, the critical individual may be a teenager or an adult. The dose associated with shoreline sediment is based on the assumption that the shoreline would be utilized as a recreational area. This dose may be derived from liquid effluent data and Regulatory Guide 1.109 methodology or from actual shoreline sediment sample analysis data.
Equations used to evaluate doses from actual fish and shoreline sediment samples are based on Regulatory Guide 1.109 methodology. Because of the sample medium type and the half-lives of the radionuclides historically observed, the decay corrected portions of the equations are deleted. This does not reduce the conservatism of the calculated doses but increases the simplicity from an evaluation point of view. Table 3-23 presents the parameters used for calculating doses from liquid effluents.
The dose from fish sample media is calculated as:
Rapj
= yj [Cif (U)(Daipj) fl (1E+3)
Where:
R~pj
= The total annual dose to organ j, of an individual of age group a, from nuclide i, via fish pathway p, in mrem per year.
Cif
= The concentration of radionuclide i in fish samples in pCi/gram.
U
= The consumption rate of fish in kg/yr.
1E+3
= Grams per kilogram.
Unit 1 ODCM Revision 21 24 December 2001 4.0
Evaluation of Doses From Liquid Effluents (Cont'd)
(D~jpj)
= The ingestion dose factor for age group a, nuclide i, fish pathway p, and organ j, (Reg. Guide 1.109, Table E-11) (mrem/pCi).
f
= The fractional portion of the year over which the dose is applicable.
The dose from shoreline sediment sample media is calculated as:
R.pj
= Ei [Cis (U)(4E+4)(0.3)(Daipj) f]
Where:
Rapj
= The total annual dose to organ j, of an individual of age group a, from nuclide i, via the sediment pathway p, in mrem per year.
Cj'
= The concentration of radionuclide i in shoreline sediment in pCi/gram.
U
= The usage factor, (hr/yr) (Reg. Guide 1.109).
4E+4
= The product of the assumed density of shoreline sediment (40 kilogram per square meter to a depth of 2.5 cm) times the number of grams per kilogram.
0.3
= The shore width factor for a lake.
Daipj
= The dose factor for age group a, nuclide i, sediment pathway s, and organ j. (Reg. Guide 1.109, Table E-6)(mrem/hr per pCi/m2).
f
= The fractional portion of the year over which the dose is applicable.
4.2 Evaluation of Doses From Gaseous Effluents For the evaluation of doses to real members of the public from gaseous effluents, the pathways contained in section 3.2.2.3 of the ODCM will be considered. These include the deposition, inhalation cows milk, goats milk, meat, and food products (vegetation).
However, any updated field data may be utilized that concerns locations of real individuals, real time meteorological data, location of critical receptors, etc. Data from the most recent census and sample location surveys should be utilized. Doses may also be calculated from actual environmental sample media, as available. Environmental sample media data such as TLD, air sample, milk sample and vegetable (food crop) sample data may be utilized in lieu of effluent calculational data.
Doses to member of the public from the pathways contained in ODCM section 3.2.2.3 as a result of gaseous effluents will be calculated using the dose factors of Regulatory Guide 1.109 or the methodology of the ODCM, as applicable. Doses calculated from environmental sample media will be based on the methodologies found in Regulatory Guide 1.109.
Unit 1 ODCM Revision 21 25 December 2001 4.1
Evaluation of Doses From Direct Radiation The dose contribution as a result of direct radiation shall be considered when evaluating whether the dose limitations of 40 CFR 190 have been exceeded.
Direct radiation doses as a result of the reactor, turbine and radwaste buildings and outside radioactive storage tanks (as applicable) may be evaluated by engineering calculations or by evaluating environmental TLD results at critical receptor locations, site boundary or other special interest locations. For the evaluation of direct radiation doses utilizing environmental TLDs, the critical receptor in question, such as the critical residence, etc.,
will be compared to the control locations. The comparison involves the difference in environmental TLD results between the receptor location and the average control location result.
4.4 Doses to Members of the Public Within the Site Boundary The Semi-Annual Radioactive Effluent Release Report shall include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary as defined by Figure 5.1-1 of the specifications.
A member of the public, as defined by the Technical Specifications, would be represented by an individual who visits the sites' Energy Center for the purpose of observing the educational displays or for picnicking and associated activities.
Fishing is a major recreational activity in the area and on the Site as a result of the salmonoid and trout populations in Lake Ontario. Fishermen have been observed fishing at the shoreline near the Energy Center from April through December in all weather conditions. Thus, fishing is the major activity performed by members of the public within the site boundary. Based on the nature of the fishermen and undocumented observations, it is conservatively assumed that the maximum exposed individual spends an average of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per week fishing from the shoreline at a location between the Energy Center and the Unit 1 facility. This estimate is considered conservative but not necessarily excessive and accounts for occasions where individuals may fish more on weekends or on a few days in March of the year.
The pathways considered for the evaluation include the inhalation pathway, the ground dose pathway with the resultant whole body and skin dose and the direct radiation dose pathway with the associated whole body dose. The direct radiation dose pathway, in actuality, includes several pathways. These include: the direct radiation gamma dose to an individual from an overhead plume, a gamma submersion plume dose (as applicable), possible direct radiation dose from the facility and a ground plane dose (deposition). Because the location is in close proximity to the site, any beta plume submersion dose is felt to be insignificant.
Other pathways, such as the ingestion pathway, are not applicable since these doses are included under calculations for doses to members of the public outside of the site boundary.
In addition, pathways associated with water related recreational activities, other than fishing, are not applicable here. These include swimming, boating and wading which are prohibited at the facility.
Unit 1 ODCM Revision 21 26 December 2001 4.3
Doses to Members of the Public Within the Site Boundary (Cont'd)
The inhalation pathway is evaluated by identifying the applicable radionuclides (radioiodine, tritium and particulates) in the effluent for the appropriate time period. The radionuclide concentrations are then multiplied by the appropriate XIQ value, inhalation dose factor, air intake rate, and the fractional portion of the year in question. Thus, the inhalation pathway is evaluated using the following equation adapted from Regulatory Guide 1.109. Table 3 23 presents the reference for the parameters used in the following equation.
NOTE:
The following equation is adapted from equations C-3 and C-4 of Regulatory Guide 1. 109. Since many of the factors are in units of pCi/mn3, m3/sec., etc.,
and since the radionuclide decay expressions have been deleted because of the short distance to the receptor location, the equation presented here is not identical to the Regulatory Guide equations.
D12
=
Yj [(COF (X/Q)(DFA)Ija(BR)2 t]
Where:
D=
The maximum dose from all nuclides to the organ j and age group (a) in mrem/yr.
Ci The average concentration in the stack release of nuclide i for the period in pCi/rm3.
F Unit 1 average stack flowrate in m3/sec.
X/Q The plume dispersion parameter for a location approximately 0.50 miles west of NMP-1; the plume dispersion parameter is 8.9E-06 sec/r 3 (stack) and was obtained from the C.T. Main five year average annual X/Q tables. The stack (elevated) X/Q is conservative when based on 0.50 miles because of the close proximity of the stack and the receptor location.
(DFA)i, The dose factor for nuclide i, organ j, and age group a in mrem per pCi (Reg. Guide 1.109, Table E-7).
(BR).
Annual air intake for individuals in age group a in m1 per year (obtained from Table E-5 of Regulatory Guide 1.109).
t
=
Fractional portion of the year for which radionuclide i was detected and for which a dose is to be calculated (in years).
Unit I ODCM Revision 21 27 December 2001 4.4
Doses to Members of the Public Within the Site Boundary (Cont'd)
The ground dose pathway (deposition) will be evaluated by obtaining at least one soil or shoreline sediment sample in the area where fishing occurs. The dose will then be calculated using the sample results, the time period in question, and the methodology based on Regulatory Guide 1.109 as presented in Section 4.1. The resultant dose may be adjusted for a background dose by subtracting the applicable off-site control soil or shoreline sediment sample radionuclide activities. In the event it is noted that fishing is not performed from the shoreline, but is instead performed in the water (i.e., the use of waders), then the ground dose pathway (deposition) may not be evaluated.
The direct radiation gamma dose pathway includes any gamma doses from an overhead plume, potential submersion in the plume, possible direct radiation from the facility and ground plane dose (deposition). This general pathway will be evaluated by average environmental TLD readings. At least two environmental TLDs will be utilized at one location in the approximate area where fishing occurs. The TLDs will be placed in the field on approximately the beginning of a calendar quarter and removed on approximately the end of the calendar quarter. For the purposes of this evaluation, TLD data from quarters 2, 3, and 4 will be utilized.
The average TLD readings will be adjusted by the average control TLD readings. This is accomplished by subtracting the average quarterly control TLD value from the average fishing location TLD value. The applicable quarterly control TLD values will be utilized after adjusting for the appropriate time period (as applicable). In the event of loss or theft of the TLDs, results from a TLD or TLDs in a nearby area may be utilized.
Unit 1 ODCM Revision 21 28 December 2001 4.4
ENVIRONMENTAL MONITORING PROGRAM 5.1 Sampling Stations The current sampling locations are specified in Table 5-1 and Figures 5.1-1, 5.1-2. The meteorological tower is shown in Figure 5.1-1. The location is shown as TLD location 17.
The Radiological Environmental Monitoring Program is a joint effort between the owners and operators of the Nine Mile Point Unit 1 and the James A. FitzPatrick Nuclear Power Plant. Sampling locations are chosen on the basis of historical average dispersion or deposition parameters from all three units. The environmental sampling location coordinates shown on Table 5-1 are based on the NMP-2 reactor centerline.
The average dispersion and deposition parameters have been calculated for a 5 year period, 1978 through 1982. These average dispersion or deposition parameters for the site are used to compare results of the annual land use census.
If it is determined that sample locations required by Technical Specifications are unavailable or new locations are identified that yield a significantly higher (i.e., 50%) calculated D/Q value, actions will be taken as required by Technical Specifications 3.6.20 and 3.6.22, and the Radiological Environmental Monitoring Program updated accordingly.
5.2 Interlaboratory Comparison Program Analyses shall be performed on samples containing known quantities of radioactive materials that are supplied as part of a Commission approved or sponsored Interlaboratory Comparison Program, such as the EPA Crosscheck Program. Participation shall be only for those media, e.g., air, milk, water, etc., that are included in the Nine Mile Point Environmental Monitoring Program and for which crosscheck samples are available. An attempt will be made to obtain a QC sample to program sample ratio of 5 % or better. The site identification symbol or the actual Quality Control sample results shall be reported in the Annual Radiological Environmental Operating Report so that the Commission staff may evaluate the results.
Specific sample media for which EPA Cross Check Program samples are available include the following:
- gross beta in air particulate filters
- gamma emitters in air particulate filters
- gamnma emitters in milk
- gamma emitters in water
- tritium in water 131 in water Unit 1 ODCM Revision 21 29 December 2001 5.0
Capabilities for Thermoluninescent Dosimeters Used for Environmental Measurements Required detection capabilities for thermoluminescent dosimeters used for environmental measurements required by Table 4.6.20-1, footnote b of the Technical Specifications are based on ANSI Standard N545, section 4.3. TLDs are defined as phosphors packaged for field use. In regard to the detection capabilities for thermoluminescent dosimeters, only one determination is required to evaluate the above capabilities per type of TLD. Furthermore, the above capabilities may be determined by the vendor who supplies the TLDs. Required detection capabilities are as follows:
5.3.1 Uniformity shall be determined by giving TLDs from the same batch an exposure equal to that resulting from an exposure rate of 10 mR/hr during the field cycle. The responses obtained shall have a relative standard deviation of less than 7.5 %. A total of at least 5 TLDs shall be evaluated.
5.3.2 Reproducibility shall be determined by giving TLDs repeated exposures equal to that resulting from an exposure rate of 10 uR/hr during the field cycle. The average of the relative standard deviations of the responses shall be less than 3.0%. A total of at least 4 TLDs shall be evaluated.
5.3.3 Dependence of exposure interpretation on the length of a field cycle shall be examined by placing TLDs for a period equal to at least a field cycle and a period equal to half the same field cycle in an area where the exposure rate is known to be constant. This test shall be conducted under approximate average winter temperatures and approximate average summer temperatures. For these tests, the ratio of the response obtained in the field cycle to twice that obtained for half the field cycle shall not be less than 0.85. At least 6 TLDs shall be evaluated.
5.3.4 Energy dependence shall be evaluated by the response of TLDs to photons for several energies between approximately 30 keV and 3 MeV. The response shall not differ from that obtained with the calibration source by more than 25 % for photons with energies greater than 80 keV and shall not be enhanced by more than a factor of two for photons with energies less than 80 keV. A total of at least 8 TLDs shall be evaluated.
5.3.5 The directional dependence of the TLD response shall be determined by comparing the response of the TLD exposed in the routine orientation with respect to the calibration source with the response obtained for different orientations. To accomplish this, the TLD shall be rotated through at least two perpendicular planes. The response averaged over all directions shall not differ from the response obtained in, the standard calibration position by more than 10%. A total of at least 4 TLDs shall be evaluated.
5.3.6 Light dependence shall be determined by placing TLDs in the field for a period equal to the field cycle under the four conditions found in ANSI N545, section 4.3.6. The results obtained for the unwrapped TLDs shall not differ from those obtained for the TLDs wrapped in aluminum foil by more than 10%. A total of at least 4 TLDs shall be evaluated for each of the four conditions.
Unit 1 ODCM Revision 21 30 December 2001 5.3
5.3.7 Moisture dependence shall be determined by placing TLDs (that is, the phosphors packaged for field use) for a period equal to the field cycle in an area where the exposure rate is known to be constant. The TLDs shall be exposed under two conditions: (1) packaged in a thin, sealed plastic bag, and (2) packaged in a thin, sealed plastic bag with sufficient water to yield observable moisture throughout the field cycle. The TLD or phosphor, as appropriate, shall be dried before readout. The response of the TLD exposed in the plastic bag containing water shall not differ from that exposed in the regular plastic bag by more than 10%. A total of at least 4 TLDs shall be evaluated for each condition.
