ZS-2016-0042, Radioactive Effluent Release Report, Radioactive Effluent Control Program Report, Offsite Dose Calculation Manual and Process Control Program for 2015
| ML16123A125 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 04/27/2016 |
| From: | Gerard van Noordennen ZionSolutions |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| ZS-2016-0042 | |
| Download: ML16123A125 (437) | |
Text
{{#Wiki_filter:~ ~--~~-------ZIONSOLUTIONSL-u--~----------- An EnergySo/utions Company April27,2016 ZS-2016-0042 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Zion Nuclear Power Station, Units 1, 2 and ISFSI Facility Operating License Nos. DPR-39 and DPR-48
- NRC Docket Nos. 50-295, 50-304 and 72-1037
Subject:
Radioactive Effluent Release Report, Radioactive Effluent Control Program Report, Offsite Dose Calculation Manual and Process Control Program for 2015 In accordance with Facility Operation License Nos. DPR-39 and DPR-48, Quality Assurance Project Plan Appendix B Section 5.7.3, "Radioactive Effluent Release Report," for Zion Nuclear Power Station, Units 1 and 2, this is the submittal of a Radioactive Effluent Release Report for the year 2015. The report is required to be submitted prior to May 1, 2016 and is provided as Attachments 1 through 6 to this letter. Certificate of Compliance No. 1031 for the MAGNASTOR SYSTEM, Appendix A, Technical Specifications 5.1.1and5.1.3 require submittal of an Annual Radioactive Effluent Control Program report which is included in this document. Pursuant to 10 CFR 50.4 and Offsite Dose Calculation Manual (ODCM) 12.7.4, there were changes made to the Zion Station Liquid Effluent Treatment System during the period of January through December 2015. The changes to the Liquid Effluent Treatment System are summarized in Attachment 1, Section 7, for the calendar year of 2015. There were surveillances conducted for an inoperable plant monitoring system that exceeded the time listed in ODCM Section 12.2.2. ODCM Section 12.7.2 requires an explanation as to why the inoperability requirements of the monitoring system was not corrected in the time specified. Attachment 1, Section 8, provides this explanation and a summary of the results of the station review conducted to restore the plant monitoring system to operable status. There were changes made to the ODCM including a complete re-write of the ODCM for post fuel transfer operations in 2015. Per ODCM 12.7.3.lc, a summary of changes made during each revision and a complete copy of the current ODCM is submitted in Attachment 6. There were no changes to the Process Control Program during 2015. 101 Shiloh Boulevard, Zion
- IL 60099 (224) 789-4016
- Fax: (224) 789-4008
- www.zionsolutionscompany.com
ZionSolutions, LLC ZS-2016-0042 Page 2 of2 There are no new regulatory commitments in this submittal. If you have any questions about this submittal please contact Mr. Christopher Keene at (224)789-4073. Respectfully, {;~~~ Gerard van Noordennen Vice President of Regulatory Affairs Attachments:
- 1. Radioactive Effluent Release Report
- 2. ECN# 400577 Extending liquid effluent discharge line through the discharge tunnel
- 3. ECN# 400657 Installing additional liquid effluent discharge flowmeters
- 4. ECN# 400986 Increased capacity dilution water pump of 10,000 .gpm and associated flowmeters
- 5. ECN# 2015-04 Installation of new liquid effluent radiation monitor for ORT-PR04 and dilution flow permissive for lake discharge valve OSOV-WDOlO
- 6. Current Copy of Zion Station ODCM, Rev. 5 cc: John Hickman, U.S. NRC Senior Project Manager Regional Administrator, U.S. NRC, Region III Service List (Cover letter only, no attachments)
Zion Nuclear Power Station, Unit 1and2 License Transfer Service List cc: Ken Robuck Russ Workman Group President Disposal and General Counsel Decommissioning EnergySolutions EnergySolutions 299 South Main Street, Suite 1700 299 South Main Street, Suite 1700 Salt Lake City, UT 84111 . Salt Lake City, UT 84111 Alwyn C. Settles John Sauger
- Section Head, Nuclear Facility Inspection Executive VP & General Manager Bureau of Nuclear Facility Safety ZionSolutions, LLC Illinois Emergency Management Agency 101 Shiloh Boulevard 1011 North St., PO Box 250 Zion, IL 60099 Mazon, IL 60444 Gerard van Noordennen Kelly F. Grahn VP Regulatory Affairs Senior Health Physicist, Unit Superviso~
ZionSolutions, LLC Bureau of Radiation Safety, Environmental 101 Shiloh Boulevard Management Zion, IL 60099 Illinois Emergency Management Agency 245 W Roosevelt Road, Building 8, Suite 55 Anthony Orawiec West Chicago, IL 60185 Decommissioning Plant Manager ZionSolutions, LLC Kent McKenzie 101 Shiloh Boulevard Emergency Management Coordinator Zion, IL 60099 Lake County Emergency Management Agency 1303N. Milwaukee Avenue Dan Shrum Libertyville, IL 60048-1308 Senior VP Regulatory Affairs EnergySolutions John E. Matthews 299 South Main Street, Suite 1700
- Morgan, Lewis & Bockius LLP Salt Lake City, UT 84111 1111 Pennsylvania Avenue, NW Washington, DC 20004
ZionSolutions LLC ZS-2016-0042: Attachments ATTACHMENT 1 Radioactive Effluent Release Report
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 1 of 48 List of Sections Section# Description 1 Supplemental Information 2 Effluent & Waste Disposal Summary 2.1 Unit 1 Gaseous Effluent 2.2 Unit 2 Gaseous Effluent 2.3 Liquid Effluent 2.4 Direct Radiation 2.5 LLD's 2.6 Error Estimation 3 Solid Waste and Irradiated Fuel Shipments 4 Radiological Impact on Man, 40CFR190 & 10CFR72 Compliance summary 4.1Unit1 4.2 Unit 2 4.3 ISFSI 4.4 Combined 40CFR190 report 5 Meteorology Data 6 Errata Data from previous years 7 Summary of Liquid Radwaste System Changes 8 Corrective Actions for Inoperable Rad Monitor 9 Changes to the ODCM
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 2of48 Sectiorr 1: Supplemental Information
- 1. Regulatory Limits: The dose to a member of the public from direct radiation, liquid and gaseous effluents released from each unit to areas at or beyond site boundary shall be limited to the following:
- a. Fission and Activation products:*
- i. Tech Spec Whole Body: 500 mrem/year ii. Tech Spec Skin: 3000 mrem/year
- b. Particulates with half-lives > 8 days, tritium and Iodine:
- i. Tech Spec Organ:
- 1500 mrem/year ii. 10CFR50 Organ: 7.5 mrem/quarter, 15 mrem/year
- c. Liquid Effluents:
- i. 10CFRSO Whole body: 1.5 mrem/quarter, 3 mrem/year ii. 10CFR50 Organ: 5 mrem/quarter, 10 mrem/year
- d. Combined dose to real individual beyond controlled area:
- i. 10CFR72 Whole body: 25 mrem/year ii. 10CFR72 Thyroid: 75 mrem/year 111. 10CFR72 Organ: 25 mrem/year
- 2. Effluent Concentration Limits (ECL): Limits used in determining allowable release.rates or concentrations.
- a. Gaseous Effluents: 10CFR20 Appendix B Table 2 Column 1.
- b. Liquid Effluents: 10 X 10CFR20 Appendix BTable 2 Column 2.
- 3. Measurements and Approxima.tions of Total Radioactivity.
- a. Fission and Activation Products: 100% Kr-85 is assumed in calculations since other isotopes have decayed. Vent stack activity is continuously monitored for fission and activation gases. In January of 2015 all fuel was removed from the Fuel Handling Building and Transferred to the ISFSI. After the last fuel assembly was transferred, noble gases are no longer present as potential gaseous effluents.
- b. Particulate and tritium releases are continuously monitored and samples collected and analyzed weekly. Particulate filters are sent to an independent lab for quarterly composite analysis. During periods when 1RIA-PR49 and 2RIA-PR49 were Out of Service. for maintenarn:;e, particulate activity was continuously monitored. The air samples were analyzed daily while decommissioning activities were in progress in each of the areas feeding into the respective Units vent stack (i.e. Unit 1 purge system for Unit 1 vent stack and Unit 2 purge system, Aux. building, Fuel Handling Building for Unit 2 vent stack). A separate composite was sent to an independent lab for composite analysis for each area monitored. Tritium activity in gaseous releases in Unit 2 vent stack were monitored during the weekly sampling. Due to pumping down the reactor cavities and spent fuel pool, the remainder of the Tritium present was monitored and calculated in liquid effluent releases instead of estimating the release via evaporation. For the purpose of freeze protection of the liquid effluent release line, an air compressor was used to blow air through the line. The air compressor drew air from a room in the Auxiliary Building thus .this pathway was added to gaseous release calculations .. The air in the room from which the air compressor
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 3of48 drew its suction was continuously monitored and the samples analyzed daily. Any activity detected in this air sample was added to continuous abnormal gaseous releases and the samples sent for quarterly composite analysis. per ODCM requirements. * .
- c. Liquid effluents are continuously monitored and isotopic analysis performed weekly. Liquid batch releases are mixed and a representative sample taken and
'analyzed prior to batch release. A complete analysis of all liquid volumes was performed by an offsite laboratory to determine hard to detect nuclide activity. A conservative ratio to Co-60 was calculated for each hard to detect nucJide. Prior to each batch release, these scaling factors were used to calculate the concentration of these hard to detect nuclides. During 2015, all potential radioactive inputs were removed from the turbine building fire sump, and the OR-PR25 fire sump monitor was removed as it was no longer required. To facilitate turbine building demolition, the fire sump compositor was moved to the Waste Water Treatment Facility (WWTF) which receives input from the remaining turbine building drains. Weekly samples and quarterly composites are analyzed on the WWTF compositor to verify there are no radioactive isotopes in the water discharged via theWWTF.
- d. . Occupancy factors were used in determining direct radiation dose to the maximally exposed member of the public based on habits of a real individual in ES&H Technical Support Document 13-009 "Member of the Public Dose from All Onsite Sources."
- 4. Batch Releases:
- a. Liquid:
- 1. There were 67 liquid batch releases in 2015
- 2. Total time period for batch releases: 2.32E+OS min.
- 3. Maximum time period for a batch release: 1.13E+04 min.
- 4. Average time period for batch release: 3.46E+03 min.
- 5. Minimum time period for a batch release: 6.12E+02 min.
- b. Gaseous:* There were no gaseous batch releases in 2015.
- 5. Abnormal Releases:**
- a. Liquid: There were no abnormal liquid releases in 2015.
- b. Gaseous: Auxiliary Building Air Compressor freeze protection discharged a total of3.05E+10 ccs. of air from 12/22/2015 to 1/1/2016.
- 6. Gaseous and Liquid Waste Treatment Systems and Process Control Program Zion Station ODCM Section 12.6.4 requires major changes to the Gaseous and Liquid Waste Treatment Systems to be reported in the Annual Radioactive Effluent Release Report. There were some changes to the Liquid Waste Treatment System, these changes and their technical bases are described in Section 7.
Zion Station ODCM Section 12. 7.2 requires major changes to the Process Control Program(PCP) to be submitted in the Annual Radioactive Effluent Release Report.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 4 of 48 The Waste Gas Hold-up System was permanently vented. In Zion's defueled configuration this system is no longer applicable. In Zion's defueled configuration, the charcoal iodine removal system is no longer applicable. Due to radioactive decay and no means of production, radioactive iodine is* not a concern at Zion.
- 7. Limiting Conditions of Operation (LCOs)
Zion Station ODCM Section 12.7.2 requires explanation as to why the inoperability of liquid or gaseous monitoring instrumentation was not corrected within the time specified in the ODCM to be submitted with the Annual Radioactive Effluent Release Report. OR-PR04 Lake Release Tank liquid effluent radiation monitor was Out of Service for a period greater than 14 days. A detailed discussion of the reasons and resolution to this issue is described in Section 8.
- 8. Liquid Holdup Tanks and Gas Storage Tanks Zion Station ODCM Section 12.7.2 requires a description of events leading to liquid holdup tanks or gas storage tanks exceeding technical specification limits to be included in the Annual Radioactive Effluent Release Report.
The contents of the six gas decay tanks have been sampled and determined to have negligible activity. The Gas Decay Tanks have been decommissioned. No liquid holdup tanks exceeded the limits of Pennanently Defueled Technical Specifications 5.6.3 during 2015.
- 9. Offsite Dose Calculation Manual (ODCM)
Changes to the ODCM and Process Control Program are required by Zion Station Permanently Defueled Technical Specification 5.6.1. and ODCM Section 12.6.3 to be submitted as part of, or concurrent with, the Annual Radioactive Effluent Release Report.
- a. ODCM Revisions: There was a major re-write to the ODCM for the purpose of the change in licensing to Post Fuel Transfer operations. The ODCM chapters were consolidated into a single document and the revision number was reset to*
revision 0. A list of changes made during 2015 are listed in Section 9.
- b. Process Control Program(PCP): There were no changes to the PCP in 2015.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 5of48
- 10. Switchyard Area The switchyard is an onsite area that is monitored for direct radiation dose. Access to the*
site is controlled by Commonwealth Edison and is not accessible to members of the general public. The dose limits for this area are regulated differently than the general offsite dose areas and comply with 10CFR20 annual dose limit of 100 mrem/year. ES&H TSD 13-009 lists the evaluation performed to determine habits of the real individual working in the switchyard and are calculated to be occupied no more than 2088 hours/year.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 6of48 Section 2.1 - Unit 1 Gaseous Releases GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit 1 Vent Stack - GROUND RELEASES REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases
- 1. Total Release Ci <LLD <LLD <LLD <LLD <LLD 2 . Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Iodine-131
- 1. Total Release Ci <LLD <LLD <LLD <LLD <LLD 2 . Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Particulates Half Life >= 8 days
- 1. Total Release Ci O.OOE+OO 2.57E-06 9.04E-04 3.43E-05 9.41E-04
- 2. Avg. Release Rate uCi/sec O.OOE+OO 3.27E-07 1.15E-04 4.36E-06 2.99E-05 Tritium
- 1. Total Release Ci <LLD <LLD <LLD. <LLD <LLD
- 2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity
- 1. Total Release Ci <LLD <LLD <LLD <LLD <LLD
- 2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation <LLD <LLD <LLD <LLD <LLD Gases Iodines <LLD <LLD <LLD <LLD <LLD
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 7of48 Particulates Half Life >= 8 days C0-60 Ci <LLD O.OOE+OO 7.46E-04 2.62E-05 7.72E-04 CS-137 Ci <LLD 2.57E-06 1.58E-04 8 .12E-0.6 1.69E-04 Totals for Period ... Ci <LLD 2.57E-06 9.04E-04 3.43E-05 9.41E-04 Tritium <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity <LLD .<LLD <LLD <LLD <LLD GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR No Batch Releases. LLD values are listed in Section 2.5 Total Error values are listed in Section 2.6
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 8of48 Section 2.2 - Unit 2 Gaseous Releases GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit 2 Vent Stack - GROUND RELEASES REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases
- 1. Total Release - Ci <LLD <LLD <LLD <LLD <LLD 2 . Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Iodine-131
- 1. Total Release Ci <LLD <LLD <LLD <LLD <LLD 2 . Avg. Release Rate uCi/sec <LLD. <LLD <LLD <LLD <LLD Particulates Half Life >= 8 days
- 1. Total Release Ci 4.99E-06 2.72E-06 1.40E-05 3.40E-06 2.SlE-05
- 2. Avg. Release Rate uCi/sec 6.34E-07 3.46E-07 1.78E-06 4.32E-07 7.97E-07 Tritium
- 1. Total Release , Ci <LLD <LLD <LLD <LLD <LLD
- 2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity
- 1. Total Release Ci <LLD <LLD <LLD <LLD- <LLD
- 2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation <LLD <LLD <LLD <LLD <LLD Gases Iodines <LLD <LLD <LLD <LLD <LLD
ZionSolutiOns LLC ZS-2016-0042: Attachment 1 Page 9of48 Particulates Half Life >= 8 days C0-60 Ci 3.28E-07 2.72E-06 7.89E-06 O.OOE+OO 1.09E-05 CS-137 Ci 4.66E-06 O.OOE+OO 6.07E-06 3.40E-06 1.41E-05 Totals for Period... Ci 4.99E-06 2.72E-06 1.40E-05 3.40E-06 2.51E-05 Tritium <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity <LLD <LLD <LLD <LLD <LLD GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR No Batch Releases. LLD values are listed in Section 2.5 Total Error values are listed in Section 2.6
ZionSolutions LLC ZS-2016-0042: Attachment l, Page 10 of 48 Section 2.3 - Liquid Effluent Releases LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (Unit 1 & Unit 2 combined) REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products AG-108M Ci O.OOE+OO O.OOE+OO 1.04E-05 2.51E-06 1.29E-05 C-14 Ci 4.41E-06 3.85E-04 3.50E-04 1.86E-04 9.25E-04 C0-60 Ci 1.00E-05 8.09E-04 7.82E-04 4.15E-04 2.02E-03 CS-137 Ci 0.00E+OO 1.28E-05 9.54E-06 1.30E-05 3.54E-05 FE-55 Ci 1.57E-06 l.13E-04 l.OSE-04 5.73E-05 2.79E-04 NI-59 Ci 3.0lE-06 2.llE-04 1. 06E-04 5.65E-05 3.77E-04 NI-63 Ci l.31E-04 1.0SE-02 8.83E-03 4.69E-03 2.45E-02 PU-241 Ci 1.03E-07 9.00E-06 8.75E-06 4.6SE-06 2.25E-05 SR-90 Ci 1.69E-06 9.47E-05 4.31E-06 2.29E-06 1.03E-04 Totals for Period... Ci 1.52E-04 l.24E-02 1.02E-02 5.43E-03 2.82E-02 Tritium H-3 Ci 6.64E-03 2.57E-01 2.57E-01 5.43E-01 1.06E+OO Totals for Period... Ci 6.64E-03 2.57E-01 2.57E-01 5.43E-01 1.06E+OO Dissolved and Entrained Gases
- 1. Total Release Ci <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity ALPHA Ci 0.00E+OO 7.22E-06 4.90E-06 6.55E-06 1.87E-05 Totals for Period... Ci O.OOE+OO 7.22E-06 4.90E-06 6.55E-06 1.87E-05 Volume of liquid waste liters 1.27E+06 1.82E+06 2.23E+06 l.01E+07 1.54E+07 Volume of dil. water liters 1.23E+09 1.24E+09 2.48E+09 5.01E+09 9.96E+09 LLD values are listed in Section 2.5 Total Error values are listed in Section 2.6
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 11of48 Section 2.3 - Liquid Effluent Releases (cont.) LIQUID EFFLUENTS - CONTINUOUS MODE (Unit 1 & Unit 2 combined) REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products <LLD <LLD <LLD <LLD <LLD Tritium <LLD <LLD <LLD <LLD <LLD Dissolved and Entrained Gases <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity <LLD <LLD <LLD <LLD <LLD LLD values are listed in Section 2.5 Total Error values are listed in Section 2.6
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 12of48 Section 2.3 - Liquid Effluent Releases (cont.) LIQUID EFFLUENTS - BATCH MODE (Unit 1 & Unit 2 combined) REPORT FOR 2015 . Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products AG-108M Ci O.OOE+OO O.OOE+OO 1.04E-05 2.51E-06 1.29E-05 C-14 Ci 4.41E-06 3.85E-04 3.50E-04 1.86E-04 9.25E-04 C0-60 Ci l.OOE-05 8.09E-04 7.82E-04 4.15E-04 2.02E-03 CS-137 Ci O.OOE+OO 1.28E-05 9.54E-06 1.30E-05 3.54E-05 FE-55 Ci 1.57E-06 1.13E-04 1.08E-04 5.73E-05 2.79E-04 NI-59 Ci 3.0lE-06 2.llE-04 1.06E-04 5.65E-05 3.77E-04 NI-63 Ci 1.31E-04 1.08E-Q2 8.83E-03 4.69E-03 2.45E-02 PU-241 Ci 1.03E-07 9.00E-06 8.75E-06 4.65E-06 2.25E-05 SR-90 Ci 1.69E-06 9.47E-05 4.31E-06 2.29E-06 1. 03E-04 Totals for Period... Ci 1.52E-04 1.24E-02 1.02E-02 5.43E-03 2.82E-02 Tritium H-3 Ci 6.64E-03 2.57E-01 2.57E-01 5.43E-01 l.06E+OO Totals for Period... Ci 6.64E-03 -2.57E-01 2.57E-01 5.43E-01 1.06E+OO Dissolved and Entrained Gases N/A <LLD <LLD <LLD <LLD Gross Alpha Radioactivity ALPHA Ci O.OOE+OO 7.22E-06 4.90E-06 6.55E-06 1.87E-05 Totals for Period... Ci O.OOE+OO 7.22E-06 4.90E-06 6.55E-06 1.87E-05 LLD values ar~ listed in Section 2.5 Tbtal Error valu~s are listed in Section 2.6
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 13 of 48 Section 2.3 - Liquid Effluent Releases (cont.) SUPPLEMENTAL INFORMATION LIQUID EFFLUENTS - BATCH MODE REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of releases 1 16 17 33 67 Total release time minutes 2.57E+03 7.87E+04 4.93E+04 1.01E+05 2.32E+05 Maximum release time minutes 2.57E+03 1.13E+04 9.22E+03 4.32E+03 1.13E+04 Average release time minutes 2.57E+03 4.92E+03 2.90E+03 3.08E+03 3.46E+03 Minimum release time minutes 2.57E+03 l.19E+03 6.17E+02 1.92E+03 6.17E+02 Permit dilution vol ltr 2.58E+07 9.92E+08 l.62E+09 3.84E+09 6.48E+09 Permit dilution flow gpm 2.65E+03 3.33E+03 8.68E+03 1.00E+04 7.38E+03 Permit max total diluted concentration (no H-3) uCi/ml 5.89E-09 6.46E-08 2.17E-08 5.17E-09 6.46E-08 Period dilution vol ltr 1.23E+09 1.24E+09 2.48E+09 5.01E+09 9.96E+09 Period dilution flow gpm 2.51E+03 2.50E+03 4.95E+03 9.99E+03 5.01E+03
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 14of48 Section 2.4-Direct Radiation Maximally exposed sector: J (25mrem/year limit) Unit Qtr 1 (mrem) Qtr 2 (mrem) Qtr 3 (mrem) Qtr4 (mrem) 2015 (mrem) Unit 1 8.25E-01 1.57E+OO 1.83E+OO 1.57E+OO 5.80E+OO Unit 2 8.25E-01 1.57E+OO 1.83E+OO 1.57E+OO 5.80E+OO ISFSI - gamma 8.25E-01 1.57E+OO 1.83E+OO 1.57E+OO 5.80E+OO ISFSI - neutron 3.00E-01 4.70E-01 7.15E-01 4.20E-01 1.91E+OO Sum: 2.78E+OO 5.18E+OO 6.21E+OO 5.13.E+OO 1.93E+Ol Maximally exposed sector Switchyard South (1 OOmrem/year limit) Switchyard Qtr 1 (mrem} Qtr 2 (mrem} Qtr 3 (mrem} Qtr 4 (mrem} 2015 (mrem} Gamma 2.61E+01 1.81E+01 2.23E+01 1.58E+01 8.23E+01 Neutron 3.10E+OO 1.80E+OO 2.90E+OO 1.40E+OO 9.20E+OO Sum 2.92E+01 1.99E+01 2.52E+01 1.72E+01 9.lSE+Ol
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 15 of 48 Section 2.5-LLD's Various detectors were used on different counting platforms for the gaseous and liquid weekly effluent samples. The lower limit of detection(LLD) accompanies each counted sample and is verified to meet the following maximum LLD's: A. Liquid Lower Limit of Detection Sample frequency Type of analysis (LLD) uCi/mL Weekly/prior to each release Principal Gamma Emitters: <5.00E-07 Dissolved and Entrained <1.00E-05 Gases Monthly composite Tritium <1.00E-05 Gross Alpha <1.00E-07 Quarterly composite Sr-90 5.00E-08 Fe-55, Ni-63 l.OOE-06 B. Gaseous Lower Limit of Detection Sample frequency Type of analysis (LLD) uCi/mL Continuous/daily/weekly Principle gamma emitters <l.OOE-11 Continuous Noble gas <1.00E-06 Monthly Noble Gas I Principle gamma <1.00E-04 emitters Tritium l.OOE-06 Quarterly composite Sr-90 <l.OOE-11 Fe-55 <3.00E-11 Ni-63 <l.OOE-11 Gross Alpha <l.OOE-11
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 16 of 48 Section 2.6-Error Estimation Estimates of Total Error The following is a calculated estimate of the maximum potential total error associated with reported values in the Annual Radioactive Effluent Release Report. The Total error is determined by calculating the square root of the sum of the squares of the individual errors.
- a. Gaseous Effluents Sampling Error 5%
Calibration Error 10% Counting Statistics Error 17% Sample Volume Error 10% Total Error 23%
- b. Liquid Effluents Sampling Error 5%
Calibration Error 10% Counting Statistics Error 16% Sample Volume Error 2% Total Error 20%
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 17of48 Section 3- Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)
- 1. .Types ofWaste Total Total Est. Total Types of Waste Quantity Activity Period (m3) Error%.
(Ci)
- a. Spent Resins, filter sludges, 6.993E+Ol 1)57E+02 2015 2.50E+Ol evaporator bottoms
- b. Dry compressible waste, 3.115E+03 l.804E+02 2015 2.50E+Ol contaminated equipment
- c. Irradiated components, 4.958E+02 8.316E+03 2015 2.50E+Ol control rods, etc.
- d. Other (describe) O.OOE+OO O.OOE+OO 2015 2.50E+Ol
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 18 of 48 Section 3- Solid Waste and Irradiated Fuel Shipments (cont.)
- 2. Estimate of major nuclide composition (by waste type)
Major Nuclide Waste Type a. Resins, Waste Type b. DAW Waste Type d. Irradiated Waste Type Composition sludges bottoms (%) contaminated equipment(%) components (%) d. Other% Ag-108m O.OOE+OO 2.26E-03 O.OOE+OO 0.00 Ag-llOm O.OOE+OO O.OOE+OO O.OOE+OO 0.00 Am-241 2.75E-03 2.30E-02 4.66E-05 0.00 C-14 l.50E-02 5.43E-02 5.64E-02 0.00 Ce-144 l.03E-03 5.86E-02 l.73E-04 0.00 Cm-242 3.91E-05 8.57E-05 l.78E-07 0.00 Cm-243 9.25E-04 7.19E-03 l.68E-05 0.00 Cm-244 O.OOE+OO 4.22E-03 8.82E-06 0.00 Co-60 , 4.36E+Ol 2.98E+Ol 6.49E+Ol 0.00 Cs-134 O.OOE+OO O.OOE+OO 2.61E-07 0.00 Cs-137 l.02E+Ol 5.37E+OO 3.22E-03 0.00 Fe-55 2.19E-01 3.60E+OO 9.23E+OO 0.00 H-3 5.87E-03 6.75E-02 l.43E-01 0.00 I-129 1.08E-03 5.97E-03 2.45E-05 0.00 Mn-54 O.OOE+OO l.76E-02 l.05E-04 0.00 Nb-94 5.29E-03 2.44E-02 l.06E-03 0.00 Ni-59 3.81E+OO 7.63E-01 3.26E-01 0.00 Ni-63 4.18E+Ol 5.86E+Ol 4.lOE-04 0.00 Ni-63am O.OOE+OO l.18E+OO . 2.54E+Ol 0.00 Np-237 O.OOE+OO 6.69E-11 O.OOE+OO 0.00 Pu-238 l.50E-03 1.49E-02 2.17E-05 0.00 Pu-239 8.l lE-04 5.21E-03 8.55E-06 0.00 Pu-240 O.OOE+OO 1.12E-03 6.65E-06 0.00 Pu-241 3.76E-02 9.07E-02 2.86E-04 0.00 Pu-242 4.45E-06 1.68E-04 4.03E-07 0.00 Ra-226 O.OOE+OO 7.58E-04 l.OlE-05 0.00 Sb-125 6.59E-03 6.86E-02 l.42E-04 0.00 Sr-89 l.98E-03 l.73E-02 7.33E-06 0.00 Sr-90 2.69E-01 6.58E-02 6.50E-05 0.00 Tc-99 l.18E-02 5.34E-02 1.96E-04 0.00 EU-152 O.OOE+OO 6.69E-03 O.OOE+OO 0.00 EU-154 O.OOE+OO 9.29E-04 O.OOE+OO 0.00 U-235 O.OOE+OO l.3 lE-03 O.OOE+OO 0.00 U-236 O.OOE+OO 4.34E-05 O.OOE+OO 0.00 U-237 O.OOE+OO l.lOE-05 O.OOE+OO 0.00 U-238 O.OOE+OO 4.6JE-07 O.OOE+OO 0.00 Zn-65 6.39E-03 5.29E-02 9.34E-05 0.00
- Ni-63AM - activated metal
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 19of48 Section 3- Solid Waste and Irradiated Fuel Shipments (cont.)
- 3. Solid Waste Disposition Number of shipments Mode of Transportation Destination 34 Truck CliveCWF 0 Rail CliveCWF 12 Truck CliveBWF 32 Rail CliveBWF 12 Truck wcs B. Irradiated Fuel Shipments (disposition)
Number of shipments Mode of Transportation Destination I 0 I C. Changes to the Process Control Program: None
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 20 of 48 Section 4-40CFR190 & 10CRF72 Compliance Summary UNIT 1, 2 & ISFSI (DOCKET Numbers 50-295, 50-304 & 72-1037) EXECUTIVE
SUMMARY
A review of 2015 effluent data indicates that the activity released from the station was far below any regulatory limit. There was no noble gas released in 2015. This trend can be attributed to the shutdown ofboth units since late September 1997. Airborne Dose to Maximally Exposed Dose to Maximally Exposed Receptor from Unit 1 Receptor from Unit 2 Gamma Air O.OOE+OO mrad O.OOE+OO mrad Beta Air O.OOE+OO mrad O.OOE+OO mrad Total Body 2.94E-02 mrem 2.94E-02 mrem Skin O.OOE+OO mrem O.OOE+OO mrem Organ 6.75E-02 mrem (Infant Liver) 6.75E-02 mrem (Infant Liver) Aquatic Dose to Maximally Exposed Dose to Maximally Exposed Receptor (Any) from Unit 1 Receptor (Any) from Unit 2 Total Body l.82E-03 mrem l.82E-03 mrem Organ 5.00E-02 mrem(Child Bone) 5.00E-02 mrem(Child Bone) Direct Radiation Dose to Maximally Dose to Maximally Dose to Maximally Exposed Member of the Exposed Member of the Exposed Member of the public from Unit 1 public from Unit 2 public from ISFSI Total Body 5.80E+00mrem (Sec J) 5.80E+OOmrem (Sec J) 7.71E+OOmrem (Sec J) Switchyard Direct Radiation (10CFR20 limit lOOmrem/year) Switchyard Qtr 1 (mrem) Qtr 2 (mrem) Qtr 3 (mrem) Qtr4 (mrem) 2015 (mrem) Gamma 2.61E+Ol l.81E+Ol 2.23E+Ol l.58E+Ol 8.23E+Ol Neutron 3.IOE+OO l.80E+OO 2.90E+OO 1.40E+OO 9.20E+OO Sum 2.92E+Ol l.99E+Ol 2.52E+Ol l.72E+Ol 9.15E+Ol
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 21of48 Section 4.1 - Unit 1 I. Unit 1 (Docket Number 50-295) A. 10 CFR20 & 40CFR 190 Compliance Assessment: The demonstration of compliance with 40CFR190 will be used to demonstrate compliance with 10CFR20.
- 1. Total Effective Dose Equivalent 5.83E+OO mrem/year
- 2. 40 CFR 190 Whole body limit 25 mrem/year
- 3. 40 CFR 190 Max exposed organ 25 mrem (75 mrem thyroid)
- 4. % Whole body limit 2.33E+01%
- 5. % Max exposed organ 2.36E+Ol % child bone Qtr 1 mrem Qtr2 mrem Qtr 3 mrem Qtr4 mrem 2015 mrem TBody 8.25E-01
- l.57E+OO 1.86E+OO l.57E+OO 5.83E+OO Adult Thody Child Thody Adult Thody Adult Thody Adult Thody Organ 8.26E-01 l.62E+OO l.89E+OO l.58E+OO 5.90E+OO Child Bone Child Bone Child Bone Child Bone Child Bone B. Maximally Exposed Receptor:
- 1. Airborne QtrObj lst,Qtr 2nd Qtr 3rd Qtr 4th Qtr Yearly limit Total Dose % of Yearly IOCFR50 2015 limit App. I Gamma air (mrad) 5.0 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 10.0 O.OOE+OO O.OOE+oO Beta Air (mrad) 10.0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+oO 20.0 0.00E+OO O.OOE+OO Total Body (mrem) 7.5 2.48E-04 2.0IE-04 2.76E-02 I .30E-03 15.0 2.94E-02 l.96E-01 Skin (mrem) 7.5 O.OOE+oO O.OOE+OO O.OOE+OO O.OOE+OO 15.0 O.OOE+OO O.OOE+OO Organ (mrem) 7.5 l.23E-03 7.40E-04 6.20E-02 3.71E-03 15.0 6.75E-02 4.50E-Ol Critical Organ Infant liver Infant liver Infant liver Infant liver Infant !iv.er Infant liver
- 2. Aquatic Yearly limit %of 2nd Qtr 3rd Qtr 4tl'Qtr Total Dose QtrObj l"Qtr IOCFR 50 Yearly 2015 App.I limit 1.97E- 1.64E- 6.35E- 2.16E- 3.0 1.82E- 6.0lE-Total Body (mrem) 2.5
*05 03 04 04 03 02 5.95E- 4.70E- 1.73E- 4.64E- 10.0 5.00E- 5.00E-Organ (mrem) 2.5 04 02 02 03 02 01 Critical Organ Child bone Child bone Child bone Child bone Child bone Child bone
- 3. Direct (gamma) Maximally Exposed Sector: J Yearly Qtr 2nd Qtr 3rd Qtr 4tl'Qtr limit Total Dose I"Qtr % of Yearly limit Obj 40CFR 2015 190 Total body 6.25 8.25E-OI l.57E+OO l.83E+OO l.57E+OO 25.0 5.80E+OO 2.32E+Ol (mrem)
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 22of48 Section 4.2 - Unit 2 II. Unit 2 (Docket Number 50-304) A. 10 CFR20 & 40CFR190 Compliance Assessment: The demonstration of compliance with 40CFR190 will be used to demonstrate compliance with 10CFR20.
- 1. Total Effective Dose Equivalent 5.83E+OO mrem/year
- 2. 40 CFR 190 Whole body limit 25 mrem/year
- 3. 40 CFR 190 Max exposed organ 25 mrem (75 mrem thyroid)
- 4. % Whole body limit 2.33E+01%
- 5. % Max exposed organ 2.36E+Ol % child bone Qtr 1 mrem Qtr2mrem Qtr 3 mrem Qtr4mrem 2015 mrem TBody 8.25E-01 1.57E+OO l.86E+OO l.57E+OO 5.83E+OO Adult Thody Child Thody Adult Thody Adult Thody Adult Thody Organ 8.26E-01 l.62E+OO l.89E+OO l.58E+OO 5.90E+OO Child Bone Child Bone Child Bone Child Bone Child Bone B. Maximally Exposed Receptor:
- 1. Airborne Qtr 1'1 Qtr 211 " Qtr 3'" Qtr 4m Qtr Yearly limit Total Dose % of Yearly Obj !OCFR 50 2015 limit App. I Gamma air (mrad) 5.0 O.OOE+OO O.OOE+OO O.OOE+oO O.OOE+OO 10.0 O.OOE+oO O.OOE+OO Beta Air (mrad) 10.0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 20.0 O.OOE+OO O.OOE+OO Total Body (mrem) 7.5 2.48E-04 2.0lE-04 2.76E-02 l .30E-03 15.0 2.94E-02 l.96E-Ol Skin (mrem) 7.5 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 15.0 0.00E+OO 0.00E+OO Organ (mrem) 7.5 l .23E-03 7.40E-04 6.20E-02 3.71E-03 15.0 6.75E-02 4.SOE-01 Critical Organ Infant liver Infant liver Infant liver Infant liver Infant liver Infant liver
- 2. Aquatic Yearly limit Qtr 1 Total Dose 1'1 Qtr 2"" Qtr 3" .Qtr 4tl'Qtr 10CFR % of Yearly limit Obj 2015 50 App.
I Total Body 2.5 l.97E-05 l.64E-03 6.35E-04 2.16E-04 3.0 l.82E-03 6.0lE-02 (mrem) Organ 2.5 5.95E-04 4.70E-02 l.73E-02 4.64E-03 10.0 5.00E-02 5.00E-01 (mrem) Critical Child bone Child bone Child bone Child bone Child bone Child bone Onmn
- 3. Direct (gamma) Maximally Exposed Sector: J Yearly Qtr 3rd Qtr limit Total Dose lQtr 2°" Qtr 4thQtr % of Yearly limit Obj 40CFR 2015 190 Total body 6.25 8.25E-Ol l.57E+o0 l.83E+OO l.57E+OO 25.0 5.80E+o0 2.32E+Ol (mrem)
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 23 of 48 Section 4.3 - ISFSI III. ISFSI (Docket Number 72-1037) A. 10CFR72 & 40CFR190 Compliance Assessment:
- 1. Total Effective Dose Equivalent 7. 71 +00 mrem/year
- 2. 40 CFR190 I 10CFR72 Whole body limit 25 mrem/year
- 3. 40 CFR190 I 10CFR72 Max exposed organ 25 mrem (75 mrem thyroid)
- 4. % Whole body limit 3.08E+01%
- 5. % Max exposed organ (child bone/thyroid) 3.08E+Ol % I l.03E+Ol %
Qtr 1 mrem Qtr 2 mrem Qtr 3 mrem Qtr4 mrem 2015 mrem TEDE l.13E+OO 2.04E+OO 2.55E+OO l.99E+OO 7.71E+OO TODE l.13E+OO 2.04E+OO 2.55E+OO l.99E+OO 7.71E+OO B. Maximally Exposed Receptor Sector: J
- 1. Direct (gamma+ neutron)
Yearly limit Qtr Total Dose % of Yearly lQtr 2"d Qtr 3"1 Qtr 4th Qtr 40CFR190/ Obj 2015 limit 10CFR72.104 Total body 6.25 l.13E+OO 2.04E+OO 2.55+00 l.99E+OO 25.0 7.71E+OO 3.08E+Ol (mr_em)
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 24 of 48 Section 4.4-Combined 40CRF190 Report IV. Combined 40CFR190 Report: 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID ANNUAL DOSE
SUMMARY
Year . . . . . . . . . . . . . . . . . . : 2015 From Unit . . . . . . . . . . . . . : 1 To Unit . . . . . . . . . . . . . . . : 2 Liquid Receptor ....... : 0 Liquid Receptor === MAXIMUM PERIOD DOSE TO LIMIT (Any Organ) Dose Age Dose Limit Admin Admin Sl- 0 T.Spec T.Spec Sl-0 Period Group Organ (mrem) Period Limit of Limit Limit of Limit Quarter 1 CHILD BONE 1.19E-03 Quarter 2.50E+OO 4.76E-02 2.50E+OO 4.76E-02 Quarter 2 CHILD BONE 9.40E-02 Quarter 2.50E+OO 3.76E+OO 2.50E+OO 3.76E+OO Quarter 3 CHILD BONE 3.46E-02 Quarter 2.50E+OO 1.38E+OO 2.50E+OO 1. 38E+OO Quarter 4 CHILD BONE 9.27E-03 Quarter 2.50E+OO 3.71E-01 2.50E+OO 3.71E-01 Annual CHILD BONE 1.00E-01 Annual 5.00E+OO 2.00E+OO 5.00E+OO 2.00E+OO --- MAXIMUM PERIOD DOSE TO LIMIT (Tot Body)) =================================== Dose Age Dose Limit Admin Admin % T ..Spec T.Spec 9,. 0 Period Group Organ (mrem) Period Limit of Limit Limit of Limit Quarter 1 CHILD TBODY 3.93E-05 Quarter 1.50E+OO 2.62E-03 1.50E+OO 2.62E-03 Quarter 2 CHILD TBODY 3.28E-03 Quarter 1.50E+OO 2.lSE-01 1. 50E+OO 2.lSE-01 Quarter 3 CHILD TBODY l.27E-03 Quarter 1.50E+OO 8.48E-02 1.50E+OO 8.48E-02 Quarter 4 ADULT TBODY 4.31E-04 Quarter 1.50E+OO 2.87E-02 1.50E+OO 2.87E-02 Annual CHILD TBODY 3.64E-03 Annual 3.00E+OO 1.21E-01 3.00E+OO 1.21E-01
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page25of48 Section 4.4- Combined 40CRF190 Report (cont.) 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GAS ANNUAL DOSE
SUMMARY
Year . . . . . . . . . . . . . . . . . . : 2015 From Unit ............. : 1 To Unit . . . . . . . . . . . . . . . : 2 Coefficient Type ...... : Historical Gas Receptor .......... : 5 Composite Crit. Receptor - IP Distance (meters) ..... : 0.00 Compass Point ......... : NA --- MAXIMUM PERIOD DOSE TO LIMIT (Any Organ) =================================== Dose Age Dose Limit Admin Admin ~ T.Spec 0 T.Spec ~ 0 Period Group Organ (mrem) Period Limit of Limit Limit of Limit Quarter 1 INFANT LIVER 2.46E-03 Quarter 5.63E+OO 4.38E-02 7.50E+OO 3.28E-02 Quarter 2 INFANT LIVER l.48E-03 Quarter 5.63E+OO 2.64E-02 7.50E+OO l.98E-02 Quarter 3 INFANT LIVER 1.24E-01 Quarter 5.63E+OO 2.20E+OO 7.50E+OO 1.65E+OO Quarter 4 INFANT LIVER 7.42E-03 Quarter 5.63E+OO 1.32E-01 7.50E+OO 9;90E-02 Annual INFANT LIVER 1.35E-01 Annual 1.13E+Ol 1. 20E+OO 1.50E+Ol 9.0lE-01 --- MAXIMUM PERIOD DOSE TO LIMIT (Tot Body)) =================================== Dose Age Dose Limit Admin Admin ~ T.Spec 0 T.Spec ~0 Period Group Organ (mrem) Period Limit of Limit Limit of Limit Quarter 1 ADULT TBODY 4.95E-04 Quarter 5.25E+OO 9.43E-03 7.50E+OO 6.60E-03 Quarter 2 ADULT TBODY 4.02E-04 Quarter 5.25E+OO 7.66E-03 7.50E+OO 5.37E-03 Quarter 3 ADULT TBODY 5.52E-02 Quarter 5.25E+OO 1.05E+OO 7.50E+OO 7.37E-01 Quarter 4 ADULT TBODY 2.59E-03 Quarter 5.25E+OO 4.93E-02 7.50E+OO 3.45E-02
~ .. '
Annual ADULT TBODY 5.87E-02 Annual 1.05E+Ol 5.59E-01 1.50E+Ol 3.92E-01
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 26 of 48 Section 4.5- Combined 40CRF190 Report (cont.) 40CFR190 URANIUM FUEL CYCLE DOSE REPORT COMBINED MAXIMUM ANNUAL DOSE
SUMMARY
Year . . . . . . . . . . . . . . . . . . : 2015 From Unit . . . . . . . . . . . . . : 1 To Unit . . . . . . . . . . . . . . . : 2 Liquid Receptor ....... : 0 Liquid Receptor Coefficient Type ...... : Historical Gas Receptor .......... : 5-composite Crit. Receptor - IP Distance (meters) ..... : 0.00 Compass Point ......... : NA --- MAXIMUM PERIOD DOSE TO LIMIT (Any Organ) =================================== Dose Age Dose Limit Percent Period Group Organ (mrem) Period Limit of Limit Quarter 1 CHILD BONE 2.83E-03 Quarter 6.25E+OO 4.53E-02 Quarter 2 CHILD BONE 9.50E-02 Quarter 6.25E+OO 1.52E+OO Quarter 3 CHILD BONE 1.29E-01 Quarter 6.25E+OO 2.07E+OO Quarter 4 CHILD BONE 1.47E-02 Quarter 6.25E+OO 2.35E-01 Annual CHILD BONE 2.03E-01 Annual 2.50E+Ol 8.12E-01 --- MAXIMUM PERIOD DOSE TO LIMIT (Tot Body)) =================================== Dose Age Dose Limit Percent Period Group Organ (mrem) Period Limit of Limit Quarter 1 ADULT TBODY 5.25E-04 Quarter 6.25E+OO 8.40E-03 Quarter 2 CHILD TBODY 3.62E-03 Quarter 6.25E+OO 5.80E-02 Quarter 3 ADULT TBODY 5.64E-02 Quarter 6.25E+OO 9.03E-01 Quarter 4 ADULT TBODY 3.02E-03 Quarter 6.25E+OO 4.83E-02 Annual ADULT TBODY 6.23E-02 Annual 2.50E+Ol 2.49E-01
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 27of48 Section 5-Meteorological Data
- 1. Introduction The purpose of the meteorological program conducted at Zion Station site was to provide information sufficient to assess the local weather conditions and was used to determine the degree of atmospheric dispersion of airborne radioactive effluent from the station.
During the first quarter of2015, all fuel had been removed to the ISFSI location and continuous meteorological monitoring was no longer required. The previous 6 years of data from Jan. 1, 2009 to Dec. 31, 2014 was queried to generate the historic average wind rose and atmospheric dispersion parameters for future airborne effluents from Zion Station. The method of dose calculation that will be used going forward is ground level release and relevant information that is applicable to this method of effluent dose calculation has been included in this report. The meteorological tower that was used in calculation of these historical averages was 250 ft. in elevation and was instrumented at two levels. Wind speed and direction measured at 35 ft. and 250 ft. Ambient temperature was measured at 35 ft. Differential temperature, referenced to 35 ft. was measured at 250 ft. Dew point temperature was measured approximately ten feet from the tower at an elevation of 5 ft. Precipitation was measured by a rain gauge located on the roof of the meteorological shelter building. Joint frequency stability wind rose tables of wind direction, wind speed, and stability were routinely tabulated from hourly measurements during the six year period of this historical average. The six year historical average data tables are included in this report.
- 2. Summary For the six year period from Jan. 1 2009 to Dec. 31, 2014 considered in calculating the historical average, Zion Stations meteorological monitoring program generated 51,918 total hours of valid data out of a possible 52596 total hours, 678 total hours of data were lost representing a 98.71 %
data recovery rate. The stability wind rose tables included in this report have been.generated using the 35 ft. wind data with the 250-35 ft. differential temperature data.
- 3. Data Acquisition Information regarding Data Acquisitio?-, Data Analysis and instruments used can be found in the meteorological monitoring sections of_prior Zion Stations Annual Radioactive Environmental Monitoring Reports from 2009 to 2014.
- 4. The following two programs were used to calculate doses resulting from radioactive releases:
- a. XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations (NUREG/CR-2919)
The program is based on the theory that material released to the atmosphere will be normally distributed (Gaussian) about the plume centerline. A straight-line trajectory is assumed between the point of release and all receptors.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 28 of 48 The program implements the assumptions outlined in Section C of NRC Regulatory Guide 1.111. In evaluating routine releases from nuclear power plants, it primarily is designed to calculate annual relative effluent concentrations, X/Q values and annual average relative deposition, D/Q values. The historical average output from the XOQDOQ program from 2009-2014 was used to develop the input to the RETDAS program.
- b. RETDAS: Radiological Effluent Tracking and Dose Assessment Software.
RETDAS is a program written for the evaluation ofradiological impacts due to the release of radioactive material to the environment during normal operation ofreactors. The RETDAS code implements the radiological impact models ofNRC Regulatory Guide 1.109 Rev. 1, for atmospheric releases. The program is used to estimate the maximum individual doses at the maximally exposed location in the vicinity of the plant.
- 5. Detailed information regarding the meteorological maintenance and calibration information of the meteorological tower and instruments used during the historical average evaluation time period can be found in prior Zion Station Annual Radioactive Environmental Operating Reports from 2009 to 2014.
- 6. Stability Wind Rose Data The historical stability wind roses are given in Tables 4 through 8. For the year, winds measured at 35ft. most frequently came from the West (10.86%) and fell into the 3.6 to 7.5 mph wind speed class (34.94%). Calms (wind speeds at or below lmph were measured at 0.16% ofthe time and speeds greater than 24.5 mph were measured 0.09% of the time.
Stability based on the 250-35 ft. differential temperature most frequently fell into the neutral classification(3 9 .5 8%)
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 29of48 Section 5-Meteorological Data (cont.) Table 1 Wind Direction Classes Wind Direction Compass Direction the Wind is Coming From
- Class N 348.75° <WD:S 11.25° NNE 11.25° <WD:S 11.25° NE 33.75° <WD:S 33.75° ENE 56.25° <WD:S 56.25° E 78.75° <WD:S 78.75° ESE 101.25° <WD:S 101.25° SE 123.75° <WD:S 123.75° SSE 146.25° <WD:S 146.25° s 168.75° <WD:S 168.75° SSW 191.25° <WD:::; 191.25° SW 213.75° <WD:S 213.75° WSW 236.25° <WD:S 236.25° w 258.75° <WD:S 258.75° WNW 281.25° <WD:S 281.25° NW 303.75° <WD:S 303.75° NNW 326.25° <WD:S 348.75° Table 2 Wind Speed Classes Wind Speed Class Wind Speeds are in miles per hour (mph) 1 0.0 <WS:::; 0.7 2 0.7 <WS:S 3.5 3 3.5 <WS:S 7.5 4 7.5 <WS:S 12.5 5 12.5 <WS:S 18.5 6 18.5 <WS:S 24.5 7 24.5 <WS
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 30of48 Section 5-Meteorological Data (cont.) Table 3 Atmospheric Stability Classes Class Differential Temperature Differential Temperature Interval (in °C/l 00m)< 1) Interval (in Op OVer the 250-35 ft. interval)(2 ) A - Extremely Unstable ~T:S-1.9 ~T:S-2.3 B - Moderately Unstable -1.9 < ~T :'.S-1.7 -2.3 < ~ T :S -2.l C - Slightly Unstable -1.7 < ~T :'.S-1.5 -2.1 <~T:S-1.8 D -Neutral -1.5 < ~T :S -0.5 -1.8 < ~T :S-0.6 E - Slightly Stable -0.5<~T:S1.5 -0.6 < ~T :S 1.7 F - Moderately Stable 1.5 < ~T :S 4.0 1.7 < ~T :S 4.7 G - Extremely Stable 4.0 <~T 4.7<~T (1) From ANSI/ANS 2.5 (2) ANSI/ANS 2.5 intervals scaled for instrument heights on the Zion meteorological tower.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 31of48 Section 5-Meteorological Data (cont.) Table 4 Percent of time at each Wind Speed and Direction Period of Record: Jan.* 1, 2009 to Dec. 31, 2014 Stability Class: A - Extremely Unstable Elevation: Ground Level Release Wind Speed (mph) at 1Om Level Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0 0 0.031 0.156 0.254 0.04 0.002 0.48 NNE 0 0 0.176 0.98 0.287 0.006 0 1.45 NE 0 0.002 0.391 0.559 0.075 0.004 0 1.03 ENE 0 0.002 0.368 0.22 0.019 0.002 0 0.61 E 0 0.004 0.412 0.133 0.023 0 0 0.57 ESE 0 0.002 0.379 0.141 0 0 0 0.52 SE 0 0 0.272 0.219 0.01 0 0 0.5 SSE 0 0 0.05 0.249 0.035 0 0 0.33 s 0 0 0.01 0.046 0.019 0 0 0.08 SSW 0 0.002 0.015 0.068 0.144 0.01 0 0.24 SW 0 0.002 0.041 0.319 0.331 0.015 0.006 0.71 WSW 0 0 0.133 0.516 0.366 0.021 0.004 1.04 w 0 0 0.12 0.577 0.401 0.01 0 1.11 WNW 0 0 0.089 0.492 0.187 0.002 0 0.77 NW 0 0.006 0.068 0.404 0.112 0 0 0.59 NNW 0 0 0.039 0.058 0.037 0 0 0.13 Total: 0 0.019 2.591 5.137 2.3 0.11 0.012 10.17
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 32of48 Section 5-Meteorological Data (cont.) Table 4(cont.) Percent of time at each Wind Speed and Direction Period ofRecord: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: B - Moderately Unstable
*Elevation: Ground Level Release Wind Speed (mph) at 1Om Level Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6-18.5 18.6 - 24.5 >24.5 Total:
Direction N 0 0 0.039 0.102 0.119 0.015 0 0.28 NNE 0 0 0.112 0.196 0.058 0.004 0.002 0.37 NE 0 0.012 0.108 0.052 0.014 0.004 0 . 0.19 ENE 0 0.012 0.068 0.029 0.014 0 0 0.12 E 0 0.004 0.077 0.025 0.002 0 0 0.11 ESE 0 0.008 0.066 0.045 0 0 0 0.12 SE 0 0 0.097 0.041 0 0 0 0.14 SSE *o 0 0.06 0.164 0.025 0 0 0.25 s 0 0 0.01 0.052 0.008 0.002 0 0.07 SSW 0 0 0.013 0.058 0.098 0.008 0.002 0.18 SW 0 0.002 0.033 0.149 0.158 0.013 0.002 0.36 WSW 0 0 0.062 0.193 0.089 0.012 0.002 0.36 w 0 0.002 0.068 0.211 0.129 0.004 0 0.41 WNW 0 0 0.06 0.179 0.081 0.004 0 0.32 NW 0 0.004 0.049 0.191 0.052 0 0 0.29 NNW 0 0.002 0.021 0.054 0.027 0.002 0 0.11 Total: 0 0.044 0.938 i.739 0.872 0.067 0.008 3.67
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 33 of 48 Section 5-Meteorological Data (cont.) Table 4(cont.) Percent of time at each Wind Speed and Direction Period ofRecord: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: C - Slightly Unstable Elevation: Ground Level Release Wind Speed (mph) at lOm Level Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0 0.004 0.086 0.243 0.177 0.013 0.008 0.53 NNE 0 0.01 0.183 0.31 0.079 0.004 0 0.59 NE 0 0.023 0.15 0.102 0.031 0.01 0.006 0.32 ENE 0 0.023 0.1 0.044 0.021 0.012 0.002 0.2 E 0 0.01 0.146 0.025 0.018 0 0 0.2 ESE 0 0.019 0.115 0.037 0.014 0 0 0.18 SE 0 0.0.06 0.181 0.054 0.016 0 0 0.26 SSE 0 0.006 0.106 0.351 0.11 0.01 0 0.58 s 0 0.004 0.066 0.101 0.021 0 0 0.19 SSW 0 0.002 0.041 0.119 0.154 0.017 0.004 0.34 SW 0 0 0.094 0.244 0.189 0.023 0.006 0.56 WSW 0 0.004 0.11 0.252 0.139 0.01 0.002 0.52 w 0 0.008 0.133 0.277 0.165 0.008 0 0.59 WNW 0 0.008 0.127 0.308 0.079 0 0 0.52 NW 0 0.01 0.096 0.206 0.096 0 0 0.41 NNW 0 0.01 0.033 0.133 0.045 0.004 0 0.22 Total: 0 0.145 1.768 2.806 1.352 0.11 0.027 6.21
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 34of48 Section 5-Meteorological Data (cont.) Table 4(cont.) Percent of time at each Wind Speed and Direction Period of Record: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: D - Neutral Elevation: Ground Level Release Wind Speed (mph) at 1Om Level Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0 0.102 0.597 1.392 1.05 0.21 0.06 3.41 NNE 0 0.142 0.758 1.123 0.769 0.042 0.031 2.87 NE 0 0.161 0.528 0.57 0.405 0.046 0.025 1.74 ENE 0.001 0.137 0.348 0.346 0.347 0.092 0.008 1.28 E 0 0.121 0.392 0.303 0.353 0.094 0.013 1.28 ESE 0 0.148 0.489 0.289 0.163 0.035 0.002 1.13 SE 0 0.127 0.567 0.378 0.149 0.008 0 1.23 SSE 0 0.075 0.523 1.258 0.944 0.168 0.054 3.02 s 0 0.106 0.686 0.805 0.314 0.015 0 1.93 SSW 0 0.128 0.641 0.994 0.774 0.087 0.008 2.63 SW 0 0.152 0.612 1A43 1.003 0.108 0.015 3.33 WSW 0.001 0.138 0.849 1.327 0.659 0.042 0.002 3.02 w 0 0.146 1.1 1.766 0.961 0.029 0.002 4 WNW 0 0.169 1.139 1.402 0.52 0.012 0 3.24 NW 0 0.164 1 1.404 0.489 0.021 o. 3.08 NNW 0 0.098 0.655 L21 0.387 0.039 0.006 2.39 Total: 0.006 2.117 10.886 16.01 9.286 1.048 0.225 39.58
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 35of48 Section 5-Meteorological Data (cont.) Table 4(cont.) Percent of time at each Wind Speed and Direction Period of Record: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: E - Slightly Stable Elevation: Ground Level Release Wind Speed (mph) at 1Om Level Wind <1 1- 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24. Total Direction 3.5 5 N 0.005 0.302 0.672 0.53 0.173 0.021 0.012 1.72 NNE 0.004 0.245 0.564 0.447 0.058 0.013 0 1.33 NE 0.004 0.204 0.314 0.167 0.075 0.002 0 0.77 ENE 0.003 0.154 0.212 0.092 0.071 0.01 0 0.54 E 0.003 0.148 0.212 0.082 0.11 0.054 0.008 0.62 ESE 0.002 0.129 0.233 0.091 0.052 0.017 0 0.52 SE 0.003 0.163 0.456 0.273 0.079 0.004 0 0.98 SSE 0.004 0.192 .0.452 0.84 0.291 0.029 0.019 1.83 s 0.005 0.292 1.375 0.839 0.166 0.004 0 2.68 SSW 0.005 0.441 1.19 0.661 0.154 0.015 0 2.47 SW 0.006 0.324 0.855 0.607 0.183 0.013 0 1.99 WSW 0.004 0.277 1.008 0.503 0.069 0.002 0 1.86 w 0.005 0.353 1.349 0.649 0.117 0.006 0.002 2.48 WNW 0.005 0.38 1.136 0.599 0.05 0.002 0 2.17 NW 0.005 0.319 1.069 0.48 0.073 . 0 0 1.95 NNW 0.004 0.252 0.593 0.203 0.058 0 0 1.11 Total: 0.065 4.178 11.692 7.063 1.779 0.193 0.04 25.01
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 36of48 Section 5-Meteorological Data (cont.) Table 4(cont.) Percent of time at each Wind Speed and Direction Period of Record: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: F - Moderately Stable Elevation: Ground Level Release Wind Speed (mph) at lOm Level Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0.002 0.151 0.162 0.043 0 0 0 0.36 NNE 0.001 0.094 0.106 0.019 0 0 0 0.22 NE 0.001 0.083 0.086 0.025 0 0 0 0.2 ENE 0.001 0.076 0.064 0.024 0.014 0.002 0 0.18 E 0.001 0.079 0.077 0.027 0.01 0 0 0.19 ESE 0.001 0.077 0.111 0.045 0.016 0 0 0.25 SE 0.001 0.072 0.156 0.07 0.006 0 0 0.3 SSE 0.001 0.068 0.154 0.351 0.118 0.013 0 0.7 s 0.003 0.24 0.714 0.368 0.08 0.002 0 1.41 SSW 0.004 0.472 0.51 0.031 0.004 0 0 1.02 SW 0.005 0.454 0.334 0.023 0.002 0 0 0.82 WSW 0.005 0.495 0.368 0.015 0 0 0 0.88 w 0.005 0.416 0.637 0.015 0 0 0 1.07 WNW 0.003 0.307 0.458 0.008 0 0 0 0.78 NW 0.004 0.333 0.466 0.012 0 0 0 0.82 NNW 0.003 0.202 0.165 0.002 0.002 0 0 0.37 Total: 0.042 3.618 4.571 1.075 0.251 0.017 0 9.57
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 37of48 Section 5-Meteorological Data (cont.) Table 4( cont.) Percent of time at each Wind Speed and Direction Period of Record: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: G - Extremely Stable Elevation: Ground Level Release Wind Speed (mph) at 1Om Level Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0.001 0.058 0.025 0 0 0 0 0.08 NNE 0.001 0.034 0.028 0 0 0 0 0.06 NE 0.001 0.03 0.01 0.008 0.002 0 0 0.05 ENE 0.001 0.029 0.018 0.008 0.012 0 0 0.07 E 0.001 0.033 0.029 0.02 0.008 0 0 0.09 ESE 0.001 0.039 0.058 0.021 0.004 0 0 0.12 SE 0.001 0.034 0.066 0.029 0.002 0 0 0.13 SSE 0.001 0.052 0.095 0.167 0.054 0 0 0.37 s 0.002 0.116 0.424 0.316 0.057 0 0 0.91 SSW 0.005 0.256 0.11 0.006 0 0 0 0.38 SW 0.005 0.258 0.189 0 0 0 0 0.45 WSW 0.006 0.481 0.316 0 0 0 0 0.8 w 0.008 0.586 0.609 0 0 0 0 1.2 WNW 0.007 0.353 0.401 0 0 0 0 0.76 NW 0.003 0.104. 0.108 0 0 0 0 0.22 NNW 0.003 0.07f 0.016 0 0 0 0 0.09 Total: 0.048 2.534 2.498 0.574 0.139 0 0 5.79
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 38of48 Section 5-Meteorological Data (cont.) Table 5 Percent Wind Direction by Stability Class Wind Stability Class Direction A B c D E F G Total N 0.48 0.28 0.53 3.4 1.72 0.36 0.08 6.86 NNE 1.45 0.37 0.59 2~9 1.33 0.22 0.06 6.89 NE 1.03 0.19 0.32 1.7 0.77 0.2 0.05 4.3 ENE 0.61 0.12 0.2 1.3 0.54 0.18 0.07 3 E 0.57 0.11 0.2 1.3 0.62 0.19 0.09 3.06 ESE 0.52 0.12 0.18 1.1 0.52 0.25 0.12 2.84 SE 0.5 0.14 0.26 1.2 0.98 0.3 0.13 3.54
'SSE 0.33 0.25 0.58 3.0 1.83 0.7 0.37 7.08 s 0.08 0.07 0.19 1.9 2.68 1.41 0.91 7.27 SSW 0.24 0.18 0.34. 2.6 2.47 1.02 0.38 ' 7.26 SW 0.71 0.36 0.56 3.3 1.99 0.82 0.45 8.22 WSW 1.04 0.36 0.52 3.02 1.86 0.88 0.8 8.48 w 1.11 0.41 0.59 4 2.48 1.07 1.2 10.86 WNW 0.77 0.32 0.52 3.24 2.17 0.78 0.76 8.56 NW 0.59 0.29 0.41 3.08 1.95 0.82 0.22 7.36 NNW 0.13 0.11 0.22 2.39 1.11 0.37 0.09 4.42 TOTAL 10.17 3.61 6.21 39.58 25.01 9.57 5.79 100
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 39of48 Section 5-Meteorological Data (cont.) Table 6 Percent Wind Direction by Wind Speed Wind Speed in mph Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.6 - 18.6 - >24.5 Total: Direction 12.5 18.5 24.5 N 0.008 0.617 1.612 2.466 1.773 0.299 0.082 6.86 NNE 0.006 0.525 1.927 3.075 1.251 0.069 0.033 6.89
*NE 0.006 0.515 1.587 1.483 0.602 0.066 0.031 4.3 ENE 0.006 0.433 1.178 0.763 0.498 0.118 0.01 3 E 0.005 0.399 1.345 0.615 0.524 0.148 0.021 3.06 ESE 0.004 0.422 1.451 0.669 0.249 0.052 0.002 2.84 SE 0.005 0.402 1.795 1.064 0.262 0.012 0 3.54 SSE 0.006 0.393 1.44 3.38 1.577 0.22 0.073 7.08 s 0.01 0.758 3.285 2.527 0.665 0.023 0 7.27 SSW 0.014 1.301 2.52 1.937 1.328 0.137 0.014 7.26 SW 0.016 1.192 2.158 2.785 1.866 0.172 0.029 8.22 WSW 0.016 1.395 2.846 2.806 1.322 0.087 0.01 8.48 w 0.018 1.511 4.016 3.495 1.773 0.057 0.004 10.86 WNW 0.015 1.217 3.41 2.988 0.917 0.02 0 8.56 NW 0.012 0.94 2.856 2.697 0.822 0.021 0 7.36 NNW 0.01 0.635 1.522 1.66 0.556 0.045 0.006 4.42 Total 0.161 12.655 34.944 34.404 15.979 1.545 0.312 100
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 40 of 48 Section 5-Meteorological Data (cont.) Table 7 Percent Speed by Stability Class Speed Stability Class (mph) A B c D E F G Total
<1. 0 0 0 0.006 0.065 0.042 0.048 0.161 1 - 3.5 0.227 0.177 0.524 4.22 6.601 4.625 3.303 19.677 3.6 - 7.5 2.591 0.938 1.768 10.886 11.692 4.571 2.498 34.944 7.6 - 5.137 1.739 2.806 16.01 7.063 1.075 0.574 34.404 12.5 12.6 - 2.3 0.872 1.352 9.286 1.779 0.251 0.139 15.979 18.5 18.6 - 0.11 0.067 0.11 1.048 0.193 0.017 0 1.545 24.5 >24.5 0.012 0.008 0.027 0.225 0.04 0 0 0.312 Total: 10.17 3.67 6.21 39.58 25.01 9.57 5.79 100
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 41of48 Section 6 - Errata data There are no errata corrections from prior years reports in 2015
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 42 of 48 Section 7 - Changes to Zion Station Liquid Radwaste System Gaseous Effluent Treatment and Monitoring Systems. Summary: All of the changes to the Liquid Radwaste System were evaluated and were either system improvements, had the effect of lowering the dose to the public, or had no impact on dose to the public. There was no change to the Gaseous Effluent System. There were changes to the continuous liquid process monitoring system, the liquid effluent batch reiease system, and the associated liquid dilution flow system as follows:
- 1. Turbine Building Fire Sump continuous effluent monitor system: All potential radioactive inputs from the auxiliary building and fuel handling building were removed from the turbine building fire sump prior to removing OR-PR25. The potential inputs (spent fuel pool secondary cooling water quality system monitor blow down and air conditioning condensate drains from the aux building) were removed. An evaluation was performed to determine impact of minute quantities of historical radioactivity found in the turbine building, no activity could be detected greater than QDCM required lower limits of detection. With no potential for any future introduction of radioactive material into the fire sump and historically no detectable traces ofradioactive material from the turbine building floor drains, it was determine OR-PR25 was no longer required. There was no change in the flowpath or system structural piping. The fire sump discharges to the Waste Water Treatment Facility (WWTF) for processing. The compositor in this flowpath is sampled and analyzed weekly for radioactive material and a quarterly composite is sent to an offsite laboratory for analysis as was previously done.
- 2. Lake Release Tank liquid effluent batch release system: With the high concentration of Boron in the Spent Fuel Pool, the Boron concentration was the limiting component of batch releases. New calibrated low flowrate flowmeters had to be installed to ensure the flowrate of the discharge was within the calibrated range of the instruments. One flowmeter was installed for each Lake Release Tank, and an additional common discharge line flowmeter was installed as a backup. ORT-PR04 failed in February of 2015 and an entirely new liquid radwaste effluent monitor was designed with higher capabilities than the previously used monitor. This monitor was designed, constructed and tested and was found to outperform the previous liquid radiation monitor. The liquid radwaste discharge line which entered the Unit 2 discharge tunnel was extended to travel the entire length of the discharge tunnel, inside the tunnel, to allow final status survey of the discharge tunnel. The new location of the liquid effluent discharge is approximately 5 feet downstream of the dilution flow at the valve house area.
- 3. Dilution flow system: The service water system with a minimum flowrate of 2500 gpm.
was replaced with a new dilution flow pump with a minimum output of 10,000 gpm. This change was done to allow for a larger discharge flowrate while still maintaining the Boron concentration within Federal limits. All applicable changes have been evaluated in accordance with 10CFR 50.59 by ANSI qualified technical review personnel. Doses to members of the public have been evaluated during system design to ensure that the system continues to maintain doses to the public and workers are as low as reasonably attainable and well within limits. The Engineering Change packages (ECNs) for the system changes are included in Attachments 2-5.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 43of48 Section 8 - Correction Action for Inoperable Rad Monitor ORT-PR04 Liquid Effluent Radiation Monitor Inoperable for> 30 days Per ODCM 12.2.1.A.3:
- 3. Restore the inoperable effluent monitor to OPERABLE status within 30 days, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report the reasons as detailed in Section 12.7.2 and perform a review to detemiine course of action to restore to OPERABLE status.
ORT-PR04 became inoperable on 2/20/2015. Batch releases from the Lake Release Tanks continued in accordance with ODCM surveillance requirements listed in Table 12.2-1. During the period of inoperability, every attempt was made to locate and acquire repair parts for the radiation monitor. Due to the age of the equipment, it was not possible to locate the parts needed for repair. After review, an alternate plan ofrestoring the radiation monitor to operable status was determined. Identical detector elements were available from Ludlum instruments and on-hand Zion Station repair parts. The malfunctioning meter was removed from ORT-PR04 and an adapter interface was redesigned and tied into the alarm system. Additional features were available that were not present in the old system. The new monitor was tested and new efficiencies calculated. Calibration parameters and alarm setpoints were created. The work resulted in an overall improvement to the system and was verified to outperform the old monitor. Additionally, repair parts are available to the new system for future maintenance. ORT-PR04 was declared operable on 9/912015.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 44 of 48 Section 9 List of Changes to the ODCM In accordance with ODCM section 12.7.3.1.c. Many changes were made to the ODCM, including an interim change for post-fuel transfer operations and a finalized change for post-fuel transfer operations. A summarized list of the changes is presented here, along with a complete copy of the current ODCM.
- 1. Ch.12 Rev 29 Page Section Change Summary 12-i PDTS changed to QAPP Appendix B 12-iii TOC 12.4 Removed Dose-Noble Gases, I-131,1-133 12-3 12.1.26 Added definition for unventilated building releases 12-3 12.1.27 Removed line stating effects on noble gas and iodine.
12-4 Table 12.1-1 Removed duplicate notation on REMP program frequency limitation. 12-5 12.2.1.C Removed notation 'within the plant' to broaden bases to entire site. 12-6 Table* 12.2-1 Removed words (Boric Acid Tanks (BAT). Added note related to surveillance 1. 12-7 Table 12.2-1 Surveillance 1, removed limitation of 14 days for inoperable monitor 12-8 Table 12.2-2 Removed words Boric Acid Tanks (BAT) 12-9 12.2.2.C Removed words 'within the plant' to expand bases for entire site. Removed the word 'record' as printer function is unavailable. 12-11 Table 12.2-3 2R-PR49A(Channel 1) renamed to 2R-PR49. Removed 2R-PR49E (channel 5) entirely. Removed Fuel building monitoring section. (ORT-ARB, ORT-AR21, ORT-AR22, ORT-AR24) 12-12 Table 12.2-3 Surveillance 8: Removed 'operations' as chemistry personnel are qualified to perform this surveillance. Changed 'station review' to
'review' Changed 'panel' to 'equipment'. Surveillance 10: Deleted, Surveillance 11-3 deleted (covered by surveillance 8), Surveillance 12:
Deleted, Surveillance 13: Deleted 12-13 Table 12.2-4 2R-PR49A (Channel 1) renamed to 2R-PR49. Gas Activity Monitor 2R-PR49E (channel 5) deleted. Fuel Building Monitoring ORT-AR13,21,22,24 deleted. 12-14 Table 12.2-4 Changed control room alarm ammnciation occurs to 'alaims occur.' Deleted note (3) and (4) 12-15 12.3.1.A.l Deleted 'For dissolved or entrained noble gases sentence. 12-17 Table 12.3-1 Deleted page 12-18 Table 12.3-2 Deleted (Boric Acid Tank) verbiage. Deleted sampling and analysis requirements for dissolved and entrained noble gases. 12-24 12.4.1.A 12.4.1.A.l. Deleted. 12.4.1.A.2. Removed I-131, I-133. 12.4.1.C removed 3000 mrem/year to the skin noble gas dose calculation.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 45 of 48 Page Section Change Summary 12-25 Table 12.4-1 Moved Unit 2, FHB, AB sample requirement to combine with Unit 1 requirements. Added modular HEP A ventilation requirements (if applicable). Removed sampling and LLD limits for noble gas. 12-26 Table 12.4-1 Removed Unit 2, AB, FHB sample requirements and moved to Unit 1. Added note to explain sampling requirements for unventilated releases. Deleted note using old unventilated releases definition. 12-27 Table 12.4-1 Deleted notes: d, g, I, j 12-28 12.4.2 Deleted entire section. Dose-Noble Gas 12-29 12.4.2.C Deleted section- Bases of dose-noble Gas 12-30 12.4.3 Deleted 1-131, 1-133 12-32 12.4.4.A Deleted 1,2 mrad gamma, beta dose from noble gas. 12-37 Table 12.5-1 Changed 30 TLD stations to 31 TLD stations. Deleted ISFSI Indicator TLD locations. 12-39 Table 12.5-1 Added 5. Vegetation, sampling frequency and type of analysis 12-41 Table 12.5-2 Added Vegetation reporting activity concentration 12-42 Table 12.5-3 Added Vegetation LLD concentration. 12-45 12.5.2 A. Added a nearest garden census must be performed, C. Removed from Bases that a nearest garden census is not required. 12-49 12.7.2.1 Changed Tech Specs. to QAPP
- 12-51 12.7.3.1 Changed Tech Specs. to QAPP
- 2. Ch.12 Rev 30 Page Section Change Summary 12-6 Table 12.2-1 - Removed OR-PR25, changed Turbine Building Fire Sump to WWTF 12-7 Table 12.2-1 Deleted Surveillance 2 12-8 Table 12.2-2 Removed OR-PR25 changed Turbine Building Fire Sump to WWTF 12-18 Table 12.3-2 Changed Turbine Building Fire Sump to WWTF 12-20 Table 12.3-2 Changed Turbine Building Fire Sump to WWTF
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 46 of 48
- 3. ODCMRevO Page Section Change Summary - Post Fuel Transfer Operations re-write All All Consolidation of all Chapters and appendices into a single document.
Removal of Exelon generic information that is not applicable to Zion such as river flows and boiling water reactor requirements. Removal of requirements to maintain meteorological tower. Groundwater sampling surveillances added. Added gaseous effluent considerations for future open-air demolition. Remove requirement to monitor tritium from vent stack as the tritium in water volumes is released via liquid effluents. Aerial site photographs and maps have been updated to better illustrate TLD placement locations. 14 day limitation for OOS OR-PR04 had been changed to 30 days.
- 4. ODCMRev 1 Page Section Change Summary 35 10.1.2.1 Clarified description of Aux Building Vent Stack Effluent Monitor 39 10.4.1 Editorial change, clarified wording 39 10.4.2 Editorial change, clarified wording 59 Table 12.2-1 Added OFI-WD005A and OFI-WD006A low flow flowmeters 61 Table 12.2-2 Added surveillance and calibration requirements forOFI-WD005A and OFI-WD006A 64 Table 12.2-3 Claiified surveillance 8 for 1&2 LP-084 panel sample pump operation requirements.
69 Table 12.3-2 Added wording to clarify WWTF compositor sampling required only during release. 71 Table 12.3-2 Clarified section fto require WWTF only during system operation.
- 5. ODCMRev2 Page Section Change Summary 44 Table 11-1.1 Changed location of Air Sampler Z-03 from 0.25 miles sector R(NNW) to 0.2 miles sector B(NNE) 45 Table 11-1.2.b. Changed location ofTLD Z-03-1 and 2 from 0.25 miles sector R(NNW) to 0.2 miles sector B(NNE) 50 Figure 11-la Revised inner ring REMP map to correct sector labels. REMP sample location Z-03 moved. MET tower removed from map.
51 Figure 11-lb Re-added REMP outer ring sample locations. 57 12.2.1.A Added time frame of actions to take in inoperability of liquid effluent monitor referenced by section 12. 7.2
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 47of48 Page Section Change Summary 58 Table 12."2-l Added OFIT-SW54B flowmeter for high capacity dilution pump. 59 Table 12.2-1 Added verbage to indicate the surveillance applies to the applicable (High or Low flowrate) flowmeter. 60 Table 12.2-2 Added OFIT-SW54B 61 12.2.2.A Moved verbage for inoperable rad monitor reporting requirements reference by section 12. 7 .2 to this section from surveillance 8 requirement as it is more appropriately located in the Action section. 63 Table 12.2-3 Removed verbage for returning channel to operable status time requirements from surveillance 8 to relocate to section 12.2.2.A where it is more appropriately described. 97 12.7.2 Permanently Defueled Tech Spec change to QAPP App. B
- 6. ODCMRev3 Page Section Change Summary 58 Table 12.2-1 Added OFI-WD007 common discharge flowmeter 60 Table 12.2-2 Added surveillance for OFI-WD007
- 7. ODCMRev4 Page Section Change Summary 58 Table 12.2-1 Deleted SW54 and 54B service water flowmeters.
Added OPI-SWOlA and OPI-SWOl Pressure Gauge 59 Table 12.2-1 Added Surveillance 2 for Service Water Pressure gauge inoperability. 60 Table 12.2-2 Deleted SW54 and SW54B flowmeters. Added OPI-SWOlA and OPI-SWOl service water pressure gauge. Modified note 4 to indicate pressure gauge verification once per day and to estimate dilution flow once per day.
- 8. ODCMRev 5 Page Section Change Summary 56 Table 12.1-1 Deleted Four-Hourly notation for frequency of every 4 hours.
58 Table 12.2-1 Editorial correction OPI-SWOlA and OPI-SWOl are listed as Discharge pressure flow indicators. Note** added to clarify either pressure indication may be used to apply to minimum channels operable. Changed surveillance requirement to surveillance 3.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 48of48 Page Section Change Summary 59 Table 12.2-1 Deleted Surveillance 2 for Service Water Pressure gauge. 60 Table 12.2-2 Editorial correction OFI-WD007 should be listed under common discharge Editorial correction OPI-SWOlA and OPI-SWOl are dilution flow pressure indicators. Modified note 4 to indicate pressure indicators shall be checked once per day and pump curves used for flow estimation during lake release tank releases. is a complete copy of Zion Stations Current ODCM.
ZionSolutions LLC ZS-2016-0042: Attachments ATTACHMENT 2 ECN# 400577 Extending liquid effluent discharge line through the discharge tunnel
Exhibit A NEP-OS-01 Revision 1 Engineering Change Notice (Part 1)
- ECN No.. 400577 ISSUANCE: ~FOR CONSTRUCTION 0 FOR COMMENT Page: of .)1:_ 1.11 ,
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Station: ZlQN D Safety Related Design Change No. 400576 D Affected Unit: Unit 2 and Common 181 Non-Safety Related Project No. (ifappL): . D Regulatory Supp ID No. (ifeppL): Changes to a previously Approved ECN D System: WD Description of Design Change Request: Problem Statement Llquid Radioactive Waste System (LRWS) eftluent has been discharged into the Unit 2 Circulating Water System (CW) Discharge Tunnel on the west end of the tunnel. This release point has added water to the tunnel that is borated and will need to be diluted prior to release to the lake to meet the Illinois Environmental Protection Agency National PolJution Discharge Elimination System (NPDES) Permit. The NPDES permit limit for boron is 1 ppm. The current SFP water boron concentration is approximately 2,000 ppm. The current release point does not support the D&D schedule if the effluent discharge point remains on the west end of the tunnel dqe to having to process (dilute) the borated water released into the tunnel. There is approximately 720,000 gallons of this highly borated SFP water that would be released into the Unit 2 CW Discharge Tunnel. The milestone for isolating the Unit 2 CW Outlet Isolation valve is 1/1/16. Utilizing the current release point on the west end of the tunnel will not meet th~ schedule milestone. \. ) , I Resolution To minimize the further addition of LRWS effluent into the west end of the Unit 2 CW Discharge Tunnel the LRWS discharge hose will be extended to the east end of the tunnel. The installation of an extension hose onto the existing LRWS discharge hose from the west end of the tunnel and route it inside the tunnel to the east end of the tunnel. The extension hose will be routed* in the CW tunnel and the effluent release point will be placed past the dilution source near the Unit 2 CW Discharge Isolation Valve. This will prevent further input of borated water into the tunnel. This will also allow additional time to release the borated water currently in the tunnel to the environment that has not reached the Service Water (SW) dilution point on the west end of the tunnel. Technical Review Letter TR-002-2015 and 50.59 Screening SCR 2015-008 completes the engineering and licensing 1 justification for this ECN Reason for Design Change: . Change Biid action required (Provide ~soo for chaoge, specific actions required. attach supporting docwnew, es a,PJicable). Minimize future LRWS effluent from being released to the west end of the discharge tunnel. This will shorten the duration to remove the current LR.WS eftluent in the tunnel while still meeting the TB demo and tunnel FSS milestones. INTERFACING CQMMENTS by: Design Group or Discipline Name of Commenter (Printed) SignatiJrc of Commenter Date 'CorNC ElecL/I&C NIA Mechanical Structural NIA ) Others Others
tr Exhibit A NEP-08-01 Revision l ) Engineering Change Notice (Part 1) Others Prepared by: Lee DuBois oD~ Reviewed by: Approved by:. [;,'~.;:.=..;;~LJ=~-=-W--=- Date: 1-2.6-/J; Date: oate: All affected design documents revised by (date): v crified by: Date: - - - - - - ) ECNNo.: _....40=0=5~77~--- ) Design Change No.: 400576
/'Jc, PageNo.: 2 ofl4 ll '\-
Engineering Change Print Date: 02/02/2015 EC Number : 0000400577 000
'tatus/Date : REGISTER 01/12/2015 I 'l 1' t y .ac1 : ZIN Type/Sub-type: DCP MOD uowum llW1111111111IYU1111111111lllU1111111111 llffIIUU Bii1111 Page: J/ t( ~/;>
EC
Title:
LRWS RELEASE HOSE EXTENSION FROM 02 TB SW STANDPIPE TO 02 CW DISC HAR.GE VALVE HOUSE TYPE: ECN Mod Nbr : 400576 KWl: NS KW2: KW3: KW4: KWS: Master EC : N Work Group : Temporary : N out~ge : N Alert Group: CFILE Aprd Reqd Date: WO Required : Image Addr : Exp Insvc Date: Adv Wk Appvd: Alt Ref. : . Expires On : Auto-Advance: N Priority : Auto-Asbuild : N Caveat outst: Department : Discipline : Resp Engr : GARY XXINACTIVE-MACGREGOR Location : A£rected Documents L1st Sub-
'Fac .!m! ,In?! Document Sheet .QE! Rvw , ?£! .!!!£ 'itN DWGC M-31 N Y N Minor Rev: Maj or Rev: Updt Due:
Title:
DIAGRAM OF CIRCULATING WATER .PIPING . ,_ UNITS 1 & 2 ZIN DWGC M-49 1 N y N Minor Rev: Maj or Rev: Updt Due:
Title:
DIAGRAM OF WASTE DISPOSAL SYSTEM (LIQUID} MONITOR AND DISPOSAL SYSTEM
Exhibit A NEP-08-01 Revision 1 ECN No.: 400577
~~~~~~~~
Design Change No.: 400576 Page No.: 4 of M"u Back~Up Calculation Listing
,Pv (Part 2)
Calculation/Analysis No. Revision No. Description None
Part4 Construction Support Information Recommended Installation Steps I . Prepare for diving activities( i.e. Build Scaffold, Remove grating at air vent on U2 CW Discharge Valve House Vent Shaft, Remove instruments from air vent on U2 CW Discharge Valve House, safety plans, diver retrieval rig, pull rig, lay hose strings out, couple hoses, gang hoes, etc.)
- 2. Cut hole in U2 SW Stand Pipe per below photo. Field to determine size. Clean up/smooth off edges of hole to prevent damage to hose during pull evolution. Location is Unit 2 Turbine Building 592' Row/Colmnn F-9 Existing LRWS Cut large hole in stand pipe for hose pull and new LRWS and spare pull rope entry to CW tunnel
- 3. Have diver feed pull rope through the tunnel. Diver will most likely enter the tunnel on the east end of the Unit 2 CW Discharge Tunnel into the air relief shaft.
- 4. Pull hose gang through the tunnel. Reference Mark ups on M-101, M-49 Sht 1 and M-31. Divers may need to assist in pull.
5.Configure and tie off hoses.
- 6. For LRWS discharge hose add test ends and perform a hydro or pressure decay test at "'100 psi to verify no leaks.
7.ln TB connect LRWS discharge 3" hose to existing 2" LRWS hose. EC 400577 Prepared By: _-L __J).__,~._..._ _ Da~: I ~u~.-1f' Paie 5 of,)¥ I.
Final Route for LR\'1/S discharge hose I ICW Tunnel Section View Looking South I A !VVest
;Recommended End point for 6 hose, 3 RecirCTl
,...... -i~suction hose. sample hoses an~~E_~pe /
Approximate/Recommended End points t-*- -----::==:::::io--~--_, Tunnel Entry *1 for sample hoses 1/4. 1/2 & 314 through f' . /point for LWRS
.....,_____......,..........______""'----itunnel m---'----:;.ijjir=:::::i......~=:+::::::=:::::z:~--L----------*-.--..----___., \
! '-~":.,umNt .::J!1!2H-H'3!1fa1E+-+--n;~'w Discharge Hose I iand spare pull I
+-+ll+-ii£,~1 lrope (SW stand {
'-~~==:=::=::~~~=~::;;.~:;;t~~J:tqj::c;t~:(i-A-_.t=::j~p1~ pe_)~--~
l mus! be a Initial route for minimum vf LRWS l 5 ft east of SW dilut1011 rrt~J.,..~kJ::: fl.r-_'r discharge flow into the r--fl,~ ~ Hose tunnel: discharge pipe EC 400577 Prepared By: ~ J;/6,. Date: {-~-I'( Page 6 of%11 '('~'-
u-* recirc 1ine, 3' Existing 315" access manway J 4~~---1fEast I West reci rc.:suc:tion hne. sample lines and pipe to CW tunnel future pull rope ioc.ation
---- 1\ "GRATINC&
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)£ ~ ' minimum of 5 ft past dilution point SEE_..... ..
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- Page 7 of rL
*1M-1O1 Mark Up for instalfation clarity .. ,L
, Initial LWRS Discharge Hose rou e. Up through Pre~ared by: ~~?; Date: 1-2'-1~ CW Acess manway and then back down to open Reviewed B: ~ - ~~ ~fLl/L,o/s CW d"scharge vaive. Secured at top ~o it can be retrieved at a later date for future re-routing . Must Hose Gang route be 5 ft past dilution point r
~ 112. Date: /-z-C -ts*' Reviewed By: _ _ _ _ _ _ Date: _ __
Page 7 ofJZ'j I rv EC 400577 Prepared By:
Bill OfMaterial Job Name: _LRWS Hose Extension in U2 CW Tunnel Requestor~ _Stan Mastalerz/ Lee buBois~------ Work Order#: _01801664 Purchase Order#: _ _ _ _ _ __
~~ ~~~ .
Activity#: EC#: 400576 I 400577 Item Description Size Item# Vendor Substitute YIN QTY PRICE COMMENTS Hose Recirculation, &' 75 psi minimum working pressure. 6" Spiraflex Red Goodyear N 500 May come in shorter Goodyear Spiratlex Red Medium Duty Medium Duty ft lengths, typically 300 ft, this is acceptable. min Hose LRWS Discharge, 3" 100 psi minimum working 3" Versiflo 150 Goodyear N 600 May come in shorter pressure and vacuum.rated. GoodyearVersiflo 150 ft lengths, typically 100 ft, this is acceptable total Hose contingency, 3", 100 psi minimum working pressure 3" Versiflo 150 Goodyear N 600 May come in shorter and vacuum rated. Goodyear Versiflo 150 ft lengths, typically 100 ft, this is acceptable total Hose Sample #1, 1-114", 100 psi minimum working pressure 1-114" Versiflo 150 Goodyear N 450 May come in shorter and vacuum rated, Goodyear Versiflo 150 ft lengths, typically 100 ft, this is acceptable min Hose Sample #2, 1-1/4", 100 psiminimum working pressure 1-1/4" Versiflo 150 Goodyear N 300 .May come in shorter and vacuum rated. Goodyear Versiflo 150 ft lengths, typically 100 ft, this is acceptable min Hose Sample #3, 1-114", 100 psi minimum working pressure 1-114" Versiflo 150 Goodyear N 150 May come in shorter and vacuum rated, GoodyearVersiflo 150 ft lengths, typically 100 ft, this is acceptable min Hose couplings, 6", shank to shank, Brass, Steel or SST 75 6" Mcmaste y 2 psi minimum working pressure. r Carr, Goodyear or similar Hose couplings, 3", shank to shank, Brass, steel or SST 100 53605K15 or . Mcmaste y 10 psi minimum Working pressure 53805K67 or r Carr or
~:~K.3 6 0~. similar Hose Coupling, shank to shank, 1-1/4" Brass, steel or SST 1-1/4" 53605Kll or Mcmaste Y 8 100 psi minimum working pressure 53605K64 or r~rr or 53605K~r(? i / 7* / ,,
ac 400577 Prq>ared By: L, J;Vi,_ Date: f- Z. <>16' teage 8 of~ I . I 1'~ '-'
-- 53605K33'or' sitJtllar similar Cam and groove coupling Plug with shank connection. type #3x 52155K146 or Mcmaste y 1 E. #3 coupling by 2" hose. Brass, Steel or SST 100 psi 2" Similar r Carr or minimum working pressure similar Cam and groove hose coupling type C sockets with shank #3x 52155K37 or Mcmaste y 1 connection 3" hose by #3 coupling with locking levers. 3" 53015K37 or r Carr or Brass, steel or SST. 100 psi minimum. working pressure similar similar Low profile Hose Band Clamps/center punch hose clamps %"x 5655K29 or McMaster y 100 May come in multiple %" x 7"(ntln inside diameter) Galvanized carbon steel or 7" 5655K49or Carr or piece pieces per vendor PN SST 5655K28 or siniilar smin 5655K48 or similar Heavy Duty Ratchet Action Banding tool 14 5657K.42 or McMaster y similar Carr or similar PullRope, Low-Stretch Polyester, Minimum strength 4000 :}"or 3789T19 or ., McMaster y 600 lbs. 3/4" Extra-Strength Double Braid or 1" Lightweight 1" 8878T77 or Carr or ft Blend or similar similar similar min Contingency Pull Rope, Low-Stretch Polyester Minimum t" or 3789T19 or M;cMaster 600 ..
strength 4000 lbs. %" Extra-Strength Double Braid or 1" 1" 8878!77 or Carr or ft Lightweight Blend or similar similar similar min Special tooling. Capstan Rope Winch/puller. May be able to 1500 v* 2 rent. Not permanent part of Installation. As determined by lb pull D&D and dive contractor. min Misc pWl hardware (i.e. hose/cable support grips; Kellem grips, shackles, rope pulleys, etc.). Not part of permanent installation. Not permanent part of installation. As determined by D&D and dive contractor.
- .c 400577 Prepared By: nate: 1-zwt(
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Revievved By -:hf.~ . cf~ Date tJ;/21/J.a/s EC400577 P~eparedBy: ~ iJ../2.;v Date: /-U.* J? ReviewedBy: _ _ _ _ _ Date: Page}.fof)Z, v ---
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3.," Hose from LRWS
.................ii M-49 Sh.t . 1 (E-10) f 1/T
- 3/4~ RED.
Hose Gang 6 .. ~ 3"' and three 1-11.2** for recirculating., flushing/ disch.arge suction and
* *s ampling respect1vely _
...... sample hoses 114, 112 and 3f4 down tunnel 12 EC*N 400577 ~~~ ~
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, ~DCMI I
*-31 Mark Up ~.........
repared y
~ f)ftu-Date: 1-2G-is- Hose en*d at Re~wed 1 y: dilution point r Pt tzr:J-fi,._,
Date: ~~21/-?'/s-EC4005*~~~_.......!!!!il!f"lll!I~----__. Page of.JZ: v-i/ /{ ~
January 26, 2015 In reply refer to CZE-15-001 To: Anthony Orawiec
Subject:
Zion Station, Unit 2 and Common Exempt Change No. 400576 Liquid Radioactive Waste System (LRWS) Release Hose Extension from Unit 2 (U2) Turbine Building(TB) Service Water(SW) Standpipe to U2 Circulating Water(CW) Discharge Valve House The Engineering Department has revi~wed the subject Exempt Change in accordance with ZAP 510-02C and the applicable Zion Solution Quality Requirements. The applicable Design Input Requirements are discussed in this letter. System Code: WO, SW, CW LRWS effluent has been discharged into the Unit 2 (U2) CW Discharge Tunnel on the West end of the tunnel. The discharged effluent has boron in* it. The Environmental Protection Agency National 'I ) Pollutant _Discharge Elimination System (NPDES) Permit has a limit of l part per million (PPM) of boron for lake discharge. The current LRWS effluent release point on the west end of the U2 CW has added borated water to the U2 CW Discharge Tunnel that will need to be diluted prior to release to the lake. The current release point does not support the D&O schedule if the effluent discharge point remains on the west end of the tunnel due to the increased time for releasing borated water in the tunnel. The milestone for isolating the U2 CW Discharge Tunnel outlet Isolation valve is 1/1/2016.* Resofutlon To minimize the further addition of LRWS effluent into the Unit 2 CW Discharge Tunnel extend the LRWS effluent discharge hose from the west end of the tunnel and route it to the east end of the tunnel. The hose extension will be routed in the U2 CW Discharge Tunnel and the effluent release point will be placed past the dilution source near the U2 CW Discharge Isolation Valve. This will. min.imize future LRWS effluent from being released to the U2 CW Discharge Tunnel. This will shorten the duration to remove the current LRWS effluent in the tunnel while still meeting the TB demo and tunnel FSS milestones. Description of Change: This exempt change will extend the LRWS effluent discharge hose from the west end of the U2 CW
, Discharge Tunnel to the east end of the U2 CW Discharge Tunnel. This will place the LRWS release location past the dilution source flow therefore reducing the probability LRWS effluent from entering
the U2 CW Discharge Tunnel. Contingency hoses and pull rope will also be Installed for future use if required. Exempt Change Design Packace: The design for this exempt change will be contained in ECN 400577 and is issued "F~r Construction" by this letter. 10 CFR 50.59 Evaluation I Decommissioning Impact Evaluation: A 10 CFR 50.59 Evaluation was performed in accordance with ZAP 100-06 and is being transmitted along with this letter. This activity can be implemented without prior NRC approval. A Decommissioning Impact Evaluation was performed; and it concluded that the proposed activity is not restricted by 10 CFR 50.82. DSAR I ODCM Impact Review: DSAR Chapters 1 through 6 was reviewed for this exempt change. There is no impact on the DSAR. ODCM Chapters 10 and 12 were reviewed for this exempt change .. There is no impact on the ODCM.
) ""Applicable Codes and Standards:
This exempt change shall be installed in accordance with Zion Specification X-3646, which is the general work specification for mechanical work; as well as applicable site, vendor, and corporate procedures. Installation requirements identified in ECN 400577 supersede Specification X-3646 specifications. Alternate materials and standards are allowed per ECN 400577 and are justified in TR-002-2015 Installation Schedule I Outage Requirements: Installation of this exempt change does NOT require an outage; and therefore will be scheduled via the site work schedule process. Technical Specification Changes: The existing Technical Specifications do not require revisions as a result of this exempt change. ODCM Changes: The existing ODCM does not require revisions as a result of this exempt change. )
ALARA I Fire Protection Review: This exempt change is not being performed In a radiological area. An RWP will not be required for this exempt change. There are minimal additional combustibles being added. The combustibles being added are mainly located under water. As such there is no impact on the Fire Protection Report. Impact of Pending Modifications or Temporary Alterations: There are no other pending design changes that are impacted by this installation. There are no pending changes against affected design drawings that have an impact on this activity. Other Considerations j Engineering considerations are documented in TR-002-2015 and are found to be acceptable. Construction Drawings; } Construction is authorized to proceed in accordance with ECN 400577. Identification of the Installer: D & o will perform this exempt change. D&O will have to contract for diving services to perform diving activities. Operating Procedures: No changes are required to existing Operating Procedures. No new Operation Procedures are required. Training Requirements: None Testing Requirements: A functional leak check should be performed to verify system tightness for portions of the new hoses outside of the U2 CW Discharge Tunnel. Th!s may be completed with a leak check or a hydro. A hydro ) pressure of 100 psi is acceptable.
Operating Requirements: None Technical Review: The LRWS and WD system is Important to the Defueled Condition (ITOC)j therefore this modification is subject to a Technical Review in accordance with the requirements ofZAP 500-08 and the ZNPS A Technical Review was completed under TR-002-2015 and found to be acceptable. If there are any questions or comments regarding this Exempt Change, please contact Lee DuBois at 224-789-4065. Prepared By: Date: }. (.~ Lee DuBois D & D Project Engineering Approved By:~/,/) £f?;f.. Date: . ~@&t~ Donald F. Roth D & D Engineering Supervisor cc: MAL ECN 50.59 Central File 1 1 1 Tara Pratt original original original Work Planning 2 2 2 Tony Orawiec 1 1 1 .J
TECHNICAL REVIEW LITTER TR-002-2015 To: Anthony Orawiec Decommissioning Plant Manager Zion Station
Subject:
Extending Liquid Radioactive Waste System (LRWS) discharge hose from west end of Unit 2 (U2) CW Discharge Tunnel to the east end of the U2 CW Discharge Tunnel. The purpose of this letter is to document the Technical Review of the Desfgn Change Package for Exempt Change EC# 400576 and associated ECN 400577. Summary: This Exempt Change provides the details for the following:
- 1. Extends the existing LRWS discharge 2" hose* with a 3" hose extension from west end of the Unit 2 CW Discharge Tunnel to the East end of the U2 CW Discharge Tunnel.
- 2. Install contingency hoses for sampling and recirculation of the U2 CW Discharge Tunnel. A 6" hose will be installed as a recirculation hose. Install a 3" hose that could be used as a
*flush/recirculation or west end suction release hose. Install three 1-1/4" hoses that could be used to sample the tunnel.
- 3. Install a contingency pulling rope if additional hoses need to be pulled into the tunnel in the future.
There are multiple design considerations not covered under other modification documentation. Mechanical Design Considerations The design flow rate needs to be determined as well as the hose length and size. Hose lengths-324 ft horizontal Center line (CL) of outlet water box to CW discharge house Ref M-100 27 ft horizontal CL outlet water box to west standpipe. Ref 8-100 110 Ft vertical down then vertical up, 2 x (592' TB elev -537' tunnel bottom) Ref M-101 so ft additional hose to allow routing out of cw discharge house manway into cw discharge valve vault (contingency length) 200 ft from Unit 1 LRWS pump discharge to Ul LRWS pump discharge to west CW stand pipe. Estimate based on M-100 600 ft (new hose) 800 ft (for hose sizing evaluation purposes) Page 1 of7
TECHNICAL REVIEW LETTER TR-002-2015 Flow rate sizing for LRWS The allowable release rate determines flow rates. Maximum Flow Rate The boron release rate is much lower than the radioactivity release rate so it is the driving factor. The allowable release rate is det~rmined via lppm boron at the outfall. Unit 1 cavity water is at "'356 ppm 12-18-14 analysis value SFP boron concentration is> 2000 ppm Assume 12,QOO gpm Service Water (SW) Dilution Pump Release rate can be up to 34 gpm of borated water.. Size hose for 35 gpm Hose Sizing for LRWS Discharge At 35 gpm the LRWS lake discharge pump has 110 ft of head or 47 psig Hose losses at 35 gpm per 100 ft of hose (Goodyear tables) 2" 1.18 psi 2. 7 ft
'e-1/2" 0.40 psi 0.9 ft
. ) 3'~ 0.17 psi 0.4 ft Loss at 800 ft of hose for only the hose at 35 gpm 2". 22 ft 2-1/2" 7 ft 3" 3 ft To account for other fittings (valves, flow meters, pipe fittings) conservatively double the pressure loss from the hose 2" 44 ft 2-1/2" 14 ft 3" 6 ft Recommend using 3" hose. Reason is for contingency we may need to re-circulate the tunnel; a 3" hose will allow faster recirculation. Hose pressure rating for LRWS Discharge This hose will be in the tunnel and protected by the tunnel from personn~I, equipment and incidental contact. The rating on the hose needs to be a minimum of the pump dead head rating for industrial safety concerns just in case the hose is blocked or crimped. Pump dead head rating is 110 ft. The static head from the top of the tank to the bottom of the tunnel is 80 ft (top of tank conservatively assume 617' -537' bottom of drained tunnel M-101). Total static. head is 190 ft or 83 psi. Hoses typically have a Page 2of7
TECHNICAL REVIEW LETTER
.TR-002-2015 )
burst pressure of 3 times the operating pressure rating (Ref Goodyear www site). Recommen~ a hose rating of 100 psig minimu~. Hoses currently being used on site per walkdown: Manufacturer Model Pressure(PSl)(3") Vacuum(in HG) Weight/ft(3") Goodyear Con-Ag 100 N/A 1.76 Goodyear Versiflo 150 29 1.44 Goodyear Plicord 150 N/A 1.37 Goodyear Gorilla 500 (2" max .size) N/A 1.22 Utilize Goodyear VersiFlo. This hose meets the pressure rating. This hose also meets a vacuum rating as a contingency to re-purpose the ho~e to re-circulate and/or dilute the CW tunnel in the future. All fittings need to be rated for a minimum of 100 psi working pressure.
- Contingency hoses An additional 3" Versiflo contingency hose should be pulled into the tunnel. This hose may be used for dilution source from the east side of the site via the SW dilution pump tap valve~ The current SW dilution pump could be used to supply water via this hose. This will allow the removal of water from
) west to east wheri a LRWS discharge in not in progress. The hose coulcf also be used for recirculation, sampling or as a discharge source on the west end of the tunnel if they wanted to place a pump on the east side of the site allowing less interferences for 0th.er D&D activities. If using this hose from the existing SW dilution pump then a flow meter shall be installed to limit the flow to allowed discharge rates per the LWRS. Because this hose could be used in a pump discharge or suction condition the Versiflo hose is recommended. As a contingency for future tunnel recirculation install a. 611 hose. The hose will only be used for recirculation so the recommended hose is a Goodyear Spiraflex Red (medium duty). This hose is rated for 100 psi working pressure. Referencing Goodyear hose pressure loss table a 6" hose has a head loss of 0.79 psi per 100 ft at 500 gpm. For a conservative 600 ft hose run in the tunnel the loss would be approximately 5 psi or 11 ft of head. Based on review of typical 4-6" de-watering pumps (i.e. Flygt) we should be able to obtain a minimum of 500 gpm recirculation. The tunnel conservatively has 800,000 gallons of holding capacity; at 500 gpm the t~nnel turn over time is approximately 27 hours. The hose fittings need to be rated for a minimum of SO psi. As a contingency for water sampling at intermediate tunnel locations; utilize 1-1/4" Goodyear Versiflo hose because it has a vacuum rating. The vacuum rating will allow it to be utilized on sample pump suction(s). As a sampling contingency up to 3 sample hoses at approximately 25%, 50% and 75% down the tunnel length. A minimum of 1 sample hose at approximately 50% down the tunnel should be run. Do to the potential, to process water out of the tunnel after access to the TB is not available the sample hoses should be pulled above grade on the east end of the tunnel. Page 3of 7
TECHNICAL REVIEW LITTER TR-002-2015 As a contingency an extra pull rope should also be routed through the tunnel and staged for future use. The pull ropes should be tied off on each end for future access. In conclusion, the proposed Exempt Change does not affect the design or the design function of the WO System; as well, the proposed Exempt Change does not affect the ability of the LRWS to perform that design function. Prepared By: -: :Le~e:. :D=u=B=o=is=- ~-----~_..:;.~-~-*~---
...... Date: 01/26/2015 Required Review Disciplines:~ 01~ 9 Engineering Supervisor
/-U:-15 Discipline Date
) Discipline I Concur and Approve: _c4_.,..-=+- E__________ 7 _ Deco~g Plant Manager Distribution: Decommissioning Plant Manager Operations Supervisor Engineering Supervisor SRC Coordinator Master File ) Page 4of7
TECHNICAL REVIEW LEITER TR-002-2015 ) Supporting Vendor Data GENERAL INFORMATION __ ,__ ----'-- o..~ ..GOl C.4 l ~ 00~ 3 :12 UI 11.42 l.!i .AX*S n~ z~s I Oil
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~500 3.56 1!00 *OJ 2JOC* us H:;t1. Tl>r ortmire ~11.,11Pri111~ lrl i Jiq,Jld l~1n1 l~1oi;uch I ~av. d11pen*s.tri !Ill! 1atl"ol ft...,.,_ Ille: V15'11silf,r llir fi~111d . lhr 1-tsa I.I>., ~h1umo:t~.nns *Hhc ~ube 1nd 1hc hov.~nch Tltir ct art s1* r,11Uh~ rt.ltti011shi11 l:clwticr. tlllHI fbw. LI> .. llld prnHrr Iva fuT
""*ter tt ~"r wtll 1 lli$etsi~* C'1 one tentipols* Tht. preunl'l! k lllree.IJ PMDIW'tlonlll to 'Ille il'ftet* of the"'" * ~. tire mu1tt.v."'
c:29 ::>111JJl~*atmdld lit us! al i:r11por110~1. Lf *. 1111 press1111 dre::i rs 50 '8!l af ,,_...se IEftllh is t~U tlull fir !OD 11!1!1 Page 5of7
TECHNICAL REVIEW LETTER TR-002-2015
)
SPIRAFLEX RED MEDIUM DUTY
-i&iiiAmt~i11m-clu1J
- antJallOI: fir distllarie appucatklns In minln£. construction, l!KluSUY. agrJc:uttum aJKI i nmtn& !!IVk:e. Ulllltlll an 11111 cll&mlcal a*t!tim II COllSlllC1Jn 11IBE: Blatl Pliml.'6 .liitde tUbllertulN!
I I I ClftR: ltd Plill'li£, MSHA 2G-1.4C/15 II mm:unrRE: -llTF to 150'f {-23"C to 65"C) I I IUIDlll: ExllllPflr. ~J'i' Spnfletb Red r (50.fl mml 150 psi WP (LOO Mila}, Flame ReslstBnt, USMSHA26-lACllfi. Made in USA I COOPUH$: 11111-SllCMIZR Cootact ttttinl mal!Ufactun!r f<< proper fitting liCOmmenelatlOll ancl coupling procedUff.
.. _ _ run mi""""..,.,,,_,, ,...,"'1d*D.
) l~~~-D-Rotk~Cl~DES-*_.-~-7-~-~~~~~~~~~~~~~~~~~~~~- 2.24 56.9 63.5 2.79 70.9 150 1.03 0-41 0.61 3 762 3..29 83.6 125 0.86 0.46 0.68 4 101.6 4.32 109.7 100 0.69 0.73 l.Cl9 6 152.4 6.40 162.6 100 0.69 1.18 1.76 Note: Working pressures ar& rattd at 72'f. Page 6 of 7
TECHNICAL REVIEW LITTER TR--002-2015 I
- f
' I, VERSIFLQ** 150 WATER S&D Protluct Spectncations tmn111CJ*
'RE: Black. \le'si~ Sjntflett ndtber Clla Bladt. \e'sipTif ~ 111~ (Wraptied 1inish) tm"HCEll;EWJ: P~~ Bf~ filbric with will! lleliJ:
1Elftllllm'.: -3fUr;2a&"f {-3lt m*!l3"C) PACIMllli: 5.12~2i wrr -kmgths.calec!' and pol)'lirippecl 5'1-QB. tJlstmn lellgtfr5 8U11D1H {Sf'IJWJ: fxam;tfe. C:11r1d~ \!r<""'llo'" i 5G Waffr Suctioo &Dlstharp COi~ Cuir!act fitti11g manufai:tllrer far proper iittinf recommendation and r;1111piing pn.:Edu~. llllli-$JOl:<<ISIZ£S: For :spei:illl p!Ollm:tiim run minimum requiremen1s, Sl!I! Appentfix 0. H4 31.S Hi3 41.4 HB 29 737 0.53 0.79 l~ 38.l 1.87 47.5 150 1.00 4 102 29 731 {).65 fJ!J1 l 50.B 2.~ 00.7 'D50 1.03 7 178 29 737 0.87 l.29 2~ 53.5 2.89 73.4 150 UB 10 254 29 731 1.00 1:61 3 762. 3.4.?. 85.9 t50 1.03 14 356 29 737 l.44 2.14 4 101.6 4.45 na.o 150 1.03 18 457 29 737 2.00 zgg cao 6 8 10
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12 JCT.i.O 1a.23 I 336.D 100 l.m 72 18>0 29 737 18.70 21.90: 14 400.0 i5.$7 396.0 150 l.D3 84 2100 29 7"37 25.10 31.40 Page 7of7
ZAP-100-06 Revision 25 Information Use ATTACHMENT E: 50.59 APPLICABILITY REVIEW FORM Activity/Document Number: EC 400576 and ECN 400577 Revision Number: o Address the questions below for all aspects of the Activity. If the answer Is yes for any portion of the Activity, apply the Identified process(es) to that portion of the Activity. Note that it is not unusual to have more than on1:1 process apply to a given ACtivity. See Section 4 of the Resource Manual (RM) for additional guidance. I. Does the proposed Activity involve a change:
- 1. Technical Specifications or Operating License {10CFR50.90)? . X NO YES See Section 4.2.1.1 of the RM
- 2. Conditions of License Quality Assurance program (10CFR50.54(a})? X NO YES Security Plan (10CFR50.54(p))? )(NO
- YES See Section 4.2.1.2 of the RM
_x_ NO
- YES Emergency Plan (10CFR50.54(q))? -
- 3.
- Specific Exemptions (10CFR50.12)? _X_NO YES See Section 42.1.5 of the RM
- 4. Radiation Protection Program (1 OCFR20)? . . x_ NO - YES See Section 4.2.1.6 of the RM *
- 5. Fire Protection Program (applicable UFSAR or operating license _X_NO YES See Section 4.2.1. 7 of the RM condition)? -
- 6. Programs controlled by the Operating License or the ,Technical Specifications (such as the ODCM). _x_ NO - YES See Section 4.2~ 1.7 of the RM
- 7. Environmental Protection Program _X_NO YES See Section 4.2.1.7 of the RM
- a. Other programs controlled by other regulations. _X_NO YES See Section 4.2.1 of the RM
)
II. Does the proposed Activity involve maintenance which restores SSCs to their original condition or involve a temporary alteration supporting . maintenance that will be in effect during at-power operations for 90 days _X_NO - YES See Section 4.2.2 of the RM or less? l Ill. Does the proposed Activity involve a change to the:
- 1. UFSAR (including documents incorporated by reference) that is excluded from the requirement to perfonn a 50.59 Review by _x_ NO - YES See Section 4.2.3 of the RM NEI 96-07 or NEI 98-03?
- 2. Managerial or administrative procedures governing the conduct of _X_NO YES See Section 4.2.4 of the RM facility operations -
- 3. Procedures for performing maintenance activities (subject to 10 CFR
_X..;.NO YES See Section 4~2.4 of the RM 50.65(a)(4 ))? -
- 4. Regulatory commitment not covered by another regulation based _x_ NO - YES See Section 4.2.3/4.2.4 of the change process (see NEI 99-04)? RM IV. Does the proposed Activity involve a change to the Independent Spent _X_NO
- YES See Section 4.2.6 of the RM Fuel Storage Installation (ISFSI) (su.bject to control by 10 CFR 72.48) -
- v. Does the proposed Activity Involve a change to the Packaging & _x_ NO YES -
Transportation of Radioactive Material? (subject to oontrol by 10CFR71) - Vi. I s the proposed activity a Decommissioning Activity that does NOT _X_NO YES require a 50.59 Scref:)nlng, as described in Attachment 1 of ZS*EG-100? - Check one of the following: o If all aspects of the Activity are controlled by one or more of the above processes, then a 50.59 Screening -is not required and the Activity may be Implemented In accordance with its governing procedure. X ff any oortion of the Activity is not controlled by one or more of the above processes, then process a 50.59 Screening for the portion not covered by any of the above processes. The remaining portion of the activity should
. be implemented in accordance with its governing procedure.
his Exempt Change affects systems discussed in the DSAR that are Important to Defueled Condition.srgnoff: _// ~ 50.59 Screen& 50.59 Ewfualor: ?,;"",.,._ r: ~"'-"'"~ Sign: /<-,,./.~~' d/1 ..t11.L*/'$ (Circle (Print name) (Signature)
ZAP-100-06 Revision 25 Information Use ATTACHMENT D: 50.59 REVIEW COVERSHEET FORM* Station: Zion Activity/Document Number: EC 400576 and associated ECN 400577 Revision Number: O
Title:
Liquid Radioactive Waste System CLRWS) effluent dlscharae hose extension in Unit 2 Circulatfng Water Discharge Tunnel. NOTE: For 50.59 Evaluations, infonnation on this form will provide the basis for preparing the blennlal summary report submitted to the NRC in accordance with the requirements Of-10 CFR 50.59{d)(2). Description of Activity: (Provide a brief, concise description of what the proposed activity involves.) To minimize the further addition of LRWS effluent into the Unit 2 CW Discharge Tunnel extend the LRWS effluent discharge hose from the west end of the tunnel and route it to the east end
)f the tunnel. The hose extension will be routed in the U2 CW Discharge Tunnel and the ~ffluent release* point will be placed past the dilution source near the U2 CW Discharge solation Valve. This will minimize future LRWS effluent from ~eing released to the U2 CW Jischarge Tunnel. This will shorten the duration to remove the curr~iit LRWS effluent in the
.unnel while still meeting the TB demo and tunnel FSS milestones. u *
)on for Activity:
- _ .;USS why the proposed activity is being performed.)
mnimize LRWS effluent being deposited in the U2 CW Discharge Tunnel. ffect of Activity:
)iscuss how the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.)
his activity does not change any descriptions in the DSAR and ODCM. llmmary of Conclusion for the Activity's 50.59 Review: irovide justification for the conclusion, including sufficient detail to recognize and understand the essential:arguments leading the conclusion. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment
~quest, as applicable, is. not required.)
50.59 Screening will be' required because the LRWS is described in the DSAR. tachments: tach all 50.59 Reviewforms completed, as appropriate. OTE: if both a Screening and Evaluation are completed, no Screening No. is required.) rms Attached: (Check all that apply.) Appllcablfity Review x 50.59 Screening 50.59 Screening No. 2015-008 Rev. 0 I
.J 50.59 Evaluation 50.59 Evaluation No. Rev*
ZAP-100-06 Revision 25 Information Use ATTACHME1'1T F: 50.59 SCREENING FORM 50.59 Screening No. ____2=0....1__s..... -oo~s______ Rev. No. __.o__ Activity/Document Number: Exempt Change EC 400576 and ECN 400577 Revision Number:____o~__,_
- r. . 50.59 Screening Questions (Check correct response and provide separate written response providing the basis for the answer to each question) (See Section 5 of the Resource Manual (RM) for additional guidance):
- 1. Does the proposed Activity involve a change to an SSC that adversely affects an UFSAR YES _)(_NO, described design function? (See Section 5.2.2.1 of the RM)
The relocation LRWS discharge point Is within the licensing basis design function as described In the DSAR section 4.5.2 and Figure 4-1 The ODCM Section 10.2 does not describe where within the CW tunnel the LRWS discharges. The ODCM refers to the DSAR. The LRWS Is not discussed In the Technlcal Sj,eclflcatlons: Design Basis (LRWS excerpt from DSAR 4.5.2) The Liquid Waste Systems are designed to coilect, store, process, monitor, and dispose of liquid radioactive waste from the statjon. The principle design criteria. ) for the Liquid Waste Systems are as follows:
- 1. Ensure that the quantities of radioactive waste discharged from the plant during decommissioning are as low as practicable and, in any event, well within the allowable concentration limits; and
- 2. Limit the inadvertent release of radioactive material from the plant so that the resulting radiation exposure to the public is as low as practicable and, in any event, well within the allowable concentration limits.
The allowable concentration limits described above are defined as 1Otimes 10CFR20 limits for batch releases from the Lake Release Tanks (Boric Acid Tanks)..
- 2. Does the proposed Activity involve a change to a procedure that adversely affects how UFSAR YES _X_NO described SSC design functions are performed or controlled? (See Section 5.2.2.2 of the RM)
There are no procedures that are affected by the re-route of the hoses.
- 3. Does the proposed Activity involve an adverse change to an element of a UFSAR described _)'ES _X_NO evaluation methodology, or use of an alternative evaluation methodology, that is used in establishing the design bases or used in the safety analyses? (See Section 5.2.2.3 of the RM)
DSAR Section 4.5.2 does not Identify any methods of evaluation. Chapter 5 accidents do not Identify a LRWS release or spill as an accident that is evaluated. No methods of evaluation are changed.
ZAP-100-06 Revision 25
*Information Use
- 4. Does the proposed Activity involve a test or experiment not described in the UFSAR, where an YES _}(_NO SSC is utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is Inconsistent with analyses or descriptions In the UFSAR? (See Section 5.2.2.4 of the RM)
The proposed activity does not Involve an experiment or a test.
- 5. Does the proposed Activity require a change in the Technical Specifications or Operating License? YES _}(_NO (See Section 5.2.2.5 of the RM)
This proposed activity does not Involve a change to the Operating License or Tech Specs. II. List the documents (e.g., UFSAR, Technlcal Specifications, other licensing basis, technical, commitments, etc.) reviewed, including sections numbers where relevant infonnation was found (if not identified in the response to each question). DSAR Chapters 4 and 5 ODCM Section 10.2 Ill. Select the appropriate conditions: If all questions are answered NO, then complete the 50.59 Screening and implement the Activity per the applicable X governing procedure. If question 1, 2, 3, or 4 is answered YES and question 5 is answered NO, then a 50.59 Evaluation shall be performed.
- If questions 1, 2, 3, and 4 a~ answered NO and question 5 is answered YES, then a License Af!lendment is required
) prior to implementation of the Activity.
- If question 5 is answered YES for any portion of an Activity, then a License Amendment Is required prior t9 implementation of that portion of the Activity.. In addition, If question 1, 2, 3, or 4 is answered YES for the remaining portions of the Activity, then a 50.59 Evaluation shall be performed for the remaining portions of the Activity.
fV. Screening_j!gnoffs: ~/ 50.59Screener: /#""111.r S. /d~.lilJo# Sign:~~.-.t Date:P/ J.2/JJd/S (Print name) (Signature
*
- 50.59 Reviewer: :[::kµA.L.P ~ l17J:JlS (Print name)
)
ZAP 100-09 Revision 4 Information Use ATTACHMENT A DECOMMISSIONING IMPACT EVALUATION Activity: Exemot Change 400576: Extension of LRWS Discharge Hose from West End of Unit 2 CW Tunnel to East End. ECN 400577 (Work Order No., Procedure No., On Site Review No., Design Change No., etc) TRACKING#: 50.59 Screening 2015-008
- 1. Does the proposed decommissioning activity result in any of the following: *
- a. Foreclose the release of the site for possible unrestricted use;
[ ] YES [x] NO Provide justification: The proposed activity does not increase the potential for the spread of radioactive contamination. The controls in place for the LRWS discharges ) cover this control. The proposed activity will not change the design function of the LRWS as discussed in the DSAR; and the LWRS will still be capable of performing its DSAR design function.
- b. Result in significant environmental impacts not previously reviewed;
[ ] YES [x] NO Provide justification: AU- of the work associated with the proposed activity will be performed within the requirements of the DSAR and the NPDES permit.
- c. - Result in there no longer being reasonable assurance that adequate funds will be available for decommissioning.
[ ] YES [x] NO Provide justification: The proposed activity is regarded as a minor design change; and does not adversely impact the budget. The proposed activity will be funded by the
- decommissioning trust fund.
) 9of10
ZAP 100-09 Revision 4-lnformation Use ATTACHMENT A DECOMMISSIONING IMPACT EVALUATION (Continued) Activity: Exempt Change 400576: Extension of LRWS Discharge Hose from West End of Unit 2 CW Tunnel to East End
- 2. Review the answers to Step 1.a-c. !f the answer to any of the questions is YES, Then the actiVity can NOT be completed, without prior notification to the NRC.
NOTE In taking actions permitted under 10CFR50.59 following submittal of the PSDAR, the licensee may perform activities inconsistent with the PSDAR, including significan.t schedule changes or significant cost increases, provided prior written notification is made to the NRC, as well as a copy of the notification to the State of Illinois.
- 3.
- Is this activity incol'J,sistent with those actions described in the Post-Shutdown ~
J Decommissioning Activities Report or cause a significant schedule change or c0st increase? [ ] YES [x] NO lf the answer is YES, Then notify the NRC and the State of Illinois prior to performing the activity. jf the answer is NO, Then proceed without notification. Provide justification:
- This exempt change is a minor design change activity that does not conflict with any of the information provided in the DSAR. It has no impact on the decommissioning trust fun~.
Implement Changes - Based on this evaluation, I have determined that the proposed activity is not restricted by 10 CFR 50.82.
- P7rint name' '1/ln.11.s S: ,C:,,,.,t,,.4 Discipline: //,fr *
~- ../. if'~tf~ o,,.,.,,.,;e'/' . e,t, .2*/S Preparer Signature Date
- 4. Review - The reviewer agrees that the proposed activity is not restricted by 10 CFR 50.82.
)
- z;~~rm*: Vr:::'gil '.O,pM-P r:.:- R..'
Discipline: A. Ci l/Z1!J/Z(){5 J eviewer Signature Date 10of10
\ ZionSolutions LLC ZS-2016-0042: Attachments ATTACHMENT 3 ECN# 400657 Installing additional liquid effluent discharge flowmeters
Exhibit A NEP-08-01 Revision 1 Engineering Change Notice (Part 1) ECN No. 400657 ISSUANCE: 1:8:1 FOR CONSTRUCTION D FOR COMMENT Page: _1_ of .J.l_ Station: ZION D Safety Related Design Change No. 4006~6 Affected Unit: 00 181 Non-Safety Rel!lted Project No. (ifappl): NA Changes to a previously Approved ECN 181 D Regulatory Supp ID No. (ifappL): NA System: WD Description of Design Change Request: This ECN adds an additional flowmeter to the new liquid Waste Disposal system. Equipment identified as ABANDONED in this ECN will be de-energized and renioved via deconunissioning work orders. Reason for Design Change: Change 8Dd action required (Provide n:ason fur change, specific actions rcquiml. auach SllppOrting documents, as applicable). The current liquid waste system uses a flowmeter that has a minimum calibrated flowrate of 5 gpm. This ECN will allow
- the discharge of liquid waste at flowrates less than 5 gpm.
INTERFACING COMMENTS by: Design. Group or Discipline Name of Commenter (Printed) Signature of Commenter Date CorNC Elect./I&C Mechanical Structural Others Others Others Prepared by: A R. Adams 'J- . Reviewed by: t,,,OA.& ~A or Ne Approved b;.7~..11/?}Jj:;J?J
'Z.J t- 1'~'10 Date:*- ~/~LS Date: 2-~-lS Date:
All affected design documents revised by (date): verified by: Date:
Exhibit' A NEP-08-01 Revision 1 DESIGN CHANGE DOCUMENT - AFFECTED DOCUMENT LIST (Part2) Print Dllte: 02/18/~0lS BC NUmbe:.r : 0000400657 000
~
~Exelon.
s-:..tus/:>at.e : REGISTER 01/~l/2015 Facility : z:w 'I'YJ>e/ft.i:J- t;}'Pe I DCP NOD . . .
- (JlID,lll.lll,llllllJQtnlllll Pages 2of 13 KW2s MUter RC ':* H Wark. aroup = 'l'e8'10r.u"Y I N outage : .R Alert Groupt Ap.rd Reqd Data ~
wo Recr~ired : Ir.age ~ ,,** J!xp IIiavc Date.: Mv Wk .App'Wi1 Auto-Advil!Wc:e= Y.
.Alt Ref, Pd.Qrit:y r
J!:xpires On 11\1to-1'Sb\Jild :
~ .* :
Caveat .Outst: D*part.:ment : IJia:eipUne I R.esp E?'lg'r : FAlllmLL A LtJXXEN Loc*ticm. : ' 8\lb* ns, !la m! llOeUIUae Sil~ W, !!!f !.£!' ZIN J>KQC M-119S N Y l t'linor Rev: Maj 0% ReV* Updt DUe:
'l'itlei lllAGRAK OF CHEMICAL & VOLUME CONI'ROL: SYS'IEM (CRITICAL CoHTRoL. ROOM DRA zm DWGC* M-49 ;L N y N Minor Rev: Major tcev: Updt Due~
Title:
DJAGRAM OF WASTE D!SPOSAL SYSTEM CLIQUID} MON!TOR >>lD* DI:&POSJU.. SYSTEM ZIH OC "'11 Bqgipment : N/A WJ>OOOSA Minv't' Jtevf Coniponen~ : Majo.r Rev: Bquip. Tag; OY1-WD0005A States leviawe~? N 1~st/B11u Rev 'l'rackable: Inc: K N~ r RBI.BASS: TAN'K l'LON lND:tCA'l'OR ii 'l'Q'DU..!i:ZIR 4 1A ZIN 00 WT.t Bquipmut:. z 'II/A WOOOOU Mina~ Rev: COtapCDen~ ~ Ma'jor Rev; equip. Tag; OJ'l'-W'D0006A st.u~ :Reviewed? 1~ Xl:.8t/Rm1 Rev Trackables m Iner K Jfatne. : RBLBASE TANK FLOW IRDICM'Oll. ii. TODLIZER. # .2A
Exhibit A NEP-08-01 Revision 1 DESIGN CHANGE DOCUMENT - AFFECTED DOCUMENT LIST (Part 2) l'i'int Date: o'/11/2015 JtC Numbllr OC004006S7 000 ..,, .
~"Exelon .
l!l;atus/Date .IBGIS'!EI. 01/21/2015 h.dlit:y ZD Typ~/SUb-typc: DCP M'OD rmm*-**111111*1111 Page: 3of 13 ZIN 00 tt"D BqUipment i v...s l.l16A Minor ltev: CClq10rlent MA'ar :ReV:
&:qi.lip. Tag-: ' OWDJ.11'1\.
Stace: ~v.lewedl' :N 1net./Hn:i Jlev 'l"rR~able: w UK'; N Name I l\EL!AS! 'Tr.mt fi 2A DIBCJ:Wl.QE VLV Zl1i QO WD .
&:qWpmer.t : vi~ L117A Minor Rev*
camponent. : Mar.jar Rcv1
~:ip. 'l'ag1 OHD1.ll 7A Sta.te: :ReVieWed? :. I0&t/R11u uv ~rac:kable1 111 Ir.c1 I\'
Nilll!e 1 Rr...EllS!! TANK tt 1A l)ISCHA.~ V!..V
Exhibit A NEP-08-01 Revision 1 DESIGN CHANGE DOCUMENT - AFFECTED DOCUMENT LIST (Part 2) ECN No.: -.:.40=0=6=-57,___ _ __ Design Change No.: 400656 PageNo.: *4 of ---=-1=-3_ _ Back-Up Calculation Listing (Part2) Calculation/Analysis No. Revision No. Description None
Commonwealth Edison Company Engineering Change Notice
- ECNNo.: ___,4=00=6=-57..__ _ __
Design Change No.: 400656 Station: ZION Affected Unit: 1 & 2 Page No.: 6 of 13 Part4 Construction Support Information MECHANICAL PARTS LIST
*. Substitute parts may NOT be used without Eng Approval
# Item numbers reference the components of the isometric Figures
# DESCRIPTION MANUF. PART#
1 Pipe fitting, Tee, NPT, 1-1/2", SST 150 psi min 2 Pipe 1" Schedule 40 SST 3 Pipe fitting, elbow 90 degrees, 1" SST, 150 psi (min) 4* Valve, globe, SST or Bras~, 1", Milwaukee 590T ~ " NPTends 5 Pipe union, 1" NPT SST 6* l Flow Gauge & Totalizer Turbine Flow Met~ (see below) Valve, Check, 1", npt ends, Mcmaster carr PIN 7 4463K66 or 4708K55 or SST or brass or bronze, 150.psi min working pressure Similar 8 Pipe fitting, Male x female hex reducing bushing, NPT 1-1/2" x 1", SST 9 Pipe, 1-112", schedule 40, SST Pipe* fitting Reducing Bushing Male Mcmaster carr PIN 10 xFemale 1-1/2"MNPTx W'FNPT 4464K155 or 4452K186 or SST similar Pipe Fitting Female x Male street Mcmaster carr PIN 11 90 degree elbow, ~" FNPT x W' 4464K38 or 4453K474 or MNPT,SST similar
.,,.,._. a-~ .z,S Prepared By: A. R. Adamyj&Dedvia email q-- Date: 2-t-a-15 Reviewed By: (.IJ.IJw ~JRA.. Date;:iiiiiiiiiiiiiiiitiiii,.iiii~~'riiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiii-..!/
Commonwealth Edison Company Engineering Change Notice ECNNo.: ___..40=0=6=-57,__ _ __ Design Change No.: __,,4=-00=6=-56"---- Station: ZION Affected Unit: 1 & 2 Page No*.: 7 of 13 Part4 Construction Support Information MECHANICAL PARTS LIST Continued Pipe fitting, redueing coupling, 1 . Mcmaster carr PIN 12 FNPT x W' FNPT, SST 446K534 or 4458K263 or Similar 13 Pipe 1/2", schedule 40, SST 14 Pipe Fitting, Reducing coupling, :MCm.aster carr PIN female x female, 2" FNPT x 1" 4464K548 or 4452K277 or FNPT,SST Similar 15 Pipe fitting, tee, 1", SST Mcmaster carr PIN 4464K53 or 4452K2436 or Similar
*Cameron Flow Meter, Liquid Turbine style,, flow element with element mounted flow analyzer, Nuflo MC-II flow analyzer and flow element; range 0.75-7.5 gpm, standard grade, standard accuracy, gallon totalizer; gallon rate indicator, body material SST, process fluid is water, Process
- range 33 Fto 120F, process pressure 150 psi max, ambient temperature range 32 F to 120 F, 1/2 flow meter with 1" NPT x 1" NPT connections; with dated calibration certificates, flow element part number 9A-100003532 J-t~ ,, "
Prepared By: A. ~Adams signed via .mi Date:._ __.2=--.::.:~::;...-=15"------- Reviewed By: ~ 4c. L, fld .fc Date: tZ-z..f-K
FIGURE 1 Part4 ECN No. 400657 EC No~ 400656 Page _8_ of 13 Prepared By: A R Ad . +,pl~ ~~ ~
*
- ams srgned via ~r "l) a.L.-.*
- .r.>*15 Reviewed By: l, IJ./?tJJ #/i
FIGURE 2 Part4 ECN No. 400657 EC No. 400656 Page _9_ of _13_
-1~ /..CAif, 'l. . Z.1-14" Prepared By: A. R. Adams signed via Mulil-2 13 15-Reviewed By: l.(J..~1/, ~o!JA. 2
- Z,S-"'ltl'
(J Nil 2...
- \fo!ES:
I) (J<! TI Ui' - f)T;1rr1.,,:;f1;.t. 5kc.*tu N z) Fife..!) Ftr up A'.> Af o U.!:f\f: /) FIGURE 3 Part 4 ECN No. 400657 EC No. 400656 Page _10_ of _13_ d""'*... 2 -t-kr' Prepared By: A. R. Adams signed via..e~aU
- Ho 1-!r Reviewed By: LMow (LIJt [. 2f°-tll'
Remove check valve and attached pipe nipples. Discard all three. Replace with pipe FIGURE 4 Part4 ECN No. 400657 EC No. 400656 Page _11_ of _13_
-I.ft: f>* f._. ~'J-lf' Prepared By: A. R. Adams signed via e00 ail 2 13 !1:5
- Reviewed By: &;.,,,oP,4. l. /J,,,,f-tr 2..- 2. !'--~'
Commonwealth Edison Company Engineering Change Notice ECNNo.: ___,4=00=6=5_,_7_ _ _ __ Design Change No.: 400656 Station: ZION Affected Unit: 1 & 2 PageNo.: 5 of 13 Part4 Construction Support Information Note When disassembling hose and flow meter manifolds there is an estimated 15-20 gallons of water that could drain out. For contamination control insure the water can be collected.
~stall Unit 1 low flow ~sgnbly ~#)-lVith ~xis~g flow assemb~y .as sho~ in_ .
Figures 1 and 2 on pageS,K\ndf.' 'fliis~ reqmre disassembly of eX1sting Unit 1 piping; other configurations of installation are allowed with Engineering approval. The Unit 1 check valve located in the Unit 2 Lake Release Room will be removed and a new check valve is installed on the Unit 1 assembly as shown. The configuration control drawings M-49 andM-119Sareonpage~ and~.-
. 8_ ~)fl.
- 2. ~tall Unit 2 low flow ass~bly in RAT~/?.:and ~th e~isting flow ass~~ly as s~own in Fi~ 3 and 4 Oli pagesd md )-0!1this Will require disassembly of existing Unit 2 piping; other configurations of installation *are allowed with Engineering approval. The cqnfiguration control drawings M-49 and M-1195 are on pages)'! and,)1.
. r~.. 13 ~/
l'/S""
'Prepared By: A R. Adams signed via ~-'-~eemil
- 1-k> Date:._ ____.2=-..g.:.::...=15,.__
e.J ReviewedBy: ' - JJI;~ c.._atjo,G. Date: l* 2 fl .. /~
Unit 1
.ORWDOOOS 1VC0330 OWD1117 10PR04 1VC0329 Unit2
< "°""°'
IMUbt1. ( Part 5 ECN No. 400657 EC No. 400656 Page _12_ of _13_ Drawing No. M-1195 Rev. B
"'""'~ Z,'2."J-tr Prepared By: A. R. Adams*signed via email ~ a.a tS -
Reviewed By: '~ £. ~4 z . tzr,,,.r'
~LJ;;i I
I *.i.r' I I ..
. L..,
Part 5 ECN No. 400657 EC No. 400656 Page _13_ of _13_ Drawing No. M-49 Sht 1 Rev. B
-J-~°""' i- z,..,,i-Prepared By: A. R. Adams signed via eirrail 2 i3 i":5-Reviewed By: l. /)fi~/s .A. M+f 2-'L~'l'I
February 13, 2015 Iµ reply refer to CZE-15-004 To: Tony Oraweic
Subject:
Zion Station, Units 0, 1 & 2 Exempt Change No. 400656 Liquid Rad Waste System Code: WD, VC The Engineering Department has reviewed the subject exempt change in accordance with
. NEP-04-02 and applicable Zion *Solutions Quality Requirements. Design Input Requirements (DIRs) as identified in NEP 12-01 have been reviewed and are included in
- the design change approval letter as applicable.
Description of Change: This Design Change installs another flow control valve and flowmeter to the existing
- liquid rad-waste system to alfow low flow (less than 5 gpm) releases.
Exempt Change Design Package: The mechanical portion of the design for this Exempt Change is contained in ECN 400657 which is.issued For Construction" by this letter. There is no electrical portion for this Exempt Change. This Exempt Change installs components to the liquid. waste system installed by the previous Exempt Change 392999. ' 10CFR 50.59 Evaluation I Decommissioning Impact Evaluation: A 10CFRS0.59 Screening was performed in accordance with ZAP l 00-06 and is being transmitted along with this letter. This activity can be implemented without prior NRC approval. A Decommissioning Impact Evaluation was performed and it was concluded that the proposed activity is not restricted by 10CFRS0.82. .DSAR I ODCM Impact Review: DSAR Chapters 1 through 6 were reviewed for this exempt change. No changes to the DSAR are required. Additionally, a reyiew of the ODCM was conducted. Revisions to the ODCM are required as a result of this design change as identified in ZAP 510~02C, Attachment A. Attachment A is included in the DCP. 1
Febmary 13, 2015 In reply refer to CZE-15-004 Applicable Codes and Standards: This exempt change shall be installed in accordance with Zion Specification X-3646, which is the general work specification for mechanical, structural and electrical .work as well as applicable site and corporate procedures. Installation requirements identified in the ECN supersede X-3646 guidance. Basic Functions: This Design Change adds a second flow control valve and flowmeter in parallel to the existing flow control valve/flow meter assembly to expand the capability of the system. The existing flowmeter has a minllnum calibrated tlowrate of 5 gpm; the added components will allow flowrates of less than 5 gpm. Industrial Safety: This design change has no effect on the industrial safety of the plant. Installation Schedule I Outage Requirements: Installation of this exempt change will be scheduled via the site work schedule process. Technical Specification Changes: The existing Technical Specifications do not require revision as a result of this exempt change. ALARA Review: An ALARA review will not need to be performed for this exempt change. Fire Protection Review: No changes to the Fire Protection Report are required by this EC. Impact of Pending Modifications or Temporary Alterations: A review of pending design changes has been completed. This Exempt Change does not impact any pending design changes.
- 2
February 13, 2015 In reply refer to CZE-15-004 Construction Drawings: Construction is authorized to proceed in accordance with ECN 400657. Identification of the Installer: This Exempt Change will be performed by the D&D maintenance department with assistance from the other groups as required. Procurement Requirements: A Bill of Material has been included with the ECN. Spare parts should be ordered as needed. Training Requirements: Training will be required for the Operations Department and other associated plant personnel on the operation and limitations of the new portion of the system. Testing Requirements: None Operating Requirements: Existing Zion procedures will require revision as identified in ZAP 510-02C, Attachment A. Attachment A is included in the DCP. Due to the configuration of the flow path to the radiation monitor PR04, the actual release rates are at least 0.3 gpm less than shown on the flowm.eter. This reduction in actual release rate may be accounted for administratively within the procedures. 3
February 13, 2015 In reply refer to CZE-15-004 Technical Review: The Liquid Rad Waste system is considered Important to the Defueled Condition (ITDC). Therefore, this design change is subject to a Technical Review in accordance with the requirements of ZAP 500-08. A Technical Review (TR-06-2015) has been performed and
- submitted with this desigri package.
If there are any questions regarding this exempt change, please contact Arthur (Bob) Adams at extension 4010.
- Prepared By: signed vfaemtrit f-e.-k c....,, ~ l-27-es ...
Arthur R. Adams DesigIJ, Engineering Approved By: 1:Z!l_FJ{J
-'Don Roth D&D Engineering Supervisor cc:
MAL ECN 50.59. Central File 1 1 .1 Darcey Neuenfeldt originals Jim Denio 3 3 3 Mod Coordinator 1 1 1 J. Brandis 2 2 2 4
TECHNICAL REVIEW LETTER TR-006-2015
- To: Tony Orawiec Decommissioning Plant Manager
. Zion Station fl.
/"
Subject:
EC 40~ Low :Flow Meter For Liquid Waste System (i.S"h_' S~acy: J;f . This Technical Review documents the review of the technical basis for changes to the existing liquid Rad-Waste system, and installation of the new flow meter. The new flow meter will provide the capability of release flow rates of0.75 gpm to 7.5 gpm. v,;,, ~~- s Prepared By: Arthur R. Adams 1diUUt& Date:---""2""""'-Jj=-=-1=5_ _ __ Required Review Disciplines:_A....,.......B..,.._4; 9} ___ ,]2_"""-'~-* ~-- _"_T-i._.- _I/)_...* ..- EngSupv Qualified Technical Reviews 1110/}- l ZG~ fd'l/ 1 Discipline Date A,8,£Q, d~;_I~ *
~ ~
Signature Discipline Date Distribution: Decommissioning Plant Manager Operations Manager Engineering Supervisor RP Supervisor SRC Coordinator Master File
ZAP-100-06 Revision25 Information Use ATTACHMENT D: 50.59 REVIEW COVERSHEET FORM Station: ZION , _A_ ~\~\\'3 Activity/Document Number: .:E:.::C~N=-40.:..::.:.;*~65~71....-_ _ _ _ _ _ _ _Revislon Number: ,,.,o_ __
Title:
Install Additional Flowmeter and Flow Control Valve To Liq Waste Sys NOTE: For 50.59 Evaluations, lnfonnation on this fonn will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2). Description of Activity: (Provide a brief, concise description of what the proposed actiyity involves.) This activity installs an additional flowmeter and flow control valve to the liquid waste system. Reason for Activity: (Discuss why the proposed activity is being performed.) The existing flowmeter has a minimum calibrated flowrate of 5 gpm. The additional flowmweter and flow control valve will allow flowrates of less than 5 gpm to be released. Effect of Activity: . . . (Discuss how the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.) There is no change associated with the design bases, or safety analyses d~scribed in the UFSAR. Summary of Conclusion for the Activity's 50.59 Review: (Provide justification for the .conclusion, including sufficient detail to recognize and understand the essential arguments leading to the conclusion. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment Request, as applicable, is not required.) No changes to the release path from the site or controls associated with releases are changed by this revision. As such, the design function of "controlling liquid release concentrations to less than the allowablen is not changed.
- Attachments:
Attach all 50.59 Review forms completed, as appropriate. (NOTE: if both a Screening and Evaluation are completed, no Screening No. is required.) Forms Attached: (Check all that apply.) Applicability Review x 50.59 Screening 50.59 Screening No. 2015-023 50.59 Evaluation 50.59 Evaluation No. 22.of26
ZAP 100-06 Revision25 Information Use ZAP 100-06 ATTACHMENT F: 50.59 SCREENING FORM 50.59 Screening No:.---J'2~0__1__ 5-__0=23..___ _ _ _ _ _ _.....;Rev No: 0 . Activity/Document No: =E=C'--4"""0"""0=65"""'6..___ _ _ _ _Revision No: _JL I. 50.59 Screening Questions (Check correct response and provide separate written response providing the basis for the answer to each question) (See Section 5 of the Resource Manual (RM) for additional guidance):
- 1. Does the proposed Activity involve a change to an SSC that adversely affects an UFSAR YES ..X.NO described designfunctio_n? (See Section 5.2.2.l ofthe RM)
Design Change 392999 installed a new liquid rad-waste system and abandoned portions of the existing system. This change adds an additional flow control valve and flowm.eter that allows release rates of less than 5 gpm. The existing flowmeter has a minimum calibrated flowrate of 5 gpm. The dedicated release path from the site to Lake Michigan and associated control methods for monitoring releases is not changed such that the concentrations of effluent are maintained well within the allowable limits of 10CFR20 and the limits of the ODCM.
- 2. Does the proposed Activity involve a change to a procedure that adversely affects how YES _K_NO UFSAR described SSC design functions are peiformed or controlled? (See Section 5.2.2.2,ofthe RM) *
- Procedures* associated with the operation of the Liquid Waste systems will be revised under_ a separate 50.59.
ZAP 100-06 Revision25 Information Use ZAP 100-06 AITACHMENT F: 50.59 SCREENING FORM 50.59 Screening No:___,_2__0~15~---02=3..___ _ _ _ _ _ __;Rev No: 0 Activity/Document No: E=C-=---'4=0~06=5....6.__________Revision No: .JL
- 3. Does the proposed Activity involve an adverse change to an element ofa UFSAR - -
YES ..JLNO described evaluation methodology, or use ofan alternative evaluation methodology, that is used in establishing the design bases or used in the safety analyses? {See Section 5.2.2.3 ofthe RM) The Liquid Waste system is used to store, process and release liquid effluent from the RCA to the release point of the plant. The release path is defined in the DSAR. This \) activity d0es not change or affect the dedicated release path from the site or the controls of the effluent such that the concentrations of the releases will remain within the limits of 10CFR20. This is due to the existing controls, which are not being affected by this change; (1) the release paths are controlled by plant personnel, (2) effluent flowrates are determined prior to release and controlled during release that ensures co:ncentrations less than the allowable, and (3) the existing rad monitor terminates the release in the event of a high radiation in the discharge line.
- 4. Does the proposed Activity involve a test or experiment not described in the UFSA.R, __ YES _x_ NO where an SSC is utilized or controlled in a manner that is outside the reference bounds of * --
the design for that SSC or is inconsistent with analyses or descriptions in the UFSAR? (See Section 5.2.2.4 ofthe RM) This change is not a test or experiment of the liquid waste system. The release path and controls of the release path associated with the new system has not changed. 5.. Does the proposed Activity require a change in the Technical Specifications or _-YES _A_NO Operating License? (See Section 5.2.2.5 ofthe RM) No Tech Specs are affected by this change.
ZAP 100-06 Revision25 Information Use ZAP 100-06 ATTACHMENT F: 50.59 SCREENING FORM 50.59 Screening No:.___;.2=0=1=-5-""""02=3.___ _ _ _ _ _ _ _Rev No: 0 Activity/Document No: =E""'C....4.....0.....06=5....6____-'--_ ______,Revision No: _JL II. List the documents {e.g., UFSAR, Technical Specifications, other licensing basis, technical, commitments, etc.) reviewed, including sections numbers where relevant information was found {if not identified in the response to each question). DSAR Chap 4 & 5 ODCM EC393000 Ill. Select the appropriate conditions: X If all questions are answered NO, then complete the 50.59 Screening and implement the Activity per the applicable governing procedure. H question 1~ 2, 3, or 4 is answered YES and question 5 is answered NO, then a 50.59 Evaluation shall be performed. H questions 1, 2, 3, and 4 are answered NO and question 5 is answered YES, then a License Amendment is required prior to implementation of the Activity. If question 5 is answered YES for any portion of an Activity, then a License Amendment is required prior to implementation of that portion of the Activity. In addition, if question l, 2, 3, or 4 is answered YES for the remaining portions of the Activity, then a 50.59 Evaluation shall be performed for the remaining portions of the Acti~ty. IV.:_SereenJng Signoffs: _,..,,1_..,,,,, ~fl,A Z'. 50.59 Screener: Arthur R Adams Sign: via emeii- Date: _2_/~/_15 (Print name) (Signature) S0.59Reviewer: ~!.IL,.,;( g~igo:~ (Print name) / (S' ature) Date:3:._J2'P//./
ZAP 100-09 Revision 4 Information Use ATTACHMENT A DECOMMISSIONING IMPACT EVALUATION Activity: EC 400656 (Work Order No., Procedure No., On Site Review No., Design Change No., etc) TRACKING#: ......2....0..... 1-...5-..--02=-3....___ _ _ _ __
- 1. Does the proposed decommissioning activity result in any of the following:
- a. Foreclose the release of the site for possible unrestricted use;
[ ] YES [ X] NO Provide justification: The proposed activity involves replacing an existing flow meter with a new more sensitive flow meter. The flow meter is installed in the Crib House Forebay which is not part of the Radiologically Controlled Area (RCAl of the plant. Therefore. this. activity does not increase the potential for spread of radioactive contamination and will not foreclose release of the site for possible unrestricted use.
- b. Result in significant environmental impacts not previously reviewed;
[ ] YES [X] NO Provide justification: All the work associated with this activitv will be performed within the envelope of the station's double fence former Resticted Area. Therefore. this activity will not have any impact on NUREG 0586 Supplement 1 criteria of land use. aquatic ecology, terrestrial ecology. threatened and endangered species. environmental justice. or cultural impacts. The amount of water used will be non-detectable. so there will be no imoact on NUREG 0586 Supolement 1 criteria for water use or water quality.
- c I
The new flow meter will be installed along the eastern edge of the plant which borders *on Lake Michigan but will be shielded from the lake by a concrete wall. Therefore. this activity will have no impact on NUREG 0586 Supplement 1 criteria for aesthetics or noise. As stated above. the work will not be performed in the RCA. therefore the activity will have no impact on radiological criteria.
- Finallv. this modification does.not change the requirements fot effluent Releases.
- 9
ZAP 100-09 Revision 4 Information Use
- c. Result in there no longer being reasonable assurance that adequate funds will be available for decommissioning.
[ ] YES [X] NO Provide justification: This is minor modification to an existing svstem with minimal associated costs.
- 10
ZAP 100-09 Revision 4 Information Use ATTACHMENT A DECOMMISSIONING IMPACT EVALUATION (Continued) Activity:
- EC 400656
- 2. Review the answers to Step 1.a-c. jf the answer to any of the questions is YES, Then the activity can NOT be completed, without prior notification to the NRC.
NOTE In taking actions permitted under 10CFR50.59 following submittal of the PSDAR, the licensee may perform activities inconsistent with the PSDAR, including significant schedule changes or significant cost increases, provided prior written notification is made to the NRC, as well as a copy of the notification to the State of Illinois.
- 3. Is this activity inconsistent with those actions described in the Post-Shutdown Decommissioning Activities Report or cause a significant schedule change or cost increase?
[ ] YES [X] NO Jf the answer is YES, Then notify the NRC and the State of Illinois prior to performing the activity.
!f the answer is NO, Then proceed without notification.
Provide justification: This is minor modification to an existing system.
- 4. Implement Changes - Based on this evaluation, I have determined that the proposed activity is not restricted by 10 CFR 50.82.
Preparer print name: Arthur R. Adams Discipline: A B. C. G
~J.
signed via envU: r~ta~.,.,, ~ ~ 24if15 Preparer Signature Date
- 5. Review - The reviewer agrees that the proposed activity is not restricted by 10CFR 50.82.
~print nam~Donald F. Roth Discipline: _A_,._<.i____
.. M£~f. ~/20/iatf
""R:eviewer Signature Oat~ '
11
ZionSolutions LLC ZS.:.2016-0042: Attachments ATTACHMENT 4 ECN# 400986 Increased capacity dilution water pump of 10,000 gpm and associated flow1neters
'Exhibit A NEP-08-01 Revision 1 Engineering Change Notice (Part 1)
ECN No. 400986 ISSUANCE: ~FOR CONSTRUCTION 0 FOR COMMENT .. Page: _I_ of ..%1_ Station: ZION D Safety Related Design Change No. 400985 Affected Unit: 00 181 Non-Safety Related Project No. (ifappl.): NIA Changes to a previously Approved ECN D [j -Regulatory Supp ID No. (ifsppl): NIA System: SW Description of Design Change Request: This change will add a higher capacity SW dilution pump (OB) in the Forebay in parallel With pump OA installed under EC396794. A new SW flow meter (OFIT-SWS4B) and flow control valve (OFCV-SWS4B) will also be installed. The Unit l & 2 Oil Separators Will be capped and the Unit l & 2 Oil Separator Composite Samplers will be removed from service.
\
Reason for Design Change: Change and action required (Provide reason for change, specific actions requiJed. attach supporting documents, as applicable). Decommissioning schedules along With the high boron concentrations in the SFP and other LRWS discharge streams will require a higher dilution flow rate than can be achieved With the present pump. The capping.of the Oil Separator inputs Will allow removal of the Oil Separator Composite Samplers allowing for the space needed for the new dilution pump discharge path. INTERFACING COMMENTS by: Design Group or Discipline Name of Commenter (Printed) Signature of Commenter Date CorNC Elect./l&C NIA Mechanical ..... - Structural
- Dave Carter 1/JdJ:J- $-17-1..!i" .NC-.
Others NIA Prepared by: IJDuBois Reviewed by: PJBeinecke~ Approved b; j ~ .~~£Bd Date: ~eiM.r c@ Date: - ~1ee/zois-3-1 ?-1~- Date: a/18L16"' ' r AU affected design documents revised by (date): verified by: Date: W~ ca~ lM'lS ec.N ge4A.t--' B~l2e 3/t'-/zat~ So tT USeS OLP ~t:2.M.S... rt-{ 12&J.LSE0 l:Of2i'JlS 'DO NOT R..e. tJCrcafJAt-t...~ Otfl_ ""TGO-fa-..l<CALL'"f APF6Cf ""t1:fe wod211<, .
~/ F~ 3/10/~ots
Exhibit A NEP-08-01 .( Revision 1 DESIGN CHANGE DOCUMENT -AFFECTED DOCUMENT LIST (Part 2) ECN No. 400986 Design Change No. 400985
. ll~!Jtt: IJl.;t~u 03/U/2015 EC~;t a OOOGC00916 DO() ....,
~Exelon, SC.tu/Date , JWGJS'l'ER 02/0t/2015 J.ID.c.1 Hty : %:IN Type/Sub-type:
DCP MOD llBlllElllrSlllill*- BC ~it.le: sat .. ttisiAU A HIGJlft Pl.ON' SW' llll.>>tlON ~ H!mlf lHr.ALl:aTIOR IW2: Kil41
!9, !XU Iii!
*u- !MJ!!Mt !lt!U 211 ID !!! J!e ZDI nMGC M-100 g y H Mimiir aev~ ~or MV1 VpGt Puea.
Title 1 CIRC!Ut-l'IHG WAmR elPDTG PLR.11 - 1DltfS 1 .- 2 zm DUGC 11-31 ll y N iunor b'1': Majo:r Rev: 11pclt Dtiie: I Title 1 JJlMRNil or c~ WA'J'JIR P:i::PIW - tmJTs 1 " ' . ZiR SJlllGC M* 32 t N Y 1 Minor Rev-: Hll..jar Rw: Ugdt Duet
'tit.le' J)JMJWI! OP "1t\1%Ct NATa CCIU'!"IQI, t:mn'ROJ.i ROOM DJWrUIC) "Lrt.~ fJwG c: fll.40( !TH 00 SN Zqui9f11mt : *Fl' SWS4B Mino&' bVi CC!lllOIWlt
- Ma'or Rev:
Bqu,p. Tag; OFI'l'-stf5U 8t.ate l llev.le-4? N Dltl/MD: 1te1r 1'redcUlei II Xl\ru II
-- I OB SW lQU> DXW'J'!OIJ fUlff DDXCM'CR I ~
Exhibit A NEP-08-01 Revision 1 / DESIGN CHANGE DOCUMENT -AFFECTED DOCUMENT LIST {Part 2) ECN No. 400986 Design Change No. 400985 Print ~tes OJ/11/2015 BC Numb~r ~ DD00tOO!J86 ltOD Stat.-us/D~te l'iitilUty JtBGrSTICR 02/0>>/2015 Int IE,xelon. Type/sub-type: DCI" MOil' . . llDlHlllllDllllll~llllM Page~ pof27 ,, ZlN 00 BqW.pment : B/A lOtllB ampon~t ~ V25 c: EljF.ip. Tag: 0Stf1001B stab:; MViewed?
- Inst/llm:
NAM ~ 08 SW DILU'l'lOll WAn.R l1UMP ZDI 00 SW squ1pawmt PCVA 6"541! ~-- le\t: Comp<ment : vis ~ Major uv: Bqu.ip. Tag: OFCV*SNOOSfB s~ate1 R.eVieweci? w ln*t/Rmi MY ~le: N Inc: Ii' Jlame : Oll SW D:Ilt'U'l'JON PUMP ftaOW COR'l'JIOI. VAS.VB
Exhibit A NEP-08-01 Revision 1 ( ECN No.: ___,_40=0=9-=86"------ Design Change No.: 400985 PageNo.: 4 of --=2-=-7_ _ Back-Up Calculation Listing (Part2) Calculation/.Analysis No. Revision No. Description None
Commonwealth Edison Company Engineering Change Notice ECN No.: __.....:.40=0=9=86"------ Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 5 of -=27""---- Prerequisite
- 1. At the direction of Environmental Manager and Waste Operations Manager remove all oil stored on clean and dirty oil storage pad on north side of Turbine Building or protect it from oil release to the environment, RefB-803
- 2. W allc down the site with Environmental Manager to determine if any mitigating actions need to be taken for any oils stored outside. Reference drawing B-803, 804, and B-876 for areas that feed the Oil Separators.
- 3. Verify Storm Water Pollution Prevention Plan and associated procedures and guidelines are implemented for the rem.oval of the Oil Separators with Environmental Manager.
. 4. Verify the Spill Prevention Control and Countermeasures Plan and associated procedures and guidelines are implemented for the removal of the Oil Separators with Environmental Manager.
Notes:
- 1. This Installation is laid out in sections.
- 2. Section 1 Unit 2 Oil Separator needs to be completed prior to starting Section 2 Step2 Section 1: Capping Inputs to Unit 1 and Unit 2 Storm Water Oil Separator
- 1. At Fuel Building Car Shed (Truck Wash Down Area) verify sealed or install mechanical plumbers plugs in floor drains. A total of 7 drains shown on drawing.
Reference B-492
- 2. At Outdoor Clean and Dirty Oil Storage pads (North of TB) install mechanical plumbers plugs in drains. Remove manhole cover, cut a W' steel plate to fit manhole, seal plate to manhole, install manhole cover over plate seal plate. See Sketch 3. Ref B-803, B-876.
- 3. Use plumbers plugs or similar to plug input and outputs to Man Hole 2-15. Reference drawiJ!g B-803, two 4", two 24" See Sketch 3.
- 4. Fill Man Hole 2-15 with concrete or grout to a minimum of 1 ft above the top of the highest internal pipe. See Sketch 3.
- 5. Discontinue periodic sampling of the Unit 2 Storm Drain Oil Separator eftluent.
Notify/Contact Environmental Manager, RP Technical and Chemistry Supervisor.
- 6. Use plumbers plugs or similar to plug input and outputs to Man Hole 1-17 Reference drawtng B-803, two 10"~ two 24", See.Sketch 3 Prepared By: Date: '3-17 Date: !1~/lr
Commonwealth Edison Company Engineering Change Notice .( ECN No.: . ___,,4=00=9-=86=------ Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 6 of --=27..____
- 7. Fill Man Hole 1-17 with concrete or grout to a minimum of 1 ft above the top of the highest internal pipe. See Sketch 3.
- 8. Discontinue periodic Sampling of Unit 1 Strom Water Oil Separator Eftluent.
Notify/Contact Environmental Manager, RP Technical and Chemistry Supervisor.
- 9. Verify electrically gap the Unit 1 Storm Water Oil Separator Composite Sampler and heat tracing per ECN 400987.
- 10. Electrically gap the Unit 2 Storm Water Oil Separator Composite ~ampler and heat tracing per ECN 400987.
Bill Of Material Quantity Description (MinReq'd) 7 Car Shed Mechanical Plumbers Plug, Field to determine size, capable ofl psi.
.3 Clean and dirty oil storage pad drain mechanical plumbers plugs, 6" 2 4" inflatable plumbers plug. Capable of2 psi 4 24" inflatable plum.hers plug, capable o£2 psi 2 1O" inflatable plumbers plug. Capable of 2 psi 4 Cu Yards of concrete 1 W' steel plate, 24" x 24" 1 Silicone sealant or similar, Tube Section 2-Unit 2 CW Discharge Isolation Valve House Preparations
- 1. Verify Section 1 capping of Unit 2 Oil Separator Inputs are complete.
- 2. Remove Unit 2 Oil S_eparator Composite Sampler. Cut back electrical cables, sample lines, supports* and heat trace as required clearing the area for a hole in the floor. See Photo 2 and Electrical ECN 400987.
- 3. Verify relocated electrical box on south wall to west wall per ECN 400987. See Photo 3 of this ECN.
- 4. Remove abandon ml\terials (conduits, cables, cameras, etc) as required in preparation to remove a portion of the south wall. See Photo 2, 4 and 6.
Prepared By: ~~ Reviewed Bv:
":'.li Commonwealth Edison Company Engineering Change Notice
( 40=0=9=86~---- ECN No.: _____ Design Change No.: 400985 Station: ZION Affected Unit: 00 PageNo.: 7
- of --=2_,_7_ _
- 5.
- Cut hole. in south wall. Leave 2 courses of block along door and along east wall.
See Photos 2 and 6.
- 6. Cut a hole in the floor approximately 4 ft x 4 ft. Floor is 2 ft thick and has re-inforcing bar (rebar), RefB-39. See Photo 2, Sketch 1 and Sketch 8.
- 7. Dive and cut relief windows in CW Discharge pipe downstream of 2MOV-CW-0006. There shall be 1 ft of pipe remaining circumferentially between each window.
See M-101 Part 5 ofthiseC~ ,_,,....,,
- 8. If installed per ECN 40oi'77 then Relocate LRWS discharge hose from entering in front of 2MOV-CW-0006 into new relief windows otherwise NIA. Ensure hose is at least 5 feet on lake side of relief window. See Sketch 2 and M-101inPart5 of this ECN.
Section 3-Installation of Piping
- 1. Verify beach construction equipment traverse route with Environmental Manager.
- 2. Remove interference-as required (i.e. conduits, yard lights, razor ribbon on aft bay wall, conduit, etc.). Coordinate with Security removal of the razor ribbon and*
barbed wire on the aft bay east wall. Security will determine if the security features need to be replaced. See Photo 4, 5 and 6.
- 3. Per Sketches 4A, 4B and Pipe Fabrication Vendor drawing and instructions install piping and pipe supports (Engmeerlng to review and approve vendor drawings and instructions). Install all piping from Unit 2 CW Discharge Valve house to riser on the pump. Pipe does not need to be sloped for this application. See photos 4, 5, 6 and7.
- 4. Install the flow meter and program meter per the vendor manual. Flow meter may be mounted at a convenient location, (i.e..next to the pump control switches)
Bill of Material Quantity D~scription (MinReq'd) 1 24" throttle valve(or equivalent). Lake Michigan Water service, 33F-85F process temperature, max system pressure 85 ft/37 psi. Part of lot 1 below. Reference Sketch 4A and 4B 1 Flexible boot assembly. Geneial Rubber 1101-0240-100-0EE (1101 OJA 24 x 10" F/F EPDM, Open Arch, Rated for 130 psi, 30 in Hg Vacuum, 250 F, Standard 150# Drilling, with PPRS-0240~CSG (R/R Set 24 in. CSG) Set of Split Retaining rings for 24" expansion joint with standard 150# drillin , 3/8" thick, Carbon Steel Galvanized or Prepared By: Date: ~-
~: 5};1//J /-
Commonwealth Edison Company Engineering Change Notice ECN No.: ___,,40=0=9=86..___ _ __ Design Change No.: 400985 . Station: ZION Affected Unit: 00 Page No.:
- 8 of ~27~--
similar Provided with Lot 1 Reference Sketch 4A and 4B 1 lot Prefabricated and spooled HDPE 24" piping, UV protected; Piping to including all flange bolting, backing rings, gaskets, valve and flexible joint. Process is Lake Michigan Water, 33F-85F process temperature, max system pressure 85 ft/3 7 psi, ambient temperature -10 F to 100 F. This lot will include 24" throttle valve and flexible boot above. Reference Sketch 4A and 4B. Pipe vendor/fabricator to provide engineering, layout, supports and installation requirements. (ZS Engineering to review and approve vendor drawings and instructions) 1 Ultrasonic Flow Meter with dated calibration certificate. Application 24" HPDE piping, DR-17, 4,000-15,000 gpm, process fluid is fresh lake Michigan water, temperature range of process fluid 33-85F, outdoor applications ambient -1 OF to +105 F; Omega FDH-1-50FT-NIST Hybrid Ultrasonic Flow Meter with dated calibration certificate with 50 ft leads. Section 4 Installation Pump
- 1. Verify that the thickness of the pump mounting plate is' greater than or equal to 0.7 5 inches. If not replace plate with one greater than or equal to 0.75 inches.
- 2. Cut pump access hole (34" +/-1 ") in the center of the pump mounting plate.
- 3. Lower pump onto pump mounting plate and face discharge nozzle in the North direction. (Cascade-I Stage 20MF Mixed Flow Pump, ref Drawing 3MS7633A) using manufacturer's instructions and good work practices. *
- 4. Shim pump as required to level pump head.
- 5. Drill and tap holes (3/4 - 10) in pump deck plate for pump discharge head mounting bolts. *
- 6. Illstall hold down bolts and tighteii.
- 7. Recheck pUm.p level and adjust as necessary.
- 8. Install motor using manufacturer's instructions and good work practices.
- 9. Coupling alignment shall be done using a straight edge (or equivalent) method.
PreparedBy. g_, o£6v. Date: "J-11-1r
!leviewedBy: * ~- Date: Jbt'lS
Commonwealth Edison Company Engineering Change Notice ECN No.: __._40=0=9=86::..___ _ __ Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 9 of --=2""-7_ _
- 10. Install flexible boot to pump per Sketch 4A, photo 7.
- 11. Install riser pipe per Sketches 4A, 4B and Pipe Fabrication Vendor drawing and instructions. (Engineering to review and approve vendor drawings and instructions)
- 12. Install pipe anchor per Sketches 5, 6 and 7.
Bill Of Material Quantity l,)escription 1 Pump and motor assembly Cascade-I Stage 20MF Mixed Flow Pump, ref Drawing 3MS7633A 4 Studs, %-10 UNC x 4" long 4 Washers, %" 4 Nuts, %-lOUNC 1 Fiexible boot assembly. General Rubber 1101-0240-100-0EE (1101 O/A 24 x 10" F/F EPDM, Open Arch, Rated for 130 psi, 30 in Hg Vacuum, 250 F, Standard 150# Drilling, with PPRS-0240-CSG (R/R Set 24 in. CSG) Set of Split Retaining rings for 24" expansion joint with standard 150# drilling, 3/8" thick, Carbon Steel Galvanized or similar Provided with Lot 1 in Piping Installation section. 20 Bolts, 1 1/4-7 UNC by 8" long 20 Nuts, 1 ~-7 UNC 10 ft Structural Steel HSS 5x5x5/16 12 Hilti Kwik Bolt 3, 3/4" . 2 Plate, Steel,%" x l '-6" x 2'-3" 4 Plate Steel, %" x 6" x l '-8" 1 Plate, Steel, W' x 3' x 4' Prepared By: ~ SL;""". Date:
~~ Date:
Commonwealth Edison Company Engineering Change Notice ECNNo.: _40..:.=0=-9=86_ _ __ Design Change No. : 400985 Station: ZION Affected Unit: 00 PageNo.: 10 7_ _ of __.2......... P~'t Photo 2 Cut Hole in wall, top to bottom. Leave 2 course of block along door and east wall Date: Reviewed By: Date:
Commonwealth Edison Company Engineering Change Notice ( ECNNo.: _4"'""'0=09=.= 86~--- Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 11 of __.2......... 7__ Photo 3 Inside Unit 2 CW Discharge Va1ve House Looking South Prepared By: ___A--'--~--- _-L Date:
*~
Reviewed By: Date:
Commonwealth Edison Company Engineering Change Notice ECNNo.: _4~0~09~86'----- Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 12 of ~2~7_ _ Photo 4 Remove Door, hand rails and kick plates as required Prepared By: Date: n -..:-......- ..3 n .. . a
Commonwealth Edison Company Engineering Change Notice ECNNo.: _4=00~98""--6_ __ Design Change No. : 400985 Station: ZION Affected Unit: 00 Page No.: 13 of -=2,_.,_7_ Photo 5 Pipe route on ground and up to Aft Bay plate'form. Approxima.e location of control valve 1 PreparedBy: ~~ Date: RevicwedBy: ZLP~- Date: .l#Ms~
Commonwealth Edison Company Engineering Change Notice ECNNo.: _4o...:.,=.00"-""'986...___ _ Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 14 of --=2"'---7_ Photo 6 Remove ~all section. Leave 2 block courses on east and an along door. Remove electrJcal conduits and boxes. Remove light pole and camera if required. Approximate location of throttle valve Approximate .pipe routing on ground. Pipe goes into valve house and down through hole in floor Prepared By: Date: ~ t?-f~ n -.:---*- .JI "D- ** Oato* .Jtd~J,..--
Commonwealth Edison Company Engineering Change Notice ECN No.: ___:.:40:<..:::-09=8~6_ _ __ Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 15 of -=27'---_ Photo 7 New Pump Location Prepared By: ~ ol9A Date: Reviewed Bv: ~/.f'~ - Date:
Commonwealth Edison Company Engineering Change Notice ECNNo.: _:40~0!2.£98~6_ _ _ Design Change No. : 400985 Station: ZION Affected Unit: 00 Page No.: 16 of 27 __ _
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INSTAt _i_ CGYR~ -...--..,. High Capacity
- Dilution Pump Unit2 CW
** Loc _:tion . 'Discharge Tunn.el
...-....::~..._.* .....
~~~ Isolation Vafv-e 1;
J1
~
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PotentaH locations
- Unit 2 I
- for Flow l.ndicator, c.w
*Pipe Mounted Oischarg E * *Tunnel oca ion r---.. . Lake Side Prepared By:
- . *~
Commonwealth Edison Company Engineering Change Notice ECN No.: -"-"40=-=09'""'"'86"----- Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 17 of __,2=<..7_ _ Sketch 2 111111<(-----.I 1:ast J West 5~DJA.MAN .ENTRY Hose Route
- through tunnel Per Wrtit l!LlND 'RAN~-------....
- iiii _ .....u
ECN400577
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Existing 364' access manway I r---._.__. pipe to cw tunnel
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Route LRWS Dischaige Hose route after access wtnoow is cut If. in CW pipe do!Nnstream Of CW
... Diseharge isolation Valve and t VaJve is dosed. Must be a .
,. minimum of 5 ft past dflution point c,*_* --
If inslaHed Under ECN 400577
.-ct EL L..V Hose Gang route Per ECN 400577 Prepared By: 4cl9Atr? Date: y t?vl'f
£d,?4--- Date: .~bRILS
Commonwealth Edison Company Engineering Change Notice ECN No.: ---'4-=-00=9~8=6_ _ _ __ Design Change No.: 400985 Station: ZION Affected Unit: 00 PageNo.: 18 of --=2'-'-7_ _ _ Sketch 3 iT T i
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Prepared By: Date: Date :
Commonwealth Edison Company Engineering Change Notice ECNNo.: 400986 Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.; 19 of --=2:.<.7_ __ VAL.VE HCXISE FLAt\IOES.F~ OIIFICE ~NSTALLATION PLAN VIE!
~ Pllh!P 10'-0" 2' .. i a*-11 1, * *I I I
I I I I 24" HPDE PIPE
;z-4" tPDE PIPE
- EDGE Or CONCRETE T FLEX JOI~ __
<GENERA£ IWl!BER MAXI JOINT STYLE 1101 OR SI~ILARI t 5U'-&"
I ___ ,......_...............K PUMP DISCHARGE HEAD rSEE DETAIL 1 ~ EL. 584' -51'2" 2~-h: FUT FACED DISCHARGE FLANGE 150# SECTION C LOCIKINC WEST SECTION A LOO(ItiliG SOUTH SECTION B LOOKJNG WEST
-'SOTES:
- 1. Ziii! " HPDE P JPE, UV PROTECTED
- 2. PRDtESS FLUID1 WATER DESIGN PRESSURE:
NORMAL 1JPSI PWP DEAD HEAD IMAXI a'rPS1 GRADE EL 592 * -0" FLPlf RATE 4000-1-4000 GAi PROCESS T9PERATlJIE.r 33' F-SS*F UJlllENT TEiil'ERATURE.: -!i"F TD 10o*F SERVICE LIFEt 1 ~EAR 3* i\LL DIE~SIONS ARE REFERENCE. DIWTJON PUMP
~. PIPE FABRI~ATOR SHALL fALKDOWN THEN PIPING LA~OUT SIZE PIPE* LAYOUT AJIO RECO\!MEND DETAJL I SUPPORT JNlPVALS.
- 5. ELEClRJCAL PD'llER LINE OVER PIPE ROIITE
~~lrx-vliTI:AL C9i1ERL.Ih'E lHAT LIMIT OVERHEAD CLEAJANCE FOR INSTALLATION*
'SECTION C
&. PIPE FABRltATOR TO PROVIDE ALL PIPING+
JOINT HARDWARE, tAiKETS, VALVE AND FLEX JOINT. LOOkJNG iEST 1. BUTTERFLl VALVE SHALL HAVE A MANUAL OPERATOR. Prepared By: Date: }.--17-1~
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Commonwealth Edison Company Engineering Change Notice ECN No.: ---.:.40=0=9....,86,.___ _ __ Design Change No.: __,4=00=9-=85~-- Station: -=Z=IO=N~- Affected Unit: 00 Page No.: 20 of 27
@ lS<METRIC Prepared By: Date:
Re"iewed By: Date:
Commonwealth Edison Company Engineering Change Notice ECNNo.: _4..!..><.00=9=86_ _ __ ( Design Change No.: 400985 Station: ZION Affected Unit: 00 PageNo.: 21 of _..2....._7_ _ N~ I 3'-0" t+"(mil)
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1* I Sketcl1 5 On pump Platform
,Flex Joi*nt Side of Pump*
~Ref B-14.38 l ..
Prepared By: Date: Reviewed Bv: Date:
Commonwealth Edison Company Engineering Change Notice ECNNo.: --'-=40~09'-""'86,,__ __ . ( Station: ZION Affected Unit: 00 Design Change No.: 400985 Page No.: 22 of __,2...._7_ _ pJfir*'1. 314" plate - - - - - Detail 1 {typ.) r 1"-7112" 1'-7112'" Section A-A Prepared By: Date: 7rt7-ff Reviewed By: Date:
Commonwealth Edison Company Engineering Change Notice '(J.*~-" I
*' '. '_J,., :*it'
( ECNNo.: _4~0~09=86<---- ' ;*~ - .J' ~-- Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 23 of __.2=-=-7_ _
.._,. E=3116
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Detail 1 Sketc:i1 7:* On pump platform
*on pump side of flex
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101*n
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Section 8:8 Section C::C Prepared By: Date: ~t7~~ Reviewed Bv: Date: &f 1d .('
Commonwealth Edison Company Engineering Change Notice Station: ZION Affected Unit: 00 Prepazec!By: ~ . rf),/j_ Date: '7J-r7- /~ RP.ViP.Wf'.d Rv'. ~.L.l~,-1/3.----- Date: ~tf(a-
Commonwealth Edison Company Engineering Change Notice ECNNo.: _4=00=986=---- Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 25 of ___..2~7_ Parts., NOTES:
- 1. iO PURCHASERS FOREBAY BUBBLER TUBES
- 2. PURCHASERS SUCTIONMMY SIPHON tUBES
- 3. . : PIPl~C TO. ANO l.NCWOIY ICH. e.o. SHALL BE
.* IN ACCORDANCE WITH TABLE G__J .
'
- ALL PIPING LARGER THAN JI INCH. 0.0. SHALL BE INS
. WITH CORK FILLED MASTIC AS INDICATED
- IN THE. SPEC
- 5. PIPING 1'1 OJ>" AND SMAirWt SHALL BE INSULATED IN ACCOROANCE WITH TABLE CQ)
ECN 6. ALL OTHER PIPING SHALL BE INSULATED WITH *vzMASa 400986 INDICATED IN THE SPECIF'ICATION.
- 7. FOR DETAILS or MISC. PIPINC S£E (D-2) OF THIS ORA OVO JCM JAD DIGRAM OF CIRCULATIN RFD JCM JRD WATER PIPING
-- -- -- :NONE MTE .
Prepared By:
Commonw.ealth Edison Company Engineering Change Notice ( ECNNo.: _40~0~98_6_ __ Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 26 of ~2~7_ Part5
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Prepared By: Date: 1-fltr R P.ViP.wPA Rv* Date: _g/rf)/t.5
Commonwealth Edison Company Engineering Change Notice . _. _.. . ___ , Station: ZION Affected Unit: 00
~.;~4:.~6 400985 .(#r" Page No.: 27 of 27
---=..!----
*E: .. *i~q
- Cut 4' (min) x 4'(rmn) hote in
* ~!'DIA I MAN f.NTRV ~"
lloor on soulh-south east side of I ',
/ii**~. . .~
WITit 8.JND R...*ClE.:----__..~ - 7
- Vatite fOr dilution i water fiOW pipe.
lnstaD hand rans a::.;a ,ECN for safety.
-~- t ..
400986 PORT. DE.TAIL *a~. I * *
,Cut 4 Windows in CW pipe .
11-611 (min) x 3' (min) tor -* . tr dHUtion water loW. one I h<>le neects to be located . ; .
- l:P..1' ._. --~---1 at top. one hole needs to * ;, **
.t'~=='
windowS are in CW pipe. cut *-** I-Bi_;;_a_-** ii
~
,!ii_ ___ .-..-~li.I be located-on south side *
!!: . . . . . . -45 degrees off verticat
. one fOOt minimum
* . between holes along ttae
' circurnfe~(lce of the pipe.
MinimUm 5 ft past pipe WindoW.
.. ,_ ... ~.
t LRWS Discharge
- Hose Route Per ill " i: ECN 4005T7 Cl Re; ,
'i ~ -
PL<<N*4M~101 Unit 2 CW Dis a j Valve House struciure Cross Section. I I Lookin SOUlh Prepared By: Date: 77-17-tr-Reviewed Bv: Date; 1/11'/!~
( March 17, 2014 In reply refer to CZE-15-005 To: Tony Orawiec
Subject:
Zion Station, Unit 0 and 2 Exempt Change No. 400985 OB Dilution Water Pump The Engineering Deparbnent h~ reviewed the subject Exempt Change in accordance with ZAP 510-02C and the applicable Zion Solutions Quality Requirements. The applicable Design Input Requirements are discussed in this letter. System Code: SW, CW Description of Change: This activity will add an additional SW dilution water pump (OB) in the Forebay and the flow will run in parallel to the OA SW dilution water pump to the discharge tunnel. This activity will also abando.n (cap inputs to) the Unit 1 and Unit 2 Storm Drain Oil** Separators. Exempt Change Design Package: The design for this exempt change will be contained in ECNs 400986 and 400987 are issued "For Construction" by this letter. 10 CFR 50.59 Evaluation I Decommissioning Impact Evaluation:
~~11-lC, ~3/ri{ZP~. -
A 10 CFR 50.59 B11al1:1&tiee. was performed in accordance with ZAP 100-06 and is being transmitted along with this letter. This activity can be implemented without prior NRC approval. A Decommissioning Impact Evaluation was performed and it was concluded that the proposed activity is not restricted by 10 CPR 50.82. DSAR I ODCM Impact Review: There is no impact to the DSAR or the ODCM as a result of this Exempt change.
CZE-15-005 Applicable Codes and Standards: This exempt change shall be installed in accordance with Zion Specification X-3646, which is the general work specification for mechanical, structural and electrical work as well as applicable site, vendor and corporate procedures. Installation requirements identified in ECN 400896 and 400897 supersede X-3646 specifications. Installation Schedule I Outage Reauirements: Installation of this exempt change does NOT require *an outage and therefore will be* scheduled via the site work schedule process. . Technical Specification Changes: The existing Technical Specifications do not require revisions as a result of this exempt change. - ALARA I Fire Protection Review: This exempt change is NOT being performed in a radiological area. Therefore, an ALARA review will NOT be performed as a part of the work package preparation. There are minor additional combustibles being added. These combustibles (cable and motor oil) will not be near any critical equipment. Construction Drawings: Construction is authorized to proceed in accordance with ECN 400896 and 400897 ,_. Identification of the Installer: D & D will perform this exempt change. Procurement Reauirements: Procurement is the responsibility of the installing organization other than the pump/motor which will be procured by Engineering. Procedures: Operations, Chemistry, Radiation Protection and Environmental have identified affected procedures and are responsible for updating the required procedures prior to declaring this modification Operable. Page2of4
CZE-15-005 Traiiiing Requirements: There are no training requirements as a result of this exempt change. Testing Requirements: There are no testing requirements as a direct result of this exempt change. However, the new valve, flange and piping should be checked for no visible leakage and any leakage identified should be evaluated by engineering as acceptable. Operating Requirements: None required. Technical Review: The SW system is mentioned in the DSAR; therefore this modification is subject to a Technical Review in accordance with the requirements of ZAP 500-08 and the ZNPS. A Technical Review was completed under the ECNs and found to be acceptable. Other Considerations Engineering considerations are documented in ECN engineering document files. They are found to be acceptable. Page3 of4
CZE-15-005 / Environmental Considerations The removal of the Oil Separators was evaluated. As part of this activity the site will be transitioning to the Storm Water Pollution Protection Plan for storm water management. Roof drains from major buildings (Fuel Building, Auxiliary Building and Turbine Building) will now be discharged to the ground through the existing yard man ways. Oil and Grease storage will be at the guidance of the Environmental M~ager. If there are any questions regarding this exempt change, please contact Lee DuBois at 224-789-4065. PreparedB}" ~ J. L. DuBois J)~~ Design Engineering ApprovedBy~,;-JZd,
- on Roth Design Engineering Supervisor cc:
MAL ECN 50.59 Central File I I 1 Tara Pratt originals Dennis Gruh/Jam.es Gaskill 2 2 2' tony Orawiec .1 *I 1 Page4 of4
TECHNICAL REVIEW LITTER TR-010-2015 I To: Anthony Orawiec r Decommissioning Plant Manager Zion Station
Subject:
Installing an additional Service Water (SW) Dilution Pump (Pp) with increased flow rates. The purpose of this letter is to document the Technical Review of the Design Change Package for Exempt Change EC# 400985 and associated ECNs 400986 and 400987. Our conclusion, the proposed exempt change does not impact the operation of any system which may be credited in any DSAR evaluation, the methodology used to establish the design bases or in the safety analyses as described.in DSAR Chapters 3 or 5 in support of the safe storage of nuclear fuel. In conclusion, the proposed Exempt Change does not affect the design or the design function of the SW System; as well, the proposed Exempt Change does not affect the ability of SW to perform that design function. o...,is'---~---"""'~------- Prepared By:_.=Le=e....D=-u=B.... Date: 03/11/2015 Required Review Disciplines: A/ ~ ~ GJ Engineering Supervisor Qualified Technical Reviews 3-17-ltf Discipline Date
&Bfo-e-Signature Discipline Date Date Distribution:
Decommissioning Plant Manager Operations Supervisor Engineering Supervisor SRC Coordinator Master File Page 1of1
ZAP 100-06 Revision25 Infopnation Use ( ATTACHMENT D: 50.59 REVIEW COVERSHEET FORM Activity/Document Number: Design Change 400986 Revision Number: 0----
Title:
Increase the SW Pump Capacity and Elimination of the Ul & U2 Storm Drain Oil Separators NOTE: For 50.59 Evaluations, information on this form will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2). Description of Activity: (Provide a brief, concise description of what the proposed activity involves.) Design Change 400985 adds a higher capacity SW pump and eliminates the Ul & U2 Oil Seoarators. Reason for Activity: (Discuss why the proposed activity is being performed.) fncreased capacity is needed to sgpport RCA dewatering efforts and decommissioning schedules. Effect of Activity: (Discuss how the activity impacts plant operations, design bases, or safety analyses descnbed in the UFSAR.) L activity merely increases the capacity of the SW system so as to allow for quicker removal of LRW. Removal of the oil seoarators is a nanagement discretion activity and under the control of the Environmental Manager. Summary of Conclusion for the Activity's 50.59 Review: (Provide justification for the conclusion, including sufficient detail to recogniie and understand the essential arguments leading to the conclusioll. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation. or a License Amendment Request, as applicable, is not required.) The SW system and the Oil Sq?arators are not credited for any design function nor are they credited for any accident mitigation in the DSAR. Additionally. this activity merely adds capacity and does not change the design :function of the SW system. The Oil Separator
- function is being transition to the Storm Water Pollution Protection Plan.
Attachments: Attach all 50.59 Review forms completed, as appropriate. (NOTE: ifboth a Screening and Evaluation are completed, no Screening No. is required.) FM-jxxT~,:::=y.) 50.59 Screening No. Rev. 50.59 Screening
-2015-041 50.59 Evaluation 50.59 Evaluation No. Rev.
* \JJ~ o..,J -n+tS SOLS~ SC-ReE'lJLt.J~ BEGA~ 8~ 3/c~/l~ so lT UTt.Ll;cES OL'D \:D~S .. T~ i<at£SU::> 'f=D~S Do N.OT1CC\-l)..ll~'f 0 e,_ Hiµ 0\1.0~ALL~ AP-F6Cl TI4t t.N 012.tL, p~ h~ ~fte/zolS
ZAP-100-06 Revision 25 Information Use ATTACHMENT E: 50.59 APPLICABILITY REVIEW FORM Activity/Document Number: EC 400985 and ECN 400986 ECN 400987 Revision Number: 0 Address the questions below for all aspects of the Activity. tf the answer is yes for any portion of the Activity, apply the identified process(es) to that portion of the Activity. Note that it is not unusual to have more than one process apply to a given Activity. See Section 4 ofthe Resource Manual (RM)'for additional guidance. I. Does the proposed Activity involve a change:
- 1. Technical Specifications or Operating License (10CFR50.90)? X NO YES See Section 4.2.1.1 of the RM
- 2. Conditions of License Quality Assurance program (10CFR50.54(a))?
Security Plan (10CFR50.54(p))? _X_NO _X_NO -- YES YES See Section 4.2.1.2 of the RM Emergency Plan (10CFR50.54(q))? _}(_NO YES
- 3. Specific Exemptions (10CFR50.12)? _X_NO YES See Section 4.2.1.5 of the RM
- 4. . Radiation Protection Program (10CFR20)? _X_NO YES See Section 4.2.1.6 of the RM
- 5. Fire Protection Program (applicable UFSAR or operating license
_X_NO YES See Section 4.2.1.7 of the RM condition)? -
- 6. Programs controlled by the Operating License or the Technical Specifications (such as the ODCM). _X_NO - YES See Section 4.2.1.7 of the RM
- 7. Environmental Protection Program _X_NO YES See Section 4.2.1.7 of the RM
- 8. Other programs controlled by other regulations. _)(_NO YES See Section 4.2.1 of the RM II. Does the pr:oposed Activity involve maintenance which restores SSCs to their origlnal condition or involve a temporary alteration supporting maintenance that will be in effect during at-power operations for 90 days _X_NO YES See Section 4.2.2 of the RM or less?
Ill. Does the proposed Activity involve a change to the:
- 1. UFSAR (including documents incorporated by reference) that is excluded from the requirement to perfonn a 50.5~ Review by _X_NO YES See Section 4.2.3 of the RM NEI 96-07 or NEI 98-03? -
- 2. Managerial or administrative procedures governing the conduct of
_X_NO YES See Section 4.2.4 of the RM facility operations -
- 3. Procedures for performing maintenance activities (subject to 10 CFR 50.65(a)(4))? _X_NO - YES See Section 4.2.4 of the RM
- 4. Regulatory commitment not covered by another regulation based See Section 4.2.3/4.2.4 of the
_X_NO YES change process (see NEI 99-04)? - RM IV. Does the proposed Activity Involve a change to the Independent Spent Fuel Storage Installation (ISFSI) (subject to control by 10 CFR 72.48) _X_NO - YES See Section 4.2.6 ofttie RM
- v. Does the proposed Activity involve a change to the Packaging &
Transportation of Radioactive Material? (subject to control by 10CFR71) _X_NO - YES Vi. Is the proposed activity a Decommissioning Activity that does NOT require a 50.59 Screening, as described in Attachment 1 of ZS-EG-100? _X_NO - YES Check one of the following: D If all asoects of the Activity are controlled by one or more of the above processes, then a 50.59 Screening is not required and the Activity may be implemented in accordance with Its governing procedure. x If any portion of the Activity is not controlled by one or more of the above processes, then process a 50.59 Screening for the portion not covered by any of the above processes. The remaining portion of the activity should be implemented In accordance with its governing procedure. This Exempt Change affects systems discussed in the DSAR that are Important to Defueled
- l. Condition.Signoff:
50.59Screener~r:~LJ: ~~tr (Circle 6~ (Print name)
- S~n:~ ~ . (Sl9li8tllre)
Date: Lf ti""" 1'.JlJ...
~1 2f ?4
ZAP 100-06 Revision25 Information Use ( ZAP 100-06 ATTACHMENT F: 50.59 SCREENING FORM 50.59 Screening No:___,.2~0. .1~5-
. . . .04
. .__1...___ _ _ _ _ _ _.Rev No:_~o_ _
Activity/Document No: Design Change 400985 Revision No: 0- - - I. 50.59 Screening Questions (Check correct response and provide separate written response providing the basis for the answer to each question) (See Section 5 of the Resource Manual (RM) for adQitional guidance):
- 1. Does the proposed Activity involve a change to an SSC that adversely affects an - YES X NO UFSAR described design function? (See Section S.2.2.1 of the RM)
Neither the SW system nor the Storm Drain Oil Separators are required SSC per the DSAR. There are no described design functions for these systems.
- 2. Does the proposed Activity involve a change to a procedure that adversely affects
- YES _X_NO how UFSAR described SSC design functions are performed or controlled? (See Section S.2.2.l of the RM)
Procedure changes associated with this design acticity will be reviewed under a separate 50.59.
- 3. Does the proposed Activity involve an adverse change to an element of a UFSAR - YES _X_NO described evaluation methodology, or use of an alternative evaluation methodology, that is used in establishing the design bases or used in the safety analyses? (See Section 5.2.2.3 of the RM)
This activity does not involve a change to an element of a DSAR described evaluation methodology, or use of an alternative evaluation methodology, that is used in establishing the design bases or used in the safety analyses.
- 4. Does the proposed Activity involve a test or experiment not described in the
- YES _X_NO UFSAR, where an SSC is utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is inconsistent with analyses or descriptions in the UFSAR? (See Section S.2.2.4 of the.RM)
The change activity is not a test or experiment.
.*5. Does the proposed Activity require a change in the Technical Specifications or
- YES _x_NO Operating License? (S~ Section 5.2.2.5 of the RM)
No changes are required to the Zion Technical Specifications. II. List the documents (e.g., UFSAR, Technical Specifications, other licensing basis, technical, commitments, etc.) reviewed, including sections numbers where relevant information was found (if not identified in the response to each question).
ZAP 100-06 i: Revision25 Information Use ZAP 100-06 ATTACHMENT F: 50.59 SCREENING FORM 50.59 Screening No;__.;;2--=0--.1=-5-.....0.41=----------'Rev
... No:___o~-
Activity/Document No: Design Change 400985 Revision No:_O_ __ Zion DSAR 3, 4.6, ODCM, FPR Ill. Select the appropriate conditions: x If all qµestions are answered NO, then complete the 50.59 Screening and implement the Activity per the applicable governing procedure. . If question 1, 2, 3, or 4 is answered YES and question 5 is answered NO, then a 50.59 Evaluation shall be performed. If questions 1, 2, 3, and 4 are answered NO and question 5 is answered YES, then a License Amendment is required prior to implementation of the Activity.
)
If question 5 is answered YES for any portion of an Activity, then a License Amendment is . required prior to implementation of that portion of the Activity. In addition, if question 1, 2, 3, or 4. is answered YES for the remaining portions of the Activity~ then a 50.59 Evaluation shall be performed for the remaining portions of the Activity. IV. Screening Signotfs: 50.59 Screener: Paul i. Beinecke Sign: u~ Dare: 3 I 11 !?s>t5 2015 (Print riame) (Signature) 50.59 Reviewer:~ (Print name) F-"k'o"Y-tJ SignP~FC.d
. (Signature)
Date: ~~2.ols-
') . ZionSolutions LLC ZS-2016-0042: Attachments ATTACHMENT-5 ECN# 2015-04 Installation of new liquid effluent radiation monitor for ORT-PR04 and dilution flow permissive for lake discharge valve OSOV-WDO 10
I' DCP2015-04 ECNlOlS-04 Attachment 4 ZS-WC-100 Design :Changes - DCPs, ECNs, FCRs, and DCRs Revision 10
\I 1-----~~~~~~~~~~~~~~~~~~~~~~~~~~~-'-~~...;.;...._:__.....:....:;~;.;____...;_s Information Use.
Exhibit A (page* At) ENGINEERING CHANGE NOTICE (Part 1) ECNNo.~ ISSUANCE: f I FOR CONSTRUCTION [ ] FOR COMMENT Page: I or 1-r Station: ZiQ!! [ J Safety Related DesignChangeNo. 2015-04 [X] Non-Sl!fety Related . Project No.(1toppLl Affected Unit: 0 [ ] Regulatmy Supp IO No. (itlJllll~ a Changes to previollllly Approved ECN [ ] System: lS Delcription of Desiga Change Request: _ Install new radiation monitor for ORT-PR04 .and_ add a dilution flow permissive for lake discharge valve OSOV-WDOlO. Reason for J;>i!iign CbllllgC: Change and action required (Provide reason for change, specific actions required, attach supporting documents, as applicable).
) The existing sensor"for ORT-PR04 has failed and compatible parts are unavailable. The dilution flow pertnissive iS an enhancement to the existing, system to ensure adequate dilution flow is maintained for lake releases.
INTERFACING COMMENTS by Design Group or. Name ofCommcmtm" (Printed) Signature of Ccmmmter Date CorNC Discipline - - Elect.II&C Mcehanical Structural \ D&D Operations - Olbars Prepared by: it ,,,71
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-=>rAzlJ:;7~ -
Approved.by: .J.2,UJ£JM .. - . Date: Date: "-17-1. Date: aft7/2Df.s All affected design docummits revised by (date): Vmifiedby; Date: Page I of 11
*DCP 2015-04 ECN2015-04 Attachment4 ZS-WC;-100 Design Changes - DCPs, ECNs, FCRs, and DCRs Revision 10 ) L-~~~~~-----~~~~---~-~~~~~-~~----L~~-===~~~~ fu~~~
Exhibit A (pageA2) . DESIGN CHANGE DOCUMENT-AFFECTED DOCUMENT LIST
. (Part 2)
Associated With: ECN - Comment DCP Number: 2015-04 X ECN - Construction
~_FCR Other:
Part 1 - General Information :_optional fur FCR Date Prepared: 16 June 2015
) Originator: James Hausser W.O. Number:._....::2~0~1~5-=03~1~-----
Description:
_ Install new radiation monitor for ORT-PR04 and add a dilution flow pemtissive for lake discharge valve OSOV-WDOlO Part 2 - Related Design Change Documents (i.e.. ECN,FCRl Ref. Re£ No. ~ Number No. J:Y.ru! Number
- 1. DCP .,- 2015-04::- s.
- 2. ECN 2015-04 6.
- 3. -;;. 7.
- 4. 8.
Prepaml By; ~ 7~ Dato &/11{/j ReviewedBy: ~
- Date ~-o~r.:-
Page2 of It 7
DCP2015-04
-~**
ECN 2015--04 Attachment 4 ZS-WC-100 Design Changes - DCPs, ECNs, FCRs, and DCRs Revision 10 Information Use Part 2 - Affected Design Documents DESIGN DOCUMENT (DD) n Related DCDs lncorp. Rev.
~ ~* (Ref# from Part or
* ** 2 Date (Optional)
Type Number Sheet Rev. Rev Code /Page No. Date (1-Dwg I 2-Calc 3-0ther) ECN Drawings Part 4
)
*'C' for Consttuetlon m: 'R' fur Record l
**'F for Funct1.onal .!!I 'D fur Detailed
) PreparedBy: f;;Ji.c 14--nate 6/11/ls ReviewedBy: ..... .~ D_ate t- n-1.;- Pa¥e3 of /7
.. DCP2015-04 ECN2015-04 Attachment 4 ZS-WC*lOO
.Design Changes -DCPs, ~CNs, FCRs, and DCRs Revision 10
) 1..-~~~~---~~~~~~~~~~~~~~~~~~~J.._~-=Info==nn==ati=*o~n~U~s.=....re Exhibit A (pageA3)
;Baek~~p -Cal~ulation Listing (Part 2) .
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. 7
DCP2015-04 ECN2015-04 Attachment 4 ZS-WC-100 Design Changes - DCPs, ECNs, FCRs, and DCRs Revision 10 Information Use Exhibit A (pageA4) CERrmICATION PAGE (Part 3)
*ECN No: 2015-04 Design Change No.: 2015-04
. Page 5 of . \ll
-_.-**-- ~---~ -- ----*
CERTIFICATION OF ECN NO. _ _ __;;;N--./A.. . . .___ _ _ _ ___;_
)
I certify that this Engineering Change Notice was prepared by me or under my supervision and that I am a registered Professional Engineer under the laws of the State of Illinois.
'l Certified by:_ _ _ _---:..:N=/A-=-----------Date:_*_ _ _ _ __
Seal
.PreparedBy: ~?~ Date t/t'-1/IS Reviewed By: ------' j;r Datet... 17- ,.;-
Pa~e S of 11
Station: Zion DCP2015-04 Affected Unit: 0 ECN2015-04 Part 4 - Construction Support Information
- 1. ORT-PR04/0SOV-WD010 Control Panel Construction Note:
Steps in Section 1 can be performed in any logical order at the discretion ~ ** of the responsible work group. \ I .a. Install components and wire according to Sketch 7 1.b. , Obtain PR04 electronics module from Engineering and mount on right side of control panel as shown on Sketch 1. 1.c. Request Engineering to program the Pico control relay. I .d. With Engineering assistance, apply power to the control panel and verify proper operation of the control relay, control switches, and indicating lights.
- 2. Field Installation Note:
The steps of section 2 can be performed in any logical order at the discretion of the responsible work group. 2.a. At unit 2 boric acid tank room, determinate and remove the test cart associated with ORT-PR04. 2.b. At unit 2 boric acid tank room, install new PR04/WD010 control panel on wall. 2.c. At unit 2 boric.acid tank room, determinate and remove ca.hies from 120 Vac junction box. 2.d. At unit 2 boric acid tank room, install new 120 Vac jUJ;lction box and terminal strip as depicted in$ketch 1. 2.e. At unit 2 boric acid tank room, terminate cable 04264 at temrinal strip in. new junction box as shown in Sketch l. 2.f. At unit 2 boric acid tank room, field route and tenninate Cable C at new 120 Vac junction box and PR04/WD010 control panel as shown on Sketches 1 and 7. ~ 2.g. At unit 2 boric acid tank room, terminate cable "B" in PR04/WD010 control panel as shown in Sketch 7. 2.h. At unit 2 boric acid tank room, plug OPS into wall outlet supplied by 120 Vac jlln.ction box. 2.i. At unit 2 boric acid tank room, plug cable B" into UPS as. depicted in Sketch 1. .) 2.j. Above 480 V SWGR 232, connect cables 75316 and 75323 as shown on Sketch 9. Prepan:dBy: ~n... 6/1?/l.r ReviewedBy: ~~Date C**/7- /!>,. Page6ofJ1
Station: Zion DCP2015-04 Affected Unit: 0 ECN201S..04 Part 4 - Construction Support Information 2.k. At Unit 2 valve house, field route cable OSWOOS from OSW1001A starter to flow transmitter OFIT-SW054B. 2.1. Terminate cable OSWOOS at OSWl OOlA starter and flow transmitter OFIT-SW054B as shown on Sketch 9. 2.m. .At new PR04/WD010 control panel, terminate the following cables as shown on Sketch 7:
*- Cable "B" from PR04 UPS
** Cable "C" :from* 120 Vac Junction Box
.;-.' Cable 75323
- Wire pair associated with ADS Alarm Zone 505
- f
- Wire pair associated with ADS Alarm Zone 506
** Wire pair associated with ADS Alarm Zone 512
- Wire pair associated with ADS Alarm Zone 513
- 3. Functional Testing
)
Note: Engineering and RP:*'f.echnician assistance are required for the following steps. Note: The steps in Section 3 can be performed in any logical order at the direction of Engineering and RP Instrument Technician. 3.a.
- Isolate qsoV-WDOl 0 to allow cycling of the valve for testing pw:poses.
3.b. Verify Dilution Pumps OSWlOOlA and OSWlOOlB are shut off. 3.c. .At PR04/WD010 control panel, verify all five fuses are pulled out. 3.d. At PR04/WD010 contr,ol panel, insert Fuse Fl and verify 24 Vdc power supply and PR04 electronics module are both energized. 3.e. At PR04/WD010 control panel, insert Fuse FS and verify all four (4) red lights on the control panel illuminate. 3.f. At PR04/WD010 control panel, PRESS PR04 Alarm Reset Push Button and VERIFY relays PR04~RLY01 and PR04-RL02 energize and remain energized (Ref. Sketch 3). ) 3.g. At PR04/WD010 control pan~l, insert Fuse F2 and verify Pico relay energizes. Prepared By: ~~ Date 6/Jlf/.r Reviewed By:
- Date~ *fl- t!z ..--
Station: Zion DCP2015..04 Affected Unit: 0 ECN2015-04 Part 4 - Construction Support Information 3.h. At PR04/WD010 control panel, insert Fuses F3 and F4. 3.i. At Engineering and RP Instrument Tech direction, verify the following (Lift Leads and install jumpers as* necessary to simulate normal/alarm conditions. Reset logic and alarms as necessary). .__ o Open Fuse Fl and verify light indication and ADS alanns are received for both PR04 Inst. Alarm and Inst. Fail.
- Induce PR04 high radiation alann and verify proper light indication and ADS alarm.
- Using a jumper, CYCLE Dilution Pump Running/Trip alarm and verify proper light indication and ADS alarm.
- Using a jumper, CYCLE low dilution pump flow alarm and verify proper light indication and ADS Alarm.
ti With ORT-PR04 Test Switch in TEST, verify valve cycles with receipt of either PR04 radiation or instrument fail alarm. Verify this operates independently of control switch for OSOV-WDOI 0 position as well as other alarm conditions.
) e* With OSOV-WDOlO control switch in AUTO, verifyOSOV-WDOlO closes upon -* receipt of any of the individual alanns. Also verify that the valve will NOT open until the appropriate reset button is actuated.
- ci With OSOV-WDOlO control switch in OPEN~ verifyOSOV-WDOlO remains open regardless ofORT-PR04 alarm status. Al~o verify valve closes upon receipt of any alarm other than ORT-PR04.
4~ Post Installation Calibration 4.a. Request RP perform the appropriate calibration sunreillances to enable placing ORT-PR04-in service. } Prepared By: ~ ~ Date f/11/lf ReviewedBy: ~: ; . Date t.-{l-1.:,- Page8 of~11
r-----~-----~-----------------------------------1 I I I I I Cable 04264 I Cable "C" 1 1 I 3/C#14 I 3/C#14 I I 1 J 120Vac JB
.:.i; RLC #31 Ckt"L"
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- Tank Room :
I I I I I I I I .1 I I I I I ORT-PR04 ORT-PR04 Alarm ~ Alarm Reset a0 a : I ORT-PR04 lhst. Fail ~ au Normal I Test Dilution Pump Trip/Off~ 0
~
0 Dil~tion Low Flow ~ ORT-PR04 OSOV-WD010 Open~ TO PR04 Sensor Test Switch PR04 UPS 0 Existing Equipment I I Installed Per ECN 389831 and TA 15-004 I I f Auto j Close I Open I: 0 SOV~WD010 (/) Logic Reset Cable"E"
- e>
OSOV-WD010
©. 7/C.#18 Cable "B" OSOV-WD010 Test Points Control switch 3/C#14 Cable"D" 3/C#14 Cable From ADS Alarm System 4-Pair #16 --~
See EC 399569 Cable 75323n5316 4/C#12----- CABLE
- 00. See EC 400987 "0426411' Sllpplyto 00 Outlet Box/
00 00 UPS Sketch 1 00 Part4
. GROUND - - + - - - " - . J ECN No. 2015~04 Isolation Valve Page '1 of 11 OSOV-WD010 Mod. 'No. 2015-04 120VAC Prepared by: ~ ?~
JB Date: 6/11-/t.rP IN#2BA Reviewed by:...r-<ll'.qb. .. TANK ROOM Date: t- iz-rs
OSOV-WD010 ORT-PR04 ORT-PR04 Control Switch Test SWitch Dilution Pump Dilution Pump Low Flow Running Alarm Close Auto Alarm Fail Open Test Normal I
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___.Y I Sketc.h 2 Part4 ECN No. 2015-04 Page JO of /~ Low Dilution PR04 PR04 Inst. WD01 OSolenoid Flow Alarm Fail Alarm lVlod.No.2015-04 Dilution Pump Trip/Trouble (Energize to Open) Alarm Prepared by: ~ '- ?.ftr,..- Date: 6/l~/1} Reviewed by: A;lk_ Date: /. -rz~i~ 7'
120 Vac (PR04 UPS)
---e---.....-.-------.,....----( . . Cont on Sketch 4 "i
Neutral
----~---~----------c' :,~*-'"~*_qf11~. . ,. -~if' -. ""'";C-k::~fuh 4 1A. F1 '~ 810
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5 PR04- 5 PR04- 3 PB-1 DC Power : ;: RLY01 :~ RLY02 : ;. PR04 Alann Supply 9 Seal-In 9 Seal-In 4 Reset Push Button 24Vdc
- !l ~- C2
...... l' C1 "85 11'"87 1~86
-----------------------~--------------~~~------~----,
Ludlum 2350-1 Data Logger I I ORT-PR04 I I I I I I Voltage Regulator 1-+~s~Vud~c:....__ _-11-.--1 Electronics ~A=la:u;rm~--------j: I 1 v 1s ::1-----+----t{)-----J NTE962 ModUI$ 5V-Normal ..-----;,_.. ...1--_ ____._1- - - - - ( / ) - - - - - - - - - - - . ........ u OV-Alarm [ 1J t Darlingto~ O c Array b [ NTE2019 0 [ J [
-{9 1: -- -1 Sketch 3 tt.=.:-:::*~ -:-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ....:.~~ - - - - - - - - - - - - - - - - - - -..- - - -~* Part4 Ground ECNNo. 2015-04 Page JI of I 'f Mod. No. 2015-04 Prepared by: ~ (. ~
Date: fi//1-//f . Reviewed by: rr21:J:.6 ._.,. Date: ~ -t7~r~,,.. _ ,r
120Vac Line FromSke~h32(PR04UPS) : I F2-1Aj :~~,.........-----~~~J----.------------------.-----------------------....----~----~...-----~------...------~------...----------------------------------------------..._---------------4a-.~ FromSke~h3~~~~N_eu_t_ra_l__________________-+__,......______t--~--------+--------------t--------------t-----------------t-------------r-------------------------------------~-1-----------...J,....~--
~' A10 i' A11 Diiution CS2 CS1 CS1 Pump PR04- PRO~
LB-3 RB- 3 6 6_.._ 3 PB-2 OSOV-W0010 AUTO OSOY-W0010 Logic : ~OFIT-SW0548 -
--'- RLY01 _,.... RLY02 RB-3 ORT-PR04
; :;: Test Swjtch - - SOV-WD010 LB-4 RB ... OPcN (Ref.Sk.6 & 10 (Sk. 03) 10 (Sk. 03) RS-4 TEST 4
- ..... LOGIC RESET (Ref. Sk. 5) (Ref. Sk. 5) EC400987) PUSH BUTTON (Ref. Sit. 5}
l~ A12 I~ A13 j' 811 l ' 812
~' 813 l' 814 L1 AL21 11 12 13 14 15 16 17 18 19 110 111 OuOO 0 0 0 0 0 0000 0 0 Allen Bradley Pico 1760-L18AWA 1 2 1 2 1 2 t 2 s1Q_,_9 S3CL_9. 849__,_9 S5*CL-9
,, 817 I TP1
' ' 818 l' 819 A7 .[;II"~---~
WD10-RLY04 13 WD10-RLY03 13
-o*-.
LGT5 DILUTION PMP OSOV- DILUTION PMP
> WD010 W OSOV-WD010 LOW FLOW
~ TRIPAIARM Open 14 (Ref. Sk. 5) 14 ALARM (Ref. Sk. 5)
-- A8vi
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TP2 F3 F4 Sketch 4 5A j' 820 2A
,, 821 Part4 ECN No. 2015-04 Page /'). of J 1-120 Mod. No. 2015-04 Vac ._"'To Sketch 5 RLC31 {
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- Date: c. -1 .,_ r:;,,.. ., 7
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~ 111 i 7 RLY02 1
- 1 :L 111 1 3 PR04 Inst. Alarm PR04 ln&t. Fail Trip/Off Dilution Low Row r P 1P RLY01 Inst. Fail (Sketch 3) (Sketch 4)
(Sketch 3) (Sketch 4) Inst.Alarm (Coil on Sketch 3) 14f P1P11 (Coil on Sketch 3) 14 11 12 LGT2 LGT3 LGT4 LGT1 ORT-PR04 DUutlon Pump Dllutlon RLY01, 02: Schneider Electric ORT-PR04 Inst. Fail Trip/Off Low Flow RXM4GB2BD (24 Vdc Col) Alarm From Sketch 4 Neutral RLC 31 ORT-PR04 Test Switch CS OSOV-WD010 WD10-WD10- Open Contacts Normal Test RLY04 Crose RLY03 Dilution PMP 1
- 1 :L 111 7 Dilution PMP Low Flow 1
- 1 :L 111 7 Contacts LB :y~
'Auto x LBL..-f~ x Trip/OFF Alarm (Collon 14 f P1P11 Alarm (Coil on 14 f P1P11 RB:Y~
x RB:Y~ x Sketch4) Sketch4) RLY03, 04: Schneider Electric RXM4GB2F7 (120 Vac Coil) Sketch 5 Part4 ECN No. 2015-04 Page J1 of Ir Mod. No. 2015-04 Prepared by: Qa;.., C ~ Date: 'Itr/1? Reviewed by: ~~ Date: t 1..:-
OSW1001A & OSW1001B Ref. EC400987 TBA-10 (Boric Acid Tank Room) RED (CA 75316)/ WHT( CA 75323) OSW1001A 9 Starter Cabinet 1 cs OFF 2 43X (CA OSW002) OSW1001B Starter Cabinet CAOSW002 1 43X
~ M OSW1001A OFF a starter Cabinet 2 44X i-----------+--4' 84X --i--~ 11 84X 11 M
M a a 83X 12 BLK (CA 75316)/BLK(CA 75323) (Boric Acid Tank Room) TBA-12 i1 Pico Relay i'l_ (Ref. Sk. 4) L2 :'
' Sketc*h 6
__.j Part4 ECN No. 2015-04 Page l'I of Ir Mod. No. 2015-04 Prepared by: ~ L ~ Date: ( /1-;/fi Reviewed by: ~ Date: c. r':J - ;:>
, - - - - - - - - ---~------- ----~--------------------~-
------------, I I EM I I I I Eiectronlcs Module r I
I I I I +6Vdc Tone I GND Out In I I I I ..... I I Q I I I I I I I I I I I. I
- II IC1 I TBD-3 EM-Tone Out I
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----------- -- - - - - - _:z1.~: Date: r- -17 *1:a,,,..
L------------------- I ----------------
r----RED---==--~;~~~~-----: I ~- I
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......... BU< =: BlK PR1&PR2 I BLU == WHT PR3&PR4 To PR04/0SOV-WD010 ORG == BLK PR3&PR4 ~-..1...,,..,_~
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-=CA~ 75~32;;::;3;--i Control Panel (Sketch 7)
Splice above 480V~~ff!~ ____ J Excerpt from ------ EC400987 TO OSW1001 B $TARTER '.f~.;'7-~~"'"-""::"'-~*~ ~*':""~-.=:;::;:-:~- -
- - - - ~-._ - - - - - - - - - - - - - - - - ------ -----------------,I :
(EC 400987 SKETCH 6) l*I h l'
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!~ I Iti' OFIT-SW054B ------------------------ 1
*OSW1001A starter L-------------~------- - - - - - - - - - - - - - - -
.J~ef. EC4009Q7)
Sketch*9 Part4 ECN No. 2015-04 Page If- of J 1 Mod. No. 2015-04 l ~ Prepared by: ~ ~ Dale: 6';'l 1/1~::.:rl__ Reviewed by: -4.~ 7 Date: t. - f::,
June 17, 2015 CZE-15-010 To: A. Orawiec
Subject:
Zion Station, Unit 1 & 2 Design Change No. 2015-004 System Codes: PR The Engineering Department has reviewed the subject design change in accordance with ZS-WC-100. Applicable design input requirements are included in the design change approval letter as applicable. *
- Description of Change:
This design change addresses the design issues required to replace ORT-PR04 with a new detector unit and electronics module. The functionality of the original equipment will be maintained. This design change also adds an interlock to ensure closure of OSOV-WDOl 0 due to inadequate dilution flow as measured by flow transniitter OFIT-SW054B. The logic for discharge valve OSOV:-WDOl 0 will be configured such that the valve will automatically close upon receipt of any of the following signals:
~* ORT-PR04 Alarm or Instrument Fail
- Trip of a dilution p~p or no dilution pump running e: U>w dilution flow from OFIT-SW054B Design Change Package:
The design for this Design Change is contained in ECN 2015-04 which is issued "For Construction" by this letter. 10 CFR 50.59 Evaluation I Decommissioning Impact Evaluation: 10CFR 50.59 screening 2015-066 was performed in accordance with AD-11 and is being transmitted along with this letter. This activity can be implemented without prior NRC approval. A Decommissioning Impact Evaluation was performed and it was concluded that the proposed activity is not restricted by 10 CFR 50.82. The ~valuation is also being transmitted along with this letter.
- DSAR I ODCM Impact Review:
DSAR Chapters 1 through 6 were reviewed for this design change. No DSAR changes are required as a result of this design change. Additionally, a review of the ODCM was conducted. No ODCM changes are planned as a result of this design change. ) Page 1of3
June 17, 2015 CZE-15-010 1 Applicable Codes and Standards: This design change shall be installed in accofdance with Zion Specification X-3646, which is the general work specification for mechanical, structural and electrical work as well as applicable site and Zion Solutions procedures. Installation requirements identified in ECN 2015-04 supersede X-3646 guidance. Basic Functions: ORT-PR04 monitors the liquid radiation waste release point to the service water system* and ultimately Lake Michigan. An alarm signal from ORT-PR04 will result in automatic closure of discharge valve OSOV-WDOl 0. The valve will also receive automatic closure signals due to either low dilution flow or trip of a running dilution pump. Industrial Safety: There are no industrial safety concerns associated with this design change. Installation Schedule I Outage Requirements: I Installation of this design change will require that valve OSOV*WDO 10 be out of service.
- ) Technical Specification Changes:
- The existing Technical Specifications do not require revision as a result of this design change. ,
ALARA I Fire Protection Review: Ali ALARA review was performed for this exempt change. The bulk of the work is being performed in the Unit 2 boric acid tank room. Any additional cable adds minimal combustibles and will not contn'bute significantly to the combustible loading. Impact of Pending Modifications or Temporary Alterations: A review of pending design changes has been completed. This design change does not impact any pending modifications. This Design Change Package (DCP) is being issued to document the installation of a new detector and electronics module for ORT-PR04 and to add an automatic closure of OSOV-WDOlO due to low flow in the dilution system. Identification of the Installer: This Design Change will be performed by Zion Solutions or an approved contractor. . } Page 2 of 3
June 17, 2015 CZE-15-010 Procurement Requirements: None Training Reguirements: None Security Requirements: None Technical Review: This design change is subject to a Technical Review in accordance with the requirements ofAD-1. A Technical Review has been performed and submitted with this design package (TR:.Ol 7-2015). If there are* any questions regarding this design change, please contact Jim Hausser at 224-789-4285. Prepared By: f~ l ~
/Jim Hausser
- Zion Solutions Engineering.
Approved By: ~F./2:t£
--D. Roth . . .
DrrectorofEngineering MAL ECN 50.59 50.82 Central File 1 1 1 1 D.Roth 1 l 1 1 J.Hausser 1 1 1 l T. Lukken 1 1 1. t Page 3of3
AD-11 RevisionO Information Use ATTACHMENT B-1 50.59 Review Coversheet Form
-=---=-----
Station: Zion
- Acth>ity/Document Number: DCP 2015--04._ _ _ _ _ _ _ _ _Revision Number: !!
Title:
Install New Radiation Monitor for ORT-PR04 NOTE: For SO.S9 Evaluations, information on this form will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2). Description of Activity: (Provide a briet; concise description of what the proposed activity involves.) This modification will replace the sensor and rate counting module for liquid radiation monitor ORT-PR04. A permissive signal requiring adequate dilution system flow to allow opening of lake discharge valve OSOV-WDOl 0 will also be added by this change.
- Reason for Activity:
(Discuss why the proposed activity is being performed.) The sensor for the existing radiation monitor has failed and compatible replacement parts are unavailable. The addition of the dilution flow pemnssive is a system enhancement.
- Effect of Activity:
(Discuss how the activity impacts plant operations, design bases, or safety analyses descn"bed in the UFSAR.) The radiation monitor will generate a signal to automatically close lake discharge valve OSOV-WD010 upon detection of a high radiation level. Likewise, the dilution flow permissive will cause an automatic closure of the lake discharge valve should dilution flow drop below prescn"bed levels. These automatic actions are enhancements to sampling and periodic ~onitoring to ensure compliance With the ODCM. The modification does not affect the accident evaluated in the DSAR. Summary of Conclusion for the Activity's 50.59 Review: (Provide justification for the conclusion, including sufficient detail to recognize and understand the essential arguments leading to the conclusion. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment Request, as applicable, is not required.) The modification only changes the specific devices used to monitor the liquid radiation waste discharge. The function of the devices remains unchanged. This modification does not represent a change to the facility as described in the DSAR and it may be installed under 10CFRS0.59 without prior NRC approval. Attachments: Attach all S0.59 Review forms completed, as appropriate. (NOTE: if both a Screening and Evaluation are completed, no Screening No. is required.) Forms Attached: (Check all that apply.) Applicability Review 1------1 x 50.59 Screening 50.59 Sc~ No. 2015-066 Rev. 0 ) 50.59 Evaluation 50.59 Evaluation No. Rev.
AD-11 Revision 0 Information Use
.I ATTACHMENT C-1 50.59 APPLICABILITY REVIEW FORM Actfvlty/Doeument Number:_ DCP 201S..04_ _ _ _ _ _ _ _ _ _ _ _Revisioo Number:_o._ _ __
Address the questions be1ow for all aspects of the Activity. If the answer is yes for any portion of the Activity, apply the identified process(es) to that portion of the Activity. Note Chat it is not unusual to have more than one process apply to a given Activity. See Section 4 of the Resource Manual (RM) fur additional guidance. I. Does the proposed Actimymvolve* a chiDge:. -
- 1. Technical Snccifications or Operating License (10 CFR 50.90)? xNO YES Sec Section 4.2.1.1 of the RM
- 2. Conditions ofLicense
_xNO - YES . Quality Assurance program (10 CFR SO.S4(a))? _x NO - YES Sec Section 4.2.1.2 oftheRM* Security Plan (IO CFR S0.54(p))? _xNO YES Emergency Plan (10 CFR 50.S4(q))? -
- 3. Specific Exemptions (10 CFR 50.12)? _xNO - YES See Section 4.2.l.5 of the RM YES See Section 4.2.1.6 of the RM
- 4. Radiation Protection Program (10 CFR20)?