5.3.8 Self irradiation shall be determined by placing TLDs for a period equal to the field cycle in an area where the exposure rate is less than 10 uR/hr and the exposure during the field cycle is known. If necessary, corrections shall be applied for the dependence of exposure interpretation on the length of the field cycle (ANSI N545, section 4.3.3). The average exposure inferred from the responses of the TLDs shall not differ from the known exposure by more than an exposure equal to that resulting from an exposure rate of 10 uR/hr during the field cycle. A total of at least 3 TLDs shall be evaluated.
Unit 1 ODCM Revision 21 31 December 2001
TABLE 1-1 Average Energy Per Disintegration ISOTOPE Ar-41 Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Kr-89 Kr-90 Xe-131M Xe-133 Xe-133m Xe-135 Xe-135m Xe-137 Xe-138 in mev/dis 1.294 0.00248 0.0022 0.159 0.793 1.95 2.22 2.10 0.0201 0.0454 0.042 0.247 0.432 0.194 1.18 (Ref)
(3)
(1)
(1)
(1)
(1)
(1)
(2)
(2)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
ORNL-4923, Radioactive Atoms - Supplement I, M.S. Martin, November 1973.
(2)
NEDO-12037, "Summary of Gamma and Beta Emitters and Intensity Data"; M.E. Meek, R.S.
Gilbert, January 1970. (The average energy was computed from the maximum energy using the ICRP II equation, not the 1/3 value assumption used in this reference).
(3)
NCRP Report No. 58, "A Handbook of Radioactivity Measurements Procedures"; 1978 (4)
The average energy includes conversion electrons.
Unit 1 ODCM Revision 21 32 December 2001 Eymev/dis 4(
0.464 0.0371 0.250 0.253 1.32 0.377 1.37 1.01 0.143 0.135 0.19 0.317 0.095 1.64 0.611 (Ref)
(3)
(1)
(1)
(1)
(1)
(1)
(2)
(2)
(1)
(1)
(1)
(1)
(1)
(1)
(1)
TABLE 2-1 Aw VALUES - LIQUID*
RADWASTE TANK INFANT mrem - ml hr -[I NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 2.90E-1 Cr 51 Cu 64 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Mn 56 Mo 99 Na 24 1131 1 133 Ni 65 1132 Cs 134 Cs 136 Cs 137 Ba 140 Ce 141 Nb 95 La 140 Ce 144 1.31E+1 2.84E+ 1 1.72E1+1 2.32E+3 1.74E1+4 1.91E-1 2.37 3.03E+ 1 4.22 1.33E-3 1.58E-4 3.54E+2 4.05E+ 1 4.91E+2 1.50E+2 7.21E-2 3.85E-2 1.18E-2 2.79 1.13E-1 1.87E+1 8.44 4.96E+1 3.34 1.02E+1 5.91E+1 4.66E-2 2.40E-4 2.34E + 1 2.37 3.54E + 1 6.15 1.51E-4 3.2 1E-4 6.60E +2 1.19E+2 5.75E+2 1.50E-1 4.40E-2 1.59E-2 4.67E-3 1.14 2.90E-1 1.29E-2 5.23E-2 4.23 2.26 1.96E+1 8.34 2.40E+ 1 2.73E+ 1 6.66E+ 1 4.43E1+3 3.30E-2 4.15E-5 4.57 2.37 1.57E+1 1.80 6.85E-5
- 1. 14E-4 6.67E + 1 4.45E+ 1 4.07E + 1 7.74 5.17E-3 9.18E-3 1.20E-3 1.57E-1 Calculated in accordance with NUREG 0133, Section 4.3.1; Section 1.
33 2.90E-1 2.90E-1 2.90E-1 8.39E-3 1.83E-3 1.91E-1 4.14 1.63E-2 4.13 1.47E+ I 2.87E+ 1 2.37 1.17E+4 1.12E+3 1.50E-2 5.02E-2 2.07E-4 3.50E+1 2.37 4.17E +1 7.23 3.58E-4 1.70E+2 4.75E+ 1 1.54E+2 3.57E-2 1.36E-2 1.14E-2 4.62E-1 2.37 6.97E+1 9.71E+1 6.24E+1 9.23E-2 2.90E-1 3.75E-1 2.32 6.86 1.07 2.37E1+1 8.33 2.42E+ 1 5.00E+1 4.77E + 1 2.17E+2 2.32E+1 2.18E-2 7.71 2.37 1.28 1.04 1.15E-2 2.60E-4 1.79 1.81 1.80 3.69E+ 1 2.27E+ 1 1.34E+1 5.48E+ 1 1.60E1+2 and Regulatory Guide 1.109, Regulatory position C, Unit 1 ODCM Revision 21 December 2001
TABLE 2-2 Aw VALUES - LIQUID*
RADWASTE TANK CHILD mrem - ml hr-tCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT 419R-1 H3 Cr 51 Cu 64 Mn 54 Fe 55 Fe59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Mn 56 Mo 99 Na 24 1131 1 133 Ni 65 1132 Cs 134 Cs 136 Cs 137 Ba 140 Ce 141 Nb 95 La 140 Ce 144 2.13E-2 2.70 3.38E+3 4.88E+2 2.11E+3 7.46E+ 1 3.28E+2 5.73E+4
- 1. 10E-4 2.13E-2 2.51E-6 6.92 9.21E+2 1.30E+3 1.89 1.12E+2 2.15E+4 3.26E+4 4.26E+5 1.70 5.35E-3 1.52E+2 2.09E+2 3.39E+1 2.67E-1 6.13E-3 3.68E+5 3.52E+4 5.15E+5 3.61E+2 1.50E-1 5.21E+2 1.50E-1 5.00 4.39E-1 1.40 1.63 9.06E+2 1.51E+2 1.05E+3 2.24E+2 7.48E+2 3.56E+4 9.32E+2 1.08E+5 1.32 3.73E-2 2.37E+I 1.52E+2 1.19E+2 1.59E+ 1 1.47E-2 5.18E-3 1.27E+5 6.26E+4 7.28E+4 2.11E+1 6.99E-2 1.45E+2 2.68E-2 6.06E-1 4 391-1 4.39E-1 4 39E-1 7.86E-1 2.51E-6 6.92 1.34 1.89 1
1.12E+2 3.85 1.1 OE-4 1.23 5.35E-3 1.52E+2 6.94E +4 7.78E+3 5.22E-1 3.54E+ 1 6.21E-1 5.37E+ 1 7.96E-2 6.34E-2 6.39E-1 1.03E-2 3.58E-1 2.30E-1 6.52 9.53E+2 1.34
.89 1.12E+2 3.61E+4 1.1 OE-4 1.38 2.OOE-1 2.04E +2 1.52E+2 3.45E+2 6.98E+1 1.72E-2 1.87E+5 5.15E+4 1.61E+5 1.82E-1 8.24E-2 1.91E+2 1.03E-2 1.16 1.42 2.511E-6 6.92 2.76E+2 6.122E + 2 1.89 1.12E+2 3.85
- 1. 1OE-4 1.23 5.35E-3 1.52E+2 5.60E-2 1.38E-4 6.72E+4 7.68E + 3 5.78E+4 2.68E-1 6.34E-2 6.39E-1 1.03E-2 3.58E-1 Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section 1.
Unit 1 ODCM Revision 21 34 December 2001 1.33 1.65E-1 9.57E+1 1.52E+2 2.10E+2 4.19E+1 2.51 E-2 1.13E-2 6.04E+5 9.67E1+4 4.93E+5 3.96E-1 1.07E-1 2.03E+2 5.93E-2 1.81 4.39E-1 7.31E+1 1.27E+2 2.84E + 3 9.05E+ 1 2.19E+3 4.26E+2 1.31E+3 1.01E+4 1.26E+3 5.74E+3 1.08E+2 2.39E + 1 7.91E+1 1.52E+2 1.87E+1 1.69E +1 3.08 1.32E-2 3.29E+3 3.40E+3 3.14E+3 1.83E+2 5.40E + 1 3.75E+5 1.36E+3 3.80E +2
TABLE 2-3 An, VALUES - LIQUID*
RADWASTE TANK TEEN mrem - ml hr - p.Ci NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H13 3 28E-1 3 28E-1 3
R813-1
'A 28RE1 3 9R1E.-1
)
9RR-1 Cr 51 Cu 64 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Mn 56 Mo 99 Na 24 1131 1133 Ni 65 1132 Cs 134 Cs 136 Cs 137 Ba 140 Ce 141 Nb 95 La 140 Ce 144 1.02E-1 1.20E-5 3.31E+1 6.94E+2 1.07E+3 9.03 5.36E+2 2.10E+4 2.44E+4 4.66E+5 6.20 2.56E-2 1.39E+2 1.55E+2 2.53E+ 1 2.08E-1 4.90E-2 3.05E+5 2.98E+4 4.09E+5 2.35E+2 3.46E-1 4.44E+2 1.57E-1 3.99 1.02E-1 2.89 4.34E+3 4.92E+2 2.49E+3 9.82E+ 1 7.96E+2 7.28E+4 5.24E-4 6.00 1.81E-1 9.22E+ I 1.39E+2 2.17E+2 4.29E+ 1 2.66E-2 1.28E-2 7.18E+5 1.17E+5 5.44E+5 4.10E-1 3.32E-1 2.48E+2 1.02E-1 2.65 1.39 1.36 8.87E+2 1.15E+2 9.64E+2 2.15E+2 1.12E+3 3.40E+4 6.98E+2 1.15E+5 5.97 3.22E-2 1.76E+1 1.39E+2 1.16E+2 1.31E+1 1.21E-2 4.60E-3 3.33E+5 7.88E+4 1.90E+5 1.55E+ 1 3.07E-1 1.18E+2 6.35E-2 1.83 8.16E-1 1.20E-5 3.31E+1 6.41 9.03 5.36E+2 1.84E+ 1 5.24E-4 5.90 2.56E-2 1.39E+2 6.31E+4 5.99E + 3 4.32E-1 1.69E+2 2.97 2.57E+2 3.81E-1 3.04E-1 3.06 4.94E-2 1.71 3.84E-1 7.32 1.32E+3 6.41
.03 5.36E+2 4.66E+4 5.24E-4 6.04 2.29E-1 2.11E+2 1.39E+2 3.73E+2 7.52E+1 2.02E-2 2.28E+5 6.38E+4 1.85E+5 4.79E-1 3.17E-1 2.40E +2 4.94E-2 2.27 1.94 1.20E-5 3.31E+1 3.12E+2 7.89E+2 9.03 5.36E+2 1.84E+1 5.24E-4 5.90 2.56E-2 1.39E+2 2.68E-1 6.60E-4 8.73E+4 1.01E+4 7.21E+4 5.75E-1 3.04E-1 3.06 4.94E-2 1.71 2.16E+2 2.24E+2 8.86E+3 2.13E+2 5.87E+3 1.24E+3 3.93E+3 3.08E+4 2.90E+3 1.31E+4 2.28E+2 1.19E +1 1.65E+2 1.39E+2 4.30E+ 1 3.25E+1 1.44 5.59E-3 9.10E+3 9.44E+3 7.99E+3 3.63E+2 8.16E+ 1 1.05E+6 3.05E+3 5.74E+2 Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1 Section 1.
35
.109, Regulatory position C, Unit 1 ODCM Revision 21 December 2001
TABLE 2-4 Aia VALUES - LIQUID*
RADWASTE TANK ADULT mrem - ml hr - Ci NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT 4 45E-1 Cr 51 Cu 64 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Mn 56 Mo 99 Na 24 1131 1133 Ni 65 1132 Cs 134 Cs 136 Cs 137 Ba 140 Ce 141 Nb 95 La 140 Ce 144 1.82E-2 5.94 6.64E +2 1.03E+3 1.62 9.60E+ 1 2.3 1E4 2.25E+4 5.60E + 5 1.36 4.58E-3 1.35E+2 1.45E+2 2.35E+ 1 1.93E-1 4.68E-3 2.98E+5 2.96E+4 3.82E+5 2.24E+2 9.53E-2 4.39E+2 1.1 1E-1 2.48 1-82E-2 2.75 4.38E+3 4.58E+2 2.43E+3 9.15E+ 1 2.57E+2 7.36E1+4 9.39E-5 1.15E 1.73E-1 8.70E+ 1 1.35E+2 2.07E1+2 4.09E+ 1 2.5 1E-2 1.25E-2 7.08E+5 1.17E+5 5.22E+5 3.49E-1 8.20E-2 2.44E+2 6.03E-2 122 4.45E-1 1.27 1.29 8.41E+2 1.07E+2 9.31E+2 2.03E+2 6.71E+2 3.32E+4 6.45E+2 1.37E+5 1.12 3.07E-2 1.66E+1 1.35E+2 1.19E+2 1.25E+ 1 1.14E-2 4.38E-3 5.79E+5 8.42E+4 3.42E + 5 1.47E1+1 5.75E-2 1.32E+2 2.24E-2 4.24E-1 4.45E-1 7.64E-1 5.94 1.15 1.62 9.60E+1 3.30 9.39E-5 1.06 4.58E-3 1.35E+2 6.79E+4 6.02E+3 4.38E-1 3.03E+1 5.32E-1 4.60E+1 6.83E-2 5.44E-2 5.47E-1 8.84E-3 3.07E-1 4.45E-1 2.93E-1 6.94 1.31E+3 1.15 1.62 9.60E+ 1 4.92E1+4 9.39E-5 1.21 2.20E-1 1.97E+2 1.35E+2 3.55E+2 7.14E + 1 2.00E-2 2.29E+5 6.51E+4 1.77E+5 1.64E-1 6.72E-2 2.41E+2 8.84E-3 8.47E-1 4.45E-1 1.67 5.94 2.56E+2 6.79E+2 1.62 9.60E+ 1 3.30 9.39E-5 1.06 4-58E-3 1.35E+2 4.80E-2 1.18E-4 7.611E+4 8.93E+3 5.90E +4 2.29E-1 5.44E-2 5.47E-1 8.84E-3 3.07E-1 4.45E-1 3.14E+2 2.35E+2 1.34E+4 2.63E+2 8.09E + 3 1.82E+3 4.99E+3 4.63E+4 3.60E+3 1.62E+4 3.06E+2 5.52 2.02E+2 1.35E+2 5.47E + 1 3.68E+1 6.36E-1 2.35E-3 1.24E+4 1.33E+4 1.02E+4 4.61E+2 1.06E+2 1.48E+6 3.78E+3 7.37E+2 Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide Section 1.