- 5. Fire Protection Program (applicable UFSAR or operating license
_xNO
.JoNO - YES See Section 4.2.1.7 of the RM condition)?
- 6. Programs controlled by the Operating License or fhe TcclmicaJ Specifications (such as the ODCM).
_xNO
- YES See Section4.2.l.7 oftheRM 7.*Environmental Protection Program _xNO - YES See Section 4.2.1.7 of the RM See Section 4.2.1 of the RM
- 8. Other programs control1ed by other regulations. _xNO - YES 10CFRS0.37
) Does the proposed Activity involve maintenance which restores SSCs to their original condition or involve a temporary alteration supporting II.
maintenance that will be in effect during at-power operations for 90 days _xNO
- YES See Section 4.2.2 of the RM or less?
Ill. Does the nrooosed Activity involve a change to the:
- 1. UFSAR (including documents incorporated by reference) that is excluded from the requirement to perform a 50.59 Review by _xNO - YES See Section 4.23 of the RM NEI 96-07 or NEI 98-03?
- 2. Mariagerial or administrative procedures governing the conduct of _xNO
- YES See Section 4.2.4 of the RM facility operations
- 3. Proeedures for performing maintenance activities (subject to l 0 CFR
_xNO - YES See Section 4.2.4 of the RM 50.6S(a)(4))?
- 4. Regulatmy commitment not covered by another regulation based change process (see NEI 99-04)?
_xNO
- YES See Section 4.2.3/4.2.4 of the RM Does the proposed Activity involve a change to the Independent Spent IV. Fuel Storage Installation (ISFSl) (subje¢ to control by 10 CFR 72.48) _xNO .,
YES See Section 4.2.6 of the RM Does the proposed Activity involve a change to the Packaging &
- v. Transportation of Radioactive Material? (subject to control by 10 CFR 71)
_xNO -YES Is the proposed activity a Decommissioning Activity that requires a _xNO VI. - YES Change to DSAR Chapter 3, 4 or 5 thereby requiring a 50.59 Screening. Check one of the following: CJ If a)I asnccts of the Activity are controlled by one or more of the above p~ the~ a 50.59 Screening is nm required and the Activity may be implemented in accordance with its governing procedure. X If anv portion of the Activity is not controlled by one or more of the above processes, Chen process a 50.59 Screening fur the portion not covered by any of the above processes. The remaining portion of the activity should be implemented in ) accordancewithits~. * , ~
- I"""
Signotr: S0.59 Scrc:cn 150.59 Evalua Garv F. Fanning Si * * ~: £' */ 7- ~ . (Circle (Print name) (Sign ~
AD-11 Revision 0 Information Use ATTACHMENT D-1 50.59 Screening Form 50.59 Screening No. _2015-066_ Rev. No. ~o__ Activity/Document Number:_DCP 2015-04_ _ _ _ _ _ _ _ _ Revislon Number:_ _o___ I. 50.59 Screening Questions (Check concct response and provide separate written response providing the basis for the answer to each question) (See Section 5 of the Resource Manual (RM) for additional guidance):
- 1. Does the proposed Activity involve a change to. an SSC that adversely affects YES _x_NO
~~"
an UFSAR descn"bed design function? (See Section 5.2.2.1 of the RM) The function of liquid radiation monitor ORT-PR04 is unchanged by this modification. The only change is to the actual equipment used to perform the design function. The addition of the dilution flow permissive for the lake discharge valve iS a system enhancement.
- 2. Does the proposed Activity involve a change to a procedure that adverseiy * '*=?_).'ES _x_NO affects how UFSAR dcscnoed SSC design functions are performed or controlled? (See Section 5.2.2.2 of the RM)
The only procedures affected by this change are those directly related to the
. physical device installed. The function of the radiation monitor and responses J to 81ann conditions are not altered by this design. change.
- 3. Does the proposed Activity involve an adverse change to an element of a ~- -. YES _x_NO UFSAR descnbed evaluation methodology, or use of an alternative evaluation methodology, that is used in establishing the design. bases or used in the safety
(} analyses? (See Section S.2.2.3 of the RM) There are no evaluation methods altered by this change. This change will only alter the equipment used to monitor lake releases. Methods for detemtining the alarm setpoints ~not affected by this change.
- 4. Docs the proposed Activity involve a test or experiment not descnbed in the . ..
YES _x_NO UFSAR. where an SSC is utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is inconsistent with analyses or descriptions in the UFSAR? (See Section 5.2.2.4 of the RM) The replacement of the radiation monitor and addition of the flow interlock do not represent a test or experiment not descnbed in the UFSAR. The function of the radiation monitor is not altered by this change.
- 5. Does the proposed Activity require a change in the Technical Specifications or ~YES* _x_NO Operating License? (See Section S.2.2.5 of the RM)
The new radiation monitor equipment will support operation of the liquid~ waste system as described in DSAR sections 4.5 and 4.6. The riew monitoring equipment will also support plant operations as described in ODCM section 10.2.2.l and tables 12.2-1and12.2-2. No changes to anyplant licensing ,.i documents are required for this design change.
AD*ll Revision 0 Information Use II. List the documents (e.g., UFSAR, Technical Specifications, other licensing basis, technical, commitments, etc.) reviewed, including sections numbers where relevant information was found (if not identified in the response to each question). DSAR Change 2013-010 DSAR Chapters 1 through 6 Zion Stadon Offsite Dose Calculation Manual (0DCM) Permanently Defueled Technical Specifications (PDTS) Zion Station Unit 1 and 2 Composite Licenses IIL Select the appropriate conditions: If all questions are answered NO, then complete the S0.59 Screening and implement the Activity per x the applicable governing procedure. If question 1, 2, 3, or4 is answered YES and question 5 is answered NO, then a 50.59 Evaluation shall be perfornied. If questions 1, 2, 3, and 4 are answered NO and question 5 is answered YES, then a License Amendment is required prior to implementatiOn of the Activity. If question 5 is answered YES for any portion of an Activity, then a License Amendment is required prior to implementation of that portion of the Activity. In addition, if question 1, 2, 3, or 4 is answered YES for the remaining portions of the Activity, then a 50.59 Evaluation shall be performed for the remaining portions of the Activity. *
) IV. Screening Slgnoffs:
50.59 Screener: Gaty F. Fanning Date: t, t/7 /rt~ *
. (Print ipupe) 50.S9 Reviewer: D~~ F: k'o'N Date:~ ll'"ll~ii;;
(Print name)
- J
TECHNICAL REVIEW LETTER TR/017/2015 To: T. Orawiec Decommissioning Plant Manager Zion Station
Subject:
DCP 2015-004. Replace ORT-PR04 Summary: The purpose of this Technical Review Is to provide basis and justification for replacing the original ORT-PR04 detector and electronics unit with new equipment. This design change package will also add logic to automatically close OSOV-WD010 due to low dilution flow measured by flow transmitter OFIT-SW054B. Prepared By: James C. Hausser 6//7//S" Date Required review Dlsclpllnes: A,8,' 6'
- JZJ/r:/U Engineering Supervisor Qualified Technical Reviewers
/
l-17-1~. Discipline Date G-1Z?:-15 Discipline Date Signature Discipline Date
- I Concur and Approve: -~-.ZS:._!ll_.,,;,~CZ------
Deco"1mlSSIOning Plant Manager Distribution: Decommissioning Plant Manager Operations Manager Engineering Manager SRc*coordinator Master File
ZionSolutions LLC ZS-2016-0042: Attachments ATTACHMENT 6 Zion Station ODCM, Rev. 5
Revision 5 Aug 31, 2015 Zion Station Offsite Dose Calculation Manual Docket Numbers: 50-295, 50-304 and 72-1037 Page 1of267
Revision 5 Aug 31, 2015 OFFS/TE DOSE CALCULATION MANUAL TABLE OF CONTENTS PAGE Chapter 1 Introduction 3 Chapter 2 Regulations and Guidelines 4 Chapter 3 Pathways 13 Chapter 4 Introduction to Methodology 16 Chapter 5 Measurement 27 Chapter 6 Implementation of Offsite Dose Assessment Program 28 Chapter 7 References 29 Chapter 8 Deleted 34 Chapter 9 Deleted 35 Chapter 10 Radioactive Effluent Treatment System and Monitoring 36 Chapter 11 Radiological Environmental Monitoring Program 44 Chapter 12 Radiological Effluent Technical Standards 54 Appendix A Compliance Methodology 99 Appendix B Models and Parameters for Airborne and Liquid Effluent Calculations 129 Appendix C Generic Data 159 Appendix D Deleted 176 Appendix E Deleted 177 Appendix F Station Specific Data 178 Appendix 0 ODCM Bases and Reference Document 251 Page 2 of 267
Revision 5 Aug 31, 2015 CHAPTER 1 INTRODUCTION
1.0 INTRODUCTION
The Offsite Dose Calculation Manual (ODCM) presents a discussion of the following:
- The basic concepts applied in calculating offsite doses from Zion Station effluents.
- The regulations and requirements for the ODCM and related programs.
- The methodology and parameters for the offsite dose calculations used to assess impact on the environment and compliance with regulations.
The methodology detailed in this manual is intended for the calculation of radiation doses during routine (i.e., non-accident) conditions. The calculations are normally performed using a computer program. Manual calculations may be performed in lieu of the computer program. The dose effects of airborne radioactivity releases predominately depend on meteorological conditions (wind speed, wind direction, and atmospheric stability). For airborne effluents, the dose calculations prescribed in this manual are based on historical average atmospheric conditions. This methodology is appropriate for estimating annual average dose effects and is stipulated in the Bases Section of the Radiological Effluent Technical Standards (RETS). 1.1 STRUCTURE OF THIS MANUAL Chapters 1 thru 7 provide a brief introduction and overview of Zion Stations offsite dose calculation methodology and parameters. Chapters 10 thru 12 provide specific requirements for the treatment and monitoring of radioactive effluents covered by the Radiological Environmental Monitoring Program (REMP) and the Radiological Effluent Technical Standards (RETS). Appendices A and B provide detailed information on specific aspects of the methodology. Appendix C contains tables of values of the generic parameters used in offsite dose equations. Appendix F contains tables of values for the parameters used in the offsite dose equations. Appendix 0 provides description of the bases for the methodology and parameters discussed in the ODCM. Page 3 of 267
Revision 5 Aug 31, 2015 CHAPTER2 REGULATIONS AND GUIDELINES
2.0 INTRODUCTION
This chapter of the ODCM serves to illustrate the regulations and requirements that define and are applicable to the ODCM. Any information provided in the ODCM concerning specific regulations are not a substitute for the regulations as found in the Code of Federal Regulations (CFR) or Quality Assurance Project Plan (QAPP). 2.1 CODE OF FEDERAL REGULATIONS Various sections of the Code of Federal Regulations (CFR) require nuclear power stations to be designed and operated in a manner that limits the radiation exposure to members of the public. These sections specify limits on offsite radiation doses and on effluent radioactivity concentrations and they also require releases of radioactivity to be "As Low As Reasonably Achievable". These requirements are contained in 10CFR20, 10CFR50, 10CFR72 and 40CFR190. In addition, 40CFR141 imposes limits on the concentration of radioactivity in drinking water provided by the operators of public water systems. 2.1.1 10CFR20, Standards for Protection Against Radiation The 10CFR20 dose limits are summarized in Table 2-1. 2.1.2 Design Criteria (Appendix A of 10CFR50) Section 50.36 of 10CFR50 requires that an application for an operating license include proposed Technical Specifications. Final Technical Specifications are developed through negotiation between the applicant and the NRC. The Technical Specifications are then issued as a part of the operating license, and the licensee is required to operate the facility in accordance with them. The remaining Defueled Technical Specification requirements have been relocated to the QAPP. Section 50.34 of 10CFR50 states that an application for a license must state the principal design criteria of the facility. Minimum requirements are contained in Appendix A of 10CFR50. 2.1.3 ALARA Provisions (Appendix I of 10CFR50) Sections 50.34a and 50.36a of 10CFR50 require that the nuclear plant design and the station RETS have provisions to keep levels of radioactive materials in effluents to unrestricted areas "As Low As Reasonably Achievable" (ALARA). Although 10CFR50 does not impose specific limits on releases, Appendix I of 10CFR50 does provide numerical design objectives and suggested limiting conditions for operation. According to Section I of Appendix I of 10CFR50, design objectives and limiting conditions for operation, conforming to the guidelines of Appendix I "shall be deemed a conclusive showing of compliance with the "As Low As Reasonably Achievable" requirements of 10CFR50.34a and 50.36a." An applicant must use calculations to demonstrate conformance with the design objective dose limits of Appendix I. The calculations are to be based on models and data such that the actual radiation exposure of an individual is "unlikely to be substantially underestimated" (see 10CFR50 Appendix I, Section 111.A.1 ). The guidelines in Appendix I call for an investigation, corrective action and a report to the NRC whenever the calculated dose due to the radioactivity released in a calendar quarter exceeds one-half of an annual design objective. The guidelines also require a surveillance program to monitor releases, monitor the environment and identify changes in land use. Page 4 of 267
Revision 5 Aug 31, 2015 2.1.3 10CFR72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste During normal operations and anticipated occurrences, the annual dose equivalent to any real individual who is located beyond the Controlled Area must not exceed 25 mrem to the whole body, 75 mrem to the thyroid and 25 mrem to any other critical organ as a result of exposure to:
- Planned discharges of radioactive materials, radon and its decay products excepted, to the general environment,
- Direct radiation from ISFSI or MRS operations, and
- Any other radiation from uranium fuel cycle operations within the region.
2.1.4 40CFR190, Environmental Radiation Protection Standards for Nuclear Power Operations Under an agreement between the NRG and the EPA, the NRG stipulated to its licensees in Generic Letter 79-041 that "Compliance with Radiological Effluent Technical Specifications (RETS}, NUREG-0472 (Rev.2) for PWR's or NUREG-0473 (Rev.2) for BWR's, implements the LWR provisions to meet 40CFR190". (See reference 103 and 49.) The regulations of 40CFR190 limit radiation doses received by members of the public as a result of operations that are part of the uranium fuel cycle. Operations must be conducted in such a manner as to provide reasonable assurance that the annual dose equivalent to any member of the public due to radiation and to planned discharges of radioactive materials does not exceed the following limits:
- 25 mrem to the total body
- 75 mrem to the thyroid
- 25 mrem to any other organ An important difference between the design objectives of 10CFR50 and the limits of 40CFR190 is that 10CFR50 addresses only doses due to radioactive effluents. 40CFR190 limits doses due to effluents and also to radiation sources maintained on site. See Section 2.4 for further discussion of the differences between the requirements of 10CFR50 Appendix I and 40CFR190.
2.1.5 40CFR141, National Primary Drinking Water Regulations The following radioactivity limits for community water systems were established in the July, 1976 Edition of 40CFR141:
- Combined Ra-226 and Ra-228: ~ 5 pCi/L.
- Gross alpha (particle activity including Ra-226 but excluding radon and uranium): ~ 15 pCi/L.
- The average annual concentration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annual dose equivalent to the total body or any internal organ greater than 4 mrem/yr.
The regulations specify procedures for determining the values of annual average radionuclide concentration which produce an annual dose equivalent of 4 mrem. Radiochemical analysis methods are also specified . . The responsibility for monitoring radioactivity in a community water system falls on the supplier of the water. However, Zion Station has requirements related to 40CFR141 in their specific RETS. For calculation methodology, see Section A.6 of Appendix A. Page 5 of 267
Revision 5 Aug 31, 2015 2.2 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS The Radiological Effluent Technical Standards (RETS) were formerly a subset of the Technical Specifications. They implement provisions of the Code of Federal Regulations aimed at limiting offsite radiation dose. The NRC published Standard Radiological Effluent Technical Specifications for PWRs (Reference 2) as guidance to assist in the development of technical specifications. These documents have undergone frequent minor revisions to reflect changes in plant design and evolving regulatory concerns. The Radiological Effluent Technical Specifications have been removed from the Technical Specifications and placed in the ODCM as the Radiological Effluent Technical Standards (RETS) (see Reference 90). The Zion Station RETS are similar, but not identical to the guidance of the Standard Radiological Effluent Technical Specifications. 2.2.1 Categories The major categories found in the RETS are the following:
- Definitions A glossary of terms (not limited to the ODCM).
- Instrumentation This section states the Operability Requirements (OR) for instrumentation performance as well as the associated Surveillance Requirements. The conservative alarm/trip setpoints ensure regulatory compliance for both liquid and gaseous effluents. Surveillance requirements are listed to ensure ORs are met through testing, calibration, inspection and calculation. Also included are the bases for interpreting the requirements. The Operability Requirement (OR) is the ODCM equivalent of a Limiting Condition for Operation (LCO) as defined in both the NRC published Standard Radiological Effluent Technical Specifications and the stations' Technical Specifications.
- Liquid Effluents This section addresses the limits, special reports and liquid waste treatment systems required to substantiate the dose due to liquid radioactivity concentrations to unrestricted areas. Surveillance Requirements and Bases are included for liquid effluents.
- Gaseous Effluents This section addresses the limits, special reports and gaseous radwaste and ventilation exhaust treatment systems necessary for adequate documentation of the instantaneous offsite radiation dose rates and doses to a member of the public. Surveillance Requirements and Bases are included for gaseous effluents.
- Radiological Environmental Monitoring Program
_ This section details the Radiological Environmental Monitoring Program (REMP) involving sample collection and measurements to verify that the radiation levels released are minimal. This section describes the annual land use census and participation in an interlaboratory comparison program. Surveillance Requirements and Bases are included for environmental monitoring.
- Reports and Records This section serves as an administrative guide to maintain an appropriate record tracking system. The management of procedures, record retention, review/audit and reporting are discussed.
Page 6 of 267
Revision 5 Aug 31, 2015 2.3 OFFSITE DOSE CALCULATION MANUAL The NRG in Generic Letter 89-01 defines the ODCM as follows (not verbatim) (see Reference 90): The Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs and (2) descriptions of the Information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports. Additional requirements for the content of the ODCM are contained throughout the text of the RETS. 2.4 OVERLAPPING REQUIREMENTS In 10CFR20, 10CFR50, 10CFR72 and 40CFR190, there are overlapping requirements regarding offsite radiation dose and dose commitment to the total body. In 10CFR20.1301 the total effective dose equivalent (or TEDE) to a member of the public is limited to 100 mrem per calendar year. In addition, Appendix I to 10CFR50 establishes design objectives on annual total body dose or dose commitment of 3 mrem per reactor for liquid effluents and 5 mrem per reactor for gaseous effluents (see 10CFR50 Appendix I, Sections II.A and ll.B.2(a)). Per 10CFR72, the annual dose equivalent to a real individual beyond the controlled area boundary is limited to 25 mrem whole body from both effluents and direct radiation combined. Finally, 40CFR190 limits annual total body dose or dose commitment to a member of the public to 25 mrem due to all uranium fuel cycle operations. While these dose limits/design objectives appear to overlap, they are different and each is addressed separately by the RETS. Calculations are made and reports are generated to demonstrate compliance to all regulations. Refer to Tables 2-1, 2-2 and 2-3 for additional information regarding instantaneous effluent limits, design objectives and regulatory compliance. 2.5 DOSE RECEIVER METHODOLOGY Table 2-2 lists the location of the dose recipient and occupancy factors, if applicable. Dose is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures with the exception of dose from contained sources. The dose calculation methodology is consistent with the methodology of Regulatory Guide 1.109 (Reference 6), NUREG 0133 (Reference 14) and NRG ISG-13 Rev. 0, Spent Fuel Project Office Interim Staff Guidance - 13 Real Individual, May 17, 2000 (Reference 108). The "maximum individual" is characterized as "maximum" with regard to food consumption, occupancy and other usage of the area in the vicinity of the plant site. Occupancy of a "maximum individual" is not used in dose assessments from contained sources. Such a "maximum individual" represents reasonable deviation from the average for the population in general. In all physiological and metabolic respects the maximum individual is assumed to have those characteristics that represent averages for their corresponding age group. When calculating dose attributed to contained sources for the "maximum individual" dose receptor location, occupancy is defined as a habit for a "real individual" at that location. 100% occupancy is not assumed when calculating dose from contained sources. Finally Table 2-3 relates the dose component (or pathway) to specific ODCM equations and the appropriate regulation. Page 7 of 267
Revision 5 Aug 31, 2015 Table 2-1 Regulatory Dose Limit Matrix REGULATION DOSE TYPE DOSE LIMIT(s) ODCM EQUATION Airborne Releases: (quarterly) (annual) 10CFR50 App. I~ Gamma Dose to Air due to Noble Gas 5 mrad 10 mrad A-1 Radionuclides (per reactor unit) Beta Dose to Air Due to Noble Gas 10 mrad 20 mrad A-2 Radionuclides (per reactor unit) Organ Dose Due to Specified Non-Noble 7.5 mrem 15 mrem A-7 Gas Radionuclides (per reactor unit) Total Body and Skin Total Body 2.5 mrem 5 mrem A-3 Dose {if air dose is exceeded} Skin 7.5 mrem 15 mrem A-4 QAPP Organ Dose Rate Due to Specified Non- 1,500 mrem/yr A-16 Noble Gas Radionuclides (instantaneous limit, per site) Liquid Releases: (quarterly) (annual) 10CFR50 App. I~ Whole (Total} Body Dose 1.5 mrem 3 mrem A-17 (per reactor unit) Orqan Dose (per reactor unit) 5 mrem 10 mrem A-17 QAPP The concentration of radioactivity in liquid Ten (10) times the effluents released to unrestricted areas concentration values A-21 listed in 10CFR20 Appendix B; Table 2, Column2 Total Doses ': 10CFR20.1301 (a)(1) Total Effective Dose Equivalent q 100 mrem/vr A-25 10CFR20.1301 (d}, Total Body Dose 25 mrem/yr A-25 10CFR72.104 (a} and 40CFR190 Thyroid Dose 75 mrem/vr A-25 Other Orqan Dose 25 mrem/vr A-25 Other Limits ;t: 40CFR141 Total Body Dose Due to Drinking Water 4 mrem/yr A-17 From Public Water Systems Organ Dose Due to Drinking Water From 4 mrem/yr A-17 Public Water Svstems 1 These doses are calculated considering all sources of radiation and radioactivity in effluents. 2 These limits are not directly applicable to nuclear power stations. They are applicable to the owners or operators of public water systems. However, the Zion Station RETS requires assessment of compliance with these limits. For additional information, see Section A.6 of Appendix A. 3 Note that 10CFRSO provides design objectives not limits. 4 Compliance with 10CFR20.1301 (a)(1) is demonstrated by compliance with 40CFR190. Note that it may be necessary to address dose from on-site activity by members of the public as well. Page 8 of 267
Revision 5 Aug 31, 2015 TABLE 2-2 DOSE ASSESSMENT RECEIVERS Location; Occupancy if Dose Component or Pathway Different than 100% "Instantaneous" concentration limits in liquid Point where liquid effluents enter the unrestricted effluents area Annual average concentration limits for liquid Point where liquid effluents enter the unrestricted effluents area Direct dose from contained sources Dose receptor location and occupancy with respect to the habits of a real individual as described in EH&S TSD 13-009, "Member of the Public Dose from all Onsite Sources." Direct dose from airborne plume Receiver is at the unrestricted area boundary location that results in the maximum dose. Dose due to tritium and particulates with half- Receiver is at the location in the unrestricted area lives greater than 8 days for inhalation, where the combination of existing pathways and ingestion of vegetation, milk and meat, and receptor age groups indicates the highest potential ground plane exposure pathways. exposures. Ingestion dose from drinking water The drinking water pathway is considered as an additive dose component in this assessment only if the public water supply serves the community immediately adjacent to the plant. Ingestion dose from eating fish The receiver eats fish from the receiving body of water (lake) Total Organ Doses Summation of ingestion/inhalation doses Total Dose Summation of above data (Note it may also be necessary to address dose from on-site activity by members of the public.) Page 9 of 267
Revision 5 Aug 31, 2015 TABLE 2-3 DOSE COMPONENT/REGULATION MATRIX Regulation in which dose component is utilized Dose Component or Reference equation; 10CFR50 Pathway Comments 10CFR20 10CFR72 40CFR190 App. I "Instantaneous" concentration A-21: limits in liquid effluents Ten times the limits of Table 2, Col. x(2J 2, 10CFR20, Appendix B to
§§20.1001 - 20.2402 Annual average concentration 10CFR20, Appendix B to limits for liquid effluents §§20.1001 - 20.2402( 2) x(3J Direct dose from contained Section A.3.1 x x x sources Direct dose from radioactivity deposited on the ground A-7 and A-8 x x x x Inhalation dose from airborne effluents A-7 and A-9 ( 1J x x x x Ingestion dose from vegetables A-7, A10 and A-11 (1J x x x x Ingestion dose from milk A-7, A-12 and A-13 (1J x x x x Ingestion dose from meat A-7, A-14 and A-15 (1J x x x x Ingestion dose from drinking 1J water A-17, A-18 and A-19 ( x x x x Ingestion dose from eating fish A-17, A-18 and A-20 ( 1J x x x x Total Organ Doses A-25 x x x Total Effective Dose Equivalent A-25\'+I x Ingestion/inhalation dose assessment is evaluated for adult/teen/child and infant for 10CFR50 Appendix I compliance and for 10CFR20/40CFR190 compliance. Ingestion/inhalation dose factors are taken from Reg.
Guide 1.109 (Reference 6). 2 With the relocation of fuel to the ISFSI, noble gas releases can no longer occur. 3 Optional for 10CFR20 compliance. 4 Compliance with the Total Effective Dose Equivalent limits of 10CFR20 is demonstrated by compliance with 40CFR190. It may also be necessary to address dose from on-site activity by members of the public. Page 10 of 267
Revision 5 Aug 31, 2015 Figure 2-1 2 Simplified Chart of Offsite Dose Calculations Frequency of Catego~ Radionuclides Pathwall Text Section Rece~tor Code and Limits Calculation 1 Airborne RETS: As required by Non-Noble Child lnhalationb A.1.5 1500 mrem/yr Station Releases: Gases: (Any Organ) Instantaneous Procedure Ground A.1.4.1 Total Body Depositionc lnhalationc A.1.4.2 3 Non-Noble 10CFR50 : Gases: Vegetationd A.1.4.3.1 Monthly and Annually Milkd Four Age Groups 7.5 mrem/qtr, 15 mrem/yr A.1.4.3.2 (All Organs) Meatd A.1.4.3.3 RETS, 10 times 10CFR20 As Required by All Water A.2.2 Not Applicable Appendix B; Table 2; Col. Station 2 Procedure Water* and 3 Non-No_ble 10CFR50 : A.2.1 Total Body Liquid Gases 1 1.5 mrem/qtr 3 mrem/yr Fish Monthly Releases: Water* and 3 Non-Noble All Organs (4 10CFR50 : A.2.1 Gases Fish 1 Age Groups) 5 mrem/qtr 10 mrem/yr Total Body and Non-Noble 40CFR141: When Required Water* A.6 All Organs Gases 4 mrem/yr by RETS (Adult) Total Body 40CFR190: Uranium All releases 25 mrem/vr plus direct 40CFR190: Fuel All radiation from A.4.2 Thyroid (Adult) Annually 75 mrem/yr contained Cycle: sources Any Other Organ 40CFR190: (Adult) 25 mrem/yr Total Body 10CFR72: 25 mrem/vr All releases ISFSI and plus direct 10CFR72: Thyroid (Adult) Uranium All radiation from A.4.2 75 mrem/yr Annually Fuel Cycle: ISFSI plus any other radiations Any Other 10CFR72: Critical Organ 25 mrem/yr (Adult) All Licensed Total Effective Total Body and 10CFR20: All Dose A.5 All Organs Annually Operations: 100 mrem/yr Eauivalent (Adult) Page 11 of 267
Revision 5 Aug 31, 2015 Figure 2-1 (Cont'd) Notes for Figure 2-1:
- 1. Definition: Monthly means at least once per 31 days or once per month. See station RETS for exact requirements.
- 2. Additional Calculations: In addition to the calculations shown in this figure, monthly projections of doses due to radioactive materials are required for gaseous and liquid effluents. See Sections A.1.6 and A.2.5 of Appendix A.
- 3. 10 CFR 50 prescribes design objectives not limits.
- 4. If the air dose is exceeded, doses to the total body and skin are calculated. Total body objectives are 2.5 mrem/qtr and 5.0 mrem/year; the skin dose objectives are 7.5 mrem/qtr and 15 mrem/year.
a Evaluated at the unrestricted area boundary. b Evaluated at the location of maximum offsite X/Q. c Ground plane and inhalation pathways are considered to be present at all offsite locations. d Evaluated at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures. If no real pathway exists then a hypothetical cow-milk producer is evaluated at 5 miles in the highest D/Q sector. e Evaluated for the nearest downstream community water supply as specified in Table A-3 of Appendix A. The flow and dilution factors specified in Table F-1 of Appendix F are used. Evaluated for fish caught in the near-field region downstream of plant using the flow and dilution factors specified in Table F-1 of Appendix F. Page 12 of 267
Revisions Aug 31, 2015 CHAPTER3 EXPOSURE PATHWAYS
3.0 INTRODUCTION
Figure 3-1 illustrates some of the potential radiation exposure pathways to humans due to routine nuclear power station activities. These exposure pathways may be grouped into three categories:
- 1. Airborne Releases - Exposures resulting from radioactive materials released with gaseous effluents to the atmosphere.
- 2. Liquid Releases - Exposures resulting from radioactive materials released with liquid discharges to bodies of water.
- 3. Radiation from Contained Sources - Exposures to radiation from contained radioactive sources.
When performing radiation dose calculations, only exposure pathways that significantly contribute (~ 10%) to the total dose of interest need to be evaluated. The radiation dose from air and water exposure pathways is routinely evaluated. (See Regulatory Guide 1.109, Reference 6.) 3.1 AIRBORNE RELEASES For airborne releases of radioactivity, the NRG considers the following pathways of radiation exposure of persons:
- External radiation from radioactivity airborne in the effluent plume.
- External radiation from radioactivity deposited by the plume on the ground.
- Ingestion of radioactivity on, or in, edible vegetation (from direct plume deposition).
- Ingestion of radioactivity that entered an animal food product (milk or meat) because the animal ingested contaminated feed, with the contamination due to direct deposition on foliage.
- Inhalation of radioactivity in the plume.
Dose for airborne releases is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures. 3.2 LIQUID RELEASES For liquid releases of radioactivity (Figure 3-1 ), the NRG considers the following pathways of radiation exposure of persons:
- Ingestion of aquatic food (e.g., fish or invertebrate) obtained from the body of water to which radioactive station effluents are discharged.
- Ingestion (drinking) of potable water contaminated by radioactive liquid effluents discharged from the station.
For the aquatic food pathway, only fish is considered since it is the only significant locally produced aquatic food consumed by humans. Zion Station omits the pathways involving irrigation and animal consumption of.contaminated water because these pathways were determined to be insignificant. Zion Station also omits the pathway of radiation exposure from shoreline sediment because this pathway was also found to be insignificant (see Appendix 0, Section 0.3.2). Zion Station has also verified that the dose contribution to people participating in water recreational activities (swimming and boating) is negligible. (See Appendix 0, Table 0-3.) This pathway was not addressed explicitly in Regulatory Guide 1.109. Thus, Zion Station also omits dose assessments for the water recreational activities pathway.
- Page 13 of 267
Revision 5 Aug 31, 2015 Periodically, the Illinois Army Corps of Engineers dredges silt and debris from the river beds near Zion Station. As a part of the land use census, Zion Station will determine if the Corps performed dredging within one mile of the discharge point. If so, Zion Station Will obtain spoils samples, through its REMP vendor, for analysis. The impact to the offsite dose will be evaluated on a case by case basis and added to the ODCM when applicable. In addition, to assure that doses due to radioactivity in liquid effluents will be ALARA, concentrations will be limited to ten times (1 Ox) the values given in 10CFR20 Appendix B, Table 2; Column 2. 3.3 RADIATION FROM CONTAINED SOURCES Radioactivity contained within waste containers, including those present at the ISFSI, can produce radiation at offsite locations. Annual offsite radiation doses near Zion Station due to such sources have the potential to challenge annual dose limits to members of the public dLie to direct radiations. Additions or rearrangements of waste storage locations that may impact the offsite dose through increases to the direct radiation levels are monitored through site administrative processes and procedures. Page 14 of 267
Revision5 Aug 31, 2015 Figure 3*1 Radiation Exposure Pathways to Humans Nuclear Power Plant Contained Sources Ingestion of Potable Water Liquid Effluent Releases Ingestion of Aquatic Food Inhalation Ingestion Deposition onto Vegetation Ingestion by Ingestion of Animals Milk and Meat Airborne Effluent Deposition onto Direct Radiation Soil Exposure Direct Radiation Exposure Human Page 15 of 267
Revision 5 Aug 31, 2015 CHAPTER4 METHODOLOGY
4.0 INTRODUCTION
This chapter provides an introduction to the methodology used at the Zion Station to calculate offsite radiation doses. Additional explanation and details of the methodology are provided in Appendices A and B. Appendix A discusses each dose limit in the RETS and provides the associated assessment equations. Appendix B describes methods used to determine values of parameters included in the equations. 4.1 IMPORTANT CONCEPTS AND PARAMETERS 4.1.1 Dose The dose calculation equations contained in the ODCM are based on two types of exposure to radiation; external and internal exposure. The first type of exposure is that resulting from radioactive sources external to the body (including radiation emanating from an effluent plume, radiation emanating from radioactivity deposited on the ground and radiation emanating from contained sources (also referred to as direct radiation)). Exposure to radiation external to the body only occurs while the source of the radioactivity is present. It should be noted that with the relocation of the fuel from the Spent Fuel Pool to the ISFSI there is no longer an exposure pathway from noble gases which affects the dose impacts at the Zion Station. Although noble gases are no longer included as an effluent from Zion Station activities, the associated information included in this chapter of the ODCM will remain at this time for historical purposes. Internal exposure occurs when the source of radioactivity is inside the body. Radiation can enter the body by breathing air containing the radioactivity, or by consumption of food or drinking water containing radioactivity. Once radioactivity enters the body and becomes internal radiation, a person will continue to receive radiation dose until the radioactivity has decayed or is eliminated by biological processes. The dose from this type of exposure is also termed dose commitment, meaning that the person will continue to receive dose even-though the plume containing the radioactivity has passed by the individual, or even-though the individual is no longer drinking water containing radioactivity. The regulations addressed by the ODCM may require assessment of either type of exposure to radiation or of both types in summation. The term dose is used instead of the term "dose equivalent," as defined by the International Commission on Radiological Units and Measurements {ICRU). When applied to the evaluation of internal deposition of radioactivity, the term "dose," as used in the ODCM, includes the prospective dose component arising from retention in the body beyond the period of environmental exposure, i.e. the dose commitment. The dose commitment is evaluated over a period of 50 years. 4.1.2 Exposure Pathways All of the exposure pathways are discussed in Chapter 3. This section presents the exposure pathways addressed by Zion Station in the ODCM and associated software. For releases of radioactivity in airborne effluents the primary pathways are the following:
- Direct radiation from an effluent plume.
- Direct radiation from radioactivity deposited on the ground by a plume.
- Inhalation of radioactivity in a plume.
- Ingestion of radioactivity that entered the food chain from a plume that deposited radioactivity on vegetation.
For releases of radioactivity in liquid effluents, the exposure pathways considered are human consumption of water and fish. Page 16 of 267
Revision 5 Aug 31, 2015 When determining total doses, as required by 10CFR20, 10CFR72 and 40CFR190, Zion Station considers exposure to radiation emanating from onsite radioactive waste. 4.1.3 Categories of Radioactivity Radionuclide content of effluent releases from Zion Station can be categorized according to the characteristics of the radionuclides. In evaluating doses associated with a particular pathway, only those categories of radionuclides that significantly contribute to the dose need to be included in the dose calculations (See Section 3.0). The categories of radionuclides considered by Zion Station for each of the airborne pathways are summarized in Table 4-1. Selection of the significant airborne pathways was based on the following:
- The requirements in the RETS (see discussion in Appendix A),
- Applicable regulatory guidance (References 6 and 14), and
- A study of the potential radiological implications of nuclear facilities in the upper Mississippi River basin (Reference 20).
4.1.4 Atmospheric Release Point Classifications The dose impact from airborne release of radioactivity is determined by the height of the release of the effluent plume relative to the ground and by the location of the dose recipient. The height an effluent plume maintains as it travels above the ground is related to the elevation of the release point and to the height of structures immediately adjacent as follows:
- If the elevation of the release point is sufficiently above the height of any adjacent structures, the plume will remain elevated for considerable distances.
- If the elevation of the release point is at or below the heights of adjacent structures, the plume is likely to be caught in the turbulence of the wakes created by wind passing over the buildings. The plume elevation would then drop to ground level.
- If the elevation of the release point is not significantly above the heights of adjacent structures, then the plume may be elevated or at ground level.
For the calculations of this manual, each established release point has been designated as belonging to one of three release point classifications: Stack (or Elevated) Release Points (denoted by the letter Sor subscripts) These are release points approximately twice the height of adjacent solid structures. Releases are treated as elevated releases unaffected by the presence of the adjacent structures. Ground Level Release Points (denoted by the letter G or subscript g) These are release points at ground level or lower than adjacent solid structures. Releases are considered drawn into the downwind wake of these structures and are treated as ground level releases. Vent (or Mixed Mode) Release Points (denoted by the letter V or subscript v) These are release points as high or higher than adjacent solid structures but lower than twice the structure's heights. These releases are treated as a mixture of elevated and ground level releases. The proportion of the release attributed to either elevated or ground level in a vent release is determined by the ratio of stack exit velocity to the wind speed (see Section B.1.2.4 of Appendix B). The definitions of these classifications are based on Regulatory Guide 1.111 (Reference 7). Zion Station has no Stack (Elevated) or Vent (Mixed Mode) release points, therefore; all releases at Zion Station are considered Ground Level. Page 17 of 267
Revision 5 Aug 31, 2015 4.1.5 Historical Average Atmospheric Conditions The dispersion characteristics of airborne effluents from a nuclear power station are dependent on weather conditions. Meteorological factors that directly affect the concentration of airborne radioactivity in c;i plume include the following:
- Wind Direction The concentration of radioactivity is highest in the direction toward which the wind is blowing.
- Wind Speed Greater wind speeds produce more dispersion and consequently lower concentrations of radioactivity.
- Atmospheric Turbulence The greater the atmospheric turbulence, the more a plume spreads both vertically and horizontally.
For calculations in this manual, the degree of turbulence is classified by use of seven atmospheric stability classes, designated A (extremely unstable) through G (extremely stable). The seven classes and some of their characteristics are listed in Table C-4 of Appendix C. Meteorological conditions strongly impact the values of various parameters applied in the dose calculations of this manual. These include:
- The Relative Concentration Factors x/Q and gam ma-x!Q (Section 4.1.6)
- The Relative Deposition Factor D/Q (Section 4.1. 7)
The bases sections of the Standard Radiological Effluent Technical Specifications (guidance documents NUREGs 0472, 0473, 1301 and 1302) and the RETS specify that dose calculations be based on "historical average atmospheric conditions". Therefore, this manual provides values for the,above parameters that are based on Zion Station historical average meteorological conditions. These values were obtained by averaging hourly values of the parameters over a long-term, several-year period of record. The averaging period was based on calendar years in order to avoid any bias from weather conditions associated with any one season. The period of record is identified in each of the tables providing the values (see Appendix F). 4.1.6 Relative Concentration Factors xJQ and Gamma-x/Q A person immersed in a plume of airborne radioactivity is exposed to radiation from the plume and may also inhale some of the radioactivity from the plume. The concentration of radioactivity in air near the exposed person must be calculated to adequately evaluate doses resulting from any inhalation. The relative concentration factor xlQ (referred to as "chi over Q") is used to simplify these calculations. xfQ is the concentration of radioactivity in air, at a specified location, divided by the radioactivity release rate. x!Q has the following units: 3 Units of xJQ = (µCi/m ) I (µCi/sec)= sec/m 3 Zion Station values of x!Q are provided in Table F-5 of Appendix F. These values.are based on historical average atmospheric conditions (see Section 4.1.5). For each of the release point classifications (eg. stack, vent and ground level) and for the 16 compass-direction sectors (N, NNE, etc.), Table F-5 provides the maximum value of xlQ for locations at or beyond the unrestricted area boundary. The value of x!Q for each sector reflects the fraction of time that the wind blew into that sector and the distribution of wind speeds and atmospheric stability classes during that time. Note that the value would be zero if the wind never blew into the sector. Page 18 of 267
Revision 5 Aug 31, 2015 The gamma-x/Q provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. It is used in place of the semi-infinite plume model that tends to underestimate gamma air dose for elevated plumes. Use of the gamma-X/Q also corrects for the tendency of the semi-infinite plume model to overestimate gamma air dose for mixed mode and ground level releases. The methodologies for determining x/Q and gamma-x/Q are discussed in detail in Section B.3 of Appendix B. 4.1.7 Relative Deposition Factor D/Q As a plume travels away from its release point, portions of the plume may touch the ground and deposit radioactivity on the ground and/or on vegetation. Occurrences of such deposition are important to model since any radioactivity deposited on the ground or on vegetation may directly expose people and/or may be absorbed into food products which can ultimately be ingested by people. The relative deposition factor is used to simplify the dose calculations for these pathways. The relative deposition factor D/Q is the rate of deposition of radioactivity on the ground divided by the radioactivity release rate. Its value was determined for specific conditions. In this manual it has the following units: Units of D/Q =[(pCi/sec)/m 2
] I (pCi/sec) =1/m 2 The values of D/Q are affected by the same parameters that affect the values of x!Q: release characteristics, meteorological conditions and location (see Section 4.1.6). Zion Station values of D/Q are provided in Appendix F Tables F-5 and F-6. These values are based on historical average atmospheric conditions (see Section 4.1.5).
For each release point classification and for each of the 16 compass-direction sectors {N, NNE, etc.), Table F-5 provides the maximum value of D/Q for locations at or beyond the unrestricted area boundary. In Table F-6, values of D/Q are given for the locations of the nearest milk and meat producers within 5 miles of Zion Station. The methodology for determining D/Q is discussed in Section B.4 of Appendix B. 4.1.8 Dose Factors Various dose factors are used in this manual to simplify the calculation of radiation doses. These factors are listed in Table 4-2. Definitions of these factors are given in the remainder of this chapter. Methods of determining their values are addressed in Appendix B. 4.2 AIRBORNE RELEASES 4.2.1 Gamma Air Dose The term 'gamma air dose' refers to the component of dose absorbed by air resulting from the absorption of energy from photons emitted during nuclear and atomic transformations, including gamma rays, x-rays, annihilation radiation, and Bremsstrahlung radiation (see foetnote on page 1.109-19 of Regulatory Guide 1.109). The noble gas dose factors of Reg. Guide 1.109, Table B-1 are based upon assumption of immersion in a semi-infinite cloud. For ground level and mixed mode releases this tends to overestimate the gamma air dose arising from a plume that is actually finite in nature. For elevated releases, the Reg. Guide 1.109 noble gas dose factors will underestimate exposure as they consider only immersion and not that portion of exposure arising from sky shine. At distances close in to the point of elevated release, the ground level co~ncentration as predicted by xJQ will be essentially zero. In such a case, the sky shine component of the exposure becomes significant and must be considered. The gamma-x/Q provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. The methodology of Reg. Guide 1.109, Section C.2 and Appendix B provide the methodology for calculating finite cloud gamma air dose factors from which the gamma-x/Q values can be derived. Section B.5 addresses the calculation of these dose factors." Page 19 of 267
Revision 5 Aug 31, 2015 Three gamma-x/Q values are defined: (x/Q)/, (x/Q)/ and (x/Q)9Y for stack, vent and ground level releases, respectively. Section B.3.5 addresses the calculation of the gamma-x/Q values. 4.2.1.1 Finite Cloud Gamma Air Dose Factor The finite cloud gamma air dose factor is determined by calculating the gamma dose rate to air (at a specific location and corresponding to a given release rate) and dividing that dose rate by the corresponding release rate: Finite Cloud Gamma Air Dose Factor= [(mrad/yr)/(µCi/sec)] The methodology for this calculation is discussed in Section B.5 of Appendix B. The calculation is complex because the dose rate at any given point is affected by the radioactivity concentration and distance. Calculation of the finite cloud gamma air dose factor takes into consideration release characteristics, meteorological conditions and location (see Section 4.1.6). Additionally, the value is affected by radiological parameters: the distribution of energies and intensities for gamma emissions from each specific radionuclide and the photon attenuation characteristics of air. In the ODCM, station-specific values of gamma dose factors are provided for Zion Station in Appendix F, Table F-7. These values are based on historical average atmospheric conditions (see Section 4.1.5). For the release point classification and for each of the 16 compass-direction sectors, Table F-7 provides the maximum value of the gamma air dose factor for noble gas radionuclides at the unrestricted area boundary. The value includes a correction for radioactive decay during transport of the radionuclide from the release point to the dose calculation location. 4.2.1.2 Semi-Infinite Cloud Gamma Air Dose Factor The semi-infinite cloud gamma dose factor is the gamma air dose rate divided by the concentration of radioactivity in air at the dose calculation location. Values of these gamma dose factors are radionuclide specific and are provided in Appendix C, Table C-9. The semi-infinite cloud gamma dose factor is used in conjunction with gamma-x/Q to calculate noble gas gamma air dose and dose rate for elevated and finite noble gas plumes. The gamma-x/Q is defined such that for a given finite cloud the semi-infinite cloud methodology will yield the same gamma air dose as the finite cloud methodology. 4.2.2 Beta Air Dose The term 'beta air dose' refers to the component of dose absorbed by air resulting from the absorption of energy from emissions of beta particles, mono-energetic electrons and positrons during nuclear and atomic transformations (see the footnote on Page 1.109-20 of Regulatory Guide 1.109). The Beta Air Dose Factor The beta air dose factor is the beta air dose rate divided by the concentration of radioactivity in air at the dose calculation location. Values of the beta air dose factor are radionuclide specific and are provided in Appendix C Table C-9. 4.2.3 Total Body Dose and Dose Rate Total Body Dose Equation A-3 of Appendix A is used to calculate dose to the total body from noble gas radionuclides released in gaseous effluents. The total body dose equation is similar to that used to calculate gamma air dose (Equation A-1 of Appendix A). Page 20. of 267
Revision 5 Aug 31, 2015 Total Body Dose Rate Equation A-5 of Appendix A is used to calculate dose rate to the total body. The assumptions used for this equation are the same as those used in the calculation of total body dose (Equation A-3 of Appendix A) except that any shielding benefit (dose attenuation) provided by residential structures is not applied. Since the calculation is for the maximum instantaneous dose rate, the dose recipient may be out of doors when exposed and would not be shielded from the exposure by any structural material. The Total Body Dose Factor The total body dose factor is the total body dose rate divided by the radioactive release rate. Values for the total body dose factor are site specific and are provided in Table C-9 of Appendix C. 4.2.4 Skin Dose and Dose Rate Skin Dose Equation A-4 of Appendix A is used to calculate dose to skin from noble gas radionudides released in gaseous effluents. The skin dose is the summation of dose to the skin from beta and gamma radiation. The equation for beta dose to skin is similar to that used to calculate beta dose to air (Equation A-2 of Appendix A) except that beta skin dose factors are used instead of beta air dose factors. The beta skin dose factor differs from the beta air dose factor by accounting for the attenuation of beta radiation by the dead layer of skin. The dead layer of skin is not susceptible to radiation damage and therefore is not of concern. The beta dose to the skin from non-noble gases is insignificant and is not calculated for the reason described in Section 4.1.3. When calculating the beta contribution to skin dose, no reduction is included in the calculations due to shielding provided by occupancy of residential structures. The equation for gamma dose to skin is similar to that used to calculate gamma dose to air except for the following:
- Equation A-4 of Appendix A includes a unit's conversion factor 1.11 rem/rad to convert from units of gamma air dose (rad) to units of tissue dose equivalent (rem).
- Equation A-4 of Appendix A includes a dimensionless factor of 0.7 to account for the shielding due to occupancy of residential structures.
Equation A-4 of Appendix A uses gamma air dose factors not gamma total body dose factors. When calculating gamma dose to skin, no reduction is applied for the attenuation of radiation due to passage through body tissue (dead layer of skin). Skin Dose Rate Equation A-6 of Appendix A is used to calculate dose rate to skin. The assumptions are the same as those used in the calculation of skin dose (Equation A-4 of Appendix A) except that no credit is taken for shielding of gamma radiation by residential structures. The dose recipient may be outdoors when exposed and the maximum instantaneous dose rate is of concern. The Skin Dose Factor Values of the beta air dose factors and skin dose factors are nuclide specific and are provided in Table C-9 of Appendix C for 15 noble gas radionuclides. 4.2.5 Ground Radiation Equations A-7 and A-8 of Appendix A are used to calculate the total body dose due to non-noble gas radionuclides released in gaseous effluents and deposited on the ground. Page 21 of 267
Revision 5 Aug 31, 2015 Comment Note that if there is no release of radionuclide i during a given time period, then the deposition rate is zero, the ground plane concentration is zero and the resulting dose due to ground deposition is zero. If there is a release of radionuclide i, the ground concentration is computed as if that release had been occurring at a constant rate for the ground deposition time period. The Ground Plane Dose Conversion Factor The ground plane dose conversion factor is the dose rate to the total body per unit of radioactivity concentration on the ground. Values of the ground plane dose conversion factor that are calculated by assuming constant concentration over an infinite plane are provided for various radionuclides in Table C-10 of Appendix C. 4.2.6 Inhalation Dose Radioactivity from airborne releases of particulate and tritium can enter the body through inhalation. Equations A-7 and A-9 of Appendix A are used to calculate dose commitment to the total body or organs due to inhalation of non-noble gas radionuclides released in gaseous effluents. The Inhalation Dose Factor Values for the inhalation dose commitment factor are nuclide specific and are taken from Reg. Guide 1.109 (Reference 6) Tables E-7, 8, 9 and 10. These tables include data for four age groups (adult, teenager, child and infant) and seven body organs. Dose Rate The inhalation dose rate is the rate at which dose is accrued by an individual breathing contaminated air. Equation A-16 of Appendix A is used to calculate dose commitment rate to an organ due to inhalation of non-noble gas radionuclides. The assumptions are the same as used in the calculation of inhalation dose. The dose rate is determined for the child age group in accordance with the guidance found in NUREGs 0472, 0473, 1301and1302 (References 2, 3, 105 and 106). 4.2.7 Ingestion Airborne releases of particulate and tritium can enter the food chain through deposition on vegetation. The radioactivity can be ingested by humans who consume the vegetation or who consume products (e.g., milk or meat) of animals who have fed on the contaminated vegetation. Zion Station may consider the following ingestion pathways:
- Vegetables
- Milk
- Meat Equations A-7 and A-1 O through A-15 of Appendix A are used to calculate the dose due to ingestion of food containing non-noble gas radionuclides released in gaseous effluents. Dose is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures.
Values _of the ingestion dose commitment factors are taken from Reg. Guide 1.109 Tables E-11, 12, 13 and 14: These tables include data for four age groups and seven organs. The equations used for radioactivity concentration on vegetation and in milk, and meat are discussed in Appendix A. Page 22 of 267
Revision 5 Aug 31, 2015 4.3 LIQUID RELEASES The evaluation of dose due to releases of radioactivity in liquid effluents is required to confirm compliance with the provisions of RETS related to 10CFR50 Appendix I. The ODCM, Section 3.2 and Figure 3-1 list some of the pathways by which radioactivity in liquid effluents can impact man. The pathways used by Zion Station to calculate dose from liquid effluents are ingestion by drinking water and by eating fish from the body of water receiving station liquid discharges. Zion Station obtains the dose commitment due to radioactivity in liquid effluent releases by summing the dose commitments from the drinking water and fish pathways depending upon their presence. Equations A-17 through A-20 of Appendix A are used to calculate dose for the member of the public due to consumption of drinking water and fish. The radioactivity concentration in water is obtained by dividing the quantity of radioactivity released by the volume of water in which the release is diluted. The result can be modified by a factor to represent any additional dilution that might occur. The radioactivity concentration in fish is the product of the radioactivity concentration in water and a bioaccumulation factor. The dilution factors for fish may be different from those for water. (The fish may be caught at a location different from where drinking water is drawn.) The bioaccumulation factor accounts for the fact that the quantity of radioactivity in fish can build up with time to a higher value relative to the concentration of the radioactivity in the water they consume. The bioaccumulation factor is the equilibrium ratio of the concentration of radionuclide i in fish to its concentration in water. The same values are used for the bio-accumulation factor at Zion Station. These values are provided in Appendix C, Table C-8. 4.4 CONTAINED SOURCES OF RADIOACTIVITY In addition to the total body, skin and single organ dose assessments previously described, an additional assessment is required. The additional assessment addresses radiation dose due to radioactivity contained within the nuclear power station and its structures. 4.4.1 Deleted 4.4.2 Onsite Radioactive Waste and Radioactive Material Storage Facilities Low-level radioactive waste and radioactive material may be stored at Zion Station in the following types of locations:
- Concrete Rad Vaults
- Miscellaneous Shipping Containers
- Existing and temporary support structures Spent Fuel is stored at the Independent Spent Fuel Storage Installation. Administrative controls are implemented by Zion Station to ensure compliance to applicable regulations. The impact to the offsite dose from contained sources shall be documented in site Technical Support Documents. In addition, a 10CFR50.59 analysis may be required for selected radwaste storage facilities.
4.5 TOTAL DOSE REQUIREMENTS 4.5.1 Total Effective Dose Equivalent Limits; 10CFR20 and 40CFR190 10CFR20 requires compliance to dose limits expressed as "Total Effective Dose Equivalent" (TEDE). Although annual dose limits in 10CFR20 are now expressed in terms of TEDEs, 40CFR190 limits remain stated as organ dose. The NRC contim1es to require 10CFR50 Appendix I and 40CFR190 doses to be reported in terms of organ dose and not TEDE. Due to the fact that organ dose limits set forth in 40CFR190 are substantially lower than those of 10CFR20 (25 mrem/yr vs. 100 mrem/yr), the NRC has stated that demonstration of compliance with the dose limits in 40CFR190 will be deemed as demonstration of compliance with the dose limits of 10CFR20 for most facilities (Reference 104). Page 23 of 267
Revision 5 Aug 31, 2015 In addition to compliance with 40CFR190, it may be necessary for a nuclear power plant to address dose from on-site activity by members of the public. 4.5.2 Total Dose For Uranium Fuel Cycle Zion Station is required to determine the total dose to a member of the public due to all uranium fuel cycle sources in order to assess compliance with 40CFR190 as part of demonstrating compliance with 10CFR20. The total dose for the uranium fuel cycle is the sum of doses due to radioactivity in airborne and liquid effluents and the doses due to direct radiation from contained sources at the Zion Station. When the evaluation of total dose is required for the Zion Station, the following contributions are summed:
- Doses due to airborne and liquid effluents.
- Doses due to liquid effluents from nuclear power stations upstream
- Doses due to any onsite radioactive waste storage facilities; if applicable.
Section A.5.2 of Appendix A discusses the details of evaluations. Page 24 of 267
Revision 5 Aug 31, 2015 Table 4-1 Radionuclide Types Considered For Airborne Effluent Exposure Pathways External Radiation Internal Radiation Category Plume Ground Inhalation Ingestion Noble Gases X Tritium (H-3) x x Particulate8 x x x a Only particulates with half-life greater than 8 days need be considered. For details, see Generic Letter 89-01 and the RETS. Page 25 of 267
Revision 5 Aug 31, 2015 Table 4-2 Radiation Dose Factors Name and Symbol Units Definition Table Gamma Air Dose mrad/yr Gamma air dose rate per RG 1.109 Factor per unit of radioactivity Table B-1, 3 Mi µCi/m concentration for Column 4 radionuclide i. Total Body Dose mrem/yr Total body dose rate per RG 1.109 Factor: per unit of radioactivity Table B-1, 3 Ki µCi/m concentration for Column 5 radionuclide i. Beta Air Dose mrad/yr Beta air dose rate per RG 1.109 Factor Ni per unit of radioactivity Table B-1, 3
µCi/m concentration for Column 2 radionuclide i.
Beta Skin Dose mrem/yr Beta skin dose rate per RG 1.109 Factor Li per unit of radioactivity Table B-1, 3
µCi/m concentration for Column 3 radionuclide i.
Ground Plane Dose mrem/hr Dose rate per unit RG 1.109 Conversion Factor per of ground radioactivity Table E-6, 2 DFGi pCi/m concentration for Column 2 radionuclide i. Inhalation Dose mrem Dose to organ j of age RG 1.109 Commitment Factor per group a per unit of Tables; DFAiia pCi radioactivity inhaled E-7, E-8, for radionuclide i. E-9, E-10 (see Note 1) Ingestion Dose mrem Dose to organ j of age RG 1.109 Commitment Factor per group a per unit of Tables; DFhia pCi radioactivity ingested E-11, E-12, for radionuclide i. E-13, E-14 (see Note 1) Note 1: Dose assessments for 10CFR20, 10CFR72 and 40CFR190 compliance are made for an adult only. Dose assessments for 10CFR50 Appendix I are made using dose factors of Regulatory Guide 1.109 (Reference 6) for all age groups. Page 26 of 267
Revision 5 Aug 31, 2015 CHAPTER 5 MEASUREMENT
5.0 INTRODUCTION
Zion Station has two measurement programs associated with offsite dose assessment:
- Measurement of releases of radioactivity at the site.
- Measurement of levels of radiation and radioactivity in the environs surrounding the site.
5.1 EFFLUENT AND PROCESS MONITORING Radioactivity in liquid and gaseous effluents is measured in order to provide data for calculating radiation doses and radioactivity concentrations in the environment. Measurement of effluent radioactivity is required by 10CFR20.1302 and 10CFR50. The RETS provides detailed requirements for monitoring the effluents from the Zion Station. Relevant Regulatory Guides are 1.21 (Reference 4) and 4.15 (Reference 13). Chapter 10 of the ODCM includes brief descriptions of the systems. The RETS requires submission to the NRC of reports of effluent radioactivity releases and environmental measurements. 5.2 METEOROLOGICAL MONITORING A historical average of meteorological measurements is used at the Zion Station in lieu of real time monitoring. 5.3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) Zion Station has a REMP that provides representative measurements of radiation and radioactive material in the environment. The program provides verification that measurable radiological impacts from the station on the environment are within expectations derived from effluent measurements and calculations. The REMP is required by 10CFR50 (see Appendix I, Sections IV.B.2 and IV.8.3). General requirements of the program are prescribed in Zion Stations RETS and more precise details (such as specific monitoring locations) are specified in the ODCM Chapter 11. 5.3.1 lnterlaboratory Comparison Program The laboratory which performs the REMP analyses is required by the RETS to participate in an interlaboratory comparison program. The purpose is to provide an independent check on the laboratory's analytical procedures and to alert it to potential problems (e.g. accuracy). In order to assess the measurements of radioactivity in environmental media, an independent agency supplies participating laboratories with samples of environmental media containing unspecified amounts of radioactivity. The laboratories measure the radioactivity concentrations and report the results to the agency. At a later time, the agency informs the participating laboratories of the actual concentrations and associated uncertainties. Any significant discrepancies are investigated by the participating laboratories. A similar process is used to assess measurements of environmental radiation by passive thermoluminescent dosimeters. Page 27 of 267
Revision 5 Aug 31, 2015 CHAPTERS IMPLEMENTATION OF OFFSITE DOSE ASSESSMENT PROGRAM 6.1 NUCLEAR POWER STATION Zion Station staff is responsible for effluent monitoring. The staff determines effluent radioactivity concentration and flow rate. These data are used to determine the radioactivity release information required for the Radioactive Effluent Release Report and to perform monthly calculations and projections of offsite radiation dose. Zion Station staff is also responsible for control of effluent radioactivity. Procedures are implemented for determining, calculating and implementing monitor setpoints. Liquid and gaseous radwaste treatment systems and ventilation exhaust treatment systems are utilized when appropriate. Zion Station staff implements the Process Control Program (PCP) for solid radwaste and measures tank radioactivity. Zion Station staff maintains instrumentation associated with these activities and demonstrates operability of the instrumentation in accordance with the surveillance requirements of the RETS. In the event that any RETS requirements are violated, Zion Station staff is responsible for taking one of the actions allowed by the RETS and issuing any required reports to the NRC. Zion Station assembles and distributes the Annual Radioactive Effluent Release Report. 6.2 REMP CONTRACTOR The radiological environmental contractor collects environmental samples and performs radiological analyses as specified in the Zion Station REMP (see ODCM Chapters 11 and 12). The contractor issues reports of results to appropriate points of contact. The contractor participates in an interlaboratory comparison program and reports results in the Annual Radiological Environmental Operating Report. The contractor performs the annual land use census and assembles the Annual Radiological Environmental Operating Report. Page 28 of 267
Revision 5 Aug 31, 2015 CHAPTER 7 REFERENCES
- 1. Deleted
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NUREG/CR-2919, PNL-4380, September 1982.
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Page 29 of 267
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Randerson, DOE/TIC-27601, 1984.
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Turner, Office of Air Programs Publication No. AP-26, 1970.
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- 27. American Society of Mechanical Engineers, Recommended Guide for the Prediction of the Dispersion of Airborne Effluents, 1973.
- 28. Eisenbud, M., Environmental Radioactivity, 3rd Edition, (Academic Press, Orlando, FL, 1987).
- 29. Glasstone, S., and Jordan, W. H., Nuclear Power and Its Environmental Effects (American Nuclear Society, LaGrange Park, IL, 1980).
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- 31. National Council on Radiation Protection and Measurements, Radiological Assessment:
Predicting the Transport. Bioaccumulation. and Uptake by Man of Radionuclides Released to the Environment, NCRP Report No. 76, March 15, 1984.
- 32. American National Standards Institute, Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities, ANSI N13.1-1969, February 19, 1969.
- 33. Institute of Electrical and Electronics Engineers, Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N13.10-1974, September 19, 1974.
- 34. American National Standards Institute, Testing and Procedural Specifications for Thermoluminescence Dosimetry (Environmental Applications), ANSI N545-1975, August 20, 1975.
- 35. American Nuclear Insurers, Effluent Monitoring, ANl/MAELU Engineering Inspection Criteria for Nuclear Liability Insurance, Section 5.1, Rev. 2, October 24, 1986.
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Page 30 of 267
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- 37. American Nuclear Insurers, Environmental Monitoring Programs, ANl/MAELU Information Bulletin 86-1, June 9, 1986.
- 38. Cember, H., Introduction to Health Physics, 2nd Edition (Pergamon Press, Elmsford, NY 1983).
- 39. Deleted
- 40. Deleted
- 41. U.S. Nuclear Regulatory Commission, Branch Technical Position, Radiological Assessment Branch, Revision 1, November 1979. (This is a branch position on Regulatory Guide 4.8.)
- 42. Deleted
- 43. U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code),
NUREG-0017, April 1976.
- 44. Deleted
- 45. Deleted
- 46. Deleted
- 47. Deleted
- 48. Deleted
- 49. U.S. Nuclear Regulatory Commission, Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190), NUREG-0543, February 1980.
- 50. International Commission on Radiological Protection, Report of Committee Two on Permissible Dose for Internal Radiation, Recommendations of the International Commission on Radiological Protection, ICRP Publication 2, 1959.
- 51. U.S. Nuclear Regulatory Commission, Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, Battelle Pacific Northwest Laboratories, NUREG-0172, 1977.
- 52. W. C. Ng, Transfer Coefficients for Prediction of the Dose to Man via the Forage-Cow-Milk Pathway from Radionuclides Released to the Biosphere, UCRL-51939.
- 53. E. C. Eimutis and M. G. Konicek, Derivations of Continuous Functions for the Lateral and Vertical Atmospheric Dispersion Coefficients, Atmospheric Environment 6, 859 (1972).
- 54. D. C. Kocher, Editor, Nuclear Decay Data for Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities, ORNL/NUREG/TM-102, August 1977.
- 55. R. L. Heath, Gamma-Ray Spectrum Catalog, Aerojet Nuclear Co., ANCR-1000-2, third or subsequent edition.
- 56. S. E. Thompson, Concentration Factors of Chemical Elements in Edible Aquatic Organisms, UCRL-50564, Rev. 1, 1972.
- 57. U.S. Nuclear Regulatory Commission, Instruction Concerning Risks from Occupational Radiation Exposure, Regulatory Guide 8.29, July 1981.
- 58. Deleted
- 59. "Verification of Environmental Parameter Used for Commonwealth Edison Company's Offsite Dose Calculations," NUS Corporation, 1988.
Page 31 of 267
Revision 5 Aug 31, 2015
- 60. Deleted
- 61. Deleted
- 62. Deleted
- 63. Deleted
- 64. "Verification of Environmental Parameter Used for Commonwealth Edison Company's Offsite Dose Calculations," NUTECH Engineering Group, 1992.
- 65. Deleted
- 66. Deleted
- 67. Deleted
- 68. Deleted
- 69. Deleted
- 70. D. C. Kocher, Radioactivity Decay Data Tables, DOE/TIC-11026, 1981.
- 71. J.C. Courtney, A Handbook of Radiation Shielding Data, ANS/SD-76/14, July 1976.
- 72. Commonwealth Edison Company, Information Relevant to Keeping Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonably Achievable, Zion Station. Units 1 and 2, June 4, 1976.
- 73. Deleted
- 74. Deleted
- 75. Sargent & Lundy, METWRSUM, S&L Program Number 09.5.187-1.0.
- 76. Sargent & Lundy, Comments on CECo ODCM and List of S&L Calculations, Internal Office Memorandum, P. N. Derezotes to G. R. Davidson, November 23, 1988.
- 77. Sargent & Lundy, AZAP. A Computer Program to Calculate Annual Average Offsite Doses from Routine Releases of Radionuclides in Gaseous Effluents and Postaccident X/Q Values, S&L Program Number 09.8.054-1.7.
- 78. National Oceanic and Atmospheric Administration, A Program for Evaluating Atmospheric Dispersion from a Nuclear Power Station, J. F. Sagendorf, NOAA Technical Memorandum ERL ARL-42, Air Resources Laboratory, Idaho Falls, Idaho, May 1974.
- 79. G. P. Lahti, R. S. Hubner, and J.C. Golden, Assessment of Gamma-Ray Exposures Due to Finite Plumes, Health Physics 41, 319 (1981).
- 80. National Council of Radiation Protection and Measurements, Ionizing Radiation Exposure of the Population of the United States. NCRP Report No. 160, March 3, 2009.
- 81. Sargent & Lundy, Nuclear Analysis and Technology Division, Calculation No. ATD-0090, Revision 0.
- 82. Deleted
- 83. Deleted
- 84. Deleted Page 32 of 267
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- 85. U.S. Environmental Protection Agency, Environmental Analysis of the Uranium Fuel Cycle. Part I - Fuel Supply, EPA-520/9-73-003-8, October 1973.
- 86. U.S. Nuclear Regulatory Commission, Final Generic Environmental Statement on the Use of Recycle Plutonium in Mixed Oxide Fuel in Light Water Cooled Reactors, NUREG-0002, August 1976.
- 87. U.S. Nuclear Regulatory Commission, Demographic Statistics Pertaining to Nuclear Power Reactor Sites, NUREG-0348, Draft, December 1977.
- 88. Nuclear News 31, Number 10, Page 69 (August 1988).
- 89. Deleted
- 90. U.S. Nuclear Regulatory Commission, Generic Letter 89-01, "Guidance For The Implementation of Programmatic Controls For RETS In The Administrative Controls Section of Technical Specifications and the Relocation of Procedural Details of Current RETS to the Offsite Dose Calculation Manual or Process Control Program", January 1989.
- 91. Deleted
- 92. Deleted
- 93. Deleted
- 94. Deleted.
- 95. U.S. Nuclear Regulatory Commission, Standards for Protection Against Radiation (10CFR20).
- 96. U.S. Nuclear Regulatory Commission, Licensing of Production and Utilization Facilities (10CFR50).
- 97. Federal Register, Vol. 57, No. 169, Monday, August 31, 1992, page 39358.
- 98. Miller, Charles W., Models and Parameters for Environmental Radiological Assessments, U.S.
Dept. of Energy, DE8102754, 1984, pages 32, 33, 48, and 49.
- 99. Kocher, D. C., "Dose-Rate Conversion Factors For External Exposure To Photons and Electrons", Health Physics Vol. 45, No. 3 (September), pp. 665-686, 1983.
100. U.S. Department of Health, Education and Welfare Public Health Service, Radiological Health Handbook, January 1970. 101. Deleted 102. Deleted 103. U.S. Nuclear Regulatory Commission, Generic Letter 79-041, September 17, 1979. 104. Federal Register, Vol. 56, No. 98, Tuesday, May 21, 1991, page 23374, column 3. 105. U.S. Nuclear Regulatory Commission, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, NUREG-1301, April 1991. 106. Deleted 107. U.S. Nuclear Regulatory Commission, LADTAP 11- Technical Reference and Users Guide, NUREG-4013, April 1986. . 108. NRC ISG-13 Rev. 0, Spent Fuel Project Office Interim Staff Guidance -13 Real Individual, May 17,2000 Page 33 of 267
Revision 5 Aug 31, 2015 CHAPTER 8 Deleted Page 34 of 267
Revision 5 Aug 31, 2015 CHAPTER9 Deleted Page 35 of 267
Revision 5 Aug 31, 2015 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT SYSTEM AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description During operation of the ventilation systems, the principal release points for potentially radioactive airborne effluents are the two auxiliary building ventilation stacks (Unit 1 and Unit 2). Each is classified as a ground level release. These ventilation systems maintain acceptable ambient air temperatures for equipment operation and personnel habitability, they provide air flow as needed for contamination control purposes, from lesser contamination potential to areas of greater contamination potential, and they provide bulk exhaust flow for ease of effluent control, sampling, and quantification. The Unit 2 Aux Bldg (AB) ventilation st~ck provides the release point for airborne effluent from the Aux Bldg, Fuel Building, and the Containments (when the Containment Purge Fans are not in operation). Operation of the AB ventilation system is administratively controlled to ensure that at least one (of 3) exhaust fan is operating when a supply fan is running. During times when the Containment Purge Fans are operating; the Unit 1 AB ventilation stack provides the release point for airborne effluent from the Unit 1 Containment, and the Unit 2 AB ventilation stack provides the release point for airborne effluenffrom the Unit 2 Containment. Gaseous effluent system and ventilation systems are described in the Defueled Safety Analysis Report (DSAR) and Section 10.4. 10.1.1.1 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce radioactive material in particulate form in gaseous effluents by passing ventilation through HEPA and/or pre-filters prior to release to the environment for ALARA reasons. 10.1.2 Radiation Monitors Pertinent information is provided in the DSAR and Section 10.4. 10.1.2.1 Auxiliary Building Ventilation Stack Effluent Monitors 2RIA-PR49 (Unit 2) continuously monitors the final effluent from the Aux Bldg, Fuel Bldg, and Unit 2 containment for beta, particulate and provides an alarm function. 10.1.2.2 Containment Purge Effluent Monitors 1RIA-PR49 (Unit 1) continuously monitors the final effluent from the Unit 1 containment when the associated Purge Fan is in operation for beta particulate and provides an alarm function. 2RIA-PR49 (Unit 2) continuously monitors the final effluent from the Unit 2 containment when the associated Purge Fan is in operation for beta particulate and provides an alarm function. 10.1.3 to 10.1.3.4 Deleted Page 36 of 267
Revision 5 Aug 31, 2015 10.1.3.5 HVAC Flow Rates Flow rates for aux vent stack release are provided by flow measuring instrumentation. However, flow rates out of the vent stack can be calculated based on the number of operating fans in the monitored flow path. FM = (10-4) FM = Total Flow In Monitored Flow Path [cc/sec] Fip = Flow from fan i in path p. [cc/sec] Ni = Number of fans, in operation The maximum flow for each fan is used for setpoint calculations because this maximizes the flow, establishing a conservative, "worst case" release rate/concentration for setpoint determination. Pertinent data for the fans is provided in Table 10-2. HVAC flows for the remaining monitors are conservatively fixed at upper bound values. 10.2 LIQUID RELEASES 10.2.1 System Description The liquid waste system description is provided in the DSAR and Section 10.4. The liquid radwaste treatment system is designed and installed to allow for a reduction if needed, in the concentration of radioactive liquid effluents by filtration, providing for retention or holdup and/or providing for treatment by demineralizers. The overall purpose is to ensure releases to the lake do not exceed any concentration release limit and liquid effluent releases to the public are ALARA. 10.2.1.1 Lake Release Tanks There are two Lake Release Tanks which receive processed liquid waste before discharge to Lake Michigan. 10.2.1.2 Holdup Tanks There are three Holdup Tanks (120,000-gallon capacity each) which receive and store liquid waste from the Containments, AB and FB. The Holdup Tanks (HUTS) will store the liquid waste water until it can be processed for release to Lake Michigan or removed from the site. 10.2.2 Radiation Monitors 10.2.2.1 Lake Release Tank Monitors If the option is used, ORT-PR04 monitors releases from the Lake Release Tanks. On high alarm, the monitor automatically initiates closure of a valve to prevent further releases. The monitor and valve are located in an arrangement that allows closure prior to exceeding release limits. The monitor setpoints are found by solving Equation 10-5 for release setpoint P. Available information is provided in the DSAR and Section 10.4. Page 37 of 267
Revision 5 Aug 31, 2015 10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculation Alarm and trip setpoint of liquid effluent monitor at the principal release points is established to ensure that the concentration limits of the QAPP and 10 CFR 20 are not exceeded in the unrestricted area. The monitor setpoint is found by solving Equation 10-5 for a conservative mixture of radionuclides found in liquid effluents. (10-5) P Release Setpoint [µCi/ml] The alarm setpoint for radioactivity to be released in liquid effluents. Cmpc Maximum Permissible Concentration [µCi/ml] Fd Dilution Flow Rate [gpm] The flow rate of the radwaste dilution stream. Fr Discharge Flow Rate [gpm] The flow rate from the Lake Release Tank. K Factor of conservatism K = 0.5 for Lake Release Tank 10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Lake Release Tank Discharge Flow Rate Prior to each batch release, the water is recirculated, sampled, and analyzed. (1) The results of the analysis of the waste sample determine the discharge rate of each batch as follows: Frmax= (Cmpc)(Fd actfC) (10-6) Frmax Maximum Permitted Discharge Flow Rate [gpm] The maximum permitted flow rate from the Lake Release Tank. [gpm] Fd act Actual Dilution Flow Rate [gpm] The actual flow rate of the radwaste dilution stream. 1
<> C Sample Radioactivity Concentration [µCi/ml]
The concentration of radioactivity in the Lake Release Tank, based on measurements of a sample drawn from the tank. Cmpc has the same definition as in Equation 10-5. 10.2.3.2 Release Limits Release limits are determined from 10 CFR 20. Page 38 of 267
Revision 5 Aug31, 2015 10.2.3.3 Release Mixture The release mixture used for setpoint determination is based on a composition of 100% of a nuclide with a conservative concentration discharge limit to the lake (e.g. Sr90) 1 ( > A more conservative discharge rate may be calculated based on concentration limits for NPDES constituents (e.g., boron concentration). In either case, discharge procedures verify that all discharge limits to the lake are below applicable limits. 10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from the Lake Release Tanks are comprised of contributions from both units. Under normal site conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation is based on the unit discharge canal used for dilution. 10.3 SOLIDIFICATION OF WASTE/PROCESS CONTROL PROGRAM The process control program (PCP) contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured. 10.4 Radioactive Effluent Radiation Monitoring Systems 10.4.1 Design Bases The Radiation Monitoring System is designed to detect, indicate and alarm based on the radiation levels at selected locations in the facility. The system consists of the process radiation monitoring system, which includes the effluent monitors which are designed to provide early warning of increasing radiation activity due to a malfunction of plant equipment, and to monitor radioactive discharges to the environment to ensure concentrations do not exceed specified limits. In the decommissioning state, radioactive material exists in the form of particulates. As such, the instrument channels in the radiation monitoring system monitor only particulates. None of the radiation monitors are relied upon to initiate an accident mitigation function for the radioactive waste handling event described in Chapter 5.0 of the DSAR. In the decommissioning configuration, the source term continues to be reduced as the buildings are prepared for decontamination and demolition. Based on this, pote_ntial radiological events of concern are limited, but will focus on major structures with radioactive material and liquid releases to the lake. The process radiation monitoring system provides general radiological monitoring, as well as specific information on the concentration of radioactivity in the event of a radiological event or an abnormal liquid release to the lake. This enables personnel to evaluate and respood to an event accordingly. 10.4.2 System Description The Process Radiation Monitoring System consists of several channels which primarily give early warning of an unexpected elevated release. Effluent Radiation Monitors are controlled in accordance with Chapter 12 to ensure an "as low as reasonably achievable" site boundary dose is obtained. This is consistent with the design characteristics of the monitoring equipment, and acceptable operating considerations. The Process Radiation Monitoring System provides radiological monitoring of key areas and activities at the station. The primary areas of focus for the current radiation monitoring system are: Gaseous effluents through the vent stacks and the litjuid effluent pathways. As decommissioning progresses, these monitors will no longer be needed and will be removed from service. Page 39 of 267
Revision 5 Aug 31, 2015 10.4.3 Containment Purge System Effluent Monitoring Unit 1 Containment Purge Exhaust is monitored for radiation by the Unit 1 Auxiliary Building vent stack particulate Air Monitor. Unit 2 Containment Purge Exhaust is monitored for radiation by the Unit 2 Auxiliary Building vent stack particulate Air Monitor. 10.4.4 Fuel Building Exhaust Air Monitor The Fuel Building Ventilation exhaust is monitored via the Unit 2 Auxiliary Building ventilation stack effluent monitor. 10.4.5 Waste Disposal System Liquid Effluent Monitor The liquid radiation monitor PR-04 remains an option for lake Water discharges. It is a self-contained monitor and is used to measure radioactivity levels in liquid effluent being discharge to site effluent discharge point. Detector outputs are transmitted to the Radiation Monitoring alarms. High radioactivity-alarms are communicated so that actions can be implemented in accordance with approved procedures. The accuracy of these monitors will be maintained to provide a highly reliable backup to the multiple sample analyses prior to discharge. A single monitor is provided on each discharge line and is considered adequate since the tank sample analyses are the primary method for determination of allowable discharge volume and flow. The release of liquid waste is performed under administrative control and these channels provide continuous monitoring during the release. An additional option exists to complete lake water radioactive effluent discharges to alternate controls as described in Chapter 12. 10.4.6 Calibration and Testing Each channel employs a check source for channel testing. Check source testing is performed as defined in Chapter 12. All radiation monitors are calibrated by exposing the detectors to an isotope(s) of known activity. By changing the distance or placing filters between detector and the standard isotope, the field intensity is varied thereby allowing for a multi-point calibration. The waste disposal system liquid effluent monitors are calibrated by the use of two (2) isotopic standards of different intermediate activity levels. The standards are monitored during calibration in a configuration similar to that of the monitored sample during normal operation. This method allows for an accurate isotopic calibration without contamination of the system. The method of calibration of laboratory radiation counting instrumentation is in accordance with the vendor's manual. Complete documentation of calibration checks is maintained. 10.4.7 Effluent Monitoring and Sampling The methods used in quantifying routine effluent releases to the environment consist of continuous Radiation Monitoring Systems and/or laboratory analyses. Laboratory analyses are conducted on either grab samples or composite samples. All liquid and gaseous effluents sample results are recorded/saved in some form to provide a complete history of abnormal occurrences for evaluation; high radiation level alarms are sent to an on-shift individual when effluent releases are in progress. The high radiation alarm setpoints are based upon a value of activity which is sufficiently low to be in conformance with the concentration limit requirements. Laboratory instrumentation used for radiation analysis of effluent grab samples are as described in the Chapter 12. The calibration of counting equipment will be maintained by the use of sources certified against the National Institute of Standards and Technology (NIST) certificates. Page 40 of 267
Revision 5 Aug 31, 2015 Effluent monitors will be calibrated at frequencies established in the Chapter 12. The multi-channel gamma analyzer will be performance checked when in use. Sources are used to verify against known energy lines and activity. Geometry factors will be checked in accordance with approved procedures. The liquid scintillation counter will be checked in accordance with approved procedures when in use, Complete documentation of all calibration checks will be maintained. Effluent discharge line waste monitors will be checked against laboratory analyzed or established known portable sources. Page 41 of 267
Revision 5 Aug 31, 2015 TABLE 10-1 DELETED Page 42 of 267
Revision 5 Aug 31, 2015 TABLE 10-2 HVAC EXHAUST FAN CAPACITIES FAN CC/SEC CFM CFH
- 2 Aux. Bldg.
7 OD Exh. Fan 3.16 x 10 6.70x10 4 4,020,000 7 4 OE Exh. Fan 3.16 x 10 6.70x10 4,020,000 7 4 OF Exh. Fan 3.16 x 10 6.70 x 10 4,020,000
- 1 Purge Exh.
7 4 1A Purge Fan 2.12 x 10 4.50 x 10 2,700,000 7 4 1B Purge Fan 2.12 x 10 4.50 x 10 2,700,000 6 3 U1 Mini-Purge Fan 1.42 x 10 3:00 x 10 180,000 H2 Purge Fan 1A 1.70 x 10 5 3.60 x 102 21,600 5 2 H2 Purge Fan 1B 1.75 x 10 3.40 x 10 22,200
- 2 Purge Exh.
7 2A Purge Fan 1.65 x 10 3.50 x 104 2,102,400 7 4 2B Purge Fan 1.72 x 10 3.65 x 10 2,188,800 6 3 U2 Mini-Purge Fan 1.42 x 10 3.00 x 10 180,000 2 H2 Purge Fan 2A 1.82 x 105 3.85 x 10 23,100 5 2 H2 Purge Fan 2B 1.75 x 10 3.71x10 22,260 6 3 Hot Lab Exh. OA 1.50 x 10 3.18 x 10 191,000 6 3 Hot Lab Exh. OB 1.18 x 10 2.51x10 150,600 Page 43 of 267
Revision 5 Aug 31, 2015 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The parameters of the radiological environmental monitoring program for the environs around Zion Station are given in Table 11-1. Figures 11-1 a, 11-1 band 11-2 show sampling and monitoring locations. Page 44 of 267
Revision 5 Aug 31, 2015 Table 11-1 Radiological Environmental Monitoring Program Exposure Pathway Sampling or Monitoring Sampling or Collection Frequency Type and Frequency of Analysis And/or Sam pie Locations
- 1. Airborne
- a. Indicators - Near Field Particulate Sam pier:
Z-01 Onsite No. 1 South side, Continuous sam pier operation with Gross beta analysis following 2 0.2 mi S (0.3 km J) particulate filter collection weekly or weekly filter change and 3 Z-02 Onsite No. 2 West side, more frequently if required by dust gamma isotopic analysis 0.2 mi W (0.3 km N) loading. quarterly on composite filters by location. Z-03 Onsite No. 3 North side, 0.20 mi NNE (0.3 km B)
- b. Control- Far Field Z-13 Pleasant Prairie Wisconsin 10 mi NW (15 km Q)
Page 45 of 267
Revision 5 Aug 31, 2015 Table 11-1 Radiological Environmental Monitoring Program - Cont. Exposure Pathway Sampling or Monitoring Sam piing or Collection Frequency Type and Frequency of Analysis And/or Sam pie Locations
- 2. Direct Radiation a. Indicators - Inner Ring 5 Quarterly Gamma dose on each TLD quarterly Z-101-1 and 2 0.2 mi N (0.3 km A)
Z-102-1 and 2 0.2 mi NNE (0.3 km B) Z-103-1 and2 0.15 mi NE (0.25 km C) Z-104-1 and2 0.13 mi ENE (0.2 km D) Z-105-1 and2 0.1 mi E (0.15 km E) Z-106-1 and 2 0.1 mi ESE (0.15 km F) Z-107-1 and 2 0.1 mi SE (0.15 km G) Z-108-1 and2 0.13 mi SSE (0.2 km H) Z-109-1 and 2 0.2 mi SSE (0.3 km H) Z-112-1 and 2 0.7 mi WSW (1.1 km M) Z-113-1 and 2 0.6 miW (1.0 km N) Z-114-1 and 2 0.6 mi WNW (1.0 km P) Z-115-1 and 2 0.4 mi NW (0.6 km Q) Z-121-1 and 2 0.2 mi NNW (0.3 km R) Z-124-1 and 2 0.5 mi SW (0.8 km L) Z-125-1 and 2 0.4 mi SSW (0.6 km K) Z-129-1 and 2 0.2 mi NW (0.3 km P) Z-130-1 and 2 0.2 mi WNW (0.3 km N) Quarterly Gamma dose on each TLD Z-131-1 and 2 0.2 mi WSW (0.3 km L) quarterly
- b. Other One at each airborne location given in 1.a.
Z01-1 and 2 0.2 mi S (0.3 km J) Z02-1 and 2 0.2 mi E (0.3 km N) Z03-1 and 2 0.2 mi NNE (.3 km B) One control at control airborne location Z13-1thru6 10 mi NW (15 km Q) Page 46 of 267
Revision 5 Aug 31, 2015 Table 11-1 Radiological Environmental Monitoring Program - Cont. Exposure Pathway Sam piing or Monitoring Sampling or Collection Frequency Type and Frequency of Analysis And/or Sam pie Locations
- 2. Direct Radiation - d. Indicators - Outer Ring Quarterly Gamma dose on each TLD Cont. quarterly Z-209-1 and 2 5.1 mi S (8.2 km K)
Z-211-1 and 2 4.7 mi SW (7.6 km L) Z-212-1 and 2 5.1 mi WSW (8.2 km M) Z-213-1 and2 5.1 miW (8.2 km N) Z-214-1 and 2 4.6 mi WNW (7.4 km P) Z-215-1 and 2 4.0 mi NW (6.4 km Q) Z-216-1 and2 3.0 mi NNW (4.8 km R) Gamma dose on each TLD quarterly Page 47 of 267
Revision 5 Aug 31, 2015 Table 11-1 Radiological Environmental Monitoring Program - Cont. Exposure Pathway Sampling or Monitoring Sampling or Collection Frequency Type and Frequency of Analysis And/or Sam pie Locations
- 3. Waterborne 6
- a. Drinking Water lndicator Z-15 Lake County Water Works, Gross beta and gamma isotopic3 1.4 mi NNW (2.2 km R) Weekly grab samples. analysis on monthly composite; Z-16 Waukegan Water W arks, tritium analysis on quarterly 6.1 mi S (9.8 km J) composite.
- b. Control 6 Z-14 Kenosha Water Works, 10.0 mi N Gross beta and gamma isotopic3 (1.60.km A) Weekly grab samples. analysis on monthly composite; Z-18 Lake Forest Water Works, 12.9 mi tritium analysis on quarterly S (20.8 km J) composite.
- c. Sediments Z-25 Lake Michigan, Illinois Beach Semiannually Gamma isotopic3 analysis State Park, 2.0 mi S (3.2 km J) semiannually.
Page 48 of 267
Revision 5 Aug 31, 2015 Table 11-1 Radiological Environmental Monitoring Program - Cont. Exposure Pathway Sampling or Monitoring Sam piing or Collection Frequency Type and Frequency of Analysis And/or Sam pie Locations
- 4. Ingestion a. Fish Indicator Semiannually Z-26, Lake Michigan in vicinity of station Discharge 3
Gamma isotopic analysis on
.. b. Fish Control edible portions.
Z-27, Lake Michigan, 10.0 mi N (16.0 km A)
- 5. Vegetation a. Vegetation Indicator Annual (during growing season)
Z-QUAD 3, Pleasant Prairie market, 4 mi Gamma isotopic3 analysis on NNW (6.4 km R) edible portions. Z-QUAD 4, Sheridan Road Zion Farmers market, 1.1 mi W (1.7 km N)
- b. Vegetation Control Z-Control, Kenosha Farmers Market, 11 mi NNW (18 km R}
Page 49 of 267
Revision 5 Aug 31, 2015 Table 11-1 Radiological Environmental Monitoring Program - Cont.
- 1. Deleted - No longer applicable.
- 2. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in any individual air particulate sample is greater than 10 times the 1999 mean of control samples, then, a gamma isotopic analysis shall be performed on that elevated individual sample.
- 3. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the station.
- 4. Deleted - No longer applicable.
- 5. Limited TLD placements due to Lake Michigan and location of air samplers.
- 6. The closest drinking water locations (North/South) chosen for drinking water indicators; two other locations beyond 6.2 miles (North/South) chosen for control sam pies.
Page 50 of 267
Revision 5 Aug 31 , 20 15 Figure 11-1a Airborne and Direct Radiation Sample Locations - Inner Ring
- TLD Monitoring Location A. Air Sampling Location Page 51 of 267
Revision 5 Aug 31, 20 15 Figure 11-1 b Direct Radiation Sample Locations - Outer Ring Page 52 of 267
Revision 5 Aug 31, 2015 Figure 11-2 Location of Waterborne and Ingestion Sampling Sites Kenosha Waterworks Z-14
*Z-27
---~~~~----------- Zion Lake County Water Works
- Z-15 Zion*
- 2 -26 LAKE Illinois Beach Z-25 State Park MICHIGAN Waukegan Water Works North Chicago Water Works
- Sampling Locations Page 53 of 267
Revision 5 Aug 31, 2015 CHAPTER12 Radiological Effluent Technical Standards (RETS) SPECIAL NOTE The requirements of Quality Assurance Project Plan (QAPP) Appendix B shall take precedence over this chapter, should any differences occur. Page 54 of 267
Revision 5 Aug 31, 2015 12.1 DEFINITIONS 12.1.1 A BATCH RELEASE is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling. 12.1.2 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds with the necessary range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors (where possible), alarm interlock and/or trip functions (if applicable) and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated. 12.1.3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent INSTRUMENT CHANNELS measuring the same parameter. 12.1.4 A CHANNEL FUNCTIONAL CHECK shall be:
- a. Instruments-The injection of a simulated signal(s) into the channel as close to the primary sensor(s) as practicable to verify OPERABILITY, including all channel outputs, as appropriate.
- b. Logics-The application of input signals, or the operation of relays or switch contacts, in all the combinations required to produce the required decision outputs including the operation of all ACTUATION DEVICES. Where practicable, the test shall include the operation of the ACTUATED EQUIPMENT as well (i.e. pumps will be started, valves operated, etc.).
12.1.5 A COMPOSITE SAMPLE is one in which the quantity of liquid sample is proportional to the quantity of liquid waste discharged and in which the method of sampling employ~d results in a specimen which is representative of the liquids released. 12.1.6 A CONTINUOUS RELEASE is the discharge of liquid or gaseous wastes of a nondiscrete volume (e.g. from a volume or system that has an input flow during the release). 12.1.7 CONTINUOUS SAMPLING is uninterrupted sampling with the exception of sampling interruptions of short duration for routine activities (e.g. filter replacements). 12.1.8 MEMBER OF THE PUBLIC means any individual except when that individual is receiving an occupational dose. 12.1.9 OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public. 12.1.10 OPERABLE -A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s). 12.1.11 OPERATING is defined as performing the intended function in the intended manner. Page 55 of 267
Revision 5 Aug 31, 2015 12.1.12 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste. 12.1.13 PURGE OR PURGING is the controlled process of discharging air from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner, that replacement air or gas is required to purify the confinement. 12.1.14 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by the licensee. 12.1.15 SOLIDIFICATION shall be the conversion of radioactive liquid, resin and sludge wastes from liquid systems into a form that meets shipping and burial site requirements. 12.1.16 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. 12.1.17 SURVEILLANCE shall be those parts of the sections which prescribe remedial measures required under designated conditions, activities required to demonstrate instrument operability, and activities performed to ensure applicable offsite dose limits are not exceeded. 12.1.18 The SURVEILLANCE FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 12.1-1. 12.1.19 UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee. 12.1.20 UNVENTILATED BUILDING RELEASE means A building that is not negative pressure controlled with presence of radioactive that could potentially become airborne that has a pathway to be released to the environment. 12.1.21 GASEOUS EFFLUENT TREATMENT SYSTEM shall be any system designed and installed to reduce radioactive material in particulate form in effluents by passing ventilation through HEPA filters for the purpose of removing particulates from the gaseous exhaust stream prior to the release to the environment 12.1.22 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air is not provided or required during venting. Vent, used in system names, does not imply a venting process. Page 56 of 267
Revision 5 Aug 31, 2015 TABLE 12.1-1 SURVEILLANCE FREQUENCY NOTATIONS NOTATION FREQUENCY* s (Shiftly) At least once per 12 hours D (Daily) At least once per 24 hours w (Weekly) At least once per 7 days M (Monthly) At least once per 31 days Q (Quarterly) At least once per 92 days SA (Semiannually) At least once per 184 days A (Annually) At least once per 366 days R At least once per 18 months p (Prior) Complete prior to start of release N/A Not Applicable
- Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.
Page 57 of 267
Revision 5 Aug 31, 2015 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Plant Monitoring Instrumentation Operability Requirements 12.2.1.A The radioactive liquid plant monitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE AND, the radioactive liquid effluent monitoring instrumentation channels shall have their alarm/trip setpoints set to ensure that the limits of Section 12.3.1.A are met. Applicability: As indicated in Table 12.2-3.
- 1. With a radioactive liquid effluent monitoring instrument channel trip setpoint less conservative than the value necessary to prevent violating the limits of Section 12.3.1.A, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.
- 2. With one or more radioactive liquid plant monitoring instrumentation channels inoperable, initiate the SURVEILLANCE requirement delineated in Table 12.2-1.
- 3. Restore the inoperable effluent monitor to OPERABLE status within 30 days, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report the reasons as detailed in Section 12.7.2 and perform a review to determine course of action to restore to OPERABLE status.
Surveillance Requirements 12.2.1.B.1 The liquid effluent monitor setpoints shall be determined in accordance with procedures as described in the ODCM. 12.2.1.B.2 Each radioactive liquid plant monitoring instrumentation channel shall be demonstrated OPERABLE by performance of a CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-2. 12.2.1.C The radioactive liquid plant monitoring instrumentation is provided to indicate abnormal radiological conditions, AND, The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive materials in liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of RETS. The OPERABILITY and use of this instrumentation is consistent with the requirements of Appendix A to 10CFR Part 50. Page 58 of 267
Revision 5 Aug 31, 2015 TABLE 12.2-1 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE# CONDITION
- 1. Liquid Effluent Monitors Providing Automatic Termination of Release A. Lake Release Tanks
- 1. OR-PR04 1 1* Liquid Release through this Pathway
- 2. Effluent Continuous Composite Sampler A. WWTF 1 4 During Release via this pathway
- 3. Effluent Flow Rate Monitor A. Lake Release Tank #1
- 1. OFl-WD005 1 3 Liquid Release through this Pathway
- 2. OFl-WD005A 1 3 Liquid Release through this Pathway B. Lake Release Tank #2
- 1. OFl-WD006 1 3 Liquid Release through this Pathway
- 2. OFl-WD006A 1 3 Liquid Release through this Pathway C. Common discharge pathway
- 1. OFl-WD007 1 3 Liquid Release from Either LRT #1 or #2
- 4. Plant System Monitors A. Dilution Flow Pressure Indication
- 1. OPl-SW01A 1** 3 Liquid Release from Either LRT #1 or #2
- 2. OPl-SW01 1** 3 Liquid Release from Either LRT #1 or #2
- - The Surveillance 1 may be used as an equivalent alternative to the use of OR-PR04.
- -Minimum Channels Operable for Dilution flow Pressure Indication is one channel from OPl-SW01 OR one channel from OPl-SW01A during LRT releases.
Page 59 of 267
Revision 5 Aug 31, 2015 TABLE 12.2-1 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION (Cont'd) SURVEILLANCE 1 If the monitor is inoperable, effluent releases from the tank may continue provided that prior to initiating the release:
- 1. At least two independent samples of the tank's contents are analyzed, in accordance with Section 12.3.1.B.1, and
- 2. At least two technically qualified members of the facility staff independently verify the release-rate calculations and discharge flow path valving; and
- 3. Approval by the Plant Manager.
- 4. Restore the inoperable effluent monitor to OPERABLE status within 30 days, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report the reasons as detailed in Section 12.7.2 and perform a review to determine course of action to restore to OPERABLE status.
Otherwise, suspend release of radioactive effluents via this pathway. SURVEILLANCE 2 Deleted. SURVEILLANCE 3 For the applicable flowpath at least one of the listed flowmeters within the flowpath must be operable to monitor flow provided the monitored flowrate falls within the calibration range of the flowmeter. With the no flow channels OPERABLE within the flowpath, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves may be used to estimate flow. SURVEILLANCE 4 If the composite sampler is inoperable, effluent releases via this pathway may continue, provided that at least once per day grab samples are taken. The samples shall be analyzed in accordance with Section 12.3.1.B.3. Page 60 of 267
Revision 5 Aug 31, 2015 TABLE 12.2-2 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION SURVEILLANCE CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION (1) TEST (2)
- 1. Liquid Effluent Monitors Providing Automatic Termination Of Release A. Lake Release Tanks
- 1. OR-PR04 p p R Q
- 2. Effluent Continuous Composite Sampler A. WWTF N/A N/A N/A N/A
- 3. Effluent Flow Rate Monitor A. Lake Release Tank #1
- 1. OFl-WD005 D{3) N/A R N/A
- 2. OFl-WD005A D{3) N/A R N/A B. Lake Release Tank #2 1 . OFl-WD006 D(3) N/A R N/A
- 2. OFl-WD006A D{3) N/A R N/A C. Common Discharge pathway
- 1. OFl-WD007 D{3) N/A R N/A
- 4. Plant System Monitors A. Dilution Flow Pressure Indication
- 1. OPl-SW01A D(4) N/A R N/A
- 2. OPl-SW01 D(4) N/A R N/A (1) CHANNEL CALIBRATION shall include performance of a CHANNEL FUNCTIONAL TEST.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that any automatic isolation of this pathway occurs and that control room alarm annunciation occurs if any of the following conditions exist. (if the capability is installed): a) Instrument indicates levels above the alarm setpoints. b) Circuit failure. c) Instrument indicates a downscale failure. d) Instrument controls not set in operate mode. (3) CHANNEL CHECK shall consist of verifying indications of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or BATCH RELEASES are made. (4) Dilution Flow Pressure Gauge OPl-SW01A OR OPl-SW01 may be used. The pressure gauge being used shall be verified operating at least daily during Lake Release Tank Batch discharge And pump curves used to estimate flow once per day based on the readings. Page 61 of 267
Revision 5 Aug 31, 2015 12.2.2 Radioactive Plant Monitoring Instrumentation Operability Requirements 12.2.2.A The radioactive plant monitoring instrumentation channels shown in Table 12.2-3 shall be OPERABLE, AND, the radioactive gaseous effluent monitoring instrumentation shall have their alarm/trip setpoints set in accordance with the method prescribed in the ODCM to ensure that the limits of Section 12.4.1.A are met. Applicability: As indicated in Table 12.2-3.
- 1. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Section, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.
- 2. With one or more radioactive plant monitoring instrumentation channels inoperable, initiate the SURVEILLANCE requirement as delineated in Table 12.2-3.
- 3. Restore the inoperable effluent monitor to OPERABLE status within 30 days, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report the reasons as detailed in Section 12. 7.2 and perform a review to determine course of action to restore to OPERABLE status.
Surveillance Requirements 12.2.2.B.1 The effluent monitor setpoints shall be determined in accordance with procedures as described in the ODCM. 12.2.2.B.2 Each radioactive plant monitoring instrumentation channel shall be demonstrated OPERABLE, when in its APPLICABLE CONDITION, by performance of a CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-4. 12.2.2.C The radioactive plant monitoring instrumentation is provided to indicate abnormal radiologi_cal conditions. The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20. Page 62 of 267
Revision 5 Aug 31, 2015 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE CONDITION
- 1. Effluent Containment Purge or Vent A. Particulate Monitor
- 1. 1R-PR49 1 11 Gaseous Release through this Pathway
- 2. 2R-PR49 1 11 Gaseous Release through this Pathway B. Flow Rate Monitor
- 1. 1LP-084 1 8 Gaseous Release through this Pathway
- 2. 2LP-084 1 8 Gaseous Release through this Pathway
- 2. Aux Building Effluent Monitoring A. DELETED B. Particulate Monitor
- 1. 2R-PR49 1 11 Gaseous Release through this Pathway C. Flow Rate Monitor
- 1. 2LP-084 1 8 Gaseous Release through this Pathway Page 63 of 267
Revision 5 Aug 31, 2015 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION - (Cont'd) TABLE NOTATIONS SURVEILLANCE 6 DELETED SURVEILLANCE 7 DELETED SURVEILLANCE 8 Effluent releases via this pathway may continue provided: 1 . The effluent flow rate is estimated at least once per day while a release is in progress.
- 2. Continuous sampling is maintained with either inline sample pump or air sampling at locations that input into the gaseous effluent system.
- 3. A Channel Check is performed daily
- 4. Restore the inoperable effluent monitor to OPERABLE status within 30 days, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report the reasons as detailed in Section 12.7.2 and perform a review to determine course of action to restore to OPERABLE status.
SURVEILLANCE 9 DELETED SURVEILLANCE 10 DELETED SURVEILLANCE 11 With the number of OPERABLE channels less than the minimum number required:
- 1. Effluent releases via this pathway may continue provided samples are continuously collected as required in Table 12.4-1.
- 2. Restore the channel to OPERABLE status within 30 days or conduct a review to determine a plan of action to restore the channel to OPERABLE status.
Compensatory sampling does not return the monitor to an OPERABLE status. SURVEILLANCE 12 DELETED. SURVEILLANCE 13 DELETED SURVEILLANCE 14 DELETED Page 64 of 267
Revisions Aug 31, 2015 TABLE 12.2-4 RADIOACTIVE PLANT MONITORING INSTRUMENTATION SURVEILLANCE CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL CHECK CHECK CALIBRATION (1) TEST (2)
- 1. Effluent Containment Purge or Vent A. Particulate Monitor
- 1. 1R-PR49 D M R Q
- 2. 2R-PR49 D M R Q B. Flow Rate Monitor
- 1. 1LP-084 D N/A R Q
- 2. 2LP-084 D N/A R Q
- 2. Aux Building Effluent Monitoring A. DELETED B. Particulate Monitor
- 1. 2R-PR49 D M R Q C. Flow Rate Monitor
- 1. 2LP-084 D N/A R Q Page 65 of 267
Revision 5 Aug 31, 2015 Table 12.2-4 RADIOACTIVE PLANT MONITORING INSTRUMENTATION SURVEILLANCE (Cont'd) TABLE NOTATIONS (1) CHANNEL CALIBRATION shall include performance of a CHANNEL FUNCTIONAL TEST. (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that any automatic isolation occurs; and that alarms occur if any of the following conditions exist (if the capability is installed): a) Instrument indicates measured levels above the alarm setpoint. b) Circuit failure. c) Instrument indicates a downscale failure. d) Instrument controls not set in "operate" mode. Page 66 of 267
Revision 5 Aug 31, 2015 12.3 LIQUID EFFLUENTS 12.3.1 Concentration Operability Requirements 12.3.1.A.1 The concentration of radioactive material released from the site to UNRESTRICTED AREAS (see Appendix F, Figure F-1) shall be limited to 10 times the concentrations specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402 12.3.1.A.2 During the release of radioactive liquid wastes, the combination of dilution water flow and waste water discharge flow shall be established to ensure the discharge concentration limits of 12.3.1.A.1 are not exceeded. Applicability: At all times.
- 1. With the concentration of radioactive materials released from the site to UNRESTRICTED AREAS exceeding the limits specified in Section 12.3.1.A.1 immediately decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits.
Surveillance Requirements 12.3.1.B.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 12.3-2. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1.A.1. 12.3.1.B.2 Post-release analyses of samples composited from BATCH RELEASES shall be performed in accordance with Table 12.3-2. The results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1. 12.3.1.B.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 12.3-2. The results of the analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1. 12.3.1.B.4 Appropriate discharge and dilutions flows for each batch radioactive liquid release shall be determined with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1 .A.1. 12.3.1.C This Section is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than ten (10) times the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR 20.1001-20.2402. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10CFR20.1301. Page 67 of 267
Revision 5 Aug 31, 2015 TABLE 12.3-1 DELETED Page 68 of 267
Revision 5 Aug 31, 2015 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE MINIMUM ANALYSIS LOWER LIMIT OF LIQUID RELEASE SAMPLING FREQUENCY TYPE OF DETECTION (LLD) TYPE FREQUENCY ACTIVITY ANALYSIS (µCi/ml) (a,e) A. Lake Release Prior to Each Release Prior to Each Principal Gamma 5E-7 (c) Release Emitters (e) p M Tritium 1E-5 Each Batch (c) Composite (b) Gross Alpha 1E-7 p Q Sr-90 5E-8 Each Batch ( c) Composite (b) Fe-55, Ni-63 1E-6 B. WWTF (f) Continuous During W when discharging Principal Gamma 5E-7 Release (d) Emitters(e) Continuous During M Tritium 1E-5 Release(d) Composite (b) Gross Alpha 1E-7 Continuous During Q Sr-90 5E-8 Release (d) Composite (b) Fe-55, Ni-63 1E-6 C. Waste Prior to each Release Prior to each Release Principal Gamma 5E-7 Neutralizing Tank Emitters (e) p M Tritium 1E-5 Each Batch (c) Composite (b) Gross Alpha 1E-7 D. Groundwater Prior to each Release Prior to each Release Principal Gamma 5E-7 Emitters (e) p M Tritium 1E-5 Each Batch (c) Composite (b) E. Groundwater (f) Continuous During w Principal Gamma 5E-7 Release (d) Emitters( e) Continuous (d) M Tritium 1E-5 Composite (b) Page 69 of 267
Revision 5 Aug 31, 2015 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd) TABLE NOTATIONS
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95%
probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): LLD= 4.66 sb A* E
- V
- 2.22
- Y *exp (-Mt)
Where: LLD is the lower limit of detection as defined above in picocuries (pCi) per unit mass or volume, sb is the square root of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), A is the number of gamma rays emitted per disintegration for gamma ray radionuclide analysis (A= 1.0) for gross alpha, strontium, and tritium measurement. Eis the counting efficiency (as counts per gamma), Vis the sample size (in units of mass or volume), 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield when applicable (otherwise Y = 1.0)
'A is the radioactive decay constant for the particular radionuclide, and L\t is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental sample).
The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and L\t shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be within+/-. one FWHM (Full Width at Half Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide. Page 70 of 267
Revision5 Aug 31, 2015 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd) TABLE NOTAT IONS For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using observed ratios with those radionuclides which are measurable.
- b. A COMPOSITE SAMPLE is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
- 1) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
- 2) The weekly and monthly Proportional Composite samples are not required provided that (1) the analysis required for each of these composite samples has been run on each batch discharged, and (2) a monthly record of radionuclides discharged (isotope and quantity) is maintained.
- c. A BATCH RELEASE is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
- d. A CONTINUOUS RELEASE is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.
- e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Nb-94, Co-60, Cs-137 and Sb-125. This list does not mean that only these nuclides are
.to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD, and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations.
- f. If the composite sampler is inoperable, grab samples shall be taken from the discharge stream once per day during system operation.
Page 71 of 267
Revision 5 Aug 31, 2015 12.3.2 Dose Operability Requirements 12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC above background from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS (see Appendix F, Figure F-1) shall be limited:
- 1. 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
- 2. 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.
Applicability: At all times.
- 1. With the calculated dose from the release of radioactive materials in liquid effluents exceeding twice the limits specified in Section 12.3.2.A, limit the subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cyele sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) ovE)r 12 consecutive months. Demonstrate that radiation exposures to all MEMBERS OF THE PUBLIC from all u_ranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40CFR Part 190 and 40CFR Part 141 Standard, otherwise obtain a variance from the Commission to permit releases which exceed the 40CFR Part 141 or 190 Standard.
The radiation exposure analysis shall use methods prescribed in the ODCM. Surveillance Requirements 12.3.2.B Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodologies and parameters of the ODCM at least once per 31 days. 12.3.2.C This Section is provided to implement the requirements of Sections II.A, Ill.A and IV.A of Appendix I, 10CFR Part SQ. The limiting Condition of Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required OPERATING flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites_ with drinking water supplies, which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are excess of the requirements of 40CFR 141 . The dose calculations in the ODCM implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the dose due to the actual release rate of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109; Calculation of Annual Doses to Man from Routine Releases of Radioactive Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guides 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. Page 72 of 267
Revision 5 Aug 31, 2015 This Section applies to the release of liquid effluents from each unit at the site. For shared radwaste treatment systems, the liquid effluents from the shared systems are proportioned among the units sharing the system. 12.3.3 Liquid Radwaste Treatment System Operability Requirements 12.3.3.A The Liquid Radwaste Treatment System shall be OPERABLE* and appropriate portions of the system shall be used to reduce the radioactive materials in liquid effluents prior to discharge when the projected doses due to liquid effluent, from each unit, to UNRESTRICTED AREAS (see Appendix F, Figure F-1) would exceed 0.06 mrem to the total body or 0.20 to any organ in a 31-day period.
*The liquid Radwaste Treatment System shall be considered OPERABLE, if liquid waste can be held up and/or discharged within applicable limits.
Applicability: At all times. With the Liquid Radwaste Treatment System inoperable for more than 30 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, return the system to OPERABLE status and place the appropriate portions of the system in use. Surveillance Requirements 12.3.3.B Doses due to liquid releases from the.site to UNRESTRICTED AREAS, shall be projected at least once per 31 days in accordance with the methodologies and parameters of the ODCM when the Liquid Radwaste Treatment System is not being fully utilized. 12.3.3.C The OPERABILITY of the Liquid Radwaste Treatment System ensures that the system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This Section implements the requirements of 10CFR Part 50.36a, General Design Criterion of Appendix A to 10CFR Part 50 and the design objective given in Section 11.D of Appendix I to 10CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a 2% fraction of the dose design objectives set forth in Section II.A of Appendix I, 10CFR Part 50, for liquid effluents. Page 73 of 267
Revision 5 Aug 31, 2015 12.4 GASEOUS EFFLUENTS 12.4.1 Dose Rate Operating Requirements 12.4.1.A The dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (see Appendix F, Figure F-1 ), shall be limited to the following:
- 1. DELETED
- 2. For tritium and all radionuclides in particulate form with half-lives greater than 8 days the limit is less than or equal to 1500 mrem/yr to any organ.
Applicability: At all times. With a release exceeding the above limits, immediately reduce the release rate to within the above limits. Surveillance Requirements 12.4.1.B The dose rate due to radioactive materials in gaseous effluents shall be determined to be within the prescribed limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 12.4-1. 12.4.1.C This Section is provided to ensure that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an Unrestricted Area, either at or beyond the Site Boundary in excess of the design objectives of appendix I to 10 CFR part 50. This section is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.A and II design objectives of appendix I to 10 CFR part 50. These release-rate limits also restrict, at all times, the corresponding organ dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year. For purposes of calculating dose resulting from airborne releases, the stack is considered a ground-level release. The Sampling and Analysis Program requirements prescribed in Table 12.4-1 are established to provide representative and appropriate sampling of the radiologically controlled areas. The method and frequency of sampling is based on the effluent flowrate. Continuous Releases are defined for areas with forced ventilation release points. Unventilated Building Releases are defined for areas with no specific release point. Page 74 of 267
Revision 5 Aug 31, 2015 TABLE 12.4-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE OF LOWER LIMIT OF GASEOUS RELEASE SAMPLING ANALYSIS ACTIVITY DETECTION (LLD) TYPE METHOD FREQUENCY ANALYSIS (µCi/cc) (f) A. Deleted B. Continuous Continuous (b)(h) Weekly(c) Particulate 1E-11 Releases <1> Daily( a) Principal Gamma Containment Vent Emitters (e) and Purge C. Continuous Releases< 1> Aux Building Unit 2 Composite Quarterly Sr-90 Particulate 1E-11 Ventilation Stack Unit 1 Vent Stack, Modular HEPA Fe-55 Particulate 3E-11 Ventilation discharge (if Ni-63 Particulate 1E-11 applicable) Gross Alpha 1E-11 (1) The requirements listed in this table for Continuous Releases are applicable for release paths that are available. Page 75 of 267
Revision 5 Aug 31, 2015 TABLE 12.4-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM (Cont'd} MINIMUM TYPE OF LOWER LIMIT OF GASEOUS RELEASE SAMPLING ANALYSIS ACTIVITY DETECTION (LLD} TYPE METHOD FREQUENCY ANALYSIS (µCi/cc} (f} D. Unventilated Building Releases< 1> Continuous (h} Daily(c) Particulate 1 E-11 Principal Gamma Emitters (e) Composite Quarterly Sr-90 Particulate 1E-11 Fe-55 Particulate 3E-11 Ni-63 Particulate 1 E-11 Gross Alpha 1E-11 1 This requirement sampling point may be used for any release point that is unventilated and will be tracked as an abnormal gaseous discharge point.TABLE 12.4-1 Page 76 of 267
Revision 5 Aug 31, 2015 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM (Cont'd) TABLE NOTATIONS
- a. The daily sampling requirement is applicable when 1RIA-PR49 or 2R-PR49A is inoperable AND decommissioning activities that can create airborne radioactivity are in progress in the associated building (Containment and/or AB).
- b. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period in Section 12.4.1.
- c. The particulate filter(s) shall be saved for a quarterly composite analysis for Sr-90, Ni-63, Fe-55 and gross alpha.
- d. DELETED
- e. For particulate emissions, the principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Nb-94, Co-60, Cs-137 and Sb-125. Other peaks which are measurable and identifiable by gamma-ray spectrometry, together with the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being at the LLD level for that nuclide.
- f. The LLD is defined in Notation a. of Table 12.3-2.
- g. DELETED
- h. Sampling interruptions of short duration for routine activities, e.g. filter replacement or opening/closing of the construction door, do not constitute a deviation from the requirements for continuous sampling.
- i. DELETED Page 77 of 267
Revision 5 Aug 31, 2015 12.4.2 DELETED 12.4.3 Dose - Tritium and Radioactive Material in Particulate Form Operability Requirements 12.4.3.A The dose to a MEMBER OF THE PUBLIC from tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas at or beyond the SITE BOUNDARY (see Appendix F, Figure F-1) shall be limited to the following:
- 1. During any calendar quarter: Less than or equal to 7 .5 mrem to any organ, and
- 2. During any calendar year: Less than or equal to 15 mrem to any organ.
Applicability: At all times. With the calculated dose from the release of tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding twice the limits of Section 12.4.3.A:
- 1. Limit subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources to less than or equal to 25 mrem to the total body or organ (except the thyroid which is limited to less than or equal to 75 mrem) over 12 consecutive months.
- 2. Prepare an analysis which demonstrates that radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40CFR Part 190 Standard. Otherwise, request a variance from the Commission to permit release which exceeds the 40CFR Part 190 Standard. The radiation exposure analysis shall use the methods prescribed in the ODCM.
Surveillance Requirements 12.4.3.B Cumulative dose contribution for the current calendar quarter and current calendar year for tritium, and all radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodologies and parameters in the ODCM at least once per 31 days. 12.4.3.C This Section implements the requirements of Sections 11.C, Ill.A and IV.A of Appendix I, 10CFR Part 50. The Operability Requirements are the guides set forth in Section 11.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time, implement the guides set forth in Section IV.A of Appendix I to assare that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculation methods specified in the Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The release-rate specifications for radioactive material in particulate form are dependent on the existing radionuclide pathways to man, at or beyond the SITE BOUNDARY. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) disposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man. Page 78 of 267
Revision 5 Aug31, 2015 12.4.4 Gaseous Effluent Treatment System Operability Requirements 12.4.4.A The GASEOUS EFFLUENT TREATMENT SYSTEM shall be OPERABLE* and appropriate portions of these systems shall be used to reduce radioactive materials in gaseous effluents when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at or beyond the SITE BOUNDARY (see Appendix F, Figure F-1) would exceed 0.3 mrem to any organ.
*The GASEOUS EFFLUENT TREATMENT SYSTEM shall be considered OPERABLE by meeting Sections 12.4.1 and/or 12.4.3, as applicable.
Applicability: At all times. Action: With the Gaseous Effluent Treatment System inoperable for more than 30 days or with radioactive gaseous waste being discharged without treatment and in excess of the above limits, return the system to OPERABLE status and place the appropriate portions of the system in use. Surveillance Requirements 12.4.4.B Doses due to gaseous releases from each unit to areas at or beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodologies and parameters in the ODCM when the Gaseous Effluent Treatment Systems are not beirig fully utilized. 12.4.4.C The OPERABILITY of the GASEOUS EFFLUENT TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to the release to the environment. he requirement that the appropriate portions of this system be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This section implements the requirement of 10CFR50.36a, General Design Criterion 60 of Appendix A to 10CFRSO and the design objective given in Section 11.D of Appendix I to 10CFR50. The specified limits governing the use of appropriate portions of the Gaseous Effluent Treatment System were specified as a 2% fraction of the dose design objectives set forth in Section 11.B and 11.C of Appendix I, 10CFR50, for gaseous effluents. Page 79 of 267
Revision 5 Aug 31, 2015 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitoring Program Operability Requirements 12.5.1.A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1. Applicability: At all times.
- 1. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting a program as required and the plans for preventing a recurrence.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditjons, seasonal unavailability, malfunction of sampling equipment, if a person who participates in the program goes out of business or no longer can provide sample, or contractor omission which is corrected as soon as discovered. If the equipment malfunctions, corrective actions shall be completed as soon as practical. If a person/business supplying samples goes out of business, a replacement supplier shall be found as soon as possible. All deviations from the sampling schedule $hall be described in the Annual Radiological Environmental Operating Report.
- 2. With the level of radioactivity as a result of plant effiuents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of Section 12.3.2or12.4.3. When more than one of the radionuclides in Table 12.5.2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) + concentration (2) + ... ~ 1.0 reporting level (1) reporting level (2) When radionuclides other than those in Table 12.5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Section 12.3.2 or 12.4.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
- The methodology and parameters used to estimate the potential dose to a MEMBER OF THE PUBLIC shall be indicated in the report.
Page 80 of 267
Revision 5 Aug 31, 2015
- 3. If the sample type or sampling location(s) required by Table 12.5-1 become(s) permanently unavailable, identify suitable alternative sampling media for the pathway of interest and/or specific locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program as soon as practicable. The specific locations from which samples were unavailable may then be deleted from the program.
Prepare and submit a controlled version of the ODCM within 180 days including a revised figure(s) and table reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location(s) for obtaining samples. Surveillance Requirements 12.5.1.B.1 The Radiological Environmental Monitoring samples shall be collected from the locations specified in the ODCM and analyzed pursuant to Table 12.5-1 and the detection capabilities required by Table 12.5-3. 12.5.1.C The Radiological Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10CFR50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements anc! modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The specified monitoring program is based on baseline/historical conditions for direct radiation measurements, soil, biota, and sediments established over years of operational experience and current site conditions/operating activities. The REMP need only be re-evaluated for major changes to site conditions/configuration (e.g., prior to site decommissioning, if a significant release occurs, changing baseline data ... ). Program changes may be initiated at any time based on operational experience. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLD}. The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., "Limits for Qualitative Detection and Quantitative Determination-Application to Radiochemistry," Anal. Chem. 40, 586-93 {1968), and Gartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). Interpretations 12.5.1.D Table 12.5-1 requires "one sample of each community drinking water supply downstream of the plant within 1O kilometers (6.2 miles)." Drinking water supply is defined as water taken from river, lakes, or reservoirs (not well water) which is used for drinking. Since Lake Michigan has no designated downstream or upstream direction, two drinking water locations (one north/one south} within 10 kilometers shall be sampled as drinking water indicator locations, and two other locations (one north/one south) beyond 10 kilometers shall be sampled as control locations. Page 81 of 267
Revision 5 Aug 31, 2015 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONs< 1> FREQUENCY ANALYSIS . G '**
- 1. Airborne Samples from a total of three locations: Particulate Sam~ler:
Continuous sampler operation Gross beta analysis following
- a. Indicator- Near Field with particulate sample collection 3 weekly filter chan~e< >and gamma weekly (or more frequently if isotopic analysis< quarterly on Three samples from locations within 4 km required due to dust loading).
composite filters by location on (2.5 mi) in different sectors. near field samples.
- b. Control- Far Field One sample from location 15-25 km (10-17 mi) in minimal D/Q sector.
Page 82 of 267
Revision 5 Aug 31, 2015 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1 EXPOSURE NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONs< > SAMPLING AND TYPE AND PATHWAY COLLECTION FREQUENCY OF AND/OR FREQUENCY ANALYSIS SAMPLE
- 2. Direct Thirty-one routine monitoring stations with thermoluminescent dosimeters (TLD),
Radiationt 5l placed with at least one monitoring location in each meteorological sector, as follows:
- a. Indicator- Inner Ring (100 Series TLD) in the general area of the SITE BOUNDARY (0.1 to 1.5 mi);
- b. Other- One at each Airborne location given in part 1.a. Including 1 control TLD location located at control air sample station given in part 1.b. Quarterly Gamma dose on each TLD quarterly.
- c. Indicator- Outer Ring (100 Series TLD) in the general area of the 5 mile ring.
(2.0 to 10 mi); Other TLDs may be placed at special interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Commonwealth Edison employees have routine access. Page 83 of 267
Revision 5 Aug 31, 2015 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS( 1l FREQUENCY ANALYSIS
- 3. Waterborne
- a. Drinking Water lndicator(6l One Sample from each community Gross beta and gamma isotopic drinking water supply that could be analyses( 4l on monthly composite; Weekly grab samples. tritium analysis on quarterly affected by the station discharge within 10 km (6.2 mi) of discharge (north/south). composite.
- b. Control(6>
Gross beta and gamma isotopic One sample upstream and downstream Weekly grab samples. analyses(4> on monthly composite; (north/south) of discharge. tritium analysis on quarterly composite.
- c. Sediments At least one sample within 10 km (6.2 mi) Semiannually. Gamma isotopic analysis (4l of discharge semiannually.
Page 84 of 267
Revision 5 Aug 31, 2015 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS( 1> FREQUENCY ANALYSIS
- 4. Ingestion
- a. Fish Indicator Representative samples of commercially and recreationally important species in Semiannually Gamma isotopic analysis(4l on discharge area. edible portions.
- b. Control Representative samples of commercially Semiannually Gamma isotopic analysis on edible and recreationally important species not portions.
influenced by plant discharge.
- 5. Vegetation
- a. Vegetation Indicator 3 Different types of broadleaf vegetation grown in the local area at publicly available vegetable markets. 2 Different types of root Annual (during growing season) Gamma isotopic analysis( 4l on vegetables grown in the local area at edible portions.
publicly available vegetable markets.
- b. Vegetation Control 3 Different types of broadleaf vegetation Annual {during growing season) Gamma isotopic analysis(4l on grown in the local area at publicly available edible portions.
vegetable markets. 2 Different types of root vegetables grown in an area >8 mi (12 km) from publicly available vegetable markets. Page 85 of 267
Revision 5 Aug 31, 2015 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every sample location in Table 11-1 of the ODCM Station Annexes. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. (2) Deleted - No longer applicable. (3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thorium daughter decay. If gross beta activity in any individual air particulate sample is greater than 10 times the 1999 mean of control samples, then, a gamma isotopic analysis shall be performed on that elevated individual sample. (4) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station. or identification of nuclides that are same type but not attributable to station effluents in the case of 'control' samples (5) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The number of locations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., If a station is adjacent to a lake (i.e. Zion), some sectors may be over water thereby reducing the number of dosimeters which could be placed at the indicated distances. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. (6) Refer to Section 12.5.1.D for interpretation on the applicability of "downstream" and "upstream". If no community drinking water supply exists within 6.2 miles of the discharge, surface water sampling shall be performed.
- Page 86 of 267
Revision 5 Aug 31, 2015 TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES* ANALYSIS WATER (pCi/L) AIRBORNE FISH (pCi/kg, wet) Vegetation (pCi/kg, PARTICULATE OR wet) GASES (pCi/m 3) H-3 20,000 \II Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 Cs-134 30 10 1,000 Cs-137 50 20 2,000 2,000 Ba-La-140 200 (1) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.
*This table contains reporting levels for analyses beyond the requirements of Table 12.5-1.
Page 87 of 267
Revision 5 Aug 31, 2015 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYS1s<1l LOWER LIMIT OF DETECTION (LLD)<2 > AIRBORNE Vegetation WATER PARTICULATE FISH (pCi/kg, wet) SEDIMENT ANALYSIS (pCi/L) OR GASES (pCi/kg, wet) (pCi/kg, dry) (pCi/m 3) Gross Beta 4 0.01 1000 H-3 2,000\;j) Mn-54 15 130 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 Cs-134 15 0.01 100 150 Cs-137 18 0.01 100 80 180 Page 88 of 267
Revision 5 Aug 31, 2015 TABLE 12.5-3 (Continued) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1) This table contains lower limits of detection for analyses beyond the requirements of Table 12.5-1. This table does not imply that only these nuclides are to be detected and reported; other peaks which are measurable and identifiable in the analyses required by Table 12.5-1 shall be reported in the Annual Radiological Environmental Operating Report. (2) The Lower Limit of Detection (LLD} is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation, the LLD is defined as follows: LLD = (E) (V) (2.22) (Y) (exp (-A~t)) LLD - (E) (V) (2.22) (Y) (exp (-Mt)) Where: 4.66 Sb >> 3/tb
- LLD =the "a priori" Lower Limit of Detection (picocuries per unit mass or volume),
sb = the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (counts per minute),
.J Total Counts
=
E =the counting efficiency( counts per disintegration}, V =the sample size (units of mass or volume), 2.22 =the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular ra-dionuclide (sec*1), tb =counting time of the background or blank (minutes), and Page 89 of 267
Revision 5 Aug 31, 2015 TABLE 12.5-3 (Continued) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS
~t = the elapsed time between sample collection, or end of the sample collection period, and the time of counting (sec).
Typical values of E, V, Y, and ~t should be used in the calculation. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report. (3) This is the minimum required LLD; however, environmental samples analyzed off-site will be required to use 200 pCi/I. Page 90 of 267
Revision 5 Aug 31, 2015 12.5.2 LAND USE CENSUS Operability Requirements 12.5.2.A. A Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2_mi.) the location, in each of the following meteorological sectors, A, J, K, L, M, N, P, Q, and R**, the nearest residence. For dose calculation, a garden will be assumed at the nearest will residence .. For REMP purposes, aerial phographs or equivalent method shall be used to determine the nearest garden/farm >500 sq. ft (50sq meters) in each sector within 10 mi. (15km) Applicability: At all times. Action: With a Land Use Census identifying location(s) that yields a calculated dose or dose commitment, via the same exposure pathway 20% greater than at a location from which samples are currently being obtained in accordance with Section 12.5.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in Chapter 11 of the ODCM Station Annexes. The sampling location(s), excluding the control location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.
** The nearest industrial facility shall also be documented if closer than the nearest residence.
Surveillance Requirements 12.5.2.B The Land Use Census shall be conducted, between June 1 and October 1, at least once_per calendar year using that information that will provide the best results, such as by a door-to-door survey or aerial survey. The result of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report. 12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Page 91 of 267
Revision 5 Aug 31, 2015 12.5.3 INTERLABORATORY COMPARISON PROGRAM Operability Requirements 12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an interlaboratory comparison program that correspond to samples required by Table 12.5.1. Applicability: At all times.
- 1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
Surveillance Requirements 12.5.3.B A summary of the results obtained as part of the above required interlaboratory comparison program shall be included in the Annual Radiological Environmental Operating Report. 12.5.3.C The requirement for participation in an interlaboratory comparison program is provided to ensure that independent checks on the preci$ion and accuracy of the measurements of radioactive material in environmental samples matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the resultS are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50. Page 92 of 267
Revision 5 Aug 31; 2015 12.6 PROCESS CONTROL PROGRAM (PCP) 12.6.1 PCP Program Requirements Contains the requirements and methodology for the current formulas, sampling, analyses, tests, and determinations performed to ensure the processing and packaging of solid radioactive wastes based on actual or simulated wet solid wastes is accomplished in compliance with:
- 10CFR Parts 20, 61, and 71
- State Regulations
- Burial Site Requirements
- Other Requirements Governing the Shipping and Burial of Radioactive Waste 12.6.2 Changes to the PCP Changes to the PCP include those changes that affect the process or methodology, by which wastes are solidified, packaged to meet burial site form requirements, classified, or dewatered.
12.6.2.1. Shall be documented and records of reviews performed shall be retained, and Shall contain sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s), and Shall contain a determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations, and Shall become effective after review and approval by the Decommissioning Plant Manager. Page 93 of 267
Revision 5 Aug 31, 2015 12.7 REPORTING REQUIREMENTS 12.7.1 Annual Radiological Environmental Operating Report* Routine Annual Radiological Environmental Operating Report covering the operation of the Unit(s) during the previous calendar year shall be submitted according to the Permanently Defueled Technical Specifications. The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including, as found appropriate, a comparison of preoperational studies with operational controls or with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The Annual Radiological Environmental Operating Report shall include the results of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in the Chapter 11 of the ODCM Station Annexes, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section 12.5.1, and discussion for all deviations from the sampling schedule of Table 11.1-1; a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents; discussion of all analyses in which the LLD required by Table 12.5-3 was not achievable; results of the Land Use Census required by Section 12.5.2; and the results of licensee participation in an interlaboratory comparison program and the corrective actions being taken if the specified program is not being performed as required by Section 12.5.3. The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the applicable year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
- A single submittal may be made for a multiple unit station.
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Revision 5 Aug 31, 2015 The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This report shall also include an assessment of radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM and in compliance with 10 CFR 20 and 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation." 12.7.2 Annual Radioactive Effluent Release Report** The Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluent from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases of radioactive material in liquid effluents from the site to UNRESTRICTED AREAS and of unplanned releases of radioactive material in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY during the reporting period. The Annual Radioactive Effluent Release Report shall include any changes made during the reporting period to the Process Control Program as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12. 7.4. The Annual Radioactive Effluent Release Report shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Section 12.2.1 or 12.2.2, respectively; and description of the events leading to liquid holdup tanks exceeding the limits of the Quality Assurance Project Plan App.B. 12.7.2.1 Exceptions to Regulatory Guide 1.21 Reporting Requirements:
- a. All references to "semiannual" are not applicable. The report will be submitted according to Quality Assurance Project Plan (QAPP).
- b. Hourly meteorological data is recorded for all periods throughout the year, and quarterly summaries will be reported. Separate meteorological data for periods of batch releases are not required to be included.
- c. Total body and significant organ doses to the maximally exposed individual from receiving-water-related exposure pathways will be provided. Associated population dose is not required to be included.
- d. Organ doses to the maximally exposed individual in unrestricted areas from radioactive material in particulate form from all exposure pathways will be provided. Associated population dose is not required to be included.
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Revision 5 Aug 31, 2015
- e. Total body doses to the maximally exposed individual in unrestricted areas from direct radiation from the facility should be included in the report. Associated population dose is not required to be included.
- f. Total body doses to the population and average doses to individuals in the population from all receiving-water-related pathways are not required to be included.
- g. Total body doses to the population and average doses to individuals in the population from gaseous effluents to a distance of 50 miles from the site and beyond will not be included.
- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
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Revision 5 Aug 31, 2015 12.7.3 Offsite Dose Calculation Manual CODCM) 12.7.3.1 Changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be retained as required by QAPP. This documentation shall contain:
- 1. Sufficient Information to support the change together with the appropriate analyses or evaluations justifying the change( s); and
- 2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- 3. Documentation of the fact that the change has been reviewed and found acceptable by a Qualified Technical Review.
- b. Shall become effective after the approval of the Decommissioning Plant Manager on the date specified by the Qualified Technical Review.
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,
month/year) the change was implemented. 12.7.4 Major Changes to Liquid and Gaseous Effluent Treatment Systems*** Licensee-initiated major changes to the Effluent Treatment Systems (liquid and gaseous):
- a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by a Qualified Technical Review. The discussion of each change shall contain:
- 1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;
- 2) Sufficient detailed information to totally support the reason for the change without benefit of additional and supplemental information;
- 3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.
- 4) An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the License application and amendments thereto;
- 5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC and to the general population that differ from those previously estimated in the License application and amendments thereto; Page 97 of 267
Revision 5 Aug 31, 2015
- 6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made;
- 7) An estimate of the exposure to plant operating personnel as a result of the change; and
- 8) Documentation of the fact that the change was reviewed and found acceptable by a Qualified Technical Review.
- b. Shall become effective upon review and acceptance by the Qualified Technical Review.
- Licensees may choose to submit the information called for in this standard as part of the biennial DSAR update.
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Revision 5 Aug 31, 2015 APPENDIX A COMPLIANCE METHODOLOGY Page 99 of 267
Revision 5 Aug 31, 2015 APPENDIX A COMPLIANCE METHODOLOGY A.O INTRODUCTION This appendix reviews the offsite radiological limits applicable to Zion Station' and presents in detail the equations and procedures used to assess compliance with these limits. An introduction to the calculation approach used here is given in Chapter 4. The approach incorporates simplifications such as the following: Use of pre-calculated atmospheric transport parameters based on historical average atmospheric conditions (see Section 4.1.5). These atmospheric dispersion and deposition factors are defined in Chapter 4. The equations and parameters of this appendix are for use in calculating offsite radiation doses during routine operating conditions. They are not for use in calculating doses due to non-routine releases (e.g., accident releases). This section of the ODCM provides the methodological details for demonstrating compliance with the 10CFR20, 10CFR50 Appendix I, 10CFR72.104 and 40CFR190 radiological limits for liquid and gaseous effluents. An overview of the required compliance is given in Tables 2-1, 2-2, and 2-3. In Table 2-1, the dose components are itemized and referenced, and an indication of their regulatory application is noted. A more detailed compliance matrix is given in Table 2-3. Additionally, the locations of dose receivers for each dose component are given in Table 2-2. The following sections detail the required radiological dose calculations. A.1 AIRBORNE RELEASES A.1.1 Release Point Classifications The pattern of dispersion of airborne releases is dependent on the height of the release point relative to adjacent structures. For the equations of this appendix, each release point is classified as one of the following three height-dependent types, which are defined in Section 4.1.4:
- Stack (or Elevated) Release Point (denoted by the letter Sor subscripts)
- Ground Level Release Point {denoted by the letter G or subscript g)
- Vent (or Mixed Mode) Release Point (denoted by the letter V or subscript v)
The release point classifications of routine release points at Zion Station are stated in Table A-2. A.1.2 Dose Due to Noble Gas Radionuclides A.1.2.1 Gamma Air Dose Requirement RETS limit the gamma air dose due to noble gas effluents released from each reactor unit to areas at and beyond the unrestricted area boundary to the following:
- Less than or equal to 5 mrad per calendar quarter.
- Less than or equal to 10 mrad per calendar year.
Page 100 of 267
Revision 5 Aug 31, 2015 Equation The gamma air dose due to noble gases released in gaseous effluents is calculated by the following expression: Dr = (3.17E - 8 )L M; { (x/Qt i A;s + (x/Q)~ A;v + (x/Q)~ A; 0 } (A-1) The summation is over noble gas radionuclides i. Gamma Air Dose [mrad] Dose to air due to gamma radiation from noble gas radionuclides released in gaseous effluents. 3.17E-8 Conversion Constant (seconds to years) [yr/sec] M; Gamnia Air Dose Conversion Factor [(mrad/yr)/(µCi/m 3 )] Gamma air dose rate factor per unit of radioactivity release rate for radionuclide i. From Table B-1 of Reg Guide 1.190. (x/Q)~' (x/Q)~' (x/Q)~ Gamma-x/Q Factor Radioactivity concentration based on finite cloud methodology at a specific location per unit of radioactivity release rate from a stack, vent or ground level release, respectively. See Section B.3.5 and Table F-5b of appendix F. Cumulative Radionuclide Release [µCi] Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively. Application RETS require determination of cumulative and projected gamma air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days (see Sections 12.4 of Zion Station' RETS or Technical Specifications). Gamma air dose is calculated for the sector with the highest offsite (x/Qf and is compared with the RETS limits on gamma air dose. For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10. Page 101 of 267
Revision 5 Aug 31, 2015 A.1.2.2 Beta Air Dose Requirement RETS limit the beta air dose due to noble gases in gaseous effluents released from each reactor unit to areas at and beyond the unrestricted area boundary to the following:
- Less than or equal to 10 mrad per calendar quarter.
- Less than or equal to 20 mrad per calendar year.
Equation The beta air dose due to noble gases released in gaseous effluents is calculated by the following expression: Dp =(3.17E- s)L {N;((x/Q)sAis + (x/Q)vAiv + (x/Q)9 A; 9 ]} (A-2) i The summation is over noble gas radionuclides i. Beta Dose [mrad] Dose to air due to beta radiation from noble gas radionuclides released in gaseous effluents. 3.17E-8 Conversion Constant (seconds to years) [yr/sec] 3 N; 13eta Air Dose Conversion Factor [(mrad/yr)/(µCi/m )] Beta air dose rate per unit of radioactivity concentration for radionuclide i. Take from Table C-9 of Appendix C. (x/Q)s Relative Concentration Factor (x/Q)v
<xtQ)g Radioactivity concentration based on semi-infinite cloud methodology at a specified location per unit of radioactivity release rate for a stack, vent, or ground level release, respectively. See Section 4.1.6, Section B.3 of Appendix B, and Table F-5 of Appendix F.
Cumulative Radionuclide Release [µCi] Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively. Application RETS require determination of cumulative and projected beta air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days (see Section 12.4
- of Zion Station RETS or Technical Specification).
Beta air dose is calculated for the sector with the highest offsite (x/Q) and is compared with the RETS limit on beta air dose. For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10. Page 102 of 267
Revision 5 Aug 31, 2015 A.1.2.3 Total Body Dose Requirement The total body dose, to any receiver is due, in part, to gamma radiation emitted from radioactivity in airborne effluents. This component is added to others to demonstrate compliance to the requirements of 40CFR190 and 10CFR20. Equation The total body dose component due to gamma radiation from noble gases released in gaseous effluents is calculated by the following expression: Dre =(3.17E-8}LK;{(x/Q)~A;s +{x/Q)~A;v +{x;onA;9 } (A-3) i The summation is over noble gas radionuclides i. Drs Total Body Dose [mrem] Dose to the total body due to gamma radiation from noble gas radionuclides released in gaseous effluents. 3.17E-8 Conversion Constant (seconds to years) [yr/sec] K; Gamma Total Body Dose Conversion Factor [(mrem/yr)/(uCi/m3)] Gamma total body dose factor due to gamma emissions for noble gas radionuclide i released from a stack, vent or ground level release point, respectively. Taken from Table C-9 of Appendix C. A;s, A;v. A;g Cumulative Radionuclide Release [µCi] Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively. Application The total body dose is also calculated for the 40CFR190 and 10CFR20 compliance assessments. In some cases, the total body dose may be required in 10CFR50 Appendix I assessments (See Table 2-1 ). A.1.2.4 Skin Dose Requirement There is no regulatory requirement to evaluate skin dose. However, this component is evaluated for reference as there is skin dose design objective contained in 10CFR50 Appendix I. Note that in the unlikely event that if beta air dose guideline is exceeded, then the skin dose will require evaluation. Equation The part of skin dose due to noble gases released in gaseous effluents is calculated by the following expression: DsK = (3.17E - 8} L {L; [ {x/Q} A; 5 5 + {x/Q}v A;v + {x/Q}9 A, 9 ] i (A-4)
+ (1.11)M, [ (x/Q)~Ais +{x/Q)~Aiv +{x/Q)~A;g]}
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Revision 5 Aug 31, 2015 The summation is over noble gas radionuclides i. DsK Skin Dose [mrem] Dose to the skin due to beta and gamma radiation from noble gas radionuclides released in gaseous effluents. 3 Beta Skin Dose Conversion Factor [(mrem/yr)/(µCi/m )] Beta skin dose rate per unit of radioactivity concentration for radionuclide i. Taken from Table C-9 of Appendix C. 1.11 Conversion Constant (rads in air to rem in tissue) [mrem/mrad] All other terms have been previously defined. Application The skin dose is calculated for reference only. A.1.3 Dose Rate Due to Noble Gas Radionuclides A.1.3.1 Total Body Dose Rate Requirement RETS limit the total body dose rate due to noble gases in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to 500 mrem/yr at all times. (see Section 12.4 of Zion Station RETS and Technical Specifications) Equation The total body dose rate due to noble gases released in gaseous effluents is calculated by the following expression: ihe = LK; ((x/Q)~Qis +{x/Q)~Qiv +{x/0)~0; 9 } (A-5) i The summation is over noble gas radionuclides i. D10 Total Body Dose Rate [mrem/yr] Dose rate to the total body due to gamma radiation from noble gas radionuclides released in gaseous effluents. Release Rate [µCi/sec] Measured release rate of radionuclide i from a stack, vent or ground level release point, respectively. All other terms have been previously defined. Page 104 of 267
Revision 5 Aug 31, 2015 Application RETS require the dose rate due to noble gases in gaseous effluents be determined to be within the above limit in accordance with methodology specified in the ODCM (see Section 12.4 of Zion Stations RETS and Technical Specifications). To comply with this specification, Zion Station uses an effluent radiation monitor setpoint corresponding to an offsite total body dose rate at or below the limit (see Chapter 10). In addition, Zion Station assesses compliance by calculating offsite total body dose rate on the basis of periodic samples obtained in accordance with station procedures. A.1.3.2 Skin Dose Rate Requirement RETS limit the skin dose rate due to noble gases in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to a dose rate of 3000 mrem/yr at all times. (See Section 12.4 of Zion Stations RETS and/or Technical Specifications) Equation The skin dose rate due to noble gases released in gaseous effluents is calculated by the following expression: DsK = L{L;[(x/Q)sQis +{x/Q)vQiv +{x/0) 0; 9 9] i (A-6)
+ (1.11) M; [ (x/Q)~O;s +{x/Q)~O;v +{x/Q)~0; 9 ]}
The summation is over noble gas radionuclides i. DsK Skin Dose Rate [mrem/yr] Dose rate to skin due to beta and gamma radiation from noble gas radionuclides released in gaseous effluents. Release Rate [µCi/sec] Measured release rate of radionuclide i from a stack, vent or ground level release point, respectively. All other terms been previously defined. Application RETS require the dose rate due to noble gases in gaseous effluents to be determined to be within the above limit in accordance with methodology specified in the ODCM. (See Section 12.4 of ZionSolutions' RETS and Technical Specifications.) To comply with this specification, Zion Station uses an effluent radiation monitor setpoint corresponding to an offsite skin dose rate at or below the limit (see Chapter 10). In addition, ZionSo/utions' assesses compliance by calculating offsite skin dose rate on the basis of samples obtained periodically in accordance with site procedures. Page 105 of 267
Revision 5 Aug 31, 2015 A.1.4 Dose Due to Non-Noble Gas Radionuclides Requirement RETS provide the following limits, based on 10CFR50 Appendix I, on the dose to a member of the public from specified non-noble gas radionuclides in gaseous effluents released from each reactor unit to areas at and beyond the unrestricted area boundary: Less than or equal to 7.5 mrem to any organ during any calendar quarter. Less than or equal to 15 mrem to any organ during any calendar year. The individual dose components are also required as part of the 40CFR190 assessments and combined as part of the 10CFR20 assessment (See Section A.4 ). The dose due to radionuclides deposited on the ground is considered to be a component of the deep dose equivalent for 10CFR20 compliance and an organ (and total body) dose component for 10CFR50 Appendix I and 40CFR190 compliance. In accordance with the definition of dose in Regulatory Guide 1.109, the term "dose" in this document when applied to individuals, is used instead of the more precise term "dose equivalent," as defined by the International Commission on Radiological Units and.Measurements (ICRU). When applied to the evaluation of internal deposition of radioactivity, the term "dose" as used here, includes the prospective dose component arising from retention in the body beyond the period of environmental exposure, i.e., the dose commitment. The dose commitment is evaluated over a period of 50 years. Assessments for 10CFR50 Appendix I compliance are made for 4 age groups (adulUteenager/child/infant) using Regulatory Guide 1.109 (Reference 6) dose conversion factors. Equation The dose is calculated for releases in the time period under consideration. Specifically, the dose is calculated as follows: D~NG = (3.17E-8)_'L_'L[WsRaipiAis + WvRaipiAiv + W 9 RaipiA; 9 ] (A-7) p i The summation is over pathways p and non-noble gas radionuclides i. Dose Due to Non-Noble Gas Radionuclides [mrem] Dose due to non-noble gases (tritium and particulates) to age group a, and to organ j. 3.17E-8 Conversion Constant (seconds to years) [yr/sec] Relative Concentration Factor Radioactive concentration at a specific location per unit of radioactivity release rate or concentration for stack, vent or ground level release, respectively. Ws, Wv, or W 9 = (x/O)s, (x/O)v or (x/0)9 for immersion, inhalation and all tritium pathways. W 5 , Wv, or W 9 =(D/0) 5 , (D/O)v or (D/Q) 9 for ground plain and all ingestion pathways. Page 106 of 267
Revision 5 Aug 31, 2015 3 (x/Q)s, (x/Q)v. (x/Q)g Relative Concentration Factor [sec/m ] Radioactivity concentration based on semi-infinite cloud model at a specified location per unit of radioactivity release rate for a stack, vent, or ground level release, respectively. See Section 4.1.6, Section B.3 of Appendix B, and Table F-5 of Appendix F. (D/Q)s. (D/Q)v. (D/Q)g Relative Deposition Factor Radioactivity concentration at a specified location per unit of radioactivity release concentration for a stack, vent, or ground level release, respectively. See Section 4.1.6, Section B.3 of Appendix B, and Table F-6 of Appendix F. 2 Raipi Site-Specific Dose Factor [(m mrem/yr)/(µCi/sec)] 3 or [(mrem/yr)/(µCi/m )] Site-specific dose factor for age group a, nuclide i, pathway p and organ
- j. Pathway included are ground plane exposure, inhalation, vegetation inge~tion, milk ingestion and meat ingestion. Values of Raipi are provided in Appendix F.
Cumulative Radionuclide Release [µCi] Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively. Application RETS require cumulative and projected dose contributions for the current calendar quarter and the current calendar year for the specified non-noble gas radionuclides in airborne effluents to be determined at least once per 31 days (see Section 12.4 of Zion Stations' RETS and Technical Specifications). To comply with this specification, Zion Station obtains and analyzes samples in accordance with the radioactive gaseous waste or gaseous effluent sampling and analysis program in its RETS. In accordance with NUREG 0133 (Reference 14), dose due to non-noble gases is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure. The inhalation and ground plane exposure pathways are considered to exist at all locations. The food ingestion pathways at a specific location are considered based on their existence as determined by land use census. The values used for (x/Q) and (D/Q) correspond to the applicable pathway location. For a release attributable to a processing or effluent system shared by more than one reactor, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10. The dose evaluated is also included as part of the 10CFR20 and 40CFR190 assessment (See Section A.4). A.1.4.1 Ground Deposition The site-specific dose factor for ground deposition of radioactivity is considered to be a total body dose component and is calculated by the following expression: Page 107 of 267
Revision 5 Aug 31, 2015 (A-8) 2 Rai(GP)i [D/Q] Ground Plane Deposition Dose Factor [(m mrem/yr)/(µCi/sec)] Site-specific ground plane dose factor for age group a, nuclide i and organ j. The ground plane dose is calculated using (D/Q). K' Conversion Constant (1 E6 pCi per µCi) [pCi/µCi] K" Conversion Constant (8760 hr/yr) [hr/yr] 0.7 Shielding Factor; a factor which accounts for dimensionless shielding due to occupancy of structures. 2 Ground Plane Dose Conversion Factor [(mrem/hr)/(pCi/m )] Dose rate to the total body per unit of surface radioactivity concentration due to standing on ground uniformly contaminated with radionuclide i. Taken from Table C-10 of Appendix C. Note that ground plane dose factors are only given for the total body and no age group. Doses to other organs are assumed to be equal to the total body dose. All age groups are assumed to receive the same dose. Radiological Decay Constant Radiological decay constant for radionuclide i. See Table C-7 of Appendix C. Time Period of Ground Deposition [hr] Time period during which the radioactivity on the ground is assumed to have been deposited. See Table C-1 of Appendix C. Application The ground plane exposure pathway is considered to exist at all locations. A.1.4.2 Inhalation The site-specific dose factor for inhalation is calculated by the following expression: (A-9) 3 Rai(lnhal)j [x/Q] Inhalation Pathway Dose Factor [(mrem/yr)/(µCi/m )] Site-specific inhalation dose factor for age group a, nuclide i and organ j. The inhalation dose is calculated using (x/Q). K' Conversion Constant (1 E6 pCi per µCi) [pCi/µCi] 3 BRa Individual Air Inhalation Rate [m /yr] Page 108 of 267
Revision 5 Aug 31, 2015 The air intake rate for individuals in age group a. See Table C-2 of Appendix C. DFAaii Inhalation Dose Conversion Factor [mrem/pCi] Dose commitment to an individual in age group a to organ j per unit of activity of radionuclide i inhaled. Taken from Tables E-7 through E-10 of Regulatory Guide 1.109. The value for H-3 is taken from NU REG 4013 (Reference 107). Application The inhalation exposure pathway is considered to exist at all locations. A.1.4.3 Food Ingestion Pathway Dose Factors Application Food ingestion pathway doses are calculated at locations indicated by the land use census survey. If no real pathway exists within 5 miles of the station, the cow-milk pathway is assumed to be located at 5 miles. Food pathway calculations are not made for sectors in which the offsite regions near the station are over bodies of water. A.1.4.3.1 Vegetation Ingestion Pathway Dose Factor The dose factor for consumption of vegetables is calculated by the following expression: (A-10) 2 Vegetation Ingestion Pathway Dose Factor [(m mrem/yr)/(µCi/sec)] Site-specific vegetation ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3, the vegetation dose is calculated using (D/Q). K' Conversion Constant (1 E6 pCi per µCi) [pCi/µCi] r Vegetation Retention factor dimensionless Agricultural Productivity Yield Radiological Decay Constant [1/sec] Radiological decay constant for radionuclide i. See Table C-7 of Appendix C. Weathering Decay C<?nstant [1/sec] Removal constant for physical loss of activity by weathering. See Table C-1 of Appendix C. DFLaii Ingestion Dose Conversion Factor [mrem/pCi] Ingestion dose conversion factor for age group a, nuclide i and organ j. Converts pCi ingested to mrem. Taken from Tables E-11 though E-14 of Page 109 of 267
Revision 5 Aug 31, 2015 Regulatory Guide 1.109. The value for H-3 is taken from NUREG 4013 (Reference 107). Consumption Rate for Fresh Leafy Vegetation [kg/yr] Consumption rate for fresh leafy vegetation for age group a. Consumption Rate for Stored Vegetation [kg/yr] Consumption rate for stored vegetation for age group a. Local Leafy Vegetation Fraction dimensionless Fraction of the annual intake of fresh leafy vegetation which is grown locally. Local Stored Vegetation Fraction dimensionless Fraction of the annual intake of stored vegetation which is grown locally. Environmental Transport Time - Fresh Vegetation [sec] Average time between harvest of leafy vegetation and its consumption. Environmental Transport Time - Stored Vegetation [sec] Average time between harvest of stored vegetation and its consumption. The tritium dose from the vegetation pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium vegetation pathway is: (A-11) Ra(H-3)(vee)i [x/Q] Tritium Vegetation Ingestion Pathway Dose Factor [(mrem/yr)/(µCi/m 3l] Site-specific tritium vegetation ingestion dose factor for age group a and organ j. The tritium vegetation dose is calculated using x/Q. K"' Conversion Constant (1 E3 gm per Kg) [gm/Kg] H Absolute Atmospheric Humidity [gm/m 3] 0.75 Water Fraction dimensionless The fraction of total vegetation that is water. 0.5 Specific Activity Ratio dimensionless Page 110 of 267
Revision 5 Aug 31, 2015 A.1.4.3.2 Milk Ingestion Pathway Dose Factor The dose factor for consumption of milk is calculated by the following expressions: (A-12) 2 Rai(Milk)j [D/Q] Milk Ingestion Pathway Dose Factor [(m mrem/yr)/(µCi/sec)] Site-specific milk ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3, the milk dose factor is calculated using (D/Q). K' Conversion Constant (1E6 pCi per µCi) [pCi/µCi] Feed Co_nsumption [Kg/da] Amount of feed consumed by milk animal each day. See Table C-1 of Appendix C. Milk Consumption Rate [I/yr] Milk consumption rate for age group a. Stable Element Transfer Coefficient for Milk [da/I] Fraction of animal's daily intake of a particular chemical element which appears in each liter of milk (pCi/I in milk per pCi/da ingested by animal). See Table C-3 of Appendix C. Pasture Time Fraction dimensionless Fraction of year that animal is on pasture. Pasture Grass Fraction dimensionless Fraction of animal feed that is pasture grass while animal is on pasture. Agricultural Productivity Yield - Pasture Grass The agricultural productivity by unit area of pasture feed grass. Ys Agricultural Productivity Yield - Stored Feed The agricultural productivity by unit area of stored feed. Environmental Transport Time - Stored Feed [sec] Average time between harvest to consumption of stored feed by milk animal. Page 111 of 267
Revision 5 Aug 31, 2015 Environmental Transport Time - Pasture to Consumption [sec] Average time from pasture, to milk animal, to milk, to consumption. All other terms have been previously defined. The tritium dose from the milk pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium milk pathway is: (A-13) 3 Tritium Milk Ingestion Pathway Dose Factor [(mrem/yr)/(µCi/m )] Site-specific tritium milk ingestion dose factor for age group a and organ
- j. The tritium milk dose is calculated using x/Q.
K"' Conversion Constant (1 E3 gm per Kg) [gm/Kg] H Absolute Atmospheric Humidity [gm/m 3] 0.75 Water Fraction dimensionless The fraction of total vegetation that is water. 0.5 Specific Activity Ratio dimensionless All other terms have been previously defined. A.1.4.3.3 Meat The dose factor for consumption of meat is calculated by the following expression: (A-14) 2 Rai(Meat)j [D/Q] Meat Ingestion Pathway Dose Factor [(m mrem/yr)/(µCi/sec)] Site-specific meat ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3, the meat dose factor is calculated using (D/Q). Meat Consumption Rate [I/yr] Meat consumption rate for age group a. Stable Element Transfer Coefficient for Meat [da/Kg] Fraction of animal's daily intake of a particular chemical element which appears in each liter of meat (pCi/Kg in meat per pCi/da ingested by animal). See Table C-3 of Appendix C. Page 112 of267
Revision 5 Aug 31, 2015 Environmental Transport Time - Stored Feed [sec] Average time between harvest to consumption of stored feed by meat animal. Environmental Transport Time - Pasture to Consumption [sec] Average time from pasture, to meat animal, to meat, to consumption. All other terms have been previously defined. The tritium dose from the meat pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium meat pathway is: (A-15) R a(H:-3 )(Meat )i fx/ Q] Tritium Meat Ingestion Pathway Dose Factor [(mrem/yr)/(µCi/m 3
)]
Site-specific tritium meat ingestion dose factor for age group a and organ
- j. The tritium meat dose is calculated using x/O.
K"' Conversion Constant (1 E3 gm per Kg) [gm/Kg] 3 H Absolute Atmospheric Humidity [gm/m ] 0.75 Water Fraction dimensionless The fraction of total vegetation that is water. 0.5 Specific Activity Ratio dimensionless All other terms have been previously defined. A.1.5 Dose Rate Due to Non-Noble Gas Radionuclides Requirement RETS limit the dose rate to any organ, due to radioactive materials in gaseous effluents released from a site to areas at and beyond the site boundary, to less than or equal to a dose rate of 1500 mrem/yr (see Section 12.4 of ZionSolutions' RETS and Technical Specifications). Typically the child is considered to be the limiting receptor in calculating dose rate to organs due to inhalation of non-noble gas radionuclides in gaseous effluents. Equation The dose rate to any child organ due to inhalation is calculated by the following expression: (A-16) The summation is over non-noble gas radionuclides i. Page 113 of267
Revision 5 Aug 31, 2015
- NNG D (Child)i(lnhal)i Inhalation Dose Rate [mrem/yr]
Dose rate to the child age group from radionuclide i, via the inhalation pathway to organ j due to non-noble gas radionuclides. 3 R(Child)i(lnhal)j Inhalation Dose Factor [(mrem/yr)/(µCi/m )] Inhalation dose factor for child age group for radionuclide i, and organ j. This dose factor is defined by Equation A-9. Radionuclide Release Rate [µCi/sec] Measured release rate of radionuclide i from a stack, vent, or ground level release point, respectively. All other terms have been previously defined. Application RETS require the dose rate due to non-noble gas radioactive materials in airborne effluents be determined to be within the above limit in accordance with a sampling and analysis program specified in the RETS (see Section 12.4 of Zion Solutions' RETS and Technical Specifications). To comply with this specification, ZionSo/utions' obtains and analyzes samples in accordance with the sampling and analysis program in its RETS. The child organ dose rate due to inhalation is calculated in each sector at the location of the highest offsite x/O. The result for the sector with the highest organ inhalation dose rate is compared to the limit. A.1.6 Operability and Use of Gaseous Effluent Treatment Systems Requirement 10CFR50 Appendix I and the station RETS require that the ventilation exhaust treatment system and the waste gas holdup system be used when projected offsite doses in 31 days, due to gaseous effluent releases, from each reactor unit, exceed any of the following limits:
- 0.2 mrad to airfrom gamma radiation.
- 0.4 mrad to air from beta radiation.
- 0.3 mrem to any organ of a member of the public.
ZionSolutions' is required to project doses due to gaseous releases from the site at least once per 31 days. Equation Offsite doses due to projected releases of radioactive materials in gaseous effluents are calculated using Equations A-1, A-2 and A-7. Projected cumulative radionuclide releases are used in place of measured cumulative releases Ais* Aiv and Aig* Application For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in Chapter 10 of this manual. Page 114 of 267
Revision 5 Aug 31, 2015 A.2 LIQUID RELEASES A.2.1 Dose Requirement The design objectives of 10CFR50, Appendix I and RETS provide the following limits on the dose to a member of the public from radioactive materials in liquid effluents released from each reactor unit to restricted area boundaries: During any calendar quarter, less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ. During any calendar year, less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ. The organ doses due to radioactivity in liquid effluents are also used as part of the 40CFR190 compliance and are included in the combination of doses to determine the total dose used to demonstrate 10CFR20 compliance. (See Section A.4) Dose assessments for 10CFR50 Appendix I compliance are made for four age groups (adulUteenager/child/infant) using NU REG 0133 (Reference 14) methodology and Regulatory Guide 1.109 (Reference 6) dose conversion factors. Equation The dose from radioactive materials in liquid effluents considers the contributions for consumption of fish and potable water. All of these pathways are considered in the dose assessment unless demonstrated not to be present. While the adult is normally considered the maximum individual, the methodology provides for dose to be calculated for all four age groups. The dose to each organ (and to the total body) is calculated by the following expression: D~]q = F At LLAaipiC; (A-17) p i The summation is over exposure pathways p and radionuclides i. Organ and Total Body Dose Due to Liquid Effluents [mrem] Dose to organ j (including total body) of age group a due to radioactivity in liquid effluents. F Near Field Average Dilution Factor dimensionless Dilution in the near field averaged over the period of interest. Defined as: F= Waste Flow (A-18) Dilution Flow x Z Waste Flow Liquid Radioactive Waste Flow [gpm] The average flow during disposal from the discharge structure release point into the receiving water body. Dilution Flow Dilution Water Flow During Period of Interest [gpm] Page 115 of 267
Revision 5 Aug 31, 2015 z Discharge Structure Mixing Factor dimensionless Site-specific factor to account for the mixing effect of the discharge structure. The factor addresses the dilution which occurs in the near field between the discharge structure and the body of water containing the fish in the liquid ingestion pathway. From Table F-1, Appendix F. At Duration of Release [hrs] Average Radionuclide Concentration [µCi/ml] Average concentration of radionuclide i, in the undiluted liquid effluent during time period At. Aaipj Site-Specific Liquid Dose Factor [(mrem/hr)/(µCi/ml)] Site-specific dose factor for age group a, nuclide i, liquid pathway p and organ j. The pathways included are potable water and fish ingestion. Aaipi is defined for these pathways in the following sections. Values for Aaipi are provided in Appendix F. A 2.1.1 Potable Water Pathway The site-specific potable water pathway dose factor is calculated by the following expression: (A-19) Where: Aai(PW)j Site-Specific Dose Factor for Potable Water [(mrem/hr)/(µCi/ml)] Pathway Site-specific potable water ingestion dose factor for age group a, nuclide i and organ j. Conversion Constant (1.14E05) [(yr-pCi-ml)/(hr-µCi-1)] Units constant to convert years to hours, pCi to µCi and liters to ml. Potable Water Consumption Rate [I/yr] Potable water consumption rate for age group a. Taken from Table E-5 of Regulatory Guide 1.109. Potable Water Dilution Factor dimensionless Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake. From Table F-1, Appendix F. DFLaii Ingestion Dose Conversion Factor [mrem/pCi] Ingestion dose conversion factor for age group a, nuclide i and organ j. Converts pCi ingested to mrem. Taken from Tables E-11 though E-14 of Page 116 of 267
Revision 5 Aug 31, 2015 Regulatory Guide 1.109. The value for H-3 is taken from NU REG 4013 (Reference 107). A.2.1.2 Fish Ingestion Pathway The site-specific fish ingestion pathway dose factor is calculated by the following expression: (A-20) Where: Aai(Fish)j Site-Specific Dose Factor for Potable Water [(mrem/hr)/(µCi/ml)] Pathway Site-specific fish ingestion dose factor for age group a, nuclide i and organj. Fish Consumption Rate [kg/yr] Fish consumption rate for age group a. Taken from Table E-5 of Regulatory Guide 1.109. Bioaccumulation Factor [(pCi/kg)/(pCi/I)] Bioaccumulation factor for nuclide i in fresh water fish. Taken from Table C-8 of Appendix C. All other terms have been previously defined. Application RETS require determination of cumulative and projected dose contributions from liquid effluents for the current calendar quarter and the current calendar year at least once per 31 days. (see Section 12.3 of ZionSolutions' RETS and/or Technical Specifications). For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10. A.2.2 Liquid Effluent Concentrations Requirement Requirement One method of demonstrating compliance to the requirements of 10CFR20.1301 is to demonstrate that the annual average concentrations of radioactive material released in gaseous and liquid effluents do not exceed the values specified in 10CFR20 Appendix B, Table 2, Column 2. (See 10CFR 20.1302(b)(2).) However, as noted in Section A.5.1, this mode of 10CFR20.1301 compliance has not been elected. As a means of assuring that annual concentration limits will not be exceeded, and as a matter of policy assuring that doses by the liquid pathway will be ALARA; RETS provides the following restriction: "The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentration values in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402." This also meets the requirement of Station Technical Specifications and RETS. Page 117 of 267
Revision 5 Aug 31, 2015 Equation According to the footnotes to 10CFR20 Appendix B, Table 2, Column 2, if a radionuclide mix of known composition is released, the concentrations must be such that L( C; )<1 10ECL; - (A-21) where the summation is over radionuclide i. C; Radioactivity Concentration in [µCi/ml] Liquid Effluents to the Unrestricted Area Concentration of radionuclide i in liquid released to the unrestricted area. ECL; Effluent Concentration Limit in Liquid [µCi/ml] Effluents Released to the Unrestricted Area The allowable annual average concentration of radionuclide i in liquid effluents released to the unrestricted area. This concentration is specified in 10CFR20 Appendix B, Table 2; Column 2. Concentrations for noble gases are different and are specified in the stations' Technical Specifications/RETS. 10 Multiplier to meet the requirements of Technical Specifications. If either the identity or concentration of any radionuclide in the mixture is not known, special rules apply. These are given in the footnotes in 10CFR20 Appendix B, Table 2, Column 2. Application The RETS and Technical Specifications require a specified sampling and analysis program to assure that liquid radioactivity concentrations at the point of release are maintained within the required limits. To comply with this provision, ZionSo/(Jfions' obtains and analyzes samples in accordance with the radioactive liquid waste (or effluent) sampling and analysis program in its RETS. Radioactivity concentrations in tank effluents are determined in accordance with Equation A-22 in the next section. Comparison with the Effluent Concentration Limit is made using Equation A-21. A.2.3 Tank Discharges When radioactivity is released to the unrestricted area with liquid discharge from a tank (e.g., a radwaste discharge tank), the concentration of a radionuclide in the effluent is calculated as follows: Waste Flow C; = C~ Dilution Flow (A-22) Concentration in Liquid effluent to the unrestricted area. [µCi/ml] Concentration of radionuclide i in liquid released to the unrestricted area. Concentration in the Discharge Tank [µCi/ml] Measured concentration of radionuclide i in the discharge tank. All other terms have been previously defined. Page 118 of 267
Revision 5 Aug 31, 2015 A.2.4 Tank Overflow Requirement To limit the consequences of tank overflow, the quantity of radioactivity that may be stored in unprotected outdoor tanks is limited. Unprotected tanks are tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. The specific objective is to provide assurance that in the event of an uncontrolled release of a tank's contents, the resulting radioactivity concentrations beyond the unrestricted area boundary, at the nearest potable water supply and at the nearest surface water supply, will be less than the limits of 10CFR20 Appendix B, Table 2, Column 2. Application Table F-1 of Appendix F provides information on the limits for Zion Station. A.2.5 Operability and Use of the Liquid Radwaste Treatment System Requirement The design objectives of 10CFR50, Appendix I and RETS/Technical Specifications require that the liquid radwaste treatment system be operable and that appropriate portions be used to reduce releases of radioactivity when projected doses due to the liquid effluent from each reactor unit to restricted area boundaries exceed either of the following (see Section 12.3 of Zion Solutions' RETS or Technical Specifications);
- 0.06 mrem to the total body in a 31 day period.
- 0.2 mrem to any organ in a 31 day period.
Equation Offsite doses due to projected releases of radioactive materials in liquid effluents are calculated using Equation A-17. Projected radionuclide release concentrations are used in place of measured concentrations, Ci. A.2.6 Drinking Water Zion Solutions' has requirements for calculation of drinking water dose that are related to 40CFR 141, the Environmental Protection Agency National Primary Drinking Water Regulations. These are discussed in Section A.6. A.2.7 Non-routine Liquid Release Pathways Cases in which normally non-radioactive liquid streams (such as the Service Water) are found to contain radioactive material are non-routine will be treated on a case specific basis if and when this occurs. Since Zion Station has sufficient capacity to delay a liquid release for reasonable periods of time, it is expected that planned releases will not take place under these circumstances. Therefore, the liquid release setpoint calculations need not and do not contain provisions for treating multiple simultaneous release pathways. A.3 DOSE DUE TO CONTAINED SOURCES There are multiple types of contained sourc~s of radioactivity which contribute to ZionSo/utions' offsite radiological dose assessments. When the ISFSI if fully loaded it will contain 61 Vertical Concrete Casks (VCCs) containing Spent Nuclear Fuel and 4 VCCs containing Greater Than Class C (GTCC) Waste. The GTCC waste is composed primarily of reactor internals segments from both Unit 1 and Unit 2. There is a waste staging area in the Southern region of the Radiological Restricted Area for 8-120 liners containing Waste Class A, B and C. Page 119 of 267
Revision 5 Aug 31, 2015 This waste is composed primarily of reactor internals segments from both Unit 1 and 2. These 8-120s are stored inside of concrete Rad Vaults then surrounded by several feet of soil above ground level. At various times throughout D&D, there will be various rail cars, lntermodals, Sealands, and various other waste containers staged onsite prior to shipment to a disposal facility. All of these various sources contribute to offsite dose from both directly emitted radiations and radiations due to skyshine from directly emitted radiations. A.3.1 Dose from Onsite Radioactive Waste Storage Low-level radioactive waste may be stored at Zion in the following types of containers and storage areas:
- Concrete vaults
- Butler buildings/warehouses
- Shipping containers while awaiting shipment
- Independent Spent Fuel Storage Installation (ISFSI) Facilities The dose rates resulting from these containers and storage areas will be monitored frequently as they are being utilized, and if necessary, a dose calculation performed to assess projected dose rates from such containers and storage areas. Dose calculations shall be documented in site specific Technical Support Documents and referenced in the ODCM.
A.4 Total Dose Limits (10CFR20, 10CFR72 and 40CFR190) The regulatory requirements of 10CFR20, 10CFR72 and 40CFR190 each limit total dose to individual members of the public without regard to specific pathways. The only significant exposure pathways for light water reactors included in 10CFR20, 10CFR72 and 40CFR190 not addressed by 10CFR50 Appendix I are the direct radiation pathway and exposure from on-site activity by members of the public. Sections A.1 and A.2 considered organ doses from the gaseous and liquid effluent streams for purposes of compliance with 10CFR50 Appendix I. Section A.3 addresses the direct radiation component that must be considered for 10CFR20, 10CFR72 and 40CFR190 compliance. The following sections will describe the methodology of assessing direct radiation dose and then the manner in which the various doses are combined to obtain the appropriate "total" for regulatory compliance purposes. Althbugh annual dose limits in 10CFR20 are now expressed in terms of Total Effective Dose Equivalent (TEDE) 40CFR190 limits are still stated as organ dose. The NRC continues to require 10CFR50 Appendix I, 10CFR72 and 40CFR190 doses to be reported in terms of organ dose. Due to the fact that organ dose limits set forth in 40CFR190 are substantially lower than those of 10CFR20 (25 mrem/yr vs 100 mrem/yr), the NRC has stated that demonstration of compliance with the dose limits in 40CFR190 will be deemed as demonstration of compliance with the dose limits of 10CFR20 for most facilities (Reference 104). In addition to compliance with 40CFR190 it may be necessary for a nuclear power plant to address dose from on-site activity by members of the public. A.4.1 External Total Body Dose The external total body dose is comprised of the following parts:
- 1) Total body dose due to noble gas radionuclides in gaseous effluents (Section A.1.2),
- 2) Dose due to radioactive waste and the ISFSI (Section A.3.1) and
- 3) Total body dose due to radioactivity deposited on the ground (Section A.1 .4.1 ).
The external total body dose due to radioactivity deposited on the ground is accounted for in the determination of the non-noble gas dose (See Equations A-7 and A-8) and is not considered here. Page 120 of 267
Revision 5 Aug 31, 2015 The total external total body dose, DEx, is given by: oEx= 0 Ts + 0 osF (A-23) Total External Total Body Dose [mrem] Total external~total body dose due to irradiation by external so1.irces at the location of interest. Noble Gas Total Body Dose [mrem] External total body dose due to gamma radiation from noble gas radionuclides released in gaseous effluents at the location of interest. See Equation A-3. Dose From On-Site Storage Facilities [mrem] External total body dose due to gamma radiation from on-site storage facilities at the location of interest. See Section A.3.1 . A.4.2 Total Dose The total dose, DTot, in the unrestricted area to a member of the public due to plant operations is given by: (A-24) where: 0Tot Total Dose To Member of Public [mrem] Total off-site dose to a member of public due to plant operations. Total External Total Body Dose [mrem] Total body dose due to external exposure to noble gases and on-site radioactive waste storage. Liquid Effluent Dose [mrem] Dose due to liquid effluents to age group a and organ j. The age group and organ with the highest dose from liquid effluents is used. Non-Noble Gaseous Effluent Dose [mrem] Dose due to non-noble gaseous effluents to age group a and organ j. The age group and organ with the highest dose from non-noble gas effluents is used. Page 121 of 267
Revision 5 Aug 31, 2015 A.5 COMPLIANCE TO TOTAL DOSE LIMITS A.5.1 Total Effective Dose Equivalent Limit -10CFR20 Compliance Requirement ZionSo/utions' RETS limits the Total Effective Dose Equivalent {TEDE) to an annual limit of 100 mrem, as required by 10CFR20.1301 (a)(1 ). Demonstration of compliance with the limits of 40CFR190 (per Section 4.5.2) will be considered to demonstrate compliance with the 100 mrem/year limit. A.5.1.1 Dose to a Member of the Public in the Unrestricted Area The NRC has stated that demonstration of compliance with the limits of 40CFR190 or with the design objectives of Appendix I to 10CFR50 will be deemed to demonstrate compliance with the limits of 10CFR20.1301{a}{1 ). Power reactors that comply with 10CFR50 Appendix I may also have to demonstrate that they are within the 25 mrem limit of 40CFR190 (See Reference 104). Zion Station ISFSI pad operations are required to demonstrate compliance with 10CFR72.104 limits. A.5.1.2. Dose to a Member of the Public in the Restricted Area In August of 1995, a revision to 10CFR20 was implemented that changed the definition of a member of the public. NUREG/CR-5569, "Health Physics Positions Database" Question 26(a) clarifies dose to a member of the public while inside the Restricted Area. "By definition, and with the exceptions given in the definitions of "occupational dose", any dose received by any individual in a "restricted area" is an "occupational dose." No one in a restricted area is a "member of the public."" Non-trained radiation workers are administratively restricted to less than 160 total hours on site property per year. Application Evaluation of the 40CFR190 dose is used to demonstrate compliance to 10CFR20, 10CFR72 and satisfy station RETS and Technical Specifications (see Chapter 12). A.5.2 Total Dose due to the Uranium Fuel Cycle (40CFR190) Requirement RETS, 40CFR190 and 10CFR72.104 limit the annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources to the following:
- Less than or equal to 25 mrem to the total body.
- Less than or equal to 25 mrem to any organ except the thyroid.
- Less than or equal to 75 mrem to the thyroid.
Total Dose Components This requirement includes the total dose from operations at the nuclear power station. This includes doses due to radioactive effluents (airborne and liquid) and dose due to direct radiation from non-effluent sources (e.g., sources contained in systems on site such as the ISFSI). The operations comprising the uranium fuel cycle are specified in 40CFR190.02(b). The following are included to the extent that they directly support the production of electrical power for public use utilizing nuclear energy:
- Milling of uranium ore.
- Chemical conversion of uranium.
Page 122 of 267
Revision 5 Aug 31, 2015
- Isotopic enrichment of uranium.
- Fabrication of uranium fuel.
- Generation of electricity by a light-watered-cooled nuclear power plant using uranium fuel.
- Reprocessing of spent uranium fuel.
Excluded are:
- Mining operations.
- Operations at waste disposal sites.
- Transportation of any radioactive material in support of these operations.
- The re-use of recovered non-uranium special nuclear and by-product materials from the cycle.
The different methods of Decommissioning, SAFSTOR, ENTOMB and DEGON, are not mentioned in 40CFR190. Zion was previously a light-water-cooled nuclear power plant that used uranium fuel to generate electricity, therefore, 40CFR190 is applied to the different methods of Decommissioning at Zion. When Compliance Assessment is Required Compliance with the 40CFR190 regulations is now required as part of demonstration of compliance to 10CFR20 regulations per 10CFR20.1301(d), and 10CFR72 regulations per 10CFR72.104. Equation The dose due to the uranium fuel cycle is determined by equation A-24. A.5.3 Summary of Compliance Methodology The required compliance is given in Tables 2-1, 2-2 and 2-3. In Table 2-1, the dose components are itemized and referenced, and an indication of their regulatory application is noted. A more detailed compliance matrix is given in Table 2-3. The locations of dose receivers for each dose component are given in Table 2-2. Further, Table 2-2 states the location of the receiver and occupancy factors, if applicable. In general, the receiver spends time in locations that result in maximum direct dose exposure and inhales and ingests radioactivity from sites that yield maximum pathway doses. Thus, the dose calculated is a very conservative one compared to the "average" receiver who does not go out of his way to maximize radioactivity uptakes. Occupancy as a habit of a "real individual" is applied to doses received from contained sources. Finally, the connection between regulations, the ODCM equations and the station RETS and Technical Specifications is given in Table 12-0. ISFSI 10CFR72.104 dose limits are the same as those specified by 40CFR190. ISFSI dose contribution is in the form of direct radiation as no liquid or gas releases are expected to occur. The report prepared in accordance with 10CFR72.212 requirements assumes a certain array of vertical concrete casks exists on the ISFSI. The dose contribution from this array of casks was analyzed to be within the 40CFR190 and 10CFR72.104 limits, and is documented in NAC International Calculation 630073-5501 ZION Site Boundary Skyshine Evaluation, Zion Technical Support Document TSD 13-008 "Evaluation of Independent Spent Fuel Storage Installation and Associated processes Dose Rates" and TSD 13-009 "Member of the Public Dose From All Onsite Sources". If the dose limits of 40CFR190 or 10CFR72.104 are exceeded, a special report to the NRC as well as an appropriate request for exemption/variance is required to be submitted to the NRC. Page 123 of 267
Revision 5 Aug 31, 2015 The requirement that the dose limits of 10CFR72.104 apply to any "real individual" is controlled for ISFSI activities in the ISFSI 72.212 report. Therefore, for the purposes of analyzing dose from the ISFSI, the member of the public as defined in 40CFR 190 is the same as the "real individual" identified in the ES&H TSD 13-008 "Evaluation of Independent Spent Fuel Storage Installation and Associated processes Dose Rates" and TSD 13-009 "Member of the Public Dose From All Onsite Sources". A.6 DOSE DUE TO DRINKING WATER (40CFR141) The National Primary Drinking Water Regulations, 40CFR141, contain the requirements of the Environmental Protection Agency applicable to public water systems. Included are limits on radioactivity concentration. Although these regulations are directed at the owners and operators of public water systems, Zion Station has requirements in their Technical Specifications related to 40CFR141. A.6.1 40CFR141 Restrictions on Manmade Radionuclides Section 141.16 states the following (not verbatim): (a) The average annual concentration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annual dose equivalent to the total body or any internal organ greater than 4 millirem/year. (b) Except for the radionuclides listed in Table A-0, the concentration of man-made radionuclides causing 4 mrem total body or organ dose equivalents shall be calculated on the basis of drinking 2 liter of water per day. (Using the 168 hour data listed in "Maximum Permissible Body Burdens and Maximum Permissible Concentration of Radionuclides in Air or Water for Occupational Exposure, "NBSHandbook 69 as amended August 1963, U.S. Department of Commerce.). If two or more radionuclides are present, the sum of their annual dose equivalents to the total body or any organ shall not exceed 4 millirem/year. Page 124 of 267
Revision 5 Aug 31, 2015 TABLEA-0 AVERAGE ANNUAL CONCENTRATIONS ASSUMED TO PRODUCE A TOTAL BODY OR ORGAN DOSE OF 4 MREM/YR Radionuclide Critical Oraan oCi/Liter Tritium Total Bodv 20,000 Strontium-90 Bone Marrow 8 A.6.2 Application The projection or calculation of dose due to the drinking water pathway is made using Equations A-17 and A-19. Projections are made using projected radionuclide releases in place of measured releases Ai. Doses calculated using Equations A-17 and A-19 may differ from doses determined by the methodology prescribed in 40CFR141.16. When required, Zion Station prepares a special report on radiological impact at the nearest community water system. This system is taken as the one listed in Table A-3 of this appendix. The report should include the following:
- The doses calculated by Equations A-17 and A-19.
- A statement identifying the dose calculation methodology (e.g., a reference to this manual).
- A statement that the doses calculated by the ODCM methodology are not necessarily the same as doses calculated by the methodology prescribed in 40CFR141.16.
- The data used to calculate the doses. This information includes the amounts of radioactivity released and the flow rate and dilution values used (see Table F-1). This information is provided to assist the operator of the community water system in performing its own dose assessment.
Page 1*25 of 267
Revision 5 Aug 31, 2015 Table A-1 COMPLIANCE MATRIX Regulation Dose to be compared to limit 10CFR50
- Gamma air dose and beta air dose due to airborne radioactivity in effluent Appendix I plume.
- Total body and skin dose due to airborne radioactivity in effluent plume are reported only if certain gamma and beta air dose criteria are exceeded.
- Dose for all organs and all four age groups due to particulate in effluent plume. Existing pathways are considered.
- Dose for all organs and all four age groups due to radioactivity in liquid effluents.
10CFR20
- Adherence determined by compliance with dose limits of 40CFR190 .
40CFR190
- Total body dose due to direct radiation, ground and plume exposure from all sources at a station.
- Organ doses to an adult due to all pathways .
RETS/ODCM * "Instantaneous" noble gas total body and skin dose rates and tritium and particulate inhalation dose rates to a child due to radioactivity in airborne effluents.
* "Instantaneous" concentration limits for liquid effluents .
10CFR72.104(a)
- During normal operations and anticipated occurrences .
Page 126 of 267
Revision 5 Aug 31, 2015 TableA-2 Release Point Classifications Release Release Point Station Point Classificationa Zion 1 & 2 Vent Stacks Ground Level aThe definitions of release point classifications (stack, vent and ground level) are given in Section 4.1.4. TableA-3 Nearest Downstream Community Water Systems Characteristics of Nearest Affected Downstream Community Water Supply Location and Station Distancea Zion Lake County Intake, 1.4 miles a Appendix 0 Table 0-2 provides the basis of the location and distance data. Page 127 of 267
Revision 5 Aug 31, 2015 TableA-4 40CFR190, 10CFR72.104(a) Compliance 40CFR190 Dose Annual Limit ODCM Dose and Equation Number (mrem) 10CFR72.104(a) Dose Total Body 25 Total Body Dose; A-24 evaluated for total body Thyroid 75 Thyroid Dose; A-24 evaluated for thyroid Other Organs 25 Organ Dose; A-24 evaluated for all organs except thyroid Notes:
- 1. The evaluation is made considering the following sources:
- a. Radioactivity in contained sources within the station;
- b. Radioactivity in station gaseous and liquid effluents; Page 128 of 267
Revision 5 Aug 31, 2015 APPENDIX B MODELS AND PARAMETERS FOR AIRBORNE AND LIQUID EFFLUENT CALCULATIONS Page 129 of 267
Revision 5 Aug 31, 2015 APPENDIX B MODELS AND PARAMETERS FOR AIRBORNE EFFLUENT CALCULATIONS B.O INTRODUCTION The equations used for calculation of doses due to radioactive airborne effluents are given in Section A.1 of Appendix A. The equations involve the following types of parameters:
- Meteorological Parameters These include xJQ, gamma-x/Q, D/Q and wind speed. Their values are based on historical average atmospheric conditions at a site for a selected multi-year historical period (see Section 4.1 .5).
- Dose Factors These parameters are used to provide a simple way to calculate doses and dose rates due to gamma and beta radiation. These parameters are independent of meteorological conditions and therefore generic (i.e., not station-specific).
- Measured Release Parameters These are measured values of radioactivity releases and release rates.
- Radiological Decay Constants These are used to account for the radioactive decay between the release of radioactivity to the environment and the exposure of persons to it.
- Production/Exposure Parameters These are parameters characterizing agricultural production (e.g., length of growing season, transport times) and human exposure patterns (e.g., exposure period, breathing rate, food consumption rates). These parameters affect the quantities of radioactivity to which persons may be exposed.
This appendix discusses the methodology used to determine values of these parameters. Section 8.1 addresses how the historical meteorology of a site is characterized by use of a function called the joint frequency distribution. Section 8.1 and Sections 8.3 through 8.5 present equations that use the joint frequency distribution to obtain values for site-specific meteorological parameters. These equations involve a mathematical model of a plume known as the Gaussian plume model. This model is developed in Section 8.2. Various generic dose factors are discussed in Sections 8.6 through B.10. The other parameters are discussed in the remaining sections. B.1 METEOROLOGICAL DATAAND PARAMETERS Predicting where airborne effluent will travel requires information on the following:
- Wind speed
- Wind direction
- Atmospheric turbulence The greater the atmospheric turbulence, the more an effluent plume will tend to broaden and the more dilute the concentration will be. Atmospheric turbulence is affected by the general condition of the atmosphere (e.g., the vertical temperature distribution) and by local features (e.g., objects that protrude into the wind stream). A commonly used classification scheme for the degree of atmospheric turbulence associated with the general condition of the atmosphere involves seven stability classes:
A Extremely Unstable 8 Moderately Unstable C Slightly Unstable D Neutral E Slightly Stable Page 130 of 267
Revision 5 Aug 31, 2015 F Moderately Stable G Extremely Stable This classification scheme is based on Reference 5, Table 1. Each class is associated with a particular range of wind direction fluctuations and of vertical temperature gradients in the atmosphere. These are specified in Table C-4 of Appendix C. 8.1.1 Data Historical atmospheric conditions at Zion Station were recorded by an instrumented meteorological tower that measured wind speed, wind direction, and temperature at various heights. Hourly average values of wind speed, wind direction, and stability class were determined. The difference in temperature between two heights was used to assign an atmospheric stability class based on the correlation between temperature gradient and stability class in Table C-4 of Appendix C. In obtaining the data, quality assurance checks and corrections were made. Also, corrections were applied to compensate for the limitations of wind sensors at low speeds. A calm was said to exist if the wind speed was less than that of the threshold of either the anemometer (wind speed meter) or the wind direction vane. For calm conditions, a wind speed equal to one-half of the higher threshold was assigned. For each stability class, the wind directions during calm conditions were assumed to be distributed in proportion to the observed wind direction distribution of the lowest non-calm wind speed class. 8.1.2 Joint Frequency Distribution The data for a particular historical period are summarized by developing a joint frequency distribution (JFD). Each such distribution specifies the fraction of time during the historical period that the following jointly occur: *
- Wind speed within a particular range (wind speed class).
- Downwind direction in one of the 16 sectors corresponding to the 16 principal compass directions (N, NNE, etc.).
- Atmospheric conditions corresponding to one of the seven atmospheric stability classes discussed in Section B.1. Table B-1 of this appendix displays a portion of an example JFD.
Different JFDs are associated with the different release classifications defined in Section 4.1.4. One JFD is defined for stack releases, and another JFD is defined for ground level releases. Two JFDs are associated with vent (mixed mode) releases, one for the portion of the time the release is treated as elevated and the other for the portion of the time the release is treated as ground level. 8.1.2.1 Downwind Direction Versus Upwind Direction Unless otherwise noted, any reference to wind direction in this document represents downwind direction, i.e., the direction in which the wind is blowing toward. _This is because the parameters developed in this document are used to calculate radioactivity concentration and radiation dose downwind of a release point. In contrast, it is conventional for meteorologists to provide JFDs based on upwind direction, the direction from which the wind is blowing. For example, the JFDs presented in the annual operating report of Zion Station are obtained from a meteorological contractor and the directions specified in the reports are upwind directions. Users of JFDs should always be careful to ascertain whether the directions specified are upwind or downwind. 8.1.2.2 Stack JFD For a stack release, the JFD is defined as follows: Page 131 of 267
Revision 5 Aug 31, 2015 l:f5 (n,0,c) Joint Frequency Distribution, Stack Release The fraction of hours during a period of observation that all of the following hold:
- The average wind speed is within wind speed class n.
- The downwind direction is within the sector denoted by 0.
- The atmospheric stability class is c.
This function is defined for application to a stack release point (see Section 4.1.4 ). Its value is based on hourly average wind data obtained at a height representative of the release point height. The stack JFD is normalized to 1: l: f 5 (n,0,c) =1 (B-25) The summation is over all wind speed classes n, all compass direction sectors 0, and all stability classes c. B.1.2.3 Ground Level JFD For a ground level release, the JFD fg(n, 0,c) is defined in the same way as for a stack release except that the wind data are obtained at a height representative of a ground level release point. This height is taken as about 10 meters. The ground level JFD is normalized to 1: l: t 9 (n,0,c) =1 (B-26) The summation is over all wind speed classes n, all compass direction sectors, and all stability classes c. B.1.2.4 VentJFDs In accordance with the approach recommended in Regulatory Guide 1.111 (Reference 7), the plume from a vent release is treated as elevated part of the time and as ground level the rest of the time. Two JFDs are determined:
- fv,elev(n,0,c) characterizes the plume during the part of the time that it is considered elevated;
- fv,gnd(n,0,c) characterizes the plume during the part of the time that it is considered ground level.
Their definitions are as follows: fv,elev(n,0,c) Joint Frequency Distribution, Elevated Portion of a Vent Release The fraction of hours during a period of observation that the plume is considered elevated and that all of the following hold:
- The average wind speed is within wind speed class n.
- The downwind direction is within the sector denoted by 0.
- The atmospheric stability class is c.
fv,gnd(n,0,c) Joint Frequency Distribution, Page 132 of 267
Revision 5 Aug 31, 2015 Ground Level Portion of a Vent Release The fraction of hours during a period of observation that the plume is considered ground level and that all of the following hold:
- The average wind speed is within wind speed class n.
- The downwind direction is within the sector denoted by 0.
- The atmospheric stability class is c.
The value of fv,elev(n, 0,c) is based on hourly average wind data at a height representative of the vent release point. Where the measurement height differed considerably from the release height, wind speed data for the release height was obtained by extrapolation. The value of fv,gnd(n, 0,c) is based on hourly average wind data obtained at a height representative of a ground level release point. This is taken as about 10 meters. The sum of these two JFDs is normalized to 1:
- t{ fv,elev(n, 0,c) + fv,gnd(n, 0,c) } =1 (B-27)
The summation is over all wind speed classes n, all compass direction sectors 0, and all stability classes c. The prescription of Regulatory Guide 1.111 is used in determining the fraction of time that the plume is considered elevated and the fraction of time that it is considered ground level. The fractions are obtained from the ratio of stack exit velocity W 0 to hourly average wind speed u at the height of the vent release point as follows:
*If W 0 /u > 5, then the plume is considered elevated for the hour.
*If W 0 /u ~ 1, then the plume is considered ground level for the hour.
*If 1 < W 0 /u ~ 5, the plume is considered to be a ground level release for a fraction Gt of the hour and an elevated release for a fraction (1 - Gt) of the hour where Gt is defined as follows:
Gt= 2.58 -1.58(W0 /u) for 1.0 < W 0 /u ~ 1.5 (B-28) Gt= 0.30 - 0.06(W0 /u) for 1.5 < W 0 /u ~ 5.0 (B-29) B.1.3 Average Wind Speed Using the joint frequency distribution, average wind speeds are obtained for Zion Station. Values are obtained for each downwind direction (N, NNE, etc.) and for various release point classifications (stack, vent, and ground level). B.1.3.1 Stack Release For a stack release, the following formula is used: u5 (0) = :t{ f5 (n; 0,c)un }/ :t{ f5 (n, 0,c)} (B-30) where th.e summations are over wind speed classes n and stability classes c. u5 (0) Average Wind Speed, Stack Release [m/sec] Page 133 of 267
Revision 5 Aug 31, 2015 The average wind speed in downwind direction 0 for a stack release. Un Wind Speed for Class n [m/sec] A wind speed representative of wind speed class n. For each wind speed class except the highest, Un is the average of the upper and lower limits of the wind speed range for the class. For the highest wind speed class, Un is the lower limit of the wind speed range for the class. The parameter fs is defined in Section 8.1.2.2. B.1.3.2 Ground Level Release For a ground level release, the following formula is used: ug(0) =~{ fg(n, 0,c)un }/ ~{ fg(n, 0,c)} (B-31) where the summations are over wind speed classes n and stability classes c. ug(0) Average Wind Speed, Ground Level Release [m/sec] The average wind speed in downwind direction 0 for a ground level release. The parameter fg is defined in Section 8.1.2.3. B.1.3.3 Vent Release For a vent release, the following formula is used: uy(0) =~ {[fv,elev(n, 0,c) + fv,gnd(n, 0,c)]un } (B-32) I~{ fv,elev(n,0,c) + fv,gnd(n,0,c) } where the summations are over wind speed classes n and stability classes c. uy(0) Average Wind Speed, Vent [m/sec] Release The average wind speed in downwind direction 0 for a vent release. The parameters fv,elev and fv,gnd are defined in Section 8.1.2.4. B.2 GAUSSIAN PLUME MODELS As a plume of airborne effluents moves away from an elevated release point, the plume both broadens and meanders. It has been found that the time-averaged distribution of material in an effluent plume can be well represented mathematically by a Gaussian function. Page 134 of 267
Revision 5 Aug 31, 2015 8.2.1 Mathematical Representation In a widely used form of the Gaussian plume model, the distribution of radioactivity in a plume is represented mathematically by the equation below: X(X,y,z) =[Q/(21t cry O'zU)]exp(-y2/2cr2y) X {exp[-(z-he)2/2cr2z] + exp[-(z+he)2/2cr2z]} (B-33) x(x,y,z) Radioactivity Concentration [µCi/m 3] The concentration of radioactivity at point (x,y,z). The x, y, and z axis are defined as follows: x Downwind Distance [m] Distance from the stack along an axis parallel to the wind direction. y Crosswind Distance [m] Distance from the plume centerline along an axis parallel to the crosswind direction. z Vertical Distance [m] Distance from the ground (grade level at the stack) along an axis parallel to the vertical direction. Q Release Rate [µCi/sec] Release rate of radioactivity. cry, crz Horizontal and Vertical Dispersion Coefficients [m] Standard deviations of the Gaussian distributions describing the plume cross-sections in they and z directions, respectively. The values of cry and crz depend on several parameters:
- Downwind distance x.
Because a plume broadens and meanders as it travels away from its release point, the values of cry and crz increase as x increases.
- Atmospheric stability class.
The plume is broadest for extremely unstable atmospheric conditions (Class A) and narrowest for extremely stable conditions (Class G).
- Time period of averaging plume concentration.
The values of cry and crz increase as the averaging period increases. u Average Wind Speed [m/sec] The average wind speed. The average speed of travel of the plume in the x direction. Page 135 of 267
Revision 5 Aug 31, 2015 he Effective Release Height [m] The effective height of effluent release above grade elevation. This may be greater than the actual release height (see Section B.3.1.1.1 ). The two exponential functions of z in the curly brackets of Equation B-9 represent the emitted and reflected components of the plume. The reflected component (represented by the exponential with (z + he) in its argument) arises from the assumption that all material in a portion of the plume that touches ground is reflected upward. This assumption is conservative if one is calculating airborne radioactivity concentration. 8.2.2 Sector-Averaged Concentration Sometimes, it is desired to determine the average concentration of radioactivity in a sector due to release at a constant rate over an extended period of time (e.g., a year). For such a case, it is reasonable to assume that the wind blows with equal likelihood toward all directions within the sector. From Equation B-9, the following equation for ground level radioactivity concentration can be derived: Xsector =[2.032 f Q/(o-z u x)]exp(-h2e/2o-2z) (B-34) XsectorSector-Averaged Ground Level [µCi/m3] Concentration The time-averaged concentration of airborne radioactivity in a sector at ground level at a distance x from the release point. 2.032 A dimensionless constant. f Sector Fraction The fraction of time that the wind blows into the sector. Q Release rate of radioactivity. [µCi/sec] The other parameter definitions are the same as for Equation B-9. Page 136 of 267
Revision 5 Aug 31, 2015 8.3 RELATIVE CONCENTRATION FACTOR xtQ The relative concentration factor xtQ (called "chi over Q") provides a simplified method of calculating the radioactivity concentration at a given point in an effluent plume when the release rate is known: x =Q <xtQ) (8-35) x Concentration of Radioactivity [µCi/m3] Concentration of radioactivity at point (x,y,z) in the atmosphere. Q Release Rate [µCi/sec] Release rate of radioactivity. xtQ Relative Concentration Factor Relative concentration factor for point (x,y,z). The airborne radioactivity concentration at (x,y,z) per unit release rate. Expressions for x!Q based on Gaussian plume models can be obtained from the equations for x concentration in Section B.2 simply by dividing both sides of each equation by the release rate Q. For example, from Equation B-10, we obtain the following expression for the sector-averaged x/Q: (XsectorfQ) =[2.032 f/(crz u x)]exp(-h2e/2a2z) (8-36) The values of x!Q used in ODCM calculations are both sector-averaged and time-averaged. The time averaging is based on the historical average atmospheric conditions of a specified multi-year time period (see Section 4.1.5) and is accomplished by use of the joint frequency distribution discussed in Section B.1.2. The formulas used to obtain the time- and sector-averaged xtQ are based on Equation B-12, but vary depending on whether the release is a stack, ground level, or vent release. The three cases are discussed below. 8.3.1 Stack Release For a stack release, the relative concentration factor is designated (x/Q)5 . Its value is obtained by the following formula: (x/Q)5 =(2.032/R) l:{ f 5 (n,0,c) x [exp (-h2e/2a2z)]/(un crz)} (8-37) The summation is over wind speed classes n and atmospheric stability classes c. (x/Q) 5 Relative Concentration Factor, Stack Release The time- and sector-averaged relative concentration factor due to a stack release for a point at ground level at distance R in downwind direction e. Page 137 of 267
Revision5 Aug 31, 2015 2.032 Constant A dimensionless constant. R Downwind Distance [m] The downwind distance from the release point to the point of interest. f 5 (n,0,c) Joint Frequency Distribution, Stack Release This function is defined in Section B.1.2.2. he Effective Release Height [m] The effective height of an effluent release above grade elevation. For a stack release, he is obtained by correcting the actual height of the release point for plume rise, terrain effects, and downwash as described in Section B.3.1.1, below. O"z Standard Vertical Dispersion Coefficient [m] A coefficient characterizing vertical plume spread in the Gaussian model for stability class cat distance R (see Table C-5 of Appendix C). Un Wind Speed [m/sec] A wind speed representative of wind speed class n. For each wind speed class except the highest, un is the average of the upper and lower limits of the wind
. speed range for the class. For the highest wind speed class, Un is the lower limit of the wind speed range for the class.
This expression is recommended by the NRC in Regulatory Guide 1.111 (Reference 7) and is based on a model designated there as the "constantmean wind direction model." In this model it is assumed that the mean wind speed, the mean wind direction, and the atmospheric stability class determined at the release point also apply at all points within the region in which airborne concentration is being evaluated. B.3.1.1 Effective Release Height For a stack release, the effective height of an effluent plume is the height of the release point corrected for plume rise and terrain effects: If (hs + hpr- ht)< 100 meters, then
- he =hs + hpr - ht (B-38)
If (hs + hpr - ht)~ 100 meters, then; he =100 meters (B-39) he Effective Release Height [m] The effective height of an effluent release above grade elevation. hs Actual Release Height [m] The actual height of the release above grade elevation. Page 138 of 267
Revision 5 Aug 31, 2015 Plume Rise [m] The rise of the plume due to its momentum and buoyancy. (See Section B.3.1.1.1.) ht Terrain Correction Parameter [m] A parameter to account for the effect of terrain elevation on the effective height of a plume. Taken as zero (see Section B.3.1.1.2}. B.3.1.1.1 Plume Rise Because nuclear power stations generally have plumes that are not significantly warmer than room temperature, plume rise due to buoyancy is neglected. The formulas used to calculate plume rise due to momentum are given below. Stability Classes A, B, C, and D For these stability classes (corresponding to unstable and neutral conditions), hpr is taken as the lesser of two quantities: hpr =Minimum of [(hpr)1. (hpr)2] (B-40) (hpr)1 =(1.44)(W0 /u)2/3(Rfd)1/3(d) - hd (B-41) (hpr)2 =(3)(W 0 /u)(d) (B-42) W0 Stack Exit Velocity [m/sec] The effluent stream velocity at the discharge point. uWind Speed [m/sec] R Downwind Distance [m] The downwind distance from the release point to the point of interest. d Internal Stack Diameter [m] The internal diameter of the stack from which the effluent is released. Downwash. Correction [m] A parameter to account for downwash at low exit velocities. The parameter hd is calculated by the following equations: hd =(3)(1.5 - W 0 /u)(d) if W 0 <1.5u (B-43) hd =Oif W0==.1.~u (B-44) Note that (hprh can increase without limit as R increases; thus, the effect of (hpr)2 is to limit calculated plume rise at large distances from the nuclear power station. Stability Classes E, F, and G Page 139 of 267
Revision 5 Aug 31,2015 For these stability classes (corresponding to stable conditions), hpr is taken as the minimum of four quantities: (B-45) (hpr)a =(4)(F/S)1/4 (B-46) (hpr) 4 =(1.5)(F/u)1/3(st116 (8~47) F Momentum Flux Parameter [m4/sec2] A parameter defined as: F =W0 2(d/2)2 (B-48) S Stability Par~meter [1/sec2] A parameter defined as follows: Stability Class s E 8.?0E-4 F 1.75E-3 G 2.45E-3 The quantities (hpr)1 and (hpr)2 are as defined by Equations B-17 and B-18. B.3.1.1.2 Terrain Effects Due to general flatness of the terrain in the vicinity of the Zion site, the terrain correction parameter ht was taken as zero in all calculations of meteorological dispersion and dose parameters for this Manual. B.3.2 Ground Level Release For a ground level release, the relative concentration factor is designated (x/Q)9 . Its value is obtained by the following formula: (x/Q)g = (2.032/R) :E{ f g(n,0,c)/(unSz) } (B-49) The summation is over wind speed classes n and atmospheric stability classes c. (x/Q)g Relative Concentration Factor, Ground Level Release The time- and sector-averaged relative concentration factor due to a ground level release for a point at ground level at distance R in downwind direction 0. fg(n,0,c) Joint Frequency Distribution, Ground Level Release This function is defined in Section B.1.2.3. Page 140 of 267
Revision 5 Aug 31, 2015 Sz Wake-Corrected Vertical Dispersion Coefficient [m] The vertical dispersion coefficient corrected for building wake effects. The correction is made as described below. The remaining parameters are defined in Section 8.3.1. Wake-Corrected Vertical Dispersion Coefficient The wake-corrected vertical dispersion coefficient Sz in Equation 8-25 is taken as the lesser of two quantities: (B-50) (B-51)
=(o-z)(3112) (B-52)
Wake-Corrected Vertical Dispersion Coefficient [m] The vertical dispersion coefficient corrected for building wake effects. O"z Standard Vertical Dispersion Coefficient [m] The coefficient characterizing vertical plume spread in the Gaussian model for stability class cat distance R (see Table C-5 of Appendix C). D Maximum Height of Neighboring Structure [m] The maximum height of any neighboring structure causing building wake effects (see Table F-2 of Appendix F). B.3.3 Vent Release For a vent release, the relative concentration factor is designated (x/Q)v. Its value is obtained by the following formula: (x/Q)v =(2.032/R) I:{ f v,elev(n,9,c) (B-53) 2 2 x [exp(-h el2cr z}]l(un O"z)
+ fv,gnd(n,9,c)/(unSz) }
The summation is over wind speed classes n and atmospheric stability classes c. (x/Q)v Relative Concentration [sec/m3] Factor, Vent Release The time and sector averaged relative concentration factor due to a vent release for a point at ground level at distance R in downwind direction 9. The parameters fv,elev(n,9,c) and fv,gnd(n,9,c) are defined in Section 8.1.2.4. The parameter Sz is defined in Section 8.3.2. The remaining parameters are defined in Section 8.3.1. Page 141 of 267
Revision 5 Aug 31, 2015 B.3.4 Removal Mechanisms In Regulatory Guide 1.111, the NRC allows various removal mechanisms to be considered in evaluating the radiological impact of airborne effluents. These include radioactive decay, dry deposition, wet deposition, and deposition over water. For simplicity, these removal mechanisms cited by the NRC are not accounted for in the evaluation or use of x!Q in this manual. This represents a conservative approximation as ignoring removal mechanisms increases the value of x!Q. B.3.5 Gamma-x/Q The noble gas dose factors of Reg. Guide 1.109, Table B-1 are based upon assumption of immersion in a semi-infinite cloud. For ground level and mixed mode releases this tends to overestimate the gamma air dose arising from a plume that is actually finite in nature. For elevated releases, the Reg. Guide 1.109 noble gas dose factors will underestimate exposure as they consider only immersion and not that portion of exposure arising from sky shine. At distances close iri to the point of elevated release, the ground level concentration as predicted by x!Q will be essentially zero. In such a case, the sky shine component of the exposure becomes significant and must be considered. The gamma-x/Q provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. The methodology of Reg. Guide 1.109, Section C.2 and Appendix B provides the methodology for calculating finite cloud gamma air dose factors from which the gamma-x/Q values can be derived. Section B.5 addresses the calculation of these dose factors. The gamma-x/Q is defined such that for a given finite cloud the semi-infinite cloud methodology will yield the same gamma air dose as the finite cloud methodology. Three gamma-x/Q values are defined: (x/Q)/, (x/Q)} and (x/Q)9r for stack, vent and ground level releases, respectively. These gamma-x/Q values are calculated as follows: For stack releases: (B-54) The summation is over all noble gas radionuclides i. Gamma-y/Q for Stack Releases [sec/m3] Noble Gas Nuclide Fraction dimensionless Fraction of total noble gas release that is due to radionuclide i. Values for fi are listed in Table B-0. Si Stack Release Gamma Air Dose Factor [(mrad/yr)/(µCi/sec)] Gamma air dose factor for radionuclide i for stack releases as defined in Section B.5.1. Taken from Appendix F, Table 7. 3 Semi-Infinite Cloud Dose Factor [(m rad/yr)/(µCi/m )] Dose factor for immersion exposure to a semi-infinite cloud of noble gas. Taken from Reg. Guide 1.109, Table B-1, Col 4. (Note that the units in Reg. Guide 1.109 must be multiplied by 1 E6 to convert pCi to µCi.) Page 142 of 267
Revision 5 Aug 31, 2015 For vent releases: Lf;V; {x/Q)~ = :ti f.M. I I (B-55) The summation is over all noble gas radionuclides i. Gamma-y/Q for Vent Releases [sec/m3] Vent Release Gamma Air Dose Factor [( mrad/yr)/(µCi/sec )] Gamma air dose factor for radionuclide i for stack releases as defined in Section B.5.3. Taken from Appendix F, Table 7. All other terms have been previously defined. For ground level releases: (B-56) The summation is over all noble gas radionuclides i. Gamma-y/Q for Ground Releases [sec/m3] G; Ground Level Release Gamma Air Dose Factor [(mrad/yr)/(µCi/sec)] Gamma air dose factor for radionuclide i for ground level releases as defined in Section B.5.2. Taken from Appendix F, Table 7. All other terms have been previously defined. The Noble Gas Nuclide Fraction, f; is determined from historical release data and defined as: (B-57) The summation is over all noble gas radionuclides i. A; Cumulative Radionuclide Release units of activity Cumulative release of noble gas radionuclide i over a period 9f time. 8.4 RELATIVE DEPOSITION FACTOR D/Q The quantity D/Q (called "Dover Q") is defined to provide the following simple way of calculating the rate of deposition of radioactivity at a given point on the ground when the release rate is known. d =Q (D/Q) (B-58) Page 143 of 267
Revision 5 Aug 31, 2015 d Deposition Rate [(µCi/m2)/sec] Rate of deposition of radioactivity at a specified point on the ground. Q Release Rate of radioactivity. [µCi/sec] D/Q Relative Deposition Factor [1 /m2] Relative deposition factor for a specified point on the ground. The deposition rate per unit release rate. The values of D/Q used in this manual are time-averaged. The time averaging is based on the historical average atmospheric conditions of a specified multi-year time period (see Section 4.1.5) and is accomplished by use of the joint frequency distribution described in Section B.1.2. The formulas used to obtain D/Q vary depending on whether the release is a stack, ground level, or vent release. The three cases are discussed below. B.4.1 Stack Release For a stack release, the relative deposition factor is designated (D/Q)5 . Its value is obtained by the following formula: (D/Q)5 =[1/(21tR/16)] l:{f5 (n,0,c) Dr(c,R,he)} (B-59) The summation is over wind speed classes n and stability classes c. (D/Q)5 Relative Deposition Factor, Stack Release The time-averaged relative deposition factor due to a stack release for a point at distance R in the direction 0. 21t/16 Sector Width [radians] The width of a sector over which the plume direction is assumed to be uniformly distributed (as in the model of Section B.2.2). Taken as 1/16 of a circle. R Downwind Distance [m] The downwind distance from the release point to the point of interest. f 5 (n,0,c) Joint Frequency Distribution, Stack Release This function is defined in Section B.1.2.2. Relative Deposition Rate, Stack Release The deposition rate per unit downwind distance [µCi/(sec-m)] divided by the source strength [µCi/sec] due to a stack release for stability class c, downwind distance R, and effective release height he. The value is based on Figures 7 to 9 of Regulatory Guide 1.111, which apply, respectively, to release heights of 30, 60, and 100 m. Linear interpolation is used to obtain values at intermediate release heights. If the Page 144 of 267
Revision 5 Aug 31, 2015 effective release height is greater than 100 meters, then the data for 100 meters are used. he Effective Release Height [m] The effective height of the release above grade elevation. See Section .B.3.1.1. B.4.2 Ground Level Release For ground level release, the relative deposition factor is designated (D/Q) 9 . Its value is obtained by the following formula: (D/Q)9 =[1/(27tR/16)] Dr(R) l:{ f 9 (n,0,c)} (B-60) The summation is over wind speed classes n and stability classes c. (D/Q)g Relative Deposition Factor, Ground Level Release The time-averaged relative deposition factor due to a ground level release for a point at distance R in the direction 0. fg(n,0,c) Joint Frequency Distribution, Ground Level Release This function is defined in Section B.1.2.3. Dr(R) Relative Deposition Rate, Ground Level The deposition rate per unit downwind distance [µCi/(sec-m)] divided by the source strength [µCi/sec] due to a ground level release for downwind distance R. The value is taken from Figure 6 of Regulatory Guide 1.111 and is the same for all atmospheric stability classes. The remaining parameters are defined in Section B.4.1. B.4.3 Vent Release For a vent release, the relative deposition factor is designated (D/Q)v. Its value is obtained by the following formula: (D/Q)v =[1/(21tR/16)] x [:E{ fv,elev(n,0,c) Dr(c,R,he)} + Dr(R) l:{ fv,gnd(n,0,c) }] (B-61) The summation is over wind speed classes n and stability classes c. (D/Q)v Relative Deposition Factor, Vent Release The time-averaged relative deposition factor due to a ground level release for a point at distance R in the direction 0. The parameters fv,elev(n,0,c) and fv,gnd(n,0,c) are defined in Section B.1.2.4. The remaining parameters are defined in Sections B.4.1 and B.4.2. Page 145 of 267
Revision 5 Aug 31, 2015 B.5 GAMMA AIR DOSE FACTORS (Sj, Vi, Gj) The gamma air dose factors provide a simple way of calculating doses and dose rates to air due to gamma radiation. For example, using a dose factor DFj, gamma air dose rate may be calculated as follows: (B-62) (B-63) The summations are over i radionuclides. D Gamma Air Dose Rate [mrad/yr] The gamma air dose rate due to all radionuclides released. Di Gamma Air Dose Rate Due to Radionuclide i [mrad/yr] Qi Release Rate of Radionuclide i [µCi/sec] DFi Gamma Air Dose Factor for [(mrad/yr)/ (µCi/sec)] Radionuclide i A factor used to calculate gamma air dose or dose rate due to release of radionuclide i. Gamma air dose rate at a particular location per unit release rate. Three gamma air dose factors are defined: Sh Vh and Gi. They are used for stack, vent, and ground level releases, respectively. These three release point classifications are defined in Section 4.1.4. The calculation of the three dose factors is discussed below. B.5.1 Stack Release For a stack release, the gamma air dose factor Si is obtained by a model similar to that of Equation 6 of Regulatory Guide 1.109 (Reference 6). A sector-averaged Gaussian plume is assumed and the dose factor is evaluated on the basis of historical average atmospheric conditions. The value of Si depends on distance R from the release point and on downwind sector 0. The following equation is used: (B-64) The summation is over wind speed classes n, atmospheric stability classes c, and photon group indices k. Si Gamma Air Dose Factor, Stack Release [(mrad/yr)/ (µCi/sec)] The gamma air dose factor at ground level for a stack release for radionuclide i, downwind sector 0, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period. Page 146 of 267
Revision 5 Aug 31, 2015 260 Conversion factor [(mrad-radians-m3-disintegrations)/(sec-MeV-Ci)] Reconciles units of Equation B-36. 21t/16 Sector Width [radians] The width of a sector over which the plume direction is assumed to be uniformly distributed (as in the model of Section B.2.2). Taken as 1/16 of a circle. fs(n,0,c) Joint Frequency Distribution, Stack Release This function is defined in Section B.1.2.2. A.i Radiological Decay Constant [hr-1] Radiological Decay Constant for radionuclide i (see Table C-7 of Appendix C). 3600 Conversion Factor [sec/hr] The number of seconds per hour. Used to convert wind speed in meters/sec to meters/hr. Ek Photon Group Energy [MeV/photon] An energy representative of photon energy group k. The photons emitted by each radionuclide are grouped into energy groups in order to facilitate analysis. All photons with energy in energy group k are assumed to have energy Ek. µ3(Ek) Air Energy Absorption Coefficient The linear energy absorption coefficient for air for photon energy group k. The fraction of energy absorbed in air per unit of distance traveled for a beam of photons of energy Ek. Distance is measured in units of linear thickness (meters). Aki Effective Photon Yield [photons/disintegration] The effective number of photons emitted with energy in energy group k per decay of nuclide i. On the basis of Section B.1 of Regulatory Guide 1.109 (Reference 6), the parameter Aki is calculated as follows: (B-.65) The summation in the numerator is over the index m. True Photon Yield [photons per disintegration] The actual number of photons emitted with energy Em per decay of nuclide i. Em Photon Energy [MeV/photon] Page 147 of 267
Revision 5 Aug 31, 2015 1 The energy of the m h photon within photon energy group k. J.la(Em) Air Energy Absorption Coefficient The linear energy absorption coefficient for air for photon energy Em. I(... ) I Function A dimensionless parameter obtained by numerical evaluation of integrals that arise in the plume gamma dose problem. The value of I depends on the arguments (...) listed in Equation B-40. A specific definition for I is given by Equation F-13 of Regulatory Guide 1.109. The integrals involved in calculating I arise from conceptually dividing up the radioactive plume into small elements of radioactivity and adding up the doses produced at the point of interest by all of the small elements. The distribution of radioactivity in the plume is represented by a sector-averaged Gaussian plume model like that discussed in Section B.2.2. The parameters R, he. Un, and O'z are defined in Section B.3.1. B.5.2 Ground Level Release The gamma air dose factor Gi for a ground level release is defined as follows: Gi Gamma Air Dose Factor, Ground Level Release [(mrad/yr)/(µCi/sec)] The gamma air dose factor at ground level for a ground level release for radionuclide i, downwind sector e, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period. The value of Gi is obtained by the same equation as used for a stack release, Equation B-36 of Section B.5.1, with the following modifications:
- The joint frequency distribution for a ground level release (f9 of Section B.1.2.3) is used in place of the one for a stack release (f5 ).
- In evaluating the I function, the effective release height he is taken as zero.
This corresponds to use of a finite plume model. B.5.3 Vent Release For a vent release, the gamma air dose factor is calculated as follows: Vj =[260/(21tR/16)] X l:{fv,elev(n,9,c)[exp(-A.iR/3600un)] X Ak1EkJ.1a(Ek) l(he,Un,C,O'z,Ek)/un (B-66)
+ fv,gnd(n,9,c)[exp(-A.iR/3600un)] X AkiEkJ.la(Ek) 1(0,UmC,O'z,Ek)/un}
The summation is over wind speed classes n, atmospheric stability classes c, and photon group indices k. Vi Gamma Air Dose Factor, Vent Release [( mrad/yr)/(µCi/sec )] Page 148 of 267
Revision 5 Aug 31, 2015 The gamma air dose factor at ground level for a vent release for radionuclide i, downwind sector 0, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period. The parameters fv,elev(n,0,c) and fv,gnd(n,0,c) are defined in Section 8.1.2.4. The parameter O"z is defined in Section 8.3.2. The remaining parameters are discussed in Section 8.5.1. 8.6 Gamma Total Body Dose Conversion Factor (Ki) . The gamma total body dose conversion factors (Ki) are used to calculate doses and dose rates due to gamma irradiation of the whole body. The gamma total body dose conversion factors are taken from Reg. Guide 1.109, Table 8-1, Column 5. The gamma total body dose conversion factors in Table 8-1 of Reg. Guide 1.109 are based upon the semi-infinite cloud model. B.7 BETAAIRAND BETA SKIN DOSE CONVERSION FACTORS (Nj,Lj) The beta air (Nj) and beta skin (Lj) dose conversion factors are used to calculate doses and dose rates due to noble gas beta exposure. The beta air dose conversion factors are taken from Reg, Guide 1.109, Table 8-1, Column 2. The beta skin dose conversion factors are taken from Column 5 of that same table. The values are based on a semi-infinite cloud model. B.8 GROUND PLANE DOSE CONVERSION FACTOR DFGi The ground plane dose conversion factor DFGi is used to calculate dose due to standing on ground contaminated with radionuclide i (see Equation A-8 of Appendix A). The units of DFGi are (mrem/hr) per 2 (pCi/m ). Values are provided (see Table C-10 of Appendix C) for dose to the whole body. The values are taken from Regulatory Guide 1.109 and are based on a model that assumes a uniformly contaminated ground plane. B.9 INHALATION DOSE COMMITMENT FACTOR DFAiia The inhalation_dose commitment factor DFAiia is used to calculate dose and dose rate to organ j of an individual of age group a due to inhalation of radionuclide i (see Equations A-7 and A-9 of Appendix A). Values of DFAiia for 10CFR50 compliance are taken from Regulatory Guide 1.109 (Reference 6). The units of DFAija-are mrem per pCi inhaled. Values are provided for seven organs, with the whole body considered as an organ (see Tables E-7, E-8, E-9 and E-10 in Reg. Guide 1.109). B.10 INGESTION DOSE COMMITMENT FACTOR DFLiia The ingestion dose commitment factor DFLiia is used to calculate dose to organ j of an individual of age group a due to ingestion of radionuclide i (see Equations A-7 and A10 through A20 of Appendix A). Values of DFLiia for 10CFR50 compliance are taken from Regulatory Guide 1.109 (Reference 6). The units of DFLiia:are mrem per pCi ingested. In Tables E-11, E-12, E-13 and E-14 of Reg. Guide 1.109, values are provided for seven organs, with the whole body considered as an organ. B.11 MEASURED RELEASE PARAMETERS Input parameters required for calculations of dose or dose rate due to airborne effluents include measured values of radioactivity release (A15 , Aiv* and Ai 9 ) or release rate (Qis* Qiv. and Qi9 ) (see Section A.1 of Appendix A). These are obtained per Zion station procedures. Page 149 of 267
Revision 5 Aug 31, 2015 B.12 RADIOLOGICAL DECAY CONSTANTS Values used for these are obtained from the literature and are specified in Table C-7 of Appendix C. B.13 PRODUCTION/EXPOSURE PARAMETERS These parameters characterize various aspects of agricultural production and human exposure. Values used for generic (site-independent) parameters are specified in Appendix C. Values of site-specific parameters are given in Appendix F. Many of the values are based on Reg. Guide 1.109, while others are based on site-specific considerations. Page 150 of 267
Revision 5 Aug 31, 2015 SECTION 2: MODELS AND PARAMETERS FOR LIQUID EFFLUENT CALCULATIONS B.14 INTRODUCTION Equations for radiation dose and radioactivity concentration due to liquid effluents are given in Section A.2 of Appendix A. The equations involve the following types of parameters:
- Flow and Dilution Parameters.