36 1.109, Regulatory position C, Unit 1 ODCM Revision 21 December 2001
TABLE 2-5 A, VALUES - LIQUID*
EMERGENCY CONDENSER VENT INFANT mrem - ml hr-4Ci NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H3 7.43E-4 7.43E-4 7.43E-4 7.43E-4 Cr 51 Cu 64 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Mn 56 Mo 99 Na 24 1131 1 133 Ni 65 1132 Cs 134 Cs 136 Cs 137 Ba 140 Ce 141 Nb 95 La 140 Ce 144 3.35E-2 7.29E-2 4.42E-2 5.95 4.46E+ 1 4.90E-4 6.07E-3 7.77E-2 1.08E-2 3.41E-6 4.05E-7 9.08E-1 1.04E-1 1.26 3.85E-1 1.85E-4 9.88E-5 3.03E-5 7.16E-3 2.89E-4 4.79E-2 2.16E-2 1.27E-1 8.58E-3 2.60E-2 1.52E-1
- 1. 19E-4 6.17E-7 6.00E-2 6.07E-3 9.16E-2 1.58E-2 3.86E-7 8.22E-7 1.69 3.06E-1 1.47 3.85E-4 1.13E-4 4.07E-5 1.20E-5 2.93E-3 3.30E-5 1.34E-4 1.08E-2 5.78E-3 5.02E-2 2.14E-2 6.15E-2 6.99E-2 1.71E-1 1.14E+1 8.47E-5 1.06E-7 1.17E-2 6.07E-3 4.03E-2 4.62E-3 1.76E-7 2.93E-7 1.71E-1 1.14E-1 1.04E-1 1.99E-2 1.33E-5 2.35E-5 3.08E-6 4.02E-4 2.15E-5 6.07E-3 3.01E+1 2.87 3.85E-5 4.70E-6 4.89E-4 1.06E-2 7.35E-2 1.29E-4 5.30E-7 8.97E-2 6.07E-3 1.07E-1 1.85E-2 9.17E-7 4.36E-1 1.22E-1 3.95E-1 9.15E-5 3.48E-5 2.92E-5 1.19E-3 Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section 1.
Unit 1 ODCM Revision 21 37 December 2001 7.43E-4 7.43E-4 4.18E-5 9.61E-4 5.94E-3 1.76E-2 1.06E-2 2.75E-3 3.76E-2 6.08E-2 2.14E-2 6.19E-2 1.28E-1 1.22E-1 5.57E-1 5.95E-2 5.60E-5 1.98E-2 6.07E-3 6.07E-3 3.27E-3 2.67E-3 2.94E-5 6.66E-7 1.79E-1 4.60E-3 2.49E-2 4.64E-3 1.60E-1 4.61E-3 2.37E-4 9.47E-2 5.82E-2 3.43E-2 1.41E-1 4.11E-1
TABLE 2-6 A, VALUES - LIQUID*
EMERGENCY CONDENSER VENT CHILD mrem - ml hr - tCi NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT H-13 144E-1 Cr 51 Cu 64 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Mn 56 Mo 99 Na 24 1131 1133 Ni 65 1132 Cs 134 Cs 136 Cs 137 Ba 140 Ce 141 Nb 95 La 140 Ce 144 3.78E-5 1.23E-2 9.04E+2 1.28E+3 3.36E-3 1.99E-1 2.15E+4 3.07E+4 4.01E+5 3.01E-1 1.50E+2 1.86E+2 3.08E + 1 2.66E-1 6.01E-3 3.68E+5 3.51E+4 5.14E+5 2.48E+2 3.08E-2 5.21E+2 1.31E-1 1.64 3.78E-5 2.63 3.36E+3 4.79E+2 2.07E+3 7.01E+1 2.08E+2 5.73E+4 6.78E-2 1.65E-1 8.16E + 1 1.50E+2 1.87E+2 3.81E+1 2.50E-2
- 1. 1OE-2 6.04E+5 9.66E+4 4.92E+5 2.17E-1 1.54E-2 2.03E+2 4.59E-2 5.15E-1 1.44E-1 1.37 1.59 8.95E+2 1.49E+2 1.03E+3 2.15E+2 6.14E+2 3.56E+4 8.78E+2 1.02E+5 6.06E-2 3.73E-2 2.02E+ 1 1.50E+2 1.06E+2 1.44E+1 1.46E-2 5.08E-3 1.27E+5 6.25E+4 7.27E+4 1.45E+1 2.39E-3 1.45E+2 1.55E-2 8.81E-2 1.44E-1 7.58E-1 1.23E-2 2.38E-3 3.36E-3 1.99E-1 6.84E-3 2.19E-3 1.50E+2 6.19E+4 7.07E+3 5.12E-1 6.29E-2 1.1 OE-3 9.55E-2 1.42E-4 1.13E-4 1.14E-3 1.83E-5 6.36E-4 1.44E-1 2.07E-1 6.35 9.42E+2 2.38E-3 3.36E-3 1.99E-1 3.61E+4 9.61E-2 2.OOE-1 1.74E+2 1.50E+2 3.08E+2 6.35E+1 1.69E-2 1.87E+5 5.14E+4 1.60E+5 7.09E-2 6.83E-3 1.90E+2 1.83E-5 2.85E-1 Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1.109, Regulatory position C, Section 1.
Unit 1 ODCM Revision 21 38 December 2001 1.44E-1 1.44E-1 1.38 7.24E+1 1.23E+2 1.23E-2 2.82E+3 2.71E+2 8.88E+1 6.OOE+2 2.15E+3 3.36E-3 4.09E+2 1.99E-1 1.15E+3 6.84E-3 1.01E+4 1.19E+3 5.40E+3 2.19E-3 6.84E + 1 2.39E+1 6.75E + 1 1.50E+2 1.50E+2 1.67E+1 1.53E+ 1 3.07 1.30E-2 6.71E+4 3.25E+3 7.67E+3 3.40E+3 5.77E+4 3.08E+3 1.30E-1 1.26E+2 1.13E-4 1.91E+1 1.14E-3 3.75E+5 1.83E-5 1.28E+3 6.36E-4 1.34E+2
TABLE 2-7 A, VALUES - LIQUID*
EMERGENCY CONDENSER VENT TEEN mrem - ml hr-i NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-TRACT T---
1 I7AP-_
Cr 51 Cu 64 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Mn 56 Mo 99 Na 24 1131 1 133 Ni 65 1132 Cs 134 Cs 136 Cs 137 Ba 140 Ce 141 Nb 95 La 140 Ce 144 1.81E-4 5.89E-2 6.89E+2 1.05E+3 1.61E-2 9.53E-1 2.10E+4 2.38E+4 4.54E+5 2.56E-1 1.38E+2 1.47E+2 2.42E+ 1 2.08E-1 4.86E-3 3.05E+5 2.98E+4 4.09E+5 1.96E+2 2.43E-2 4.41E+2 1.05E-1 1.27 1.81E-4 2.86 4.29E+3 4.88E+2 2.46E+3 8.78E+1 2.57E+2 7.28E+4 8.80E-2 1.81E-1 8.57E+1 1.38E+2 2.06E1+2 4.11E+1 2.66E-2 1.27E-2 7.18E +5 1.17E+5 5.44E+5 2.47E-2 1.64E-2 2.45E+2 5.17E-2 5.28E-1 1.74E-1 7.12E-1 1.74E-1 1.28 1.35 8.52E+2 1.14E+2 9.50E+2 2.02E+2 5.78E+2 3.39E+4 6.81E+2 1.12E+5 6.38E-2 3.22E-2 1.63E+1 1.38E+2 1.10E+2 1.25E+1 1.21E-2 4.56E-3 3.33E+5 7.87E+4 1.89E1+5 1.27E + 1 2.36E-3 1.15E+2 1.38E-2 7.12E-2 5.89E-2 1.14E-2 1.61E-2 9.53E-1 3.28E-2 1.05E-2 1.38E+2 6.003E+4 5.74E+3 4.29E-1 3.01E-1 5.28E-3 4.57E-1 6.77E4 5.40E-4 5.43E-3 8.78E-5 3.04E-3 Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide 1 Section 1.
.109, Regulatory position C, Unit 1 ODCM Revision 21 December 2001 39 1.74E-1 2.81E-1 7.24 1.28E+3 1.14E-2 1.61E-2 9.53E-1 4.66E+4 1.24E-1 2.29E-1 1.96E+2 1.38E+2 3.54E+2 7.21E+1 2.OOE-2 2.28E+5 6.38E+4 1.85E+5 8.23E-2 8.02E-3 2.37E+2 8.78E-5 3.17E-1 1.74E-1 1.74E-I 1.83 2.15E+2 2.22E+2 5.89E-2 8.81E+3 3.10E+2 2.11E+2 7.76E2 5.82E+3 1.61E-2 1.21E+3 9.53E-1 3.34E+3 3.28E-2 3.08E+4 2.83E+3 1.27E+4 1.05E-2 1.79E+2 1.19E+1 1.54E+2 1.38E+2 1.38E+2 4.77E-4 4.07E+ 1 3.11E+1 1.44 5.54E-3 8.71E+4 8.93E+3 1.01E+4 9.43E+3 7.19E+4 7.73E+3 1.62E-1 3.03E+2 5.40E-4 4.54E+ 1 5.43E-3 1.05E+6 8.78E-5 2.96E+3 3.04E-3 3.19E+2
TABLE 2-8 A, VALUES - LIQUID*
EMERGENCY CONDENSER VENT ADULT mrem - ml hr - RCi "NUCLIDE BONE LIVER T BODY THYROID
) 1)7P-1 H3 Cr 51 Cu 64 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Mn 56 Mo 99 Na 24 1131 1133 Ni 65 1132 Cs 134 Cs 136 Cs 137 Ba 140 Ce 141 Nb 95 La 140 Ce 144 3.24E-5 1.06E-2 6.58E+2 1.02E+3 2.88E-3 1.71E-1 2.31E+4 2.18E+4 5.44E+5 2.40E-1 1.34E+2 1.37E+2 2.25E1+1 1.93E-1 4.64E-3 2.98E+5 2.96E+4 3.82E+5 1.84E+2 2.21E-2 4.38E+2 9.90E-2 1.17 3.24E-5 2.72 4.37E1+3 4.55E+2 2.41E+3 8.83E+1 2.56E1+2 7.36E+4 7.81E-2 1.73E-1
.04E+ 1 1.34E+2 1.96E+2 3.91E+1 2.50E-2 1.24E-2 7.08E +5 1.17E1+5 5.22E +5 2.32E-1 1.50E-2 2.44E+2 4.99E-2 4.89E-1 2.27E-1 1.24 1.28 8.33E+2 1.06E+2 9.22E+2 1.98E+2 5.65E+2 3.32E+4 6.27E+2 1.34E+5 5.35E-2 3.07E-2 1.53E+ 1 1.34E+2 1.12E+2 1.19E+1
- 1. 14E-2 4.34E-3 5.79E+5 8.42E+4 3.42E+5 1.21E+ 1 1.78E-3 1,31E+2 1.32E-2 6.33E-2 2.27E-1 7.43E-1 1.06E-2 2.04E-3 2.88E-3 1.71E-1 5.87E-3 1.88E-3 1.34E+2 6.43E+4 5.75E+3 4.34E-1 5.39E-2 9.46E-4 8.19E-2 1.21E-4 9.67E-5 9.73E-4 1.57E-5 5.45E-4 KIDNEY 2.27E-1 2.74E-1 6.86 1.30E+3 2.04E-3 2.88E-3 1.71E-1 4.92E1+4 1.22E-1 2.20E-1 1.82E+2 1.34E+2 3.36E1+2 6.82E+ 1 1.98E-2 2.29E1+5 6.51E+4 1.77E+5 7.88E-2 7.OOE-3 2.41E+2 1.57E-5 2.90E-1 Calculated in accordance with NUREG 0133, Section 4.3.1; and Regulatory Guide C, Section 1.
40 LUNG GI-TRACT 1.109, Regulatory position Unit 1 ODCM Revision 21 December 2001 2.27E-1 2.27E-1 1.65 3.12E+2 2.32E+2 1.06E-2 1.34E+4 2.54E+2 2.61E+2 6.72E+2 8.02E+3 2.88E-3 1.79E+3 1.71E-1 4.81E+3 5.87E-3 4.63E+4 3.50E+3 1.57E+4 1.88E-3 2.42E+2 5.52 1.86E+2 1.34E+2 1.34E+2 5.17E+1 3.51E+1 6.36E-1 2.33E-3 7.61E+4 1.24E+4 8.92E+3 1.33E+4 5.89E+4 1.01E+4 1.33E-1 3.79E+2 9.67E-5 5.68E+1 9.73E-4 1.48E+6 1.57E-5 3.66E+3 5.45E-4 3.95E+2
TABLE 3-1 Critical Receptor Dispersion Parameters' For Ground Level and Elevated Releases LOCATION Residences Dairy Cows' Milk Goats' Meat Animals Gardens Site Boundary DIR E (98')
SE (1300)
SE (1300)
ESE (1150)
E (970)
ENE (67-)
MILES 1.4 2.6 2.6 1.8 1.8 0.4 ELEVATED X/Q (sec/m3) 1.8 E-07b 2.2 E-08c 2.2 E-08c 5.1 E-08c 1.0 E-07C 2.4-E-06 b, ELEVATED DIQ (M-2 5.2 E-09b 7.0 E-10c 7.0 E-10O 1.7 E-09C 3.5 E-09° 4.4 E-08" GROUNDe X/Q(sec/m3) 4.02 E-07 6.00 E-08 6.00 E-08 1.16 E-07 2.53 E-07 6.63 E-06
- a.
These values will be used in dose calculations beginning in April 1986 but may be revised periodically to account for changes in locations of farms, gardens or critical residences.
- b.
Values based on 5 year annual meteorological data (C.T. Main, Rev. 2)
- c.
Values based on 5 year average grazing season meteorological data (C.T. Main Rev. 2)
- d.
Value are based on most restrictive X/Q land-based sector (ENE). (C.T. Main, Rev. 2)
- e.
Values are based on average annual meteorological data for the year 1985.
- f.
Conservative location based on past dairy cow and goat milk history.
Unit 1 ODCM Revision 21 41 December 2001 GROUNDe 8.58 E-09 1.64 E-09 1.64 E-09 3.54 E-09 5.55 E-09 6.35 E-08
TABLE 3-2 Gamma Air and Whole Body Plume Shine Dose Factors*
For Noble Gases Gamma Whole Body V, mrem/yr
.,Cilsec Nuclide Kr-85 Kr-85m Kr-87 Kr-88 Kr-89 Kr-83m Xe-133 Xe-133m Xe-135 Xe-135m Xe-137 Xe-138 Xe-131m Ar-41 Gamma Air Bi mradlyr
!ICi/sec 2.23E-6 1.75E-3 1.02E-2 2.23E-2 2.50E-2 2.26E-6 2.80E-4 2.27E-4 2.62E-3 5.20E-3 2.30E-3 1.32E-2 1.74E-5 1.64E-2
- Calculated in accordance with Regulatory Guide 1.109. (See Appendix B.)
Unit 1 ODCM Revision 21 December 2001 42 1.68E-3 9.65E-3 2.17E-2 1.71E-2 2.41E-4 1.87E-4 2.50E-3 4.89E-3 2.20E-3 1.26E-2 1.47E-6 1.57E-2
TABLE 3-3 IMMERSION DOSE FACTORS*
Nuclide Kr 83m Kr 85m Kr 85 Kr 87 Kr 88 Kr 89 Kr 90 Xe 131m Xe 133m Xe 133 Xe 135m Xe 135 Xe 137 Xe 138 Ar 41 S(y-Body)**
7.56E-02 1.17E3 1.61E1 5.92E3 1.47E4 1.66E4 1.56E4 9.15El 2.5 1E2 2.94E2 3.12E3 1.81E3 1.42E3 8.83E3 8.84E3 Li(g-Skin)**
1.46E3 1.34E3 9.73E3 2.37E3 1.01E4 7.29E3 4.76E2 9.94E2 3.06E2 7.11E2 1.86E3 1.22E4 4.13E3 2.69E3 Mj!(_-Air)***
1.93E1 1.23E3 1.72E1 6.17E3 1.52E4 1.73E4 1.63E4 1.56E2 3.27E2 3.53E2 3.36E3 1.92E3 1.51E3 9.2 1E3 9.30E3 From, Table B-i.Regulatory Guide 1.109 Rev. 1 mrem/yr per ýtCi/m3.
- mrad/yr per ýICi/m 3.
Unit 1 ODCM Revision 21 December 2001 43
_N 3(!Ar***
2.88E2 1.97E3 1.95E3 1.03E4 2.93E3 1.06E4 7.83E3 1.11E3 1.48E3 1.05E3 7.39E2 2.46E3 1.27E4 4.75E3 3.28E3
TABLE 3-4 DOSE AND DOSE RATE R, VALUES - INHALATION - INFANT' NUCLIDE H3*
C 14*
Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1-131 1133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 BONE 2.65E4 1.97E4 1.36E4 1.93E4 3.98E5 4.09E7 1.15E5 1.57E4 3.79E4 1.32E4 3.96E5 5.49E5 5.60E4 5.05E2 2.77E4 3.19E6 7.94E3 LIVER 6.47E2 5.3 1E3 2.53E4
- 1. 17E4 2.35E4 1.22E3 8.02E3 6.26E4 2.79E4 6.43E3 1.65E2 4.44E4 1.92E4 7.03E5 6.12E5 5.60E1 2.00E2 1.67E4 1.21E6 8.13E3 KIDNEY 6.47E2 5.31E3 1.32E1 4.98E3 T. BOD' 6.47E2 5.31E3 8.95E1 4.98E3 3.33E3 9.48E3 1.82E3
- 1. 18E4 3.11E4
- 1. 14E4 2.59E6 2.03E4 3.78E3 3.23E1 1.96E4 5.60E3 7.45E4 4.55E4 2.90E3 5.15EI 1.99E3 1.76E5 5.00E2 mrem/yr
- tCi/m 3
(
THYROID 6.47E2 5.31E3 5.75E1 1.48E7 3.56E6 mrem/yr per 4Cilm3.
' This and following Ri Tables Calculated in accordance with NUREG 0133, Section 5.3.1, except C 14 values in accordance with Regulatory Guide 1.109 Equation C-8.
Unit 1 ODCM Revision 21 44 December 2001 LUNG 6.47E2 5.31E3 1.28E4 1.00E6 8.69E4 1.02E6 7.77E5 4.51E6 6.47E5 2.03E6
- 1. 12E7 1.75E6 4.79E5 1.35E5 7.97E4 7.13E4 1.60E6 1.68E5 5.17E5 9.84E6 3.22E5 3.25E4 GI-LLI 6.47E2 5.31E3 3.57E2 7.06E3 1.09E3 2.48E4 1.11E4 3.19E4 5.14E4 6.40E4 1.31E5 2.17E4 1.27E4 4.87E4 1.06E3 2.16E3 1.33E3 1.33E3 3.84E4 8.48E4 2.16E4 1.48E5 3.12E4 3.11E4 4.72E3 2.65E2 5.18E4 2.24E4 1.90E5 1.72E5 1.34E1 5.25E3 5.38E5 3.15E3
TABLE 3-5 DOSE AND DOSE RATE R* VALUES - INHALATION - CHILD NUCLIDE H 3*
C 14*
Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 mrem/yr 4Ci/m 3
THYROID
- 1. 12E3 6.73E3 8.55E1 KIDNEY
- 1. 12E3 6.73E3 2.43E1 1.00E4
- mremlyr per 0Ci/m3.
Unit 1 ODCM Revision 21 December 2001 45 BONE 3.59E4 4.74E4 2.07E4 4.26E4 5.99E5 1.01E8 1.90E5 2.35E4 4.81E4 1.66E4 6.5 1E5 9.07E5 7.40E4 6.44E2 3.92E4 6.77E6 1.08E4 LIVER 1.12E3 6.73E3 4.29E4 2.52E4 3.34E4 1.77E3 1.31E4 1.13E5 4.18E4 9.18E3 1.72E2 4.8 1E4 2.03E4 1.01E6 8.25E5 6.48E1 2.25E2 1.95E4 2.12E6 8.73E3 T. BODY
- 1. 12E3 6.73E3 1.54E2 9.51E3 7.77E3 1.67E4 3.16E3 2.26E4 7.03E4 1.72E4 6.44E6 3.70E4 6.55E3 4.26E1 2.73E4 7.70E3 2.25E5 1.28E5 4.33E3 7.55E1 2.90E3 3.61E5 6.81E2 LUNG
- 1. 12E3 6.73E3 1.70E4 1.58E6 1.11E5 1.27E6 1.11E6 7.07E6 9.95E5 2.16E6 1.48E7 2.23E6 6.14E5 1.35E5 1.21E5 1.04E5 1.74E6 1.83E5 5.44E5 1.20E7 3.28E5 GI-LLI 1.12E3 6.73E3 1.08E3 2.29E4 2.87E3 7.07E4 3.44E4 9.62E4 1.63E4 1.67E5 3.43E5 6.1 1E4 3.70E4 1.27E5 2.84E3 5.48E3 3.85E3 3.62E3 1.02E5 2.26E5 5.66E4 3.89E5 8.2 1E4 7.14E4 1.62E7 3.85E6 5.96E4 8.62E3 3.92E2 7.88E4 3.38E4 3.30E5 2.82E5 2.11E1 8.55E3
- 1. 17E6 4.8 1E3
TABLE 3-6 DOSE AND DOSE RATE R1 VALUES - INHALATION - TEEN DE BONE LIVER i ")7]P' NUCLU H 3*
C 14" Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 2.60E4 3.34E4 1.59E4 3.86E4 4.34E5 1.08E8 1.46E5 1.86E4 3.54E4 1.22E4 5.02E5 6.70E5 5.47E4 4.79E2 2.84E4 4.89E6 7.86E3 4.87E3 5.1 1E4 2.38E4 3.70E4 2.07E3 1.51E4 1.34E5 4.58E4 1.03E4 1.69E2 4.91E4 2.05E4
- 1. 13E6 8.48E5 6.70E1 2.36E2 1.90E4 2.02E6 8.56E3 T. BODY 1.27E3 4.87E3 1.35E2 8.40E3 5.54E3 1.43E4 2.78E3 1.98E4 6.24E4 1.25E4 6.68E6 3.15E4 5.66E3 3.22E1 2.64E4 6.22E3 5.49E5 3.1 1E5 3.52E3 6.26E1 2.17E3 2.62E5 5.13E2
- mrem/yr per !tCi/m?.
Unit 1 ODCM Revision 21 December 2001 46 mrem/yr LICi/m 2
THYROID 1.27E3 4.87E3 7.50E1 1.46E7 2.92E6 KIDNEY 1.27E3 4.87E3 3.07E1 1.27E4 8.64E4 6.74E4 1.00E4 4.1 1E2 8.40E4 3.59E4 3.75E5 3.04E5 2.28E1 8.88E3 1.21E6 5.02E3 LUNG 1.27E3 4.87E3
- 2. 10E4 1.98E6 1.24E5 1.53E6 1.34E6 8.72E6 1.24E6 2.42E6 1.65E7 2.69E6 7.51E5 1.54E5 1.46E5 1.21E5 2.03E6 2.14E5 6.14E5 1.34E7 3.72E5 GI-LLI 1.27E3 4.87E3 3.00E3 6.68E4 6.39E3 1.78E5 9.52E4 2.59E5 4.66E4 3.71E5 7.65E5 1.49E5 9.68E4 2.69E5 6.49E3 1.03E4 9.76E3 8.48E3 2.29E5 4.87E5 1.26E5 8.64E5 1.82E5
TABLE 3-7 DOSE AND DOSE RATE R, VALUES - INHALATION - ADULT NUCLIDE H 3*
C 14*
Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 mremlyr 11Ci/mz THYROID 1.26E3 3.41E3 5.95E1
- mremn/yr per ýtCi/m 3.
Unit 1 ODCM Revision 21 December 2001 47 KIDNEY 1.26E3 3.41E3 2.28E1 9.84E3 BONE 1.82E4 2.46E4 1.18E4 3.24E4 3.04E5 9.92E7 1.07E5 1.41E4 2.52E4 8.64E3 3.73E5 4.78E5 3.90E4 3.44E2 1.99E4 3.43E6 5.27E3 LIVER 1.26E3 3.41E3 3.96E4 1.70E4 2.78E4 1.58E3 1.15E4 1.03E5 3.44E4 7.82E3 1.21E2 3.58E4 1.48E4 8.48E5 6.21E5 4.90E1 1.74E2 1.35E4 1.43E6
- 6. 10E3 T. BODY 1.26E3 3.41E3 1.00E2 6.30E3 3.94E3 1.06E4 2.07E3 1.48E4 4.66E4 8.72E3
- 6. 10E6 2.33E4 4.21E3 2.30E1 2.05E4 4.52E3 7.28E5 4.28E5 2.57E3 4.58E1 1.53E3 1.84E5 3.65E2 LUNG 1.26E3 3.41E3 1.44E4 1.40E6 7.21E4 1.02E6 9,28E5 5.97E6 8.64E5 1.40E6 9.60E6 1.77E6 5.05E5 9.12E4 9.76E4 7.52E4 1.27E6 1.36E5 3.62E5 7.78E6 2.21E5 GI-LLI 1.26E3 3.41E3 3.32E3 7.74E4 6.03E3 1.88E5 1.06E5 2.85E5 5.34E4 3.50E5 7.22E5 1.50E5 1.04E5 2.48E5 6.28E3 8.88E3 1.04E4 8.40E3 2.18E5 4.58E5 1.20E5 8.16E5 1.73E5 6.90E4
- 1. 19E7 2.15E6 5.42E4 7.74E3 2.91E2 6.13E4 2.58E4 2.87E5 2.22E5 1.67E1 6.26E3 8.48E5 3.56E3
TABLE 3-8 DOSE AND DOSE RATE Rý VALUES - GROUND PLANE ALL AGE GROUPS m2-mremlyr g~Ci/sec TOTAL BODY H3 C 14 Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1 131 1133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 SKIN 4.65E6 1.40E9 2.73E8 3.80E8 2.15E10 7.46E8 2.16E4 2.45E8 1.36E8 3.99E6 1.72E7 2.39E6 6.83E9 1.03El0 2.05E7 1.92E7 1.37E7 6.96E7 8.46E6 48 NUCLIDE 5.50E6 1.64E9 3.20E8 4.45E8 2.53E10 8.57E8 2.5 1E4 2.85E8 1.61E8 4.63E6 2.09E7 2.91E6 7.97E9 1.20E10 2.35E7 2.1 8E7 1.54E7 8.07E7 1.01E7 Unit 1 ODCM Revision 21 December 2001
TABLE 3-9 DOSE AND DOSE RATE R, VALUES - COW MILK - INFANT NUCLIDE H3" C 14" Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147
'-mrem/yr LLCi/sec THYROID 2.38E3 6.89E5 5.45E4 KIDNEY 2.38E3 6.89E5
- 1. 19E4 5.56E6
- mrem/yr per ýtCi/m3.