- Dose Factors.
- Measured Release Parameters.
- Transport/Consumption Parameters.
This section discusses the methodology used to determine these parameters. Section 8.15 addresses dose calculations and Section B.16 addresses concentration calculations for tank discharges. For dose calculations, flow and dilution parameters are discussed for the Lake Michigan Model, which is used for Zion. B.15 DOSE B.15.1 Drinking Water The radiation dose due to consumption of drinking water containing released radioactivity is calculated by Equations A-17, A-18 and A-19 of Appendix A: D~;q = F At LLAaipjci (A-17) p i F= Waste Flow (A-18) Dilution Flow x Z (A-19) The summation is over index i (radionuclides) and p (pathways). The parameters are defined in Section A.2.1 of Appendix A. This methodology addresses the following considerations:
- The duration of the release, Lit.
- The concentration of the activity released, Cj.
- The dilution that takes place in the environment is represented by the parameters F and Z.
- Receptor consumption rate, Uaw*
- Dilution which occurs from the near field discharge area to potable water intake as represented by Dw .
- The dose commitment per unit of ingested radioactivity is DFLaii*
B.15.2 Aquatic Foods (Fish) Near Zion station, the only aquatic food of significance for human consumption is fish. The liquid dose due to consumption of fish containing released radioactivity is calculated by Equations A-17, A-18 and A-20 of Appendix A. (A-20) Page 151 of 267
Revision 5 Aug 31, 2015 The parameters are defined in Section A.2.1 of Appendix A. This is similar to the methodolgy used for calculating the dose due to drinking water except for the addition of the bioaccumulation factor, BF1* This factor is the equilibrium ratio of the concentration of radionuclide i in fish (pCi/kg) to its concentration in water (pCi/L). It accounts for the fact that radioactivity ingested by fish can accumulate in their bodies to a higher concentration than in the waters in which the fish live. B.15.3 Parameters B.15.3.1 Flow and Dilution The values of dilution can differ for potable water and fish. The dilution for potable water will depends on where water is drawn, while that for fish will depends on where the fish are caught. Models used to determine these parameters are discussed below. The values used for Zion Station are summarized in Table F-1 of Appendix F. B.15.3.1.1 Lake Michigan Model Only (Zion) discharges liquid effluents into Lake Michigan. For Zion station, it is assumed that the dilution in the near-field (Z) is dictated by the initial entrainment dilution is a factor of 10. The potable water pathway dilution factor of 6 (Ow) is derived from the plume dilution (a factor of 3 over approximately 1 mile) and the current direction frequency (annual average factor of 2). B.15.3.2 Dose Factors Equations A-17 through A-20 of Appendix A determine dose due to ingested radioactivity using the same ingestion dose factor DFLija as used in the evaluation of airborne radioactivity which is ingested with foods. The units of DFLija are: (mrem) per (pCi ingested) For 10CFR50 Appendix I compliance, the data of Tables E-1, E-12, E-13 and E-14 of Reg. Guide 1.109, are used for four age groups and for seven organs, with the whole body considered as an organ. B.15.3.3 Measured Releases Calculations of dose due to liquid effluents require measured values of radioactivity concentration release (C 1) for input. These release values are obtained per ZionSo/utions' procedures. B.15.3.4 Consumption Equations A-19 and A-20 of Appendix A involve consumption rates for water and fish (Uaw and U/). The values used are specified for Zion Station in Table F-1 of Appendix F. B.16 CONCENTRATION IN TANK DISCHARGES The concentration of radioactivity in a release to the unrestricted area due to a tank discharge is calculated by Equation A-22 of Appendix A: C = C~ Waste Flow (A-22) 1
' Dilution Flow Page 152 of 267
Revision 5 Aug 31, 2015 The parameters are defined in Section A.2.3 of Appendix A. The radioactivity concentration released from the tank (cti at flow rate Fr) is diluted by mixing with the initial dilution stream (with flow rate Fd) to yield a lower concentration (Ci ) in the combined streams. Table B-0 Noble Gas Nuclide Fractions 1 Nuclide Zion Ar-41 O.OOE+OO Kr-83m 0.00E+OO Kr-85 1.00E+OO Kr-85m O.OOE+OO Kr-87 O.OOE+OO Kr-88 O.OOE+OO Kr-89 O.OOE+OO Kr-90 O.OOE+OO Xe-131m O.OOE+OO Xe-133 0.00E+OO Xe-133m O.OOE+OO Xe-135 O.OOE+OO Xe-135m O.OOE+OO Xe-137 O.OOE+OO Xe-138 O.OOE+OO Notes: (1) From Table 10-1. Page 153 of 267
Revision 5 Aug 31, 2015 Table B-1 Portion of an Example Joint Frequency Distribution S~ry Tabl* af P*rc8"t by Direction and Cl*** C1Bllll N NNE NE ENE E ESE 5£ SSE s A .289 .317 .301 .244 .249 .UK>
- tH .un .33&
B
- t90 .t87 *.t78
- tfi8
- t2!5 .065 .079 .t30 .t93 c .269 .226 .262 .218 .190
- t18 .162 .189 .302 D 3.298 2.327 2.338 2.684 1.192 1.334 t.365 2. t72 3.0t2 E t.466 t.198 .988 t.331 '. 86 f t.226 1.472 2.!553 3.G:?I F .!504 .318 .fBS .276 .6911 .848 *.103 1 .293 1. 7~2 G .202 .091 .061 .099 .2fi3 .2!50 .35!5 .400 .624 Total 6.217 4.663 4.304 &.Ott &.169 3.830 4.424 6.933 9.126 SU11111U1ry Tab1* of Percent by Dtr9CUon and Speed Speed N NNE NE ENE E ESE SE SSE s
.45 .098 .099 .078 -030 .009 .000 .Ot4 .032 .048 1.05 .308 .154 .125 .137 .121 .093 .090 .090 .t27 2.05 .939 -~02 .458 .594 .1143 .IO& .!598 .605 t.0011 3.05 1.164 1.030 .779 .981 t.468 t.075 t.093 t.4"18 t.982 4.05 1. t79 t .024 .178 .995 t. 243 .a3t 1.027 t. 727 2. tto !5.05 .839 .631 .858 .798 .724 .474 .152 1.2fi4 t.636 8.05 .612 .467 .496 .1589 .417 .313 .411 .803 1.1!53 B.05 .7155 .437 .812 .695 .3*10 .313 .405 .735 1.319 10.05 .253 .157 ** 183 .165 .032 .093 .103 .tao .374 13.0S .053 .061 .034 .021 .001 .031 .025 .028 .072 '8.00 .016 .001 .004 .ooo .ooo .oot .001 .002 .000 99.00 .ooo .000 .000 .ooo .OOQ .000 .000 .000 .ooo lot:al 6.217 4.&63 4.304 a.011 !5. 169 3.830 4.424 1.933 9.82&
Su_..ry Tabla of P*rcent by ~ and C\aaa Class A B c D E F G Speed
. .cs .O<M .()()1 .000 _095 .2!57 .275 .346 1.05 .018 .012 .027 .508 1.035 1.080 .780 2.05 .286 .171 .246 3.256 15.028 3.228 1.419 3.05 .7"44 .428 .816 6.2'58 7. 173 3.*272 .985 4.05 .992 . !581
- 781 8. 165 6.404 1.902 .400 15.05 .909 .W6 .908 7.302 4.357 .807 .077 6.05 .712 .388 .613 6. 167 2.938 .16.C .013 8.05 .819 .!500 .75!5 7.616 2.734 .081 .011 10.05 .230 . 1!50 .196 2.606 .867 .009 .000 13.05 .07!5 .032 .ass
- 7&!5
- 1111 .001 .000 ULOO .004 .000 .OUl
- 117 .012 .000 .000 99.00 .000 .000 .001 .001 .000 .000 .oo6 Page 154 of 267
Revision 5 Aug 31, 2015 Figure 8-1 Instantaneous View of Plume y Wind This figure represents a snapshot of a projection of a plume on the horizontal plane. As it moves downwind, the plume meanders about the average wind direction and broadens (adapted from Reference 18). Page 155 of 267
Revision 5 Aug 31, 2015 Figure 8*2 A Gaussian Curve 1.0 0.1 0.1 a.T 0.1 y *a * .;:;- 0.5 o.* G.3 o.z 0.1 O.D
-2 _, 0 .,
-s-T CJ (Adapted from Reference 24 of Chapter 9, Page 61.)
Page 156 of 267
Revision 5 Aug 31, 2015 Figure B-3 Effect of Observation Period on Plume Shape
*U.&Tlvl CO,.CtNU&Tle>>I This sketch represents the approximate outlines of a smoke plume observed instataneously and averaged over periods of 10 minutes and 2 hours. The diagram on the right shows the corresponding cross plume distribution patterns. The plume width increases as the period of observation increases (from Reference 18).
Page 157 of 267
Revision 5 Aug 31, 2015 Figure 8-4 A Gaussian Plume I x (x,-y,Z) This sketch illsutrates a plume characterized by Equation B-9. The plume is moving downwind in the x direction. Both the horizontal dispersion parameter sz increases as x increases. The reflected component has been omitted in this illustration (adapted from Reference 24). Page 158 of 267
Revision 5 Aug 31, 2015 APPENDIX C GENERIC DATA Page 159 of 267
Revision 5 Aug 31, 2015 APPENDIXC GENERIC DATA C.1 INTRODUCTION This appendix contains generic offsite dose calculation parameter factors, or values. Site specific factors are provided in the station annex Appendix F. The factors described in section C.2 are found in the prescribed references and are not repeated in this appendix. C.2 10CFR50 DOSE COMMITMENT FACTORS With the exception of H-3, the dose commitment factors for 10CFR50 related calculations are exactly those provided in Regulatory Guide 1.109 (Reference 6). The following table lists the parameters and the corresponding data tables in the RG 1.109: PATHWAY ADULT TEENAGER CHILD INFANT Inhalation RG 1.109:Table E-7 RG 1.109:Table E-8 RG 1.109:Table E-9 RG 1.109:Table E-10 Ingestion RG 1.109:Table E-11 RG 1.109:Table E-12 RG 1.109:Table E-13 RG 1.109:Table E-14 These tables are contained in Regulatory Guide 1.109 (Reference 6). Each table (E-7 through E-14) provides dose factors for seven organs for each of 73 radionuclides. For radionuclides not found in these tables, dose factors will be derived from ICRP 2 (Reference 50) or NUREG-0172 (Reference 51 ). The values for H-3 are taken from NUREG-4013 (Reference 107). Page 160 of 267
Revision 5 Aug 31, 2015 Table C-1 Miscellaneous Dose Assessment Factors - Environmental Parameters Parameter Value Comment Equation Basis a fn 0.76 A-10, A-11 A fl 1.0 A-10, A-11 A fo 1.0 A-12, A-14 A fs 1.0 A-12, A-14 A tb 262,800 hrs 30 years A-8 c tf 48 hrs Cow Milk Pathway A-12 A tf 480 hrs Cow Meat Pathway A-14 A th 1440 hrs 60 days for produce A-10 A th 2160 hrs 90 days for produce A-12, A-14 A tl 24 hrs 1 day for leafy veQetables A-10 A QF 50 Kg/da A-12, A-13, A-14, A-15 B r 0.2 For Particulates A-10, A-12, A-14 A Yo 0.7 Kg/m" A-12, A-14 A Ys 2.0 KQ/m" A-12, A-14 A Yv 2.0 Kg/m" A-10 A
'Aw 0.0021 h(' A-10, A-12, A-14 A H 8 gm/m;j Absolute Atmospheric Humidity A-11, A-13, A-15 D 8
8asis key: A: Reference 6, Table E-15. B: Reference 6, Table E-3. C: The parameter tb is taken as the midpoint of plant operating life {based upon an assumed 60 year plant operating lifetime). D: Reference 14, Section 5.3.1.3. Page 161 of 267
Revision 5 Aug 31, 2015 Table C-2 Miscellaneous Dose Assessment Factors - Consumption Parameters Type Variable Infant Child Teenager Adult BRa 1400 3700 8000 8000 Air (m3/yr) Milk Uam 330 330 400 310 (L/yr) Produce Ua~ 0 520 630 520 (Kg/yr) Leafy UaL 0 26 42 64 Vegetables (Kg/yr) Meat Uat 0 41 65 110 (Kg/yr) Water Uavv 330 510 510 730 (L/yr) Fish Uar 0 6.9 16 21 (Kg/yr) From Regulatory Guide 1.109, Table E-5. Page 162 of 267
Revision 5 Aug 31, 2015 Table C-3 Stable Element Transfer Data Ft FM( Cow) Element Meat (d/kg) Milk (d/L) Reference H 1.2E-02 1.0E-02 6 Be 1.5E-03 3.2E-03 Footnote 1 c 3.1 E-02 1.2E-02 6 F 2.9E-03 1.4E-02 Footnote 2 Na 3.0E-02 4.0E-02 6 Mg 1.5E-03 3.2E-03 Footnote 1 Al 1.5E-02 1.3E-03 Footnote 3 p 4.6E-02 2.5E-02 6 Cl 2.9E-03 1.4E-02 Footnote 2 Ar NA NA NA K 1.8E-02 7.2E-03 16 Ca 1.6E-03 1.1E-02 16 Sc 2.4E-03 7.5E-06 Footnote 4 Ti 3.4E-02 5.0E-06 Footnote 5 v 2.8E-01 1.3E-03 Footnote 6 Cr 2.4E-03 2.2E-03 6 Mn 8.0E-04 2.5E-04 6 Fe 4.0E-02 1.2E-03 6 Co 1.3E-02 1.0E-03 6 Ni 5.3E-02 6.7E-03 6 Cu 8.0E-03 1.4E-02 6 Zn 3.0E-02 3.9E-02 6 Ga 1.5E-02 1.3E-03 Footnote 3 Ge 9.1 E-04 9.9E-05 Footnote 7 As 1.7E-02 5.0E-04 Footnote 8 Se 7.7E-02 1.0E-03 Footnote 9 Br 2.9E-03 2.2E-02 Ft Footnote 2;FM from Ref. 16 Kr NA NA NA Rb 3.1 E-02 3.0E-02 6 Sr 6.0E-04 8.0E-04 6 y 4.6E-03 1.0E-05 6 Zr 3.4E-02 5.0E-06 6 Nb 2.8E-01 2.5E-03 6 Mo 8.0E-03 7.5E-03 6 Tc 4.0E-01 2.5E-02 6 Ru 4.0E-01 1.0E-06 6 Rh 1.5E-03 1.0E-02 6 Pd 5.3E-02 6.7E-03 Footnote 10 Cd 3.0E-02 2.0E-02 Footnote 11 In 1.5E-02 1.3E-03 Footnote 3 Sn 9.1 E-04 9.9E-05 Footnote 7 Sb 5.0E-03 2.0E-05 98 Ag 1.7E-02 5.0E-02 6 Te 7.7E-02 1.0E-03 6 I 2.9E-03 6.0E-03 6 Xe NA NA NA Cs 4.0E-03 1.2E-02 6 Ba 3.2E-03 4.0E-04 6 La 2.0E-04 5.0E-06 6 Ce 1.2E-03 1.0E-04 6 Pr 4.7E-03 5.0E-06 6 Nd 3.3E-03 5.0E-06 6 Page 163 of 267
Revision 5 Aug 31, 2015 Table C-3 (Cont'd) Stable Element Transfer Data Ft FM (Cow) Element Meat (d/kg) Milk (d/L) Reference Pm 2.9E-04 2.0E-05 16 Sm 2.9E-04 2.0E-05 16 Eu 2.9E-04 2.0E-05 16 Gd 2.9E-04 2.0E-05 16 Dy 2.9E-04 2.0E-05 16 Er 2.9E-04 2.0E-05 16 Tm 2.9E-04 2.0E-05 16 Yb 2.9E-04 2.0E-05 16 Lu 2.9E-04 2.0E-05 16 Hf 3.4E-02 5.0E-06 Footnote 5 Ta 2.8E-01 1.3E-03 FM - Ref.16; Fr -Footnote 6 w 1.3E-03 5.0E-04 6 Re 1.0E-01 1.3E-03 FM - Ref.16; Fr -Footnote 12 Os 2.2E-01 6.0E-04 Footnote 13 Ir 7.3E-03 5.5E-03 Footnote 14 Pt 5.3E-02 6.?E-03 Footnote 10 Au 1.3E-02 3.2E-02 Footnote 15 Hg 3.0E-02 9.?E-06 FM - Ref.16; Fr -Footnote 11 Tl 1.5E-02 1.3E-03 FM - Ref.16; Fr -Footnote 3 Pb 9.1 E-04 9.9E-05 98 Bi 1.?E-02 5.0E-04 98 Ra 5.5E-04 5.9E-04 98 Th 1.6E-06 5.0E-06 98 u 1.6E-06 1.2E-04 98 Np 2.0E-04 5.0E-06 6 Am 1.6E-06 2.0E-05 98 Notes:
- 1. NA= It is assumed that noble gases are not deposited on the ground.
- 2. Elements listed are those considered for 10CFR20 assessment and compliance.
Footnotes: There are numerous Ft and FM values that were not found in published literature. In these cases, the periodic table was used in conjunction with published values. The periodic table was used based on a general assumption that elements have similar characteristics when in the same column of the periodic table. The values of elements in the same column of the periodic table, excluding atomic numbers 58-71 and 90-103, were averaged then assigned to elements missing values located in the same column of the periodic table. This method was used for all columns where there were missing values except column 3A, where there was no data, hence, the average of column 2B and 4A were used.
- 1. Values obtained by averaging Reference 6 values of Ca, Sr, Ba and Ra.
- 2. Ft value obtained by assigning the Reference 6 value for I. FM value obtained by averaging l(Ref. 6) and Br (Ref.16).
- 3. Ft values obtained by averaging Zn (Ref.6) and Pb (Ref. 98); there were novalues for elements in the same column; an average is taken between values of columns 2B and 4A on the periodic table. FM values obtained by using the value for Tl from Reference 16.
- 4. Values obtained by averaging Reference 6 values of Y and La.
- 5. Values obtained by assigning the Reference 6 value for Zr.
- 6. Ft values obtained from Ref. 6 value for Nb. FM values obtained by averaging values for Nb (Ref.6) and Ta (Ref. 16).
- 7. Values obtained from the Reference 6 values for Pb.
- 8. Values obtained from the Reference 6 values for Bi.
- 9. Values obtained from the Reference 6 values for Te.
- 10. Values obtained from the Reference 6 values for Ni.
- 11. Ft values obtained from Ref. 6 values for Zn. FM values obtained by averaging the Reference 6 values for Zn and Hg.
- 12. Values obtained by averaging Reference 6 values for Mn, Tc, Nd and Reference 98 value for U.
- 13. Values obtained by averaging Reference 6 values from Fe and Ru.
- 14. Values obtained by averaging Reference 6 values from Co and Rh.
- 15. Values obtained by averaging Reference 6 values from Cu and Ag.
Page 164 of 267
Revision 5 Aug 31, 2015 Table C-4 Atmospheric Stability Classes Pasquill Temperature Change Stability a with Height cre Description Class (degrees) (°C/100 m) Extremely A >22.5 <-1.9 Unstable Moderately B 17.5 to 22.5 -1.9to-1.7 Unstable Slightly c 12.5 to 17.5 -1.7to-1.5 Unstable Neutral D 7.5to12.5 -1.5 to -0.5 Slightly E 3.8 to 7.5 -0.5 to 1.5 Stable Moderately F 2.1 to3.8 1.5 to 4.0 Stable Extremely G 0 to 2.1 >4.0 Stable acre is the standard deviation of horizontal wind direction fluctuation over a period of 15 minutes to 1 hour. From Regulatory Guide 1.21, Table 4B. Page 165 of 267
Revision 5 Aug 31, 2015 Table C-5 Vertical Dispersion Parameters Section 1 Vertical Dispersion Parameters cr2 cr2 (meters)= aRb+c with cr2 limited to a maximum of 1000 meters R =downwind range (meters) a, b and c have the values listed below: Stability 100 < R < 1000 R > 1000 Class g b Q g Q Q A * *
- 0.00024 2.094 -9.6 B * * * * *
- c 0.113 0.911 0.0 * *
- D 0.222 0.725 -1.7 1.26 0.516 -13.0 E 0.211 0.678 -1.3 6.73 0.305 -34.0 F 0.086 0.74 -0.35 18.05 0.18 -48.6 G 0.052 0.74 -0.21 10.83 0.18 -29.2 Basis: Reference 53, except for cases denoted by an asterisk. In these cases, the value of cr2 is obtained by a polynomial approximation to the data from Reference 53 (see Section 2 of this table). The functions given in Reference 50 are not used because they are discontinuous at 1000 meters.
Section 2 Polynomial Approximation for crz.;. 2 3 cr2 (meters)= exp [a 0 + a1P + a2 P + a3P ] with cr2 limited to a maximum of 1000 meters P = loge [R(meters)] ao, a1, az and a3 have the values listed below: Stability Class Range Coefficients A 100 ~ R~ 1000 ao = -10.50 a1 = 6.879 a2 = -1.309 a3= 0.0957 B 100 ~ R~ 1000 ao = -0.449 a1 = 0.218 a2 = 0.112 a3 = -0.00517 B R > 1000 ao = 319.148 a1 = -127.806 a2 = 17.093 a3= -0.750 c R > 1000 ao = 5.300 a1 = -1.866 a2= 0.3509 a3 = -0.01514 Page 166 of 267
Revision 5 Aug 31, 2015 Table C-6 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste Allowable Concentration (µCi/ml) 3 Nuclide Zion Kr85m 2E-4 Kr85 5E-4 Kr87 4E-5 Kr88 9E-5 Ar41 7E-5 Xe 131m 7E-4 Xe 133m 5E-4 Xe 133 6E-4 Xe 135m 2E-4 Xe 135 2E-4 3 Computed from Equation 17 of ICRP Publication 2 (Reference 50) adjusted for infinite cloud submersion in water, and R =0.01 rem/week, Pw =1.0 gm/cm , and Pw /P1 =1.0. 3 Page 167 of 267
Revision 5 Aug 31, 2015 Table C-7 Radiological Decay Constants p.,i) in hf1 Isotope Lambda Isotope Lambda lsotoQe Lambda H-3 6.44E-06 As-73 3.6E-04 Tc-104 2.31E+OO Be-7 5.4E-04 As-74 1.62E-03 Ru-97 9.96E-03 C-14 1.38E-08 As-76 2.63E-02 Ru-103 7.34E-04 F-18 3.78E-01 As-77 1.79E-02 Ru-105 1.56E-01 Na-22 3.04E-05 Se-73 9.69E-02 Ru-106 7.84E.:.05 Na-24 4.62E-02 Se-75 2.41E-04 Rh-106 8.33E+01 Mq-27 4.39E+OO Br-77 1.21 E-02 Pd-109 5.15E-02 Mg-28 3.31 E-02 Br-80 2.38E+OO Cd-109 6.22E-05 Al-26 1.10E-10 Br-82 1.96E-02 ln-111 1.02E-02 Al-28 1.85E+01 Br-83 2.90E-01 ln-115M 1.59E-01 P-32 2.02E-03 Br-84 1.30E+OO ln-116 7.66E-01 Cl-38 1.12E+OO Br-85 1.45E+01 Sn-113 2.51E-04 Ar-41 3.79E-01 Kr-79 1.98E-02 Sn-117M 2.12E-03 K-40 6.19E-14 Kr-81 3.77E-10 Sn-119M 9.85E-05 K-42 5.61 E-02 Kr-83M 3.79E-01 Sb-117 2.48E-01 K-43 3.07E-02 Kr-85M 1.55E-01 Sb-122 1.07E-02 Ca-47 6.37E-03 Kr-85 7.38E-06 Sb-124 4.80E-04 Sc-44 1.76E-01 Kr-87 5.44E-01 Sb-125 2.86E-05 Sc-46M 1.33E+02 Kr-88 2.44E-01 Sb-126 2.33E-03 Sc-46 3.44E-04 Kr-90 7.71 E+OO Aq-108M 6.23E-07 Sc-47 8.44E-03 Rb-84 8.78E-04 Ag-108 1.75E+01 Ti-44 1.67E-06 Rb-86 1.55E-03 Aq-110M 1.16E-04 V-48 1.81 E-03 Rb-87 1.67E-15 Ag-111 3.87E-03 Cr-51 1.04E-03 Rb-88 2.33E+OO Te-121 M 1.88E-04 Mn-52M 1.94E+OO Rb-89 2.69E+OO Te-121 1.72E-03 Mn-52 5.16E-03 Sr-85 4.45E-04 Te-123M 2.41 E-04 Mn-54 9.23E-05 Sr-87M 2.47E-01 Te-125M 4.98E-04 Mn-56 2.69E-01 Sr-89 5.71 E-04 Te-125 O.OOE+OO Fe-52 8.37E-02 Sr-90 2.77E-06 Te-127M 2.65E-04 Fe-55 2.93E-05 Sr-91 7.29E-02 Te-127 7.41 E-02 Fe-59 6.47E-04 Sr-92 2.56E-01 Te-129M 8.59E-04 Co-57 1.07E-04 Y-86 4.70E-02 Te-129 5.96E-01 Co-58 4.08E-04 Y-87 8.63E-03 Te-131M 2.31E-02 Co-60 1.50E-05 Y-88 2.71 E-04 Te-131 1.66E+OO Ni-63 7.90E-07 Y-90 1.08E-02 Te-132 8.86E-03 Ni-65 2.75E-01 Y-91M 8.35E-01 Te-134 9.93E-01 Cu-64 5.46E-02 Y-91 4.94E-04 1-123 5.28E-02 Cu-67 4.67E-04 Y-92 1.96E-01 1-124 6.91E-03 Cu-68 8.31 E+01 Y-93 6.86E-02 1-125 4.80E-04 Zn-65 1.18E-04 Zr-95 4.51 E-04 1-130 5.61 E-02 Zn-69M 5.04E-02 Zr-97 4.10E-02 1-131 3.59E-03 Zn-69 7.46E-01 Nb-94 3.90E-09 1-132 3.01E-01 Ga-66 7.37E-02 Nb-95 8.00E-03 1-133 3.33E-02 Ga-67 8.85E-03 Nb-97M 4.15E+01 1-134 7.89E-01 Ga-68 6.10E-01 Nb-97 5.76E-01 1-135 1.05E-01 Ga-72 4.91E-02 Mo-99 1.05E-02 Xe-127 7.93E-04 Ge-77 6.13E-02 Tc-99M 1.15E-01 Xe-129M 3.25E-03 As-72 2.67E-02 Tc-101 2.92E+OO Xe-131M 2.44E-03 Page 168 of 267
Revision 5 Aug 31, 2015 Table C-7 (Cont'd) Radiological Decay Constants (A.i) in hr"1 lsotooe Lambda lsotooe Lambda Xe-133M 1.32E-02 Yb-175 6.89E-03 Xe-133 5.51E-03 Lu-177 4.30E-03 Xe-135M 2.70E+OO Hf-181 6.81 E-04 Xe-135 7.61 E-02 Ta-182 2.52E-04 Xe-137 1.08E+01 Ta-183 5.78E-03 Xe-138 2.94E+OO W-187 2.91 E-02 Cs-129 2.16E-02 Re-188 4.08E-02 Cs-132 4.46E-03 Os-191 1.88E-03 Cs-134 3.84E-05 lr-194 3.62E-02 Cs-136 2.19E-03 Pt-195M 7.18E-03 Cs-137 2.62E-06 Pt-197 3.79E-02 Cs-138 - 1.29E+OO Au-195M 8.15E+01 Cs-139 4.41 E+OO Au-195 1.58E-04 Ba-131 2.45E-03 Au-198 1.07E-02 Ba-133M 1.78E-02 Au-199 9.20E-03 Ba-133 7.53E-06 Hq-197 2.91 E-02 Ba-135M 2.41E-02 Hg-203 6.20E-04 Ba-137M 1.63E+01 Tl-201 9.49E-03 Ba-137 O.OOE+OO Tl-206 9.90E+OO Ba-139 4.99E-01 Tl-208 1.36E+01 Ba-140 2.26E-03 Pb-203 1.33E-02 Ba-141 2.27E+OO Pb-210 3.55E-06 Ba-142 3.88E+OO Pb-212 6.51 E-02 La-140 1.72E-02 Pb-214 1.55E+OO La-142 4.35E-01 Bi-206 4.63E-03 Ce-139 2.10E-04 Bi-207 2.37E-06 Ce-141 8.88E-04 Bi-214 2.09E+OO Ce-143 2.10E-02 Ra-226 4.94E-08 Ce-144 1.02E-04 Th-232 5.63E-15 Pr-142 3.62E-02 U-238 1.77E-14 Pr-143 2.13E-03 Np-239 1.23E-02 Pr-144 2.40E+OO Am-241* 1.83E-07 Nd-147 2.63E-03 Nd-149 4.01E-01 (A.i) =Radiological Decay C onstant Pm-145 4.47E-06 = 0.693/Ti Pm-148M 6.99E-04 Pm-148 5.38E-03 Ti = Radiological Half-Life in hours Pm-149 1.31 E-02 (from Reference 70). Sm-153 1.48E-02 Except for Cu-68, Tc-104, Ba-137, Ta-183, TL-206, Eu-152 5.82E-06 Bi-206 which are fro m References 100. Eu-154 8.99E-06 Eu-155 1.59E-05 Gd-153 1.20E-04 Dv-157 8.60E-02 Er-169 3.07E-03 Er-171 9.22E-02 Tm-170 2.25E-04 Yb-169 9.03E-04 Page 169 of 267
Revision 5 Aug 31, 2015 Table C-8 Bioaccumulation Factors (BF;) to be Used in the Absence of Site-Specific Data BF; for Freshwater Fish Element {12Ci/kg per pCi/L} Reference H 9.0E-01 6 Be 2.8E+01 Footnote 2 c 4.6E+03 6 F 2.2E+02 Footnote 16 Na 1.0E+02 6 Mg 2.8E+01 Footnote 2 Al 2.2E+03 Footnote 13 p 1.0E+05 6 Cl 2.2E+02 Footnote 16 Ar NA NA K 1.0E+03 Footnote 1 Ca 2.8E+01 Footnote 2 Sc 2.5E+01 Footnote 3 Ti 3.3E+OO Footnote 4 v 3.0E+04 Footnote 5 Cr 2.0E+02 6 Mn 4.0E+02 6 Fe 1.0E+02 6 Co 5.0E+01 6 Ni 1.0E+02 6 Cu 5.0E+01 6 Zn 2.0E+03 6 Ga 2.2E+03 Footnote 13 Ge 2.4E+03 Footnote 12 As 3.3E+04 Footnote 14 Se 4.0E+02 Footnote 15 Br 4.2E+02 6 Kr NA NA Rb 2.0E+03 6 Sr 3.0E+01 6 y 2.5E+01 6 Zr 3.3E+OO 6 Nb 3.0E+04 6 Mo 1.0E+01 6 Tc 1.5E+01 6 Ru 1.0E+01 6 Rh 1.0E+01 6 Pd 1.0E+02 Footnote 9 Cd 2.0E+03 Footnote 11 In 2.2E+03 Footnote 13 Sn 2.4E+03 Footnote 12 Sb 1.0E+OO 98 Ag 2.3E+OO 56 Te 4.0E+02 6 I 1.5E+01 6 Xe NA NA Cs 2.0E+03 6 Ba 4.0E+OO 6 La 2.5E+01 6 Ce 1.0E+OO 6 Pr 2.5E+01 6 Nd 2.5E+01 6 Pm 3.0E+01 98 Sm 3.0E+01 Footnote 3 Page 170 of 267
Revision 5 Aug 31, 2015 Table C-8 (Cont'd) Bioaccumulation Factors (BFj) to be Used in the Absence of Site-Specific Data BFi for Freshwater Fish Element (pCi/kg per pCi/L) Reference Eu 1.0E+02 Footnote 3 Gd 2.6E+01 Footnote 3 Dy 2.2E+03 Footnote 3 Er 3.3E+04 Footnote 3 Tm 4.0E+02 Footnote 3 Yb 2.2E+02 Footnote 3 Lu 2.5E+01 Footnote 3 Hf 3.3E+OO Footnote 4 Ta 3.0E+04 Footnote 5 w 1.2E+03 6 Re 2.1E+02 Footnote 6 Os 5.5E+01 Footnote 7 Ir 3.0E+01 Footnote 8 Pt 1.0E+02 Footnote 9 Au 2.6E+01 Footnote 10 Hg 2.0E+03 Footnote 11 Tl 2.2E+03 Footnote 13 Pb 3.0E+02 98 Bi 2.0E+01 98 Ra 5.0E+01 98 Th 3.0E+01 98 u 1.0E+01 98 Np 1.0E+01 6 Am 3.0E+01 98 Footnotes: NA =It is assumed that noble gases are not accumulated. In Reference 6, see Table A-1. A number of bioaccumulation factors could not be found in literature. In this case, the periodic table was used in conjunction with published element values. This method was used for periodic table columns except where there were no values for column 3A so the average of columns 2B and 4A was assigned.
- 1. Value is the average of Reference 6 values in literature for H, Na, Rb and Cs.
- 2. Value is the average of Ref. 6 values in literature for Sr, Ba and Ref. 98 values for Ra.
- 3. Value is the same as the Reference 6 value used for Y.
- 4. Value is the same as the Reference 6 value used for Zr.
- 5. Value is the same as the Reference 6 value used for Nb.
- 6. Value is the average of Reference 6 values in literature for Mn and Tc.
- 7. Value is the average of Reference 6 values in literature for Fe and Ru.
- 8. Value is the average of Reference 6 values in literature for Co and Rh.
- 9. Value is the same as the Reference 6 value used for Ni.
- 10. Value is the average of Reference 6 values in literature for Cu and Reference 56 value for Ag.
- 11. Value used is the same as the Reference 6 value used for Zn.
- 12. Value is the average of Reference 6 value in literature for C and Reference 98 value for Pb.
- 13. Value is the average of columns 2B and 4A, where column 2B is the "Reference 6 value for Zn" and column 4A is the average of "Reference 6 value for C and Reference 98 value for Pb".
- 14. Value is the average of Ref. 6 value found in literature for P and the Ref. 98 values for Bi and Sb.
- 15. Value is the same as the Reference 6 value used for Te.
- 16. Value is the average of Reference 6 values found in literature for Br and I.
Page 171 of 267
Revision 5 Aug 31, 2015 Table C-9 Dose Factors for Noble Gases Beta Air Beta Skin GammaAir Gamma Total Body Dose Factor Dose Factor Dose Factor Dose Factor Ni Li Mi Ki Nuclide (mrad/yr ~er uCi/m") (mrem/yr ~er uCi/m") (mrad/yr ~er uCi/m") (mrem/yr ~er uCi/m") Kr-83m 2.88E+02 --- 1.93E+01 7.56E-02 Kr-85m 1.97E+03 1.46E+03 1.23E+03 1.17E+03 Kr-85 1.95E+03 1.34E+03 1.72E+01 1.61E+01 Kr-87 1.03E+04 9.73E+03 6.17E+03 5.92E+03 Kr-88 2.93E+03 2.37E+03 1.52E+04 1.47E+04 Kr-89 1.06E+04 1.01 E+04 1.73E+04 1.66E+04 Kr-90 7.83E+03 7.29E+03 1.63E+04 1.56E+04 Xe-131m 1.11 E+03 4.76E+02 1.56E+02 9.15E+01 Xe-133m 1.48E+03 9.94E+02 3.27E+02 2.51E+02 Xe-133 1.05E+03 3.06E+02 3.53E+02 2.94E+02 Xe-135m 7.39E+02 7.11 E+02 3.36E+03 3.12E+03 Xe-135 2.46E+03 1.86E+03 1.92E+03 1.81E+03 Xe-137 1.27E+04 1.22E+04 1.51 E+03 1.42E+03 Xe-138 4.75E+03 4.13E+03 9.21E+03 8.83E+03 Ar-41 3.28E+03 2.69E+03 9.30E+03 8.84E+03 Source: Table B-1 of Reference 6. Page 172 of 267
Revision 5 Aug 31, 2015 Table C-10 External Dose Factors for Standing on Contaminated Ground DFGi.i {mrem/hr ~er ~Ci/ m } 2 Whole Body Element Dose Factor Reference Element Dose Factor Reference H-3 O.OOE+OO 6 Be-7 5.95E-10 99 C-14 O.OOE+OO 6 F-18 1.19E-08 99 Na-22 2.42E-08 99 Na-24 2.50E-08 6 Mg-27 1.14E-08 99 Mg-28 1.48E-08 99 Al-26 2.95E-08 99 Al-28 2.00E-08 99 P-32 O.OOE+OO 6 Cl-38 1.70E-08 99 Ar-41 1.39E-08 99 K-40 2.22E-09 99 K-42 4.64E-09 99 K-43 1.19E-08 99 Ca-47 1.14E-08 99 Sc-44 2.50E-08 99 Sc-46m 1.21 E-09 99 Sc-46 2.24E-08 99 Sc-47 1.46E-09 99 Ti-44 1.95E-09 99 V-48 3.21E-08 99 Cr-51 2.20E-10 6 Mn-52m 2.79E-08 99 Mn-52 3.80E-08 99 Mn-54 5.80E-09 6 Mn-56 1.10E-08 6 Fe-52 9.12E-09 99 Fe-55 0.00E+OO 6 Fe-59 8.00E-09 6 Co-57 1.65E-09 99 Co-58 7.00E-09 6 Co-60 1.70E-08 6 Ni-63 O.OOE+OO 6 Ni-65 3.70E-09 6 Cu-64 1.50E-09 6 Cu-67 1.52E-09 99 1 Cu-68 8.60E-09 Zn-65 4.00E-09 6 Zn-69m 5.06E-09 99 Zn-69 0.00E+OO 6 Ga-66 2.70E-08 99 Ga-67 1.89E-09 99 Ga-68 1.24E-08 99 Ga-72 3.00E-08 99 Ge-77 1.34E-08 99 As-72 2.23E-08 99 As-73 1.16E-10 99 As-74 9.41 E-09 99 As-76 6.46E-09 99 As-77 1.79E-10 99 Se-73 1.38E-08 99 Se-75 4.98E-09 99 Br-77 3.84E-09 99 Br-80 2.01E-09 99 Br-82 3.00E-08 99 Br-83 6.40E-11 6 Br-84 1.20E-08 6 Br-85 O.OOE+OO 6 Kr-79 3.07E-09 99 Kr-81 1.59E-10 99 Kr-83m 1.42E-11 99 Kr-85m 2.24E-09 99 Kr-85 1.35E-10 99 Kr-87 1.03E-08 99 Kr-88 2.07E-08 99 Kr-90 1.56E-08 99 Rb-84 1.07E-08 99 Rb-86 6.30E-10 6 Rb-87 0.00E+OO 99 Rb-88 3.50E-09 6 Rb-89 1.50E-08 6 Sr-85 6.16E-09 99 Sr-87m 3.92E-09 99 Sr-89 5.60E-13 6 Sr-90 1.84E-11 99 Sr-91 7.10E-09 6 Sr-92 9.00E-09 6 Y-86 4.00E-08 99 Y-87 5.53E-09 99 Y-88 2.88E-08 99 Y-90 2.20E-12 6 Y-91m 3.80E-09 6 Y-91 2.40E-11 6 Y-92 1.60E-09 6 Y-93 5.70E-10 6 Zr-95 5.00E-09 6 Zr-97 5.50E-09 6 Nb-94 1.84E-08 99 Nb-95 5.10E-09 6 Nb-97m 8.57E-09 99 Nb-97 8.48E-09 99 Mo-99 1.90E-09 6 Tc-99m 9.60E-10 6 Tc-101 2.70E-09 6 1 Tc-104 1.83E-08 Ru-97 2.99E-09 99 Ru-103 3.60E-09 6 Ru-105 4.50E-09 6 3 3.80E-10 99 Ru/Rh-106 5.76E-09 6, 99 Pc-109 Cc-109 1.12E-10 99 ln-111 5.11E-09 99 ln-115m 2.01E-09 99 ln-116 O.OOE+002 Sn-113 1.15E-09 99 Sn-117m 1.96E-08 99 Sn-119m 7.05E-11 99 Sb-117 O.OOE+00 2 1 1 Sb-122 2.71E-09 Sb-124 1.16E-08 Sb-125 4.56E-09 99 Sb-126 7.13E-10 99 Ag-108m 1.92E-08 99 Ag-108 1.14E-09 99 Ag-110m 1.80E-08 6 Ag-111 6.75E-10 99 Te-121m 2.65E-09 99 Te-121 6.75E-09 99 Te-123m 1.88E-09 99 Te-125m 3.50E-11 6 Te-125 O.OOE+002 Te-127m 1.10E-12 6 Te-127 1.00E-11 6 Te-129m 7.70E-10 6 Te-129 7.10E-10 6 Te-131m 8.40E-09 6 Page 173 of 267
Revision 5 Aug 31, 2015 Table C-10 (cont.) External Dose Factors for Standing on Contaminated Ground 2 DFGi1 {mrem/hr Qer QCi/ m } Whole Body Element Dose Factor Reference Element Dose Factor Reference 5 Te-131 2.20E-09 6 Te-1-132 3.40E-09 6 Te-134 1.05E-08 99 1-123 2.12E-09 99 1-124 1.23E-08 99 1-125 2.89E-10 99 1-130 1.40E-08 6 1-131 2.80E-09 6 1-133 3.70E-09 6 1-134 1.60E-08 6 1-135 1.20E-08 6 Xe-127 3.44E-09 99 Xe-129m 5.57E-10 99 Xe-131m 2.13E-10 99 Xe-133m 4.81 E-10 99 Xe-133 5.91E-10 99 Xe-135m 5.23E-09 99 Xe-135 3.36E-09 99 Xe-137 4.26E-09 99 Xe-138 1.30E-08 99 Cs-129 3.39E-09 99 Cs-132 8.40E-09 99 Cs-134 1.20E-08 6 Cs-136 1.50E-08 6 4 Cs-137/Ba-137m 1.14E-08 6, 99 Cs-138 2.10E-08 6 Cs-139 5.15E-09 99 Ba-131 5.74E-09 99 Ba-133m 8.10E-10 99 Ba-133 4.85E-09 99 Ba-135m 7.26E-10 99 Ba-137m 7.17E-09 99 2 Ba-137 O.OOE+00 Ba-139 2.40E-09 6 6 Ba-La-140 1.71 E-08 6 Ba-141 4.30E-09 6 Ba-142 7.90E-09 6 La-142 1.50E-08 6 Ce-139 2.04E-09 99 Ce-141 5.50E-10 6 7 Ce-143 2.20E-09 6 Ce-Pr-144 5.20E-10 6 Pr-142 1.84E-09 99 Pr-143 O.OOE+OO 6 Nc-147 1.00E-09 6 Nc-149 5.32E-09 99 Pm-145 3.38E-10 99 Pm-148m 2.35E-08 99 Pm-148 7.22E-09 99 Pm-149 5.32E-10 99 Sm-153 8.95E-10 99 Eu-152 1.30E-08 99 Eu-154 1.41E-08 99 Eu-155 8.27E-10 99 Gc-153 1.46E-09 99 Dy-157 4.39E-09 99 Er-169 6.12E-14 99 Er-171 5.11 E-09 99 Tm-170 3.41E-10 99 Yb-169 4.12E-09 99 Yb-175 4.94E-10 99 Lu-177 4.60E-10 99 Hf-181 6.67E-09 99 Ta-182 1.42E-08 99 1 Ta-183 2.93E-09 W-187 3.10E-09 6 Re-188 1.89E-09 99 Os-191 9.83E-10 99 lr-194 2.31E-09 99 Pt-195m 9.79E-10 99 Pt-197 3.57E-10 99 Au-195m 2.54E-09 99 Au-195 1.14E-09 99 Au-198 5.19E-09 99 Au-199 1.18E-09 99 Hg-197 9.33E-10 99 Hg-203 2.89E-09 99 Tl-201 1.24E-09 99 2 Tl-206 O.OOE+00 Tl-208 3.58E-08 99 Pb-203 3.88E-09 99 Pb-210 3.57E-11 99 Pb-212 1.91 E-09 99 Pb-214 3.18E-09 99 Bi-206 3.74E-08 99 Bi-207 1.77E-08 99 Bi-214 1.71E-08 99 Ra-226 8.78E-11 99 Th-232 8.14E-12 99 U-238 7.98E-12 99 Np-239 9.50E-10 6 Am-241 3.48E-10 99 Valued derived by comparing the percentage and MeV of the nuclide's gammas and then comparing to Cesium-137, as a value was not available in the literature. 2 0.0 due to low yield and short half life. A value was not available in the literature. 3 Value is the sum of Ru-106 (1.50E-9) and Rh-106 (4.26E-9). The Rh-106 value is from Reference 99 and the Ru-106 value is from Reference 6. 4 Value is the sum of Cs-137 (4.20E-9) and Ba-137m (7.17E-9). The values are from references 6 and 99, respectively. 5 Value is the sum ofTe-132 (1.70E-9) and 1-132 (1.70E-9). 6 Value is the sum of Ba-140 (2.10E-9) and La-140 (1.50E-8) from reference 6. In Reference 6, see Table E-6. 7 Value is the sum of Ce-144 (3.20E-10) and Pr-144 (2.00E-10) from reference 6. Note: Dose assessments for 10CFR20 and 40CFR190 compliance are made for an adult only. Dose assessments for 10CFR50 Appendix are made using dose factors of Regulatory Guide 1.109 (Reference 6) for all age groups. Page 174 of 267
Revision 5 Aug 31, 2015 Table C-11 Sector Code Definitions Angle Sector Sector from North Code Direction (Degrees) A N 348. 75 < e ~ 11 .25 B NNE 11.25 < e ~ 33. 75 c NE 33. 75 < e ~ 56.25 D ENE 56.25 < e ~ 78. 75 E E 78.75 < e ~ 101.25 F ESE 101.25 < e ~ 123.75 G SE 123.75 < e ~ 146.25 H SSE 146.25 < e ~ 168.75 J s 168.75 < e ~ 191.25 K SSW 191.25 < e ~ 213.75 L SW 213. 75 < e ~ 236.25 M WSW 236.25 < e ~ 258. 75 N w 258.75 < e ~ 281.25 p WNW 281.25 < e ~ 303.75 Q NW 303. 75 < e ~ 326.25 R NNW 326.25 < e ~ 348. 75 Page 175 of 267
Revision 5 Aug 31, 2015 APPENDIX D Deleted Page 176 of 267
Revision 5 Aug 31, 2015 APPENDIX E Deleted Page 177 of 267
Revision 5 Aug 31, 2015 APPENDIX F STATION-SPECIFIC DATA FOR ZION UNITS 1AND2 Page 178 of 267
Revision 5 Aug 31, 2015 APPENDIX F STATION-SPECIFIC DATA FOR ZION UNITS 1AND2 F.1 INTRODUCTION This appendix contains data relevant to the Zion site. Included is a figure showing the unrestricted area boundary, restricted area boundary and values of parameters used in offsite dose assessment. Page 179 of 267
Revision 5 Aug 31, 2015 Table F-1 Aquatic Environmental Dose Parameters General lnformationa The existence of irrigation is not mentioned in Zion Environmental Report. Recreation includes one or more of the following: boating, water skiing, swimming, and sport fishing. Water and Fish Ingestion Parameters Parameterb Value ow 6 z 10 Limits on Radioactivity in Unprotected Outdoor Tanksc,d,e Outside Temporary Tank Activity Concentration ~10% of 10CFR20 Appendix B Table 2 Column 2 Limits a This is based on information in Zion Environmental Report Section 2.3.2.2. b The parameters are defined in Section A.2.1 of Appendix A. Based on Lake Michigan Model discussed in Section C.1.3.1.2 of Appendix C. c See Section A.2.4 of Appendix A. d Tritium and dissolved or entrained noble gases are excluded from this limit 0 The sum of the fractions for each radionuclide cannot exceed unity Page 180 of 267
Revision 5 Aug 31, 2015 Table F-2 Station Characteristics STATION: Zion Nuclear Power Station LOCATION: Zion, Illinois Characteristics of Elevated Release Point
- 1) Release Height = _ _ m 2) Diameter= _ _ m
- 3) Exit Speed = _ _ ms-1 4) Heat Content = _ _ Kcal s-1 Characteristics of Vent Stack Release Point
- 1) Release Height = 55.32 ma 2) Diameter = 2.32 m
- 3) Exit Speed = -11.1.._ms- 1a Characteristics of Ground Level Point
- 1) Release Height = 0 m
- 2) Building Factor (D) = 57.6 ma Meterological Data A 250 ft Tower is Located 700 m NNW of Vent Stack release point Tower Data Used in Calculations Wind Speed Differential Release Point and Direction Temperature Elevated (NA) (NA)
Vent 125 250-35 Ground 35 250-35 a Used in calculating the meteorological and dose factors in Tables F-5, F-6, and F-7. See Sections B.3 through B.6 of Appendix B. Page 181 of 267
Revision 5 Aug 31, 2015 Table F-3 Critical Ranges Unrestricted Restricted Area Nearest Nearest Dairy Farm Site Direction Area Boundarya Boundary Residentb Within 5 Milesc Sector (m) (m) (m) (m) N A 469 375 4000 None NNE B 475 400 d None NE c 400 325 d None ENE D 400 200 d None E E 400 175 d None ESE F 400 175 d None SE G 400 175 d None SSE H 400 200 d None s J 433 350 d None SSW K 439 375 3700 None SW L 518 475 2000 None WSW M 671 671 2000 None w N 658 658 1100 None WNW p 893 893 2000 None NW Q 847 847 2000 None NNW R 725 250 2400 None a Used in calculating the meteorological and dose factors in Tables F-5 and F-7. See sections 8.3 through 8.6 of Appendix 8. b 1992 annual survey by Teledyne Isotopes Midwest Laboratories. The distances are rounded to the nearest conservative 100 meters. c 1992 annual milk animal census by Teledyne Isotopes Midwest Laboratories. Used in calculating the D/Q values in Table F-6. The distances are rounded to the nearest conservative 100 meters. d Lake Michigan Page 182 of 267
Revision 5 Aug 31, 2015 Table F-4 Average Wind Speeds Downwind Direction Site Sector Average Wind Speed (m/sec)a Mixed Mode Ground Level N A 5.0 3.2 NNE B 5.3 3.3 NE c 5.8 4.1 ENE D 5.6 3.9 E E 5.7 3.9 ESE F 5.1 3.3 SE G 4.9 3.0 SSE H 5.1 3.4 s J 5.9 4.6 SSW K 5.8 4.4 SW L 5.1 4.0 WSW M 5.2 4.6 w N 5.1 4.4 WNW p 4.8 3.7 NW Q 4.7 3.1 NNW R 5.1 3.9 a Calculated in Reference 81 using formulas in Section 8.1.3 of Appendix B. Based on Zion site meteorological data, January 1979 through December 1987. Page 183 of 267
Revision 5 Aug 31, 2015 Table F-5 X/Q and D/Q Maxima at or Beyond the Unrestricted Area Boundary Downwind Site Radius Mixed Mode Vent) Release Ground Level Release Direction Sector (meters) "I.IQ (sec/m;s) D/Q (1/m~) "I.IQ {sec/m;s) D/Q (1/m~) N A 469 2.032E-6 1.168E-8 9.548E-6 3.680E-8 NNE B 475 1.792E-6 9.983E-9 1.004E-5 3.256E-8 NE c 400 2.710E-6 1.997E-8 1.386E-5 5.708E-8 ENE D 400 2.180E-6 1.734E-8 1.160E-5 4.855E-8 E E 400 1.949E-6 1.889E-8 1.169E-5 5.211 E-8 ESE F 400 1.650E-9 1.319E-8 1.280E-5 4.730E-8 SE G 400 1.646E-6 1.237E-8 1.312E-5 4.985E-8 SSE H 400 1.001 E-6 9.230E-9 7.852E-6 3.238E-8 s J 433 1.272E-6 1.524E-8 7.058E-6 3.562E-8 SSW K 439 9.650E-7 1.357E-8 5.768E-6 3.290E-8 SW L 518 4.590E-7 6.081E-9 3.125E-6 1.625E-8 WSW M 671 2.311 E-7 3.509E-9 1.393E-6 8.964E-9 w N 658 2.394E-7 3.381E-9 1.445E-6 8.440E-9 WNW p 893 1.427E-7 1.869E-9 8.817E-7 4.789E-9 NW Q 847 2.110E-7 2.671 E-9 1.310E-6 6.607E-9 NNW R 725 3.740E-7 4.535E-9 2.038E-6 1.148E-8 Zion Site Meteorological Data 01/79 -12/87 NOTE: Based on the formulas in Sections B.3 and B.4 of Appendix B. x!Q is used for beta skin and inhalation pathways. See Sections A.1.2, A.1.3 and A.1.4.2 of Appendix A. D/Q is used for produce and leafy vegetable pathways. Section A.1.4 of Appendix A. The mixed mode level release data are provided for reference purposes only. Routine dose calculations are performed using ground level data. Radius is the approximate distance from the midpoint between gaseous effluent release points to the location of the highest x/Q Q or D/Q at or beyond the unrestricted area boundary (UAB). Page 184 of 267
Revision 5 Aug 31, 2015 Table F-Sa xtQ and D/Q Maxima at or Beyond the Restricted Area Boundary Downwind Site Radius Mixed Mode (Vent) Release Ground Level Release Direction Sector (meters) *xJQ (sec/m 3 ) D/Q (1/m") x/Q (sec/m~) D/Q (1/m") N A 375 3.015E~6 1.605E-8 1.420E-5 5.165E-8 NNE B 400 2.426E-6 1.278E-8 1.363E-5 4.230E-8 NE c 325 3.917E-6 2.653E-8 2.009E-5 7.781 E-8 ENE D 200 7.441 E-6 4.345E-8 4.027E-5 1.330E-7 E E 175 8.400E-6 5.512E-8 5.177E-5 1.719E-7 ESE F 175 7.025E-6 3.590E-8 5.670E-5 1.559E-7 SE G 175 7.002E-6 3.298E-8 5.811E-5 1.644E-7 SSE H 200 3.362E-6 2.113E-8 2.730E-5 8.871 E-8 s J 350 1.851 E~6 2.054E-8 1.031E-5 4.906E-8 SSW K 375 1.270E-6 1.676E-8 7.631E-6 4.174E-8 SW L 475 5.307E-7 6.818E-9 3.626E-6 1.858E-8 WSW M 671 2.311E-7 3.509E-9 1.393E-6 8.964E-9 w N 658 2.394E-7 3.381E-9 1.445E-6 8.440E-9 WNW p 893 1.427E-7 1.869E-9 8.817E-7 4.789E-9 NW Q 847 2.11 E-7 2.871E-9 1.310E-6 6.607E-9 NNW R 250 2.79E-6 1.778E-8 1.316E-5 5.779E-8 Zion ~ite Meteorological Data 01/79 - 12/87 NOTE: Based on the formulas in Sections B.3 and B.4 of Appendix B. The mixed mode level release data are provided for reference purposes only. Routine dose calculations are performed using ground level data. Radius is the approximate distance from the midpoint between gaseous effluent release points to the location of the highest x/Q or D/Q at or beyond the restricted area boundary (RAB). Page 185 of 267
Revision 5 Aug 31, 2015 Table F-Sb Maximum Offsite Gamma-x!Q Ground Vent Downwind Radius Site Sector Gamma-x/Q Gamma-x!Q Direction (meters) (sec/m 3 ) (sec/m 3 ) N A 469 2.51 E-06 8.16E-07 NNE B 475 2.51 E-06 7.26E-07 NE c 400 3.33E-06 1.0SE-06 ENE D 400 2.90E-06 8.87E-07 E E 400 2.97E-06 8.62E-07 ESE F 400 3.17E-06 7.84E-07 SE G 400 3.52E-06 8.35E-07 SSE H 400 2.13E-06 5.70E-07 s J 433 1.98E-06 6.29E-07 SSW K 439 1.78E-06 5.65E-07 SW L 518 1.05E-06 3.39E-07 WSW M 671 5.32E-07 2.17E-07 w N 658 5.42E-07 2.13E-07 WNW p 893 3.58E-07 1.41 E-07 NW Q 847 5.15E-07 2.00E-07 NNW R 725 7.59E-07 3.26E-07 Page 186 of 267
Revision 5 Aug 31, 2015 Table F-6 x!Q and D/Q at the Nearest Resident Locations within 5 miles Mixed Mode (Vent) Site Distance Ground Level Release Release Location Description Direction Sector x!Q D/Q y/Q D/Q miles meters m*;l 3 m*2 sec/m~ sec/m NEAREST RESIDENCE N A 2.49 4000 5.00E-07 7.30E-10 5.60E-08 5.80E-11 NEAREST RESIDENCE NNE B 4.97 8000 2.20E-07 2.20E-10 4.20E-08 2.50E-11 NEAREST RESIDENCE NE c 4.97 8000 2.40E-07 3.1OE-10 5.20E-08 6.40E-11 NEAREST RESIDENCE ENE D 4.97 8000 2.00E-07 2.80E-10 4.80E-08 7.10E-11 NEAREST RESIDENCE E E 4.97 8000 2.40E-07 4.30E-10 6.80E-08 1.40E-10 NEAREST RESIDENCE ESE F 4.97 8000 1.80E-07 3.10E-10 5.50E-08 1.00E-10 NEAREST RESIDENCE SE G 4.97 8000 1.50E-07 2.70E-10 5.20E-08 8.80E-11 NEAREST RESIDENCE SSE H 4.97 8000 1.10E-07 1.70E-10 3.50E-08 5.30E-11 NEAREST RESIDENCE s J 4.97 8000 1.10E-07 2.40E-10 4.20E-08 7.70E-11 NEAREST RESIDENCE SSW K 2.30 3700 3.20E-07 1.20E-09 9.30E-08 4.70E-10 NEAREST RESIDENCE SW L 1.86 3000 3.70E-07 1.20E-09 7.80E-08 3.80E-10 NEAREST RESIDENCE WSW M 1.24 2000 4.70E-07 1.50E-09 5.00E-08 4.20E-10 NEAREST RESIDENCE w N 0.68 1100 1.50E-06 3.70E-09 3.40E-08 5.30E-10 NEAREST RESIDENCE WNW p 1.24 2000 5.20E-07 1.40E-09 4.10E-08 2.20E-10 NEAREST RESIDENCE NW Q 1.24 2000 5.60E-07 1.50E-09 4.20E-08 2.30E-10 NEAREST RESIDENCE NNW R 1.49 2400 6.30E-07 1.90E-09 6.80E-08 4.10E-10 Page 187 of 267
Revision 5 Aug 31, 2015 Table F-6a xtQ and D/Q at the Nearest Cow Milk Locations within 5 miles Distance Ground Level Release Mixed Mode (Vent) Release Site Location xtQ D/Q xtQ D/Q Direction Sector miles meters -L Description sec/m;j m"" sec/m;j m COW MILK N A 4.97 8000 1.90E-07 2.10E-10 4.10E-08 1.90E-11 COW MILK NNE B 4.97 8000 2.20E-07 2.20E-10 4.20E-08 2.50E-11 COW MILK NE c 4.97 8000 2.40E-07 3.10E-10 5.20E-08 6.40E-11 COW MILK ENE D 4.97 8000 2.00E-07 2.80E-10 4.80E-08 7.10E-11 COW MILK E E 4.97 8000 2.40E-07 4.30E-10 6.80E-08 1.40E-10 COW MILK ESE F 4.97 8000 1.80E-07 3.10E-10 5.50E-08 1.00E-10 COW MILK SE G 4.97 8000 1.50E-07 2.70E-10 5.20E-08 8.80E-11 COW MILK SSE H 4.97 8000 1.10E-07 1.70E-10 3.50E-08 5.30E-11 COW MILK s J 4.97 8000 1.10E-07 2.40E-10 4.20E-08 7.70E-11 COW MILK SSW K 4.97 8000 1.00E-07 3.10E-10 4.90E-08 1.40E-10 COW MILK SW L 4.97 8000 8.50E-08 2.20E-10 3.90E-08 8.20E-11 COW MILK WSW M 4.97 8000 5.80E-08 1.30E-10 2.40E-08 5.00E-11 COW MILK w N 4.97 8000 6.90E-08 1.20E-10 2.50E-08 3.40E-11 COW MILK WNW p 4.97 8000 6.60E-08 1.20E-10 2.60E-08 2.70E-11 COW MILK NW Q 4.97 8000 7.10E-08 1.30E-10 2.70E-08 2.90E-11 COW MILK NNW R 4.97 8000 1.1 OE-07 2.20E-10 3.40E-08 5.70E-11 Page 188 of 267
Revision 5 Aug 31, 2015 Table F-6b x!Q and D/Q at the Nearest Cow Milk Locations within 5 miles Mixed Mode (Vent) Distance Ground Level Release Location Release Direction Site Sector Description x!Q D/Q x!Q D/Q miles meters 3 m-2 3 m-2 sec/m sec/m COW MEAT N A 4.97 8000 1.90E-07 2.10E-10 4.10E-08 1.90E-11 COW MEAT NNE B 4.97 8000 2.20E-07 2.20E-10 4.20E-08 2.50E-11 COW MEAT NE c 4.97 8000 2.40E-07 3.10E-10 5.20E-08 6.40E-11 COW MEAT ENE D 4.97 8000 2.00E-07 2.80E-10 4.80E-08 7.10E-11 COW MEAT E E 4.97 8000 2.40E-07 4.30E-10 6.80E-08 1.40E-10 COW MEAT ESE F 4.97 8000 1.80E-07 3.10E-10 5.50E-08 1.00E-10 COW MEAT SE G 4.97 8000 1.50E-07 2.70E-10 5.20E-08 8.80E-11 COW MEAT SSE H 4.97 8000 1.10E-07 1.70E-10 3.50E-08 5.30E-11 COW MEAT s j 4.97 8000 1.10E-07 2.40E-10 4.20E-08 7.70E-11 COW MEAT SSW K 4.97 8000 1.00E-07 3.10E-10 4.90E-08 1.40E-10 COW MEAT SW L 4.97 8000 8.50E-08 2.20E-10 3.90E-08 8.20E-11 COW MEAT WSW M 4.47 7200 6.70E-08 1.60E-10 2.70E-08 6.00E-11 COW MEAT w N 3.48 5600 1.10E-07 2.20E-10 3.30E-08 6.10E-11 COW MEAT WNW p 4.97 8000 6.60E-08 1.20E-10 2.60E-08 2.70E-11 COW MEAT NW Q 4.97 8000 7.10E-08 1.30E-10 2.70E-08 2.90E-11 COW MEAT NNW R 4.97 8000 1.10E-07 2.20E-10 3.40E-08 5.70E-11 Page 189 of 267
Revision 5 Aug31, 2015 Table F-7 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the Unrestricted Area Boundary for Kr-85 Downwind Unrestricted Mixed Mode(Vent) .Release Ground Level Release Direction Area Bound Radius v VBAR Radtus G GBAR (meters) (meters) (mrad/yr)/(uCt/sec) (meters) (mrad/yr)/(uCl/sec) N 469. 469. t .403E-05 1.356E-05 469. 4.313E*05 4. 171E*05 NNE 475. 475. 1.249E-05 1.207£-05 475. 4.315E-05 4. f73E-05 NE 400. 400. 1.803E-05 t.743E-05 400. 5.723E-05 5.534E-05 ENE 400. 400. 1.526E-05 1.476E-05 400. 4.984E-05 4.819E-05 E 400. 400. 1.482E-05 1.433£-05 400. 5.ttOE-05 4.941£-05 ESE 400. 400. 1. 349E-05 1.304£-05 400. 5.450E-05 5.270E-05 SE 400. 400. 1 .436£-05 1.388£-05 400. 6.049£-05 5.849E-05 SSE 400. 400. 9.79BE-06 9.474E-06 400. 3.657E-05 3.536E-05 s 433. 433. 1.082E-05 1.046E-05 . 433. 3.398£-05 3.286£-05 SSW 439. 439. 9.7f5E-06 9.394£-06 439. 3.053£-05 2.952£-05 SW 518. 518. 5.829E-06 5.636E-06 518. 1.805£-05 1. 74.6E-05 WSW 67t. 671. 3.737£-06 3.614E-06 67t. 9.141£-06 8.845£-06 w 658. 658. 3.664E-06 3.543£-06 658. 9.329E-06 9.021E-06 WNW 893. 893. 2.425E-06 2.345£-06 893. 6.158£*06 5.955E-06 NW 847. 847. 3.444£-06 3.330£-06 847. 8.861£-06 8.S69E*06 NNW 725. 725. *s.60tE-06 5.416£-06 725. t .305E-05 1.262£-05 Zion Stte Meteorological Data 1/79 - 12/87 Page 190 of 267
Revision 5 Aug 31, 2015 Table F-8 Site Specific Potable Water Dose Factors for Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 8.31 E-01 8.31 E-01 8.31 E-01 8.31E-01 8.31E-01 8.31E-01 Na-24 2.36E+01 2.36E+01 2.36E+01 2.36E+01 2.36E+01 2.36E+01 2.36E+01 Cr-51 O.OOE+OO O.OOE+OO 3.69E-02 2.21 E-02 8.13E-03 4.90E-02 9.28E+OO Mn-54 O.OOE+OO 6.34E+01 1.21E+01 O.OOE+OO 1.89E+01 O.OOE+OO 1.94E+02 Mn-56 O.OOE+OO 1.60E+OO 2.83E-01 O.OOE+OO 2.03E+OO O.OOE+OO 5.09E+01 Fe-55 3.81E+01 2.64E+01 6.14E+OO O.OOE+OO O.OOE+OO 1.47E+01 1.51E+01 Fe-59 6.02E+01 1.41E+02 5.42E+01 O.OOE+OO O.OOE+OO 3.95E+01 4.72E+02 Co-58 O.OOE+OO 1.03E+01 2.32E+01 O.OOE+OO O.OOE+OO O.OOE+OO 2.09E+02 Co-60 O.OOE+OO 2.97E+01 6.55E+01 O.OdE+OO O.OOE+OO O.OOE+OO 5.58E+02 Ni-63 1.80E+03 1.25E+02 6.05E+01 O.OOE+OO O.OOE+OO O.OOE+OO 2.61 E+01 Ni-65 7.32E+OO 9.51 E-01 4.34E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.41E+01 Cu-64 O.OOE+OO 1.16E+OO 5.42E-01 O.OOE+OO 2.91E+OO O.OOE+OO 9.85E+01 Zn-65 6.71 E+01 2.14E+02 9.65E+01 O.OOE+OO 1.43E+02 O.OOE+OO 1.35E+02 Zn-69 1.43E-01 2.73E-01 1.90E-02 O.OOE+OO 1.78E-01 O.OOE+OO 4.11 E-02 Br-83 O.OOE+OO O.OOE+OO 5.58E-01 O.OOE+OO O.OOE+OO O.OOE+OO 8.03E-01 Br-84 O.OOE+OO O.OOE+OO 7.23E-01 O.OOE+OO O.OOE+OO O.OOE+OO 5.67E-06 Br-85 O.OOE+OO O.OOE+OO 2.97E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.93E+02 1.36E+02 O.OOE+OO O.OOE+OO O.OOE+OO 5.77E+01 Rb-88 O.OOE+OO 8.39E-01 4.45E-01 O.OOE+OO O.OOE+OO O.OOE+OO 1.16E-11 Rb-89 O.OOE+OO 5.56E-01 3.91E-01 O.OOE+OO O.OOE+OO O.OOE+OO 3.23E-14 Sr-89 4.27E+03 O.OOE+OO 1.23E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.85E+02 Sr-90 1.21 E+05 O.OOE+OO 2.43E+03 O.OOE+OO O.OOE+OO O.OOE+OO 3.04E+03 Sr-91 7.86E+01 O.OOE+OO 3.18E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.74E+02 Sr-92 2.98E+01 O.OOE+OO 1.29E+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.91E+02 Y-90 1.33E-01 O.OOE+OO 3.58E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.41E+03 Y-91M 1.26E-03 O.OOE+OO 4.88E-05 O.OOE+OO O.OOE+OO O.OOE+OO 3.70E-03 Y-91 1.96E+OO O.OOE+OO 5.23E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.08E+03 Y-92 1.17E-02 O.OOE+OO 3.43E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.05E+02 Y-93 3.72E-02 O.OOE+OO 1.03E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.18E+03 Zr-95 4.22E-01 1.35E-01 9.15E-02 O.OOE+OO 2.12E-01 O.OOE+OO 4.29E+02 Zr-97 2.33E-02 4.70E-03 2.15E-03 O.OOE+OO 7.10E-03 O.OOE+OO 1.46E+03 Nb-95 8.63E-02 4.80E-02 2.58E-02 O.OOE+OO 4.74E-02 O.OOE+OO 2.91E+02 Mo-99 O.OOE+OO 5.98E+01 1.14E+01 O.OOE+OO 1.35E+02 O.OOE+OO 1.39E+02 Tc-99M 3.43E-03 9.68E-03 1.23E-01 O.OOE+OO 1.47E-01 4.74E-03 5.73E+OO i"c-101 3.52E-03 5.08E-03 4.98E-02 O.OOE+OO 9.14E-02 2.59E-03 1.53E-14 Ru-103 2.57E+OO O.OOE+OO 1.11E+OO O.OOE+OO 9.79E+OO O.OOE+OO 3.00E+02 Ru-105 2.14E-01 O.OOE+OO 8.43E-02 O.OOE+OO 2.76E+OO O.OOE+OO 1.31 E+02 Ru-106 3.81E+01 O.OOE+OO 4.83E+OO O.OOE+OO 7.36E+01 O.OOE+OO 2.47E+03 Ag-110M 2.22E+OO 2.05E+OO 1.22E+OO O.OOE+OO 4.04E+OO O.OOE+OO 8.38E+02 Te-125M 3.72E+01 1.35E+01 4.98E+OO 1.12E+01 1.51E+02 O.OOE+OO 1.48E+02 Page 191 of 267
Revision 5 Aug 31, 2015 Table F-8 (continued) Site Specific Potable Water Dose Factors for Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-127M 9.39E+01 3.36E+01 1.14E+01 2.40E+01 3.81E+02 O.OOE+OO 3.15E+02 Te-127 1.53E+OO 5.48E-01 3.30E-01 1.13E+OO 6.21E+OO O.OOE+OO 1.20E+02 Te-129M 1.60E+02 5.95E+01 2.52E+01 5.48E+01 6.66E+02 O.OOE+OO 8.03E+02 Te-129 4.36E-01 1.64E-01 1.06E-01 3.34E-01 1.83E+OO O.OOE+OO 3.29E-01 Te-131M 2.40E+01 1.17E+01 9.78E+OO 1.86E+01 1.19E+02 O.OOE+OO 1.17E+03 Te-131 2.73E-01 1.14E-01 8.63E-02 2.25E-01 1..20E+OO O.OOE+OO 3.87E-02 Te-132 3.50E+01 2.26E+01 2.12E+01 2.50E+01 2.18E+02 O.OOE+OO 1.07E+03 1-130 1.05E+01 3.09E+01 1.22E+01 2.62E+03 4.83E+01 O.OOE+OO 2.66E+01 1-131 5.77E+01 8.25E+01 4.73E+01 2.70E+04 1.41E+02 O.OOE+OO 2.18E+01 1-132 2.82E+OO 7.53E+OO 2.64E+OO 2.64E+02 1.20E+01 O.OOE+OO 1.41 E+OO 1-133 1.97E+01 3.43E+01 1.04E+01 5.03E+03 5.98E+01 O.OOE+OO 3.08E+01 1-134 1.47E+OO 3.99E+OO 1.43E+OO 6.92E+01 6.35E+OO O.OOE+OO 3.48E-03 1-135 6.14E+OO 1.61 E+01 5.94E+OO 1.06E+03 2.58E+01 O.OOE+OO 1.82E+01 Cs-134 8.63E+02 2.05E+03 1.68E+03 O.OOE+OO 6.64E+02 2.21E+02 3.59E+01 Cs-136 9.03E+01 3.56E+02 2.57E+02 O.OOE+OO 1.98E+02 2.72E+01 4.05E+01 Cs-137 1.11E+03 1.51 E+03 9.90E+02 O.OOE+OO 5.13E+02 1.71 E+02 2.93E+01 Cs-138 7.66E-01 1.51 E+OO 7.49E-01 O.OOE+OO 1.11 E+OO 1.10E-01 6.45E-06 Ba-139 1.35E+OO 9.58E-04 3.94E-02 O.OOE+OO 8.96E-04 5.44E-04 2.39E+OO Ba-140 2.82E+02 3.54E-01 1.84E+01 O.OOE+OO 1.20E-01 2.03E-01 5.80E+02 Ba-141 6.53E-01 4.94E-04 2.21 E-02 O.OOE+OO 4.59E-04 2.80E-04 3.08E-10 Ba-142 2.95E-01 3.04E-04 1.86E-02 O.OOE+OO 2.57E-04 1.72E-04 4.16E-19 La-140 3.47E-02 1.75E-02 4.62E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.28E+03 La-142 1.78E-03 8.07E-04 2.01 E-04 O.OOE+OO O.OOE+OO O.OOE+OO 5.89E+OO Ce-141 1.30E-01 8.78E-02 9.96E-03 O.OOE+OO 4.08E-02 O.OOE+OO 3.36E+02 Ce-143 2.29E-02 1.69E+01 1.87E-03 O.OOE+OO 7.45E-03 O.OOE+OO 6.32E+02 Ce-144 6.77E+OO 2.83E+OO 3.63E-01 O.OOE+OO 1.68E+OO O.OOE+OO 2.29E+03 Pr-143 1.28E-01 5.12E-02 6.32E-03 O.OOE+OO 2.95E-02 O.OOE+OO 5.59E+02 Pr-144 4.17E-04 1.73E-04 2.12E-05 O.OOE+OO 9.78E-05 O.OOE+OO 6.01 E-11 Nd-147 8.72E-02 1.01 E-01 6.03E-03 O.OOE+OO 5.89E-02 O.OOE+OO 4.84E+02 W-187 1.43E+OO 1.19E+OO 4.17E-01 O.OOE+OO O.OOE+OO O.OOE+OO 3.91E+02 Np-239 1.65E-02 1.62E-03 8.95E-04 O.OOE+OO 5.06E-03 O.OOE+OO 3.33E+02 Notes:
- 1) Units are mrem/hr per µCi/ml.
Page 192 of 267
Revision 5 Aug 31, 2015 Table F-8a Site Specific Potable Water Dose Factors for Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 5.85E-01 5.85E-01 5.85E-01 5.85E-01 5.85E-01 5.85E-01 Na-24 2.23E+01 2.23E+01 2.23E+01 2.23E+01 2.23E+01 2.23E+01 2.23E+01 Cr-51 O.OOE+OO O.OOE+OO 3.49E-02 1.94E-02 7.65E-03 4.98E-02 5.86E+OO Mn-54 O.OOE+OO 5.72E+01 1.13E+01 O.OOE+OO 1.71 E+01 O.OOE+OO 1.17E+02 Mn-56 O.OOE+OO 1.53E+OO 2.72E-01 O.OOE+OO 1.94E+OO O.OOE+OO 1.01 E+02 Fe-55 3.66E+01 2.60E+01 6.06E+OO O.OOE+OO O.OOE+OO 1.65E+01 1.12E+01 Fe-59 5.69E+01 1.33E+02 5.13E+01 O.OOE+OO O.OOE+OO 4.19E+01 3.14E+02 Co-58 O.OOE+OO 9.42E+OO 2.17E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.30E+02 Co-60 O.OOE+OO 2.72E+01 6.13E+01 O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+02 Ni-63 1.72E+03 1.21E+02 5.81E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.93E+01 Ni-65 7.26E+OO 9.27E-01 4.22E-01 O.OOE+OO O.OOE+OO O.OOE+OO 5.03E+01 Cu-64 O.OOE+OO 1.11 E+OO 5.24E-01 O.OOE+OO 2.82E+OO O.OOE+OO 8.64E+01 Zn-65 5.58E+01 1.94E+02 9.04E+01 O.OOE+OO 1.24E+02 O.OOE+OO 8.21 E+01 Zn-69 1.42E-01 2.71 E-01 1.90E-02 O.OOE+OO 1.77E-01 O.OOE+OO 5.00E-01 Br-83 O.OOE+OO O.OOE+OO 5.56E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 7.00E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 2.96E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.89E+02 1.36E+02 O.OOE+OO O.QOE+OO O.OOE+OO 4.27E+01 Rb-88 O.OOE+OO 8.26E-01 4.40E-01 O.OOE+OO O.OOE+OO O.OOE+OO 7.07E-08 Rb-89 O.OOE+OO 5.33E-01 3.77E-01 O.OOE+OO O.OOE+OO O.OOE+OO 8.17E-10 Sr-89 4.26E+03 O.OOE+OO 1.22E+02 O.OOE+OO O.OOE+OO O.OOE+OO 5.08E+02 Sr-90 9.88E+04 O.OOE+OO 1.98E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.26E+03 Sr-91 7.82E+01 O.OOE+OO 3.11 E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+02 Sr-92 2.96E+01 O.OOE+OO 1.26E+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.53E+02 Y-90 1.33E-01 O.OOE+OO 3.58E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.09E+03 Y-91M 1.25E-03 O.OOE+OO. 4.78E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.90E-02 Y-91 1.95E+OO O.OOE+OO 5.22E-02 O.OOE+OO O.OOE+OO O.OOE+OO 7.98E+02 Y-92 1.17E-02 O.OOE+OO 3.39E-04 O.OOE+OO O.OOE+OO O.OOE+OO 3.22E+02 Y-93 3.71E-02 O.OOE+OO 1.02E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.13E+03 Zr-95 3.99E-01 1.26E-01 8.66E-02 O.OOE+OO 1.85E-01 O.OOE+OO 2.91E+02 Zr-97 2.30E-02 4.54E-03 2.09E-03 O.OOE+OO 6.89E-03 O.OOE+OO 1.23E+03 Nb-95 7.97E-02 4.42E-02 2.43E-02 O.OOE+OO 4.28E-02 O.OOE+OO 1.89E+02 Mo-99 O.OOE+OO 5.84E+01 1.11 E+01 O.OOE+OO 1.34E+02 O.OOE+OO 1.05E+02 Tc- 99M 3.22E-03 8.97E-03 1.16E-01 O.OOE+OO 1.34E-01 4.98E-03 5.89E+OO Tc-101 3.49E-03 4.96E-03 4.87E-02 O.OOE+OO 8.97E-02 3.02E-03 8.48E-10 Ru-103 2.47E+OO O.OOE+OO 1.06E+OO O.OOE+OO 8.71E+OO O.OOE+OO 2.06E+02 Ru-105 2.11 E-01 O.OOE+OO 8.20E-02 O.OOE+OO 2.66E+OO O.OOE+OO 1.71 E+02 Ru-106 3.80E+01 O.OOE+OO 4.79E+OO O.OOE+OO 7.33E+01 O.OOE+OO 1.82E+03 Ag-110M 1.99E+OO 1.88E+OO 1.14E+OO O.OOE+OO 3.59E+OO O.OOE+OO 5.28E+02 Te-125M 3.71 E+01 1.34E+01 4.96E+OO 1.04E+01 O.OOE+OO O.OOE+OO 1.09E+02 Page 193 of 267
Revision 5 Aug 31, 2015 Table F-Ba (continued) Site Specific Potable Water Dose Factors for Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-127M 9.37E+01 3.32E+01 1.11 E+01 2.23E+01 3.80E+02 O.OOE+OO 2.34E+02 Te-127 1.53E+OO 5.43E-01 3.29E-01 1.06E+OO 6.20E+OO O.OOE+OO 1.18E+02 Te-129M 1.58E+02 5.86E+01 2.50E+01 5.10E+01 6.61E+02 O.OOE+OO 5.93E+02 Te-129 4.34E-01 1.62E-01 1.06E-01 3.1 OE-01 1.82E+OO O.OOE+OO 2.37E+OO Te-131 M 2.36E+01 1.13E+01 9.46E+OO 1.71E+01 1.18E+02 O.OOE+OO 9.10E+02 Te-131 2.70E-01 1.11 E-01 8.45E-02 2.08E-01 1.18E+OO O.OOE+OO 2.22E-02 Te-132 3.38E+01 2.14E+01 2.02E+01 2.26E+01 2.05E+02 O.OOE+OO 6.78E+02 1-130 9.98E+OO 2.89E+01 1.15E+01 2.35E+03 4.45E+01 O.OOE+OO 2.22E+01 1-131 5.67E+01 7.94E+01 4.26E+01 2.32E+04 1.37E+02 O.OOE+OO 1.57E+01 1-132 2.70E+OO 7.07E+OO 2.54E+OO 2.38E+02 1.11 E+01 O.OOE+OO 3.08E+OO 1-133 1.95E+01 3.30E+01 1.01E+01 4.61E+03 5.79E+01 O.OOE+OO 2.50E+01 1-134 1.41E+OO 3.75E+OO 1.35E+OO 6.25E+01 5.91E+OO O.OOE+OO 4.94E-02 1-135 5.91E+OO 1.52E+01 5.64E+OO 9.79E+02 2.40E+01 O.OOE+OO 1.69E+01 Cs-134 8.11E+02 1.91 E+03 8.86E+02 O.OOE+OO 6.07E+02 2.32E+02 2.37E+01 Cs-136 8.32E+01 3.28E+02 2.20E+02 O.OOE+OO 1.78E+02 2.81 E+01 2.64E+01 Cs-137 1.09E+03 1.44E+03 5.03E+02 O.OOE+OO 4.91E+02 1.91E+02 2.05E+01 Cs-138 7.52E-01 1.44E+OO 7.22E-01 O.OOE+OO 1.07E+OO 1.24E-01 6.55E-04 Ba-139 1.35E+OO 9.48E-04 3.92E-02 O.OOE+OO 8.93E-04 6.53E-04 1.20E+01 Ba-140 2.75E+02 3.37E-01 1.77E+01 O.OOE+OO 1.14E-01 2.27E-01 4.24E+02 Ba-141 6.50E-01 4.85E-04 2.17E-02 O.OOE+OO 4.51E-04 3.32E-04 1.39E-06 Ba-142 2.90E-01 2.90E-04 1.78E-02 O.OOE+OO 2.45E-04 . 1.93E-04 8.90E-13 La-140 3.37E-02 1.66E-02 4.41 E-03 O.OOE+OO O.OOE+OO O.OOE+OO 9.52E+02 La-142 1.73E-03 7.70E-04 1.92E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.34E+01 Ce-141 1.29E-01 8.60E-02 9.88E-03 O.OOE+OO 4.05E-02 O.OOE+OO 2.46E+02 Ce-143 2.28E-02 1.66E+01 1.85E-03 O.OOE+OO 7.43E-03 O.OOE+OO 4.98E+02 Ce-144 6.74E+OO 2.79E+OO 3.62E-01 O.OOE+OO 1.67E+OO O.OOE+OO 1.70E+03 Pr-143 1.27E-01 5.07E-02 6.32E-03 O.OOE+OO 2.95E-02 O.OOE+OO 4.18E+02 Pr-144 4.17E-04 1.71 E-04 2.11 E-05 O.OOE+OO 9.79E-05 O.OOE+OO 4.59E-07 Nd-147 9.09E-02 9.88E-02 5.92E-03 O.OOE+OO 5.80E-02 O.OOE+OO 3.57E+02 W-187 1.41E+OO 1.15E+OO 4.04E-01 O.OOE+OO O.OOE+OO O.OOE+OO 3.12E+02 Np-239 1.71E-02 1.61E-03 8.93E-04 O.OOE+OO 5.05E-03 O.OOE+OO 2.59E+02 Notes:
- 1) Units are mrem/hr per µCi/ml.
Page 194 of 267
Revision 5 Aug 31, 2015 Table F-Bb Site Specific Potable Water Dose Factors for Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO Na-24 5.62E+01 5.62E+01 5.62E+01 5.62E+01 5.62E+01 5.62E+01 5.62E+01 Cr-51 O.OOE+OO O.OOE+OO 8.62E-02 4.79E-02 1.31E-02 8.74E-02 4.57E+OO Mn-54 O.OOE+OO 1.04E+02 2.76E+01 O.OOE+OO 2.91E+01 O.OOE+OO 8.70E+01 Mn-56 O.OOE+OO 3.24E+OO 7.31 E-01 O.OOE+OO 3.91E+OO O.OOE+OO 4.69E+02 Fe-55 1.11E+02 5.91E+01 1.83E+01 O.OOE+OO O.OOE+OO 3.34E+01 1.09E+01 Fe-59 1.60E+02 2.59E+02 1.29E+02 O.OOE+OO O.OOE+OO 7.50E+01 2.69E+02 Co-58 O.OOE+OO 1.74E+01 5.34E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E+02 Co-60 O.OOE+OO 5.13E+01 1.51 E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.84E+02 Ni-63 5.21E+03 2.79E+02 1.77E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.88E+01 Ni-65 2.15E+01 2.03E+OO 1.18E+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.48E+02 Cu-64 O.OOE+OO 2.37E+OO 1.43E+OO O.OOE+OO 5.74E+OO O.OOE+OO 1.11 E+02 Zn-65 1.33E+02 3.54E+02 2.20E+02 O.OOE+OO 2.23E+02 O.OOE+OO 6.21 E+01 Zn-69 4.24E-01 6.13E-01 5.67E-02 O.OOE+OO 3.72E-01 O.OOE+OO 3.87E+01 Br-83 O.OOE+OO O.OOE+OO 1.66E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 1.92E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 8.84E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 6.49E+02 3.99E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.18E+01 Rb-88 O.OOE+OO 1.84E+OO 1.28E+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.03E-02 Rb-89 O.OOE+OO 1.13E+OO 1.01 E+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.88E-03 Sr-89 1.28E+04 O.OOE+OO 3.65E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.95E+02 Sr-90 2.48E+05 O.OOE+OO 4.99E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.22E+03 Sr-91 2.33E+02 O.OOE+OO 8.78E+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.14E+02 Sr-92 8.75E+01 O.OOE+OO 3.51E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.66E+03 Y-90 3.98E-01 O.OOE+OO 1.07E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.13E+03 Y-91M 3.70E-03 O.OOE+OO 1.35E-04 O.OOE+OO O.OOE+OO O.OOE+OO 7.25E+OO Y-91 5.83E+OO O.OOE+OO 1.56E-01 O.OOE+OO O.OOE+OO O.OOE+OO 7.77E+02 Y-92 3.49E-02 O.OOE+OO 9.98E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.01 E+03 Y-93 1.10E-01 O.OOE+OO 3.03E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.65E+03 Zr-95 1.12E+OO 2.47E-01 2.20E-01 O.OOE+OO 3.54E-01 O.OOE+OO 2.58E+02 Zr-97 6.77E-02 9.79E-03 5.78E-03 O.OOE+OO 1.41 E-02 O.OOE+OO 1.48E+03 Nb-95 2.18E-01 8.49E-02 6.07E-02 O.OOE+OO 7.97E-02 O.OOE+OO 1.57E+02 Mo-99 O.OOE+OO 1.29E+02 3.19E+01 O.OOE+OO 2.75E+02 O.OOE+OO 1.07E+02 Tc- 99M 8.94E-03 1.75E-02 2.91 E-01 O.OOE+OO 2.55E-01 8.91E-03 9.98E+OO Tc-101 1.04E-02 1.09E-02 1.38E-01 O.OOE+OO 1.85E-01 5.74E-03 3.45E-02 Ru-103 7.08E+OO O.OOE+OO 2.72E+OO O.OOE+OO 1.78E+01 O.OOE+OO 1.83E+02 Ru-105 6.25E-01 O.OOE+OO 2.27E-01 O.OOE+OO 5.49E+OO O.OOE+OO 4.08E+02 Ru-106 1.13E+02 O.OOE+OO 1.41 E+01 O.OOE+OO 1.53E+02 O.OOE+OO 1.76E+03 Ag-110M 5.22E+OO 3.53E+OO 2.82E+OO O.OOE+OO 6.57E+OO O.OOE+OO 4.20E+02 Te-125M 1.10E+02 2.99E+01 1.47E+01 3.10E+01 O.OOE+OO O.OOE+OO 1.0?E+02 Page 195 of 267
Revision 5 Aug 31, 2015 Table F-8b (continued) Site Specific Potable Water Dose Factors for Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-127M 2.80E+02 7.54E+01 3.32E+01 6.70E+01 7.98E+02 O.OOE+OO 2.27E+02 Te-127 4.56E+OO 1.23E+OO 9.79E-01 3.16E+OO 1.30E+01 O.OOE+OO 1.78E+02 Te-129M 4.72E+02 1.32E+02 7.33E+01 1.52E+02 1.39E+03 O.OOE+OO 5.76E+02 Te-129 1.30E+OO 3.62E-01 3.08E-01 9.26E-01 3.80E+OO O.OOE+OO 8.08E+01 Te-131M 6.98E+01 2.41E+01 2.57E+01 4.96E+01 2.34E+02 O.OOE+OO 9.79E+02 Te-131 8.04E-01 2.45E-01 2.39E-01 6.15E-01 2.43E+OO O.OOE+OO 4.22E+OO Te-132 9.79E+01 4.33E+01 5.23E+01 6.31E+01 4.02E+02 O.OOE+OO 4.36E+02 1-130 2.83E+01 5.72E+01 2.95E+01 6.30E+03 8.55E+01 O.OOE+OO 2.67E+01 1-131 1.67E+02 1.68E+02 9.53E+01 5.54E+04 2.75E+02 O.OOE+OO 1.49E+01 1-132 7.75E+OO 1.42E+01 6.55E+OO 6.61E+02 2.18E+01 O.OOE+OO 1.68E+01 1-133 5.74E+01 7.09E+01 2.68E+01 1.32E+04 1.18E+02 O.OOE+OO 2.86E+01 1-134 4.06E+OO 7.54E+OO 3.47E+OO 1.73E+02 1.15E+01 O.OOE+OO 5.00E+OO 1-135 1.70E+01 3.05E+01 1.44E+01 2.70E+03 4.68E+01 O.OOE+OO 2.33E+01 Cs-134 2.27E+03 3.72E+03 7.85E+02 O.OOE+OO 1.15E+03 4.14E+02 2.01E+01 Cs-136 2.28E+02 6.26E+02 4.05E+02 O.OOE+OO 3.33E+02 4.97E+01 2.20E+01 Cs-137 3.17E+03 3.03E+03 4.48E+02 O.OOE+OO 9.88E+02 3.56E+02 1.90E+01 Cs-138 2.21E+OO 3.07E+OO 1.95E+OO O.OOE+OO 2.16E+OO 2.33E-01 1.41 E+OO Ba-139 4.01E+OO 2.14E-03 1.16E-01 O.OOE+OO 1.87E-03 1.26E-03 2.32E+02 Ba-140 8.05E+02 7.05E-01 4.70E+01 O.OOE+OO 2.30E-01 4.21E-01 4.08E+02 Ba-141 1.94E+OO 1.09E-03 6.31E-02 O.OOE+OO 9.39E-04 6.38E-03 1.10E+OO Ba-142 8.47E-01 6.10E-04 4.73E-02 O.OOE+OO 4.93E-04 3.59E-04 1.10E-02 La-140 9.79E-02 3.42E-02 1.15E-02 O.OOE+OO O.OOE+OO O.OOE+OO 9.53E+02 La-142 5.08E-03 1.62E-03 5.07E-04 O.OOE+OO O.OOE+OO O.OOE+OO 3.21E+02 Ce-141 3.85E-01 1.92E-01 2.85E-02 O.OOE+OO 8.41 E-02 O.OOE+OO 2.39E+02 Ce-143 6.77E-02 3.67E+01 5.32E-03 O.OOE+OO 1.54E-02 O.OOE+OO 5.38E+02 Ce-144 2.02E+01 6.32E+OO 1.08E+OO O.OOE+OO 3.50E+OO O.OOE+OO 1.65E+03 Pr-143 3.81E-01 1.14E-01 1.89E-02 O.OOE+OO 6.19E-02 O.OOE+OO 4.11 E+02 Pr-144 1.25E-03 3.87E-04 6.29E-05 O.OOE+OO 2.04E-04 O.OOE+OO 8.32E-01 Nd-147 2.70E-01 2.19E-01 1.70E-02 O.OOE+OO 1.20E-01 O.OOE+OO 3.47E+02 W-187 4.16E+OO 2.46E+OO 1.10E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.46E+02 Np-239 5.09E-02 3.65E-03 2.57E-03 O.OOE+OO 1.06E-02 O.OOE+OO 2.70E+02 Notes:
- 1) Units are mrem/hr per µCi/ml.
Page 196 of 267
Revision 5 Aug 31, 2015 Table F-Bc Site Specific Potable Water Dose Factors for Infant Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.10E+OO 1.10E+OO 1.10E+OO 1.10E+OO 1.10E+OO 1.10E+OO Na-24 6.33E+01 6.33E+01 6.33E+01 6.33E+01 6.33E+01 6.33E+01 6.33E+01 Cr-51 O.OOE+OO O.OOE+OO 8.84E-02 5.77E-02 1.26E-02 1.12E-01 2.58E+OO Mn-54 O.OOE+OO 1.25E+02 2.83E+01 O.OOE+OO 2.77E+01 O.OOE+OO 4.58E+01 Mn-56 O.OOE+OO 5.13E+OO 8.84E-01 O.OOE+OO 4.41E+OO O.OOE+OO 4.66E+02 Fe-55 8.72E+01 5.63E+01 1.50E+01 O.OOE+OO O.OOE+OO 2.75E+01 7.15E+OO Fe-59 1.93E+02 3.37E+02 1.33E+02 O.OOE+OO O.OOE+OO 9.97E+01 1.61 E+02 Co-58 O.OOE+OO 2.26E+01 5.63E+01 O.OOE+OO O.OOE+OO O.OOE+OO 5.62E+01 Co-60 O.OOE+OO 6.77E+01 1.60E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.61 E+02 Ni-63 3.98E+03 2.46E+02 1.38E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.22E+01 Ni-65 2.95E+01 3.34E+OO 1.52E+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.54E+02 Cu-64 O.OOE+OO 3.82E+OO 1.77E+OO O.OOE+OO 6.46E+OO O.OOE+OO 7.84E+01 Zn-65 1.15E+02 3.96E+02 1.82E+02 O.OOE+OO 1.92E+02 O.OOE+OO 3.34E+02 Zn-69 5.85E-01 1.05E+OO 7.84E-02 O.OOE+OO 4.38E-01 O.OOE+OO 8.59E+01 Br-83 O.OOE+OO O.OOE+OO 2.28E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 2.40E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 1.22E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.07E+03 5.27E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.73E+01 Rb-88 O.OOE+OO 3.12E+OO 1.71 E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.04E+OO Rb-89 O.OOE+OO 1.79E+OO 1.24E+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.11 E-01 Sr-89 1.57E+04 O.OOE+OO 4.51E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.24E+02 Sr-90 1.77E+05 O.OOE+OO 3.60E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.45E+03 Sr-91 3.14E+02 O.OOE+OO 1.13E+01 O.OOE+OO O.OOE+OO O.OOE+OO 3.71E+02 Sr-92 1.20E+02 O.OOE+OO 4.47E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.30E+03 Y-90 5.45E-01 O.OOE+OO 1.46E-02 O.OOE+OO O.OOE+OO O.OOE+OO 7.52E+02 Y-91M 5.08E-03 O.OOE+OO 1.73E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.69E+01 Y-91 7.09E+OO O.OOE+OO 1.89E-01 O.OOE+OO O.OOE+OO O.OOE+OO 5.08E+02 Y-92 4.80E-02 O.OOE+OO 1.35E-03 O.OOE+OO O.OOE+OO O.OOE+OO 9.15E+02 Y-93 1.52E-01 O.OOE+OO 4.15E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.20E+03 Zr-95 1.29E+OO 3.15E-01 2.23E-01 O.OOE+OO 3.39E-01 O.OOE+OO 1.57E+02 Zr-97 9.28E-02 1.59E-02 7.27E-03 O.OOE+OO 1.61E-02 O.OOE+OO 1.02E+03 Nb-95 2.63E-01 1.08E-01 6.27E-02 O.OOE+OO 7.77E-02 O.OOE+OO 9.15E+01 Mo-99 O.OOE+OO 2.13E+02 4.16E+01 O.OOE+OO 3.19E+02 O.OOE+OO 7.02E+01 Tc- 99M 1.20E-02 2.48E-02 3.20E-01 O.OOE+OO 2.67E-01 1.30E-02 7.21E+OO Tc-101 1.42E-02 1.79E-02 1.77E-01 O.OOE+OO 2.13E-01 9.78E-03 3.05E+OO Ru-103 9.28E+OO O.OOE+OO 3.10E+OO O.OOE+OO 1.93E+01 O.OOE+OO 1.13E+02 Ru-105 8.53E-01 O.OOE+OO 2.87E-01 O.OOE+QO 6.27E+OO O.OOE+OO 3.39E+02 Ru-106 1.51 E+02 O.OOE+OO 1.89E+01 O.OOE+OO 1.79E+02 O.OOE+OO 1.15E+03 Ag-110M 6.24E+OO 4.56E+OO 3.02E+OO O.OOE+OO 6.52E+OO O.OOE+OO 2.36E+02 Te-125M 1.46E+02 4.88E+01 1.98E+01 4.92E+01 O.OOE+OO O.OOE+OO 6.96E+01 Page 197 of 267
Revision 5 Aug 31, 2015 Table F-Bc (continued) Site Specific Potable Water Dose Factors for Infant Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-127M 3.67E+02 1.22E+02 4.44E+01 1.06E+02 9.03E+02 O.OOE+OO 1.48E+02 Te-127 6.27E+OO 2.10E+OO 1.35E+OO 5.10E+OO 1.53E+01 O.OOE+OO 1.32E+02 Te~129M 6.27E+02 2.15E+02 9.66E+01 2.41E+02 1.57E+03 O.OOE+OO 3.74E+02 Te-129 1.78E+OO 6.14E-01 4.16E-01 1.49E+OO 4.43E+OO O.OOE+OO 1.42E+02 Te-131M 9.53E+01 3.84E+01 3.17E+01 7.77E+01 2.64E+02 O.OOE+OO 6.46E+02 Te-131 1.10E+OO 4.08E-01 3.10E-01 9.84E-01 2.82E+OO O.OOE+OO 4.46E+01 Te-132 1.30E+02 6.46E+01 6.03E+01 9.53E+01 4.04E+02 O.OOE+OO 2.39E+02 1-130 3.76E+01 8.28E+01 3.32E+01 9.28E+03 9.09E+01 O.OOE+OO 1.77E+01 1-131 2.25E+02 2.65E+02 1.17E+02 8.72E+04 3.10E+02 O.OOE+OO 9.47E+OO 1-132 1.04E+01 2.11 E+01 7.52E+OO 9.91E+02 2.36E+01 O.OOE+OO 1.71 E+01 1-133 7.84E+01 1.14E+02 3.34E+01 2.08E+04 1.34E+02 O.OOE+OO 1.93E+01 1-134 5.45E+OO 1.12E+01 3.97E+OO 2.60E+02 1.25E+01 O.OOE+OO 1.15E+01 1-135 2.28E+01 4.54E+01 1.66E+01 4.07E+03 5.06E+01 O.OOE+OO 1.64E+01 Cs-134 2.36E+03 4.41E+03 4.45E+02 O.OOE+OO 1.13E+03 4.65E+02
- 1.20E+01 Cs-136 2.88E+02 8.46E+02 3.16E+02 O.OOE+OO 3.37E+02 6.90E+01 1.29E+01 Cs-137 3.27E+03 3.83E+03 2.71E+02 O.OOE+OO 1.03E+03 4.16E+02 1.20E+01 Cs-138 3.02E+OO 4.90E+OO 2.38E+OO O.OOE+OO 2.45E+OO 3.82E-01 7.84E+OO Ba-139 5.52E+OO 3.66E-03 1.60E-01 O.OOE+OO 2.20E-03 2.22E-03 3.50E+02 Ba-140 1.07E+03 1.07E+OO 5.52E+01 O.OOE+OO 2.55E-01 6.58E-01 2.63E+02 Ba-141 2.66E+OO 1.82E-03 8.40E-02 O.OOE+OO 1.10E-03 1.11 E-03 3.25E+01 Ba-142 1.15E+OO 9.59E-04 5.68E-02 O.OOE+OO 5.52E-04 5.81 E-04 4.76E+OO La-14_0 1.32E-01 5.22E-02 1.34E-02 O.OOE+OO O.OOE+OO O.OOE+OO 6.13E+02 La-142 6.90E-03 2.53E-03 6.06E-04 O.OOE+OO O.OOE+OO O.OOE+OO 4.30E+02 Ce-141 4.93E-01 3.01 E-01 3.54E-02 O.OOE+OO 9.28E-02 O.OOE+OO 1.55E+02 Ce-143 9.28E-02 6.16E+01 7.02E-03 O.OOE+OO 1.79E-02 O.OOE+OO 3.59E+02 Ce-144 1.87E+01 7.65E+OO 1.05E+OO O.OOE+OO 3.09E+OO O.OOE+OO 1.07E+03 Pr-143 5.10E-01 1.91 E-01 2.53E-02 O.OOE+OO 7.09E-02 O.OOE+OO 2.69E+02 Pr-144 1.72E-03 6.65E-04 8.65E-05 O.OOE+OO 2.41 E-04 O.OOE+OO 3.09E+01 Nd-147 3.47E-01 3.56E-01 2.18E-02 O.OOE+OO 1.37E-01 O.OOE+OO 2.26E+02 W-187 5.66E+OO 3.94E+OO 1.36E+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.31E+02 Np-239 6.96E-02 6.23E-03 3.52E-03 O.OOE+OO 1.24E-02 O.OOE+OO 1.80E+02 Notes:
- 1) Units are mrem/hr per µCi/ml.