Unit 1 ODCM Revision 21 December 2001 49 m*
BONE 3.23E6 8.43E7 1.22E8 3.53E9 6.93E9 8.19E10 3.85E3 4.21E5 6.81E8 8.52E6 2.41E10 3.47E10 1.21E8 2.03E1 2.28E4 1.49E6 4.43E2 LIVER 2.38E3 6.89E5 2.51E7 5.44E7 2.13E8 1.39E7 5.90E7 1.21E10 9.39E2 1.64E5 1.04E8 8.02E8 1.24E7 4.49E10 4.06E10 1.21E5 7.99 1.39E4 6.10E5 4.55E2 T. BODY 2.38E3 6.89E5 8.35E4 5.68E6 1.45E7 8.38E7 3.46E7 1.39E8 5.58E9 1.99E8 2.09E10 6.66E2 1.17E5 2.03E7 3.53E8 3.63E6 4.54E9 2.88E9 6.22E6 2.06 1.64E3 8.34E4 2.79E1 4.74E9 4.41E9 7.42E4 LUNG 2.38E3 6.89E5 1.06E5 2.66E7 6.29E7 5.87E9 2.64E11 2.26E9 1.01E3 1.54E5 1.55E8 9.37E8 1.46E7 1.16E10 1.09E10 2.87E4 4.28E3 2.46E5 1.76E2 GI-LLI 2.38E3 6.89E5 2.43E6 9.21E6 6.91E6 1.02E8 3.46E7 1.40E8 1.02E10 1.42E8 1.02E9 4.68E5 3.03E8 3.43E7 2.86E7
- 2. 10E6 1.22E8 1.27E8 2.97E7 9.39E4 7.18E6 8.54E7 2.89E5
TABLE 3-10 DOSE AND DOSE RATE Rý VALUES - COW MILK - CHILD m2-mrem/yr 1ACi/sec NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H3" C 14" Cr 51 Mn 54 Fe 55 Fe 59 Co58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1 131 1133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 1.65E6 6.97E7 6.52E7 2.63E9 3.64E9 7.53E10 2.17E3 1.86E5 3.26E8 4.04E6 1.50E10 2.17E10 5.87E7 9.70 1.15E4 "1.04E6 2.24E2 1.57E3 3.29E5 1.35E7 3.07E7 1.06E8 6.94E6 2.89E7 7.00E9 4.77E2 1.03E4 4.07E7 3.28E8 4.99E6 2.45E10 2.08EI0 5.14E4 3.39 5.73E3 3.26E5 1.81E2 1.57E3 3.29E5 5.27E4 3.59E6 1.15E7 5.26E7 2.13E7 8.52E7 4.35E9 1.04E8 1.91E10 4.25E2 5.69E4 1.01E7 1.86E8 1.89E6 5.18E9 3.07E9 3.43E6 1.14 8.51E2 5.55E4 1.40El 1.57E3 3.29E5 2.93E4 1.57E3 3.29E5 7.99E3 3.78E6 1.57E3 3.29E5 5.34E4 2.09E7 3.06E7 4.41E9 1.08E1l 9.27E8 6.83E2 1.00E5 8.69E7 5.39E8 8.32E6 7.61E9 6.78E9 1.67E4 2.51 E3
- 1. 80E5 9.94E1 2.73E9 2.44E9 3.07E4 1.57E3 3.29E5 2.80E6 1.13E7 6.85E6
- 1. 10E8 4.05E7 1.60E8 1.23E9 1.41E8 1.01E9 4.98E5 4.42E8 3.37E7 2.92E7 2.01E6 1.32E8 1.30E8 2.97E7 9.45E4 7.15E6 8.49E7 2.87E5
'mrernyr per 1LCi/m 3.
Unit 1 ODCM Revision 21 December 2001 50
TABLE 3-11 DOSE AND DOSE RATE R, VALUES - COW MILK - TEEN NUCLIDE H 3 C 14" Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147
,-mrem/yr 40Ci/sec THYROID 9.94E2 1.34E5 1.44E4 KIDNEY 9.94E2 1.34E5 5.66E3 2.69E6 BONE 6.70E5 2.78E7 2.81E7 1.34E9 1.47E9 4.45E10 9.34E2 1.86E5 1.34E8 1.66E6 6.49E9 9.02E9 2.43E7 4.05 4.67E3 4.22E5 9.12E1 LIVER 9.94E2 1.34E5 9.01E6 1.97E7 6.57E7 4.55E6 1.86E7 4.65E9 2.95E2 1.03E5 2.24E7 1.88E8 2.82E6 1.53E10 1.20E10 2.98E4 1.99 3.12E3 1.74E5 9.91E1 "mrem/yr per i.Ci/m 3.
Unit 1 ODCM Revision 21 December 2001 51 LUNG 9.94E2 1.35E5 3.69E4 1.25E7 2.07E7 T. BODY 9.94E2 1.34E5 2.58E4 1.79E6 4.59E6 2.54E7 1.05E7 4.19E7 2.17E9 4.21E7 1.10E10 2.03E2 5.69E4 4.27E6 1.01E8 8.59E5 7.08E9 4.18E9 1.57E6 5.30E-1 3.58E2 2.27E4 5.94E0 4.33E2 1.00E5 5.12E7 3.24E8 4.94E6 4.85E9 4.08E9 1.01E4 1.47E3 1.04E5 5.82E1 2.97E9 1.85E9 1.59E9 2.00E4 I
GI-LLI 9.94E2 1.34E5 4.34E6 1.85E7 8.52E6 1.55E8 6.27E7 2.42E8 1.97E9 1.75E8 1.25E9 6.80E5 4.42E8 4.01E7 3.72E7 2.13E6 1.90E8 1.71E8 3.75E7
- 1. 14E5 8.91E6 1.06E8 3.58E5 5.49E10 3.93E8 m2
TAB]
DOSE AND R4 VALUES - CO mu-1 NUCLIDE H3*
C 14*
Cr 51 Mn 54 Fe55 Fe59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 LE 3-12 DOSE RATE
'W MILK - ADULT rem/yr 2ilsec THYROID KU 7.63E2 7.6 7.26E4 7.2 8.85E3 3.2 1.6 DNEY 3E2 6E4 6E3 IE6 6.04E6 1.06E7
- I BONE 3.63E5 1.57E7 1.61E7 8.71E8 7.99E8 3.15E10 5.34E2 1.09E5 7.41E7 9.09E5 3.74E9 4.97E9 1.35E7 2.26 2.54E3 2.29E5 4.74E1
- mrem/yr per ýtCi/m 3.
Unit 1 ODCM Revision 21 December 2001 52 LUNG 7.63E2 7.26E4 1.96E4 LIVER 7.63E2 7.26E4 5.41E6 1.08E7 3.79E7 2.70E6
- 1. 10E7 2.77E9 1.71E2 6.07E4 1.24E7 1.06E8 1.58E6 8.89E9 6.80E9 1.69E4 1.14 1.72E3 9.58E4 5.48E1 T. BODY 7.63E2 7.26E4 1.48E4 1.03E6 2.52E6 1.45E7 6.05E6 2.42E7 1.25E9 2.29E7 7.74E9
- 1. 16E2 3.27E4 2.36E6 6.08E7 4.82E5 7.27E9 4.46E9 8.83E5 3.01E-1 1.95E2 1.23E4 3.28E0 GI-LLI 7.63E2 7.26E4 3.72E6 1.66E7 6.21E6 1.26E8, 5.47E7 2.06E8 1.75E9 1.28E8 9.1 1E8 5.43E5 3.69E8 2.87E7 2.80E7 1.42E6 1.56E8 1.32E8 2.77E7 8.35E4 6.58E6 7.74E7 2.63E5 2.69E2 6.00E4 2.81E7 1.82E8 2.76E6 2.88E9 2.31 E9 5.75E3 7.99E2 5.68E4 3.20EI 1.85E9 3.47E10 2.32E8 9.55E8 7.68E8 9.69E3
TABLE 3-13 DOSE AND DOSE RATE B. VALUES - GOAT MILK - INFANT m2 NUCLIDE H3*
C 14" Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147
-mrem/yr
,,Cilsec THYROID 6.33E3 6.89E5 6.56E3 KIDNEY 6.33E3 6.89E5 1.43E3 6.67E5 J*
- mrem/yr per ýtCi/m3.
Unit 1 ODCM Revision 21 December 2001 53 LUNG 6.33E3 6.89E5 1.28E4 3.46E5 8.21E5 BONE 3.23E6 1.10E6 1.59E6 4.24E8 1.48E10 1.72E11 4.66E2 9.42E4 8.17E8 1.02E7 7.23E10 1.04E131 1.45E7 2.430 2.74E3 1.79E5 5.32E1 LIVER 6.33E3 6.89E5 3.01E6 7.08E5 2.78E6 1.67E6 7.08E6 1.45E9
- 1. 13E2 3.88E4 1.27E7 9.63E8 1.49E7 1.35E11 1.22E11 1.45E4 9.59E-1 1.67E3 7.32E4 5.47E1 T. BODY 6.3-3E3 6.89E5 1.00E4 6.82E5 1.89E5 1.09E6 4.16E6 1.67E7 6.70E8 4.24E8 4.38E10 8.04E1 2.24E4 2.47E6 4.23E8 4.36E6 1.36E10 8.63E9 7.48E5 2.47E-1 1.96E2 1.00E4 3.35E0 1.42E10 1.32E10 8.91E3 I
GI-LLI 6.33E3 6.89E5 2.93E5 1.11E6 8.98E4 1.33E6 4.16E6 1.68E7 1.23E9 3.04E8 2.15E9 5.65E4 3.27E7 4.17E6 3.44E7 2.52E6 3.66E8 3.81 E8 3.56E6
- 1. 13E4 8.62E5 1.03E7 3.46E4 7.04E8 3.16El I 2.71E9 1.22E2 2.78E4 1.89E7
- 1. 12E9 1.75E7 3.47E10 3.27E10 3.44E3 5.14E2 2.96E4 2.111El
TABLE 3-14 DOSE AND DOSE RATE RB VALUES - GOAT MILK - CHILD NUCLIDE H3*
C 14" Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147
ý-mrem/yr tCi/sec THYROID 4.17E3 3.29E5 3.52E3 KIDNEY 4.17E3 3.29E5 9.62E2 4.54E5
- mrem/yr per ýtCi/m 3.
Unit I ODCM Revision 21 December 2001 54 LUNG 4.17E3 3.29E5 6.43E3 2.72E5 3.99E5 BONE 1.65E6 9.06E5 8.52E5 3.15E8 7.77E9 1.58El1 2.62E2 5.05E4 3.91E8 4.84E6 4.49E10 6.52E10 7.05E6 1.16 1.38E3 1.25E5 2.68E1 LIVER 4.17E3 3.29E5 1.62E6 4.81E5 1.38E6 8.35E5 3.47E6 8.40E8 5.76E1 1.96E4 4.95E6 3.94E8 5.99E6 7.37E10 6.24E10 6.18E3 4.07E-1 6.88E2 3.91E4 2.17E1 T. BODY 4.17E3 3.29E5 6.34E3 4.3 1E5 1.49E5 6.86E5 2.56E6 1.02E7 5.23E8 2.22E8 4.01E10 5.13E1 1.40E4 1.22E6 2.24E8 2.27E6 1.55E10 9.21E9 4.12E5 1.37E-1 1.02E2 6.66E3 1.68E0 8.19E9 7.32E9 3.68E3 I
GI-LLI 4.17E3 3.29E5 3.36E5 1.36E6 8.91E4 1.43E6 4.87E6 1.92E7 1.48E8 3.01E8 2.13E9 6.01E4 3.63E7 4.09E6 3.50E7 2.41E6 3.97E8 3.91E8 3.57E6
- 1. 13E4 8.59E5 1.02E7 3.44E4 5.29E8 1.30E11 1.11E9 8.25E1 1.85E4 1.06E7 6.46E8 9.98E6 2.28E10 2.03E10 2.01E3 3.02E2 2.16E4
- 1. 19El m*
TABLE 3-15 DOSE AND DOSE RATE RI VALUES - GOAT MILK - TEEN NUCLIDE H3*
C 14" Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147
-mrem/yr 41Ci/sec THYROID 2.64E3 1.34E5 1.73E3 KIDNEY 2.64E3 1.34E5 6.82E2 3.23E5
- mremlyr per ýlCi/m 3.
Unit 1 ODCM Revision 21 December 2001 55 LUNG 2.64E3 1.35E5 4.44E3 BONE 6.70E5 3.6-E5 3.67E5 1.61E8 3.14E9 9.36E10 1.13E2 2.23E4 1.61E8 1.99E6 1.95E10 2.71E10 2.92E6 4.86E-1 5.60E2 5.06E4 1.09E1 LIVER 2.64E3 1.34E5 1.08E6 2.56E5 8.57E5 5.46E5 2.23E6 5.58E8 3.56E1 1.24E4 2.72E6 2.26E8 3.38E6 4.58E10 3.60E10 3.58E3 2.39E-1 3.74E2 2.09E4 1.19El T. BODY 2.64E3 1.34E5 3.11E3 2.15E5 5.97E4 3.31E5 1.26E6 5.03E6 2.60E8 8.99E7 2.31EI0 2.45EI 6.82E3 5.19E5 1.21E8 1.03E6 2.13E10 1.25E10 1.88E5 6.36E-2 4.30E1 2.72E3 7.13E-1 5.56E9 4.76E9 2.41E3 5.23E1 1.20E4 6.23E6 3.89E8 5.93E6 1.46E10 1.23E10 1.21E3 1.76E2 1.25E4 6.99E0 GI-LLI 2.64E3 1.34E5 5.23E5 2.22E6 1.1 1E5 2.03E6 7.53E6 2.91E7 2.36E8 3.74E8 2.63E9 8.22E4 5.30E7 4.87E6 4.47E7 2.56E6 5.70E8 5.12E8 4.50E6 1.37E4 1.07E6 1.27E7 4.29E4 1.62E5 2.70E5 3.57E8 6.59E10 4.72E8 m2
TABLE 3-16 DOSE AND DOSE RATE Ri VALUES - GOAT MILK - ADULT NUCLIDE 113*
C 14" Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 S-mrem/yr iCi/sec THYROID 2.03E3 7.26E4 1.06E3 BONE 3.63E5 2.04E5 2.10E5 1.05E8 1.70E9 6.62E10 6.45E1 1.31E4 8.89E7 1.09E6 1.12E10 1.49E10 1.62E6 2.71E-1 3.06E2 2.75E4 5.69E0
'mrem/yr per ý.Ci/m 3.
Unit 1 ODCM Revision 21 December 2001 56 KIDNEY 2.03E3 7.26E4 3.92E2 1.93E5 m*
LIVER 2.03E3 7.26E4 6.50E5 1.41E5 4.95E5 3.25E5 1.32E6 3.33E8 2.07E1 7.29E3 1.51E6 1.27E8 1.90E6 2.67E10 2.04E10 2.03E3 1.36E-1 2.07E2 1.15E4 6.57E0 T. BODY 2.03E3 7.26E4 1.78E3 1.24E5 3.28E4 1.90E5 7.27E5 2.91E6 1.51E8 4.89E7 1.63E10 1.40El 3.92E3 2.87E5 7.29E7 5.79E5 2.10El0 1.34E10 1.06E5 3.61E-2 2.34E1 1.48E3 3.93E-1 2.86E9 2.30E9 1.16E3 LUNG 2.03E3 7.26E4 2.36E3 7.85E4 1.38E5 4.17E10 2.79E8 2.23E8 3.25E1 7.21E3 3.41E6 2.18E8 3.31 E6 8.63E9 6.93E9 6.91E2 9.60E1 6.82E3 3.84E0 GI-LLI 2.03E3 7.26E4 4.48E5 1.99E6 8.07E4 1.65E6 6.58E6 2.48E7 2.1 0E8 2.73E8 1.91E9 6.56E4 4.42E7 3.49E6 3.36E7 1.71E6 4.67E8 3.95E8 3.33E6 1.00E4 7.90E5 9.30E6 3.15E4
NUCLIDE H3° C 14" Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 TABLE 3-17 DOSE AND DOSE RATE R, VALUES - COW MEAT - CHILD m2-mrem/yr gCi/sec T. BODY THYROID KII 2.34E2 2.34E2 2.3 1.06E5 1.06E5 1.0O 4.55E3 2.52E3 6.9(
"mrem/yr per *Ci/m 3.
Unit 1 ODCM "Revision 21 December 2001 57
)NEY 4E2 6E5 0E2 4E6 1.4, LUNG 2.34E2 1.06E5 4.61E3 8.66E7 9.58E7 BONE 5.29E5 2.89E8 2.04E8 2.38E8 2.65E8 7.01E9 1.51E6 4.10E6 4.15E6 9.38E-2 6.09E8 8.99E8 2.20E7 2.80E-2 1.17E4 1.48E6 5.93E3 LIVER 2.34E2 1.06E5 5.15E6 1.53E8 3.30E8 9.41E6 4.64E7 6.35E8 3.32E5 1.59E6 5.42E4 4.18E6 1.16E-1 1.00E9 8.60E8 1.93E4 9.78E-3 5.82E3 4.65E5 4.80E3 1.37E6 4.74E7 1.65E8 2.88E7 1.37E8 3.95E8 7.57E6 1.78E9 2.95E5 1.14E6 1.34E4 2.37E6 4.39E-2 2.11E8 1.27E8 1.28E6 3.30E-3 8.64E2 7.91E4 3.72E2 4.00E8 4.75E5 1.50E6 1.16E5 6.86E6 1.93E-1 3.10E8 2.80E8 6.27E3 2.55E3 2.57E5 2.64E3 GI-LLI 2.34E2 1.06E5 2.41E5 4.32E6 2.84E7 3.44E8 5.49E7 2.57E8
- 1. 12E8 1.03E7 9.44E7 3.46E8 2.95E9 4.48E4 3.72E5 4.67E-2 5.39E6 5.39E6 1.11E7 2.73E2 7.26E6 1.21E8 7.61E6 1.11E8 1.01E8 1.15E4 1.38E9 2.15El
TABLE 3-18 DOSE AND DOSE RATE Ri VALUES. COW MEAT - TEEN m2 NUCLIDE H3*
C 14*
Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1 133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147
-mrem/yr g Cilsec THYROID 1.94E2 5.62E4 1.62E3
- mrem/yr per 4aCi/m 3.
Unit 1 ODCM Revision 21 December 2001 58 KIDNEY 1.94E2 5.62E4 6.39E2 1.34E6 LUNG 1.94E2 5.62E4 4.16E3 6.77E7 8.47E7 BONE 2.81E5 1.50E8
- 1. 15E8 1.59E8 1.40E8 5.42E9 8.50E5 2.37E6 2.24E6 5.05E-2 3.46E8 4.88E8 1.19E7 1.53E-2 6.19E3 7.87E5 3.16E3 LIVER 1.94E2 5.62E4 4.50E6 1.07E8 2.69E8 8.05E6 3.90E7 5.52E8 2.68E5 1.32E6 3.90E4 3.13E6 8.57E-2 8.13E8 6.49E8 1.46E4 7.51 E-3 4.14E3 3.26E5 3.44E3 T. BODY 1.94E2 5.62E4 2.93E3 8.93E5 2.49E7 1.04E8 1.86E7 8.80E7 2.57E8 4.01E6 1.34E9 1.84E5 7.24E5 7.43E3 1.68E6 2.61E-2 3.77E8 2.26E8 7.68E5 2.OOE-3 4.75E2 4.23E4 2.06E2 GI-LLI 1.94E2 5.62E4 4.90E5 9.24E6 4.62E7 6.36E8 1.11E8 5.09E8 2.34E8 1.67E7 1.52E8 6.19E8 5.63E9 6.98E4 6.20E5 6.48E-2 1,01E7 9.24E6 1.84E7 4.31 E2 1.18E7 1.98E8 1.24E7 9.15E8 1.20El 3.53E8 3.94E5 1.28E6 8.92E4 5.40E6 1.50E-1 2.58E8 2.2 1E8 4.95E3 1.95E3 1.94E5 2.02E3 9.87E7 8.58E7 9.81E3
TABLE 3-19 DOSE AND DOSE RATE R9 VALUES - COW MEAT - ADULT NUCLIDE H 3*
C 14" Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147
,-mrem/yr LLCi/sec THYROID 3.25E2 6.66E4 2.18E3 KIDNEY 3.25E2 6.66E4 8.03E2 1.76E6 "mrem/yr per tCi/m 3.
Unit 1 ODCM Revision 21 December 2001 59 LUNG 3.25E2 6.66E4 4.84E3 7.14E7 9.46E7 BONE 3.33E5 1.85E8 1.44E8 2.26E8 1.66E8 8.38E9 1.06E6 3.04E6 2.69E6 6.04E-2 4.35E8 5.88E8 1.44E7 1.86E-2 7.38E3 9.33E5 3.59E3 LIVER 3.25E2 6.66E4 5.90E6 1.28E8 3.39E8 1.04E7 5.03E7 7.19E8 3.40E5 1.69E6 4.71E4 3.85E6 1.05E-1 1.03E9 8.04E8 1.81E4 9.37E-3 4.99E3 3.90E5 4.15E3 T. BODY 3.25E2 6.66E4 3.65E3 1.13E6 2.98E7 1.30E8 2.34E7 1.11E8 3.25E8 4.76E6 2.06E9 2.30E5 9.08E5 8.97E3 2.21E6 3.20E-2 8.45E8 5.26E8 9.44E5 2.48E-3 5.66E2 5.01E4 2.48E2 1.11E8 9.07E7 1.04E4 GI-LLI 3.25E2 6.66E4 9.17E5 1.81E7 7.34E7
- 1. 13E9 2.12E8 9.45E8 4.53E8 2.66E7 2.42E8 1.08E9 1.03E10 1.09E5 1.02E6 9.44E-2 1.81E7 1.56E7 2.97E7 6.88E2 1.91E7 3.16E8 1.99E7 4.81E8 1.26E9 1.54E1 5.34E5 1.67E6 1.07E5 6.61E6 1.83E-1 3.35E8 2.73E8 6.15E3 2.32E3 2.31E5 2.42E3 m2
TABLE 3-20 DOSE AND DOSE RATE R1 VALUES - VEGETATION - CHILD NUCLIDE H3*
C 14" Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 KIDNEY 4.01E3 7.01E5 1.77E4 1.86E8 BONE 3.50E6 7.63E8 3.97E8 8.12E8 3.59E10 1.24E12 3.86E6 1.02E6 7.16E7 1.69E6 1.60E10 2.39E10 2.77E8 3.25E3 6.56E5 1.27E8 7.23E4 LIVER 4.01E3 7.01E5 6.65E8 4.05E8 6.42E8 6.45E7 3.78E8 2.16E9 8.50E5 3.99E5 7.70E6 7.20E7 2.09E6 2.63E10 2.29E10 2.43E5 1.13E3 3.27E5 3.98E7 5.86E4 "mrem/yr per RCi/m 3.
Unit I ODCM Revision 21 December 2001 60 T. BOI 4.01E3 7.0lE5
- 1. 17E5 1.77E8 1.25E8 3.20E8 1.97E8
- 1. 12E9 1.35E9 1.03E9 3.15E1 7.56E5 2.85E5 1.91E6 4.09E7 7.92E5 5.55E9 3.38E9 1.62E7 3.83E2 4.85E4 6.78E6 4.54E3 m2-mrem/yr tgCilsec
)Y THYROID 4.01E3 7.01E5 6.49E4 1
2.38E10 3.89E8 LUNG 4.01E3 7.01E5 1.18E5 2.29E8 1.86E8 1.36E9 I
GI-LLI 4.01E3 7.01E5 6.20E6 5.58E8 7.50E7 6.69E8 3.76E8
- 2. 10E9 3.80E8 1.39E9 1.67E10 8.86E8 7.37E8 6.37E6 6.41E6 8.44E5 1.42E8 1.43E8 1.40E8 3.16E7 4.08E8 1.04E10 9.28E7 1.22E6 3.75E5 1.65E7 1.18E8 3.49E6 8.15E9 7.46E9 7.90E4 1.43E5 2.21E7 3.22E4 2.93E9 2.68E9 1.45E5
TABLE 3-21 DOSE AND DOSE RATE R1 VALUES - VEGETATION - TEEN NUCLIDE H 5" C 14" Cr 51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 Lmrem/yr 0Ci/sec THYROID 2.59E3 2.91E5 3.42E4 KIDNEY 2.59E3 2.91E5 1.35E4 1.36E8 LUNG 2.59E3 2.91E5 8.79E4 1.40E8 1.32E8
.mremlyr per jCi/m 3 Unit 1 ODCM Revision 21 December 2001 61 BONE 1.45E6 3.1 0E8 1.79E8 4.24E8 1.51E10 7.51Ell 1.72E6 4.80E5 3.85E7 9.29E5
- 7. 10E9 1.01E10 1.38E8 1.81E3 2.83E5 5.27E7 3.66E4 LIVER 2.59E3 2.91E5 4.54E8 2.20E8 4.18E8 4.37E7 2.49E8 1.47E9 5.44E5 2.66E5 5.64E6 5.39E7 1.58E6 1.67E10 1.35E10 1.69E5 8.88E2 1.89E5 2.18E7 3.98E4 T. BODY 2.59E3 2.9lE5 6.16E4 9.01E7 5.13E7 1.61E8 1.01ES 5.60E8 6.86E8 4.33E8 1.85E11 3.74E5 1.46E5 1.08E6 2.89E7 4.80E5 7.75E9 4.69E9 8.91E6 2.36E2 2.17E4 2.83E6 2.3863 1.57E10 2.20E8 9.41E8 7.99E5 2.58E5 1.29E7 9.28E7 2.76E6 5.3 IE9 4.59E9 5.74E4 8.89E4 1.30E7 2.34E4 2.03E9 1.78E9 1.14E5 GI-LLI 2.59E3 2.91E5 1.03E7 9.32E8 9.53E7 9.89E8 6.02E8 3.24E9 6.23E8 1.80E9 2.11E10 1.26E9
- 1. 14E9 1.01E7 1.07E7 1.19E6 2.08E8 1.92E8 2.13E8
- 5. 10E7 5.40E8 1.33E10 1.44E8 m*
TABLE 3-22 DOSE AND DOSE RATE R VALUES - V Ii NUCLIDE H3" C 14" Cr51 Mn 54 Fe 55 Fe 59 Co 58 Co 60 Zn 65 Sr 89 Sr 90 Zr 95 Nb 95 Mo 99 1131 1133 Cs 134 Cs 137 Ba 140 La 140 Ce 141 Ce 144 Nd 147 EGETATION - ADULT 2-mrem/yr gCi/sec THYROID KID]
2.26E3 2.26]
1.79E5 1.79]
2.77E4 1.02]
9.311 NEY E3 E5 E4 E7 BONE 8.97E5 2.00E8 1.26E8 3.17E8 9.96E9 6.05E 11 1.18E6 3.55E5 4.04E7 1.00E6 4.67E9 6.36E9 1.29E8 1.98E3 1.97E5 3.29E7 3.36E4
.mrem/yr per f.Ci/m 3 Unit 1 ODCM Revision 21 December 2001 62 LUNG 2.26E3 1.79E5 6.15E4 7.69E7 8.27E7 LIVER 2.26E3 1.79E5 3.13E8 1.38E8 2.96E8 3.08E7 1.67E8 1.01E9 3.77E5 1.98E5 6.14E6 5.78E7 1.74E6 1.11E10 8.70E9 1.61E5 9.97E2 1.33E5 1.38E7 3.88E4 T. BODY 2.26E3 1.79E5 4.64E4 5.97E7 3.22E7 1.13E8 6.90E7 3.69E8 4.56E8 2.86E8 1.48E11 2.55E5 1.06E5 1.17E6 3.31E7 5.30E5 9.08E9 5.70E9 8.42E6 2.63E2 1.51E4 1.77E6 2.32E3 GI-LLI 2.26E3 1.79E5
- 1. 17E7 9.58E8 7.9 1E7 1.02E9 6.24E8 3.14E9 6.36E8 1.60E9 1.75E10 1.20E9 1.20E9 1.42E7 1.53E7 1.56E6 1.94E8 1.68E8 2.65E8 7.32E7 5.09E8 1.11El0 1.86E8 5.92E5 1.95E5 1.39E7 9.91E7 3.03E6 3.59E9 2.95E9 5.49E4 6.19E4 8.16E6 2.27E4 6.75E8 1.90E10 2.56E8 1.19E9 9.81E8 9.25E4
TABLE 3-23 PARAMETERS FOR THE EVALUATION OF DOSES TO REAL MEMBERS OF THE PUBLIC FROM GASEOUS AND LIQUID EFFLUENTS Parameters U (kg/yr) - adult Daipj (mrem/pCi)
Value 21 Each Radionuclide Reference Reg. Guide 1.109 Table E-5 Reg. Guide 1.109 Table E-11 Reg. Guide 1.09 Assumed to be same as Adult Daipj (mrem/hr per pCi/n 2)
DFAija Each Radionuclide Each Radionuclide 63 Reg. Guide 1.109 Table E-6 Shoreline Inhalation Pathway Fish Fish Shoreline U (hr/yr)
- adult
- teen Reg. Guide 1.109 Table E-7 Unit I ODCM Revision 21 December 2001 67 67
Type of Sample Radioiodine and Particulates (air)
Radioiodine and Particulates (air)
Radioiodine and Particulates (air)
Radioiodine and Particulates (air)
Radioiodine and Particulates (air)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
TABLE 5.1 NINE MILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRi SAMPLING LOCATIONS
- Map Collection Site Location (Env. Program No.)