Page 198 of 267
Revision 5 Aug 31, 2015 Table F-9 Site Specific Fish Ingestion Dose Factors for Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.29E-01 Na-24 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 Cr-51 O.OOE+OO O.OOE+OO 1.27E+OO 7.61 E-01 2.81 E-01 1.69E+OO 3.20E+02 Mn-54 O.OOE+OO 4.38E+03 8.35E+02 O.OOE+OO 1.30E+03 O.OOE+OO 1.34E+04 Mn-56 O.OOE+OO 1.10E+02 1.95E+01 O.OOE+OO 1.40E+02 O.OOE+OO 3.51E+03 Fe-55 6.58E+02 4.55E+02 1.06E+02 O.OOE+OO O.OOE+OO 2.54E+02 2.61E+02 Fe-59 1.04E+03 2.44E+03 9.36E+02 O.OOE+OO O.OOE+OO 6.82E+02 8.14E+03 Co-58 O.OOE+OO 8.92E+01 2.00E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.81 E+03 Co-60 O.OOE+OO 2.56E+02 5.65E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.81E+03 Ni-63 3.11 E+04 2.16E+03 1.04E+03 O.OOE+OO O.OOE+OO O.OOE+OO 4.50E+02 Ni-65 1.26E+02 1.64E+01 7.49E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.17E+02 Cu-64 O.OOE+OO 9.97E+OO 4.68E+OO O.OOE+OO 2.51 E+01 O.OOE+OO 8.50E+02 Zn-65 2.32E+04 7.37E+04 3.33E+04 O.OOE+OO 4.93E+04 O.OOE+OO 4.64E+04 Zn-69 4.93E+01 9.43E+01 6.56E+OO O.OOE+OO 6.13E+01 O.OOE+OO 1.42E+01 Br-83 O.OOE+OO O.OOE+OO 4.04E+01 O.OOE+OO O.OOE+OO O.OOE+OO 5.82E+01 Br-84 O.OOE+OO O.OOE+OO 5.24E+01 O.OOE+OO O.OOE+QO O.OOE+OO 4.11 E-04 Br-85 O.OOE+OO O.OOE+OO 2.15E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.01 E+05 4.71E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.99E+04 Rb-88 O.OOE+OO 2.90E+02 1.54E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.00E-09 Rb-89 O.OOE+OO 1.92E+02 1.35E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.12E-11 Sr-89 2.21E+04 O.OOE+OO 6.35E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.55E+03 Sr-90 6.26E+05 O.OOE+OO 1.26E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.57E+04 Sr-91 4.07E+02 O.OOE+OO 1.64E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E+03 Sr-92 1.54E+02 O.OOE+OO 6.68E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.06E+03 Y-90 5.76E-01 O.OOE+OO 1.54E-02 O.OOE+OO O.OOE+OO O.OOE+OO 6.10E+03 Y-91M 5.44E-03 O.OOE+OO 2.11 E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.60E-02 Y-91 8.44E+OO O.OOE+OO 2.26E-01 O.OOE+OO O.OOE+OO O.OOE+OO 4.64E+03 Y-92 5.06E-02 O.OOE+OO 1.48E-03 O.OOE+OO O.OOE+OO O.OOE+OO 8.86E+02 Y-93 1.60E-01 O.OOE+OO 4.43E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.09E+03 Zr-95 2.40E-01 7.70E-02 5.21 E-02 O.OOE+OO 1.21 E-01 O.OOE+OO 2.44E+02 Zr-97 1.33E-02 2.68E-03 1.22E-03 O.OOE+OO 4.04E-03 O.OOE+OO 8.30E+02 Nb-95 4.47E+02 2.48E+02 1.34E+02 O.OOE+OO 2.46E+02 O.OOE+OO 1.51 E+06 Mo-99 O.OOE+OO 1.03E+02 1.96E+01 O.OOE+OO 2.34E+02 O.OOE+OO 2.39E+02 Tc-99M 8.87E-03 2.51E-02 3.19E-01 O.OOE+OO 3.81 E-01 1.23E-02 1.48E+01 Tc-101 9.12E-03 1.31E-02 1.29E-01 O.OOE+OO 2.37E-01 6.72E-03 3.95E-14 Ru-103 4.43E+OO O.OOE+OO 1.91 E+OO O.OOE+OO 1.69E+01 O.OOE+OO 5.17E+02 Ru-105 3.69E-01 O.OOE+OO 1.46E-01 O.OOE+OO 4.76E+OO O.OOE+OO 2.26E+02 Ru-106 6.58E+01 O.OOE+OO 8.33E+OO O.OOE+OO 1.27E+02 O.OOE+OO 4.26E+03 Ag-110M 8.81 E-01 8.15E-01 4.84E-01 O.OOE+OO 1.60E+OO O.OOE+OO 3.33E+02 Te-125M 2.57E+03 9.30E+02 3.44E+02 7.72E+02 1.04E+04 O.OOE+OO 1.02E+04 Page 199 of 267
Revision 5 Aug 31, 2015 Table F-9 (continued) Site Specific Fish Ingestion Dose Factors for Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-127M 6.48E+03 2.32E+03 7.90E+02 1.66E+03 2.63E+04 O.OOE+OO 2.17E+04 Te-127 1.05E+02 3.78E+01 2.28E+01 7.80E+01 4.29E+02 O.OOE+OO 8.31E+03 Te-129M 1.10E+04 4.11E+03 1.74E+03 3.78E+03 4.60E+04 O.OOE+OO 5.54E+04 Te-129 3.01E+01 1.13E+01 7.33E+OO 2.31 E+01 1.26E+02 O.OOE+OO 2.27E+01 Te-131M 1.66E+03 8.10E+02 6.75E+02 1.28E+03 8.21E+03 O.OOE+OO 8.04E+04 Te-131 1.89E+01 7.88E+OO 5.96E+OO 1.55E+01 8.26E+01 O.OOE+OO 2.67E+OO Te-132 2.41E+03 1.56E+03 1.47E+03 1.72E+03 1.50E+04 O.OOE+OO 7.38E+04 1-130 2.71E+01 8.01E+01 3.16E+01 6.79E+03 1.25E+02 O.OOE+OO 6.89E+01 1-131 1.49E+02 2.14E+02 1.22E+02 7.00E+04 3.66E+02 O.OOE+OO 5.64E+01 1-132 7.29E+OO 1.95E+01 6.82E+OO 6.82E+02 3.11E+01 O.OOE+OO 3.66E+OO 1-133 5.10E+01 8.87E+01 2.70E+01 1.30E+04 1.55E+02 O.OOE+OO 7.97E+01 1-134 3.81E+OO 1.03E+01 3.70E+OO 1.79E+02 1.64E+01 O.OOE+OO 9.01E-03 1-135 1.59E+01 4.17E+01 1.54E+01 2.75E+03 6.68E+01 O.OOE+OO 4.70E+01 Cs-134 2.98E+05 7.09E+05 5.79E+05 O.OOE+OO 2.29E+05 7.61E+04 1.24E+04 Cs-136 3.12E+04 1.23E+05 8.86E+04 O.OOE+OO 6.85E+04 9.38E+03 1.40E+04 Cs-137 3.82E+05 5.22E+05 3.42E+05 O.OOE+OO 1.77E+05 5.89E+04 1.01 E+04 Cs-138 2.64E+02 5.22E+02 2.59E+02 O.OOE+OO 3.84E+02 3.79E+01 2.23E-03 Ba-139 9.29E-01 6.62E-04 2.72E-02 O.OOE+OO 6.19E-04 3.75E-04 1.65E+OO Ba-140 1.94E+02 2.44E-01 1.27E+01 O.OOE+OO 8.30E-02 1.40E-01 4.00E+02 Ba-141 4.51 E-01 3.41E-04 1.52E-02 O.OOE+OO 3.17E-04 1.93E-04 2.13E-10 Ba-142 2.04E-01 2.10E-04 1.28E-02 O.OOE+OO 1.77E-04 1.19E-04 2.87E-19 La-140 1.50E-01 7.54E-02 1.99E-02 O.OOE+OO O.OOE+OO O.OOE+OO 5.54E+03 La-142 7.66E-03 3.48E-03 8.68E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.54E+01 Ce-141 2.24E-02 1.52E-02 1.72E-03 O.OOE+OO 7.04E-03 O.OOE+OO 5.79E+01 Ce-143 3.95E-03 2.92E+OO. 3.23E-04 O.OOE+OO 1.29E-03 O.QOE+OO 1.09E+02 Ce-144 1.17E+OO 4.88E-01 6.27E-02 O.OOE+OO 2.90E-01 O.OOE+OO 3.95E+02 Pr-143 5.51 E-01 2.21 E-01 2.73E-02 O.OOE+OO 1.27E-01 O.OOE+OO 2.41 E+03 Pr-144 1.80E-03 7.48E-04 9.16E-05 O.OOE+OO 4.22E-04 O.OOE+OO 2.59E-10 Nd-147 3.76E-01 4.35E-01 2.60E-02 O.OOE+OO 2.54E-01 O.OOE+OO 2.09E+03 W-187 2.96E+02 2.47E+02 8.65E+01 O.OOE+OO O.OOE+OO O.OOE+OO 8.10E+04 Np-239 2.85E-02 2.BOE-03 1.54E-03 O.OOE+OO 8.74E-03 O.OOE+OO 5.75E+02 Page 200 of 267
Revision5 Aug 31, 2015 Table F-9a Site Specific Fish Ingestion Dose Factors for Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 9.92E-02 9.92E-02 9.92E-02 9.92E-02 9.92E-02 9.92E-02 Na-24 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 Cr-51 O.OOE+OO O.OOE+OO 1.31 E+OO 7.30E-01 2.88E-01 1.88E+OO 2.21E+02 Mn-54 O.OOE+OO 4.30E+03 8.54E+02 O.OOE+OO 1.28E+03 O.OOE+OO 8.83E+03 Mn-56 O.OOE+OO 1.15E+02 2.05E+01 O.OOE+OO 1.46E+02 O.OOE+OO 7.59E+03 Fe-55 6.89E+02 4.89E+02 1.14E+02 O.OOE+OO O.OOE+OO 3.10E+02 2.12E+02 Fe-59 1.07E+03 2.50E+03 9.65E+02 O.OOE+OO O.OOE+OO 7.88E+02 5.91E+03 Co-58 O.OOE+OO 8.86E+01 2.04E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.22E+03 Co-60 O.OOE+OO 2.56E+02 5.77E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.34E+03 Ni-63 3.23E+04 2.28E+03 1.09E+03 O.OOE+OO O.OOE+OO O.OOE+OO 3.63E+02 Ni-65 1.37E+02 1.75E+01 7.95E+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.47E+02 Cu-64 O.OOE+OO 1.05E+01 4.93E+OO O.OOE+OO 2.65E+01 O.OOE+OO 8.14E+02 Zn-65 2.10E+04 7.30E+04 3.40E+04 O.OOE+OO 4.67E+04 O.OOE+OO 3.09E+04 Zn-69 5.36E+01 1.02E+02 7.15E+OO O.OOE+OO 6.68E+01 O.OOE+OO 1.88E+02 Br-83 O.OOE+OO O.OOE+OO 4.40E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 5.53E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 2.34E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.09E+05 5.11E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.61 E+04 Rb-88 O.OOE+OO 3.11E+02 1.66E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.66E-05 Rb-89 O.OOE+OO 2.01E+02 1.42E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.08E-07 Sr-89 2.41E+04 O.OOE+OO 6.89E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.87E+03 Sr-90 5.58E+05 O.OOE+OO 1.12E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.27E+04 Sr-91 4.42E+02 O.OOE+OO 1.76E+01 O.OOE+OO O.OOE+OO O.OOE+OO 2.00E+03 Sr-92 1.67E+02 O.OOE+OO 7.11 E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.25E+03 Y-90 6.25E-01 O.OOE+OO 1.68E-02 O.OOE+OO O.OOE+OO O.OOE+OO 5.15E+03 Y-91M 5.88E-03 O.OOE+OO 2.25E-04 O.OOE+OO O.OOE+OO O.OOE+OO 2.78E-01 Y-91 9.17E+OO O.OOE+OO 2.46E-01 O.OOE+OO O.OOE+OO O.OOE+OO 3.76E+03 Y-92 5.52E-02 O.OOE+OO 1.60E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.51E+03 Y-93 1.75E-01 O.OOE+OO 4.79E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.34E+03 Zr-95 2.48E-01 7.82E-02 5.38E-02 O.OOE+OO 1.15E-01 O.OOE+OO 1.81 E+02 Zr-97 1.43E-02 2.82E-03 1.30E-03 O.OOE+OO 4.28E-03 O.OOE+OO 7.64E+02 Nb-95 4.50E+02 2.50E+02 1.37E+02 O.OOE+OO 2.42E+02 O.OOE+OO 1.07E+06 Mo-99 O.OOE+OO 1.10E+02 2.10E+01 O.OOE+OO 2.52E+02 O.OOE+OO 1.97E+02 Tc- 99M 9.08E-03 2.53E-02 3.28E-01 O.OOE+OO 3.78E-01 1.41 E-02 1.66E+01 Tc-101 9.85E-03 1.40E-02 1.38E-01 O.OOE+OO 2.53E-01 8.54E-03 2.39E-09 Ru-103 4.65E+OO O.OOE+OO 1.99E+OO O.OOE+OO 1.64E+01 O.OOE+OO 3.89E+02 Ru-105. 3.98E-01 O.OOE+OO 1.54E-01 O.OOE+OO 5.02E+OO O.OOE+OO 3.21E+02 Ru-106 7.15E+01 O.OOE+OO 9.01E+OO O.OOE+OO 1.38E+02 O.OOE+OO 3.43E+03 Ag-110M 8.60E-01 8.14E-01 4.95E-01 O.OOE+OO 1.55E+OO O.OOE+OO 2.29E+02 Te-125M 2.79E+03 1.01 E+03 3.74E+02 7.81E+02 O.OOE+OO O.OOE+OO 8.24E+03 Page 201 of 267
Revision 5 Aug 31, 2015 Table F-9a (continued) Site Specific Fish Ingestion Dose Factors for Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-127M 7.06E+03 2.50E+03 8.39E+02 1.68E+03 2.86E+04 O.OOE+OO 1.76E+04 Te-127 1.15E+02 4.09E+01 2.48E+01 7.95E+01 4.67E+02 O.OOE+OO 8.90E+03 Te-129M 1.19E+04 4.41E+03 1.88E+03 3.84E+03 4.98E+04 O.OOE+OO 4.47E+04 Te-129 3.27E+01 1.22E+01 7.95E+OO 2.33E+01 1.37E+02 O.OOE+OO 1.79E+02 Te-131M 1.78E+03 8.54E+02 7.12E+02 1.28E+03 8.90E+03 O.OOE+OO 6.85E+04 Te-131 2.04E+01 8.39E+OO 6.36E+OO 1.57E+01 8.90E+01 O.OOE+OO 1.67E+OO Te-132 2.55E+03 1.61 E+03 1.52E+03 1.70E+03 1.55E+04 O.OOE+OO 5.11 E+04 1-130 2.82E+01 8.15E+01 3.26E+01 6.65E+03 1.26E+02 O.OOE+OO 6.27E+01 1-131 1.60E+02 2.24E+02 1.20E+02 6.54E+04 3.86E+02 O.OOE+OO 4.43E+01 1-132 7.63E+OO 2.00E+01 7.17E+OO 6.73E+02 3.15E+01 O.OOE+OO 8.70E+OO 1-133 5.50E+01 9.33E+01 2.85E+01 1.30E+04 1.64E+02 O.OOE+OO 7.06E+01 1-134 3.99E+OO 1.066+01 3.80E+OO 1.76E+02 1.67E+01 O.OOE+OO 1.40E-01 1-135 1.67E+01 4.30E+01 1.59E+01 2.76E+03 6.79E+01 O.OOE+OO 4.76E+01 Cs-134 3.05E+05 7.19E+05 3.33E+05 O.OOE+OO 2.28E+05 8.72E+04 8.94E+03 Cs-136 3.13E+04 1.23E+05 8.28E+04 O.OOE+OO 6.71E+04 1.06E+04 9.92E+03 Cs-137 4.09E+05 5.44E+05 1.89E+05 O.OOE+OO 1.85E+05 7.19E+04 7.73E+03 Cs-138 2.83E+02 5.44E+02 2.72E+02 O.OOE+OO 4.01E+02 4.67E+01 2.47E-01 Ba-139 1.01E+OO 7.14E-04 2.95E-02 O.OOE+OO 6.73E-04 4.92E-04 9.05E+OO Ba-140 2.07E+02 2.54E-01 1.34E+01 O.OOE+OO 8.61 E-02 1.71 E-01 3.20E+02 Ba-141 4.90E-01 3.66E-04 1.63E-02 O.OOE+OO 3.39E-04 2.50E-04 1.04E-06 Ba-142 2.18E~01 2.18E-04 1.34E-02 O.OOE+OO 1.85E-04 1.45E-04 6.70E-13 La-140 1.59E-01 7.80E-02 2.07E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.48E+03 La-142 8.16E-03 3.63E-03 9.03E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.10E+02 Ce-141 2.43E-02 1.62E-02 1.86E-03 O.OOE+OO 7.62E-03 O.OOE+OO 4.63E+01 Ce-143 4.29E-03 3.12E+OO 3.48E-04 O.OOE+oo 1.40E-03 O.OOE+OO 9.38E+01 Ce-144 1.27E+OO 5.25E-01 6.82E-02 O.OOE+OO 3.14E-01 O.OOE+OO 3.19E+02 Pr-143 5.97E-01 2.38E-01 2.97E-02 O.OOE+OO 1.39E-01 O.OOE+OO 1.97E+03 Pr-144 1.96E-03 8.03E-04 9.94E-05 O.OOE+OO 4.61 E-04 O.OOE+OO 2.16E-06 Nd-147 4.28E-01 4.65E-01 2.79E-02 O.OOE+OO 2.73E-01 O.OOE+OO 1.68E+03 W-187 3.20E+02 2.60E+02 9.13E+01 O.OOE+OO O.OOE+OO O.OOE+OO 7.05E+04 Np-239 3.21 E-02 3.03E-03 1.68E-03 O.OOE+OO 9.50E-03 O.OOE+OO 4.87E+02 Notes:
- 1) Units are mrem/hr per µCi/ml.
Page 202 of 267
Revision 5 Aug 31, 2015 Table F-9b Site Specific Fish Ingestion Dose Factors for Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 8.21E-02 8.21E-02 8.21E-02 8.21E-02 8.21E-02 8.21E-02 Na-24 4.56E+02 4.56E+02 4.56E+02 4.56E+02 4.56E+02 4.56E+02 4.56E+02 Cr-51 O.OOE+OO O.OOE+OO 1.40E+OO 7.77E-01 2.12E-01 1.42E+OO 7.43E+01 Mn-54 O.OOE+OO 3.37E+03 8.97E+02 O.OOE+OO 9.44E+02 O.OOE+OO 2.83E+03 Mn-56 O.OOE+OO 1.05E+02 2.37E+01 O.OOE+OO 1.27E+02 O.OOE+OO 1.52E+04 Fe-55 9.05E+02 4.80E+02 1.49E+02 O.OOE+OO O.OOE+OO 2.71E+02 8.89E+01 Fe-59 1.30E+03 2.10E+03 1.05E+03 O.OOE+OO O.OOE+OO 6.09E+02 2.19E+03 Co-58 O.OOE+OO 7.08E+01 2.17E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.13E+02 Co-60 O.OOE+OO 2.08E+02 6.14E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.15E+03 Ni-63 4.23E+04 2.27E+03 1.44E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.53E+02 Ni-65 1.75E+02 1.64E+01 9.60E+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.01E+03 Cu-64 O.OOE+OO 9.64E+OO 5.82E+OO O.OOE+OO 2.33E+01 O.OOE+OO 4.52E+02 Zn-65 2.16E+04 5.74E+04 3.57E+04 O.OOE+OO 3.62E+04 O.OOE+OO 1.01 E+04 Zn-69 6.89E+01 9.96E+01 9.20E+OO O.OOE+OO 6.04E+01 O.OOE+OO 6.28E+03 Br-83 O.OOE+OO O.OOE+OO 5.65E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 6.54E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 3.01E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.05E+05 6.48E+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.78E+03 Rb-88 O.OOE+OO 2.99E+02 2.08E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.47E+01 Rb-89 O.OOE+OO 1.84E+02 1.64E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.60E+OO Sr-89 3.11 E+04 O.OOE+OO 8.90E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.21E+03 Sr-90 6.04E+05 O.OOE+OO 1.22E+04 O.OOE+OO O.OOE+OO O.OOE+OO 5.40E+03 Sr-91 5.66E+02 O.OOE+OO 2.14E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.25E+03 Sr~92 2.13E+02 O.OOE+OO 8.54E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.04E+03 Y-90 8.08E-01 O.OOE+OO 2.16E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.30E+03 Y-91M 7.51 E-03 O.OOE+OO 2.73E-04 O.OOE+OO O.OOE+OO O.OOE+OO 1.47E+01 Y-91 1.18E+01 O.OOE+OO 3.17E-01 O.OOE+OO O.OOE+OO O.OOE+OO 1.58E+03 Y-92 7.08E-02 O.OOE+OO 2.03E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.05E+03 Y-93 2.24E-01 O.OOE+OO 6.16E-03 O.OOE+OO O.OOE+OO O.OOE+OO 3.34E+03 Zr-95 3.01 E-01 6.62E-02 5.89E-02 O.OOE+OO 9.47E-02 O.OOE+OO 6.90E+01 Zr-97 1.81 E-02 2.62E-03 1.55E-03 O.OOE+OO 3.76E-03 O.OOE+OO 3.97E+02 Nb-95 5.31E+02 2.07E+02 1.48E+02 O.OOE+OO 1.94E+02 O.OOE+OO 3.82E+05 Mo-99 O.OOE+OO 1.05E+02 2.59E+01 O.OOE+OO 2.23E+02 O.OOE+OO 8.65E+01 Tc- 99M 1.09E-02 2.14E-02 3.54E-01 O.OOE+OO 3.1 OE-01 1.08E-02 1.22E+01 Tc-101 1.26E-02 1.32E-02 1.68E-01 O.OOE+OO 2.25E-01 6.99E-03 4.20E-02 Ru-103 5.75E+OO O.OOE+OO 2.21 E+OO O.OOE+OO 1.45E+01 O.OOE+OO 1.49E+02 Ru-105 5.07E-01 O.OOE+OO 1.84E-01 O.OOE+OO 4.46E+OO O.OOE+OO 3.31E+02 Ru-106 9.20E+01 O.OOE+OO 1.15E+01 O.OOE+OO 1.24E+02 0.00-E+OO 1.43E+03 Ag-110M 9.75E-01 6.59E-01 5.26E-01 O.OOE+OO 1.23E+OO O.OQE+OO 7.83E+01 Te-125M 3.59E+03 9.72E+02 4.78E+02 1.01E+03 O.OOE+OO O.OOE+OO 3.46E+03 Page 203 of 267
Revision 5 Aug 31, 2015 Table F-9b (continued) Site Specific Fish Ingestion Dose Factors for Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-127M 9.09E+03 2.45E+03 1.08E+03 2.17E+03 2.59E+04 O.OOE+OO 7.36E+03 Te-127 1.48E+02 4.00E+01 3.18E+01 1.03E+02 4.22E+02 O.OOE+OO 5.79E+03 Te-129M 1.53E+04 4.28E+03 2.38E+03 4.94E+03 4.50E+04 O.OOE+OO 1.87E+04 Te-129 4.22E+01 1.18E+01 1.00E+01 3.01E+01 1.23E+02 O.OOE+OO 2.62E+03 Te-131M 2.27E+03 7.83E+02 8.34E+02 1.61 E+03 7.58E+03 O.OOE+OO 3.18E+04 Te-131 2.61E+01 7.96E+OO 7.77E+OO 2.00E+01 7.90E+01 O.OOE+OO 1.37E+02 Te-132 3.18E+03 1.41 E+03 1.70E+03 2.05E+03 1.31 E+04 O.OOE+OO 1.42E+04 1-130 3.45E+01 6.96E+01 3.59E+01 7.67E+03 1.04E+02 O.OOE+OO 3.26E+01 1-131 2.03E+02 2.04E+02 1.16E+02 6.75E+04 3.35E+02 O.OOE+OO 1.82E+01 1-132 9.44E+OO 1.73E+01 7.98E+OO 8.05E+02 2.65E+01 O.OOE+OO 2.04E+01 1-133 6.99E+01 8.64E+01 3.27E+01 1.60E+04 1.44E+02 O.OOE+OO 3.48E+01 1-134 4.94E+OO 9.18E+OO 4.22E+OO 2.11 E+02 1.40E+01 O.OOE+OO 6.09E+OO 1-135 2.06E+01 3.72E+01 1.76E+01 3.29E+03 5.70E+01 O.OOE+OO 2.83E+01 Cs-134 3.68E+05 6.04E+05 1.27E+05 O.OOE+OO 1.87E+05 6.72E+04 3.26E+03 Cs-136 3.70E+04 1.02E+05 6.58E+04 O.OOE+OO 5.41 E+04 8.07E+03 3.57E+03 Cs-137 5.14E+05 4.92E+05 7.27E+04 O.OOE+OO 1.60E+05 5.77E+04 3.08E+03 Cs-138 3.59E+02 4.99E+02 3.16E+02 O.OOE+OO 3.51E+02 3.78E+01 2.30E+02 Ba-139 1.30E+OO 6.95E-04 3.78E-02 O.OOE+OO 6.07E-04 4.09E-04 7.52E+01 Ba~140 2.61E+02 2.29E-01 1.53E+01 O.OOE+OO 7.46E-02 1.37E-01 1.32E+02 Ba-141 6.29E-01 3.52E-04 2.05E-02 O.OOE+OO 3.05E-04 2.07E-03 3.59E-01 Ba-142 2.75E-01 1.98E-04 1.54E-02 O.OOE+OO 1.60E-04 1.16E-04 3.59E-03 La~140 1.99E-01 6.94E-02 2.34E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E+03 La-142 1.03E-02 3.28E-03 1.03E-03 O.OOE+OO O.OOE+OO O.OOE+OO 6.51E+02 Ce-141 3.12E-02 1.56E-02 2.31E-03 O.OOE+OO 6.83E-03 O.OOE+OO 1.94E+01 Ce-143 5.50E-03 2.98E+OO 4.32E-04 O.OOE+OO 1.25E-03 O.OOE+OO 4.37E+01 Ce-144 1.64E+OO 5.13E-01 8.73E-02 O.OOE+OO 2.84E-01 O.OOE+OO 1.34E+02 Pr-143 7.73E-01 2.32E-01 3.83E-02 O.OOE+OO 1.26E-01 O.OOE+OO 8.34E+02 Pr-144 2.54E-03 7.85E-04 1.28E-04 O.OOE+OO 4.15E-04 O.OOE+OO 1.69E+OO Nd-147 5.49E-01 4.44E-01 3.44E-02 O.OOE+OO 2.44E-01 O.OOE+OO 7.04E+02 W-187 4.05E+02 2.40E+02 1.08E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.37E+04 Np-239 4.13E-02 2.97E-03 2.08E-03 O.OOE+OO 8.57E-03 O.OOE+OO 2.19E+02 Notes:
- 1) Units are mrem/hr per µCi/ml.
- 2) The infant age group is assumed to receive no dose through the fish ingestion pathway, therefore no dose factors are supplied.
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Revision 5 Aug 31, 2015 Table F-10 Ground Plane Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Na-24 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 Cr-51 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65E+06 Mn-54 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 Mn-56 9.03E+05 9.03E+05 9.03E+05 9.03E+05 9.03E+05 9.03E+05 9.03E+05 Fe-55 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-59 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 Co-58 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 Co-60 2.45E+10 2.45E+10 2.45E+10 2.45E+10 2.45E+10 2.45E+10 2.45E+10 Ni-63 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ni-65 2.97E+05 2.97E+05 2.97E+05 2.97E+05 2.97E+05 2.97E+05 2.97E+05 Cu-64 6.05E+05 6.05E+05 6.05E+05 6.05E+05 6.05E+05 6.05E+05 6.05E+05 Zn~65 7.46E+08 7.46E+08 7.46E+08 7.46E+08 7.46E+08 7.46E+08 7.46E+08 Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 Br-84 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 9.01E+06 9.01E+06 9.01 E+06 9.01E+06 9.01E+06 9.01E+06 9.01E+06 Rb-88 3.31E+04 3.31E+04 3.31 E+04 3.31E+04 3.31E+04 3.31E+04 3.31E+04 Rb-89 1.23E+05 1.23E+05 1.23E+05 1.23E+05 1.23E+05 1.23E+05 1.23E+05 Sr-89 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 Sr-90 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-91 2.14E+06 2.14E+06 2.14E+06 2.14E+06 2.14E+06 2.14E+06 2.14E+06 Sr-92 7.76E+05 7.76E+05 7.76E+05 7.76E+05 7.76E+05 7.76E+05 7.76E+05 Y-90 4.50E+03 4.50E+03 4.50E+03 4.50E+03 4.50E+03 4.50E+03 4.50E+03 Y-91M 1.00E+05 1.00E+05 1.00E+05 1.00E+05 1.00E+05 1.00E+05 1.00E+05 Y-91 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 Y-92 1.80E+05 1.80E+05 1.80E+05 1.80E+05 1.80E+05 1.80E+05 1.80E+05 Y-93 1.83E+05 1.83E+05 1.83E+05 1.83E+05 1.83E+05 1.83E+05 1.83E+05 Zr-95 2.45E+08 2.45E+08 2.45E+08 2.45E+08 2.45E+08 2.45E+08 2.45E+08 Zr-97 2.96E+06 2.96E+06 2.96E+06 2.96E+06 2.96E+06 2.96E+06 2.96E+06 Nb-95 1.37E+08 1.37E+08 1.37E+08 1.37E+08 1.37E+08 1.37E+08 1.37E+08 Mo-99 3.99E+06 3.99E+06 3.99E+06 3.99E+06 3.99E+06 3.99E+06 3.99E+06 Tc- 99M _1.84E+05 1.84E+05 1.84E+05 1.84E+05 1.84E+05 1.84E+05 1.84E+05 Tc-101 ;2.03E+04 2.03E+04 2.03E+04 2.03E+04 2.03E+04 2.03E+04 2.03E+04 Ru-103 1.08E+08 1.08E+08 1.08E+08 1.08E+08 1.08E+08 1.08E+08 1.08E+08 Ru-105 6.36E+05 6.36E+05 6.36E+05 6.36E+05 6.36E+05 6.36E+05 6.36E+05 Ru-106 4.22E+08 4.22E+08 4.22E+08 4.22E+08 4.22E+08 4.22E+08 4.22E+08 Ag-110M 3.45E+09 3.45E+09 3.45E+09 3.45E+09 3.45E+09 3.45E+09 3.45E+09 Page 205 of 267
Revision 5 Aug 31, 2015 Table F-10 (Continued) Ground Plane Dose Factors (same for all age groups) Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 1.56E+06 1.56E+06 1.56E+06 1.56E+06 1.56E+06 1.56E+06 1.56E+06 Te-127M 9.16E+04 9.16E+04 9.16E+04 9.16E+04 9.16E+04 9.16E+04 9.16E+04 Te-127 2.99E+03 2.99E+03 2.99E+03 2.99E+03 2.99E+03 2.99E+03 2.99E+03 Te-129M 1.98E+07 1.98E+07 1.98E+07 1.98E+07 1.98E+07 1.98E+07 1.98E+07 Te-129 2.62E+04 2.62E+04 2.62E+04 2.62E+04 2.62E+04 2.62E+04 2.62E+04 Te-131M 8.02E+06 8.02E+06 8.02E+06 8.02E+06 8.02E+06 8.02E+06 8.02E+06 Te-131 2.92E+04 2.92E+04 2.92E+04 2.92E+04 2.92E+04 2.92E+04 2.92E+04 Te-132 4.22E+06 4.22E+06 4.22E+06 4.22E+06 4.22E+06 4.22E+06 4.22E+06 1-130 5.50E+06 5.50E+06 5.50E+06 5.50E+06 5.50E+06 5.50E+06 5.50E+06 1-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1-132 1.25E+06
- 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1-133 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06 1-134 4.46E+05 4.46E+05 4.46E+05 4.46E+05 4.46E+05 4.46E+05 4.46E+05 1-135 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.53E+06 Cs-134 6.94E+09 6.94E+09 6.94E+09 6.94E+09 6.94E+09 6.94E+09 6.94E+09 Cs-136 1.50E+08 1.50E+08 1.50E+08 1.50E+08 1.50E+08 1.50E+08 1.50E+08 Cs-137 1.76E+10 1.76E+10 1.76E+10 1.76E+10 1.76E+10 1.76E+10 1.76E+10 Cs-138 3.59E+05 3.59E+05 3.59E+05 3.59E+05 3.59E+05 3.59E+05 3.59E+05 Ba-139 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 Ba-140 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 Ba-141 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 Ba-142 4.44E+04 4.44E+04 4.44E+04 4.44E+04 4.44E+04 4.44E+04 4.44E+04 La-140 1.92E+07 1.92E+07 1.92E+07 1.92E+07 1.92E+07 1.92E+07 1.92E+07 La-142 7.60E+05 7.60E+05 7.60E+05 7.60E+05 7.60E+05 7.60E+05 7.60E+05 Ce-141 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 Ce-143 2.31E+06 2.31E+06 2.31E+06 2.31E+06 2.31E+06 2.31E+06 2.31E+06 Ce-144 6.96E+07 6.96E+07 6.96E+07 6.96E+07 6.96E+07 6.96E+07 6.96E+07 Pr-143 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Pr-144 1.84E+03 1.84E+03 1.84E+03 1.84E+03 1.84E+03 1.84E+03 1.84E+03 Nd-147 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 W-187 2.35E+06 2.35E+06 2.35E+06 2.35E+06 2.35E+06 2.35E+06 2.35E+06 Np-239 1.71E+06 1.71 E+06 1.71 E+06 1.71E+06 1.71 E+06 1.71 E+06 1.71 E+06 Notes:
2
- 1) Units are m mrem/yr per µCi/sec.
- 2) All age groups are assumed to receive the same dose.
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Revision 5 Aug 31, 2015 Table F-11 Adult lnhalati"on Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 7.18E+02 7.18E+02 7.18E+02 7.18E+02 7.18E+02 7.18E+02 Na-24 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 Cr-51 O.OOE+OO O.OOE+OO 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 Mn-54 O.OOE+OO 3.96E+04 6.30E+03 O.OOE+OO 9.84E+03 1.40E+06 7.74E+04 Mn-56 O.OOE+OO 1.24E+OO 1.83E-01 O.OOE+OO 1.30E+OO 9.44E+03 2.02E+04 Fe-55 2.46E+04 1.70E+04 3.94E+03 O.OOE+OO O.OOE+OO 7.21E+04 6.03E+03 Fe-59 1.18E+04 2.78E+04 1.06E+04 O.OOE+OO O.OOE+OO 1.02E+06 1.88E+05 Co-58 O.OOE+OO 1.58E+03 2.07E+03 O.OOE+OO O.OOE+OO 9.28E+05 1.06E+05 Co-60 O.OOE+OO 1.15E+04 1.48E+04 O.OOE+OO O.OOE+OO 5.97E+06 2.85E+05 Ni-63 4.32E+05 3.14E+04 1.45E+04 O.OOE+OO O.OOE+OO 1.78E+05 1.34E+04 Ni-65 1.54E+OO 2.10E-01 9.12E-02 O.OOE+OO O.OOE+OO 5.60E+03 1.23E+04 Cu-64 O.OOE+OO 1.46E+OO 6.15E-01 O.OOE+OO 4.62E+OO 6.78E+03 4.90E+04 Zn-65 3.24E+04 1.03E+05 4.66E+04 O.OOE+OO 6.90E+04 8.64E+05 5.34E+04 Zn-69 3.38E-02 6.51E-02 4.52E-03 O.OOE+OO 4.22E-02 9.20E+02 1.63E+01 Br-83 O.OOE+OO O.OOE+OO 2.41 E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.32E+02 Br-84 O.OOE+OO O.OOE+OO 3.13E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.64E-03 Br-85 O.OOE+OO O.OOE+OO 1.28E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.35E+05 5.90E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.66E+04 Rb-88 O.OOE+OO 3.87E+02 1.93E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.34E-09 Rb-89 O.OOE+OO 2.56E+02 1.70E+02 O.OOE+OO O.OOE+OO O.OOE+OO 9.28E-12 Sr-89 3.04E+05 O.OOE+OO 8.72E+03 O.OOE+OO O.OOE+OO 1.40E+06 3.50E+05 Sr-90 2.87E+07 O.OOE+OO 5.77E+05 O.OOE+OO O.OOE+OO 9.60E+06 7.22E+05 Sr-91 6.19E+01 O.OOE+OO 2.50E+OO O.OOE+OO O.OOE+OO 3.65E+04 1.91 E+05 Sr-92 6.74E+OO O.OOE+OO 2.91 E-01 O.OOE+OO O.OOE+OO 1.65E+04 4.30E+04 Y-90 2.09E+03 O.OOE+OO 5.61 E+01 O.OOE+OO O.OOE+OO 1.70E+05 5.06E+05 Y-91M 2.61 E-01 O.OOE+OO 1.02E-02 O.OOE+OO O.OOE+OO 1.92E+03 1.33E+OO Y-91 4.62E+05 O.OOE+OO 1.24E+04 O.OOE+OO O.OOE+OO 1.70E+06 3.85E+05 Y-92 1.03E+01 O.OOE+OO 3.02E-01 O.OOE+OO O.OOE+OO 1.57E+04 7.35E+04 Y-93 9.44E+01 O.OOE+OO 2.61E+OO O.OOE+OO O.OOE+OO 4.85E+04 4.22E+05 Zr-95 1.07E+05 3.44E+04 2.33E+04 O.OOE+OO 5.42E+04 1.77E+06 1.50E+05 Zr-97 9.68E+01 1.96E+01 9.04E+OO O.OOE+OO 2.97E+01 7.87E+04 5.23E+05 Nb-95 1.41 E+04 7.82E+03 4.21E+03 O.OOE+OO 7.74E+03 5.05E+05 1.04E+05 Mo-99 O.OOE+OO 1.21E+02 2.30E+01 O.OOE+OO 2.91E+02 9.12E+04 2.48E+05 Tc- 99M 1.03E-03 2.91 E-03 3.70E-02 O.OOE+OO 4.42E-02 7.64E+02 4.16E+03 Tc-101 4.18E-05 6.02E-05 5.90E-04 O.OOE+OO 1.08E-03 3.99E+02 1.09E-11 Ru-103 1.53E+03 O.OOE+OO 6.58E+02 O.OOE+OO 5.83E+03 5.05E+05 1.10E+05 Ru-105 7.90E-01 O.OOE+OO 3.11 E-01 O.OOE+OO 1.02E+OO 1.10E+04 4.82E+04 Ru-106 6.91E+04 O.OOE+OO 8.72E+03 O.OOE+OO 1.34E+05 9.36E+06 9.12E+05 Ag-110M 1.08E+04 1.00E+04 5.94E+03 O.OOE+OO 1.97E+04 4.63E+06 3.02E+05 Page 207 of 267
Revision 5 Aug 31, 2015 Table F-11 (Continued) Adult Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 Te-127M 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05
- Te-127 1.40E+OO 6.42E-01 3.10E-01 1.06E+OO 5.10E+OO 6.51E+03 5.74E+04 Te-129M 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 Te-129 4.98E-02 2.39E-02 1.24E-02 3.90E-02 1.87E-01 1.94E+03 1.57E+02 Te-131M 6.99E+01 4.36E+01 2.90E+01 5.50E+01 3.09E+02 1.46E+05 5.56E+05 Te-131 1.11 E-02 5.95E-03 3.59E-03 9.36E-03 4.37E-02 1.39E+03 1.84E+01 Te-132 2.60E+02 2.15E+02 1.62E+02 1.90E+02 1.46E+03 2.88E+05 5.10E+05 1-130 4.58E+03 1.34E+04 5.28E+03 1.14E+06 2.09E+04 O.OOE+OO 7.69E+03 1-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 O.OOE+OO 6.28E+03 1-132 1.16E+03 3.26E+03 1.16E+03 1.14E+05 5.18E+03 O.OOE+OO 4.06E+02 1-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 O.OOE+OO 8.88E+03 1-134 6.44E+02 1.73E+03 6.15E+02 2.98E+04 2.75E+03 O.OOE+OO 1.01E+OO 1-135 2.68E+03 6.98E+03 2.57E+03 4.48E+05 1.11E+04 O.OOE+OO 5.25E+03 Cs-134 3.73E+05 8.48E+05 7.28E+05 O.OOE+OO 2.87E+05 9.76E+04 1.04E+04 Cs-136 3.90E+04 1.46E+05 1.10E+05 O.OOE+OO 8.56E+04 1.20E+04 1.17E+04 Cs-137 4.78E+05 6.21E+05 4.28E+05 O.OOE+OO 2.22E+05 7.52E+04 8.40E+03 Cs-138 3.31E+02 6.21E+02 3.24E+02 O.OOE+OO 4.80E+02 4.86E+01 1.86E-03 Ba-139 9.36E-01 6.66E-04 2.74E-02 O.OOE+OO 6.22E-04 3.76E+03 8.96E+02 Ba-140 3.90E+04 4.90E+01 2.57E+03 O.OOE+OO 1.67E+01 1.27E+06 2.18E+05 Ba-141 1.00E-01 7.53E-05 3.36E-03 O.OOE+OO 7.00E-05 1.94E+03 1.16E-07 Ba-142 2.63E-02 2.?0E-05 1.66E-03 O.OOE+OO 2.29E-05 1.19E+03 1.57E-16 La-140 3.44E+02 1.74E+02 4.58E+01 O.OOE+OO O.OOE+OO 1.36E+05 4.58E+05 La-142 6.83E-01 3.10E-01 7.72E-02 O.OOE+OO O.OOE+OO 6.33E+03 2.11 E+03 Ce-141 1.99E+04 1.35E+04 1.53E+03 O.OOE+OO 6.26E+03 3.62E+05 1.20E+05 Ce-143 1.86E+02 1.38E+02 1.53E+01 O.OOE+OO 6.08E+01 7.98E+04 2.26E+05 Ce-144 3.43E+06 1.43E+06 1.84E+05 O.OOE+OO 8.48E+05 7.78E+06 8.16E+05 Pr-143 9.36E+03 3.75E+03 4.64E+02 O.OOE+OO 2.16E+03 2.81E+05 2.00E+05 Pr-144 3.01 E~02 1.25E-02 1.53E-03 O.OOE+OO 7.05E-03 1.02E+03 2.15E-08 Nd-147 5.27E+03 6.10E+03 3.65E+02 O.OOE+OO 3.56E+03 2.21E+05 1.73E+05 W-187 8.48E+OO 7.08E+OO 2.48E+OO O.OOE+OO O.OOE+OO 2.90E+04 1.55E+05 Np-239 2.30E+02 2.03E+02 1.24E+01 O.OOE+OO 7.00E+01 3.76E+04 1.19E+05 Notes:
3
- 1) Units are mrem/yr per µCi/m .
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Revision 5 Aug 31, 2015 Table F-11a Teen Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 7.25E+02 7.25E+02 7.25E+02 7.25E+02 7.25E+02 7.25E+02 Na-24 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 Cr-51 O.OOE+OO O.OOE+OO 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.00E+03 Mn-54 O.OOE+OO 5.11 E+04 8.40E+03 O.OOE+OO 1.27E+04 1.98E+06 6.68E+04 Mn-56 O.OOE+OO 1.70E+OO 2.52E-01 O.OOE+OO 1.79E+OO 1.52E+04 5.74E+04 Fe-55 3.34E+04 2.38E+04 5.54E+03 O.OOE+OO O.OOE+OO 1.24E+05 6.39E+03 Fe-59 1.59E+04 3.70E+04 1.43E+04 O.OOE+OO O.OOE+OO 1.53E+06 1.78E+05 Co-58 O.OOE+OO 2.07E+03 2.78E+03 O.OOE+OO O.OOE+OO 1.34E+06 9.52E+04 Co-60 O.OOE+OO 1.51E+04 1.98E+04 O.OOE+OO O.OOE+OO 8.72E+06 2.59E+05 Ni-63 5.80E+05 4.34E+04 1.98E+04 O.OOE+OO O.OOE+OO 3.07E+05 1.42E+04 Ni-65 2.18E+OO 2.93E-01 1.27E-01 O.OOE+OO O.OOE+OO 9.36E+03 3.67E+04 Cu-64 O.OOE+OO 2.03E+OO 8.48E-01 O.OOE+OO 6.41E+OO 1.11 E+04 6.14E+04 Zn-65 3.86E+04 1.34E+05 6.24E+04 O.OOE+OO 8.64E+04 1.24E+06 4.66E+04 Zn-69 4.83E 9.20E-02 6.46E-03 O.OOE+OO 6.02E-02 1.58E+03 2.85E+02 Br-83 O.OOE+OO O.OOE+OO 3.44E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 4.33E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 1.83E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.90E+05 8.40E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.77E+04 Rb-88 O.OOE+OO 5.46E+02 2.72E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.92E-05 Rb-89 O.OOE+OO 3.52E+02 2.33E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.38E-07 Sr-89 4.34E+05 O.OOE+OO 1.25E+04 O.OOE+OO O.OOE+OO 2.42E+06 3.71E+05 Sr-90 3.31E+07 O.OOE+OO 6.66E+05 O.OOE+OO O.OOE+OO 1.65E+07 7.65E+05 Sr-91 8.80E+01 O.OOE+OO 3.51 E+OO O.OOE+OO O.OOE+OO 6.07E+04 2.59E+05 Sr-92 9.52E+OO O.OOE+OO 4.06E-01 O.OOE+OO O.OOE+OO 2.74E+04 1.19E+05 Y-90 2.98E+03 O.OOE+OO 8.00E+01 O.OOE+OO O.OOE+OO 2.93E+05 5.59E+05 Y-91M 3.70E-01 O.OOE+OO 1.42E-02 O.OOE+OO O.OOE+OO 3.20E+03 3.02E+01 Y-91 6.61E+05 O.OOE+OO 1.77E+04 O.OOE+OO O.OOE+OO 2.94E+06 4.09E+05 Y-92 1.47E+01 O.OOE+OO 4.29E-01 O.OOE+OO O.OOE+OO 2.68E+04 1.65E+05 Y-93 1.35E+02 O.OOE+OO 3.72E+OO O.OOE+OO O.OOE+OO 8.32E+04 5.79E+05 Zr-95 1.46E+05 4.58E+04 3.15E+04 O.OOE+OO 6.74E+04 2.69E+06 1.49E+05 Zr-97 1.38E+02 2.72E+01 1.26E+01 O.OOE+OO 4.12E+01 1.30E+05 6.30E+05 Nb-95 1.86E+04 1.03E+04 5.66E+03 O.OOE+OO 1.00E+04 7.51E+05 9.68E+04 Mo-99 O.OOE+OO 1.69E+02 3.22E+01 O.OOE+OO 4.11 E+02 1.54E+05 2.69E+05 Tc-99M 1.38E-03 3.86E-03 4.99E-02 O.OOE+OO 5.76E-02 1.15E+03 6.13E+03 Tc-101 5.92E-05 8.40E-05 8.24E-04 O.OOE+OO 1.52E-03 6.67E+02 8.72E-07 Ru-103 2.10E+03 O.OOE+OO 8.96E+02 O.OOE+OO 7.43E+03 7.83E+05 1.09E+05 Ru-105 1.12E+OO O.OOE+OO 4.34E-01 O.OOE+OO 1.41 E+OO 1.82E+04 9.04E+04 Ru-106 9.84E+04 O.OOE+OO 1.24E+04 O.OOE+OO 1.90E+05 1.61E+07 9.60E+05 Ag-110M 1.38E+04 1.31 E+04 7.99E+03 O.OOE+OO 2.50E+04 6.75E+06 2.73E+05 Page 209 of 267
Revision 5 Aug 31, 2015 Table F-11 a (Continued) Teen Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 4.88E+03 2.24E+03 6.67E+02 1.40E+03 O.OOE+OO 5.36E+05 7.50E+04 Te-127M 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.66E+06 1.59E+05 Te-127 2.01E+OO 9.12E-01 4.42E-01 1.42E+OO 7.28E+OO 1.12E+04 8.08E+04 Te-129M 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 Te-129 7.10E-02 3.38E-02 1.76E-02 5.18E-02 2.66E-01 3.30E+03 1.62E+03 Te-131 M 9.84E+01 6.01E+01 4.02E+01 7.25E+01 4.39E+02 2.38E+05 6.21E+05 Te-131 1.58E-02 8.32E-03 5.04E-03 1.24E-02 6.18E-02 2.34E+03 1.51 E+01 Te-132 3.60E+02 2.90E+02 2.19E+02 2.46E+02 1.95E+03 4.49E+05 4.63E+05 1-130 6.24E+03 1.79E+04 7.17E+03 1.49E+06 2.75E+04 O.OOE+OO 9.12E+03 1-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 O.OOE+OO 6.49E+03 1-132 1.59E+03 4.38E+03 1.58E+03 1.51E+05 6.92E+03 O.OOE+OO 1.27E+03 1-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 O.OOE+OO 1.03E+04 1-134 8.88E+02 2.32E+03 8.40E+02 3.95E+04 3.66E+03 O.OOE+OO 2.04E+01 1-135 3.70E+03 9.44E+03 3.49E+03 6.21E+05 1.49E+04 O.OOE+OO 6.95E+Q3 Cs-134 5.02E+05 1.13E+06 5.49E+05 O.OOE+OO 3.75E+05 1.46E+05 9.76E+03 Cs-136 5.15E+04 1.94E+05 1.37E+05 O.OOE+OO 1.10E+05 1.78E+04 1.09E+04 Cs-137 6.70E+05 8.48E+05 3.11E+05 O.OOE+OO 3.04E+05 1.21 E+05 8.48E+03 Cs-138 4.66E+02 8.56E+02 4.46E+02 O.OOE+OO 6.62E+02 7.87E+01 2.70E-01 Ba-139 1.34E+OO 9.44E-04 3.90E-02 O.OOE+OO 8.88E-04 6.46E+03 6.45E+03 Ba-140 5.47E+04 6.70E+01 3.52E+03 O.OOE+OO 2.28E+01 2.03E+06 2.29E+05 Ba-141 1.42E-01 1.06E-04 4.74E-03 O.OOE+OO 9.84E-05 3.29E+03 7.46E-04 Ba-142 3.70E-02 3.70E-05 2.27E-03 O.OOE+OO 3.14E-05 1.91 E+03 4.79E-10 La-140 4.79E+02 2.36E+02 6.26E+01 O.OOE+OO O.OOE+OO 2.14E+05 4.87E+05 La-142 9.60E-01 4.25E-01 1.06E-01 O.OOE+OO O.OOE+OO 1.02E+04 1.20E+04 Ce-141 2.84E+04 1.90E+04 2.17E+03 O.OOE+OO 8.88E+03 6.14E+05 1.26E+05 Ce-143 2.66E+02 1.94E+02 2.16E+01 O.OOE+OO 8.64E+01 1.30E+05 2.55E+05 Ce-144 4.89E+06 2.02E+06 2.62E+05 O.OOE+OO 1.21 E+06 1.34E+07 8.64E+05 Pr-143 1.34E+04 5.31E+03 6.62E+02 O.OOE+OO 3.09E+03 4.83E+05 2.14E+05 Pr-144 4.30E-02 1.76E-02 2.18E-03 O.OOE+OO 1.01 E-02 1.75E+03 2.35E-04 Nd-147 7.86E+03 8.56E+03 5.13E+02 O.OOE+OO 5.02E+03 3.72E+05 1.82E+05 W-187 1.20E+01 9.76E+OO 3.43E+OO O.OOE+OO O.OOE+OO 4.74E+04 1.77E+05 Np-239 3.38E+02 2.88E+02 1.77E+01 O.OOE+OO 1.00E+02 6.49E+04 1.32E+05 Notes: 3
- 1) Units are mrem/yr per µCi/m .
Page 210 of 267
Revision 5 Aug 31, 2015 Table F-11b Child Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 6.40E+02 6.40E+02 6.40E+02 6.40E+02 6.40E+02 6.40E+02 Na-24 1.61 E+04 1.61 E+04 1.61E+04 1.61E+04 1.61E+04 1.61 E+04 1.61 E+04 Cr-51 O.OOE+OO O.OOE+OO 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 Mn-54 O.OOE+OO 4.29E+04 9.51E+03 O.OOE+OO 1.00E+04 1.58E+06 2.29E+04 Mn-56 O.OOE+OO 1.66E+OO 3.12E-01 O.OOE+OO 1.67E+OO 1.31 E+04 1.23E+05 Fe-55 4.74E+04 2.52E+04 7.77E+03 O.OOE+OO O.OOE+OO 1.11 E+05 2.87E+03 Fe-59 2.07E+04 3.34E+04 1.67E+04 O.OOE+OO O.OOE+OO 1.27E+06 7.07E+04 Co-58 O.OOE+OO 1.77E+03 3.16E+03 O.OOE+OO O.OOE+OO 1.11E+06 3.44E+04 Co-60 O.OOE+OO 1.31 E+04 2.26E+04 O.OOE+OO O.OOE+OO 7.07E+06 9.62E+04 Ni-63 8.21E+05 4.63E+04 2.80E+04 O.OOE+OO O.OOE+OO 2.75E+05 6.33E+03 Ni-65 2.99E+OO 2.96E-01 1.64E-01 O.OOE+OO O.OOE+OO 8.18E+03 6.40E+04 Cu-64 O.OOE+OO 1.99E+OO 1.0?E+OO O.OOE+OO 6.03E+OO 9.58E+03 3.67E+04 Zn-65 4.26E+04 1.13E+05 7.03E+04 O.OOE+OO 7.14E+04 9.95E+05 1.63E+04 Zn-69 6.?0E-02 9.66E-02 8.92E-03 O.OOE+OO 5.85E-02 1.42E+03 1.02E+04 Br-83 O.OOE+OO O.OOE+OO 4.74E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 5.48E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 2.53E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.98E+05 1.14E+05 O.OOE+OO O.OOE+OO O.OOE+OO 7.99E+03 Rb-88 O.OOE+OO 5.62E+02 3.66E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.72E+01 Rb-89 O.OOE+OO 3.45E+02 2.90E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.89E+OO Sr-89 5.99E+05 O.OOE+OO 1.72E+04 O.OOE+OO O.OOE+OO 2.16E+06 1.67E+05 Sr-90 3.85E+07 O.OOE+OO 7.66E+05 O.OOE+OO O.OOE+OO 1.48E+07 3.43E+05 Sr-91 1.21 E+02 O.OOE+OO 4.59E+OO O.OOE+OO O.OOE+OO 5.33E+04 1.74E+05 Sr-92 1.31 E+01 O.OOE+OO 5.25E-01 O.OOE+OO O.OOE+OO 2.40E+04 2.42E+05 Y-90 4.11 E+03 O.OOE+OO 1.11 E+02 O.OOE+OO O.OOE+OO 2.62E+05 2.68E+05 Y-91M 5.0?E-01 O.OOE+OO 1.84E-02 O.OOE+OO O.OOE+OO 2.81E+03 1.72E+03 Y-91 9.14E+05 O.OOE+OO 2.44E+04 O.OOE+OO O.OOE+OO 2.63E+06 1.84E+05 Y-92 2.04E+01 O.OOE+OO 5.81 E-01 O.OOE+OO O.OOE+OO 2.39E+04 2.39E+05 Y-93 1.86E+02 O.OOE+OO 5.11 E+OO O.OOE+OO O.OOE+OO 7.44E+04 3.89E+05 Zr-95 1.90E+05 4.18E+04 3.70E+04 O.OOE+OO 5.96E+04 2.23E+06 6.11 E+04 Zr-97 1.88E+02 2.72E+01 1.60E+01 O.OOE+OO 3.89E+01 1.13E+05 3.51E+05 Nb-95 2.35E+04 9.18E+03 6.55E+03 O.OOE+OO 8.62E+03 6.14E+05 3.70E+04 Mo-99 O.OOE+OO 1.72E+02 4.26E+01 O.OOE+OO 3.92E+02 1.35E+05 1.27E+05 Tc- 99M 1.78E-03 3.48E-03 5.77E-02 O.OOE+OO 5.0?E-02 9.51E+02 4.81E+03 Tc-101 8.10E-05 8.51 E-05 1.08E-03 O.OOE+OO 1.45E-03 5.85E+02 1.63E+01 Ru-103 2.79E+03 O.OOE+OO 1.07E+03 O.OOE+OO 7.03E+03 6.62E+05 4.48E+04 Ru-105 1.53E+OO O.OOE+OO 5.55E-01 O.OOE+OO 1.34E+OO 1.59E+04 9.95E+04 Ru-106 1.36E+05 O.OOE+OO 1.69E+04 O.OOE+OO 1.84E+05 1.43E+07 4.29E+05 Ag-110M 1.69E+04 1.14E+04 9.14E+03 O.OOE+OO 2.12E+04 5.48E+06 1.00E+05 Page 211 of 267
Revision 5 Aug 31, 2015 Table F-11 b (Continued) Child Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 O.OOE+OO 4.77E+05 3.38E+04 Te-127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 Te-127 2.77E+OO 9.51 E-01 6.11 E-01 1.96E+OO 7.07E+OO 1.00E+04 5.62E+04 Te-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 Te-129 9.77E-02 3.50E-02 2.38E-02 7.14E-02 2.57E-01 2.93E+03 2.55E+04 Te-131 M 1.34E+02 5.92E+01 5.07E+01 9.77E+01 4.00E+02 2.06E+05 3.08E+05 Te-131 2.17E-02 8.44E-03 6.59E-03 1.70E-02 5.88E-02 2.05E+03 1.33E+03 Te-132 4.81E+02 2.72E+02 2.63E+02 3.17E+02 1.77E+03 3.77E+05 1.38E+05 1-130 8.18E+03 1.64E+04 8.44E+03 1.85E+06 2.45E+04 O.OOE+OO 5.11E+03 1-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 O.OOE+OO 2.84E+03 1-132 2.12E+03 4.07E+03 1.88E+03 1.94E+05 6.25E+03 O.OOE+OO 3.20E+03 1-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+Q4 O.OOE+OO 5.48E+03 1-134 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 O.OOE+OO 9.55E+02 1-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 O.OOE+OO 4.44E+03 Cs-134 6.51E+05 1.01 E+06 2.25E+05 O.OOE+OO 3.30E+05 1.21E+05 3.85E+03 Cs-136 6.51E+04 1.71 E+05 1..16E+05 O.OOE+OO 9.55E+04 1.45E+04 4.18E+03 Cs-137 9.07E+05 8.25E+05 1.28E+05 O.OOE+OO 2.82E+05 1.04E+05 3.62E+03 Cs-138 6.33E+02 8.40E+02 5.55E+02 O.OOE+OO 6.22E+02 6.81 E+01 2.70E+02 Ba-139 1.84E+OO 9.84E-04 5.37E..:02 O.OOE+OO 8.62E~04 5.77E+03 5.77E+04 Ba-140 7.40E+04 6.48E+01 4.33E+03 O.OOE+OO 2.11 E+01 1.74E+06 1.02E+05 Ba-141 1.96E-01 1.09E-04 6.36E-03 O.OOE+OO 9.47E-05 2.92E+03 2.75E+02 Ba-142 5.00E-02 3.60E-05 2.79E-03 O.OOE+OO 2.91E-05 1.64E+03 2.74E+OO La-140 6.44E+02 2.25E+02 7.55E+01 O.OOE+OQ O.OOE+OO 1.83E+05 2.26E+05 La-142 1.30E+OO 4.11 E-01 1.29E-01 O.OOE+OO O.OOE+OO 8.70E+03 7.59E+04 Ce-141 3.92E+04 1.95E+04 2.90E+03 O.OOE+OO 8.55E+03 5.44E+05 5.66E+04 Ce-143 3.66E+02 1.99E+02 2.87E+01 O.OOE+OO 8.36E+01 1.15E+05 1.27E+05 Ce-144 6.77E+06 2.12E+06 3.61E+05 O.OOE+OO. 1.17E+06 1.20E+07 3.89E+05 Pr-143 1.85E+04 5.55E+03 9.14E+02 O.OOE+OO 3.00E+03 4.33E+05 9.73E+04 Pr-144 5.96E-02 1.85E-02 3.00E-03 O.OOE+OO 9.77E-03 1.57E+03 1.97E+02 Nd-147 1.08E+04 8.73E+03 6.81E+02 O.OOE+OO 4.81E+03 3.28E+05 8.21E+04 W-187 1.63E+01 9.66E+OO 4.33E+OO O.OOE+OO O.OOE+OO 4.11 E+04 9.10E+04 Np-239 4.66E+02 3.01E+02 2.35E+01 O.OOE+OO 9.73E+01 5.81E+04 6.40E+04 Notes: 3
- 1) Units are mrem/yr per µCi/m .
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Revision 5 Aug 31, 2015 Table F-11c Infant Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 Na-24 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 Cr-51 O.OOE+OO O.OOE+OO 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 Mn-54 O.OOE+OO 2.53E+04 4.98E+03 O.OOE+OO 4.98E+03 1.00E+06 7.06E+03 Mn-56 O.OOE+OO 1.54E+OO 2.21E-01 O.OOE+OO 1.10E+OO 1.25E+04 7.17E+04 Fe-55 1.97E+04 1.17E+04 3.33E+03 O.OOE+OO O.OOE+OO 8.69E+04 1.09E+03 Fe-59 1.36E+04 2.35E+04 9.48E+03 O.OOE+OO O.OOE+OO 1.02E+06 2.48E+04 Co-58 O.OOE+OO 1.22E+03 1.82E+03 O.OOE+OO O.OOE+OO 7.77E+05 1.11E+04 Co-60 O.OOE+OO 8.02E+03 1.18E+04 O.OOE+OO O.OOE+OO 4.51E+06 .3.19E+04 Ni-63 3.39E+05 2.04E+04 1.16E+04 O.OOE+OO O.OOE+OO 2.09E+05 2.42E+03 Ni-65 2.39E+OO 2.84E-01 1.23E-01 O.OOE+OO O.OOE+OO 8.12E+03 5.01E+04 Cu-64 O.OOE+OO 1.88E+OO 7.74E-01 O.OOE+OO 3.98E+OO 9.30E+03 1.50E+04 Zn-65 1.93E+04 6.26E+04 3.11 E+04 O.OOE+OO 3.25E+04 6.47E+05 5.14E+04 Zn-69 5.39E-02 9.67E-02 7.18E-03 O.OOE+OO 4.02E-02 1.47E+03 1.32E+04 Br-83 O.OOE+OO O.OOE+OO 3.81E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 4.00E+02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO 2.04E+01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.90E+05 8.82E+04 O.OOE+OO O.OOE+OO O.OOE+OO 3.04E+03 Rb-88 O.OOE+OO 5.57E+02 2.87E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.39E+02 Rb-89 O.OOE+OO 3.21E+02 2.06E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.82E+01 Sr-89 3.98E+05 O.OOE+OO 1.14E+04 O.OOE+OO O.OOE+OO 2.03E+06 6.40E+04 Sr-90 1.55E+07 O.OOE+OO 3.12E+05 O.OOE+OO O.OOE+OO 1.12E+07 1.31 E+05 Sr-91 9.56E+01 O.OOE+OO 3.46E+OO O.OOE+OO O.OOE+OO 5.26E+04 7.34E+04 Sr-92 1.05E+01 O.OOE+OO 3.91 E-01 O.OOE+OO O.OOE+OO 2.38E+04 1.40E+05 Y-90 3.29E+03 O.OOE+OO 8.82E+01 O.OOE+OO O.OOE+OO 2.69E+05 1.04E+05 Y-91M 4.0?E-01 O.OOE+OO 1.39E-02 O.OOE+OO O.OOE+OO 2.79E+03 2.35E+03 Y-91 5.88E+05 O.OOE+OO 1.57E+04 O.OOE+OO O.OOE+OO 2.45E+06 7.03E+04 Y-92 1.64E+01 O.OOE+OO 4.61 E-01 O.OOE+OO O.OOE+OO 2.45E+04 1.27E+05 Y-93 1.50E+02 O.OOE+OO 4.07E+OO O.OOE+OO O.OOE+OO 7.64E+04 1.67E+05 Zr-95 1.15E+05 2.79E+04 2.03E+04 O.OOE+OO 3.11 E+04 1.75E+06 2.17E+04 Zr-97 1.50E+02 2.56E+01 1.17E+01 O.OOE+OO 2.59E+01 1.10E+05 1.40E+05 Nb-95 1.57E+04 6.43E+03 3.78E+03 O.OOE+OO 4.72E+03 4.79E+05 1.27E+04 Mo-99 O.OOE+OO 1.65E+02 3.23E+01 O.OOE+OO 2.65E+02 1.35E+05 4.87E+04 Tc- 99M 1.40E-03 2.88E-03 3.72E-02 O.OOE+OO 3.11 E-02 8.11E+02 2.03E+03 Tc-101 6.51 E-05 8.23E-05 8.12E-04 O.OOE+OO 9.79E-04 5.84E+02 8.44E+02 Ru-103 2.02E+03 O.OOE+OO 6.79E+02 O.OOE+OO 4.24E+03 5.52E+05 1.61E+04 Ru-105 1.22E+OO O.OOE+OO 4.10E-01 O.OOE+OO 8J;)9E-01 1.57E+04 4.84E+04 Ru-106 8.68E+04 O.OOE+OO 1.09E+04 O.OOE+OO 1.07E+05 1.16E+07 1.64E+05 Ag-110M 9.98E+03 7.22E+03 5.00E+03 O.OOE+OO 1.09E+04 3.67E+06 3.30E+04 Page 213 of 267
Revision 5 Aug 31, 2015 Table F-11c (Continued) Infant Inhalation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 4.76E+03 1.99E+03 6.58E+02 1.62E+03 O.OOE+OO 4.47E+05 1.29E+04 Te-127M 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31 E+06 2.73E+04 Te-127 2.23E+OO 9.53E-01 4.89E-01 1.85E+OO 4.86E+OO 1.03E+04 2.44E+04 Te-129M 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 Te-129 7.88E-02 3.47E-02 1.88E-02 6.75E-02 1.75E-01 3.00E+03 2.63E+04 Te-131 M 1.07E+02 5.50E+01 3.63E+01 8.93E+01 2.65E+02 1.99E+05 1.19E+05 Te-131 1.74E-02 8.22E-03 5.00E-03 1.58E-02 3.99E-02 2.06E+03 8.22E+03 Te-132 3.72E+02 2.37E+02 1.76E+02 2.79E+02 1.03E+03 3.40E+05 4.41E+04 1-130 6.36E+03 1.39E+04 5.57E+03 1.60E+06 1.53E+04 O.OOE+OO 1.99E+03 1-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 O.OOE+OO 1.06E+03 1-132 1.69E+03 3.54E+03 1.26E+03 1.69E+05 3.95E+03 O.OOE+OO 1.90E+03 1-133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 O.OOE+OO 2.16E+03 1-134 9.21E+02 1.88E+03 6.65E+02 4.45E+04 2.09E+03 O.OOE+OO 1.29E+03 1-135 3.86E+03 7.60E+03 2.77E+03 6.96E+05 8.47E+03 O.OOE+OO 1.83E+03 Cs-134 3.96E+05 7.03E+05 7.45E+04 O.OOE+OO 1.90E+05 7.97E+04 1.33E+03 Cs-136 4.83E+04 1.35E+05 5.29E+04 O.OOE+OO 5.64E+04 1.18E+04 1.43E+03 Cs-137 5.49E+05 6.12E+05 4.55E+04 O.OOE+OO 1.72E+05 7.13E+04 1.33E+03 Cs-138 5.05E+02 7.81E+02 3.98E+02 O.OOE+OO 4.10E+02 6.54E+01 8.76E+02 Ba-139 1.48E+OO 9.84E-04 4.30E-02 O.OOE+OO 5.92E-04 5.95E+03 5.10E+04 Ba-140 5.60E+04 5.60E+01 2.90E+03 O.OOE+OO 1.34E+01 1.60E+06 3.84E+04 Ba-141 1.57E-01 1.08E-04 4.97E-03 O.OOE+OO 6.50E-05 2.97E+03 4.75E+03 Ba-142 3.98E-02 3.30E-05 1.96E-03 O.OOE+OO 1.90E-05 1.55E+03 6.93E+02 La-140 5.05E+02 2.00E+02 5.15E+01 O.OOE+OO O.OOE+OO 1.68E+05 8.48E+04 La-142 1.03E+OO 3.77E-01 9.04E-02 O.OOE+OO O.OOE+OO 8.22E+03 5.95E+04 Ce-141 2.77E+04 1.67E+04 1.99E+03 O.OOE+OO 5.25E+03 5.17E+05 2.16E+04 Ce-143 2.93E+02 1.93E+02 2.21E+01 O.OOE+OO 5.64E+01 1.16E+05 4.97E+04 Ce-144 3.19E+06 1.21E+06 1.76E+05 O.OOE+OO 5.38E+05 9.84E+06 1.48E+05 Pr-143 1.40E+04 5.24E+03 6.99E+02 O.OOE+OO 1.97E+03 4.33E+05 3.72E+04 Pr-144 4.79E-02 1.85E-02 2.41 E-03 O.OOE+OO 6.72E-03 1.61 E+03 4.28E+03 Nd-147 7.94E+03 8.13E+03 5.00E+02 O.OOE+OO 3.15E+03 3.22E+05 3.12E+04 W-187 1.30E+01 9.02E+OO 3.12E+OO O.OOE+OO O.OOE+OO 3.96E+04 3.56E+04 Np-239 3.71E+02 2.98E+02 1.88E+01 O.OOE+OO 6.62E+01 5.95E+04 2.49E+04 Notes: 3
- 1) Units are mrem/yr per µCi/m .
Page 214 of 267
Revision 5 Aug 31, 2015 Table F-12 Adult Vegetation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.29E+03 1.29E+03 1.29E+03 1.29E+03 1.29E+03 1.29E+03 Na-24 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 Cr-51 O.OOE+OO O.OOE+OO 4.64E+04 2.77E+04 1.02E+04 6.15E+04 1.17E+07 Mn-54 O.OOE+OO 3.13E+08 5.97E+07 O.OOE+OO 9.31E+07 O.OOE+OO 9.58E+08 Mn-56 O.OOE+OO 1.54E+01 2.73E+OO O.OOE+OO 1.95E+01 O.OOE+OO 4.91E+02 Fe-55 2.10E+08 1.45E+08 3.38E+07 O.OOE+OO O.OOE+OO 8.08E+07 8.31E+07 Fe-59 1.26E+08 2.96E+08 1.13E+08 O.OOE+OO O.OOE+OO 8.27E+07 9.87E+08 Co-58 O.OOE+OO 3.08E+07 6.90E+07 O.OOE+OO O.OOE+OO O.OOE+OO 6.24E+08 Co-60 O.OOE+OO 1.67E+08 3.69E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.14E+09 Ni-63 1.04E+10 7.21E+08 3.49E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.50E+08 Ni-65 5.97E+01 7.75E+OO 3.54E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.97E+02 Cu-64 O.OOE+OO 9.09E+03 4.27E+03 O.OOE+OO 2.29E+04 O.OOE+OO 7.75E+05 Zn-65 3.17E+08 1.01 E+09 4.56E+08 O.OOE+OO 6.75E+08 O.OOE+OO 6.36E+08 Zn-69 4.95E-06 9.48E-06 6.59E-07 O.OOE+OO 6.16E-06 O.OOE+OO 1.42E-06 Br-83 O.OOE+OO O.OOE+OO 3.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.32E+OO Br-84 O.OOE+OO O.OOE+OO 2.20E-11 O.OOE+OO O.OOE+OO O.OOE+OO 1.72E-16 Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.20E+08 1.03E+08 O.OOE+OO O.OOE+OO O.OOE+OO 4.34E+07 Rb-88 O.OOE+OO *o.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO $r-89 9.95E+09 O.OOE+OO 2.86E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.60E+09 Sr-90 6.95E+11 O.OOE+OO 1.40E+10 O.OOE+OO O.OOE+OO O.OOE+OO 1.75E+10 Sr-91 3.01E+05 O.OOE+OO 1.22E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.43E+06 Sr-92 4.12E+02 O.OOE+OO 1.78E+01 O.OOE+OO O.OOE+OO O.OOE+OO 8.17E+03 Y-90 1.33E+04 O.OOE+OO 3.57E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.41E+08 Y-91M 4.93E-09 O.OOE+OO 1.91 E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.45E-08 Y-91 5.12E+06 O.OOE+OO 1.37E+05 O.OOE+OO O.OOE+OO O.OOE+OO 2.82E+09 Y-92 8.95E-01 O.OOE+OO 2.62E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.57E+04 Y-93 1.67E+02 O.OOE+OO 4.62E+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.31E+06 Zr-95 1.18E+06 3.77E+05 2.55E+05 O.OOE+OO 5.92E+05 O.OOE+OO 1.20E+09 Zr-97 3.35E+02 6.77E+01 3.09E+01 O.OOE+OO 1.02E+02 O.OOE+OO 2.10E+07 Nb-95 1.43E+05 7.95E+04 4.27E+04 O.OOE+OO 7.86E+04 O.OOE+OO 4.83E+08 Mo-99 O.OOE+OO 6.14E+06 1.17E+06 O.OOE+OO 1.39E+07 O.OOE+OO 1.42E+07 Tc- 99M 3.06E+OO 8.64E+OO 1.10E+02 O.OOE+OO 1.31 E+02 4.23E+OO 5.11 E+03 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 4.77E+06 O.OOE+OO 2.05E+06 O.OOE+OO 1.82E+07 O.OOE+OO 5.57E+08 Ru-105 5.27E+01 O.OOE+OO 2.08E+01 O.OOE+OO 6.81E+02 O.OOE+OO 3.23E+04 Ru-106 1.93E+08 O.OOE+OO 2.44E+07 O.OOE+OO 3.72E+08 O.OOE+OO 1.25E+10 Ag-110M 1;05E+07 9.75E+06 5.79E+06 O.OOE+OO 1.92E+07 O.OOE+OO 3.98E+09 Page 215 of 267
Revision 5 Aug 31, 2015 Table F-12 (Continued) Adult Vegetation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 9.67E+07 3.50E+07 1.30E+07 2.91E+07 3.93E+08 O.OOE+OO 3.86E+08 Te-127M 3.49E+08 1.25E+08 4.26E+07 8.92E+07 1.42E+09 O.OOE+OO 1.17E+09 Te-127 5.68E+03 2.04E+03 1.23E+03 4.21E+03 2.31E+04 O.OOE+OO 4.48E+05 Te-129M 2.51E+08 9.37E+07 3.97E+07 8.62E+07 1.05E+09 O.OOE+OO 1.26E+09 Te-129 7.14E-04 2.68E-04 1.74E-04 5.48E-04 3.00E-03 O.OOE+OO 5.39E-04 Te-131M 9.09E+05 4.45E+05 3.71E+05 7.04E+05 4.50E+06 O.OOE+OO 4.41E+07 Te-131 1.26E-15 5.26E-16 3.97E-16 1.03E-15 5.51 E-15 O.OOE+OO 1.78E-16 Te-132 4.28E+06 2.77E+06 2.60E+06 3.06E+06 2.67E+07 O.OOE+OO 1.31E+08 1-130 3.89E+05 1.15E+06 4.52E+05 9.72E+07 1.79E+06 O.OOE+OO 9.87E+05 1-131 8.07E+07 1.15E+08 6.62E+07 3.78E+10 1.98E+08 O.OOE+OO 3.05E+07 1-132 5.58E+01 1.49E+02 5.22E+01 5.22E+03 2.38E+02 O.OOE+OO 2.80E+01 1-133 2.08E+06 3.62E+06 1.10E+06 5.32E+08 6.31E+06 O.OOE+OO 3.25E+06 1-134 8.55E-05 2.32E-04 8.31 E-05 4.02E-03 3.69E-04 O.OOE+OO 2.02E-07 1-135 3.87E+04 1.01E+05 3.74E+04 6.68E+06 1.62E+05 O.OOE+OO 1.14E+05 Cs-134 4.67E+09 1.11E+10 9.08E+09 O.OOE+OO 3.59E+09 1.19E+09 1.94E+08 Cs-136 4.25E+07 1.68E+08 1.21E+08 O.OOE+OO 9.33E+07 1.28E+07 1.90E+07 Cs-137 6.36E+09 8.70E+09 5.70E+09 O.OOE+OO 2.95E+09 9.81E+08 1.68E+08 Cs-138 3.32E-11 6.56E-11 3.25E-11 O.OOE+OO 4.82E-11 4.76E-12 2.80E-16 Ba-139 2.71 E-02 1.93E-05 7.92E~04 O.OOE+OO 1.80E-05 1.09E-05 4.80E-02 Ba-140 1.29E+08 1.61E+05 8.42E+06 O.OOE+OO 5.49E+04 9.24E+04 2.65E+08 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 1.98E+03 9.97E+02 2.63E+02 O.OOE+OO O.OOE+OO O.OOE+OO 7.32E+07 La-142 1.94E-04 8.83E-05 2.20E-05 O.OOE+OO O.OOE+OO O.OOE+OO 6.45E-01 Ce-141 1.97E+05 1.33E+05 1.51 E+04 O.OOE+OO 6.19E+04 O.OOE+OO 5.09E+08 Ce-143 9.94E+02 7.35E+05 8.13E+01 O.OOE+0.0 3.24E+02 O.OOE+OO 2.75E+07 Ce-144 3.29E+07 1.38E+07 1.77E+06 O.OOE+OO 8.16E+06 O.OOE+OO 1.11E+10 Pr-143 6.27E+04 2.51E+04 3.11 E+03 O.OOE+OO 1.45E+04 O.OOE+OO 2.75E+08 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 3.37E+04 3.90E+04 2.33E+03 O.OOE+OO 2.28E+04 O.OOE+OO 1.87E+08 W-187 3.79E+04 3.17E+04 1.11E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E+07 Np-239 1.42E+03 1.40E+02 7.72E+01 O.OOE+OO 4.37E+02 O.OOE+OO 2.87E+07 Notes:
- 1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.
3
- 2) For H-3, the units are mrem/yr per µCi/m .
Page 216 of 267
Revision 5 Aug 31, 2015 Table F-12a Teen Vegetation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.47E+03 1.47E+03 1.47E+03 1.47E+03 1.47E+03 1.47E+03 Na-24 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 Cr-51 O.OOE+OO O.OOE+OO 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 Mn-54 O.OOE+OO 4.54E+08 9.01E+07 O.OOE+OO 1.36E+08 O.OOE+OO 9.32E+08 Mn-56 O.OOE+OO 1.39E+01 2.47E+OO O.OOE+OO 1.76E+01 O.OOE+OO 9.13E+02 Fe-55 3.26E+08 2.31E+08 5.39E+07 O.OOE+OO O.OOE+OO 1.47E+08 1.00E+08 Fe-59 1.79E+08 4.18E+08 1.61 E+08 O.OOE+OO O.OOE+OO 1.32E+08 9.89E+08 Co-58 O.OOE+OO 4.37E+07 1.01 E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.02E+08 Co-60 O.OOE+OO 2.49E+08 5.60E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.24E+09 Ni-63 1.61 E+10 1.13E+09 5.45E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.81 E+08 Ni-65 5.55E+01 7.10E+OO 3.23E+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.85E+02 Cu-64 O.OOE+OO 8.24E+03 3.87E+03 O.OOE+OO 2.08E+04 O.OOE+OO 6.39E+05 Zn-65 4.24E+08 1.47E+09 6.86E+08 O.OOE+OO 9.41E+08 O.OOE+OO 6.23E+08 Zn-69 4.64E-06 8.84E-06 6.19E-07 O.OOE+OO 5.78E-06 O.OOE+OO 1.63E-05 Br-83 O.OOE+OO O.OOE+OO 2.81E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO 2.00E-11 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.75E+08 1.29E+08 O.OOE+OO O.OOE+OO O.OOE+OO 4.06E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 1.51E+10 O.OOE+OO 4.33E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.80E+09 Sr-90 9.22E+11 O.OOE+OO 1.84E+10 O.OOE+OO O.OOE+OO O.OOE+OO *2.11E+10 Sr-91 2.81E+05 O.OOE+OO 1.12E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.27E+06 Sr-92 3.84E+02 O.OOE+OO 1.64E+01 O.OOE+OO O.OOE+OO O.OOE+OO 9.78E+03 Y-90 1.24E+04 O.OOE+OO 3.35E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E+08 Y-91M 4.59E-09 O.OOE+OO 1.75E-10 O.OOE+OO O.OOE+OO O.OOE+OO 2.17E-07 Y-91 7.84E+06 O.OOE+OO 2.10E+05 O.OOE+OO O.OOE+OO O.OOE+OO 3.21E+09 Y-92 8.41 E-01 O.OOE+OO 2.43E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.31E+04 Y-93 1.57E+02 O.OOE+OO 4.30E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.80E+06 Zr-95 1.72E+06 5.44E+05 3.74E+05 O.OOE+OO 7.99E+05 O.OOE+OO 1.26E+09 Zr-97 3.10E+02 6.14E+01 2.83E+01 O.OOE+OO 9.31 E+01 O.OOE+OO 1.66E+07 Nb-95 1.93E+05 1.07E+05 5.90E+04 O.OOE+OO 1.04E+05 O.OOE+OO 4.58E+08 Mo-99 O.OOE+OO 5.63E+06 1.07E+06 O.OOE+OO 1.29E+07 O.OOE+OO 1.01 E+07 Tc- 99M 2.70E+OO 7.52E+OO 9.75E+01 O.OOE+OO 1.12E+02 4.17E+OO 4.94E+03 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 6.82E+06 O.OOE+OO 2.91E+06 O.OOE+OO 2.40E+07 O.OOE+OO 5.69E+08 Ru-105 4.90E+01 O.OOE+OO 1.90E+01 O.OOE+OO 6.18E+02 O.OOE+OO 3.95E+04 Ru-106 3.09E+08 O.OOE+OO 3.90E+07 O.OOE+OO 5.97E+08 O.OOE+OO 1.48E+10 Ag-110M 1.52E+07 1.44E+07 8.73E+06 O.OOE+OO 2.74E+07 O.OOE+OO 4.03E+09 Page 217 of 267
Revision 5 Aug 31, 2015 Table F-12a (Continued) Teen Vegetation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 1.49E+08 5.35E+07 1.99E+07 4.15E+07 O.OOE+OO O.OOE+OO 4.38E+08 Te-127M 5.51E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 O.OOE+OO 1.37E+09 Te-127 5.36E+03 1.90E+03 1.15E+03 3.70E+03 2.17E+04 O.OOE+OO 4.14E+05 Te-129M 3.61 E+08 1.34E+08 5.72E+07 1.17E+08 1.51 E+09 O.OOE+OO 1.36E+09 Te-129 6.68E-04 2.49E-04 1.63E-04 4.77E-04 2.80E-03 O.OOE+OO 3.65E-03 Te-131 M 8.42E+05 4.04E+05 3.37E+05 6.07E+05 4.21E+06 O.OOE+OO 3.24E+07 Te-131 1.17E-15 4.82E-16 3.66E-16 9.01 E-16 5.11E-15 O.OOE+OO 9.60E-17 Te-132 3.89E+06 2.46E+06 2.32E+06 2.60E+06 2.36E+07 O.OOE+OO 7.81E+07 1-130 3.47E+05 1.01 E+06 4.01E+05 8.20E+07 1.55E+06 O.OOE+OO 7.73E+05 1-131 7.68E+07 1.08E+08 5.78E+07 3.14E+10 1.85E+08 O.OOE+OO 2.13E+07 1-132 5.03E+01 1.32E+02 4.72E+01 4.43E+03 2.07E+02 O.OOE+OO 5.73E+01 1-133 1.93E+06 3.28E+06 1.00E+06 4.58E+08 5.75E+06 O.OOE+OO 2.48E+06 1-134 7.73E-05 2.05E-04 7.36E-05 3.41 E-03 3.23E-04 O.OOE+OO 2.70E-06 1-135 3.49E+04 8.99E+04 3.33E+04 5.78E+06 1.42E+05 O.OOE+OO 9.97E+04 Cs-134 7.10E+09 1.67E+10 7.75E+09 O.OOE+OO 5.31E+09 2.03E+09 2.08E+08 Cs-136 4.35E+07 1.71E+08 1.15E+08 O.OOE+OO 9.31E+07 1.47E+07 1.38E+07 Cs-137 1.01 E+10 1.35E+10 4.69E+09 O.OOE+OO 4.59E+09 1.78E+09 1.92E+08 Cs-138 3.07E-11 5.89E-11 2.94E-11 O.OOE+OO 4.35E-11 5.06E-12 2.67E-14 Ba-139 2.55E-02 1.79E-05 7.42E-04 O.OOE+OO 1.69E-05 1.23E-05 2.27E-01 Ba-140 1.38E+08 1.69E+05 8.90E+06 O.OOE+OO 5.74E+04 1.14E+05 2.13E+08 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 1.81 E+03 8.88E+02 2.36E+02 O.OOE+OO O.OOE+OO O.OOE+OO 5.10E+07 La-142 1.78E-04 7.92E-05 1.97E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.41E+OO Ce-141 2.83E+05 1.89E+05 2.17E+04 O.OOE+OO 8.89E+04 O.OOE+OO 5.40E+08 Ce-143 9.29E+02 6.76E+05 7.55E+01 O.OOE+OO 3.03E+02 O.OOE+OO 2.03E+07 Ce-144 5.27E+07 2.18E+07 2.83E+06 O.OOE+OO 1.30E+07 O.OOE+OO 1.33E+10 Pr-143 7.01E+04 2.80E+04 3.49E+03 O.OOE+OO 1.63E+04 O.OOE+OO 2.31E+08 Pr-144 0.00,E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 3.67E+04 4.00E+04 2.39E+03 O.OOE+OO 2.35E+04 O.OOE+OO 1.44E+08 W-187 3.53E+04 2.87E+04 1.01 E+04 O.OOE+OO O.OOE+OO O.OOE+OO 7.78E+06 Np-239 1.38E+03 1.30E+02 7.24E+01 O.OOE+OO 4.09E+02 O.OOE+OO 2.10E+07 Notes:
- 1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.
3
- 2) For H-3, the units are mrem/yr per µCi/m .
Page 218 of 267
Revision 5 Aug 31, 2015 Table F-12b Child Vegetation Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H~3 O.OOE+OO 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 Na-24 3.73E+05 3.73E+05 3.73E+05 3.73E+05 3.73E+05 3.73E+05 3.73E+05 Cr-51 O.OOE+OO O.OOE+OO 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+b6 Mn-54 O.OOE+OO 6.65E+08 1.77E+08 O.OOE+OO 1.86E+08 O.OOE+OO 5.58E+08 Mn-56 O.OOE+OO 1.82E+01 4.10E+OO O.OOE+OO 2.20E+01 O.OOE+OO 2.63E+03 Fe-55 8.01E+08 4.25E+08 1.32E+08 O.OOE+OO O.OOE+OO 2.40E+08 7.87E+07 Fe-59 3.97E+08 6.42E+08 3.20E+08 O.OOE+OO O.OOE+OO 1.86E+08 6.69E+08 Co-58 O.OOE+OO 6.45E+07 1.97E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.76E+08 Co-60 O.OOE+OO 3.78E+08 1.12E+09 O.OOE+OO O.OOE+OO O.QOE+OO 2.10E+09 Ni-63 3.95E+10 2.11 E+09 1.34E+09 0.00E+OO O.OOE+OO O.OOE+OO 1.42E+08 Ni-65 1.02E+02 9.59E+OO 5.60E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.18E+d3 Cu-64 O.OOE+OO 1.09E+04 6.56E+03 O.OOE+OO 2.62E+04 O.OOE+OO 5.10E+05 Zn-65 8.12E+08 2.16E+09 1.35E+09 O.OOE+OO 1.36E+09 O.OOE+OO 3.80E+08 Zn-69 8.56E-06 1.24E-05 1.14E-06 O.OOE+OO 7.50E-06 O.OOE+OO 7.80E-04 Br-83 O.OOE+OO . O.OOE+OO 5.18E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 0.00E+OO O.OOE+OO 3.39E-11 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 4.54E+08 2.79E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.92E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 3:59E+10 O.OOE+OO 1.03E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E+09 Sr-90 1.87E+12 O.OOE+OO 3.77E+10 O.OOE+OO O.OOE+OO O.OOE+OO 1.67E+10 Sr-91 5.17E+05 O.OOE+OO 1.95E+04 O.OOE+OO O.OOE+OO O.OOE+OO 1.14E+06 Sr-92 7.04E+02 O.OOE+OO 2.82E+01 O.OOE+OO O.OOE+OO O.OOE+OO 1.33E+04 Y-90 2.31E+04 O.OOE+OO 6.18E+02 O.OOE+OO O.OOE+OO O;OOE+OO 6.57E+07 Y-91M 8.42E-09 O.OOE+OO 3.06E-10 O.OOE+OO O.OOE+OO O.OOE+OO 1.65E-05 Y-91 1.87E+07 O.OOE+OO 4.99E+05 O.OOE+OO O.OOE+OO
- O.OOE+OO 2.49E+09 Y-92 1.55E+OO O.OOE+OO 4.43E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.47E+04 Y-93 2.89E+02 O.OOE+OO 7.94E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.31E+06 Zr-95 3.86E+06 8.50E+05 7.56E+05 O.OOE+OO 1.22E+06 O.OOE+OO 8.86E+08 Zr-97 5.67E+02 8.19E+01 4.83E+01 O.OOE+OO 1.18E+02 O.OOE+OO 1.24E+07 Nb-95 4.12E+05 1.61E+05 1.15E+05 O.OOE+OO 1.51E+05 O.OOE+OO 2.97E+08 Mo-99 O.OOE+OO 7.69E+06 1.90E+06 O.OOE+OO 1.64E+07 O.OOE+OO 6.36E+06 Tc- 99M 4.64E+OO 9.10E+OO 1.51 E+02 O.OOE+OO 1.32E+02 4.62E+OO 5.18E+03 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.53E+07 O.OOE+OO 5.89E+06 O.OOE+OO 3.86E+07 O.OOE+OO 3.96E+08 Ru-105 8.97E+01 O.OOE+OO 3.25E+01 O.OOE+OO 7.89E+02 O.OOE+OO 5.86E+04 Ru-106 7.45E+08 O.OOE+OO 9.30E+07 O.OOE+OO 1.01 E+09 O.OOE+OO 1.16E+10 Ag-110M 3.21E+07 2.17E+07 1.74E+07 O.OOE+OO 4.04E+07 O.OOE+OO 2.58E+09 Page 219 of 267
Revision 5 Aug 31, 2015 Table F-12b (Continued) Child Vegetation Dose Factors Nuclide Bone Liver TBody Thyroid Kidney Lung Gl-LLI Te-125M 3.51E+08 9.52E+07 4.68E+07 9.86E+07 O.OOE+OO O.OOE+OO 3.39E+08 Te-127M 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 O.OOE+OO 1.07E+09 Te-127 9.89E+03 2.67E+03 2.12E+03 6.84E+03 2.81E+04 O.OOE+OO 3.86E+05 Te-129M 8.40E+08 2.35E+08 1.30E+08 2.71E+08 2.47E+09 O.OOE+OO 1.02E+09 Te-129 1.24E-03 3.45E-04 2.94E-04 8.83E-04 3.62E-03 O.OOE+OO 7.70E-02 Te-131M 1.54E+06 5.32E+05 5.66E+05 1.09E+06 5.15E+06 O.OOE+OO 2.16E+07 Te-131 2.15E-15 6.57E-16 6.41 E-16 1.65E-15 6.51 E-15 O.OOE+OO 1.13E-14 Te-132 6.97E+06 3.09E+06 3.73E+06 4.49E+06 2.86E+07 O.OOE+OO 3.11E+07 1-130 6.10E+05 1.23E+06 6.35E+05 1.36E+08 1.84E+06 O.OOE+OO 5.76E+05 1-131 1.43E+08 1.44E+08 8.17E+07 4.75E+10 2.36E+08 O.OOE+OO 1.28E+07 1-132 8.93E+01 1.64E+02 7.54E+01 7.61E+03 2.51E+02 O.OOE+OO 1.93E+02 1-133 3.52E+06 4.36E+06 1.65E+06 8.09E+08 7.26E+06 O.OOE+OO 1.76E+06 1-134 1.37E-04 2.55E-04 1.17E-04 5.86E-03 3.90E-04 O.OOE+OO 1.69E-04 1-135 6.20E+04 1.12E+05 5.28E+04 9.89E+06 1.71 E+05 O.OOE+OO 8.51E+04 Cs-134 1.60E+10 2.63E+10 5.55E+09 O.OOE+OO 8.16E+09 2.93E+09 1.42E+08 Cs-136 8.18E+07 2.25E+08 1.46E+08 O.OOE+OO 1.20E+08 1.79E+07 7.90E+06 Cs-137 2.39E+10 2.29E+10 3.38E+09 O.OOE+OO 7.46E+09 2.68E+09 1.43E+08 Cs-138 5.58E-11 7.75E-11 4.92E-11 O.OOE+OO 5.45E-11 5.87E-12 3.57E-11 Ba-139 4.69E-02 2.51E-05 1.36E-03 O.OOE+OO 2.19E-05 1.47E-05 2.71E+OO Ba-140 2.77E+08 2.43E+05 1.62E+07 O.OOE+OO 7.90E+04 1.45E+05 1.40E+08 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 3.25E+03 1.13E+03 3.82E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.16E+07 La-142 3.23E-04 1.03E-04 3.22E-05 O.OOE+OO O.OOE+OO O.OOE+OO 2.04E+01 Ce-141 6.55E+05 3.27E+05 4.85E+04 O.OOE+OO 1.43E+05 O.OOE+OO 4.08E+08 Ce-143 1.71 E+03 9.28E+05 1.34E+02 O.OOE+OO 3.89E+02 O.OOE+OO 1.36E+07 Ce-144 1.27E+08 3.98E+07 6.78E+06 O.OOE+OO 2.21E+07 O.OOE+OO 1.04E+10 Pr-143 1.46E+05 4.38E+04 7.24E+03 O.OOE+OO 2.37E+04 O.OOE+OO 1.57E+08 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 7.27E+04 5.89E+04 4.56E+03 O.OOE+OO 3.23E+04 O.OOE+OO 9.33E+07 W-187 6.41 E+04 3.80E+04 1.70E+04 O.OOE+OO O.OOE+OO O.OOE+OO 5.34E+06 Np-239 2.55E+03 1.83E+02 1.29E+02 O.OOE+OO 5.30E+02 O.OOE+OO 1.36E+07 Notes:
- 1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.
3
- 2) For H-3, the units are mrem/yr per µCi/m .
- 3) The infant age group is assumed to receive no due through the vegetation ingestion pathway therefore no dose factors are supplied.
Page 220 of 267
Revision 5 Aug 31, 2015 Table F-13 Adult Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 4.35E+02 4.35E+02 4.35E+02 4.35E+02 4.35E+02 4.35E+02 Na-24 2.46E+06 2.46E+06 2.46E+06 2.46E+06 2.46E+06 2.46E+06 2.46E+06 Cr-51 O.OOE+OO O.OOE+OO 2.86E+04 1.71E+04 6.29E+03 3.79E+04 7.18E+06 Mn-54 O.OOE+OO 8.41E+06 1.61 E+06 O.OOE+OO 2.50E+06 O.OOE+OO 2.58E+07 Mn-56 O.OOE+OO 4.13E-03 7.32E-04 O.OOE+OO 5.24E-03 O.OOE+OO 1.32E-01 Fe-55 2.51E+07 1.74E+07 4.05E+06 O.OOE+OO O.OOE+OO 9.68E+06 9.95E+06 Fe-59 2.97E+07 6.98E+07 2.67E+07 O.OOE+OO O.OOE+OO 1.95E+07 2.33E+08 Co-58 O.OOE+OO 4.72E+06 1.06E+07 O.OOE+OO O.OOE+OO O.OOE+OO 9.56E+07 Co-60 O.OOE+OO 1.64E+07 3.62E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.08E+08 Ni-63 6.73E+09 4.66E+08 2.26E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.73E+07 Ni-65 3.70E-01 4.81 E-02 2.19E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.22E+OO Cu-64 O.OOE+OO 2.36E+04 1.11E+04 O.OOE+OO 5.95E+04 O.OOE+OO 2.01E+06 Zn-65 1.37E+09 4.36E+09 1.97E+09 O.OOE+OO 2.92E+09 O.OOE+OO 2.75E+09 Zn-69 2.01E-12 3.84E-12 2.67E-13 O.OOE+OO 2.50E-12 O.OOE+OO 5.78E-13 Br-83 O.OOE+OO O.OOE+OO 9.65E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E-01 Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.60E+09 1.21 E+09 O.OOE+OO O.OOE+OO O.OOE+OO 5.12E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 1.45E+09 O.OOE+OO 4.16E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.33E+08 Sr-90 5.38E+10 O.OOE+OO 1.08E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.35E+09 Sr-91 2.87E+04 O.OOE+OO 1.16E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.37E+05 Sr-92 4.84E-01 O.OOE+OO 2.09E-02 O.OOE+OO O.OOE+OO O.OOE+OO 9.58E+OO Y-90 7.10E+01 O.OOE+OO 1.90E+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.52E+05 Y-91M 6.42E-20 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.89E-19 Y-91 8.59E+03 O.OOE+OO 2.30E+02 O.OOE+OO O.OOE+OO O.OOE+OO 4.73E+06 Y-92 5.57E-05 O.OOE+OO 1.63E-06 O.OOE+OO O.OOE+OO O.OOE+OO 9.75E-01 Y-93 2.22E-01 O.OOE+OO 6.12E-03 O.OOE+OO O.OOE+OO O.OOE+OO 7.03E+03 Zr-95 9.44E+02 3.03E+02 2.05E+02 O.OOE+OO 4.75E+02 O.OOE+OO 9.59E+05 Zr-97 4.32E-01 8.72E-02 3.99E-02 O.OOE+OO 1.32E-01 O.OOE+OO 2.70E+04 Nb-95 8.26E+04 4.60E+04 2.47E+04 O.OOE+OO 4.54E+04 O.OOE+OO 2.79E+08 Mo-99 O.OOE+OO 2.47E+07 4.70E+06 O.OOE+OO 5.60E+07 O.OOE+OO 5.73E+07 Tc-99M 3.31E+OO 9.35E+OO 1.19E+02 O.OOE+OO 1.42E+02 4.58E+OO 5.53E+03 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.02E+03 O.OOE+OO 4.39E+02 O.OOE+OO 3.88E+03 O.OOE+OO 1.19E+05 Ru-105 8.51 E-04 O.OOE+OO 3.36E-04 O.OOE+OO 1.10E-02 O.OOE+OO 5.20E-01 Ru-106 2.04E+04 O.OOE+OO 2.58E+03 O.OOE+OO 3.94E+04 O.OOE+OO 1.32E+06 Ag-110M 5.82E+07 5.39E+07 3.20E+07 O.OOE+OO 1.06E+08 O.OOE+OO 2.20E+10 Page 221 of 267
Revision5 Aug 31, 2015 Table F-13 (Continued) Adult Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 1.63E+07 5.91E+06 2.18E+06 4.90E+06 6.63E+07 O.OOE+OO 6.51E+07 Te-127M 4.58E+07 1.64E+07 5.58E+06 1.17E+07 1.86E+08 O.OOE+OO 1.54E+08 Te-127 6.66E+02 2.39E+02 1.44E+02 4.94E+02 2.71E+03 O.OOE+OO 5.26E+04 Te-129M 6.02E+07 2.24E+07 9.52E+06 2.07E+07 2.51E+08 O.OOE+OO 3.03E+08 Te-129 2.83E-10 1.06E-10 6.88E-11 2.17E-10 1.19E-09 O.OOE+OO 2.13E-10 Te-131M 3.61E+05 1.76E+05 1.47E+05 2.79E+05 1.79E+06 O.OOE+OO 1.75E+07 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.39E+06 1.55E+06 1.45E+06 1.71E+06 1.49E+07 O.OOE+OO 7.32E+07 1-130 4.18E+05 1.23E+06 4.86E+05 1.04E+08 1.92E+06 O.OOE+OO 1.06E+06 1-131 2.96E+08 4.23E+08 2.43E+08 1.39E+11 7.26E+08 O.OOE+OO 1.12E+08 1-132 1.65E-01 4.40E-01 1.54E-01 1.54E+01 7.02E-01 O.OOE+OO 8.27E-02 1-133 3.88E+06 6.74E+06 2.06E+06 9.91E+08 1.18E+07 O.OOE+OO 6.06E+06 1-134 1.89E-12 5.13E-12 1.83E-12 8.89E-11 8.16E-12 O.OOE+OO 4.47E-15 1-135 1.29E+04 3.38E+04 1.25E+04 2.23E+06 5.42E+04 O.OOE+OO 3.82E+04 Cs-134 5.65E+09 1.35E+10 1.10E+10 O.OOE+OO 4.35E+09 1.45E+09 2.35E+08 Cs-136 2.63E+08 1.04E+09 7.46E+08 O.OOE+OO 5.77E+08 7.91E+07 1.18E+08 Cs-137 7.38E+09 1.01 E+10 6.61E+09 O.OOE+OO 3.43E+09 1.14E+09 1.95E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 4.43E-08 3.16E-11 1.30E-09 O.OOE+OO 2.95E-11 1.79E-11 7.86E-08 Ba-140 2.69E+07 3.38E+04 1.76E+06 O.OOE+OO 1.15E+04 1.93E+04 5.54E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 4.52E+OO 2.28E+OO 6.02E-01 O.OOE+OO O.OOE+OO O.OOE+OO 1.67E+05 La-142 1.89E-11 8.59E-12 2.14E-12 O.OOE+OO O.OOE+OO O.OOE+OO 6.28E-08 Ce-141 4.84E+03 3.28E+03 3.72E+02 O.OOE+OO 1.52E+03 O.OOE+OO 1.25E+07 Ce-143 4.15E+01 3.07E+04 3.39E+OO O.OOE+OO 1.35E+01 O.OOE+OO 1.15E+06 Ce-144 3.58E+05 1.50E+05 1.92E+04 O.OOE+OO 8.87E+04 O.OOE+OO 1.21 E+08 Pr-143 1.58E+02 6.34E+01 7.83E+OO O.OOE+OO 3.66E+01 O.OOE+OO 6.92E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 9.48E+01 1.10E+02 6.56E+OO O.OOE+OO 6.41 E+01 O.OOE+OO 5.26E+05 W-187 6.51E+03 5.44E+03 1.90E+03 O.OOE+OO O.OOE+OO O.OOE+OO 1.78E+06 Np-239 3.67E+OO 3.61E-01 1.99E-01 O.OOE+OO 1.12E+OO O.OOE+OO 7.40E+04 Notes:
- 1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.
3
- 2) For H-3, the units are mrem/yr per µCi/m .
Page 222 of 267
Revision 5 Aug 31, 2015 Table F-13a Teen Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 5.66E+02 5.66E+02 5.66E+02 5.66E+02 5.66E+02 5.66E+02 Na-24 4.29E+06 4.29E+06 4.29E+06 4.29E+06 4.29E+06 4.29E+06 4.29E+06 Cr-51 O.OOE+OO O.OOE+OO 4.99E+04 2.77E+04 1.09E+04 7.12E+04 8.38E+06 Mn-54 O.OOE+OO 1.40E+07 2.78E+06 O.OOE+OO 4.18E+06 O.OOE+OO 2.87E+07 Mn-56 O.OOE+OO 7.32E-03 1.30E-03 O.OOE+OO 9.27E-03 O.OOE+OO 4.82E-01 Fe-55 4.45E+07 3.16E+07 7.36E+06 O.OOE+OO O.OOE+OO 2.00E+07 1.37E+07 Fe-59 5.18E+07 1.21E+08 4.67E+07 O.OOE+OO O.OOE+OO 3.81E+07 2.86E+08 Co-58 O.OOE+OO 7.94E+06 1.83E+07 O.ObE+OO O.OOE+OO O.OOE+OO 1.09E+08 Co-60 O.OOE+OO 2.78E+07 6.26E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.62E+08 Ni-63 1.18E+10 8.35E+08 4.01E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.33E+08 Ni-65 6.78E-01 8.66E-02 3.94E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.70E+OO Cu-64 O.OOE+OO 4.21E+04 1.98E+04 O.OOE+OO 1.06E+05 O.OOE+OO 3.26E+o6 Zn-65 2.11 E+09 7.31E+09 3.41 E+09 O.OOE+OO 4.68E+09 O.OOE+OO 3.10E+09 Zn-69 3.70E-12 7.05E-12 4.94E~13 O.OOE+OO 4.61E-12 O.OOE+OO 1.30E-11 Br-83 O.OOE+OO O.OOE+OO 1.78E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 4.73E+09 2.22E+09 O.OOE+OO O.OOE+OO O.OOE+OO 7.01E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO Sr-89 2.67E+09 O.OOE+OO 7.66E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.18E+08 sr~9o 8.13E+10 O.OOE+OO 1.63E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.86E+09 Sr-91 5.27E+04 O.OOE+OO 2.10E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.39E+05 Sr-92 8.85E-01 O.OOE+OO 3.77E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.26E+01 Y-90 1.30E+02 O.OOE+OO 3.51E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.08E+06 Y-91M 1.18E-19 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.55E-18 Y-91 1.58E+04 O.OOE+OO 4.24E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.48E+06 Y-92 1.03E-04 O.OOE+OO 2.98E-06 O.OOE+OO O.OOE+OO O.OOE+OO 2.82E+OO Y-93 4.09E-01 O.OOE+OO 1.12E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.25E+04 Zr-95 1.65E+03 5.21E+02 3.58E+02 O.OOE+OO 7.65E+02 O.OOE+OO 1.20E+06 Zr-97 7.87E-01 1.56E-01 7.17E-02 O.OOE+OO 2.36E-01 O.OOE+OO 4.22E+04 Nb-95 1.41 E+05 7.82E+04 4.30E+04 O.OOE+OO 7.58E+04 O.OOE+OO 3.34E+08 Mo-99 O.OOE+OO 4.46E+07 8.51E+06 O.OOE+OO 1.02E+08 O.OOE+OO 8.00E+07 Tc-99M 5.74E+OO 1.60E+01 2.07E+02 O.OOE+OO 2.39E+02 8.89E+OO 1.05E+04 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO o.oo.E+oo Ru-103 1.81 E+03 O.OOE+OO 7.74E+02 O.OOE+OO 6.38E+03 O.OOE+OO 1.51 E+05 Ru-105 1.55E-03 O.OOE+OO 6.03E-04 O.OOE+OO 1.96E-02 O.OOE+OO 1.25E+OO Ru-106 3.75E+04 O.OOE+OO 4.73E+03 O.OOE+OQ 7.24E+04 O.OOE+OO 1.80E+06 Ag-110M 9.63E+07 9.11E+07 5.54E+07 O.OOE+OO 1.74E+08 O.OOE+OO 2.56E+10 Page 223 of 267
Revision5 Aug 31, 2015 Table F-13a (Continued) Teen Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 3.01E+07 1.08E+07 4.02E+06 8.40E+06 O.OOE+OO O,OOE+OQ 8.87E+07 Te-127M 8.44E+07 2.99E+07 1.00E+07 2.01E+07 3.42E+08 O.OOE+OO 2.10E+08 Te-127 1.24E+03 4.38E+02 2.66E+02 8.52E+02 5.00E+03 O.OOE+OO 9.54E+04 Te-129M 1.10E+08 4.09E+07 1.74E+07 3.55E+07 4.61E+08 O.OOE+OO 4.13E+08 Te-129 5.20E-10 1.94E-10 1.27E-10 3.72E-10 2.18E-09 O.OOE+OO 2.84E-09 Te-131M 6.57E+05 3.15E+05 2.63E+05 4.74E+05 3.28E+06 O.OOE+OO 2.53E+07 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 4.27E+06 2.71E+06 2.55E+06 2.85E+06 2.60E+07 O.OOE+OO 8.57E+07 1-130 7.35E+05 2.13E+06 8.49E+05 1.73E+08 3.27E+06 O.OOE+OO 1.63E+06 1-131 5.37E+08 7.52E+08 4.04E+08 2.19E+11 1.29E+09 O.OOE+OO 1.49E+08 1-132 2.92E~01 7.64E-01 2.74E-01 2.57E+01 1.20E+OO O.OOE+OO 3.33E-01 1-133 7.08E+06 1.20E+07 3.66E+06 1.68E+09 2.11 E+07 O.OOE+OO 9.09E+06 1-134 3.35E-12 8.89E-12 3.19E-12 1.48E-10 1.40E-11 O.OOE+OO 1.17E-13 1-135 2.29E+04 5.91E+04 2.19E+04 3.80E+06 9.33E+04 O.OOE+OO 6.54E+04 Cs-134 9.82E+09 2.31 E+10 1.07E+10 O.OOE+OO 7.34E+09 2.80E+09 2.871;:+08 Cs-136 4.47E+08 1.76E+09 1.18E+09 O.OOE+OO 9.58E+08 1.51E+08 1.42E+08 Cs-137 1.34E+10 1.78E+10 6.20E+09 O.OOE+OO 6.06E+09 2.35E+09 2.53E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 8.20E-08 5.77E-11 2.39E-09 .O.OOE+OO 5.44E-11 3.98E-11 7.31 E-07 Ba-140 4.85E+07 5.95E+04 3.13E+06 O.OOE+OO 2.02E+04 4.00E+04 7.49E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 8.12E+OO 3.99E+OO 1.06E+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.29E+05 La-142 3.41 E-11 1.51E-11 3.77E-12 O.OOE+OO O.OOE+OO O.OOE+OO 4.61 E-07 Ce-141 8.88E+03 5.93E+03 6.81E+02 O.OOE+OO 2.79E+03 O.OOE+OO 1.70E+07 Ce-143 7.62E+01 5.55E+04 6.20E+OO O.OOE+OO 2.49E+01 O.OOE+OO 1.67E+06 Ce-144 6.58E+05 2.72E+05 3.54E+04 O.OOE+OO 1.63E+05 O.OOE+OO 1.66E+08 Pr-143 2.90E+02 1.16E+02 1.44E+01 O.OOE+OO 6.74E+01 O.OOE+OO 9.55E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 1.82E+02 1.98E+02 1.19E+01 O.OOE+OO 1.17E+02 O.OOE+OO 7.16E+05 W-187 1.19E+04 9.71E+03 3.40E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.63E+06 Np-239 7.00E+OO 6.60E-01 3.67E-01 O.OOE+OO 2.07E+OO O.OOE+OO 1.06E+05 Notes:
- 1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.
3
- 2) For H-3, the units are mrem/yr per µCi/m .
Page 224 of 267
Revision 5 Aug 31, 2015 Table F-13b Child Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 8.97E+02 8.97E+02 8.97E+02 8.97E+02 8.97E+02 8.97E+02 Na-24 8.93E+06 8.93E+06 8.93E+06 8.93E+06 8.93E+06 8.93E+06 8.93E+06 Cr-51 O.OOE+OO O.OOE+OO 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.39E+06 Mn-54 O.OOE+OO 2.10E+07 5.59E+06 O.OOE+OO 5.88E+06 O.OOE+OO 1.76E+07 Mn-56 O.OOE+OO 1.28E-02 2.88E-03 O.OOE+OO 1.54E-02 O.OOE+OO 1.85E+OO Fe-55 1.12E+08 5.93E+07 1.84E+07 O.OOE+OO O.OOE+OO 3.35E+07 1.10E+07 Fe-59 1.20E+08 1.94E+08 9.69E+07 O.OOE+OO O.OOE+OO 5.64E+07 2.02E+08 Co-58 O.OOE+OO 1.21E+07 3.71E+07 O.OOE+OO O.OOE+OO O.OOE+OO 7.08E+07 Co-60 O.OOE+OO 4.32E+07 1.27E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.39E+08 Ni-63 2.96E+10 1.59E+09 1.01 E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.07E+08 Ni-65 1.66E+OO 1.56E-01 9.11 E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.91E+01 Cu-64 O.OOE+OO 7.39E+04 4.47E+04 O.OOE+OO 1.79E+05 O.OOE+OO 3.47E+06 Zn-65 4.13E+09 1.10E+10 6.85E+09 O.OOE+OO 6.94E+09 O.OOE+OO 1.93E+09 Zn-69 9.10E-12 1.32E-11 1.22E-12 O.OOE+OO 7.98E-12 O.OOE+OO 8.29E-10 Br-83 O.OOE+OO O.OOE+OO 4.37E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 8.78E+09 5.40E+09 O.OOE+OO O.OOE+OO O.OOE+OO 5.65E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 6.62E+09 O.OOE+OO 1.89E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.56E+08 Sr-90 1.68E+11 O.OOE+OO 3.38E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.51E+09 Sr-91 1.29E+05 O.OOE+OO 4.88E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.86E+05 Sr-92 2.16E+OO O.OOE+OO 8.67E-02 O.OOE+OO O.OOE+OO O.OOE+OO 4.09E+01 Y-90 3.23E+02 O.OOE+OO 8.64E+OO O.OOE+OO O.OOE+OO O.OOE+OO 9.19E+05 Y-91M 2.87E-19 O.OOE+OO 1.04E-20 O.OOE+OO O.OOE+OO O.OOE+OO 5.62E-16 Y-91 3.90E+04 O.OOE+OO 1.04E+03 O.OOE+OO O.OOE+OO O.OOE+OO 5.20E+06 Y-92 2.53E-04 O.OOE+OO 7.23E-06 O.OOE+OO O.OOE+OO O.OOE+OO 7.30E+OO Y-93 1.00E+OO O.OOE+OO 2.75E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.50E+04 Zr-95 3.83E+03 8.43E+02 7.50E+02 O.OOE+OO 1.21E+03 O.OOE+OO 8.79E+05 Zr-97 1.91 E+OO 2.77E-01 1.63E-01 O.OOE+OO 3.97E-01 O.OOE+OO 4.19E+04 Nb-95 3.18E+05 1.24E+05 8.85E+04 O.OOE+OO 1.16E+05 O.OOE+OO 2.29E+08 Mo-99 O.OOE+OO 8.12E+07 2.01 E+07 O.OOE+OO 1.73E+08 O.OOE+OO 6.72E+07 Tc-99M 1.32E+01 2.58E+01 4.28E+02 O.OOE+OO 3.75E+02 1.31E+01 1.47E+04 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 4.28E+03 O.OOE+OO 1.65E+03 O.OOE+OO 1.08E+04 O.OOE+OO 1.11 E+05 Ru-105 3.79E-03 O.OOE+OO 1.38E-03 O.OOE+OO 3.33E-02 O.OOE+OO 2.48E+OO Ru-106 9.24E+04 O.OOE+OO 1.15E+04 O.OOE+OO 1.25E+05 O.OOE+OO 1.44E+06 Ag-110M 2.09E+08 1.41 E+08 1.13E+08 O.OOE+OO 2.63E+08 O.OOE+OO 1.68E+10 Page 225 of 267
Revision 5 Aug 31, 2015 Table F-13b (Continued.) Child Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 7.38E+07 2.00E+07 9.84E+06 2.d7E+07 O.OOE+OO O.OOE+OO 7.12E+07 Te-127M 2.08E+08 5.60E+07 2.47E+07 4.97E+07 5.93E+08 O.OOE+OO 1.68E+08 Te-127 3.04E+03 8.19E+02 6.51E+02 2.10E+03 8.64E+03 O.OOE+OO 1.19E+05 Te-129M 2.71E+08 7.58E+07 4.21E+07 8.75E+07 7.97E+08 O.OOE+OO 3.31E+08 Te-129 1.28E-09 3.58E-10 3.05E-10 9.16E-10 3.75E-09 O.OOE+OO 7.99E-08 Te-131M 1.60E+06 5.53E+05 5.88E+05 1.14E+06 5.35E+06 O.OOE+OO 2.24E+07 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 1.02E+07 4.52E+06 5.46E+06 6.58E+06 4.19E+07 O.OOE+OO 4.55E+07 1-130 1.72E+06 3.47E+06 1.79E+06 3.82E+08 5.19E+06 O.OOE+OO 1.62E+06 1-131 1.30E+09 1.31 E+09 7.45E+08 4.33E+11 2.15E+09 O.OOE+OO 1.17E+08 1-132 6.91 E-01 1.27E+OO 5.84E-01 5.89E+01 1.94E+OO O.OOE+OO 1.49E+OO 1-133 1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.55E+07 O.OOE+OO 8.57E+06 1-134 7.94E-12 1.47E-11 6.79E-12 3.39E-10 2.26E-11 O.OOE+OO 9.78E-12 1-135 5.43E+04 9.78E+04 4.62E+04 8.66E+06 1.50E+05 O.OOE+OO 7.45E+04 Cs-134 2.26E+10 3.72E+10 7.84E+09 O.OOE+OO 1.15E+10 4.13E+09 2.00E+08 Cs-136 1.01 E+09 2.77E+09 1.80E+09 O.OOE+Ob 1.48E+09 2.20E+08 9.75E+07 Cs-137 3.22E+10 3.09E+10 4.55E+09 O.OOE+OO 1.01E+10 3.62E+09 1.93E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.dOE+OO Ba-139 2.01 E-07 1.08E-10 5.84E-09 O.OOE+OO 9.39E-11 6.33E-11 1.16E-05 Ba-140 1.17E+08 1.03E+05 6.84E+06 O.OOE+OO 3.34E+04 6.12E+04 5.94E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 1.95E+01 6.80E+OO 2.29E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.90E+05 La-142 8.24E-11 2.63E-11 8.22E-12 O.OOE+OO O.OOE+OO O.OOE+OO 5,20E-06 Ce-141 2.19E+04 1.09E+04 1.62E+03 O.OOE+OO 4.78E+03 O.OOE+OO 1.36E+07 Ce-143 1.87E+02 1.01E+05 1.47E+01 O.OOE+OO 4.26E+01 O.OOE+OO 1.49E+06 Ce-144 1.62E+06 5.09E+05 8.66E+04 O.OOE+OO 2.82E+05 O.OOE+OO 1.33E+08 Pr-143 7.18E+02 2.16E+02 3.57E+01 O.OOE+OO 1.17E+02 O.OOE+OO 7.75E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 4.48E+02 3.63E+02 2.81 E+01 O.OOE+OO 1.99E+02 O.OOE+OO 5.75E+05 W-187 2.89E+04 1.71 E+04 7.67E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.40E+06 Np-239 1.72E+01 1.24E+OO 8.69E-01 O.OOE+OO 3.58E+OO O.OOE+OO 9.15E+04 Notes:
- 1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.
3
- 2) For H-3, the units are mrem/yr per µCi/m .
Page 226 of 267
Revision 5 Aug 31, 2015 Table F-13c Infant Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.36E+03 1.36E+03 1.36E+03 1.36E+03 1.36E+03 1.36E+03 Na-24 1.56E+07 1.56E+07 1.56E+07 1.56E+07 1.56E+07 1.56E+07 1.56E+07 Cr-51 O.OOE+OO O.OOE+OO 1.61 E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 Mn-54 O.OOE+OO 3.90E+07 8.84E+06 O.OOE+OO 8.64E+06 O.OOE+OO 1.43E+07 Mn-56 O.OOE+OO 3.13E-02 5.39E-03 O.OOE+OO 2.69E-02 O.OOE+OO 2.84E+OO Fe-55 1.35E+08 8.73E+07 2.33E+07 O.OOE+OO O.OOE+OO 4.27E+07 1.11E+07 Fe-59 2.24E+08 3.92E+08 1.54E+08 O.OOE+OO O.OOE+OO 1.16E+08 1.87E+08 Co-58 O.OOE+OO 2.43E+07 6.05E+07 O.OOE+OO O.OOE+OO O.OOE+OO 6.04E+07 Co-60 O.OOE+OO 8.82E+07 2.08E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.10E+08 Ni-63 3.49E+10 2.16E+09 1.21 E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.07E+08 Ni-65 3.51E+OO 3.97E-01 1.81 E-01 O.OOE+OO O.OOE+OO O.OOE+OO 3.02E+01 Cu-64 O.OOE+OO 1.84E+05 8.51E+04 O.OOE+OO 3.11 E+05 O.OOE+OO 3.77E+06 Zn-65 5.55E+09 1.90E+10 8.78E+09 O.OOE+OO 9.23E+09 O.OOE+OO 1.61E+10 Zn-69 1.94E-11 3.49E-11 2.60E-12 O.OOE+OO 1.45E-11 O.OOE+OO 2.85E-09 Br-83 O.OOE+OO O.OOE+OO 9.27E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 2.23E+10 1.10E+10 O.OOE+OO O.OOE+OO O.OOE+OO 5.70E+08 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 1.26E+10 O.OOE+OO 3.61E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.59E+08 Sr-90 1.86E+11 O.OOE+OO 3.77E+09 O.OOE+OO O.OOE+OO O.OOE+OO 1.52E+09 Sr-91 2.70E+05 O.OOE+OO 9.76E+03 O.OOE+OO O.OOE+OO O.OOE+OO 3.19E+05 Sr-92 4.60E+OO O.OOE+OO 1.71 E-01 O.OOE+OO O.OOE+OO O.OOE+OO 4.96E+01 Y-90 6.82E+02 O.OOE+OO 1.83E+01 O.OOE+OO O.OOE+OO O.OOE+OO 9.42E+05 Y-91M 6.09E-19 O.OOE+OO 2.07E-20 O.OOE+OO O.OOE+OO O.OOE+OO 2.03E-15 Y-91 7.33E+04 O.OOE+OO 1.95E+03 O.OOE+OO O.OOE+OO O.OOE+OO 5.25E+06 Y-92 5.37E-04 O.OOE+OO 1.51 E-05 O.OOE+OO O.OOE+OO O.OOE+OO 1.02E+01 Y-93 2.14E+OO O.OOE+OO 5.83E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.69E+04 Zr-95 6.81E+03 1.66E+03 1.18E+03 O.OOE+OO 1.79E+03 O.OOE+OO 8.26E+05 Zr-97 4.05E+OO 6.96E-01 3.18E-01 O.OOE+OO 7.01 E-01 O.OOE+OO 4.44E+04 Nb-95 5.94E+05 2.45E+05 1.41E+05 O.OOE+OO 1.75E+05 O.OOE+OO 2.07E+08 Mo-99 O.OOE+OO 2.08E+08 4.05E+07 O.OOE+OO 3.10E+08 O.OOE+OO 6.84E+07 Tc-99M 2.74E+01 5.65E+01 7.27E+02 O.OOE+OO 6.08E+02 2.95E+01 1.64E+04 Tc-101 O.OOE+OO O.OOE+bO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 8.67E+03 O.OOE+OO 2.90E+03 O.OOE+OO 1.80E+04 O.OOE+OO 1.05E+05 Ru-105 8.00E-03 O.OOE+OO 2.69E-03 O.OOE+OO 5.88E-02 O.OOE+OO 3.18E+OO Ru-106 1.90E+05 O.OOE+OO 2.38E+04 O.OOE+OO 2.25E+05 O.OOE+OO 1.44E+06 Ag-110M 3.86E+08 2.82E+08 1.86E+08 O.OOE+OO 4.03E+08 O.OOE+OO 1.46E+10 Page 227 of 267
Revision 5 Aug 31, 2015 Table F-13c (Continued) Infant Grass-Cow-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 1.51E+08 5.04E+07 2.04E+07 5.08E+07 O.OOE+OO O.OOE+OO 7.19E+07 Te-127M 4.21E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 O.OOE+OO 1.70E+08 Te-127 6.45E+03 2.16E+03 1.39E+03 5.25E+03 1.57E+04 O.OOE+OO 1.35E+05 Te-129M 5.57E+08 1.91 E+08 8.58E+07 2.14E+08 1.39E+09 O.OOE+OO 3.33E+08 Te-129 2.72E-09 9.38E-10 6.35E-10 2.28E-09 6.77E-09 O.OOE+OO 2.17E-07 Te-131 M 3.37E+06 1.36E+06 1.12E+06 2.75E+06 9.35E+06 O.OOE+OO 2.29E+07 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.10E+07 1.04E+07 9.71E+06 1.54E+07 6.51E+07 O.OOE+OO 3.85E+07 1-130 3.53E+06 7.77E+06 3.12E+06 8.71E+08 8.53E+06 O.OOE+OO 1.67E+06 1-131 2.72E+09 3.20E+09 1.41 E+09 1.05E+12 3.74E+09 O.OOE+OO 1.14E+08 1-132 1.43E+OO 2.91E+OO 1.04E+OO 1.36E+02 3.25E+OO O.OOE+OO 2.36E+OO 1-133 3.63E+07 5.29E+07 1.55E+07 9.62E+09 6.22E+07 O.OOE+OO 8.95E+06 1-134 1.65E-11 3.37E-11 1.20E-11 7.87E-10 3.77E-11 O.OOE+OO 3.49E-11 1-135 1.13E+05 2.25E+05 8.19E+04 2.01E+07 2.50E+05 O.OOE+OO 8.13E+04 Cs-134 3.65E+10 6.80E+10 6.87E+09 O.OOE+OO 1.75E+10 7.18E+09 1.85E+08 Cs-136 1.97E+09 5.80E+09 2.16E+09 O.OOE+OO 2.31E+09 4.72E+08 8.80E+07 Cs-137 5.15E+10 6.02E+10 4.27E+09 O.OOE+OO 1.62E+10 6.55E+09 1.88E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 4.29E-07 2.84E-10 1.24E-08 O.OOE+OO 1.71E-10 1.72E-10 2.72E-05 Ba-140 2.41E+08 2.41 E+OS 1.24E+07 O.OOE+OO 5.72E+04 1.48E+05 5.92E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 4.06E+01 1.60E+01 4.12E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.88E+05 La-142 1.73E-10 6.35E-11 1.52E-11 O.OOE+OO O.OOE+OO O.OOE+OO 1.08E-05 Ce-141 4.34E+04 2.64E+04 3.11 E+03 O.OOE+OO 8.15E+03 O.OOE+OO 1.37E+07 Ce-143 3.96E+02 2.63E+05 3.00E+01 O.OOE+OO 7.65E+01 O.OOE+OO 1.53E+06 Ce-144 2.33E+06 9.52E+05 1.30E+05 O.OOE+OO 3.85E+05 O.OOE+OO 1.33E+08 Pr-143 1.49E+03 5.56E+02 7.37E+01 O.OOE+OO 2.07E+02 O.OOE+OO 7.84E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 8.88E+02 9.12E+02 5.59E+01 O.OOE+OO 3.51E+02 O.OOE+OO 5.78E+05 W-187 6.08E+04 4.23E+04 1.46E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.48E+06 Np-239 3.64E+01 3.26E+OO 1.84E+OO O.OOE+OO 6.SOE+OO O.OOE+OO 9.42E+04 Notes:
- 1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.
3
- 2) For H-3, the units are mrem/yr per µCi/m .
Page 228 of 267
Revision 5 Aug 31, 2015 Table F-14 Adult Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 8.88E+02 8.88E+02 8.88E+02 8.88E+02 8.88E+02 8.88E+02 Na-24 2.95E+05 2.95E+05 2.95E+05 2.95E+05 2.95E+05 2.95E+05 2.95E+05 Cr-51 O.OOE+OO O.OOE+OO 3.43E+03 2.05E+03 7.55E+02 4.55E+03 8.62E+05 Mn-54 O.OOE+OO 1.01E+06 1.93E+05 O.OOE+OO 3.00E+05 O.OOE+OO 3.09E+06 Mn-56 O.OOE+OO 4.95E-04 8.79E-05 O.OOE+OO 6.29E-04 O.OOE+OO 1.58E-02 Fe-55 3.26E+05 2.26E+05 5.26E+04 O.OOE+OO O.OOE+OO 1.26E+05 1.29E+05 Fe-59 3.86E+05 9.07E+05 3.48E+05 O.OOE+OO O.OOE+OO 2.53E+05 3.02E+06 Co-58 O.QOE+OO 5.66E+05 1.27E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1.15E+07 Co-60 O.OOE+OO 1.97E+06 4.34E+06 O.OOE+OO O.OOE+OO O.OOE+OO 3.70E+07 Ni-63 8.07E+08 5.60E+07 2.71E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E+07 Ni-65 4.44E-02 5.77E-03 2.63E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.46E-01 Cu-64 O.OOE+OO 2.63E+03 1.23E+03 O.OOE+OO 6.63E+03 O.OOE+OO 2.24E+05 Zn-65 1.65E+08 5.24E+08 2.37E+08 O.OOE+OO 3.50E+08 O.OOE+OO 3.30E+08 Zn-69 2.41 E-13 4.61E-13 3.21 E-14 O.OOE+OO 3.00E-13 O.OOE+OO 6.93E-14 Br.:83 O.OOE+OO O.OOE+OO 1.16E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.67E-02 Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 3.12E+08 1.45E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.15E+07 Rb-88 O.OOE+Od O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 3.05E+09 O.OOE+OO 8.74E+07 O.OOE+OO O.OOE+OO O.OOE+OO 4.88E+08 Sr-90 1.13E+11 O.OOE+OO 2.27E+09 O.OOE+OO O.OOE+OO O.OOE+OO 2.84E+09 Sr-91 6.03E+04 O.OOE+OO 2.44E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.87E+05 Sr-92 1.02E+OO O.OOE+OO 4.39E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.01 E+01 Y-90 8.52E+OO O.OOE+OO 2.28E-01 O.OOE+OO O.OOE+OO O.OOE+OO 9.03E+04 Y-91M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.26E-20 Y-91 1.03E+03 O.OOE+OO 2.76E+01 O.OOE+OO O.OOE+OO O.OOE+OO 5.67E+05 Y-92 6.68E-06 O.OOE+OO 1.95E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.17E-01 Y-93 2.66E-02 O.OOE+OO 7.34E-04 O.OOE+OO O.OOE+OO O.OOE+OO 8.43E+02 Zr-95 1.13E+02 3.63E+01 2.46E+01 O.OOE+OO 5.70E+01 O.OOE+OO 1.15E+05 Zr-97 5.19E-02 1.0SE-02 4.79E-03 O.OOE+OO 1.58E-02 O.OOE+OO 3.24E+03 Nb-95 9.92E+03 5.52E+03 2.97E+03 O.OOE+OO 5.45E+03 O.OOE+OO 3.35E+07 Mo-99 O.OOE+OO 2.97E+06 5.65E+05 O.OOE+OO 6.72E+06 O.OOE+OO 6.88E+06 Tc-99M 3.97E-01 1.12E+OO 1.43E+01 O.OOE+OO 1.70E+01 5.50E-01 6.64E+02 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.22E+02 O.OOE+OO 5.26E+01 O.OOE+OO 4.66E+02 O.OOE+OO 1.43E+04 Ru-105 1.02E-04 O.OOE+OO 4.03E-05 O.OOE+OO 1.32E-03 O.OOE+OO 6.25E-02 Ru-106 2.45E+03 O.OOE+OO 3.10E+02 O.OOE+OO 4.73E+03 O.OOE+OO 1.58E+05 Ag-110M 6.99E+06 6.46E+06 3.84E+06 O.OOE+OO 1.27E+07 O.OOE+OO 2.64E+09 Page 229 of 267
Revision 5 Aug 31, 2015 Table F-14 (Continued) Adult Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 1.96E+06 7.09E+05 2.62E+05 5.88E+05 7.95E+06 O.OOE+OO 7.81E+06 Te-127M 5.49E+06 1.96E+06 6.69E+05 1.40E+06 2.23E+07 O.OOE+OO 1.84E+07 Te-127 8.00E+01 2.87E+01 1.73E+01 5.92E+01 3.26E+02 O.OOE+OO 6.31E+03 Te-129M 7.22E+06 2.69E+06 1.14E+06 2.48E+06 3.01E+07 O.OOE+OO 3.64E+07 Te-129 3.39E-11 1.27E-11 8.26E-12 2.60E-11 1.43E-10 O.OOE+OO 2.56E-11 Te-131 M 4.33E+04 2.12E+04 1.76E+04 3.35E+04 2.14E+05 O.OOE+OO 2.10E+06 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.87E+05 1.86E+05 1.74E+05 2.05E+05 1.79E+06 O.OOE+OO 8.78E+06 1-130 5.01E+05 1.48E+06 5.84E+05 1.25E+08 2.31E+06 O.OOE+OO 1.27E+06 1-131 3.55E+08 5.08E+08 2.91E+08 1.67E+11 8.71E+08 O.OOE+OO 1.34E+08 1-132 1.98E-01 5.29E-01 1.85E-01 1.85E+01 8.42E-01 O.OOE+OO 9.93E-02 1-133 4.65E+06 8.09E+06 2.47E+06 1.19E+09 1.41 E+07 O.OOE+OO 7.27E+06 1-134 2.27E-12 6.15E-12 2.20E-12 1.07E-10 9.79E-12 O.OOE+OO 5.36E-15 1-135 1.55E+04 4.06E+04 1.50E+04 2.68E+06 6.51E+04 O.OOE+OO 4.58E+04 Cs-134 1.70E+10 4.04E+10 3.30E+10 O.OOE+OO 1.31 E+10 4.34E+09 7.06E+08 Cs-136 7.88E+08 3.11 E+09 2.24E+09 O.OOE+OO 1.73E+09 2.37E+08 3.53E+08 Cs-137 2.21 E+10 3.03E+10 1.98E+10 O.OOE+OO 1.03E+10 3.42E+09 5.86E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 5.32E-09 3.79E-12 1.56E-10 O.OOE+OO 3.54E-12 2.15E-12 9.44E-09 Ba-140 3.23E+06 4.05E+03 2.11 E+05 O.OOE+OO 1.38E+03 2.32E+03 6.64E+06 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 5.43E-01 2.74E-01 7.23E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.01E+04 La-142 2.27E-12 1.03E-12 2.57E-13 O.OOE+OO O.OOE+OO O.OOE+OO 7.53E-09 Ce-141 5.81E+02 3.93E+02 4.46E+01 O.OOE+OO 1.83E+02 O.OOE+OO 1.50E+06 Ce-143 4.98E+OO 3.68E+03 4.07E-01 O.OOE+OO 1.62E+OO O.OOE+OO 1.38E+05 Ce-144 4.29E+04 1.79E+04 2.30E+03 O.OOE+OO 1.06E+04 O.OOE+OO 1.45E+07 Pr-143 1.90E+01 7.60E+OO 9.40E-01 O.OOE+OO 4.39E+OO O.OOE+OO 8.31E+04 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 1.14E+01 1.32E+01 7.87E-01 O.OOE+OO 7.69E+OO O.OOE+OO 6.31E+04 W-187 7.82E+02 6.53E+02 2.28E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.14E+05 Np-239 4.40E-01 4.33E-02 2.39E-02 O.OOE+OO 1.35E-01 O.OOE+OO 8.88E+03 Notes:
- 1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.
3
- 2) For H-3, t_he units are mrem/yr per µCi/m .
Page 230 of 267
Revision 5 Aug 31, 2015 Table F-14a Teen Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.16E+03 1.16E+03 1.16E+03 1.16E+03 1.16E+03 1.16E+03 Na-24 5.15E+05 5.15E+05 5.15E+05 5.15E+05 5.15E+05 5.15E+05 5.15E+05 Cr-51 O.OOE+OO O.OOE+OO 5.99E+03 3.33E+03 1.31E+03 8.55E+03 1.01E+06 Mn-54 O.OOE+OO 1.68E+06 3.34E+05 O.OOE+OO 5.02E+05 O.OOE+OO 3.45E+06 Mn-56 O.OOE+OO 8.78E-04 1.56E-04 O.OOE+OO 1.11 E-03 O.OOE+OO 5.78E-02 Fe-55 5.79E+05 4.11 E+05 9.57E+04 O.OOE+OO O.OOE+OO 2.60E+05 1.78E+05 Fe-59 6.74E+05 1.57E+06 6.07E+05 O.OOE+OO O.OOE+OO 4.96E+05 3.72E+06 Co-58 O.OOE+OO 9.53E+05 2.20E+06 O.OOE+OO O.OOE+OO O.OOE+OO 1.31 E+07 Co-60 . O.OOE+OO 3.34E+06 7.52E+06 O.OOE+OO O.OOE+OO O.OOE+OO 4.35E+07 Ni-63 1.42E+09 1.00E+08 4.81E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.59E+07 Ni-65 8.13E-02 1.04E-02 4.73E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.63E-01 Cu~64 O.OOE+OO 4.69E+03 2.20E+03 O.OOE+OO 1.19E+04 O.OOE+OO 3.64E+05 Zn-65 2.53E+08 8.78E+08 4.09E+08 O.OOE+OO 5.62E+08 O.OOE+OO 3.72E+o8 Zn-69 4.44E-13 8.46E-13 5.92E-14 O.OOE+OO 5.53E-13 O.OOE+OO 1.56E-12 Br-83 O.OOE+OO O,OOE+OO 2.13E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 5.68E+08 2.67E+08 O.OOE+OO O.OOE+OO O.OOE+OO 8.41 E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 5.61E+09 O.OOE+OO -1.61E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.69E+08 Sr-90 1.71 E+11 O.OOE+OO 3.41 E+09 O.OOE+OO O.OOE+OO O.OOE+OO 3.90E+09 Sr-91 1.11E+05 O.OOE+OO 4.41E+03 O.OOE+OO O.OOE+OO O.OOE+OO 5.02E+05 Sr-92 1.86E+OO O.OOE+OO 7.92E-02 O.OOE;+OO O.OOE+OO O.OOE+OO 4.74E+01 Y-90 1.56E+01 O.OOE+OO 4.21 E-01 O.OOE+OO O.OOE+OO O.OOE+OO 1.29E+05 Y~91M 1.41 E-20 O,OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.66E-19 Y-91 1.90E+03 O.OOE+OO 5.08E+01 O.OOE+OO O.OOE+OO O.OOE+OO 7.77E+05 Y-92 1.23E-05 O.OOE+OO 3.57E-07 O.OOE+OO O.OOE+OO O.OOE+OO 3.39E-01. Y-93 4.90E-02 O.OOE+OO 1.34E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.50E+03 Zr-95 1.98E+02 6.25E+01 4.30E+01 O.OOE+OO 9.18E+01 O.OOE+OO 1.44E+05 Zr-97 9.44E-02 1.87E-02 8.61 E-03 O.OOE+OO 2.83E-02 O.OOE+OO 5.06E+03 Nb-95 1.69E+04 9.38E+03 5.16E+03 O.OOE+OO 9.09E+03 O.OOE+OO 4.01E+07 Mo-99 O.OOE+OO 5.36E+06 1.02E+06 O.OOE+OO 1.23E+07 O.OOE+OO 9.59E+06 Tc- 99M 6.89E-01 1.92E+OO 2.49E+01 O.OOE+OO 2.86E+01 1.07E+OO 1.26E+03 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 2.17E+02 O.OOE+OO 9.29E+01 O.OOE+OO 7.66E+02 O.OOE+OO 1.81E+04 Ru-105 1..86E-04 O.OOE+OO 7.24E-05 O.OOE+OO 2.35E-03 O.OOE+OO 1.51 E-01 Ru-106 4.50E+03 O.OOE+OO 5.67E+02 O.OOE+OO 8.68E+03 O.OOE+OO 2.16E+05 Ag-110M 1.16E+07 1.09E+07 6.65E+06 O.OOE+OO 2.09E+07 O.OOE+OO 3.07E+09 Page 231 of 267
Revision 5 Aug 31, 2015 Table F-14a (Continued) Teen Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 3.61E+06 1.30E+06 4.82E+05 1.01 E+06 O.OOE+OO O.OOE+OO 1.06E+07 Te-127M 1.01 E+07 3.59E+06 1.20E+06 2.41 E+06 4.10E+07 O.OOE+OO 2.52E+07 Te-127 1.48E+02 5.25E+01 3.19E+01 1.02E+02 6.00E+02 O.OOE+OO 1.14E+04 Te-129M 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 O.OOE+OO 4.96E+07 Te-129 6.24E-11 2.33E-11 1.52E-11 4.46E-11 2.62E-10 O.OOE+OO 3.41E-10 Te-131M 7.88E+04 3.78E+04 3.15E+04 5.68E+04 3.94E+05 O.OOE+OO 3.03E+06 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 5.13E+05 3.25E+05 3.06E+05 3.42E+05 3.12E+06 O.OOE+OO 1.03E+07 1-130 8.82E+05 2.55E+06 1.02E+06 2.08E+08 3.93E+06 O.OOE+OO 1.96E+06 1-131 6.45E+08 9.02E+08 4.85E+08 2.63E+11 1.55E+09 O.OOE+OO 1.78E+08
- 1-132 3.SOE-01 9.17E-01 3.29E-01 3.09E+01 1.44E+OO O.OOE+OO 3.99E-01 1-133 8.50E+06 1.44E+07 4.40E+06 2.01E+09 2.53E+07 O.OOE+OO 1.09E+07 1-134 4.03E-12 1.07E-11 3.83E-12 1.78E-10 1.68E-11 O.OOE+OO 1.41 E-13 1-135 2.75E+04 7.09E+04 2.63E+04 4.56E+06 1.12E+05 O.OOE+OO 7.85E+04 Cs-134 2.94E+10 6.93E+10 3.22E+10 O.OOE+OO 2.20E+10 8.41 E+09 8.62E+08 Cs-136 1.34E+09 5.28E+09 3.54E+09 O.OOE+OO 2.87E+09 4.53E+08 4.25E+08 Cs-137 4.02E+10 5.34E+10 1.86E+10 O.OOE+OO 1.82E+10 7.06E+09 7.60E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 9.84E-09 6.92E-12 2.87E-10 O.OOE+OO 6.53E-12 4.77E-12 8.78E-08 Ba-140 5.82E+06 7.14E+03 3.75E+05 O.OOE+OO 2.42E+03 4.80E+03 8.98E+06 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 9.75E-01 '4.79E-01 1.27E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.75E+04 La-142 4.09E-12 1.82E-12 4.53E-13 O.OOE+OO O.OOE+OO O.OOE+OO 5.53E-08 Ce-141 1.07E+03 7.12E+02 8.17E+01 O.OOE+OO 3.35E+02 O.OOE+OO 2.04E+06 Ce-143 9.15E+OO 6.66E+03 7.44E-01 O.OOE+OO 2.99E+OO O.OOE+OO 2.00E+OS Ce-144 7.90E+04 3.27E+04 4.24E+03 O.OOE+OO 1.95E+04 O.OOE+OO 1.99E+07 Pr-143 3.48E+01 1.39E+01 1.73E+OO O.OOE+OO 8.08E+OO O.OOE+OO 1.15E+05 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 2.19E+01 2.38E+01 1.43E+OO O.OOE+OO 1.40E+01 O.OOE+OO 8.59E+04 W-187 1.43E+03 1.17E+03 4.08E+02 O.OOE+OO O.OOE+OO O.OOE+OO 3.15E+05 Np-239 8.40E-01 7.92E-02 4.40E-02 O.OOE+OO 2.49E-01 O.OOE+OO 1.27E+04 Notes:
- 1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.
3
- 2) For H-3, the units are mrem/yr per µCi/m .
Page 232 of 267
Revision 5 Aug 31, 2015 Table F-14b Child Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.83E+03 1.83E+03 1.83E+03 1.83E+03 1.83E+03 1.83E+03 Na-24 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 Cr-51 O.OOE+OO O.OOE+OO 1.22E+04 6.78E+03 1.85E+03 1.24E+04 6.47E+05 Mn-54 O.OOE+OO 2.52E+06 6.70E+05 O.OOE+OO 7.06E+05 O.OOE+OO 2.11E+06 Mn-56 O.OOE+OO 1.53E-03 3.46E-04 O.OOE+OO 1.85E-03 O.OOE+OO 2.22E-01 Fe-55 1.45E+06 7.71E+05 2.39E+05 O.OOE+OO O.OOE+OO 4.36E+05 1.43E+05 Fe-59 1.56E+06 2.53E+06 1.26E+06 O.OOE+OO O.OOE+OO 7.33E+05 2.63E+06 Co-58 O.OOE+OO 1.46E+06 4.46E+06 O.OOE+OO O.OOE+OO O.OOE+OO 8.49E+06 Co-60 O.OOE+OO 5.18E+06 1.53E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.87E+07 Ni-63 3.56E+09 1.90E+08 1.21E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.28E+07 Ni-65 1.99E-01 1.87E-02 1.09E-02 O.OOE+OO O.OOE+OO O.OOE+OO 2.29E+OO Cu-64 O.OOE+OO 8.24E+03 4.98E+03 O.OOE+OO 1.99E+04 O.OOE+OO 3.87E+05 Zn-65 4.96E+08 1.32E+09 8.22E+08 O.OOE+OO 8.33E+08 O.OOE+OO 2.32E+08 Zn-69 1.09E-12 1.58E-12 1.46E-13 O.OOE+OO 9.57E-13 O.OOE+OO 9.95E-11. Br-83 O.OOE+OO O.OOE+OO 5.24E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 1.05E+09 6.48E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.78E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 1.39E+10 O.OOE+OO 3.97E+08 O.OOE+OO O.OOE+OO O.OOE+OO 5.38E+08 Sr-90 3.53E+11 O.OOE+OO 7.11 E+09 O.OOE+OO O.OOE+OO O.OOE+OO 3.16E+09 Sr-91 2.72E+05 O.OOE+OO 1.03E+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.00E+05 Sr-92 4.54E+OO O.OOE+OO 1.82E-01 O.OOE+OO O.OOE+OO O.OOE+OO 8.60E+01 Y-90 3.87E+01 O.OOE+OO 1.04E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.10E+05 Y-91M 3.45E-20 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.75E-17 Y-91 4.68E+03 O.OOE+OO 1.25E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.24E+05 Y-92 3.03E-05 O.OOE+OO 8.67E-07 O.OOE+OO O.OOE+OO O.OOE+OO 8.75E-01 Y-93 1.20E-01 O.OOE+OO 3.31E-03 *O.OOE+OO O.OOE+OO O.OOE+OO 1.80E+03 Zr-95 4.60E+02 1:01E+02 9.00E+01 O.OOE+OO 1.45E+02 O.OOE+OO 1.05E+05 Zr-97 2.30E-01 3.32E-02 1.96E-02 O.OOE+OO 4.77E-02 O.OOE+OO 5.03E+03 Nb-95 3.82E+04 1.49E+04 1.06E+04 . O.OOE+OO 1.40E+04 O.OOE+OO 2.75E+07 Mo-99 O.OOE+OO 9.75E+06 2.41 E+06 O.OOE+OO 2.08E+07 O.OOE+OO 8.06E+06 Tc-99M 1.58E+OO 3.10E+OO 5.14E+01 O.OOE+OO 4.50E+01 1.57E+OO 1.76E+03 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 5.14E+02 O.OOE+OO 1.97E+02 O.OOE+OO 1.29E+03 O.OOE+OO 1.33E+04 Ru-105 4.55E-04 O.OOE+OO 1.65E-04 : O.OOE+OO 4.00E-03 O.OOE+OO 2.97E-01 Ru-106 1.11E+04 O.OOE+OO 1.38E+03 O.OOE+OO 1.50E+04 O.OOE+OO 1.72E+05 Ag-110M 2.51E+07 1.69E+07 1.35E+07 O.OOE+OO 3.15E+07 O.OOE+OO 2.01E+09 Page 233 of 267
Revision 5 Aug 31, 2015 Table F-14b (Contini.Jed) Child Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 8.86E+06 2.40E+06 1.18E+06 2.49E+06 O.OOE+oo O.OOE+OO 8.55E+06 Te-127M 2.50E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 O.OOE+OO 2.02E+07 Te-127 3.64E+02 9.83E+01 7.82E+01 2.52E+02 1.04E+03 O.OOE+OO 1.42E+04 Te-129M 3.26E+07 9.09E+06 5.05E+06 1.05E+07 9.56E+07 O.OOE+OO 3.97E+07 Te-129 1.54E-10 4.30E-11 3.66E-11 1.10E-10 4.51 E-10 O.OOE+OO 9.59E-09 Te-131M 1.92E+05 6.63E+04 7.06E+04 1.36E+05 6.42E+05 O.OOE+OO 2.69E+06 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 1.22E+06 5.42E+05 6.55E+05 7.89E+05 5.03E+06 O.OOE+OO 5.46E+06 1-130 2.06E+06 4.17E+06 2.15E+06 4.59E+08 6.23E+06 O.OOE+Op 1.95E+06 1-131 1.56E+09 1.57E+09 8.94E+08 5.20E+11 2.58E+09 O.OOE+OO 1.40E+08 1-132 8.29E-01 1.52E+OO 7.00E-01 7.07E+01 2.33E+OO O.OOE+OO 1.79E+OO 1-133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 O.OOE+OO 1.03E+07 1-134 9.53E-12 1.77E-11 8.14E-12 4.07E-10 2.71E-11 O.OOE+OO 1.17E-11 1-135 6.52E+04 1.17E+05 5.55E+04 1.04E+07 1.80E+05 O.OOE+OO 8.94E+04 Cs-134 6.79E+10 1.11 E+11 2.35E+10 O.OOE+OO 3.45E+10 1.24E+10 6.01E+08 Cs-136 3.03E+09 8.32E+09 5.39E+09 O.OOE+OO 4.43E+09 6.61E+08 2.92E+08 Cs-137 9.67E+10 9.26E+10 1.37E+10 O.OOE+OO 3.02E+10 1.09E+10 5.80E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 2.42E-08 1.29E-11 7.01E-10 O.OOE+OO 1.13E-11 7.59E-12 1.40E-06 Ba-140 1.41 E+07 1.23E+04 8.21E+05 O.OOE+OO 4.01E+03 7.34E+03 7.12E+06 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 2.33E+OO 8.16E-01 2.75E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.27E+04 La-142 9.88E-12 3.15E-12 9.87E-13 O.OOE+OO O.OOE+OO O.OOE+OO 6.24E-07 Ce-141 2.62E+03 1.31E+03 1.94E+02 O.OOE+OO 5.74E+02 O.OOE+OO 1.63E+06 Ce-143 2.25E+01 1.22E+04 1.76E+OO O.OOE+OO 5.11 E+OO O.OOE+OO 1.78E+05 Ce-144 1.95E+05 6.11E+04 1.04E+04 O.OOE+OO 3.38E+04 O.OOE+OO 1.59E+07 Pr-143 8.62E+01 2.59E+01 4.28E+OO O.OOE+OO 1.40E+01 O.OOE+OO 9.30E+04 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 5.37E+01 4.35E+01 3.37E+OO O.OOE+OO 2.39E+01 O.OOE+OO 6.89E+04 W-187 3.47E+03 2.05E+03 9.21E+02 O.OOE+OO O.OOE+OO O.OOE+OO 2.88E+05 Np-239 2.07E+OO 1.48E-01 1.04E-01 O.OOE+OO 4.29E-01 O.OOE+OO 1.10E+04 Notes:
- 1) Units are m 2 mrem/yr per µCi/sec with the exception of H-3.
3
- 2) For H-3, the units are*mrem/yr per µCi/m .
Page 234 of 267
Revision 5 Aug 31, 2015 Table F-14c Infant Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 2.78E+03 2.78E+03 2.78E+03 2.78E+03 2.78E+03 2.78E+03 Na-24 1.87E+06 1.87E+06 1.87E+06 1.87E+06 1.87E+06 1.87E+06 1.87E+06 Cr-51 O.OOE+OO O.OOE+OO 1.93E+04 1.26E+04 2.76E+03 2.46E+04 5.64E+05 Mn-54 O.OOE+OO 4.68E+06 1.06E+06 O.OOE+OO 1.04E+06 O.OOE+OO 1.72E+06 Mn-56 O.OOE+OO 3.75E-03 6.47E-04 O.OOE+OO 3.22E-03 O.OOE+OO 3.41 E-01 Fe-55 1.76E+06 1.13E+06 3.03E+05 O.OOE+OO O.OOE+OO 5.55E+05 1.44E+05 Fe-59 2.92E+06 5.09E+06 2.01E+06 O.OOE+OO O.OOE+OO 1.51 E+06 2.43E+06 Co-58 O.OOE+OO 2.91E+06 7.26E+06 O.OOE+OO O.OOE+OO O.OOE+OO 7.25E+06 Co-60 O.OOE+OO 1.06E+07 2.50E+07 O.OOE+OO O.OOE+OO O.OOE+OO 2.52E+07 Ni-63 4.19E+09 2.59E+08 1.45E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.29E+07 Ni-65 4.21 E-01 4.77E-02 2.17E-02 O.OOE+OO O.OOE+OO O.OOE+OO 3.63E+OO Cu-64 O.OOE+OO 2.05E+04 9.48E+03 O.OOE+OO 3.46E+04 O.OOE+OO 4.20E+05 Zn-65 6.66E+08 2.28E+09 1.05E+09 O.OOE+OO 1.11E+09 O.OOE+OO 1.93E+09 Zn-69 2.33E-12 4.19E-12 3.12E-13 O.OOE+OO 1.74E-12 O.OOE+OO 3.42E-10 Br-83 O.OOE+OO O.OOE+OO 1.11 E-01 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb~86 O.OOE+OO 2.67E+09 1.32E+09 O.OOE+OO O.OOE+OO O.OOE+OO 6.84E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 2.64E+10 O.OOE+OO 7.58E+08 O.OOE+OO O.OOE+OO O.OOE+OO 5.43E+08 Sr-90 3.91 E+11 O.OOE+OO 7.92E+09 O.OOE+OO O.OOE+OO O.OOE+OO 3.19E+09 Sr-91 5.66E+05 O.OOE+OO 2.05E+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.70E+05 Sr-92 9.65E+OO O.OOE+OO 3.59E-01 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E+02 Y-90 8.19E+01 O.OOE+OO 2.20E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.13E+05 Y-91M 7.31 E-20 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.44E-16 Y-91 8.79E+03 O.OOE+OO 2.34E+02 O.OOE+OO O.OOE+OO O.OOE+OO 6.30E+05 Y-92 6.44E-05 O.OOE+OO 1.81 E-06 O.OOE+OO O.OOE+OO O.OOE+OO 1.23E+OO Y-93 2.57E-01 O.OOE+OO 6.99E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.03E+03 Zr-95 8.17E+02 1.99E+02 1A1E+02 O.OOE+OO 2.15E+02 O.OOE+OO 9.91E+04 Zr-97 4.87E-01 8.35E-02 3.81 E-02 O.OOE+OO 8.42E-02 O.OOE+OO 5.33E+03 Nb-95 7.13E+04 2.94E+04 1.70E+04 O.OOE+OO 2.10E+04 O.OOE+OO 2.48E+07 Mo-99 O.OOE+OO 2.49E+07 4.86E+06 O.OOE+OO 3.72E+07 O.OOE+OO 8.21E+06 Tc-99M 3.29E+OO 6.78E+OO 8.73E+01 O.OOE+OO 7.29E+01 3.54E+OO 1.97E+03 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.04E+03 O.OOE+OO 3.48E+02 O.OOE+OO 2.16E+03 O.OOE+OO 1.27E+04 Ru-105 9.60E-04 O.OOE+OO 3.23E-04 O.OOE+OO 7.06E-03 O.OOE+OO 3.82E-01 Ru-106 2.28E+04 O.OOE+OO 2.85E+03 O.OOE+OO 2.70E+04 O.OOE+OO 1.73E+05 Ag-110M 4.63E+07 3.38E+07 2.24E+07 O.OOE+OO 4.84E+07 O.OOE+OO 1.75E+09 Page 235 of 267
Revision 5 Aug 31, 2015 Table F-14c (Continued) Infant Grass-Goat-Milk Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 1.81 E+07 6.05E+06 2.45E+06 6.09E+06 O.OOE+OO O.OOE+OO 8.62E+06 Te-127M 5.05E+07 1.68E+07 6.12E+06 1.46E+07 1.24E+08 O.OOE+OO 2.04E+07 Te-127 7.74E+02 2.59E+02 1.66E+02 6.30E+02 1.89E+03 O.OOE+OO 1.63E+04 Te-129M 6.68E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 O.OOE+OO 3.99E+07 Te-129 3.26E-10 1.13E-10 7.62E-11 2.74E-10 8.13E-10 O.OOE+OO 2.61 E-08 Te-131 M 4.05E+05 1.63E+05 1.35E+05 3.30E+05 1.12E+06 O.OOE+OO 2.74E+06 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.52E+06 1.25E+06 1.17E+06 1.84E+06 7.81E+06 O.OOE+OO 4.62E+06 1-130 4.24E+06 9.32E+06 3.74E+06 1.04E+09 1.02E+07 O.OOE+OO 2.00E+06 1-131 3.26E+09 3.85E+09 1.69E+09 1.26E+12 4.49E+09 O.OOE+OO 1.37E+08 1-132 1.72E+OO 3.49E+OO 1.24E+OO 1.64E+02 3.90E+OO O.OOE+OO 2.83E+OO 1-133 4.36E+07 6.35E+07 1.86E+07 1.15E+10 7.46E+07 O.OOE+OO 1.07E+07 1-134 1.98E-11 4.05E-11 1.44E-11 9.44E-10 4.53E-11 O.OOE+OO 4.19E-11 1-135 1.36E+05 2.70E+05 9.83E+04 2.42E+07 3.01E+05 O.OOE+OO 9.76E+04 Cs-134 1.09E+11 2.04E+11 2.06E+10 O.OOE+OO 5.25E+10 2.15E+10 5.54E+08 Cs-136 5.91E+09 1.74E+10 6.49E+09 O.OOE+OO 6.93E+09 1.42E+09 2.64E+08 Cs-137 1.54E+11 1.81 E+11 1.28E+10 O.OOE+OO 4.85E+10 1.96E+10 5.65E+08 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 5.14E-08 3.41E-11 1.49E-09 O.OOE+OO 2.05E-11 2.07E-11 3.26E-06 Ba-140 2.89E+07 2.89E+04 1.49E+06 O.OOE+OO 6.87E+03 1.78E+04 7.11E+06 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 4.88E+OO 1.92E+OO 4.95E-01 O.OOE+OO O.OOE+OO O.OOE+OO 2.26E+04 La-142 2.08E-11 7.62E-12 1.82E-12 O.OOE+OO O.OOE+OO O.OOE+OO 1.29E-06 Ce-141 5.20E+03 3.17E+03 3.73E+02 O.OOE+OO 9.78E+02 O.OOE+OO 1.64E+06 Ce-143 4.75E+01 3.15E+04 3.60E+OO O.OOE+OO 9.19E+OO O.OOE+OO 1.84E+05 Ce-144 2.79E+05 1.14E+05 1.56E+04 O.OOE+OO 4.62E+04 O.OOE+OO 1.60E+07 Pr-143 1.78E+02 6.67E+01 8.84E+OO O.OOE+OO 2.48E+01 O.OOE+OO 9.41 E+04 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 1.07E+02 1.09E+02 6.70E+OO O.OOE+OO 4.22E+01 O.OOE+OO 6.93E+04 W-187 7.29E+03 5.07E+03 1.75E+03 O.OOE+OO O.OOE+OO O.OOE+OO 2.98E+05 Np-239 4.37E+OO 3.91 E-01 2.21 E-01 O.OOE+OO 7.80E-01 O.OOE+OO 1.13E+04 Notes:
- 1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.
3
- 2) For H-3, the units are mrem/yr per µCi/m .
Page 236 of 267
Revision 5 Aug 31, 2015 Table F-15 Adult Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.85E+02 1.85E+02 1.85E+02 1.85E+02 1.85E+02 1.85E+02 Na-24 1.45E-03 1.45E-03 1.45E-03 1.45E-03 1.45E-03 1A5E-03 1.45E-03 Cr-51 O.OOE+OO O.OOE+OO 7.04E+03 4.21E+03 1.55E+03 9.34E+03 1.77E+06 Mn-54 O.OOE+OO 9.18E+06 1.75E+06 O.OOE+OO 2.73E+06 O.OOE+OO 2.81E+07 Mn-56 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 2.93E+08 2.03E+08 4.72E+07 O.OOE+OO O.OOE+OO 1.13E+08 1.16E+08 Fe-59 2.65E+08 6.24E+08 2.39E+08 O.OOE+OO O.OOE+OO 1.74E+08 2.08E+09 Co-58 O.OOE+OO 1.82E+07 4.09E+07 O.OOE+OO O.OOE+OO O.OOE+OO 3.70E+08 Co-60 O.OOE+OO 7.52E+07 1.66E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.41 E+09 Ni-63 1.89E+10 1.31E+09 6.33E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.73E+08 Ni-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cu-64 O.OOE+OO 2.52E-07 1.18E-07 O.OOE+OO 6.36E-07 O.OOE+OO 2.15E-05 Zn-65 3.56E+08 1.13E+09 5.12E+08 O.OOE+OO 7.57E+08 O.OOE+OO 7.13E+08 Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.006+00 O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 4.88E+08 2.28E+08 O.OOE+OO O.OOE+OO O.OOE+OO 9.63E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 . O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 3.01E+08 O.OOE+OO 8.65E+06 O.OOE+OO O.OOE+OO O.OOE+OO 4.83E+07 Sr-90 1.43E+10 O.OOE+OO 2.87E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.59E+08 Sr-91 1.43E-10 O.OOE+OO 5.79E-12 O.OOE+OO O.OOE+OO O.OOE+OO 6.83E-10 Sr-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 1.08E+02 O.OOE+OO 2.91E+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.15E+06 Y-91M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 1.13E+06 O.OOE+OO 3.03E+04 O.OOE+OO O.OOE+OO O.OOE+OO 6.23E+08 Y-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-93 4.39E-12 O.OOE+OO 1.21E-13 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E-07 Zr-95 1.87E+06 6.01E+05 4.07E+05 O.OOE+OO 9.43E+05 O.OOE+OO 1.91 E+09 Zr-97 2.04E-05 4.12E-06 1.88E~06 O.OOE+OO 6.22E-06 O.OOE+OO 1.28E+OO Nb-95 2.30E+06 1.28E+06 6.89E+05 O.OOE+OO 1.27E+06 O.OOE+OO 7.78E+09 Mo-99 O.OOE+OO 9.93E+04 1.89E+04 O.OOE+OO 2.25E+05 O.OOE+OO 2.30E+05 Tc- 99M O.OOE+OO 1.22E-20 1.56E-19 O.OOE+OO 1.85E-19 O.OOE+OO 7.23E-18 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.Q5E+b8 O.OOE+OO 4.53E+07 O.OOE+OO 4.01E+08 O.OOE+OO 1.23E+10 Ru-105 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-106 2.80E+09 O.OOE+OO 3.54E+08 O.OOE+OO 5.40E+09 O.OOE+OO 1.81 E+11 Ag-110M 6.68E+06 6.18E+06 3.67E+06 O.OOE+OO 1.22E+07 O.OOE+OO 2.52E+09 Page 237 of 267
Revision 5 Aug 31, 2015 Table F-15 (Continued) Adult Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 3.59E+08 1.30E+08 4.81E+07 1.08E+08 1.46E+09 O.OOE+OO 1.43E+09 Te-127M 1.12E+09 3.99E+08 1.36E+08 2.85E+08 4.53E+09 O.OOE+OO 3.74E+09 Te-127 2.50E-10 8.98E-11 5.41E-11 1.85E-10 1.02E-09 O.OOE+OO 1.97E-08 Te-129M 1.13E+09 4.23E+08 1.79E+08 3.89E+08 4.73E+09 O.OOE+OO 5.71E+09 Te-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-131M 4.49E+02 2.20E+02 1.83E+02 3.48E+02 2.23E+03 O.OOE+OO 2.18E+04 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 1.40E+06 9.03E+05 8.48E+05 9.98E+05 8.70E+06 O.OOE+OO 4.27E+07 1-130 2.03E-06 5.98E-06 2.36E-06 5.07E-04 9.33E-06 O.OOE+OO 5.15E-06 1-131 1.07E+07 1.54E+07 8.80E+06 5.03E+09 2.63E+07 O.OOE+OO 4.05E+06 1-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-133 3.70E-01 6.43E-01 1.96E-01 9.45E+01 1.12E+OO O.OOE+OO 5.78E-01 1-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-135 4.66E-17 1.22E-16 4.50E-17 8.04E-15 1.95E-16 O.OOE+OO 1.38E-16 Cs-134 6.58E+08 1.57E+09 1.28E+09 O.OOE+OO 5.07E+08 1.68E+08 2.74E+07 Cs-136 1.20E+07 4.73E+07 3.40E+07 O.OOE+OO 2.63E+07 3.61 E+06 5.37E+06 Cs-137 8.72E+08 1.19E+09 7.81E+08 O.OOE+OO 4.05E+08 1.35E+08 2.31E+07 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 2.88E+07 3.61E+04 1.88E+06 O.OOE+OO 1.23E+04 2.07E+04 5.92E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 3.76E-02 1.90E-02 5.01 E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.39E+03 La-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-141 1.40E+04 9.49E+03 1.08E+03 O.OOE+OO 4.41E+03 O.OOE+OO 3.63E+07 Ce-143 1.99E-02 1.47E+01 1.63E-03 O.OOE+OO 6.47E-03 O.OOE+OO 5.49E+02 Ce-144 1.46E+06 6.09E+05 7.83E+04 O.OOE+OO 3.61E+05 O.OOE+OO 4.93E+08 Pr-143 2.10E+04 8.42E+03 1.04E+03 O.OOE+OO 4.86E+03 O.OOE+OO 9.20E+07 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 7.21 E+03 8.33E+03 4.98E+02 O.OOE+OO 4.87E+03 O.OOE+OO 4.00E+07 W-187 2.07E-02 1.73E-02 6.04E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.66E+OO Np-239 2.57E-01 2.53E-02 1.40E-02 O.OOE+OO 7.90E-02 O.OOE+OO 5.19E+03 Notes:
- 1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.
3
- 2) For H-3, the units are mrem/yr per µCi/m .
Page 238 of 267
Revision 5 Aug 31, 2015 Table F-15a Teen Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.10E+02 1.10E+02 1.10E+02 1.10E+02 1.10E+02 1.10E+02 Na-24 1.16E-03 1.16E-03 1.16E-03 1.16E-03 1.16E-03 1.16E-03 1.16E-03 Cr-51 O.OOE+OO O.OOE+OO 5.63E+03 3.13E+03 1.23E+03 8.04E+03 9.46E+05 Mn-54 O.OOE+OO 7.00E+06 1.39E+06 O.OOE+OO 2.09E+06 O.OOE+OO 1.44E+07 Mn-56 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 2.38E+08 1.69E+08 3.94E+07 O.OOE+OO O.OOE+OO 1.07E+08 7.31E+07 Fe-59 2.12E+08 4.95E+08 1.91 E+08 O.OOE+OO O.OOE+OO 1.56E+08 1.17E+09 Co-58 O.OOE+OO 1.41E+07 3.24E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.94E+08 Co-60 O.OOE+OO 5.83E+07 1.31E+08 O.OOE+OO O.OOE+OO O.OOE+OO 7.60E+08 Ni-63 1.52E+10 1.07E+09 5.15E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.71 E+08 Ni-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cu-64 O.OOE+OO 2.06E-07 9.68E-08 O.OOE+OO 5.21 E-07 O.OOE+OO 1.60E-05 Zn-65 2.50E+08 8.69E+08 4.05E+08 O.OOE+OO 5.56E+08 O.OOE+OO 3.68E+08 Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 4.08E+08 1.91E+08 O.OOE+OO O.OOE+OO O.OOE+OO 6.03E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 2.54E+08 O.OOE+OO 7.28E+06 O.OOE+OO O.OOE+OO O.OOE+OO 3.03E+07 Sr-90 9.89E+09 O.OOE+OO 1.98E+08 O.OOE+OO O.OOE+OO O.OOE+OO 2.26E+08 Sr-91 1.21 E-10 O.OOE+OO 4.80E-12 O.OOE+OO O.OOE+OO O.OOE+OO 5.47E-10 Sr-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 9.13E+01 O.OOE+OO 2.46E+OO O.OOE+OO O.OOE+OO O.OOE+OO 7.53E+05 Y-91M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 9.54E+05 O.OOE+OO 2.56E+04 O.OOE+OO O.OOE+OO O.OOE+OO 3.91E+08 Y-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-93 3.71 E-12 O.OOE+OO 1.02E-13 O.OOE+OO O.OOE+OO O.OOE+OO 1.13E-07 Zr-95 1.50E+06 4.74E+05 3.26E+05 O.OOE+OO 6.96E+05 O.OOE+OO 1.09E+09 Zr-97 1.70E-05 3.37E-06 1.55E-06 O.OOE+OO 5.10E-06 O.OOE+OO 9.11 E-01 Nb-95 1.80E+06 9.98E+05 5.49E+05 O.OOE+OO 9.67E+05 O.OOE+OO 4.27E+09 Mo-99 O.OOE+OO 8.21E+04 1.57E+04 O.OOE+OO 1.88E+05 O.OOE+OO 1.47E+05 Tc- 99M O.OOE+OO O.OOE+OO 1.24E-19 O.OOE+OO 1.43E-19 O.OOE+OO 6.29E-18 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 8.56E+07 O.OOE+OO 3.66E+07 O.OOE+OO 3.02E+08 O.OOE+OO 7.15E+09 Ru-105 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-106 2.36E+09 O.OOE+OO 2.97E+08 O.OOE+OO 4.55E+09 O.OOE+OO 1.13E+11 Ag-110M 5.06E+06 4.79E+06 2.91E+06 O.OOE+OO 9.13E+06 O.OOE+OO 1.35E+09 Page 239 of 267
Revision 5 Aug 31, 2015 Table F-15a (Continued) Teen Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 3.03E+08 1.09E+08 4.06E+07 8.47E+07 O.OOE+OO O.OOE+OO 8.95E+08 Te-127M 9.41 E+08 3.34E+08 1.12E+08 2.24E+08 3.82E+09 O.OOE+OO 2.35E+09 Te-127 2.12E-10 7.53E-11 4.57E.:11 1.46E-10 8.60E-10 O.OOE+OO 1.64E-08 Te-129M 9.49E+08 3.52E+08 1.50E+08 3.06E+08 3.97E+09 O.OOE+OO 3.56E+09 Te-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-131M 3.75E+02 1.80E+02 1.50E+02 2.70E+02 1.87E+03 O.OOE+OO 1.44E+04 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te~132 1.14E+06 7.24E+05 6.81E+05 7.63E+05 6.94E+06 O.OOE+OO 2.29E+07 1-130 1.63E-06 4.72E-06 1.88E-06 3.85E-04 7.27E-06 O.OOE+OO 3.63E-06 1-131 8.92E+06 1.25E+07 6.71 E+06 3.64E+09 2.15E+07 O.OOE+OO 2.47E+06 1-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-133 3.09E-01 5.25E-01 1.60E-01 7.32E+01 9.20E-01 O.OOE+OO 3.97E-01 1-134 O.OOE+OO O.OOE+po O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-135 3.79E-17 9.75E-17 3.61E-17 6.27E-15 1.54E-16 O.OOE+OO 1.08E-16 Cs-134 5.23E+08 1.23E+09 5.71E+08 O.OOE+OO 3.91E+08 1.49E+08 1.53E+07 Cs-136 9.34E+06 3.68E+07 2.47E+07 O.OOE+OO 2.00E+07 3.15E+06 2.96E+06 Cs-137 7.24E+08 9.63E+08 3.36E+08 O.OOE+oo 3.28E+08 1.27E+08 1.37E+07 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba~140 2.38E+07 2.91E+04 1.53E+06 O.OOE+OO 9.88E+03 1.96E+04 3.67E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 3.09E-02 1.52E"02 4.04E-03 O.OOE+OO O.OOE+OO O.OOE+OO 8.73E+02 La-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-141 1.18E+04 7.87E+03 9.04E+02 O.OOE+OO 3.70E+03 O.OOE+OO 2.25E+07 Ce-143 1.67E-02 1.22E+01 1.36E-03 O.OOE+OO 5.46E-03 . O.OOE+OO 3.66E+02 Ce-144 1.23E+06 5.08E+05 6 ..60E+04 O.OOE+OO 3.04E+05 O.OOE+OO 3.09E+08 Pr-143 1.77E+04 7.05E+03 8.79E+02 O.OOE+OO 4.10E+03 O.OOE+OO 5_.81E+07 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 6.35E+03 6.90E+03 4.14E+02 O.OOE+OO 4.05E+03 O.OOE+OO 2.49E+07 W-187 1.73E-02 1.41 E-02 4.94E-03 O.OOE+OO O.OOE+OO O.OOE+OO 3.82E+OO Np-239 2.25E-01 2.12E-02 1.18E-02 O.OOE+OO 6.66E-02 O.OOE+OO 3.41E+03 Notes:
- 1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.
3
- 2) *Far H-3, the units are mrem/yr per µCi/m .
Page 240 of 267
- Revision 5 Aug 31, 2015 Table F-15b Child Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI H-3 O.OOE+OO 1.34E+02 1.34E+02 1.34E+02 1.34E+02 1.34E+02 1.34E+02 Na-24 1.84E-03 1.84E-03 1.84E-03 1.84E-03 1.84E-03 1.84E-03 1.84E-03 Cr-51 O.OOE+OO O.OOE+OO 8.78E+03 4.87E+03 1.33E+03 8.90E+03 4.66E+05 Mn-54 O.OOE+OO 8.01E+06 2.13E+06 O.OOE+OO 2.25E+06 O.OOE+OO 6.72E+06 Mn-56 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Fe-55 4.57E+08 2.42E+08 7.51E+07 O.OOE+OO O.OOE+OO 1.37E+08 4.49E+07 Fe-59 3.76E+08 6.08E+08 3.03E+08 O.OOE+OO O.OOE+OO 1.76E+08 6.34E+08 Co-58 O.OOE+OO 1.64E+07 5.03E+07 O.OOE+OO O.OOE+OO O.OOE+OO 9.59E+07 Co-60 O.OOE+OO 6.93E+07 2.04E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.84E+08 Ni-63 2.91E+10 1.56E+09 9.91E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.05E+08 Ni-65 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Cu-64 O.OOE+OO 2.77E-07 1.67E-07 O.OOE+OO 6.68E-07 O.OOE+OO 1.30E-05 Zn-65 3.75E+08 1.00E+09 6.22E+08 O.OOE+OO 6.30E+08 O.OOE+OO 1.76E+08 Zn-69 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-83 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-84 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Br-85 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-86 O.OOE+OO 5.78E+08 3.55E+08 O.OOE+OO O.OOE+OO O.OOE+OO 3.72E+07 Rb-88 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Rb-89 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Sr-89 4.81E+08 O.OOE+OO 1.37E+07 O.OOE+OO O.OOE+OO O.OOE+OO 1.86E+07 Sr-90 1.57E+10 O.OOE+OO 3.15E+08 O.OOE+OO O.OOE+OO O.OOE+OO 1.40E+08 Sr-91 2.26E-10 O.OOE+OO 8.54E-12 O.OOE+OO O.OOE+OO O.OOE+OO 5.00E-10 Sr-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-90 1.73E+02 O.OOE+OO 4.62E+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.92E+05 Y-91M O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-91 1.80E+06 O.OOE+OO 4.82E+04 O.OOE+OO O.OOE+OO O.OOE+OO 2.40E+08 Y-92 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Y-93 6.97E-12 O.OOE+OO 1.91E-13 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E-07 Zr-95 2.67E+06 5.86E+05 5.22E+05 O.OOE+OO 8.39E+05 O.OOE+OO 6.11 E+08 Zr-97 3.16E-05 4.57E-06 2.?0E-06 O.OOE+OO 6.56E-06 O.OOE+OO 6.93E-01 Nb-95 3.11 E+06 1.21 E+06 8.64E+05 O.OOE+OO 1.14E+06 O.OOE+OO 2.24E+09 Mo-99 O.OOE+OO 1.14E+05 2.82E+04 O.OOE+OO 2.44E+05 O.OOE+OO 9.44E+04 Tc- 99M O.OOE+OO 1.18E-20 1.96E-19 O.OOE+OO 1.72E-19 O.OOE+OO 6.72E-18 Tc-101 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-103 1.55E+08 O.OOE+OO 5.95E+07 O.OOE+OO 3.90E+08 O.OOE+OO 4.00E+09 Ru-105 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ru-106 4.44E+09 O.OOE+OO 5.54E+08 O.OOE+OO 5.99E+09 O.OOE+OO 6.90E+10 Ag-110M 8.39E+06 5.67E+06 4.53E+06 O.OOE+OO 1.06E+07 O.OOE+OO 6.74E+08 Page 241 of 267
Revision 5 Aug 31, 2015 Table F-15b (Continued). Child Grass-Cow-Meat Dose Factors Nuclide Bone Liver T Body Thyroid Kidney Lung Gl-LLI Te-125M 5.70E+08 1.54E+08 7.59E+07 1.60E+08 O.OOE+OO O.OOE+OO 5.50E+08 Te-127M 1.77E+09 4.78E+08 2.11E+08 4.24E+08 5.06E+09 O.OOE+OO 1.44E+09 Te-127 3.99E-10 1.08E-10 8.56E-11 2.76E-10 1.14E-09 O.OOE+OO 1.56E-08 Te-129M 1.79E+09 5.00E+08 2.78E+08 5.77E+08 5.25E+09 O.OOE+OO 2.18E+09 Te-129 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-131M 6.97E+02 2.41E+02 2.57E+02 4.96E+02 2.33E+03 O.OOE+OO 9.78E+03 Te-131 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Te-132 2.09E+06 9.23E+05 1.12E+06 1.34E+06 8.57E+06 O.OOE+OO 9.30E+06 1-130 2.92E-06 5.89E-06 3.04E-06 6.49E-04 8.81E-06 O.OOE+OO 2.76E-06 1-131 1.65E+07 1.66E+07 9.45E+06 5.50E+09 2.73E+07 O.OOE+OO 1.48E+06 1-132 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-133 5.75E-01 7.10E-01 2.69E-01 1.32E+02 1.18E+OO O.OOE+OO 2.86E-01 1-134 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1-135 6.86E-17 1.23E-16 5.84E-17 1.09E-14 1.89E-16 O.OOE+OO 9.40E-17 Cs-134 9.22E+08 1.51E+09 3.19E+08 O.OOE+OO 4.69E+08 1.68E+08 8.16E+06 Cs-136 1.61 E+07 4.43E+07 2.87E+07 O.OOE+OO 2.36E+07 3.52E+06 1.56E+06 Cs-137 1.33E+09 1.28E+09 1.88E+08 O.OOE+OO 4.16E+08 1.50E+08 7.99E+06 Cs-138 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-139 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-140 4.39E+07 3.84E+04 *2.56E+06 O.OOE+OO 1.25E+04 2.29E+04 2.22E+07 Ba-141 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ba-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO La-140 5.66E-02 1.98E-02 6.67E-03 O.OOE+OO O.OOE+OO O.OOE+OO 5.52E+02 La-142 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Ce-141 2.22E+04 1.11E+04 1.64E+03 O.OOE+OO 4.85E+03 O.OOE+OO 1.38E+07 Ce-143 3.14E-02 1.70E+01 2.46E-03 O.OOE+OO 7.14E-03 O.OOE+OO 2.49E+02 Ce-144 2.32E+06 7.26E+05 1.24E+05 O.OOE+OO 4.02E+05 O.OOE+OO 1.89E+08 Pr-143 3.34E+04 1.00E+04 1.66E+03 O.OOE+OO 5.44E+03 O.OOE+OO 3.61E+07 Pr-144 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Nd-147 1.19E+04 9.65E+03 7.47E+02 O.OOE+OO 5.29E+03 O.OOE+OO 1.53E+07 W-187 3.21 E-02 1.90E-02 8.52E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.67E+OO Np-239 4.23E-01 3.04E-02 2.14E-02 O.OOE+OO 8.79E-02 O.OOE+OO 2.25E+03 Notes:
- 1) Units are m2 mrem/yr per µCi/sec with the exception of H-3.
3
- 2) For H-3, the units are mrem/yr per µCi/m .
- 3) The infant age group is assumed to receive no dose through the meat ingestion pathway therefore no dose factors are supplied.
Page 242 of 267
Revision 5 Aug 31, 2015 Supplemental Table F-A Mixed Mode Joint Frequency Distribution Table Summaries 250 Foot Elevation Data Summary Table of Percent by Dlrectton and c111ss CI ass N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW Total A .267 .504 .349 .248 .243 .315 .542 .409 .247 .214 .335 .440 .648 .737 .705 .400 6.604 B .068 .110 .085 .055 .079 .069 .118 . 117 .067 ..050 .090 .105 .143 .138 .143 .152 t.590 c .t04 . 162 . 121 .059 .098 .087 .142 .139 .071 .065 .104 .132 .139
- 141 .183 . 146 t.892 D .745 .992 .685 .498 .544 .536 .741 .887 .652 .603 .978 .933 1. 115 I. 136 t .361 f.003 13.309 E t. 512 t .507 1 .234 I. 161 t.021 .924 1.376 t .887 1.597 t .672 2.358 2.073 2.051 2.097 2.238 1 .620 26.327 F .129 .603 .521 .386 .409 .410 .568 .923 1.196 t .133 1.354 .977 .897 .875 .858 .644 12.483 G .499 .4t2 .352 .283 .246 .247 .362 .700 t.366 1.480 1.008 .612 .421 .428 .463 .388 9.265 Total 3.924 4.292 3.346 2.689 2.640 2.588 3.848 5.062 5.097 !5.2t7 6.227 5.272 5.414 5.552 5.950 4.353 71.471 summary Table of Percent by Direction and Speed Speed N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW Total
.45 .003 .ooo .005 .013 .009 .006 .000 .OtO .014 .002 .000 .003 .ooo .001 .001 .005 .074 t.05 .023 .022 .026 .043 .027 .036 .030 .035 .026 .023 .027 .027 .027 .030 .026 .031 .459 2.05 .194 . '72 .200 .239 .270 .261 .262 .260 .224 .187 .189 .158 .159 .217 .213 .180 3.391 3.05 .320 .372 .529 .560 .576 .515 .586 .601 .414 .362 .393 .318 .343 .433 .572 .344 7.238 4.05 .478 .599 .629 .522 .514 .473 .722 .842 .562 .590 .595 .548 .546 .716 .831 .595 9.764 5.05 .649 .720 .650 .456 .374 .392 .753 .898 .886 .895 .937 .813 .809 1.029 1. 145 .851 12.256 6.05 .656 .713 .484 .296 .247 .262 .529 .807 .978 .968. 1. 115 .993 .872 1.215 1.362 .971 12.467 8.05 1. 106 1.257 .615 .372 .422 .478 .722 1.237 L609 1.749 2.243 1.856 1.990 1.651 , .628 1. 180 20., 16 f0.05 .458 .407 . 191 .171 .182 . 146 .229 .348 .365 .412 .677 .522 .630 .249 .164 .187 5.338 13.05 .037 .029 .016 .017 .020 .012 .017 .023 .022 .029 .048 .034 .037 .011 .007 .010 .369 18.00 .ooo .000 .000 .ooo .ooo .000 .000 .ooo .000 .ooo .ooo .ooo .ooo .ooo .ooo .000 .000 99.00 .000 .ooo .000 .000 .ooo .000 .000 .ooo .000 .ooo .ooo .000 .000 .000 .000 .000 .000 Tota1 3;924 4.292 3.346 2.689 2.640 2.588 3.848 5.062 5.097 5.217 6.227 5.272 5.414 5.552 5.950 4.353 7i. 471 NOTE: Wind directions in tables are presented in *wind from* and not "wind to* direction.
In _order to determine the final mixed mode values, 7.1.471% of the elevated value (pr~sented in the 250 FT Mixed Mode table) anCi 29.529% of the ground level value (presented in the 30 FT Mixed Mode table) are used to calculate the final values. Page 243 of 267
Revision 5 Aug 31, 2015 Supplemental Table F-A - Continued Mixed Mode Joint Frequency Distribution Table Summaries 250 Foot Elevation Data Summary Table of Percent by Spead and Class Clas!! A B c D E F G Speed
.45 .001 .ooo .003 .006 .025 .018 .023 1.05 .006 .004 .005 .034 .147 .070 .f93 2.05 .119 .048 .074 .456 1.047 .616 1.031 3.05 .564 .166 .196 1.332 2.330 1.167 1.485 4.05 .940 .22t .275 1.932 3.494 1.459 1.443 5.05 t .250 .267 .320 2.204 4.388 2.178 1.847 6.05 1.204 .321 .306 2.'76 4.544 2.456 1.460 8.05 1. 923 .401 .539 3.884 7.909 3.699 1. 760 10.05 .560 . 151 . 161 1. 188 2.279 .784 .215 13.05 .037 .OH .013 .096 .165 .039 .001 18.00 .000 .000 .ooo .ooo .ooo .000 .ooo 99.00 .000 .000 .000 .000 .ooo .000 .ooo Page 244 of 267
Revision 5 Aug 31, 2015 Supplemental Table F-A - Continued Mixed Mode Joint Frequency Distribution Table Summaries 35 Foot Elevation Data Summary Table of Percent by Dtrectton and Class Class N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW Total A .325 .401 . 141 .095 .077 .100 .120 .122 .108 .127 .198 .209 .332 .278 .210 .186 3.029 B .093 .099 .037 .028 .020 .014 .021 .048 .0'41 .020 .056 .061 .080 .049 .050 .058 .775 c .103 .122 .047 .027 .030 .028 .()28 .047 .029 .031 .065 .077 .090 * ()\;6 .054 .052 .885 D .708 .607 .317 .291 .266 .182 .186 .283 .281 .283 .607 .505 .664 .o~ .442 .396 6.431 E 1.140 .850 .531 .507 .431 .288 .289 .856 .894 .818 1.403 1. 177 1.133 .62\ .600 .384 11. 722 F .273 .144 .099 .098 .090 .066
- 109 .165 * !1!17 .449 .569 .436 .349 .232\ .175 . 109 3.919 G .059 .029 .027 .018 .031 .038 .03~ .063 .412 .289 .247 .159 . 119
- t 14 i .081 .042 1. 768 Total 2.700 2.252 1. 199 1 .065 .946 . 717 .792 1.384 2.322 2.017 3.144 2.623 2.766 1.764 '.611 1.227 28.529 Summary Table of Percent by D1rectton end Speed Speed N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW "'NW Total
.45 .001 .002 .001 .ooo .001 .001 .001 .003 .002 .003 .002 .002 .000 .002 :003 .001 .025 1.05 .007 .006 .007 .008 .005 .008 .008 .009 .019 .020 .021 .012 .Ott .011 .015 .Ott .178 2.05 .082 .053 .034 .027 .033 .042 .058 .047 .t62 .250 .218 .167 .120 .167 .219 .098 1. '775 3.05 . t70 .146 .103 .076 .075 .093 . 180 .* 148 .483 .360 .315 .312 .327 .349 .356 .205 3.699 4.05 .214 .250 .t57 .090 .086 .095 .183 .255 .614 .250 .. 350 .379 .389 .291 .350 .230 A. 182 5.05 .273 . 311 .149 .084 .090 .066 .127 .245 .469 .225 .369 .382 .391 .255 .. 251 .192 ~.878 6.05 .438 .386 . 181 .091 .107 .080. .083 .214 .278 .292 .470 .403 .450 .224 .211 . 173 4 .\)80 B.05 .892 .607 .268 .225 .208 . 161 . 118 .323 .219 .473 1.001 .677 .762 .388 .190 .262 6. l75 10.05 . 413 .313 .208 .333 .213 . .118 .032 .114 .061 .128 .317 .209 .2t9 .o6t .019 .046 2.8~
13.05 . 178 .155 .088 . 117 .102 .050 .003 .025 .Ot!S .Of4 .075 .079 .085 .014 .ooo .009 1.00~ 18.00 .032 .023 .004 .013 .025 .003 .ooo .000 .ooo .001 .005 .003 .012 .003 .000 .ooo .123 99.00 .000 .ooo .000 .ooo .ooo .ooo .ooo .000 .000 .000 .000 .000 .000 .000 .ooo .ooo .000 Total 2.700 2.252 1.199 1.065 .946 .717 .792 1.384 2.322 2.017 3. 144 2.623 2.766 1. 764 t.6t1 t.227 28.529 NOTE: Wind directions in tables are presented in *wind from* and not *wind to" direction. Page 245 of 267
Revision 5 Aug 31, 2015 Supplemental Table F-A - Continued Mixed Mode Joint Frequency Distribution Table Summaries 35 Foot Elevation Data Summary Table of Percent by Speed and C 1a1111 Class A B c D E F Q Speed
.45 .ooo .ooo .000 .001 .003 .007 .015 1.05 .001 .000 .002 .004 .032 .048 .091 2.0S .028 .010 .010 .104 .421 .544 .658 3.05 .198 .055 .062 .486 t .333 1.014 .551 4.05 .445 .098 .104 .786 1. 701 .81.B .230 5.05 .424 .093 . 118 .830 t.701 .582 .129 6.0S .429 .120 . 146 .999 1. 918 .404 .063 8.05 .937 .259 .275 1.985 2.893 .403 .023 I0.05 .405 .098 .103 .845 1.270 .078 .007 13.05 . 147 .039 .054 .348 .401 .019 .001 18.00 .014 .004 .012 .043 .049 .001 .000 99.00 .000 .000 .000 .ooo .000 .000 .000 Page 246 of 267
Revision 5 Aug 31, 2015 Supplemental Table F-B Ground Level Joint Frequency Distribution Table Summaries Summary Table of Percent by Direction and Class Class N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW Total A .573 .881 .500 .366 .343 .440 .582 .503 .397 .324 '.509 .640 .941 .989 .950 .666 9.605 B .175 . 211 . 131 .089 .087 .086 . 113 .157 .131 .058 .139 . 176 .219 .171 .215 .206 2.363 c .213 .281 .165 . 113 .103
- t20 .152
- t7f .115 .089 .168 .207 .235 .182 .250 .209 2. 771 D 1.488 1.629 1.012 .801 .756 .681 .797 .971 t.038 .783 1.610 I .454 1.820 1.478 1.967 1.433 19.716 E 2.801 2.521 1.683 I .537 1.317 1.065 1.255 2. 107 2.835 2.531 3.9tf 3.300 3.293 2.756 3.239 1.907 38.058 F t.155 .710 .463 .384 .389 .313 .509 .692 1 .908 t.815 I .987 1.547 1.385 1 .331 t.143 .707 16.439 G .472 .253 .176 .132 .127 .192 .258 .353 1.603 f .642 1.448 .987 f .028 1.192 .770 .416 1 t.049 Total 6.877 6.486 4.130 3.421 3.122 2.898 3.667 4.954 8.025 7.241 9.772 8.311 8.921 8.097 8.534 5.543 100.000 Summary Table of Percent by Direction and Speed siieed N NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW Total
.45 .048 .065 .058 .009 .022 .012 .018 .037 .027 .042 .027 .052 .042 .(\43 .075 .054 .631 t.05 .206* .168 .156 .118 .121 . tta .135 .134 .216 .238 .27t . 197 .233 .2~4 .350 .234 3.158 2.05 .903 .674 .518 .467 .458 .658 .636 .534 1.254 I .834 1.675 1.396 I .326 1.837 2.043 .990 17. 102 3.05 I .089 1 .03 I .861 .743 .683 .806 1.309 I .075 2.628 I .993 1.781 1.670 I .944 2.22U 2.304 '.333 23.474 4.05 1 .054 .t. 309 .883 .554 .456 .478 .846 1.269 2. 134 1.0BB 1.655 I .639 t. 715 I .534 1.873 1.234 19.724 !i.05 .931 1.129 .586 .345 .338 .230 .369 .797 1.005 .755 1.450 1.328 t.404 1 .079 I .079 .836 13.66 t 6.05 .906 .841 .409 .273 .279 .231 . 161 .477 .418 .573 1.176 .894 1.007 .550 .537 .468 9.201 8.05 1. I 19 .779 .354 .*415 .393 .283 .158 .482 .265 .575 1 .338 .845 .936 .489 .253 .338 9.022 10.05 .411 .312 .213 .366 .246 .127 .032 .123 .063 .129 .318 .208 .219 .062 .019 .046 2.896 13.05 .177 . 154 .087 .118 . 102 .050 .003 .026 .015 .014 .075 .078 .085 .014 .t.00 .009 1.008 18.00 .032 .023 .004 .013 .024 .003 .ooo .000 .ooo .001 .005 .003 .012 ;003 .~f) .000 .122 99.00 .000 .ooo .000 .ooo .ooo .000 .ooo .ooo .000 .000 .ooo .ooo .000 .000 ,<>Ofi .ooo .ooo Total 6.877 6.486 4.130 3.421 3. t22 2.898 3.667 ... 954 8.025 7.2 .. 1 9.772 8.311 8.921 8.097 8.534 5.543 100.000 NOTE: Wind directions in tables a~e presented in *wind from* and not *wind to* direction.
Page 247 of 267
Revision 5 Aug 31, 2015 Supplemental Table F Continued Ground Level Joint Frequency Distribution Table Summaries Summary Table of .Percent by Speed and CJaaa Class A B c D E F G Speed
.45 .006 .004 .005 .040 .t72 .t54 .249 f.05 .036 .Ot3 .024 .12t .797 .823 1.344 2.05 .464 . 14' .194 1.59t 4.805 4.405 5.502 3.05 1.606 .433 .507 3.810 8.847 5.409 2.862 4.05 2.520 .563 .613 4.211 8.107 2.995 .7t5 5.05 t.909 .419 .509 3.384 5.795 '. 394 .251 6.05 t. 2 tt .306 .368 2.527 4.023 .681 .085 8.05 f. 28 t .342 .381 2.766 3.745 .478 .030 10.05 .410 .099 .104 .877 1.317 .078 .010 13.05 .147 .039 .054 .348 .400 .019 .001 te.oo .014 .004 .012 .042 .049 .oot .ooo 99.00 .ooo .000 .000 .000 .ooo .ooo .ooo Page 248 of 267
Revision 5 Aug 31, 2015 i
1 UNllESJRICllD AREA llOUNDARY
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Revision 5 Aug 31, 2015 Meteorological Tower Shiloh Blvd.
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- J~ J Release Point OFFSITE DOSE CALCULATION MANUAL ZION STATION 200' 50'0' 200' 400' wsa FIGURE F-2 GRAPHIC SCALE 1*. 200*-o*
- Restricted Area Boundary RESTRl.CTED AREA BOUNDARY
- Meteorological Tower M5593.00I 9-92 Page 250 of 267
Revision 5 Aug 31, 2015 Appendix 0 ODCM BASES and REFERENCE DOCUMENT Page 251 of 267
Revision 5 Aug 31, 2015 Appendix 0 ODCM BASES and REFERENCE DOCUMENT This document provides supplementary information on the bases of material in Chapters 1 through 6 and Appendices A through C. 0.1 BASES OF CHAPTER 1, INTRODUCTION 0.1.1 Offsite Radiation Doses Due to Nuclear Power Plants It is estimated that the average radiation dose received by an individual in the United States is about 625 mrem/yr and that nuclear power stations account for less than two parts in a thousand of this radiation. These figures are based on data in Table 8.3 of NCRP 160, (Reference 80). The table includes the following data: Average Individual Source Dose (mrem/yr) Ubiquitous Background 311 Medical 300 Consumer 13 Industrial, security, medical, educational and research 0.3 Occupational 0.5 Total 624.8 The radiological effects of nuclear power station operation on the environment are characterized as "usually so small that they are masked by normal fluctuations in natural background sources and by the normal uncertainties of the measurement process." The text of Chapter 1 also states that "assessing compliance with regulatory limits requires calculations because some of the limits involve quantities that cannot be directly measured ... "Limits that cannot be feasibly monitored by direct measurement include doses to internal organs and doses attributable to particular pathways (see Appendix A). 0.1.2 Historical and Concurrent Meteorology The use of historical average atmospheric conditions for assessment of radiation doses due to airborne effluents is stipulated in the Bases Section 12.4 and 12.6 of the RETS. 0.2 BASES OF CHAPTER 2, REGULATIONS AND GUIDELINES See the documents cited in the text. 0.3 BASES OF CHAPTER 3, PATHWAYS General information on offsite exposure pathways may be found in several texts and monographs (see References 16, 18, 20, 22, 25, 28, 29 and 31 ). Page 252 of 267
Revision 5 Aug 31, 2015 0.3.1 Airborne Releases (Section 3.1) Zion addresses radiation dose for the airborne pathways considered in NUREG 0133 (Reference 14). The airborne pathways found in NUREG 0133 are: /
- Exposure to a cloud of noble gas.
- Exposure to standing on a contaminated ground plane.
- Inhalation of tritium and/or particulates.
- Ingestion of contaminated vegetation.
- Ingestion of contaminated cow and/or goat milk.
- Ingestion of contaminated cow meat.
The noble gas exposures are assessed at the site boundary. The ground plane, inhalation and ingestion exposures are determined at the location in the unrestricted area where the combination of pathways, age group and airborne deposition produce the highest potential dose to a member of the public. The ground plane and inhalation pathways are considered present at every location in the unrestricted area. Ingestion pathways are considered present at the locations determined by the land use census. Soil uptake is not considered by the NU REG 0133 methodology but is addressed by Regulatory Guide 1.109 (Reference 6). Ingestion exposure through the mechanism of soil uptake has been shown to be minor as compared to direct deposition onto foliage. This assumption is based upon an analysis of three nuclides: 1-131, Cs-134 and Cs-137. In a study of nuclear power station radiation exposures in the upper Mississippi River basin, these nuclides were found to contribute the major portion of the dose due to exposure to airborne radioactivity deposited on soil (see page IX-12 of Reference 20). The relative importance of uptake from soil was assessed by use of Equation C-5 of Regulatory Guide 1.109. This equation calculates radioactivity concentration in vegetation. The first term inside the curly brackets of the equation represents the contribution from radioactivity directly deposited on plant foliage. The second term represents the contribution from radioactivity initially deposited on the ground and then taken up through the root system of the vegetation. For each of the three nuclides, the ratio of the uptake term to the direct deposition term was evaluated for two pathways; the grass-cow-milk pathway and the pathway of direct ingestion by man of produce and leafy vegetables. The parameter values used and the results are in Table 0-1 of this document. For the six cases, the soil uptake term ranged from about 0.01 % to about 10% of the direct deposition term (see the column labeled "Uptake+ Direct Dep" in Table 0-1 ). 0.3.2 Liquid Releases (Section 3.2) Zion addresses radiation dose for the waterborne pathways considered in NU REG 0133. The waterborne pathways found in NUREG 0133 are:
- Ingestion of contaminated potable water.
- Ingestion of fish taken from contaminated water.
- Ingestion of invertebrates taken from contaminated water.
These dose pathways are considered unless demonstrated not be present. Exposure can also occur through recreation (shoreline actiyities, swimming and boating) and irrigation pathways (irrigation of directly ingested vegetation and food crops for animal consumption), but these are considered to be minor when compared to direct ingestion. The liquid pathways were evaluated based on surveys of surface water use and on liquid pathway dose calculations. Table 0-2 of this document summarizes principal results of the surface water use surveys. On the basis of these surveys, it was decided to ignore the following pathways: Page 253 of 267
Revision 5 Aug 31, 2015 Ingestion of vegetation contaminated because of irrigation with water containing radioactivity from plant liquid discharges. Ingestion of radioactivity that entered an animal food product (milk or meat) because the animal drank water contaminated by radioactive liquid effluents from the plant or because the animal consumed feed contaminated by irrigation with such water. Calculations were performed to estimate annual doses from the following liquid pathways:
- Consumption of drinking water.
- Consumption of fish.
- Shoreline activities (with exposure to shoreline sediments).
- Swimming and boating.
0.3.3 Radiation from Contained Sources (Section 3.3) Annual radiation doses due to contained sources of radioactivity at Zion are addressed in EH&S TSDs: 13-007, "Evaluation of Waste Classification A, Band C Storage and Staging Dose Rates"; 13-008, "Evaluation of ISFSI and Associated Processes Dose Rates" and 13-009, "Member of the Public Dose from All Onsite Sources." 0.4 BASES OF CHAPTER 4, INTRODUCTION TO METHODOLOGY Most of the material in this chapter is based on Appendix A. Additional information on bases is provided below. 0.4.1 Introduction of Time Factors The release rate of radioactive materials is the discharge of radioactive materials in liquid or gaseous effluents per unit time. The second is used as the practical reporting time unit for establishing release rates to show compliance with instantaneous limitations for noble gases. The hour is used as the practical reporting time unit is established average release rates to show conformance with the requirements of 10CFR50 for particulates released in gaseous effluents and for liquids effluents. 0.4.2 Release Point Classifications (Section 4.1.4) For additional information, see Meteorology and Atomic Energy 1968 (Reference 18), Section 3-3.5.2, and Regulatory Guide 1.111 (Reference 7), Section B.2. 0.4.3 Airborne Releases (Section 4.2) The energies and intensities of radiations emitted from them are listed in standard compendia (e.g., see Reference 70). Gamma Radiation Mean Free Path The mean free path X of gamma radiation is calculated using the following equations: x =1/µ (0-1)
µ =(µ/p)p (0-2)
Page 254 of 267
Revision 5 Aug 31, 2015 X Mean Free Path [cm] The average distance traveled by a photon before interacting with matter.
µ Attenuation Coefficient of Air Probability of photon absorption or scattering per unit distance traveled in air.
p Density of Air [glee] The results for photon mean free path (Section 4.2.1) are based on data in Reference 71. For a 4-MeV photon, the calculation is as follows: 2
µ/p = 0.0308 cm /g (per Table 5.2 of Reference 71) p = 0.001293 glee (per Table 1.3 of Reference 71)
µ = (0.0308 cm 2/g) (0.001293 glee)= 3.982E-5 cm-1 1
X = (1/3.982E-5 cm- )(1 ft/30.48 cm)= 823.9 ft Range of Beta Radiation in Air The results for beta radiation range (Section 4.2.2} are based on equations in Reference 38. The range of beta radiation with a maximum energy greater than 2.5 MeV is given by the following equation (Reference 38, Page 100): R = (530)(Emax)
- 106 (0-3)
R Range Emax Maximum Beta Energy [MeV] For Emax = 4 MeV, R = (530)(4) -106 = 2.01E3 mg/cm 2 For an air density of 1 .293 mg/cc, the range is 2 [(2.01 E3 mg/cm )/(1.293 mg/cc)] (1 ft/30.48 cm) = 51.0 ft For 0.01 ~ Emax ~ 2.5 MeV, the range of beta radiation is given by the following equation (Reference 38, Page 99): R = (412)(Emax)1.265-(0.0954)(1n Emax) (0- 4) where R and Emax have the same definitions as for Equation 0-3. For example, for Emax = 0.1 MeV, R = (412 ) (0. 1)1.2ss-10.09s411nco.1)= 13.5 mg/cm2 For an air density of 1.293 mg/cc, the range is [(13.5 mg/cm 2)/(1.293 mg/cc)] (1 ft/30.48 cm) = 0.34 ft Page 255 of 267
Revision 5 Aug 31, 2015 0.4.4 Radionuclide Types Considered For Airborne Effluent Exposure Pathways (Table 4-1) The radionuclide types considered are the same as those recommended for concern in Regulatory Guide 1.109 except that carbon-14 is omitted. The reasons for this are discussed in the next section. 0.4.5 Reasons for Not Calculating Doses Due to Carbon-14 Carbon-14 is not considered because the RETS does not require it. Zion Station is required to consider only the following non-noble gas radionuclides: tritium and all radionuclides in particulate form with half-lives greater than 8 days. Although carbon-14 has a half-life of 5730 years, it does not fall in the last category (in particulate form with half-life greater than 8 days) because it is emitted as a gas, mainly C0 2 (see Reference 29, Page 167). Moreover, carbon-14 was not found to be a significant contributor to offsite radiation dose in a study of the potential radiological implications of nuclear facilities in the upper Mississippi River basin (see Reference 20, Page IX-8, Table IX-2). 0.5 BASES OF CHAPTER 5, MEASUREMENT See the documents cited in the text. 0.6 BASES OF CHAPTER 6, IMPLEMENTATION OF THE OFFSITE DOSE ASSESSMENT PROGRAM Chapter 6 is based on ZionSolutions' organizational structure and departmental responsibilities. 0.7 BASES OF AIRBORNE EFFLUENT CALCULATIONS (SECTION A.1 AND APPENDIX B) The methodology used to calculate doses and dose rates due to releases of radioactivity in airborne effluents is discussed below. The calculations use equations presented in Section A.1 of Appendix A. The equations involve meteorological transport and dose factors that are either obtained from the literature or calculated as described in Appendix B. For the most part, the methodology of this manual for airborne effluent dose calculations is identical to that of Regulatory Guides 1.109 (Reference 6) and 1.111 (Reference 7). In the discussion below, special attention will be given to the few differences. 0.7.1 Release Point Classifications (Section A.1.1 of Appendix A) Regulatory Guide 1.109 uses two classifications for airborne releases (see Reference 6, Regulatory Position C.2):
- Releases from free standing stacks more than 80 meters high.
- All other releases.
This manual uses three classifications for airborne releases: stack, ground and vent level. The classifications used here are based on Regulatory Positions C.2.a and C.2.b of Regulatory Guide 1.111. Page 256 of 267
Revision 5 Aug 31, 2015 0.7.2 Meteorological Data (Section B.1.1 of Appendix B) The information in Section B.1.1 of Appendix B is based on Sargent & Lundy reviews and analyses of meteorological data from Zion. The procedure for treating calms is based on guidance in Regulatory Guide 1.111, Regulatory Position C.4. 0.7.3 Joint Frequency Distribution (Section B.1.2 of Appendix B) The information in Section B.1.2 of Appendix B is based on discussions with Sargent & Lundy. The procedure for determining the JFD for a vent release is based on Regulatory Position C.2.b of Regulatory Guide 1.111. An historical average JFD was calculated at Sargent & Lundy by a computer program that later evolved into the computer program METWRSUM (Reference 75). For further information on these calculations, see Reference 76. Wind speed and direction may change with height. In accordance with Regulatory Position C.2.b of Regulatory Guide 1.111, JFD calculations for elevated releases were made using wind parameters representative of conditions at the actual release height, and calculations for ground level releases were made using wind parameters corresponding to a height of approximately 10 meters. As noted in Reference 76, in some cases interpolation of wind speed data measured at different heights was used to obtain data characteristic of the height of interest. 0.7.4 Average Wind Speed (Section B.1.3 of Appendix B) The equations for obtaining average wind speed are based on the standard method of determining the average value of a quantity for which the frequency distribution is known: Average wind speeds Zionb were computed using Sargent & Lundy computer program AZAP (Reference 77). Regulatory Position C.2.a of Regulatory Guide 1.109 and C.1.c of Regulatory Guide 1.111 specify that a wind speed class be represented by the wind speed of its midpoint (i.e., average of its upper and lower limits). In the calculations this is done for each wind speed class except the highest. The highest class contains all wind speeds greater than a specified value and so has an undefined upper limit. This class is represented by the lower limit of its wind speed range in all calculations for this manual (calculations of average wind speed, x!Q, gamma dose factors, and total body dose factors). 0.7.5 Gaussian Plume Models (Section B.2 of Appendix B) For discussion of the Gaussian plume diffusion model and its applications to dose assessment, see References 18 (Sections 2-7.2, 3-3, 4-6.2, 7-4, and 7-5), 24, 31 (Section 2.1 ), and 22 (Chapter 3). Equation 8-9 of Appendix 8 is identical to Equation 3.115 on Page 99 of Reference 18. Equation 8-10 of Appendix Bis derived from Equation B-9 of Appendix 8 as follows: A location at ground level (z =0) is assumed. Equation 8-9 of Appendix 8 becomes: x,(x,y,O) =[Q/(n cry O"z u)] exp[-(y2/2cr2y) - (h//2cr2z)] (0-5) This expression for x(x,y,O} is integrated in the crosswind direction from
=
--y -oo to +oo. This yields the following result (see Equation 3.143 of Reference 18):
"[2112Q/(1t1120"zU)]exp(-h2e2/2cr2z)
Page 257 of 267
Revision 5 Aug 31, 2015 The above expression is divided by the width of a sector at downwind distance x, 27tx/16. The result is: [16/(2 112n 312)][Q/(O"z u x)]exp(-h 2 ef2cr2z) that is equal to [2.032Q/(crz u x)]exp(-h 2ef2cr2z) The result above is multiplied by a fraction f representing the fraction of time that the wind blows into the sector of interest. This yields that is identical to the expression in Equation B-10 of Appendix Band also to Equation 3.144 of Reference 18. 0.7.6 Relative Concentration Factor xtQ (Section B.3 of Appendix B) 0.7.6.1 Stack Release Equation B-13 of Appendix Bis the formula for calculating the relative concentration factor (x/0)5 due to a stack release. Equation B-13 of Appendix Bis obtained from the formula for sector-averaged concentration, Equation B-10 of Appendix B, and is of the same form as Equation 3 of Regulatory Guide 1.111. In applying Equation B-13 of Appendix B, the vertical plume spread is calculated in the way specified in the regulatory guide. The effective release height is calculated with Equation B-14 of Appendix B. The formulas used are in accordance with those in Regulatory Guide 1.111. However, the following should be noted: Plume heights are limited to a maximum of 100 meters. This is done to allow use of the plume depletion and relative deposition data in Regulatory Guide 1.111. These data are not provided for release heights above 100 meters. The limitation to 100 meters represents a conservative approximation for cases in which the release height and the plume rise formulas would lead to higher plumes. Due to the general flatness of the terrain in the vicinity of Zion, all terrain correction parameters were taken as zero. Plume rise due to buoyancy was ignored because typical nuclear power plant plumes are not significantly warmer than room temperature. This neglect of buoyancy (which can be significant for plumes from fossil plants) is in accord with the guidelines of Regulatory Guide 1 .111. The regulatory guide states that plume rise is calculated in accordance with Reference 78, which neglects rise due to buoyancy (see last sentence on Page 5 of Reference 78).
~ - --- -- -- - ------ - -- -
Page 258 of 267
Revision 5 Aug 31, 2015 0.7.6.2 Ground Level Release Equation B-25 of Appendix B is the formula for calculating the relative concentration factor (x/0)9 due to a ground level release. Equation B-25 of Appendix Bis obtained from the formula for sector-averaged concentration, Equation B-10 of Appendix B, and is of the same form as Equation 3 of Regulatory Guide 1.111. In applying Equation B-25 of Appendix B, the vertical dispersion coefficient is calculated using Equations B-26, B-21*and B-28 of Appendix B, which are based on the prescription in Regulatory Position C.2.c. 0.7.6.3 Vent Release Equation B-29 of Appendix B may be used for calculating the relative concentration factor (x/O)v due to a vent release. The relative concentration factor is obtained as a mixture of stack and ground level factors in accordance with the guidelines in Regulatory Position C.2.b of Regulatory Guide 1.111. 0.7.6.4 Removal Mechanisms Regulatory Position C.3 of Regulatory Guide 1.111 discusses three removal mechanisms that reduce airborne radioactivity concentration: radioactive decay, dry deposition and wet deposition. In the dose calculations involving x/O (see Appendix A), radioactive decay is taken into account by adjusting the measured release rate of each radionuclide for radiodecay in transit from the release point to the dose point. However, wet and dry deposition are not considered. This is a conservative approximation made to simplify the calculations. If these deposition mechanisms were considered, the X/Q values for noble gases would be different from those for particulate. 0.7.6.5 Gamma-x/Q (Section 8.3.5) The noble gas dose factors used in Equations A-1, A-3, A-4, A-5 of Appendix A are taken from Regulatory Guide 1.109, Table B-1. These values are based upon assumption of immersion in a semi-infinite cloud. For ground level and mixed mode releases this tends to overestimate the gamma air dose arising from a plume that is actually finite in nature. For elevated releases, the Regulatory Guide 1.109 noble gas dose factors will underestimate exposure as they consider only immersion and not that portion of exposure arising from sky shine. At distances close in to the point of elevated release, the ground level concentration as predicted by x/Q will be essentially zero. In such a case, the sky shine component of the exposure becomes significant and must be considered. The gamma-x/Q provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. Regulatory Guide 1.109, Section C.2 and Appendix B provide the methodology for calculating finite cloud gamma air dose factors from which the gamma-x/Q values can be derived. The gamma-x/Q is defined such that for a given finite cloud the semi-infinite cloud methodology will yield the same gamma air dose as the finite cloud methodology. Three gamma-x/Q values are defined: for stack, vent and ground level releases, respedively. The gamma-x/Q values are calculg_te_d b~_Eguation§i B-30, 8~31 ~me! B-32 of Appendix B and makes use of the finite cloud gamma air dose factors described in Section B-5 of Appendix s: -- -- - - - - - - These equations also utilize a noble gas nuclide fraction. These fractions can be based upon historical data or a calculated noble gas source term. Page 259 of 267
Revision 5 Aug 31, 2015 0.7.7 Relative Deposition Factor D/Q (Section B.4 of Appendix B) Equations B-34, B-35, and B-36 of Appendix B are used to calculate values of the relative deposition factor 2 D/Q [1/m ]. These equations use data on deposition rate Dr [1/m] provided in Figures 6 through 9 of Regulatory Guide 1.111. Values of D/Q are obtained from Dr in accordance with the prescription in paragraph 5 of Regulatory Position C.3.b. Equation B-37 of Appendix B applies to a vent release and provides a value that is a mixture of stack and ground level factors in accordance with the guidelines in Regulatory Position C.2.b of Regulatory Guide 1.111. 0.7.8 Gamma Air Dose (Section A.1.2.1 of Appendix A and Section B.5 of Appendix B) 0.7.8.1 Dose (Equation A-1 of Appendix A) Gamma air dose is calculated by Equation A-1 of Appendix A. This equation makes use of a term referred to as gamma-x/Q (gamma-chi-over-q) which is explained in Section 4.2.1.1. It is derived from the methodology of NUREG 0133, Section 5.3.1 .. NU REG 0133 deals only with two classes of noble gas releases; those from free-standing stacks more than 80 meters high and all other noble gas releases. Equation A-1 of Appendix A contains terms representing the appropriate release point classifications discussed in Section 4.1 .4. The use of three release point classifications is based on Regulatory Guide 1.111, Regulatory Position C.2. The dose factors M1 used in Equation A-1 of Appendix A are identical to the gamma air dose factors DFB 1 specified in Table B-1 of Regulatory Guide 1.109. 0.7.8.2 Dose Factors (Section B.5 of Appendix B) Calculation of gamma-x/O involves the use of finite plume gamma air dose factors, each of which represents dose rate at a specified point per unit of radioactivity release rate. The dose factors are calculated by Equations B-40 through B-42 of Appendix B. Equation B-40 of Appendix B is used to calculate the finite plume gamma air dose factors for a stack release. The formula is based on Equations 6 and B-1 of Regulatory Guide 1.109. Except for notation, Equation B-40 of Appendix B and the regulatory prescription are identical. The finite plume gamma air dose factors for a ground level release are obtained by Equation B-40 of Appendix B using the ground level joint frequency distribution data and assuming an effective release height of zero. The use of a finite plume model differs from NUREG 0133 in that ground level releases are based on a semi-infinite cloud model (see Equation 7 of Regulatory Position C.2.b). The approach used here is more realistic than that in the regulatory guide. " Equation B-42 of Appendix B is used to calculate the gamma air dose factors for a vent release. The dose factors are obtained as a mixture of stack and ground level dose factors in accordance with the guidelines in Regulatory Position C.2.b of Regulatory Guide 1.111. 0.7.8.3 Use of Unrestricted Area Boundary Values for Gamma Air Dose Factors To assess compliance with RETS limits on gamma air dose, maximum offsite values of gamma air dose should be determined. Therefore, the gamma-x/Q values should be determined for the offsite locations where they are maximum. However, the values provided in Table F-5b of Appendix Fare for the unrestricted area boundary. They are judged to be very good approximations to the maximum offsite values. Page 260 of 267
Revision 5 Aug 31, 2015 This judgment is based on published values for finite cloud gamma air dose factors used to calculate gamma-x/Q (see Reference 79). Reference 79 provides values of the gamma air factor as follows: For 13 of the 15 noble gas radionuclides included in the ODCM. For each of the seven atmospheric stability classes considered in this manual (A through G). For two release heights (0 and 100 meters). As a function of distance from the release point. (Data is provided for six downwind distances over the range from 400 to 16,090 meters.) Examination of the dose factor in Reference 79 for the sector-averaged meandering plume model reveals the following: For a ground level release, the dose factor always decreases as distance from the release point increases. (The plume broadens as it moves away from the release point.) For an elevated release, the dose factor decreases as distance from the release point increases with only a few exceptions (five exceptions among the 546 dose factors that are provided). The exceptions involve only weak gamma emitters (Xe-131m, Xe-133m, and Xe-133) in combination with certain stability classes. (The exceptions are due to portions of an elevated plume moving closer to th.e ground as the plume moves away from the release point. This increases dose rate at ground level.) The gamma air dose factors used to calculate gamma-x/Q in Appendix F are based on historical average atmospheric conditions (see Section 4.1.5). Therefore, each gamma air dose factor involves an average over all of the meteorological stability classes, nearly all of which have dose factors that decrease as distance from the release point increases. Furthermore, the gamma air dose factors in the ODCM for ground level releases or for mixed mode releases include a large ground level component. The ground level dose factors will always decrease as distance increases, and the mixed mode factors are likely to decrease with distance because of the effect of their ground level component. Thus, it is judged that a gamma-x/Q value calculated at the unrestricted area boundary in each sector is a very good approximation to the highest offsite value for that sector. 0.7.9 Beta Air Dose (Section A.1.2.2 of Appendix A and Section B.7 of Appendix B) Beta air dose is calculated by Equation A-2 of Appendix A. This equation is explained in Section 4.2.2. It is based on Section 5.3.1 of NUREG 0133. Like Equation A-1 of Appendix A for gamma air dose, Equation A-2 of Appendix A contains a term representing each of the three release point classifications discussed in Section 4.1.4. The use of three release point classifications is based on Regulatory Guide 1.111, Regulatory Position C.2. The dose factors Ni used in Equation A-2 of Appendix A are identical to the beta air dose factors DFBi specified in Table B-1 of Regulatory Guide 1.109. 0.7.10 Total Body Dose (Section A.1.2.3 of Appendix A and Section B.6 of Appendix B) Total body dose is calculated by Equation A-3 of Appendix A. This equation is explained in Section 4.2.3. It is based on Section 5.3.1 of NUREG 0133. Like Equation A-1 of Appendix A for gamma air dose, Equation A-3 of Appendix A contains a term representing each of the three release point classifications discussed in Section 4.1.4. The use of three release point classifications is based on Regulatory Guide 1.111, Regulatory Position C.2. The dose factors Ki used in Equation A-3 of Appendix A are identical to the beta air dose factors DFBi specified in Table B-1 of Regulatory Guide 1.109. Page 261 of 267
Revision 5 Aug 31, 2015 0.7.11 Skin Dose (Section A.1.2.4 of Appendix A and Section 8.7 of Appendix B) Skin dose is calculated by Equation A-4 of Appendix A. This equation is explained in Section 4.2.4. It is based on Section 5.2.1 of NUREG 0133. Like Equation A-1 of Appendix A for gamma air dose, Equation A-4 of Appendix A contains a term representing each of the three release point cl~ssifications discussed in Section 4.1.4. The use of three release point classifications is based on Regulatory Guide 1.111, Regulatory Position C.2. The dose factors Li and Mi used in Equation A-4 of Appendix A are identical to the gamma and beta skin dose factors DFSi specified in Table B-1 of Regulatory Guide 1.109. The gamma contribution to skin dose is calculated with gamma-x/Q in the same manner as that of Equation A-1 of Appendix A to calculate gamma air dose. This approach differs from that of the regulatory guide in that a finite cloud model is used in accounting for the portion of the dose contribution to the skin due to gamma emissions. This is more realistic than the semi-infinite cloud model used in the regulatory guide. 0.7.12 Total Body Dose Rate (Section A.1.3.1 of Appendix A) Total body dose rate is calculated by Equation A-5 of Appendix A. This equation is explained in Section 4.2.3. 0.7.13 Skin Dose Rate (Section A.1.3.2 of Appendix A) Skin dose rate is calculated by Equation A-6 of Appendix A. This equation is explained in Section 4.2.4. 0.7.14 Dose Due to Non-Noble Gas Radionuclides (Section A.1.4 of Appendix A) The term dose in the title of Section A.1.4 of Appendix A includes both dose and dose commitment (see Section 4.1.1 ). This is based on its usage in the standard Technical Specifications (see Specification 3: 11.2.3 of References 2 and 3). The dose due to non-noble gas radionuclides is calculated by Equation A-7 of Appendix A. It is based on Section 5.3.1 of NUREG 0133. 0.7.15 Ground Deposition Dose (Section A.1.4.1 of Appendix A and Section B.8 of Appendix B) The dose due to deposited radionuclides is calculated by Equations A-7and A-8 of Appendix A. These equations are explained in Section 4.2.5. The methodology is based upon Sections 5.3.1 and 5.3.1.2 of NUREG 0133. The ground plane dose conversion factors DFGi used in Equation A-8 of Appendix A are identical to the dose factors provided in Table E-6 of R.G. 1.109. Equation A-8 of Appendix A uses a value of 0.7 for the shielding factor which accounts for shielding due to occupancy of structures. This value is specified in Section 1 of Appendix B, Section II; of Regulatory Guide 1.109 and Section 5.3.1.2 of NU REG 0133. Page 262 of 267
Revision 5 Aug 31, 2015 0.7.16 Inhalation Dose (Section A.1.4.2 of Appendix A and Section 8.9 of Appendix 8) The dose commitment due to inhalation is calculated by Equations A-7 and A-9 of Appendix A. This equation is explained in Section 4.2.6. It is based on Sections 5.3.1 and 5.3.1.1 of NUREG 0133. The dose factors, DFAiia* used in Equation A-9 of Appendix A for 10CFR50 Appendix I compliance are identical to the inhalation dose factors provided in Tables E-7 through E-10 of Regulatory Guide 1.109. 0.7.17 Food Pathways Doses (Section A.1.4.3 of Appendix A and Section 8.10 of Appendix B) The dose commitment due to food pathways is calculated by Equations A-7 and A-10 through A-15 of Appendix A. These equations are discussed in Section 4.2. 7. They are based the methodology found in Sections 5.3.1.3 through 5.3.1.5 of NUREG 0133. The dose calculations for particulate account for doses resulting from dry deposition of radioactive materials onto the ground and foliage. Wet deposition is not considered in evaluating long-term-average environmental doses at Zion for the reason put forth in Regulatory Guide 1.111 (see Page 1.111-12):
- 0. 7 .18 Inhalation Dose Rate (Section A.1.5 of Appendix A)
Inhalation dose commitment rate is calculated by Equation A-16 of Appendix A. This equation is explained in Section 4.2.6. 0.8 BASES OF LIQUID EFFLUENT CALCULATIONS (SECTION A.2 and Appendix B; SECTION II) This section presents bases of the methodology used to calculate doses and radioactivity concentrations due to releases of radioactivity in liquid effluents. The calculations use equations presented in Section A.2 of Appendix A. The equations involve transport and dose factors that are determined as described in Appendix B; Section II. 0.8.1 Dose (Secti~n A.2.1 of Appendix A and Section 8.15 of Appendix 8) The dose due to radioactive materials in liquid effluents is calculated by Equations A-17 through A-20 of Appendix A. The dose is based upon the sum of contributions from drinking water (calculated by Equations A-17, A-18 and A-19 of-Appendix A) and fish (calculated by Equations A-17, A-18 and A-20 of Appendix A). The equations are explained in Section 4.3 and Section B.15 of Appendix B. They are based on Sections 4.3 and 4.3.1 of NUREG 0133. For Zion the flow and dilution parameters in Equations A-18 and A-19 of Appendix A are determined using the Lake Michigan model. The assumptions of this model are stated in Section B.15.3.1.2 of Appendix B. The assumptions used to obtain the additional dilution parameter for water consumption (Z =10) are based on judgment, and the assumptions used to obtain the dilution flow for fish consumption (Dw =6) are based on the cited observational data. 0.8.2 Concentration Due to Tank Discharges (Section A.2.3 of Appendix A) The concentration of radioactivity in tank discharges is calculated by Equation A-22 of Appendix A. The basis of this equation is explained in Section B.16 of Appendix B. Page 263 of 267
Revision 5 Aug 31, 2015 0.9 BASES OF CALCULATIONS OF DOSE DUE TO CONTAINED SOURCES (SECTION A.3) Annual radiation doses due to contained sources of radioactivity at Zion are addressed in EH&S TSDs: 13-007, "Evaluation of Waste Classification A, Band C Storage and Staging Dose Rates"; 13-008, "Evaluation of ISFSI and Associated Processes Dose Rates" and 13-009; "Member of the Public Dose from All Onsite Sources." 0.10 BASES OF APPENDIX C, GENERIC DATA The bases of the data in Appendix C are presented in Appendix C. Page 264 of 267
Revision 5 Aug 31, 2015 Table 0-1 Comparison of Contributions of Direct Deposition and Soil Uptake Terms To Radioactivity Concentration in Vegetation For the Grass-Cow-Milk Pathway: Ai Aw AEI te [ (hrs- 1 ) (hrs-1 ) (hrs-1 ) (hrs) 1-131 1.0 3.59E-03 2.1 E-03 5.69E-03 720 Cs-134 0.2 3.83E-05 2.1E-03 2.14E-03 720 Cs-137 0.2 2.62E-06 2.1 E-03 2.10E-03 720 Yv tb p Uptake+ (kg/m 2 ) ~jy Jh[fil (kg/m 2 ) Direct Dep 1-131 0.7 2.0E-02 1.31 E+05 240 9.40E-05 Cs-134 0.7 1.0E-02 1.31E+05 240 1.03E-02 Cs-137 0.7 1.0E-02 1.31E+05 240 4.36E-02 For Produce or Leafy Vegetables Ingested by Man: Ai Aw AEI te
.I (hrs-1 ) (hrs-1 ) (hrs-1 ) (hrs) 1-131 1.0 3.59E-03 2.1 E-03 5.69E-03 1440 Cs-134 0.2 3.83E-05 2.1E-03 2.14E-03 1440 Cs-137 0.2 2.62E-06 2.1E-03 2.10E-03 1440 Yv tb p Uptake+
(kg/m 2
) ~jy Jh[fil (kg/m 2 ) Direct Dep 1-131 2 2.0E-02 1.31 E+05 240 2.64E-04 Cs-134 2 1.0E-02 1.31 E+05 240 2.42E-02 Cs-137 2 1.0E-02 1.31 E+05 240 1.02E-01 Note: The parameter definitions are the same as in Regulatory Guide 1.109.