1 Nine Mile Point Road North (R-1) 2 Co. Rt. 29 & Lake Road (R-2) 3 "4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 Co. Rt. 29 (R-3)
Village of Lycoming, NY (R-4)
Montario Point Road (R-5)
North Shoreline Area (75)
North Shoreline Area (76)
North Shoreline Area (77)
North Shoreline Area (23)
JAF East Boundary (78)
Rt. 29 (79)
Rt. 29 (80)
Miner Road (81)
Miner Road (82)
Lakeview Road (83)
Lakeview Road (84)
Site Meteorological Tower (7)
Energy Information Center (18)
Location 1.8 mi@ 880 E 1.1 mi @ 1040 ESE 1.5 m! @ 1320 SE 1.8 mi @ 1430 SE 16.4 mi @ 42' NE 0.1 mi@5-N 0.1 mi @ 25-NNE 0.2 mi @ 450 NE 0.8 mi @ 70' ENE 1.0 mi @ 90- E 1.1 mi@ 1150 ESE 1.4 mi @ 133-SE 1.6 mi @ 159' SSE 1.6mi @ 1810 S 1.2 mi @ 200- SSW 1.1 mi @ 225-SW 0.7 mi @ 2500 WSW 0.4 mi @ 2650 W
= See Figures 5.1-1 and 5.1-2 Unit 1 ODCM Revision 21 December 2001
- Map 64
Type of Sample Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Direct Radiation (TLD)
Surface Water Surface Water TABLE 5.1 (Cont'd)
NINE MILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS
- Map Collection Site Location (Env. Program No.)
19 North Shoreline (85) 0.2 mi 20 North Shoreline (86) 0.1 mi 21 North Shoreline (87) 0.1 mIi 22 Hickory Grove (88) 4.5 mi 23 Leavitt Road (89) 4.1 mi 24 Rt. 104 (90) 4.2 mi 25 Rt. 51A (91) 4.8 mi 26 Maiden Lane Road (92) 4.4 mi (
27 Co. Rt. 53 (93) 4.4 mi 28 Co. Rt. 1 (94) 4.7 mi 29 Lake Shoreline (95) 4.1 mi (
30 Phoenix, NY Control (49) 19.8 mi 31 S. W. Oswego, Control (14) 12.6 mi 32 Scriba, NY (96) 3.6 m!
33 34 35 36 37 38 39 Alcan Aluminum, Rt. IA (58)
Lycoming, NY (97)
New Haven, NY (56)
W. Boundary, Bible Camp (15)
Lake Road (98)
OSS Inlet Canal (NA)
JAFNPP Inlet Canal (NA) 3.1 mi 1.8 mi (
5.3 mig 0.9 mi (
1.2 mi (
7.6 mi (
0.5 mi c Location WNW NNW S970 E 1110 ESE SE SSE S2055 SSW S223-SW S237-WSW
@ 163-S
@ 226° SW S199*
SSW S2206 SW S1430 SE S1230 ESE S237*
WSW S1010 E
S235*
SW S70° ENE (NA)
= Not applicable
- Map = See Figures 5.1-1 and 5.1-2 Unit I ODCM Revision 21 December 2001 65
Type of Sample Shoreline Sediment Fish Fish Fish Milk Milk Milk Milk Milk (CR)
Food Product Food Product Food Product Food Product Food Product TABLE 5.1 (Cont'd)
NINE MILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS
- Map Collection Site Location (Env. Program No.)
40 Sunset Bay Shoreline (NA) 1.5 m 41 NMP Site Discharge Area (NA) 0.3 mJ (and/l 42 NMP Site Discharge Area (NA) 0.6 i 43 Oswego Harbor Area (NA) 6.2 m, 44 Milk Location #50 8.2 mi 64 Milk Location #55 9.0 M, 65 Milk Location #60 9.5 ml 66 Milk Location #4 7.8 mJ 77 Milk Location 13.9 (Summerville) 48 Produce Location #6*
- 1.9 ml (Bergenstock) (NA) 49 Produce Location #1 *
- 1.7 ml (Culeton) (NA) 50 Produce Location #2*
- 1.9 mi (Vitullo) (NA) 51 Produce Location #5*
- 1.5 ml (C.S. Parkhurst) (NA) 52 Produce Location #3*
- 1.6 ml (C. Narewski) (NA)
@ 141" SE
@ 960 E
[@ 101*E
@ 114*ESE i@ 84"E
=
See Figures 5.1-1 and 5.1-2 Food Product Samples need not necessarily be collected from all listed locations. Collected samples will be of the highest calculated site average D/Q.
Not applicable
=
Control Result (location)
Unit 1 ODCM Revision 21 66 December 2001
- Map (NA)
CR Location S@80 E
@ 315 NW
)r) i @ 550 NE
@ 235* SW i
930 E
@ 950 E
@90 E
@ 113" ESE ni @ 191" SSW I
TABLE 5.1 (Cont'd)
NINE MILE POINT NUCLEAR STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SAMPLING LOCATIONS Type of Sample Food Product Food Product (CR)
Food Product (CR)
Food Product Food Product Food Product Food Product Food Product (CR)
- Map Location 53 54 55 56 57 58 59 60 61 62 63 67 Food Product Food Product Food Product Food Product Collection Site (Env. Program No.)
Produce Location #4* *
(P. Parkhurst) (NA)
Produce Location #7 *
(Mc Millen) (NA)
Produce Location #8 *
(Denman) (NA)
Produce Location #9 *
(O'Connor) (NA)
Produce Location # 10* *
(C. Lawton) (NA)
Produce Location #11 * *
(C. R. Parkhurst) (NA)
Produce Location #12* *
(Barton) (NA)
Produce Location #13* *
(Flack) (NA)
Produce Location #14* *
(Koeneke) (NA)
Produce Location #15* *
(Whaley) (NA)
Produce Location #16* *
(Murray) (NA)
Produce Location #17* *
(Battles)
Location 2.1 mi @ 110- ESE 15.0 mi @ 2230 SW 12.6 mi @ 225' SW 1.6 mi @ 1710 S 2.2 mi @ 1230 ESE 2.0 mi @ 112-ESE 1.9 mi @ 1150 ESE 15.6 mi @ 225-SW 1.9 mi @ 95-E 1.7 mi @ 136-SE 1.2 mi @ 2070 SSW 1.76 mi @ 97* E
=
See Figures 5.1-1 and 5.1-2 Food Product Samples need not necessarily be collected from all listed locations. Collected samples will be of the highest calculated site average D/Q.
Not applicable
.Control Result (location)
Unit 1 ODCM Revision 21 67 December 2001
- Map (NA)
CR
68
FIGURE 5.1-2 NINE MILE POINT LEGEND Interstat.........................
U.S. & Stale Highways County Roads.........................
Town o
aads County Lin"..
Town L.
city a Village Unes............
Ralihoads........................
ENVIRONMENTAL SAMPLE...........
LOCATION OFF-SITE MAP (10/2001) latitude 43"28'N.
Longitude 76'0' W.
at Omano County B1du..
Oswqo. N.Y.
Land Am 96W Square mis LAKE ONTARIO SCALE OF MILES
=11:11ME:
I 4
8.uth. of Nocth Volney Wei 31 1
4 5
%AL Mae G
0 A
Min 46 saytes CWTWWS 4
55 104 46 ount nt We We A
L A
0 pd Q.+
.A.
K 6
46 1
Mul Upson Coln Palermo 0
60 NdM a
48 y
0 y
Lowomls 57 03 Comers 4
AC=',y OL Slay it Comers usixfors I
Comers to. sut 24 DeKtor-
"=.by
-G
-L -
-J*
ID Vill*
rAnter lillbe" Muk A
N d N a
A L.
ROOSO'""
0 4
Carrier 4
I--
in" I
ýSwth HannkM 9
s r:
0
- lid, 14w: 4 M"
z
- 94.
CAY 07A To IV. Y. 370 COUNry
:-p 11101MIS HL aw Nor,&
'UM IL A PoIn INUF IL
.9.
CC03) go It UPS 00 A18NMfU1 41 SIPOWNSM.
LLPk.
Pi hoenix ONC'IND A
COWNMTY To 30 If FIGURE 5-1-2a Thres Rhws 20 M 79
70 I,-
APPENDIX A LIQUID DOSE FACTOR DERIVATION Unit 1 ODCM Revision 21 December 2001 71
Appendix A Liquid Effluent Dose Factor Derivation, A.i Aiat (mrem/hr per RCi/ml) which embodies the dose conversion factors, pathway transfer factors (e.g.,
bioaccumulation factors), pathway usage factors, and dilution factors for the points of pathway origin takes into account the dose from ingestion of fish and drinking water and the sediment. The total body and organ dose conversion factors for each radionuclide will be used from Table E-11 of Regulatory Guide 1.109. To expedite time, the dose is calculated for a maximum individual instead of each age group. The maximum individual dose factor is a composite of the highest dose factor Ai,, of each nuclide i age group a, and organ t, hence Aat. It should be noted that the fish ingestion pathway is the most significant pathway for dose from liquid effluents. The water consumption pathway is included for consistency with NUREG 0133.
The equation for calculating dose contributions given in section 1.3 requires the use of the composite dose factor Ai, for each nuclide, i. The dose factor equation for a fresh water site is:
-Aitpw
-Aitpf Aiat =KO (U._(e
) + Uf(BF)i(e I (DFL) iat +
Dw
-Xitps
-litb
+
69.3 UsW e (1-e
) (DFS)i)
(D.) (Ai)
Where:
Ai.,
Is the dose factor for nuclide i, age group a, total body or organ t, for all appropriate pathways, (mrem/hr per tCi/ml).
Ko
=
Is the unit conversion factor, 1. 14E5 = 1E6pCi/,tCi x 1E3 nil/kg -:- 8760 hr/yr.
U-Water consumption (1/yr); from Table E-5 of Reg. Guide 1.109.
Ur Fish consumption (Kg/yr); from Table E-5 of Reg. Guide 1.109.
U1 Sediment Shoreline Usage (hr/yr); from Table E-5 of Reg.
Guide 1.109.
(BF),
Bioaccumulation factor for nuclide, i, in fish, (pCi/kg per pCi/1), from Table A-I of Reg. Guide 1.109.
(DFL)iat
=
Dose conversion factor for age, nuclide, i, group a, total body or organ t, (mrem/pCi); from Table E-11 of Reg. Guide 1.109.
(DFS),
=
Dose conversion factor for nuclide i and total body, from standing on contaminated ground (mem/hr per pCi/m2); from Table E-6 of Reg. Guide 1.109.
D, Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake for the adult water consumption. This is the Metropolitan Water Board, Onondaga County intake structure located west of the City of Oswego; (unitless).
Unit 1 ODCM Revision 21 72 December 2001
Appendix A (Cont'd)
D, Dilution factor from the near field area within one quarter mile of the release point to the shoreline deposit (taken at the same point where we take environmental samples 1.5 miles; unitless).
69.3
=
conversion factor.693 x 100, 100 = K* (L/kg-hr) *40*24 hr/day/.693 in L/m2-d, and K, = transfer coefficient from water to sediment in L/kg per hour.
- Stpf, t=,Average transit time required for each nuclide to reach the point of exposure for internal dose, it is the total time elapsed from release of the nuclides to either ingestion for water (w) and fish (f) or shoreline deposit (s), (hr).
tb
=
Length of time the sediment is exposed to the contaminated water, nominally 15 yrs (approximate midpoint of facility operating life),
(hrs).
0, decay constant for nuclide i (hr').
W
=
Shore width factor (unitless) from Table A-2 of Reg. Guide 1.109.
Example Calculation For 1-131 Thyroid Dose Factor for an Adult from a Radwaste liquid effluents release:
= 2.80E-9 mrem/hr per pCi/m2
= 1.95E-3 mrem/pCi
= 15 pCi/Kg per pCi/L
= 21 Kg/yr
= 40 unitless
= 12 unitless
= 12 hr/yr
= 0.3
= 5.5 hrs (s = Shoreline S tp w tpt tb Uw Ko Xi ediment)
= 30 hrs. (w = water)
= 24 hrs. (f = fish)
= 1.314E5 hrs. (5.48E3 days)
= 730 L/yr
= 1.14E5 (pCi/QCi)(ml/kg)
(hr/yr)
= 3.61E-3hr1 These values will yield an Ai, Factor of 6.79E4 mrem-ml per PtCi-hr as listed in Table 24. It should be noted that only a limited number of nuclides are listed on Tables 2-1 to 2-8. These are the most common nuclides encountered in effluents. If a nuclide is detected for which a factor is not listed, then it will be calculated and included in a revision to the ODCM.
In addition, not all dose factors are used for the dose calculations. A maximum individual is used, which is a composite of the maximum dose factor of each age group for each organ as reflected in the applicable chemistry procedures.
Unit I ODCM Revision 21 73 December 2001 (DFS)i (DFL)iat BFi Uf Dw Ds U,
W
APPENDIX B PLUME SHINE DOSE FACTOR DERIVATION Unit 1 ODCM Revision 21 December 2001 74
APPENDIX B For elevated releases the plume shine dose factors for gamma air (B.) and whole body (V-), are calculated using the finite plume model with an elevation above ground equal to the stack height. To calculate the plume shine factor for gamma whole body doses, the gamma air dose factor is adjusted for the attenuation of tissue, and the ratio of mass absorption coefficients between tissue and air. The equations are as follows:
Gamma Air Bi
=
.KaE I, Where:
K' conversion factor (see E
RO-,
below for actual value).
p, mass absorption coefficient (cm2/g; air for Bi, tissue for V)
E Energy of gamma ray per disintegration (Mev)
V.,
averae wind speed for each stability class (s),
R
=
downwind distance (site boundary, m)
=
sector width (radians) s
=
subscript for stability class I,
=
I function = I, + kM2 for each stability class. (unitless, see Regulatory Guide 1.109) k2 Fraction of the attenuated energy that is actually absorbed in air (see Regulatory Guide 1.109, see below for equation)
Whole Body
ýU.Ltd Vi
=
1.11SFBie Where:
t
=
tissue depth (g/cm2)
SF
=
shielding factor from structures (unitless) 1.11 Ratio of mass absorption coefficients between tissue and air.
Where all other parameters are defined above.
=K conversion factor
[3.7 El0 dis]
1.6 E-6 erg]
Ci-sec Mev
=
.46 L1293
[ L100 er
]
9m*
g-rad 2k 2k =
S_
[
Where:
p mass attenuation coefficient (cm2/g; air for Bi, tissue for V.)
u =
defined above Unit 1 ODCM Revision 21 75 December 2001
APPENDIX B (Cont'd)
There are seven stability classes, A thru F. The percentage of the year that each stability class occurs is taken from the U-2 FSAR. From this data, a plume shine dose factor is calculated for each stability class and each nuclide, multiplied by its respective fraction and then summed.
The wind speeds corresponding to each stability class are, also, taken from the U-2 FSAR. To confirm the accuracy of these values, an average of the 12 month wind speeds for 1985, 1986, 1987 and 1988 was compared to the average of the FSAR values. The average wind speed of the actual data is equal to 6.78 m/s, which compared favorably to the FSAR average wind speed equal to 6.77 m/s.
The average gamma energies were calculated using a weighted average of all gamma energies emitted from the nuclide. These energies were taken from the handbook "Radioactive Decay Data Tables",
David C. Kocher.
The mass absorption (y) and attenuation () coefficients were calculated by multiplying the mass absorption (*/) and mass attenuation (ýt/p) coefficients given in the Radiation Health Handbook by the air density equal to 1.293 E-3 gfcc or the tissue density of 1 g/cc where applicable. The tissue depth is 5g/cm2 for the whole body.
The downwind distance is the site boundary.
Unit 1 ODCM Revision 21 December 2001 76
APPENDIX B (Cont'd)
SAMPLE CALCULATION F STABILITY CLASS ONLY -
Gamma Air 2.22MeV k
=
0a
=
.871 K =
.46 2.943 E-3mr-'
a VF =
5.55 m/sec 5.5064E-3m-'
R
=
644m
.39 19m.......
vertical plume spread taken from "Introduction to Nuclear Engineering", John R. LaMarsh
-I Function Uoz
=
I' 12 I
=
.06
.33
.45 i, + k1 2 =.33
+ (..871)
(.45)
=.72 dis.
0.46 [Ci-sec) (Mev/ergs]
7[12) t (g/m3)
(ergs)J (g-rad)
(2.943E-3m') (2.22Mev) (.72)
(5.55 m/s)
(.39)
(644m) 1.55(-6) rad/s (3600 s/hr) (24 h/d) (365 d/y) (lE3mrad/rad)
Ci/s (IE6MCi)
Ci 2.76(-2) mrad/yr uCi/sec Vi 1.11 (.7) 2.76(-2) mrad/yr [e I
VCi/sec]
1.89(-2) mrad/yr jiCi/sec -(.0253 cm2/g) (5g/cm2)
I NOTE:
The above calculation is for the F stability class only. For Table 3-2 and procedure values, a weighted fraction of each stability class was used to determine the Bi and Vi values.
Unit 1 ODCM Revision 21 77 December 2001 Ex. Kr-89
-DATA E
Pa e
az
APPENDIX C DOSE PARAMETERS FOR IODINE 131 and 133, PARTICULATES AND TRITIUM Unit 1 ODCM Revision 21 December 2001 78
APPENDIX C DOSE PARAMETERS FOR IODINE - 131 AND - 133, PARTICULATES AND TRITIUM This appendix contains the methodology which was used to calculate the organ dose factors for 1-131, 1-133, particulates, and tritium. The dose factor, Ri, was calculated using the methodology outlined in NUREG-0133. The radloiodine and particulate Technical Specification (Section 3.6.15) is applicable to the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure occurs, i.e., the critical receptor. Washout was calculated and determined to be negligible. R, values have been calculated for the adult, teen, child and infant age groups for all pathways. However, for dose compliance calculations, a maximum individual is assumed that is a composite of highest dose factor of each age group for each organ and pathway. The methodology used to calculate these values follows:
C.1 Inhalation Pathway Ri(I)
(BR).
(DFA)ija K, (BR)a(DFA)ija dose factor for each identified radionuclide i of the organ of interest (units = mrem/yr per,Ci/m3);
=
a constant of unit conversion, 1E6 pCi/PCi
=
Breathing rate of the receptor of age group a, (units = m3/yr);
The inhalation dose factor for nuclide i, organ j and age group a, and organ t (units = mrem/pCi).
The breathing rates (BR)a for the various age groups, as given in Table E-5 of Regulatory Guide 1.109 Revision 1, are tabulated below.
Age Group (a)
Breathing Rate (m3/yr)
Infant Child Teen Adult 1400 3700 8000 8000 Inhalation dose factors (DFA)ija for the various age groups are given in Tables E-7 through E-10 of Regulatory Guide 1.109 Revision 1.
Unit I ODCM Revision 21 79 December 2001 where:
Ri(I)
K,
APPENDIX C (Cont'd)
C.2 Ground Plane Pathway Ri (G) =
K'K' (S F) (D FG)i (1-e Where:
R,(G)
Dose factor for the ground plane pathway for each identified radionuclide i for the organ of interest (units = m2-mrem/yr per P Ci/sec)
K'
=
A constant of unit conversion, 1E6 pCi/41 Ci K,'
=
A constant of unit conversion, 8760 hr/year The radiological decay constant for radionuclide i, (units = sec"t) t (DFG)i SF
=
The exposure time, sec, 4.73E8 sec (15 years)
The ground plane dose conversion factor for radionuclide i; (units =
mrem/hr per pCi/m2)
=
The shielding factor (dimensionless)
A shielding factor of 0.7 is discussed in Table E-15 of Regulatory Guide 1.109 Revision 1. A tabulation of DFGI values is presented in Table E-6 of Regulatory Guide 1.109 Revision 1.
Unit 1 ODCM Revision 21 80 December 2001
APPENDIX C (Cont'd)
C.3 Grass-(Cow or Goat)-Milk Pathway
-Xith
-Litf Ri(C)
= K'QE(Uap) F,,(r) (DFL)iat fPfs
+
(1-fpf,) (e
)e (A
+
])P YS Where:
R1(C)
Dose factor for the cow milk or goat milk pathway, for each identified radionuclide i for the organ of interest, (units = m2-mrem/yr per P.Ci/sec)
K,
=
A constant of unit conversion, 1E6 pCi/1 jCi Qf=
The cow's or goat's feed consumption rate, (units = Kg/day-wet weight)
Uap
=
The receptor's milk consumption rate for age group a, (units = liters/yr)
YP=
The agricultural productivity by unit area of pasture feed grass, (units = kg/m2)
Y=
The agricultural productivity by unit area of stored feed, (units = kg/m2)
Fm
=
The stable element transfer coefficients, (units = pCi/liter per pCi/day) r
=
Fraction of deposited activity retained on cow's feed grass (DFL)i, The ingestion dose factor for nuclide i, age group a, and total body or organ t (units = mrem/pCi)
.i
=
The radiological decay constant for radionuclide i, (units=sec -1)
X=
The decay constant for removal of activity on leaf and plant surfaces by weathering equal to 5.73E-7 sec -1 (corresponding to a 14 day half-life) tf
=
The transport time from pasture to cow or goat, to milk, to receptor, (units = sec) th=
The transport time from pasture, to harvest, to cow or goat, to milk, to receptor (units =
sec)
Unit 1 ODCM Revision 21 81 December 2001
APPENDIX C (Cont'd) fP Fraction of the year that the cow or goat is on pasture (dimensionless)
Fraction of the cow feed that is pasture grass while the cow is on pasture (dimensionless)
Milk cattle and goats are considered to be fed from two potential sources, pasture grass and stored feeds. Following the development in Regulatory Guide 1.109 Revision 1, the value of f, is considered unity in lieu of site specific information. The value of fp is 0.5 based on 6 month grazing period. This value for fp was obtained from the environmental group.
Table C-I contains the appropriate values and their source in Regulatory Guide 1.109 Revision 1.
The concentration of tritium in milk is based on the airborne concentration rather than the deposition.
Therefore, the RT(C) is based on X/Q:
RT(C) =
K'K
FmQfUap(DFL)it 0.75(0.5/H)
Where:
Dose factor for the cow or goat milk pathway for tritium for the organ of interest, (units = mrem/yr per ýtCi/m 3)
A constant of unit conversion, 1E3 g/kg
=
Absolute humidity of the atmosphere, (units = g/m3)
The fraction of total feed that is water The ratio of the specific activity of the feed grass water to the atmospheric water Other values are given previously. A site specific value of H equal to 6.14 g/m3 is used. This value was obtained from the environmental group using actual site data.
Unit 1 ODCM Revision 21 82 December 2001 RT(C)
K' H
0.75 0.5
APPENDIX C (Cont'd)
C.4 Grass-Cow-Meat Pathway
-- ith
--Xitf Ri (C)
=
K'Qf(Uap) Ff(r) (DFL)iat fPfs
+
(1-fpf.) (e
)e
( Ai +
UI
[ Y P Y S I
Ri(M)
Dose factor for the meat ingestion pathway for radionuclide i for any organ of interest, (units = m2-mrem/yr per,Ci/sec)
Ff=
The stable element transfer coefficients, (units = pCi/kg per pCi/day)
Uap The receptor's meat consumption rate for age group a, (units = kg/year) th
=
The transport time from harvest, to cow, to receptor, (units = sec) tf=
The transport time from pasture, to cow, to receptor, (units = sec)
All other terms remain the same as defined for the milk pathway. Table C-2 contains the values which were used in calculating R1(M).
The concentration of tritium in meat is based on airborne concentration rather than deposition. Therefore, the RT(M) is based on X/Q.
RT(M)
=
K' K 'FfQfU.p(DFL)iat [0.75(0.5/H)]
Where:
RT(M) =
Dose factor for the meat ingestion pathway for tritium for any organ of interest, (units
= mrem/yr per LCi/m 3)
All other terms are defined above.
C.5 Vegetation Pathway The integrated concentration in vegetation consumed by man follows the expression developed for milk. Man is considered to consume two types of Vegetation (fresh and stored) that differ only in the time period between harvest and consumption, therefore:
-AitL.
--1ith Ri(V)
=
K' r
(DFL)iat ULaFLe
+ USaFge Y,(
i +
Uw)
]
Unit 1 ODCM Revision 21 83 December 2001
APPENDIX C (Cont'd)
Where:
Rj(V)
=
Dose factor for vegetable pathway for radionuclide i for the organ of interest, (units = mn-mrem/yr per,Ci/sec)
K'
=
A constant of unit conversion, 1E6 pCi/PCi uLa
=
The consumption rate of fresh leafy vegetation by the receptor in age group a, (units = kg/yr)
USa
=
The consumption rate of stored vegetation by the receptor in age group a (units = kg/yr)
FL
=
The fraction of the annual intake of fresh leafy vegetation grown locally F9
=
The fraction of the annual intake of stored vegetation grown locally tL
=
The average time between harvest of leafy vegetation and its consumption, (units = sec) th
=
The average time between harvest of stored vegetation and its consumption, (units = sec)
Y=
The vegetation areal P density, (units = kg/m2)
All other factors have been defined previously.
Table C-3 presents the appropriate parameter values and their source in Regulatory Guide 1.109 Revision 1.
In lieu of site-specific data, values for FL and Fg of, 1.0 and 0.76, respectively, were used in the calculation. These values were obtained from Table E-15 of Regulatory Guide 1.109 Revision 1.
The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, the RT(V) is based on X/Q:
RT(V) = K' K [ULafL + Us. fj](DFL)ht 0.75(0.5/H)
Where:
RT(V) dose factor for the vegetable pathway for tritium for any organ of interest, (units = mrem/yr per,Ci/m3).
All other terms are defined in preceeding sections.
Unit 1 ODCM Revision 21 84 December 2001
TABLE C-1 Parameters for Grass-(Cow or Goat)-Milk Pathways Parameter Qf (kg/day) r (DFL)ija (mrem/pCi)
F. (pCi/liter per pCi/day)
Yý (kg/m2)
Y. (kg/rn2) tb (seconds) tf (seconds)
Uap (liters/yr)
Value 50 (cow) 6 (goat) 1.0 (radioiodines) 0.2 (particulates)
Each radionuclide Each stable element 2.0 0.7 7.78 x 106 (90 days) 1.73 x I0W (2 days) 330 infant 330 child 400 teen 310 adult Reference (Reg. Guide 1.109 Rev. I)
Table E-3 Table E-3 Table E-15 Table E-15 Tables E-11 to E-14 Table E-1 (cow)
Table E-2 (goat)
Table E-15 Table E-15 Table E-15 Table E-15 Table E-5 Table E-5 Table E-5 Table E-5 Unit 1 ODCM Revision 21 December 2001 85
TABLE C-2 Parameters for the Grass-Cow-Meat Pathway Parameter r
Ff (pCi/Kg per pCi/day)
Uap (Kg/yr)
(DFL)t* (mrem/pCi)
Yp (kg/rn2)
Y, (kg/rn2) th (seconds) tf (seconds)
Qf (kg/day)
Value 1.0 (radioiodines) 0.2 (particulates)
Each stable element 0 infant 41 child 65 teen 110 adult Each radionuclide 0.7 2.0 7.78E6 (90 days) 1.73E6 (20 days) 50 Reference (Reg, Guide 1.109 Rev. 1)
Table E-15 Table E-15 Table E-1 Table E-5 Table E-5 Table E-5 Table E-5 Tables E-11 to E-14 Table E-15 Table E-15 Table E-15 Table E-15 Table E-3 Unit 1 ODCM Revision 21 December 2001 86
TABLE C-3 Parameters for the Vegetable Pathway r (dimensionless)
(DFL)ija (mrem/pCi)
UL), (kg/yr) - infant
- child
- teen
- adult U%)a (kg/yr) 1.0 (radioiodines) 0.2 (particulates)
Each radionuclide 0
26 42 64
- infant
- child
- teen
- adult tL (seconds) th (seconds)
Y, (kg/mn) 0 520 630 520 8.6E4 (1 day) 5.18E6 (60 days) 2.0 Table E-1 Table E-1 Tables E-11 to E-14 Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-5 Table E-15 Table E-15 Table E-15 Unit 1 ODCM Revision 21 December 2001 87 Parameter Value Reference (Reg. Guide 1.109 Rev. 1)
APPENDIX D DIAGRAMS OF LIQUID AND GASEOUS TREATMENT SYSTEMS AND MONITORING SYSTEMS Unit 1 ODCM
'Revision 21 December 2001 88
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