Page 265 of 267
Revision 5 Aug 31, 2015 Table 0-2 Principal Surface Water Uses Nearest Public Potable Station Body of Water Recreation a Irrigation Receiving Water Intake Zion 8 Lake Yes Not Lake County Citedb Public Michigan Water District (1.4 mile north of site and 3000 ft out in Lake) Note: This table summarizes selected information from the reports referenced in the footnotes below. For more complete information, see the referenced reports. a Per Zion ER, Section 2.3.2.2. Existence of irrigation not mentioned in Zion ER. Page 266 of 267
Revision 5 Aug 31, 2015 Table 0-3 Predicted PWR Annual Doses for Selected Liquid Effluent Pathways Annual Whole Body Dose (mrem/yr per reactor) Pathway/Lim it Zion a Eating Fish 4.5E-2 Drinking Water 1.7E-3 Shoreline Activities 1.4E-4 Swimming and Boating 1.1 E-5 10 CFR 50 Objective 3 Annual Thyroid Dose (mrem/yr per reactor) Pathway/Lim it Zion a Eating Fish 3.6E-2 Drinking Water 1.7E-2 Shoreline Activities 1.4E-4 Swimming and Boating 1.1 E-5 10CFR50 Objective 10 Note: This table summarizes selected information from the reports referenced in the footnotes below. For more complete information, see the referenced reports. a Per Zion Appendix I Report (Reference 72), Table 1.1-7. Except for drinking water, these values are based on water in the discharge canal; drinking water is assumed to be from the Lake County Illinois intake (see Appendix I Report, Table 1.1-6). Page 267 of 267
~
~--~~-------ZIONSOLUTIONSL-u--~----------- An EnergySo/utions Company April27,2016 ZS-2016-0042 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Zion Nuclear Power Station, Units 1, 2 and ISFSI Facility Operating License Nos. DPR-39 and DPR-48
- NRC Docket Nos. 50-295, 50-304 and 72-1037
Subject:
Radioactive Effluent Release Report, Radioactive Effluent Control Program Report, Offsite Dose Calculation Manual and Process Control Program for 2015 In accordance with Facility Operation License Nos. DPR-39 and DPR-48, Quality Assurance Project Plan Appendix B Section 5.7.3, "Radioactive Effluent Release Report," for Zion Nuclear Power Station, Units 1 and 2, this is the submittal of a Radioactive Effluent Release Report for the year 2015. The report is required to be submitted prior to May 1, 2016 and is provided as Attachments 1 through 6 to this letter. Certificate of Compliance No. 1031 for the MAGNASTOR SYSTEM, Appendix A, Technical Specifications 5.1.1and5.1.3 require submittal of an Annual Radioactive Effluent Control Program report which is included in this document. Pursuant to 10 CFR 50.4 and Offsite Dose Calculation Manual (ODCM) 12.7.4, there were changes made to the Zion Station Liquid Effluent Treatment System during the period of January through December 2015. The changes to the Liquid Effluent Treatment System are summarized in Attachment 1, Section 7, for the calendar year of 2015. There were surveillances conducted for an inoperable plant monitoring system that exceeded the time listed in ODCM Section 12.2.2. ODCM Section 12.7.2 requires an explanation as to why the inoperability requirements of the monitoring system was not corrected in the time specified. Attachment 1, Section 8, provides this explanation and a summary of the results of the station review conducted to restore the plant monitoring system to operable status. There were changes made to the ODCM including a complete re-write of the ODCM for post fuel transfer operations in 2015. Per ODCM 12.7.3.lc, a summary of changes made during each revision and a complete copy of the current ODCM is submitted in Attachment 6. There were no changes to the Process Control Program during 2015. 101 Shiloh Boulevard, Zion
- IL 60099 (224) 789-4016
- Fax: (224) 789-4008
- www.zionsolutionscompany.com
ZionSolutions, LLC ZS-2016-0042 Page 2 of2 There are no new regulatory commitments in this submittal. If you have any questions about this submittal please contact Mr. Christopher Keene at (224)789-4073. Respectfully, {;~~~ Gerard van Noordennen Vice President of Regulatory Affairs Attachments:
- 1. Radioactive Effluent Release Report
- 2. ECN# 400577 Extending liquid effluent discharge line through the discharge tunnel
- 3. ECN# 400657 Installing additional liquid effluent discharge flowmeters
- 4. ECN# 400986 Increased capacity dilution water pump of 10,000 .gpm and associated flowmeters
- 5. ECN# 2015-04 Installation of new liquid effluent radiation monitor for ORT-PR04 and dilution flow permissive for lake discharge valve OSOV-WDOlO
- 6. Current Copy of Zion Station ODCM, Rev. 5 cc: John Hickman, U.S. NRC Senior Project Manager Regional Administrator, U.S. NRC, Region III Service List (Cover letter only, no attachments)
Zion Nuclear Power Station, Unit 1and2 License Transfer Service List cc: Ken Robuck Russ Workman Group President Disposal and General Counsel Decommissioning EnergySolutions EnergySolutions 299 South Main Street, Suite 1700 299 South Main Street, Suite 1700 Salt Lake City, UT 84111 . Salt Lake City, UT 84111 Alwyn C. Settles John Sauger
- Section Head, Nuclear Facility Inspection Executive VP & General Manager Bureau of Nuclear Facility Safety ZionSolutions, LLC Illinois Emergency Management Agency 101 Shiloh Boulevard 1011 North St., PO Box 250 Zion, IL 60099 Mazon, IL 60444 Gerard van Noordennen Kelly F. Grahn VP Regulatory Affairs Senior Health Physicist, Unit Superviso~
ZionSolutions, LLC Bureau of Radiation Safety, Environmental 101 Shiloh Boulevard Management Zion, IL 60099 Illinois Emergency Management Agency 245 W Roosevelt Road, Building 8, Suite 55 Anthony Orawiec West Chicago, IL 60185 Decommissioning Plant Manager ZionSolutions, LLC Kent McKenzie 101 Shiloh Boulevard Emergency Management Coordinator Zion, IL 60099 Lake County Emergency Management Agency 1303N. Milwaukee Avenue Dan Shrum Libertyville, IL 60048-1308 Senior VP Regulatory Affairs EnergySolutions John E. Matthews 299 South Main Street, Suite 1700
- Morgan, Lewis & Bockius LLP Salt Lake City, UT 84111 1111 Pennsylvania Avenue, NW Washington, DC 20004
ZionSolutions LLC ZS-2016-0042: Attachments ATTACHMENT 1 Radioactive Effluent Release Report
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 1 of 48 List of Sections Section# Description 1 Supplemental Information 2 Effluent & Waste Disposal Summary 2.1 Unit 1 Gaseous Effluent 2.2 Unit 2 Gaseous Effluent 2.3 Liquid Effluent 2.4 Direct Radiation 2.5 LLD's 2.6 Error Estimation 3 Solid Waste and Irradiated Fuel Shipments 4 Radiological Impact on Man, 40CFR190 & 10CFR72 Compliance summary 4.1Unit1 4.2 Unit 2 4.3 ISFSI 4.4 Combined 40CFR190 report 5 Meteorology Data 6 Errata Data from previous years 7 Summary of Liquid Radwaste System Changes 8 Corrective Actions for Inoperable Rad Monitor 9 Changes to the ODCM
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 2of48 Sectiorr 1: Supplemental Information
- 1. Regulatory Limits: The dose to a member of the public from direct radiation, liquid and gaseous effluents released from each unit to areas at or beyond site boundary shall be limited to the following:
- a. Fission and Activation products:*
- i. Tech Spec Whole Body: 500 mrem/year ii. Tech Spec Skin: 3000 mrem/year
- b. Particulates with half-lives > 8 days, tritium and Iodine:
- i. Tech Spec Organ:
- 1500 mrem/year ii. 10CFR50 Organ: 7.5 mrem/quarter, 15 mrem/year
- c. Liquid Effluents:
- i. 10CFRSO Whole body: 1.5 mrem/quarter, 3 mrem/year ii. 10CFR50 Organ: 5 mrem/quarter, 10 mrem/year
- d. Combined dose to real individual beyond controlled area:
- i. 10CFR72 Whole body: 25 mrem/year ii. 10CFR72 Thyroid: 75 mrem/year 111. 10CFR72 Organ: 25 mrem/year
- 2. Effluent Concentration Limits (ECL): Limits used in determining allowable release.rates or concentrations.
- a. Gaseous Effluents: 10CFR20 Appendix B Table 2 Column 1.
- b. Liquid Effluents: 10 X 10CFR20 Appendix BTable 2 Column 2.
- 3. Measurements and Approxima.tions of Total Radioactivity.
- a. Fission and Activation Products: 100% Kr-85 is assumed in calculations since other isotopes have decayed. Vent stack activity is continuously monitored for fission and activation gases. In January of 2015 all fuel was removed from the Fuel Handling Building and Transferred to the ISFSI. After the last fuel assembly was transferred, noble gases are no longer present as potential gaseous effluents.
- b. Particulate and tritium releases are continuously monitored and samples collected and analyzed weekly. Particulate filters are sent to an independent lab for quarterly composite analysis. During periods when 1RIA-PR49 and 2RIA-PR49 were Out of Service. for maintenarn:;e, particulate activity was continuously monitored. The air samples were analyzed daily while decommissioning activities were in progress in each of the areas feeding into the respective Units vent stack (i.e. Unit 1 purge system for Unit 1 vent stack and Unit 2 purge system, Aux. building, Fuel Handling Building for Unit 2 vent stack). A separate composite was sent to an independent lab for composite analysis for each area monitored. Tritium activity in gaseous releases in Unit 2 vent stack were monitored during the weekly sampling. Due to pumping down the reactor cavities and spent fuel pool, the remainder of the Tritium present was monitored and calculated in liquid effluent releases instead of estimating the release via evaporation. For the purpose of freeze protection of the liquid effluent release line, an air compressor was used to blow air through the line. The air compressor drew air from a room in the Auxiliary Building thus .this pathway was added to gaseous release calculations .. The air in the room from which the air compressor
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 3of48 drew its suction was continuously monitored and the samples analyzed daily. Any activity detected in this air sample was added to continuous abnormal gaseous releases and the samples sent for quarterly composite analysis. per ODCM requirements. * .
- c. Liquid effluents are continuously monitored and isotopic analysis performed weekly. Liquid batch releases are mixed and a representative sample taken and
'analyzed prior to batch release. A complete analysis of all liquid volumes was performed by an offsite laboratory to determine hard to detect nuclide activity. A conservative ratio to Co-60 was calculated for each hard to detect nucJide. Prior to each batch release, these scaling factors were used to calculate the concentration of these hard to detect nuclides. During 2015, all potential radioactive inputs were removed from the turbine building fire sump, and the OR-PR25 fire sump monitor was removed as it was no longer required. To facilitate turbine building demolition, the fire sump compositor was moved to the Waste Water Treatment Facility (WWTF) which receives input from the remaining turbine building drains. Weekly samples and quarterly composites are analyzed on the WWTF compositor to verify there are no radioactive isotopes in the water discharged via theWWTF.
- d. . Occupancy factors were used in determining direct radiation dose to the maximally exposed member of the public based on habits of a real individual in ES&H Technical Support Document 13-009 "Member of the Public Dose from All Onsite Sources."
- 4. Batch Releases:
- a. Liquid:
- 1. There were 67 liquid batch releases in 2015
- 2. Total time period for batch releases: 2.32E+OS min.
- 3. Maximum time period for a batch release: 1.13E+04 min.
- 4. Average time period for batch release: 3.46E+03 min.
- 5. Minimum time period for a batch release: 6.12E+02 min.
- b. Gaseous:* There were no gaseous batch releases in 2015.
- 5. Abnormal Releases:**
- a. Liquid: There were no abnormal liquid releases in 2015.
- b. Gaseous: Auxiliary Building Air Compressor freeze protection discharged a total of3.05E+10 ccs. of air from 12/22/2015 to 1/1/2016.
- 6. Gaseous and Liquid Waste Treatment Systems and Process Control Program Zion Station ODCM Section 12.6.4 requires major changes to the Gaseous and Liquid Waste Treatment Systems to be reported in the Annual Radioactive Effluent Release Report. There were some changes to the Liquid Waste Treatment System, these changes and their technical bases are described in Section 7.
Zion Station ODCM Section 12. 7.2 requires major changes to the Process Control Program(PCP) to be submitted in the Annual Radioactive Effluent Release Report.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 4 of 48 The Waste Gas Hold-up System was permanently vented. In Zion's defueled configuration this system is no longer applicable. In Zion's defueled configuration, the charcoal iodine removal system is no longer applicable. Due to radioactive decay and no means of production, radioactive iodine is* not a concern at Zion.
- 7. Limiting Conditions of Operation (LCOs)
Zion Station ODCM Section 12.7.2 requires explanation as to why the inoperability of liquid or gaseous monitoring instrumentation was not corrected within the time specified in the ODCM to be submitted with the Annual Radioactive Effluent Release Report. OR-PR04 Lake Release Tank liquid effluent radiation monitor was Out of Service for a period greater than 14 days. A detailed discussion of the reasons and resolution to this issue is described in Section 8.
- 8. Liquid Holdup Tanks and Gas Storage Tanks Zion Station ODCM Section 12.7.2 requires a description of events leading to liquid holdup tanks or gas storage tanks exceeding technical specification limits to be included in the Annual Radioactive Effluent Release Report.
The contents of the six gas decay tanks have been sampled and determined to have negligible activity. The Gas Decay Tanks have been decommissioned. No liquid holdup tanks exceeded the limits of Pennanently Defueled Technical Specifications 5.6.3 during 2015.
- 9. Offsite Dose Calculation Manual (ODCM)
Changes to the ODCM and Process Control Program are required by Zion Station Permanently Defueled Technical Specification 5.6.1. and ODCM Section 12.6.3 to be submitted as part of, or concurrent with, the Annual Radioactive Effluent Release Report.
- a. ODCM Revisions: There was a major re-write to the ODCM for the purpose of the change in licensing to Post Fuel Transfer operations. The ODCM chapters were consolidated into a single document and the revision number was reset to*
revision 0. A list of changes made during 2015 are listed in Section 9.
- b. Process Control Program(PCP): There were no changes to the PCP in 2015.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 5of48
- 10. Switchyard Area The switchyard is an onsite area that is monitored for direct radiation dose. Access to the*
site is controlled by Commonwealth Edison and is not accessible to members of the general public. The dose limits for this area are regulated differently than the general offsite dose areas and comply with 10CFR20 annual dose limit of 100 mrem/year. ES&H TSD 13-009 lists the evaluation performed to determine habits of the real individual working in the switchyard and are calculated to be occupied no more than 2088 hours/year.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 6of48 Section 2.1 - Unit 1 Gaseous Releases GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit 1 Vent Stack - GROUND RELEASES REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases
- 1. Total Release Ci <LLD <LLD <LLD <LLD <LLD 2 . Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Iodine-131
- 1. Total Release Ci <LLD <LLD <LLD <LLD <LLD 2 . Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Particulates Half Life >= 8 days
- 1. Total Release Ci O.OOE+OO 2.57E-06 9.04E-04 3.43E-05 9.41E-04
- 2. Avg. Release Rate uCi/sec O.OOE+OO 3.27E-07 1.15E-04 4.36E-06 2.99E-05 Tritium
- 1. Total Release Ci <LLD <LLD <LLD. <LLD <LLD
- 2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity
- 1. Total Release Ci <LLD <LLD <LLD <LLD <LLD
- 2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation <LLD <LLD <LLD <LLD <LLD Gases Iodines <LLD <LLD <LLD <LLD <LLD
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 7of48 Particulates Half Life >= 8 days C0-60 Ci <LLD O.OOE+OO 7.46E-04 2.62E-05 7.72E-04 CS-137 Ci <LLD 2.57E-06 1.58E-04 8 .12E-0.6 1.69E-04 Totals for Period ... Ci <LLD 2.57E-06 9.04E-04 3.43E-05 9.41E-04 Tritium <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity <LLD .<LLD <LLD <LLD <LLD GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR No Batch Releases. LLD values are listed in Section 2.5 Total Error values are listed in Section 2.6
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 8of48 Section 2.2 - Unit 2 Gaseous Releases GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit 2 Vent Stack - GROUND RELEASES REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases
- 1. Total Release - Ci <LLD <LLD <LLD <LLD <LLD 2 . Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Iodine-131
- 1. Total Release Ci <LLD <LLD <LLD <LLD <LLD 2 . Avg. Release Rate uCi/sec <LLD. <LLD <LLD <LLD <LLD Particulates Half Life >= 8 days
- 1. Total Release Ci 4.99E-06 2.72E-06 1.40E-05 3.40E-06 2.SlE-05
- 2. Avg. Release Rate uCi/sec 6.34E-07 3.46E-07 1.78E-06 4.32E-07 7.97E-07 Tritium
- 1. Total Release , Ci <LLD <LLD <LLD <LLD <LLD
- 2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity
- 1. Total Release Ci <LLD <LLD <LLD <LLD- <LLD
- 2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation <LLD <LLD <LLD <LLD <LLD Gases Iodines <LLD <LLD <LLD <LLD <LLD
ZionSolutiOns LLC ZS-2016-0042: Attachment 1 Page 9of48 Particulates Half Life >= 8 days C0-60 Ci 3.28E-07 2.72E-06 7.89E-06 O.OOE+OO 1.09E-05 CS-137 Ci 4.66E-06 O.OOE+OO 6.07E-06 3.40E-06 1.41E-05 Totals for Period... Ci 4.99E-06 2.72E-06 1.40E-05 3.40E-06 2.51E-05 Tritium <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity <LLD <LLD <LLD <LLD <LLD GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR No Batch Releases. LLD values are listed in Section 2.5 Total Error values are listed in Section 2.6
ZionSolutions LLC ZS-2016-0042: Attachment l, Page 10 of 48 Section 2.3 - Liquid Effluent Releases LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (Unit 1 & Unit 2 combined) REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products AG-108M Ci O.OOE+OO O.OOE+OO 1.04E-05 2.51E-06 1.29E-05 C-14 Ci 4.41E-06 3.85E-04 3.50E-04 1.86E-04 9.25E-04 C0-60 Ci 1.00E-05 8.09E-04 7.82E-04 4.15E-04 2.02E-03 CS-137 Ci 0.00E+OO 1.28E-05 9.54E-06 1.30E-05 3.54E-05 FE-55 Ci 1.57E-06 l.13E-04 l.OSE-04 5.73E-05 2.79E-04 NI-59 Ci 3.0lE-06 2.llE-04 1. 06E-04 5.65E-05 3.77E-04 NI-63 Ci l.31E-04 1.0SE-02 8.83E-03 4.69E-03 2.45E-02 PU-241 Ci 1.03E-07 9.00E-06 8.75E-06 4.6SE-06 2.25E-05 SR-90 Ci 1.69E-06 9.47E-05 4.31E-06 2.29E-06 1.03E-04 Totals for Period... Ci 1.52E-04 l.24E-02 1.02E-02 5.43E-03 2.82E-02 Tritium H-3 Ci 6.64E-03 2.57E-01 2.57E-01 5.43E-01 1.06E+OO Totals for Period... Ci 6.64E-03 2.57E-01 2.57E-01 5.43E-01 1.06E+OO Dissolved and Entrained Gases
- 1. Total Release Ci <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity ALPHA Ci 0.00E+OO 7.22E-06 4.90E-06 6.55E-06 1.87E-05 Totals for Period... Ci O.OOE+OO 7.22E-06 4.90E-06 6.55E-06 1.87E-05 Volume of liquid waste liters 1.27E+06 1.82E+06 2.23E+06 l.01E+07 1.54E+07 Volume of dil. water liters 1.23E+09 1.24E+09 2.48E+09 5.01E+09 9.96E+09 LLD values are listed in Section 2.5 Total Error values are listed in Section 2.6
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 11of48 Section 2.3 - Liquid Effluent Releases (cont.) LIQUID EFFLUENTS - CONTINUOUS MODE (Unit 1 & Unit 2 combined) REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products <LLD <LLD <LLD <LLD <LLD Tritium <LLD <LLD <LLD <LLD <LLD Dissolved and Entrained Gases <LLD <LLD <LLD <LLD <LLD Gross Alpha Radioactivity <LLD <LLD <LLD <LLD <LLD LLD values are listed in Section 2.5 Total Error values are listed in Section 2.6
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 12of48 Section 2.3 - Liquid Effluent Releases (cont.) LIQUID EFFLUENTS - BATCH MODE (Unit 1 & Unit 2 combined) REPORT FOR 2015 . Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Products AG-108M Ci O.OOE+OO O.OOE+OO 1.04E-05 2.51E-06 1.29E-05 C-14 Ci 4.41E-06 3.85E-04 3.50E-04 1.86E-04 9.25E-04 C0-60 Ci l.OOE-05 8.09E-04 7.82E-04 4.15E-04 2.02E-03 CS-137 Ci O.OOE+OO 1.28E-05 9.54E-06 1.30E-05 3.54E-05 FE-55 Ci 1.57E-06 1.13E-04 1.08E-04 5.73E-05 2.79E-04 NI-59 Ci 3.0lE-06 2.llE-04 1.06E-04 5.65E-05 3.77E-04 NI-63 Ci 1.31E-04 1.08E-Q2 8.83E-03 4.69E-03 2.45E-02 PU-241 Ci 1.03E-07 9.00E-06 8.75E-06 4.65E-06 2.25E-05 SR-90 Ci 1.69E-06 9.47E-05 4.31E-06 2.29E-06 1. 03E-04 Totals for Period... Ci 1.52E-04 1.24E-02 1.02E-02 5.43E-03 2.82E-02 Tritium H-3 Ci 6.64E-03 2.57E-01 2.57E-01 5.43E-01 l.06E+OO Totals for Period... Ci 6.64E-03 -2.57E-01 2.57E-01 5.43E-01 1.06E+OO Dissolved and Entrained Gases N/A <LLD <LLD <LLD <LLD Gross Alpha Radioactivity ALPHA Ci O.OOE+OO 7.22E-06 4.90E-06 6.55E-06 1.87E-05 Totals for Period... Ci O.OOE+OO 7.22E-06 4.90E-06 6.55E-06 1.87E-05 LLD values ar~ listed in Section 2.5 Tbtal Error valu~s are listed in Section 2.6
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 13 of 48 Section 2.3 - Liquid Effluent Releases (cont.) SUPPLEMENTAL INFORMATION LIQUID EFFLUENTS - BATCH MODE REPORT FOR 2015 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Number of releases 1 16 17 33 67 Total release time minutes 2.57E+03 7.87E+04 4.93E+04 1.01E+05 2.32E+05 Maximum release time minutes 2.57E+03 1.13E+04 9.22E+03 4.32E+03 1.13E+04 Average release time minutes 2.57E+03 4.92E+03 2.90E+03 3.08E+03 3.46E+03 Minimum release time minutes 2.57E+03 l.19E+03 6.17E+02 1.92E+03 6.17E+02 Permit dilution vol ltr 2.58E+07 9.92E+08 l.62E+09 3.84E+09 6.48E+09 Permit dilution flow gpm 2.65E+03 3.33E+03 8.68E+03 1.00E+04 7.38E+03 Permit max total diluted concentration (no H-3) uCi/ml 5.89E-09 6.46E-08 2.17E-08 5.17E-09 6.46E-08 Period dilution vol ltr 1.23E+09 1.24E+09 2.48E+09 5.01E+09 9.96E+09 Period dilution flow gpm 2.51E+03 2.50E+03 4.95E+03 9.99E+03 5.01E+03
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 14of48 Section 2.4-Direct Radiation Maximally exposed sector: J (25mrem/year limit) Unit Qtr 1 (mrem) Qtr 2 (mrem) Qtr 3 (mrem) Qtr4 (mrem) 2015 (mrem) Unit 1 8.25E-01 1.57E+OO 1.83E+OO 1.57E+OO 5.80E+OO Unit 2 8.25E-01 1.57E+OO 1.83E+OO 1.57E+OO 5.80E+OO ISFSI - gamma 8.25E-01 1.57E+OO 1.83E+OO 1.57E+OO 5.80E+OO ISFSI - neutron 3.00E-01 4.70E-01 7.15E-01 4.20E-01 1.91E+OO Sum: 2.78E+OO 5.18E+OO 6.21E+OO 5.13.E+OO 1.93E+Ol Maximally exposed sector Switchyard South (1 OOmrem/year limit) Switchyard Qtr 1 (mrem} Qtr 2 (mrem} Qtr 3 (mrem} Qtr 4 (mrem} 2015 (mrem} Gamma 2.61E+01 1.81E+01 2.23E+01 1.58E+01 8.23E+01 Neutron 3.10E+OO 1.80E+OO 2.90E+OO 1.40E+OO 9.20E+OO Sum 2.92E+01 1.99E+01 2.52E+01 1.72E+01 9.lSE+Ol
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 15 of 48 Section 2.5-LLD's Various detectors were used on different counting platforms for the gaseous and liquid weekly effluent samples. The lower limit of detection(LLD) accompanies each counted sample and is verified to meet the following maximum LLD's: A. Liquid Lower Limit of Detection Sample frequency Type of analysis (LLD) uCi/mL Weekly/prior to each release Principal Gamma Emitters: <5.00E-07 Dissolved and Entrained <1.00E-05 Gases Monthly composite Tritium <1.00E-05 Gross Alpha <1.00E-07 Quarterly composite Sr-90 5.00E-08 Fe-55, Ni-63 l.OOE-06 B. Gaseous Lower Limit of Detection Sample frequency Type of analysis (LLD) uCi/mL Continuous/daily/weekly Principle gamma emitters <l.OOE-11 Continuous Noble gas <1.00E-06 Monthly Noble Gas I Principle gamma <1.00E-04 emitters Tritium l.OOE-06 Quarterly composite Sr-90 <l.OOE-11 Fe-55 <3.00E-11 Ni-63 <l.OOE-11 Gross Alpha <l.OOE-11
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 16 of 48 Section 2.6-Error Estimation Estimates of Total Error The following is a calculated estimate of the maximum potential total error associated with reported values in the Annual Radioactive Effluent Release Report. The Total error is determined by calculating the square root of the sum of the squares of the individual errors.
- a. Gaseous Effluents Sampling Error 5%
Calibration Error 10% Counting Statistics Error 17% Sample Volume Error 10% Total Error 23%
- b. Liquid Effluents Sampling Error 5%
Calibration Error 10% Counting Statistics Error 16% Sample Volume Error 2% Total Error 20%
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 17of48 Section 3- Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)
- 1. .Types ofWaste Total Total Est. Total Types of Waste Quantity Activity Period (m3) Error%.
(Ci)
- a. Spent Resins, filter sludges, 6.993E+Ol 1)57E+02 2015 2.50E+Ol evaporator bottoms
- b. Dry compressible waste, 3.115E+03 l.804E+02 2015 2.50E+Ol contaminated equipment
- c. Irradiated components, 4.958E+02 8.316E+03 2015 2.50E+Ol control rods, etc.
- d. Other (describe) O.OOE+OO O.OOE+OO 2015 2.50E+Ol
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 18 of 48 Section 3- Solid Waste and Irradiated Fuel Shipments (cont.)
- 2. Estimate of major nuclide composition (by waste type)
Major Nuclide Waste Type a. Resins, Waste Type b. DAW Waste Type d. Irradiated Waste Type Composition sludges bottoms (%) contaminated equipment(%) components (%) d. Other% Ag-108m O.OOE+OO 2.26E-03 O.OOE+OO 0.00 Ag-llOm O.OOE+OO O.OOE+OO O.OOE+OO 0.00 Am-241 2.75E-03 2.30E-02 4.66E-05 0.00 C-14 l.50E-02 5.43E-02 5.64E-02 0.00 Ce-144 l.03E-03 5.86E-02 l.73E-04 0.00 Cm-242 3.91E-05 8.57E-05 l.78E-07 0.00 Cm-243 9.25E-04 7.19E-03 l.68E-05 0.00 Cm-244 O.OOE+OO 4.22E-03 8.82E-06 0.00 Co-60 , 4.36E+Ol 2.98E+Ol 6.49E+Ol 0.00 Cs-134 O.OOE+OO O.OOE+OO 2.61E-07 0.00 Cs-137 l.02E+Ol 5.37E+OO 3.22E-03 0.00 Fe-55 2.19E-01 3.60E+OO 9.23E+OO 0.00 H-3 5.87E-03 6.75E-02 l.43E-01 0.00 I-129 1.08E-03 5.97E-03 2.45E-05 0.00 Mn-54 O.OOE+OO l.76E-02 l.05E-04 0.00 Nb-94 5.29E-03 2.44E-02 l.06E-03 0.00 Ni-59 3.81E+OO 7.63E-01 3.26E-01 0.00 Ni-63 4.18E+Ol 5.86E+Ol 4.lOE-04 0.00 Ni-63am O.OOE+OO l.18E+OO . 2.54E+Ol 0.00 Np-237 O.OOE+OO 6.69E-11 O.OOE+OO 0.00 Pu-238 l.50E-03 1.49E-02 2.17E-05 0.00 Pu-239 8.l lE-04 5.21E-03 8.55E-06 0.00 Pu-240 O.OOE+OO 1.12E-03 6.65E-06 0.00 Pu-241 3.76E-02 9.07E-02 2.86E-04 0.00 Pu-242 4.45E-06 1.68E-04 4.03E-07 0.00 Ra-226 O.OOE+OO 7.58E-04 l.OlE-05 0.00 Sb-125 6.59E-03 6.86E-02 l.42E-04 0.00 Sr-89 l.98E-03 l.73E-02 7.33E-06 0.00 Sr-90 2.69E-01 6.58E-02 6.50E-05 0.00 Tc-99 l.18E-02 5.34E-02 1.96E-04 0.00 EU-152 O.OOE+OO 6.69E-03 O.OOE+OO 0.00 EU-154 O.OOE+OO 9.29E-04 O.OOE+OO 0.00 U-235 O.OOE+OO l.3 lE-03 O.OOE+OO 0.00 U-236 O.OOE+OO 4.34E-05 O.OOE+OO 0.00 U-237 O.OOE+OO l.lOE-05 O.OOE+OO 0.00 U-238 O.OOE+OO 4.6JE-07 O.OOE+OO 0.00 Zn-65 6.39E-03 5.29E-02 9.34E-05 0.00
- Ni-63AM - activated metal
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 19of48 Section 3- Solid Waste and Irradiated Fuel Shipments (cont.)
- 3. Solid Waste Disposition Number of shipments Mode of Transportation Destination 34 Truck CliveCWF 0 Rail CliveCWF 12 Truck CliveBWF 32 Rail CliveBWF 12 Truck wcs B. Irradiated Fuel Shipments (disposition)
Number of shipments Mode of Transportation Destination I 0 I C. Changes to the Process Control Program: None
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 20 of 48 Section 4-40CFR190 & 10CRF72 Compliance Summary UNIT 1, 2 & ISFSI (DOCKET Numbers 50-295, 50-304 & 72-1037) EXECUTIVE
SUMMARY
A review of 2015 effluent data indicates that the activity released from the station was far below any regulatory limit. There was no noble gas released in 2015. This trend can be attributed to the shutdown ofboth units since late September 1997. Airborne Dose to Maximally Exposed Dose to Maximally Exposed Receptor from Unit 1 Receptor from Unit 2 Gamma Air O.OOE+OO mrad O.OOE+OO mrad Beta Air O.OOE+OO mrad O.OOE+OO mrad Total Body 2.94E-02 mrem 2.94E-02 mrem Skin O.OOE+OO mrem O.OOE+OO mrem Organ 6.75E-02 mrem (Infant Liver) 6.75E-02 mrem (Infant Liver) Aquatic Dose to Maximally Exposed Dose to Maximally Exposed Receptor (Any) from Unit 1 Receptor (Any) from Unit 2 Total Body l.82E-03 mrem l.82E-03 mrem Organ 5.00E-02 mrem(Child Bone) 5.00E-02 mrem(Child Bone) Direct Radiation Dose to Maximally Dose to Maximally Dose to Maximally Exposed Member of the Exposed Member of the Exposed Member of the public from Unit 1 public from Unit 2 public from ISFSI Total Body 5.80E+00mrem (Sec J) 5.80E+OOmrem (Sec J) 7.71E+OOmrem (Sec J) Switchyard Direct Radiation (10CFR20 limit lOOmrem/year) Switchyard Qtr 1 (mrem) Qtr 2 (mrem) Qtr 3 (mrem) Qtr4 (mrem) 2015 (mrem) Gamma 2.61E+Ol l.81E+Ol 2.23E+Ol l.58E+Ol 8.23E+Ol Neutron 3.IOE+OO l.80E+OO 2.90E+OO 1.40E+OO 9.20E+OO Sum 2.92E+Ol l.99E+Ol 2.52E+Ol l.72E+Ol 9.15E+Ol
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 21of48 Section 4.1 - Unit 1 I. Unit 1 (Docket Number 50-295) A. 10 CFR20 & 40CFR 190 Compliance Assessment: The demonstration of compliance with 40CFR190 will be used to demonstrate compliance with 10CFR20.
- 1. Total Effective Dose Equivalent 5.83E+OO mrem/year
- 2. 40 CFR 190 Whole body limit 25 mrem/year
- 3. 40 CFR 190 Max exposed organ 25 mrem (75 mrem thyroid)
- 4. % Whole body limit 2.33E+01%
- 5. % Max exposed organ 2.36E+Ol % child bone Qtr 1 mrem Qtr2 mrem Qtr 3 mrem Qtr4 mrem 2015 mrem TBody 8.25E-01
- l.57E+OO 1.86E+OO l.57E+OO 5.83E+OO Adult Thody Child Thody Adult Thody Adult Thody Adult Thody Organ 8.26E-01 l.62E+OO l.89E+OO l.58E+OO 5.90E+OO Child Bone Child Bone Child Bone Child Bone Child Bone B. Maximally Exposed Receptor:
- 1. Airborne QtrObj lst,Qtr 2nd Qtr 3rd Qtr 4th Qtr Yearly limit Total Dose % of Yearly IOCFR50 2015 limit App. I Gamma air (mrad) 5.0 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO 10.0 O.OOE+OO O.OOE+oO Beta Air (mrad) 10.0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+oO 20.0 0.00E+OO O.OOE+OO Total Body (mrem) 7.5 2.48E-04 2.0IE-04 2.76E-02 I .30E-03 15.0 2.94E-02 l.96E-01 Skin (mrem) 7.5 O.OOE+oO O.OOE+OO O.OOE+OO O.OOE+OO 15.0 O.OOE+OO O.OOE+OO Organ (mrem) 7.5 l.23E-03 7.40E-04 6.20E-02 3.71E-03 15.0 6.75E-02 4.50E-Ol Critical Organ Infant liver Infant liver Infant liver Infant liver Infant !iv.er Infant liver
- 2. Aquatic Yearly limit %of 2nd Qtr 3rd Qtr 4tl'Qtr Total Dose QtrObj l"Qtr IOCFR 50 Yearly 2015 App.I limit 1.97E- 1.64E- 6.35E- 2.16E- 3.0 1.82E- 6.0lE-Total Body (mrem) 2.5
*05 03 04 04 03 02 5.95E- 4.70E- 1.73E- 4.64E- 10.0 5.00E- 5.00E-Organ (mrem) 2.5 04 02 02 03 02 01 Critical Organ Child bone Child bone Child bone Child bone Child bone Child bone
- 3. Direct (gamma) Maximally Exposed Sector: J Yearly Qtr 2nd Qtr 3rd Qtr 4tl'Qtr limit Total Dose I"Qtr % of Yearly limit Obj 40CFR 2015 190 Total body 6.25 8.25E-OI l.57E+OO l.83E+OO l.57E+OO 25.0 5.80E+OO 2.32E+Ol (mrem)
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 22of48 Section 4.2 - Unit 2 II. Unit 2 (Docket Number 50-304) A. 10 CFR20 & 40CFR190 Compliance Assessment: The demonstration of compliance with 40CFR190 will be used to demonstrate compliance with 10CFR20.
- 1. Total Effective Dose Equivalent 5.83E+OO mrem/year
- 2. 40 CFR 190 Whole body limit 25 mrem/year
- 3. 40 CFR 190 Max exposed organ 25 mrem (75 mrem thyroid)
- 4. % Whole body limit 2.33E+01%
- 5. % Max exposed organ 2.36E+Ol % child bone Qtr 1 mrem Qtr2mrem Qtr 3 mrem Qtr4mrem 2015 mrem TBody 8.25E-01 1.57E+OO l.86E+OO l.57E+OO 5.83E+OO Adult Thody Child Thody Adult Thody Adult Thody Adult Thody Organ 8.26E-01 l.62E+OO l.89E+OO l.58E+OO 5.90E+OO Child Bone Child Bone Child Bone Child Bone Child Bone B. Maximally Exposed Receptor:
- 1. Airborne Qtr 1'1 Qtr 211 " Qtr 3'" Qtr 4m Qtr Yearly limit Total Dose % of Yearly Obj !OCFR 50 2015 limit App. I Gamma air (mrad) 5.0 O.OOE+OO O.OOE+OO O.OOE+oO O.OOE+OO 10.0 O.OOE+oO O.OOE+OO Beta Air (mrad) 10.0 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 20.0 O.OOE+OO O.OOE+OO Total Body (mrem) 7.5 2.48E-04 2.0lE-04 2.76E-02 l .30E-03 15.0 2.94E-02 l.96E-Ol Skin (mrem) 7.5 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 15.0 0.00E+OO 0.00E+OO Organ (mrem) 7.5 l .23E-03 7.40E-04 6.20E-02 3.71E-03 15.0 6.75E-02 4.SOE-01 Critical Organ Infant liver Infant liver Infant liver Infant liver Infant liver Infant liver
- 2. Aquatic Yearly limit Qtr 1 Total Dose 1'1 Qtr 2"" Qtr 3" .Qtr 4tl'Qtr 10CFR % of Yearly limit Obj 2015 50 App.
I Total Body 2.5 l.97E-05 l.64E-03 6.35E-04 2.16E-04 3.0 l.82E-03 6.0lE-02 (mrem) Organ 2.5 5.95E-04 4.70E-02 l.73E-02 4.64E-03 10.0 5.00E-02 5.00E-01 (mrem) Critical Child bone Child bone Child bone Child bone Child bone Child bone Onmn
- 3. Direct (gamma) Maximally Exposed Sector: J Yearly Qtr 3rd Qtr limit Total Dose lQtr 2°" Qtr 4thQtr % of Yearly limit Obj 40CFR 2015 190 Total body 6.25 8.25E-Ol l.57E+o0 l.83E+OO l.57E+OO 25.0 5.80E+o0 2.32E+Ol (mrem)
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 23 of 48 Section 4.3 - ISFSI III. ISFSI (Docket Number 72-1037) A. 10CFR72 & 40CFR190 Compliance Assessment:
- 1. Total Effective Dose Equivalent 7. 71 +00 mrem/year
- 2. 40 CFR190 I 10CFR72 Whole body limit 25 mrem/year
- 3. 40 CFR190 I 10CFR72 Max exposed organ 25 mrem (75 mrem thyroid)
- 4. % Whole body limit 3.08E+01%
- 5. % Max exposed organ (child bone/thyroid) 3.08E+Ol % I l.03E+Ol %
Qtr 1 mrem Qtr 2 mrem Qtr 3 mrem Qtr4 mrem 2015 mrem TEDE l.13E+OO 2.04E+OO 2.55E+OO l.99E+OO 7.71E+OO TODE l.13E+OO 2.04E+OO 2.55E+OO l.99E+OO 7.71E+OO B. Maximally Exposed Receptor Sector: J
- 1. Direct (gamma+ neutron)
Yearly limit Qtr Total Dose % of Yearly lQtr 2"d Qtr 3"1 Qtr 4th Qtr 40CFR190/ Obj 2015 limit 10CFR72.104 Total body 6.25 l.13E+OO 2.04E+OO 2.55+00 l.99E+OO 25.0 7.71E+OO 3.08E+Ol (mr_em)
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 24 of 48 Section 4.4-Combined 40CRF190 Report IV. Combined 40CFR190 Report: 40CFR190 URANIUM FUEL CYCLE DOSE REPORT LIQUID ANNUAL DOSE
SUMMARY
Year . . . . . . . . . . . . . . . . . . : 2015 From Unit . . . . . . . . . . . . . : 1 To Unit . . . . . . . . . . . . . . . : 2 Liquid Receptor ....... : 0 Liquid Receptor === MAXIMUM PERIOD DOSE TO LIMIT (Any Organ) Dose Age Dose Limit Admin Admin Sl- 0 T.Spec T.Spec Sl-0 Period Group Organ (mrem) Period Limit of Limit Limit of Limit Quarter 1 CHILD BONE 1.19E-03 Quarter 2.50E+OO 4.76E-02 2.50E+OO 4.76E-02 Quarter 2 CHILD BONE 9.40E-02 Quarter 2.50E+OO 3.76E+OO 2.50E+OO 3.76E+OO Quarter 3 CHILD BONE 3.46E-02 Quarter 2.50E+OO 1.38E+OO 2.50E+OO 1. 38E+OO Quarter 4 CHILD BONE 9.27E-03 Quarter 2.50E+OO 3.71E-01 2.50E+OO 3.71E-01 Annual CHILD BONE 1.00E-01 Annual 5.00E+OO 2.00E+OO 5.00E+OO 2.00E+OO --- MAXIMUM PERIOD DOSE TO LIMIT (Tot Body)) =================================== Dose Age Dose Limit Admin Admin % T ..Spec T.Spec 9,. 0 Period Group Organ (mrem) Period Limit of Limit Limit of Limit Quarter 1 CHILD TBODY 3.93E-05 Quarter 1.50E+OO 2.62E-03 1.50E+OO 2.62E-03 Quarter 2 CHILD TBODY 3.28E-03 Quarter 1.50E+OO 2.lSE-01 1. 50E+OO 2.lSE-01 Quarter 3 CHILD TBODY l.27E-03 Quarter 1.50E+OO 8.48E-02 1.50E+OO 8.48E-02 Quarter 4 ADULT TBODY 4.31E-04 Quarter 1.50E+OO 2.87E-02 1.50E+OO 2.87E-02 Annual CHILD TBODY 3.64E-03 Annual 3.00E+OO 1.21E-01 3.00E+OO 1.21E-01
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page25of48 Section 4.4- Combined 40CRF190 Report (cont.) 40CFR190 URANIUM FUEL CYCLE DOSE REPORT GAS ANNUAL DOSE
SUMMARY
Year . . . . . . . . . . . . . . . . . . : 2015 From Unit ............. : 1 To Unit . . . . . . . . . . . . . . . : 2 Coefficient Type ...... : Historical Gas Receptor .......... : 5 Composite Crit. Receptor - IP Distance (meters) ..... : 0.00 Compass Point ......... : NA --- MAXIMUM PERIOD DOSE TO LIMIT (Any Organ) =================================== Dose Age Dose Limit Admin Admin ~ T.Spec 0 T.Spec ~ 0 Period Group Organ (mrem) Period Limit of Limit Limit of Limit Quarter 1 INFANT LIVER 2.46E-03 Quarter 5.63E+OO 4.38E-02 7.50E+OO 3.28E-02 Quarter 2 INFANT LIVER l.48E-03 Quarter 5.63E+OO 2.64E-02 7.50E+OO l.98E-02 Quarter 3 INFANT LIVER 1.24E-01 Quarter 5.63E+OO 2.20E+OO 7.50E+OO 1.65E+OO Quarter 4 INFANT LIVER 7.42E-03 Quarter 5.63E+OO 1.32E-01 7.50E+OO 9;90E-02 Annual INFANT LIVER 1.35E-01 Annual 1.13E+Ol 1. 20E+OO 1.50E+Ol 9.0lE-01 --- MAXIMUM PERIOD DOSE TO LIMIT (Tot Body)) =================================== Dose Age Dose Limit Admin Admin ~ T.Spec 0 T.Spec ~0 Period Group Organ (mrem) Period Limit of Limit Limit of Limit Quarter 1 ADULT TBODY 4.95E-04 Quarter 5.25E+OO 9.43E-03 7.50E+OO 6.60E-03 Quarter 2 ADULT TBODY 4.02E-04 Quarter 5.25E+OO 7.66E-03 7.50E+OO 5.37E-03 Quarter 3 ADULT TBODY 5.52E-02 Quarter 5.25E+OO 1.05E+OO 7.50E+OO 7.37E-01 Quarter 4 ADULT TBODY 2.59E-03 Quarter 5.25E+OO 4.93E-02 7.50E+OO 3.45E-02
~ .. '
Annual ADULT TBODY 5.87E-02 Annual 1.05E+Ol 5.59E-01 1.50E+Ol 3.92E-01
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 26 of 48 Section 4.5- Combined 40CRF190 Report (cont.) 40CFR190 URANIUM FUEL CYCLE DOSE REPORT COMBINED MAXIMUM ANNUAL DOSE
SUMMARY
Year . . . . . . . . . . . . . . . . . . : 2015 From Unit . . . . . . . . . . . . . : 1 To Unit . . . . . . . . . . . . . . . : 2 Liquid Receptor ....... : 0 Liquid Receptor Coefficient Type ...... : Historical Gas Receptor .......... : 5-composite Crit. Receptor - IP Distance (meters) ..... : 0.00 Compass Point ......... : NA --- MAXIMUM PERIOD DOSE TO LIMIT (Any Organ) =================================== Dose Age Dose Limit Percent Period Group Organ (mrem) Period Limit of Limit Quarter 1 CHILD BONE 2.83E-03 Quarter 6.25E+OO 4.53E-02 Quarter 2 CHILD BONE 9.50E-02 Quarter 6.25E+OO 1.52E+OO Quarter 3 CHILD BONE 1.29E-01 Quarter 6.25E+OO 2.07E+OO Quarter 4 CHILD BONE 1.47E-02 Quarter 6.25E+OO 2.35E-01 Annual CHILD BONE 2.03E-01 Annual 2.50E+Ol 8.12E-01 --- MAXIMUM PERIOD DOSE TO LIMIT (Tot Body)) =================================== Dose Age Dose Limit Percent Period Group Organ (mrem) Period Limit of Limit Quarter 1 ADULT TBODY 5.25E-04 Quarter 6.25E+OO 8.40E-03 Quarter 2 CHILD TBODY 3.62E-03 Quarter 6.25E+OO 5.80E-02 Quarter 3 ADULT TBODY 5.64E-02 Quarter 6.25E+OO 9.03E-01 Quarter 4 ADULT TBODY 3.02E-03 Quarter 6.25E+OO 4.83E-02 Annual ADULT TBODY 6.23E-02 Annual 2.50E+Ol 2.49E-01
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 27of48 Section 5-Meteorological Data
- 1. Introduction The purpose of the meteorological program conducted at Zion Station site was to provide information sufficient to assess the local weather conditions and was used to determine the degree of atmospheric dispersion of airborne radioactive effluent from the station.
During the first quarter of2015, all fuel had been removed to the ISFSI location and continuous meteorological monitoring was no longer required. The previous 6 years of data from Jan. 1, 2009 to Dec. 31, 2014 was queried to generate the historic average wind rose and atmospheric dispersion parameters for future airborne effluents from Zion Station. The method of dose calculation that will be used going forward is ground level release and relevant information that is applicable to this method of effluent dose calculation has been included in this report. The meteorological tower that was used in calculation of these historical averages was 250 ft. in elevation and was instrumented at two levels. Wind speed and direction measured at 35 ft. and 250 ft. Ambient temperature was measured at 35 ft. Differential temperature, referenced to 35 ft. was measured at 250 ft. Dew point temperature was measured approximately ten feet from the tower at an elevation of 5 ft. Precipitation was measured by a rain gauge located on the roof of the meteorological shelter building. Joint frequency stability wind rose tables of wind direction, wind speed, and stability were routinely tabulated from hourly measurements during the six year period of this historical average. The six year historical average data tables are included in this report.
- 2. Summary For the six year period from Jan. 1 2009 to Dec. 31, 2014 considered in calculating the historical average, Zion Stations meteorological monitoring program generated 51,918 total hours of valid data out of a possible 52596 total hours, 678 total hours of data were lost representing a 98.71 %
data recovery rate. The stability wind rose tables included in this report have been.generated using the 35 ft. wind data with the 250-35 ft. differential temperature data.
- 3. Data Acquisition Information regarding Data Acquisitio?-, Data Analysis and instruments used can be found in the meteorological monitoring sections of_prior Zion Stations Annual Radioactive Environmental Monitoring Reports from 2009 to 2014.
- 4. The following two programs were used to calculate doses resulting from radioactive releases:
- a. XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations (NUREG/CR-2919)
The program is based on the theory that material released to the atmosphere will be normally distributed (Gaussian) about the plume centerline. A straight-line trajectory is assumed between the point of release and all receptors.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 28 of 48 The program implements the assumptions outlined in Section C of NRC Regulatory Guide 1.111. In evaluating routine releases from nuclear power plants, it primarily is designed to calculate annual relative effluent concentrations, X/Q values and annual average relative deposition, D/Q values. The historical average output from the XOQDOQ program from 2009-2014 was used to develop the input to the RETDAS program.
- b. RETDAS: Radiological Effluent Tracking and Dose Assessment Software.
RETDAS is a program written for the evaluation ofradiological impacts due to the release of radioactive material to the environment during normal operation ofreactors. The RETDAS code implements the radiological impact models ofNRC Regulatory Guide 1.109 Rev. 1, for atmospheric releases. The program is used to estimate the maximum individual doses at the maximally exposed location in the vicinity of the plant.
- 5. Detailed information regarding the meteorological maintenance and calibration information of the meteorological tower and instruments used during the historical average evaluation time period can be found in prior Zion Station Annual Radioactive Environmental Operating Reports from 2009 to 2014.
- 6. Stability Wind Rose Data The historical stability wind roses are given in Tables 4 through 8. For the year, winds measured at 35ft. most frequently came from the West (10.86%) and fell into the 3.6 to 7.5 mph wind speed class (34.94%). Calms (wind speeds at or below lmph were measured at 0.16% ofthe time and speeds greater than 24.5 mph were measured 0.09% of the time.
Stability based on the 250-35 ft. differential temperature most frequently fell into the neutral classification(3 9 .5 8%)
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 29of48 Section 5-Meteorological Data (cont.) Table 1 Wind Direction Classes Wind Direction Compass Direction the Wind is Coming From
- Class N 348.75° <WD:S 11.25° NNE 11.25° <WD:S 11.25° NE 33.75° <WD:S 33.75° ENE 56.25° <WD:S 56.25° E 78.75° <WD:S 78.75° ESE 101.25° <WD:S 101.25° SE 123.75° <WD:S 123.75° SSE 146.25° <WD:S 146.25° s 168.75° <WD:S 168.75° SSW 191.25° <WD:::; 191.25° SW 213.75° <WD:S 213.75° WSW 236.25° <WD:S 236.25° w 258.75° <WD:S 258.75° WNW 281.25° <WD:S 281.25° NW 303.75° <WD:S 303.75° NNW 326.25° <WD:S 348.75° Table 2 Wind Speed Classes Wind Speed Class Wind Speeds are in miles per hour (mph) 1 0.0 <WS:::; 0.7 2 0.7 <WS:S 3.5 3 3.5 <WS:S 7.5 4 7.5 <WS:S 12.5 5 12.5 <WS:S 18.5 6 18.5 <WS:S 24.5 7 24.5 <WS
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 30of48 Section 5-Meteorological Data (cont.) Table 3 Atmospheric Stability Classes Class Differential Temperature Differential Temperature Interval (in °C/l 00m)< 1) Interval (in Op OVer the 250-35 ft. interval)(2 ) A - Extremely Unstable ~T:S-1.9 ~T:S-2.3 B - Moderately Unstable -1.9 < ~T :'.S-1.7 -2.3 < ~ T :S -2.l C - Slightly Unstable -1.7 < ~T :'.S-1.5 -2.1 <~T:S-1.8 D -Neutral -1.5 < ~T :S -0.5 -1.8 < ~T :S-0.6 E - Slightly Stable -0.5<~T:S1.5 -0.6 < ~T :S 1.7 F - Moderately Stable 1.5 < ~T :S 4.0 1.7 < ~T :S 4.7 G - Extremely Stable 4.0 <~T 4.7<~T (1) From ANSI/ANS 2.5 (2) ANSI/ANS 2.5 intervals scaled for instrument heights on the Zion meteorological tower.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 31of48 Section 5-Meteorological Data (cont.) Table 4 Percent of time at each Wind Speed and Direction Period of Record: Jan.* 1, 2009 to Dec. 31, 2014 Stability Class: A - Extremely Unstable Elevation: Ground Level Release Wind Speed (mph) at 1Om Level Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0 0 0.031 0.156 0.254 0.04 0.002 0.48 NNE 0 0 0.176 0.98 0.287 0.006 0 1.45 NE 0 0.002 0.391 0.559 0.075 0.004 0 1.03 ENE 0 0.002 0.368 0.22 0.019 0.002 0 0.61 E 0 0.004 0.412 0.133 0.023 0 0 0.57 ESE 0 0.002 0.379 0.141 0 0 0 0.52 SE 0 0 0.272 0.219 0.01 0 0 0.5 SSE 0 0 0.05 0.249 0.035 0 0 0.33 s 0 0 0.01 0.046 0.019 0 0 0.08 SSW 0 0.002 0.015 0.068 0.144 0.01 0 0.24 SW 0 0.002 0.041 0.319 0.331 0.015 0.006 0.71 WSW 0 0 0.133 0.516 0.366 0.021 0.004 1.04 w 0 0 0.12 0.577 0.401 0.01 0 1.11 WNW 0 0 0.089 0.492 0.187 0.002 0 0.77 NW 0 0.006 0.068 0.404 0.112 0 0 0.59 NNW 0 0 0.039 0.058 0.037 0 0 0.13 Total: 0 0.019 2.591 5.137 2.3 0.11 0.012 10.17
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 32of48 Section 5-Meteorological Data (cont.) Table 4(cont.) Percent of time at each Wind Speed and Direction Period ofRecord: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: B - Moderately Unstable
*Elevation: Ground Level Release Wind Speed (mph) at 1Om Level Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6-18.5 18.6 - 24.5 >24.5 Total:
Direction N 0 0 0.039 0.102 0.119 0.015 0 0.28 NNE 0 0 0.112 0.196 0.058 0.004 0.002 0.37 NE 0 0.012 0.108 0.052 0.014 0.004 0 . 0.19 ENE 0 0.012 0.068 0.029 0.014 0 0 0.12 E 0 0.004 0.077 0.025 0.002 0 0 0.11 ESE 0 0.008 0.066 0.045 0 0 0 0.12 SE 0 0 0.097 0.041 0 0 0 0.14 SSE *o 0 0.06 0.164 0.025 0 0 0.25 s 0 0 0.01 0.052 0.008 0.002 0 0.07 SSW 0 0 0.013 0.058 0.098 0.008 0.002 0.18 SW 0 0.002 0.033 0.149 0.158 0.013 0.002 0.36 WSW 0 0 0.062 0.193 0.089 0.012 0.002 0.36 w 0 0.002 0.068 0.211 0.129 0.004 0 0.41 WNW 0 0 0.06 0.179 0.081 0.004 0 0.32 NW 0 0.004 0.049 0.191 0.052 0 0 0.29 NNW 0 0.002 0.021 0.054 0.027 0.002 0 0.11 Total: 0 0.044 0.938 i.739 0.872 0.067 0.008 3.67
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 33 of 48 Section 5-Meteorological Data (cont.) Table 4(cont.) Percent of time at each Wind Speed and Direction Period ofRecord: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: C - Slightly Unstable Elevation: Ground Level Release Wind Speed (mph) at lOm Level Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0 0.004 0.086 0.243 0.177 0.013 0.008 0.53 NNE 0 0.01 0.183 0.31 0.079 0.004 0 0.59 NE 0 0.023 0.15 0.102 0.031 0.01 0.006 0.32 ENE 0 0.023 0.1 0.044 0.021 0.012 0.002 0.2 E 0 0.01 0.146 0.025 0.018 0 0 0.2 ESE 0 0.019 0.115 0.037 0.014 0 0 0.18 SE 0 0.0.06 0.181 0.054 0.016 0 0 0.26 SSE 0 0.006 0.106 0.351 0.11 0.01 0 0.58 s 0 0.004 0.066 0.101 0.021 0 0 0.19 SSW 0 0.002 0.041 0.119 0.154 0.017 0.004 0.34 SW 0 0 0.094 0.244 0.189 0.023 0.006 0.56 WSW 0 0.004 0.11 0.252 0.139 0.01 0.002 0.52 w 0 0.008 0.133 0.277 0.165 0.008 0 0.59 WNW 0 0.008 0.127 0.308 0.079 0 0 0.52 NW 0 0.01 0.096 0.206 0.096 0 0 0.41 NNW 0 0.01 0.033 0.133 0.045 0.004 0 0.22 Total: 0 0.145 1.768 2.806 1.352 0.11 0.027 6.21
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 34of48 Section 5-Meteorological Data (cont.) Table 4(cont.) Percent of time at each Wind Speed and Direction Period of Record: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: D - Neutral Elevation: Ground Level Release Wind Speed (mph) at 1Om Level Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0 0.102 0.597 1.392 1.05 0.21 0.06 3.41 NNE 0 0.142 0.758 1.123 0.769 0.042 0.031 2.87 NE 0 0.161 0.528 0.57 0.405 0.046 0.025 1.74 ENE 0.001 0.137 0.348 0.346 0.347 0.092 0.008 1.28 E 0 0.121 0.392 0.303 0.353 0.094 0.013 1.28 ESE 0 0.148 0.489 0.289 0.163 0.035 0.002 1.13 SE 0 0.127 0.567 0.378 0.149 0.008 0 1.23 SSE 0 0.075 0.523 1.258 0.944 0.168 0.054 3.02 s 0 0.106 0.686 0.805 0.314 0.015 0 1.93 SSW 0 0.128 0.641 0.994 0.774 0.087 0.008 2.63 SW 0 0.152 0.612 1A43 1.003 0.108 0.015 3.33 WSW 0.001 0.138 0.849 1.327 0.659 0.042 0.002 3.02 w 0 0.146 1.1 1.766 0.961 0.029 0.002 4 WNW 0 0.169 1.139 1.402 0.52 0.012 0 3.24 NW 0 0.164 1 1.404 0.489 0.021 o. 3.08 NNW 0 0.098 0.655 L21 0.387 0.039 0.006 2.39 Total: 0.006 2.117 10.886 16.01 9.286 1.048 0.225 39.58
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 35of48 Section 5-Meteorological Data (cont.) Table 4(cont.) Percent of time at each Wind Speed and Direction Period of Record: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: E - Slightly Stable Elevation: Ground Level Release Wind Speed (mph) at 1Om Level Wind <1 1- 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24. Total Direction 3.5 5 N 0.005 0.302 0.672 0.53 0.173 0.021 0.012 1.72 NNE 0.004 0.245 0.564 0.447 0.058 0.013 0 1.33 NE 0.004 0.204 0.314 0.167 0.075 0.002 0 0.77 ENE 0.003 0.154 0.212 0.092 0.071 0.01 0 0.54 E 0.003 0.148 0.212 0.082 0.11 0.054 0.008 0.62 ESE 0.002 0.129 0.233 0.091 0.052 0.017 0 0.52 SE 0.003 0.163 0.456 0.273 0.079 0.004 0 0.98 SSE 0.004 0.192 .0.452 0.84 0.291 0.029 0.019 1.83 s 0.005 0.292 1.375 0.839 0.166 0.004 0 2.68 SSW 0.005 0.441 1.19 0.661 0.154 0.015 0 2.47 SW 0.006 0.324 0.855 0.607 0.183 0.013 0 1.99 WSW 0.004 0.277 1.008 0.503 0.069 0.002 0 1.86 w 0.005 0.353 1.349 0.649 0.117 0.006 0.002 2.48 WNW 0.005 0.38 1.136 0.599 0.05 0.002 0 2.17 NW 0.005 0.319 1.069 0.48 0.073 . 0 0 1.95 NNW 0.004 0.252 0.593 0.203 0.058 0 0 1.11 Total: 0.065 4.178 11.692 7.063 1.779 0.193 0.04 25.01
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 36of48 Section 5-Meteorological Data (cont.) Table 4(cont.) Percent of time at each Wind Speed and Direction Period of Record: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: F - Moderately Stable Elevation: Ground Level Release Wind Speed (mph) at lOm Level Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0.002 0.151 0.162 0.043 0 0 0 0.36 NNE 0.001 0.094 0.106 0.019 0 0 0 0.22 NE 0.001 0.083 0.086 0.025 0 0 0 0.2 ENE 0.001 0.076 0.064 0.024 0.014 0.002 0 0.18 E 0.001 0.079 0.077 0.027 0.01 0 0 0.19 ESE 0.001 0.077 0.111 0.045 0.016 0 0 0.25 SE 0.001 0.072 0.156 0.07 0.006 0 0 0.3 SSE 0.001 0.068 0.154 0.351 0.118 0.013 0 0.7 s 0.003 0.24 0.714 0.368 0.08 0.002 0 1.41 SSW 0.004 0.472 0.51 0.031 0.004 0 0 1.02 SW 0.005 0.454 0.334 0.023 0.002 0 0 0.82 WSW 0.005 0.495 0.368 0.015 0 0 0 0.88 w 0.005 0.416 0.637 0.015 0 0 0 1.07 WNW 0.003 0.307 0.458 0.008 0 0 0 0.78 NW 0.004 0.333 0.466 0.012 0 0 0 0.82 NNW 0.003 0.202 0.165 0.002 0.002 0 0 0.37 Total: 0.042 3.618 4.571 1.075 0.251 0.017 0 9.57
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 37of48 Section 5-Meteorological Data (cont.) Table 4( cont.) Percent of time at each Wind Speed and Direction Period of Record: Jan. 1, 2009 to Dec. 31, 2014 Stability Class: G - Extremely Stable Elevation: Ground Level Release Wind Speed (mph) at 1Om Level Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.5 12.6 - 18.5 18.6 - 24.5 >24.5 Total: Direction N 0.001 0.058 0.025 0 0 0 0 0.08 NNE 0.001 0.034 0.028 0 0 0 0 0.06 NE 0.001 0.03 0.01 0.008 0.002 0 0 0.05 ENE 0.001 0.029 0.018 0.008 0.012 0 0 0.07 E 0.001 0.033 0.029 0.02 0.008 0 0 0.09 ESE 0.001 0.039 0.058 0.021 0.004 0 0 0.12 SE 0.001 0.034 0.066 0.029 0.002 0 0 0.13 SSE 0.001 0.052 0.095 0.167 0.054 0 0 0.37 s 0.002 0.116 0.424 0.316 0.057 0 0 0.91 SSW 0.005 0.256 0.11 0.006 0 0 0 0.38 SW 0.005 0.258 0.189 0 0 0 0 0.45 WSW 0.006 0.481 0.316 0 0 0 0 0.8 w 0.008 0.586 0.609 0 0 0 0 1.2 WNW 0.007 0.353 0.401 0 0 0 0 0.76 NW 0.003 0.104. 0.108 0 0 0 0 0.22 NNW 0.003 0.07f 0.016 0 0 0 0 0.09 Total: 0.048 2.534 2.498 0.574 0.139 0 0 5.79
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 38of48 Section 5-Meteorological Data (cont.) Table 5 Percent Wind Direction by Stability Class Wind Stability Class Direction A B c D E F G Total N 0.48 0.28 0.53 3.4 1.72 0.36 0.08 6.86 NNE 1.45 0.37 0.59 2~9 1.33 0.22 0.06 6.89 NE 1.03 0.19 0.32 1.7 0.77 0.2 0.05 4.3 ENE 0.61 0.12 0.2 1.3 0.54 0.18 0.07 3 E 0.57 0.11 0.2 1.3 0.62 0.19 0.09 3.06 ESE 0.52 0.12 0.18 1.1 0.52 0.25 0.12 2.84 SE 0.5 0.14 0.26 1.2 0.98 0.3 0.13 3.54
'SSE 0.33 0.25 0.58 3.0 1.83 0.7 0.37 7.08 s 0.08 0.07 0.19 1.9 2.68 1.41 0.91 7.27 SSW 0.24 0.18 0.34. 2.6 2.47 1.02 0.38 ' 7.26 SW 0.71 0.36 0.56 3.3 1.99 0.82 0.45 8.22 WSW 1.04 0.36 0.52 3.02 1.86 0.88 0.8 8.48 w 1.11 0.41 0.59 4 2.48 1.07 1.2 10.86 WNW 0.77 0.32 0.52 3.24 2.17 0.78 0.76 8.56 NW 0.59 0.29 0.41 3.08 1.95 0.82 0.22 7.36 NNW 0.13 0.11 0.22 2.39 1.11 0.37 0.09 4.42 TOTAL 10.17 3.61 6.21 39.58 25.01 9.57 5.79 100
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 39of48 Section 5-Meteorological Data (cont.) Table 6 Percent Wind Direction by Wind Speed Wind Speed in mph Wind <1 1 - 3.5 3.6 - 7.5 7.6 - 12.6 - 18.6 - >24.5 Total: Direction 12.5 18.5 24.5 N 0.008 0.617 1.612 2.466 1.773 0.299 0.082 6.86 NNE 0.006 0.525 1.927 3.075 1.251 0.069 0.033 6.89
*NE 0.006 0.515 1.587 1.483 0.602 0.066 0.031 4.3 ENE 0.006 0.433 1.178 0.763 0.498 0.118 0.01 3 E 0.005 0.399 1.345 0.615 0.524 0.148 0.021 3.06 ESE 0.004 0.422 1.451 0.669 0.249 0.052 0.002 2.84 SE 0.005 0.402 1.795 1.064 0.262 0.012 0 3.54 SSE 0.006 0.393 1.44 3.38 1.577 0.22 0.073 7.08 s 0.01 0.758 3.285 2.527 0.665 0.023 0 7.27 SSW 0.014 1.301 2.52 1.937 1.328 0.137 0.014 7.26 SW 0.016 1.192 2.158 2.785 1.866 0.172 0.029 8.22 WSW 0.016 1.395 2.846 2.806 1.322 0.087 0.01 8.48 w 0.018 1.511 4.016 3.495 1.773 0.057 0.004 10.86 WNW 0.015 1.217 3.41 2.988 0.917 0.02 0 8.56 NW 0.012 0.94 2.856 2.697 0.822 0.021 0 7.36 NNW 0.01 0.635 1.522 1.66 0.556 0.045 0.006 4.42 Total 0.161 12.655 34.944 34.404 15.979 1.545 0.312 100
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 40 of 48 Section 5-Meteorological Data (cont.) Table 7 Percent Speed by Stability Class Speed Stability Class (mph) A B c D E F G Total
<1. 0 0 0 0.006 0.065 0.042 0.048 0.161 1 - 3.5 0.227 0.177 0.524 4.22 6.601 4.625 3.303 19.677 3.6 - 7.5 2.591 0.938 1.768 10.886 11.692 4.571 2.498 34.944 7.6 - 5.137 1.739 2.806 16.01 7.063 1.075 0.574 34.404 12.5 12.6 - 2.3 0.872 1.352 9.286 1.779 0.251 0.139 15.979 18.5 18.6 - 0.11 0.067 0.11 1.048 0.193 0.017 0 1.545 24.5 >24.5 0.012 0.008 0.027 0.225 0.04 0 0 0.312 Total: 10.17 3.67 6.21 39.58 25.01 9.57 5.79 100
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 41of48 Section 6 - Errata data There are no errata corrections from prior years reports in 2015
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 42 of 48 Section 7 - Changes to Zion Station Liquid Radwaste System Gaseous Effluent Treatment and Monitoring Systems. Summary: All of the changes to the Liquid Radwaste System were evaluated and were either system improvements, had the effect of lowering the dose to the public, or had no impact on dose to the public. There was no change to the Gaseous Effluent System. There were changes to the continuous liquid process monitoring system, the liquid effluent batch reiease system, and the associated liquid dilution flow system as follows:
- 1. Turbine Building Fire Sump continuous effluent monitor system: All potential radioactive inputs from the auxiliary building and fuel handling building were removed from the turbine building fire sump prior to removing OR-PR25. The potential inputs (spent fuel pool secondary cooling water quality system monitor blow down and air conditioning condensate drains from the aux building) were removed. An evaluation was performed to determine impact of minute quantities of historical radioactivity found in the turbine building, no activity could be detected greater than QDCM required lower limits of detection. With no potential for any future introduction of radioactive material into the fire sump and historically no detectable traces ofradioactive material from the turbine building floor drains, it was determine OR-PR25 was no longer required. There was no change in the flowpath or system structural piping. The fire sump discharges to the Waste Water Treatment Facility (WWTF) for processing. The compositor in this flowpath is sampled and analyzed weekly for radioactive material and a quarterly composite is sent to an offsite laboratory for analysis as was previously done.
- 2. Lake Release Tank liquid effluent batch release system: With the high concentration of Boron in the Spent Fuel Pool, the Boron concentration was the limiting component of batch releases. New calibrated low flowrate flowmeters had to be installed to ensure the flowrate of the discharge was within the calibrated range of the instruments. One flowmeter was installed for each Lake Release Tank, and an additional common discharge line flowmeter was installed as a backup. ORT-PR04 failed in February of 2015 and an entirely new liquid radwaste effluent monitor was designed with higher capabilities than the previously used monitor. This monitor was designed, constructed and tested and was found to outperform the previous liquid radiation monitor. The liquid radwaste discharge line which entered the Unit 2 discharge tunnel was extended to travel the entire length of the discharge tunnel, inside the tunnel, to allow final status survey of the discharge tunnel. The new location of the liquid effluent discharge is approximately 5 feet downstream of the dilution flow at the valve house area.
- 3. Dilution flow system: The service water system with a minimum flowrate of 2500 gpm.
was replaced with a new dilution flow pump with a minimum output of 10,000 gpm. This change was done to allow for a larger discharge flowrate while still maintaining the Boron concentration within Federal limits. All applicable changes have been evaluated in accordance with 10CFR 50.59 by ANSI qualified technical review personnel. Doses to members of the public have been evaluated during system design to ensure that the system continues to maintain doses to the public and workers are as low as reasonably attainable and well within limits. The Engineering Change packages (ECNs) for the system changes are included in Attachments 2-5.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 43of48 Section 8 - Correction Action for Inoperable Rad Monitor ORT-PR04 Liquid Effluent Radiation Monitor Inoperable for> 30 days Per ODCM 12.2.1.A.3:
- 3. Restore the inoperable effluent monitor to OPERABLE status within 30 days, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report the reasons as detailed in Section 12.7.2 and perform a review to detemiine course of action to restore to OPERABLE status.
ORT-PR04 became inoperable on 2/20/2015. Batch releases from the Lake Release Tanks continued in accordance with ODCM surveillance requirements listed in Table 12.2-1. During the period of inoperability, every attempt was made to locate and acquire repair parts for the radiation monitor. Due to the age of the equipment, it was not possible to locate the parts needed for repair. After review, an alternate plan ofrestoring the radiation monitor to operable status was determined. Identical detector elements were available from Ludlum instruments and on-hand Zion Station repair parts. The malfunctioning meter was removed from ORT-PR04 and an adapter interface was redesigned and tied into the alarm system. Additional features were available that were not present in the old system. The new monitor was tested and new efficiencies calculated. Calibration parameters and alarm setpoints were created. The work resulted in an overall improvement to the system and was verified to outperform the old monitor. Additionally, repair parts are available to the new system for future maintenance. ORT-PR04 was declared operable on 9/912015.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 44 of 48 Section 9 List of Changes to the ODCM In accordance with ODCM section 12.7.3.1.c. Many changes were made to the ODCM, including an interim change for post-fuel transfer operations and a finalized change for post-fuel transfer operations. A summarized list of the changes is presented here, along with a complete copy of the current ODCM.
- 1. Ch.12 Rev 29 Page Section Change Summary 12-i PDTS changed to QAPP Appendix B 12-iii TOC 12.4 Removed Dose-Noble Gases, I-131,1-133 12-3 12.1.26 Added definition for unventilated building releases 12-3 12.1.27 Removed line stating effects on noble gas and iodine.
12-4 Table 12.1-1 Removed duplicate notation on REMP program frequency limitation. 12-5 12.2.1.C Removed notation 'within the plant' to broaden bases to entire site. 12-6 Table* 12.2-1 Removed words (Boric Acid Tanks (BAT). Added note related to surveillance 1. 12-7 Table 12.2-1 Surveillance 1, removed limitation of 14 days for inoperable monitor 12-8 Table 12.2-2 Removed words Boric Acid Tanks (BAT) 12-9 12.2.2.C Removed words 'within the plant' to expand bases for entire site. Removed the word 'record' as printer function is unavailable. 12-11 Table 12.2-3 2R-PR49A(Channel 1) renamed to 2R-PR49. Removed 2R-PR49E (channel 5) entirely. Removed Fuel building monitoring section. (ORT-ARB, ORT-AR21, ORT-AR22, ORT-AR24) 12-12 Table 12.2-3 Surveillance 8: Removed 'operations' as chemistry personnel are qualified to perform this surveillance. Changed 'station review' to
'review' Changed 'panel' to 'equipment'. Surveillance 10: Deleted, Surveillance 11-3 deleted (covered by surveillance 8), Surveillance 12:
Deleted, Surveillance 13: Deleted 12-13 Table 12.2-4 2R-PR49A (Channel 1) renamed to 2R-PR49. Gas Activity Monitor 2R-PR49E (channel 5) deleted. Fuel Building Monitoring ORT-AR13,21,22,24 deleted. 12-14 Table 12.2-4 Changed control room alarm ammnciation occurs to 'alaims occur.' Deleted note (3) and (4) 12-15 12.3.1.A.l Deleted 'For dissolved or entrained noble gases sentence. 12-17 Table 12.3-1 Deleted page 12-18 Table 12.3-2 Deleted (Boric Acid Tank) verbiage. Deleted sampling and analysis requirements for dissolved and entrained noble gases. 12-24 12.4.1.A 12.4.1.A.l. Deleted. 12.4.1.A.2. Removed I-131, I-133. 12.4.1.C removed 3000 mrem/year to the skin noble gas dose calculation.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 45 of 48 Page Section Change Summary 12-25 Table 12.4-1 Moved Unit 2, FHB, AB sample requirement to combine with Unit 1 requirements. Added modular HEP A ventilation requirements (if applicable). Removed sampling and LLD limits for noble gas. 12-26 Table 12.4-1 Removed Unit 2, AB, FHB sample requirements and moved to Unit 1. Added note to explain sampling requirements for unventilated releases. Deleted note using old unventilated releases definition. 12-27 Table 12.4-1 Deleted notes: d, g, I, j 12-28 12.4.2 Deleted entire section. Dose-Noble Gas 12-29 12.4.2.C Deleted section- Bases of dose-noble Gas 12-30 12.4.3 Deleted 1-131, 1-133 12-32 12.4.4.A Deleted 1,2 mrad gamma, beta dose from noble gas. 12-37 Table 12.5-1 Changed 30 TLD stations to 31 TLD stations. Deleted ISFSI Indicator TLD locations. 12-39 Table 12.5-1 Added 5. Vegetation, sampling frequency and type of analysis 12-41 Table 12.5-2 Added Vegetation reporting activity concentration 12-42 Table 12.5-3 Added Vegetation LLD concentration. 12-45 12.5.2 A. Added a nearest garden census must be performed, C. Removed from Bases that a nearest garden census is not required. 12-49 12.7.2.1 Changed Tech Specs. to QAPP
- 12-51 12.7.3.1 Changed Tech Specs. to QAPP
- 2. Ch.12 Rev 30 Page Section Change Summary 12-6 Table 12.2-1 - Removed OR-PR25, changed Turbine Building Fire Sump to WWTF 12-7 Table 12.2-1 Deleted Surveillance 2 12-8 Table 12.2-2 Removed OR-PR25 changed Turbine Building Fire Sump to WWTF 12-18 Table 12.3-2 Changed Turbine Building Fire Sump to WWTF 12-20 Table 12.3-2 Changed Turbine Building Fire Sump to WWTF
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 46 of 48
- 3. ODCMRevO Page Section Change Summary - Post Fuel Transfer Operations re-write All All Consolidation of all Chapters and appendices into a single document.
Removal of Exelon generic information that is not applicable to Zion such as river flows and boiling water reactor requirements. Removal of requirements to maintain meteorological tower. Groundwater sampling surveillances added. Added gaseous effluent considerations for future open-air demolition. Remove requirement to monitor tritium from vent stack as the tritium in water volumes is released via liquid effluents. Aerial site photographs and maps have been updated to better illustrate TLD placement locations. 14 day limitation for OOS OR-PR04 had been changed to 30 days.
- 4. ODCMRev 1 Page Section Change Summary 35 10.1.2.1 Clarified description of Aux Building Vent Stack Effluent Monitor 39 10.4.1 Editorial change, clarified wording 39 10.4.2 Editorial change, clarified wording 59 Table 12.2-1 Added OFI-WD005A and OFI-WD006A low flow flowmeters 61 Table 12.2-2 Added surveillance and calibration requirements forOFI-WD005A and OFI-WD006A 64 Table 12.2-3 Claiified surveillance 8 for 1&2 LP-084 panel sample pump operation requirements.
69 Table 12.3-2 Added wording to clarify WWTF compositor sampling required only during release. 71 Table 12.3-2 Clarified section fto require WWTF only during system operation.
- 5. ODCMRev2 Page Section Change Summary 44 Table 11-1.1 Changed location of Air Sampler Z-03 from 0.25 miles sector R(NNW) to 0.2 miles sector B(NNE) 45 Table 11-1.2.b. Changed location ofTLD Z-03-1 and 2 from 0.25 miles sector R(NNW) to 0.2 miles sector B(NNE) 50 Figure 11-la Revised inner ring REMP map to correct sector labels. REMP sample location Z-03 moved. MET tower removed from map.
51 Figure 11-lb Re-added REMP outer ring sample locations. 57 12.2.1.A Added time frame of actions to take in inoperability of liquid effluent monitor referenced by section 12. 7.2
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 47of48 Page Section Change Summary 58 Table 12."2-l Added OFIT-SW54B flowmeter for high capacity dilution pump. 59 Table 12.2-1 Added verbage to indicate the surveillance applies to the applicable (High or Low flowrate) flowmeter. 60 Table 12.2-2 Added OFIT-SW54B 61 12.2.2.A Moved verbage for inoperable rad monitor reporting requirements reference by section 12. 7 .2 to this section from surveillance 8 requirement as it is more appropriately located in the Action section. 63 Table 12.2-3 Removed verbage for returning channel to operable status time requirements from surveillance 8 to relocate to section 12.2.2.A where it is more appropriately described. 97 12.7.2 Permanently Defueled Tech Spec change to QAPP App. B
- 6. ODCMRev3 Page Section Change Summary 58 Table 12.2-1 Added OFI-WD007 common discharge flowmeter 60 Table 12.2-2 Added surveillance for OFI-WD007
- 7. ODCMRev4 Page Section Change Summary 58 Table 12.2-1 Deleted SW54 and 54B service water flowmeters.
Added OPI-SWOlA and OPI-SWOl Pressure Gauge 59 Table 12.2-1 Added Surveillance 2 for Service Water Pressure gauge inoperability. 60 Table 12.2-2 Deleted SW54 and SW54B flowmeters. Added OPI-SWOlA and OPI-SWOl service water pressure gauge. Modified note 4 to indicate pressure gauge verification once per day and to estimate dilution flow once per day.
- 8. ODCMRev 5 Page Section Change Summary 56 Table 12.1-1 Deleted Four-Hourly notation for frequency of every 4 hours.
58 Table 12.2-1 Editorial correction OPI-SWOlA and OPI-SWOl are listed as Discharge pressure flow indicators. Note** added to clarify either pressure indication may be used to apply to minimum channels operable. Changed surveillance requirement to surveillance 3.
ZionSolutions LLC ZS-2016-0042: Attachment 1 Page 48of48 Page Section Change Summary 59 Table 12.2-1 Deleted Surveillance 2 for Service Water Pressure gauge. 60 Table 12.2-2 Editorial correction OFI-WD007 should be listed under common discharge Editorial correction OPI-SWOlA and OPI-SWOl are dilution flow pressure indicators. Modified note 4 to indicate pressure indicators shall be checked once per day and pump curves used for flow estimation during lake release tank releases. is a complete copy of Zion Stations Current ODCM.
ZionSolutions LLC ZS-2016-0042: Attachments ATTACHMENT 2 ECN# 400577 Extending liquid effluent discharge line through the discharge tunnel
Exhibit A NEP-OS-01 Revision 1 Engineering Change Notice (Part 1)
- ECN No.. 400577 ISSUANCE: ~FOR CONSTRUCTION 0 FOR COMMENT Page: of .)1:_ 1.11 ,
II (J' ...
.. D
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Station: ZlQN D Safety Related Design Change No. 400576 D Affected Unit: Unit 2 and Common 181 Non-Safety Related Project No. (ifappL): . D Regulatory Supp ID No. (ifeppL): Changes to a previously Approved ECN D System: WD Description of Design Change Request: Problem Statement Llquid Radioactive Waste System (LRWS) eftluent has been discharged into the Unit 2 Circulating Water System (CW) Discharge Tunnel on the west end of the tunnel. This release point has added water to the tunnel that is borated and will need to be diluted prior to release to the lake to meet the Illinois Environmental Protection Agency National PolJution Discharge Elimination System (NPDES) Permit. The NPDES permit limit for boron is 1 ppm. The current SFP water boron concentration is approximately 2,000 ppm. The current release point does not support the D&D schedule if the effluent discharge point remains on the west end of the tunnel dqe to having to process (dilute) the borated water released into the tunnel. There is approximately 720,000 gallons of this highly borated SFP water that would be released into the Unit 2 CW Discharge Tunnel. The milestone for isolating the Unit 2 CW Outlet Isolation valve is 1/1/16. Utilizing the current release point on the west end of the tunnel will not meet th~ schedule milestone. \. ) , I Resolution To minimize the further addition of LRWS effluent into the west end of the Unit 2 CW Discharge Tunnel the LRWS discharge hose will be extended to the east end of the tunnel. The installation of an extension hose onto the existing LRWS discharge hose from the west end of the tunnel and route it inside the tunnel to the east end of the tunnel. The extension hose will be routed* in the CW tunnel and the effluent release point will be placed past the dilution source near the Unit 2 CW Discharge Isolation Valve. This will prevent further input of borated water into the tunnel. This will also allow additional time to release the borated water currently in the tunnel to the environment that has not reached the Service Water (SW) dilution point on the west end of the tunnel. Technical Review Letter TR-002-2015 and 50.59 Screening SCR 2015-008 completes the engineering and licensing 1 justification for this ECN Reason for Design Change: . Change Biid action required (Provide ~soo for chaoge, specific actions required. attach supporting docwnew, es a,PJicable). Minimize future LRWS effluent from being released to the west end of the discharge tunnel. This will shorten the duration to remove the current LR.WS eftluent in the tunnel while still meeting the TB demo and tunnel FSS milestones. INTERFACING CQMMENTS by: Design Group or Discipline Name of Commenter (Printed) SignatiJrc of Commenter Date 'CorNC ElecL/I&C NIA Mechanical Structural NIA ) Others Others
tr Exhibit A NEP-08-01 Revision l ) Engineering Change Notice (Part 1) Others Prepared by: Lee DuBois oD~ Reviewed by: Approved by:. [;,'~.;:.=..;;~LJ=~-=-W--=- Date: 1-2.6-/J; Date: oate: All affected design documents revised by (date): v crified by: Date: - - - - - - ) ECNNo.: _....40=0=5~77~--- ) Design Change No.: 400576
/'Jc, PageNo.: 2 ofl4 ll '\-
Engineering Change Print Date: 02/02/2015 EC Number : 0000400577 000
'tatus/Date : REGISTER 01/12/2015 I 'l 1' t y .ac1 : ZIN Type/Sub-type: DCP MOD uowum llW1111111111IYU1111111111lllU1111111111 llffIIUU Bii1111 Page: J/ t( ~/;>
EC
Title:
LRWS RELEASE HOSE EXTENSION FROM 02 TB SW STANDPIPE TO 02 CW DISC HAR.GE VALVE HOUSE TYPE: ECN Mod Nbr : 400576 KWl: NS KW2: KW3: KW4: KWS: Master EC : N Work Group : Temporary : N out~ge : N Alert Group: CFILE Aprd Reqd Date: WO Required : Image Addr : Exp Insvc Date: Adv Wk Appvd: Alt Ref. : . Expires On : Auto-Advance: N Priority : Auto-Asbuild : N Caveat outst: Department : Discipline : Resp Engr : GARY XXINACTIVE-MACGREGOR Location : A£rected Documents L1st Sub-
'Fac .!m! ,In?! Document Sheet .QE! Rvw , ?£! .!!!£ 'itN DWGC M-31 N Y N Minor Rev: Maj or Rev: Updt Due:
Title:
DIAGRAM OF CIRCULATING WATER .PIPING . ,_ UNITS 1 & 2 ZIN DWGC M-49 1 N y N Minor Rev: Maj or Rev: Updt Due:
Title:
DIAGRAM OF WASTE DISPOSAL SYSTEM (LIQUID} MONITOR AND DISPOSAL SYSTEM
Exhibit A NEP-08-01 Revision 1 ECN No.: 400577
~~~~~~~~
Design Change No.: 400576 Page No.: 4 of M"u Back~Up Calculation Listing
,Pv (Part 2)
Calculation/Analysis No. Revision No. Description None
Part4 Construction Support Information Recommended Installation Steps I . Prepare for diving activities( i.e. Build Scaffold, Remove grating at air vent on U2 CW Discharge Valve House Vent Shaft, Remove instruments from air vent on U2 CW Discharge Valve House, safety plans, diver retrieval rig, pull rig, lay hose strings out, couple hoses, gang hoes, etc.)
- 2. Cut hole in U2 SW Stand Pipe per below photo. Field to determine size. Clean up/smooth off edges of hole to prevent damage to hose during pull evolution. Location is Unit 2 Turbine Building 592' Row/Colmnn F-9 Existing LRWS Cut large hole in stand pipe for hose pull and new LRWS and spare pull rope entry to CW tunnel
- 3. Have diver feed pull rope through the tunnel. Diver will most likely enter the tunnel on the east end of the Unit 2 CW Discharge Tunnel into the air relief shaft.
- 4. Pull hose gang through the tunnel. Reference Mark ups on M-101, M-49 Sht 1 and M-31. Divers may need to assist in pull.
5.Configure and tie off hoses.
- 6. For LRWS discharge hose add test ends and perform a hydro or pressure decay test at "'100 psi to verify no leaks.
7.ln TB connect LRWS discharge 3" hose to existing 2" LRWS hose. EC 400577 Prepared By: _-L __J).__,~._..._ _ Da~: I ~u~.-1f' Paie 5 of,)¥ I.
Final Route for LR\'1/S discharge hose I ICW Tunnel Section View Looking South I A !VVest
;Recommended End point for 6 hose, 3 RecirCTl
,...... -i~suction hose. sample hoses an~~E_~pe /
Approximate/Recommended End points t-*- -----::==:::::io--~--_, Tunnel Entry *1 for sample hoses 1/4. 1/2 & 314 through f' . /point for LWRS
.....,_____......,..........______""'----itunnel m---'----:;.ijjir=:::::i......~=:+::::::=:::::z:~--L----------*-.--..----___., \
! '-~":.,umNt .::J!1!2H-H'3!1fa1E+-+--n;~'w Discharge Hose I iand spare pull I
+-+ll+-ii£,~1 lrope (SW stand {
'-~~==:=::=::~~~=~::;;.~:;;t~~J:tqj::c;t~:(i-A-_.t=::j~p1~ pe_)~--~
l mus! be a Initial route for minimum vf LRWS l 5 ft east of SW dilut1011 rrt~J.,..~kJ::: fl.r-_'r discharge flow into the r--fl,~ ~ Hose tunnel: discharge pipe EC 400577 Prepared By: ~ J;/6,. Date: {-~-I'( Page 6 of%11 '('~'-
u-* recirc 1ine, 3' Existing 315" access manway J 4~~---1fEast I West reci rc.:suc:tion hne. sample lines and pipe to CW tunnel future pull rope ioc.ation
---- 1\ "GRATINC&
Futu1e LRWS ffscharge Hose route after access window is cut
£EL. C.OO'*O*
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- fl C\".' pipe downstream of CW Discharge tso!atio11 Valve and Valve is closed. Must be a
)£ ~ ' minimum of 5 ft past dilution point SEE_..... ..
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- Page 7 of rL
*1M-1O1 Mark Up for instalfation clarity .. ,L
, Initial LWRS Discharge Hose rou e. Up through Pre~ared by: ~~?; Date: 1-2'-1~ CW Acess manway and then back down to open Reviewed B: ~ - ~~ ~fLl/L,o/s CW d"scharge vaive. Secured at top ~o it can be retrieved at a later date for future re-routing . Must Hose Gang route be 5 ft past dilution point r
~ 112. Date: /-z-C -ts*' Reviewed By: _ _ _ _ _ _ Date: _ __
Page 7 ofJZ'j I rv EC 400577 Prepared By:
Bill OfMaterial Job Name: _LRWS Hose Extension in U2 CW Tunnel Requestor~ _Stan Mastalerz/ Lee buBois~------ Work Order#: _01801664 Purchase Order#: _ _ _ _ _ __
~~ ~~~ .
Activity#: EC#: 400576 I 400577 Item Description Size Item# Vendor Substitute YIN QTY PRICE COMMENTS Hose Recirculation, &' 75 psi minimum working pressure. 6" Spiraflex Red Goodyear N 500 May come in shorter Goodyear Spiratlex Red Medium Duty Medium Duty ft lengths, typically 300 ft, this is acceptable. min Hose LRWS Discharge, 3" 100 psi minimum working 3" Versiflo 150 Goodyear N 600 May come in shorter pressure and vacuum.rated. GoodyearVersiflo 150 ft lengths, typically 100 ft, this is acceptable total Hose contingency, 3", 100 psi minimum working pressure 3" Versiflo 150 Goodyear N 600 May come in shorter and vacuum rated. Goodyear Versiflo 150 ft lengths, typically 100 ft, this is acceptable total Hose Sample #1, 1-114", 100 psi minimum working pressure 1-114" Versiflo 150 Goodyear N 450 May come in shorter and vacuum rated, Goodyear Versiflo 150 ft lengths, typically 100 ft, this is acceptable min Hose Sample #2, 1-1/4", 100 psiminimum working pressure 1-1/4" Versiflo 150 Goodyear N 300 .May come in shorter and vacuum rated. Goodyear Versiflo 150 ft lengths, typically 100 ft, this is acceptable min Hose Sample #3, 1-114", 100 psi minimum working pressure 1-114" Versiflo 150 Goodyear N 150 May come in shorter and vacuum rated, GoodyearVersiflo 150 ft lengths, typically 100 ft, this is acceptable min Hose couplings, 6", shank to shank, Brass, Steel or SST 75 6" Mcmaste y 2 psi minimum working pressure. r Carr, Goodyear or similar Hose couplings, 3", shank to shank, Brass, steel or SST 100 53605K15 or . Mcmaste y 10 psi minimum Working pressure 53805K67 or r Carr or
~:~K.3 6 0~. similar Hose Coupling, shank to shank, 1-1/4" Brass, steel or SST 1-1/4" 53605Kll or Mcmaste Y 8 100 psi minimum working pressure 53605K64 or r~rr or 53605K~r(? i / 7* / ,,
ac 400577 Prq>ared By: L, J;Vi,_ Date: f- Z. <>16' teage 8 of~ I . I 1'~ '-'
-- 53605K33'or' sitJtllar similar Cam and groove coupling Plug with shank connection. type #3x 52155K146 or Mcmaste y 1 E. #3 coupling by 2" hose. Brass, Steel or SST 100 psi 2" Similar r Carr or minimum working pressure similar Cam and groove hose coupling type C sockets with shank #3x 52155K37 or Mcmaste y 1 connection 3" hose by #3 coupling with locking levers. 3" 53015K37 or r Carr or Brass, steel or SST. 100 psi minimum. working pressure similar similar Low profile Hose Band Clamps/center punch hose clamps %"x 5655K29 or McMaster y 100 May come in multiple %" x 7"(ntln inside diameter) Galvanized carbon steel or 7" 5655K49or Carr or piece pieces per vendor PN SST 5655K28 or siniilar smin 5655K48 or similar Heavy Duty Ratchet Action Banding tool 14 5657K.42 or McMaster y similar Carr or similar PullRope, Low-Stretch Polyester, Minimum strength 4000 :}"or 3789T19 or ., McMaster y 600 lbs. 3/4" Extra-Strength Double Braid or 1" Lightweight 1" 8878T77 or Carr or ft Blend or similar similar similar min Contingency Pull Rope, Low-Stretch Polyester Minimum t" or 3789T19 or M;cMaster 600 ..
strength 4000 lbs. %" Extra-Strength Double Braid or 1" 1" 8878!77 or Carr or ft Lightweight Blend or similar similar similar min Special tooling. Capstan Rope Winch/puller. May be able to 1500 v* 2 rent. Not permanent part of Installation. As determined by lb pull D&D and dive contractor. min Misc pWl hardware (i.e. hose/cable support grips; Kellem grips, shackles, rope pulleys, etc.). Not part of permanent installation. Not permanent part of installation. As determined by D&D and dive contractor.
- .c 400577 Prepared By: nate: 1-zwt(
- age 9 of 1 2"'
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- repared By ~ oc9a Date 1- 2&-1~ M-31 (C-9)
Revievved By -:hf.~ . cf~ Date tJ;/21/J.a/s EC400577 P~eparedBy: ~ iJ../2.;v Date: /-U.* J? ReviewedBy: _ _ _ _ _ Date: Page}.fof)Z, v ---
/b I1 ~
3.," Hose from LRWS
.................ii M-49 Sh.t . 1 (E-10) f 1/T
- 3/4~ RED.
Hose Gang 6 .. ~ 3"' and three 1-11.2** for recirculating., flushing/ disch.arge suction and
* *s ampling respect1vely _
...... sample hoses 114, 112 and 3f4 down tunnel 12 EC*N 400577 ~~~ ~
/.:.t. YI
, ~DCMI I
*-31 Mark Up ~.........
repared y
~ f)ftu-Date: 1-2G-is- Hose en*d at Re~wed 1 y: dilution point r Pt tzr:J-fi,._,
Date: ~~21/-?'/s-EC4005*~~~_.......!!!!il!f"lll!I~----__. Page of.JZ: v-i/ /{ ~
January 26, 2015 In reply refer to CZE-15-001 To: Anthony Orawiec
Subject:
Zion Station, Unit 2 and Common Exempt Change No. 400576 Liquid Radioactive Waste System (LRWS) Release Hose Extension from Unit 2 (U2) Turbine Building(TB) Service Water(SW) Standpipe to U2 Circulating Water(CW) Discharge Valve House The Engineering Department has revi~wed the subject Exempt Change in accordance with ZAP 510-02C and the applicable Zion Solution Quality Requirements. The applicable Design Input Requirements are discussed in this letter. System Code: WO, SW, CW LRWS effluent has been discharged into the Unit 2 (U2) CW Discharge Tunnel on the West end of the tunnel. The discharged effluent has boron in* it. The Environmental Protection Agency National 'I ) Pollutant _Discharge Elimination System (NPDES) Permit has a limit of l part per million (PPM) of boron for lake discharge. The current LRWS effluent release point on the west end of the U2 CW has added borated water to the U2 CW Discharge Tunnel that will need to be diluted prior to release to the lake. The current release point does not support the D&O schedule if the effluent discharge point remains on the west end of the tunnel due to the increased time for releasing borated water in the tunnel. The milestone for isolating the U2 CW Discharge Tunnel outlet Isolation valve is 1/1/2016.* Resofutlon To minimize the further addition of LRWS effluent into the Unit 2 CW Discharge Tunnel extend the LRWS effluent discharge hose from the west end of the tunnel and route it to the east end of the tunnel. The hose extension will be routed in the U2 CW Discharge Tunnel and the effluent release point will be placed past the dilution source near the U2 CW Discharge Isolation Valve. This will. min.imize future LRWS effluent from being released to the U2 CW Discharge Tunnel. This will shorten the duration to remove the current LRWS effluent in the tunnel while still meeting the TB demo and tunnel FSS milestones. Description of Change: This exempt change will extend the LRWS effluent discharge hose from the west end of the U2 CW
, Discharge Tunnel to the east end of the U2 CW Discharge Tunnel. This will place the LRWS release location past the dilution source flow therefore reducing the probability LRWS effluent from entering
the U2 CW Discharge Tunnel. Contingency hoses and pull rope will also be Installed for future use if required. Exempt Change Design Packace: The design for this exempt change will be contained in ECN 400577 and is issued "F~r Construction" by this letter. 10 CFR 50.59 Evaluation I Decommissioning Impact Evaluation: A 10 CFR 50.59 Evaluation was performed in accordance with ZAP 100-06 and is being transmitted along with this letter. This activity can be implemented without prior NRC approval. A Decommissioning Impact Evaluation was performed; and it concluded that the proposed activity is not restricted by 10 CFR 50.82. DSAR I ODCM Impact Review: DSAR Chapters 1 through 6 was reviewed for this exempt change. There is no impact on the DSAR. ODCM Chapters 10 and 12 were reviewed for this exempt change .. There is no impact on the ODCM.
) ""Applicable Codes and Standards:
This exempt change shall be installed in accordance with Zion Specification X-3646, which is the general work specification for mechanical work; as well as applicable site, vendor, and corporate procedures. Installation requirements identified in ECN 400577 supersede Specification X-3646 specifications. Alternate materials and standards are allowed per ECN 400577 and are justified in TR-002-2015 Installation Schedule I Outage Requirements: Installation of this exempt change does NOT require an outage; and therefore will be scheduled via the site work schedule process. Technical Specification Changes: The existing Technical Specifications do not require revisions as a result of this exempt change. ODCM Changes: The existing ODCM does not require revisions as a result of this exempt change. )
ALARA I Fire Protection Review: This exempt change is not being performed In a radiological area. An RWP will not be required for this exempt change. There are minimal additional combustibles being added. The combustibles being added are mainly located under water. As such there is no impact on the Fire Protection Report. Impact of Pending Modifications or Temporary Alterations: There are no other pending design changes that are impacted by this installation. There are no pending changes against affected design drawings that have an impact on this activity. Other Considerations j Engineering considerations are documented in TR-002-2015 and are found to be acceptable. Construction Drawings; } Construction is authorized to proceed in accordance with ECN 400577. Identification of the Installer: D & o will perform this exempt change. D&O will have to contract for diving services to perform diving activities. Operating Procedures: No changes are required to existing Operating Procedures. No new Operation Procedures are required. Training Requirements: None Testing Requirements: A functional leak check should be performed to verify system tightness for portions of the new hoses outside of the U2 CW Discharge Tunnel. Th!s may be completed with a leak check or a hydro. A hydro ) pressure of 100 psi is acceptable.
Operating Requirements: None Technical Review: The LRWS and WD system is Important to the Defueled Condition (ITOC)j therefore this modification is subject to a Technical Review in accordance with the requirements ofZAP 500-08 and the ZNPS A Technical Review was completed under TR-002-2015 and found to be acceptable. If there are any questions or comments regarding this Exempt Change, please contact Lee DuBois at 224-789-4065. Prepared By: Date: }. (.~ Lee DuBois D & D Project Engineering Approved By:~/,/) £f?;f.. Date: . ~@&t~ Donald F. Roth D & D Engineering Supervisor cc: MAL ECN 50.59 Central File 1 1 1 Tara Pratt original original original Work Planning 2 2 2 Tony Orawiec 1 1 1 .J
TECHNICAL REVIEW LITTER TR-002-2015 To: Anthony Orawiec Decommissioning Plant Manager Zion Station
Subject:
Extending Liquid Radioactive Waste System (LRWS) discharge hose from west end of Unit 2 (U2) CW Discharge Tunnel to the east end of the U2 CW Discharge Tunnel. The purpose of this letter is to document the Technical Review of the Desfgn Change Package for Exempt Change EC# 400576 and associated ECN 400577. Summary: This Exempt Change provides the details for the following:
- 1. Extends the existing LRWS discharge 2" hose* with a 3" hose extension from west end of the Unit 2 CW Discharge Tunnel to the East end of the U2 CW Discharge Tunnel.
- 2. Install contingency hoses for sampling and recirculation of the U2 CW Discharge Tunnel. A 6" hose will be installed as a recirculation hose. Install a 3" hose that could be used as a
*flush/recirculation or west end suction release hose. Install three 1-1/4" hoses that could be used to sample the tunnel.
- 3. Install a contingency pulling rope if additional hoses need to be pulled into the tunnel in the future.
There are multiple design considerations not covered under other modification documentation. Mechanical Design Considerations The design flow rate needs to be determined as well as the hose length and size. Hose lengths-324 ft horizontal Center line (CL) of outlet water box to CW discharge house Ref M-100 27 ft horizontal CL outlet water box to west standpipe. Ref 8-100 110 Ft vertical down then vertical up, 2 x (592' TB elev -537' tunnel bottom) Ref M-101 so ft additional hose to allow routing out of cw discharge house manway into cw discharge valve vault (contingency length) 200 ft from Unit 1 LRWS pump discharge to Ul LRWS pump discharge to west CW stand pipe. Estimate based on M-100 600 ft (new hose) 800 ft (for hose sizing evaluation purposes) Page 1 of7
TECHNICAL REVIEW LETTER TR-002-2015 Flow rate sizing for LRWS The allowable release rate determines flow rates. Maximum Flow Rate The boron release rate is much lower than the radioactivity release rate so it is the driving factor. The allowable release rate is det~rmined via lppm boron at the outfall. Unit 1 cavity water is at "'356 ppm 12-18-14 analysis value SFP boron concentration is> 2000 ppm Assume 12,QOO gpm Service Water (SW) Dilution Pump Release rate can be up to 34 gpm of borated water.. Size hose for 35 gpm Hose Sizing for LRWS Discharge At 35 gpm the LRWS lake discharge pump has 110 ft of head or 47 psig Hose losses at 35 gpm per 100 ft of hose (Goodyear tables) 2" 1.18 psi 2. 7 ft
'e-1/2" 0.40 psi 0.9 ft
. ) 3'~ 0.17 psi 0.4 ft Loss at 800 ft of hose for only the hose at 35 gpm 2". 22 ft 2-1/2" 7 ft 3" 3 ft To account for other fittings (valves, flow meters, pipe fittings) conservatively double the pressure loss from the hose 2" 44 ft 2-1/2" 14 ft 3" 6 ft Recommend using 3" hose. Reason is for contingency we may need to re-circulate the tunnel; a 3" hose will allow faster recirculation. Hose pressure rating for LRWS Discharge This hose will be in the tunnel and protected by the tunnel from personn~I, equipment and incidental contact. The rating on the hose needs to be a minimum of the pump dead head rating for industrial safety concerns just in case the hose is blocked or crimped. Pump dead head rating is 110 ft. The static head from the top of the tank to the bottom of the tunnel is 80 ft (top of tank conservatively assume 617' -537' bottom of drained tunnel M-101). Total static. head is 190 ft or 83 psi. Hoses typically have a Page 2of7
TECHNICAL REVIEW LETTER
.TR-002-2015 )
burst pressure of 3 times the operating pressure rating (Ref Goodyear www site). Recommen~ a hose rating of 100 psig minimu~. Hoses currently being used on site per walkdown: Manufacturer Model Pressure(PSl)(3") Vacuum(in HG) Weight/ft(3") Goodyear Con-Ag 100 N/A 1.76 Goodyear Versiflo 150 29 1.44 Goodyear Plicord 150 N/A 1.37 Goodyear Gorilla 500 (2" max .size) N/A 1.22 Utilize Goodyear VersiFlo. This hose meets the pressure rating. This hose also meets a vacuum rating as a contingency to re-purpose the ho~e to re-circulate and/or dilute the CW tunnel in the future. All fittings need to be rated for a minimum of 100 psi working pressure.
- Contingency hoses An additional 3" Versiflo contingency hose should be pulled into the tunnel. This hose may be used for dilution source from the east side of the site via the SW dilution pump tap valve~ The current SW dilution pump could be used to supply water via this hose. This will allow the removal of water from
) west to east wheri a LRWS discharge in not in progress. The hose coulcf also be used for recirculation, sampling or as a discharge source on the west end of the tunnel if they wanted to place a pump on the east side of the site allowing less interferences for 0th.er D&D activities. If using this hose from the existing SW dilution pump then a flow meter shall be installed to limit the flow to allowed discharge rates per the LWRS. Because this hose could be used in a pump discharge or suction condition the Versiflo hose is recommended. As a contingency for future tunnel recirculation install a. 611 hose. The hose will only be used for recirculation so the recommended hose is a Goodyear Spiraflex Red (medium duty). This hose is rated for 100 psi working pressure. Referencing Goodyear hose pressure loss table a 6" hose has a head loss of 0.79 psi per 100 ft at 500 gpm. For a conservative 600 ft hose run in the tunnel the loss would be approximately 5 psi or 11 ft of head. Based on review of typical 4-6" de-watering pumps (i.e. Flygt) we should be able to obtain a minimum of 500 gpm recirculation. The tunnel conservatively has 800,000 gallons of holding capacity; at 500 gpm the t~nnel turn over time is approximately 27 hours. The hose fittings need to be rated for a minimum of SO psi. As a contingency for water sampling at intermediate tunnel locations; utilize 1-1/4" Goodyear Versiflo hose because it has a vacuum rating. The vacuum rating will allow it to be utilized on sample pump suction(s). As a sampling contingency up to 3 sample hoses at approximately 25%, 50% and 75% down the tunnel length. A minimum of 1 sample hose at approximately 50% down the tunnel should be run. Do to the potential, to process water out of the tunnel after access to the TB is not available the sample hoses should be pulled above grade on the east end of the tunnel. Page 3of 7
TECHNICAL REVIEW LITTER TR-002-2015 As a contingency an extra pull rope should also be routed through the tunnel and staged for future use. The pull ropes should be tied off on each end for future access. In conclusion, the proposed Exempt Change does not affect the design or the design function of the WO System; as well, the proposed Exempt Change does not affect the ability of the LRWS to perform that design function. Prepared By: -: :Le~e:. :D=u=B=o=is=- ~-----~_..:;.~-~-*~---
...... Date: 01/26/2015 Required Review Disciplines:~ 01~ 9 Engineering Supervisor
/-U:-15 Discipline Date
) Discipline I Concur and Approve: _c4_.,..-=+- E__________ 7 _ Deco~g Plant Manager Distribution: Decommissioning Plant Manager Operations Supervisor Engineering Supervisor SRC Coordinator Master File ) Page 4of7
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TECHNICAL REVIEW LITTER TR--002-2015 I
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ZAP-100-06 Revision 25 Information Use ATTACHMENT E: 50.59 APPLICABILITY REVIEW FORM Activity/Document Number: EC 400576 and ECN 400577 Revision Number: o Address the questions below for all aspects of the Activity. If the answer Is yes for any portion of the Activity, apply the Identified process(es) to that portion of the Activity. Note that it is not unusual to have more than on1:1 process apply to a given ACtivity. See Section 4 of the Resource Manual (RM) for additional guidance. I. Does the proposed Activity involve a change:
- 1. Technical Specifications or Operating License {10CFR50.90)? . X NO YES See Section 4.2.1.1 of the RM
- 2. Conditions of License Quality Assurance program (10CFR50.54(a})? X NO YES Security Plan (10CFR50.54(p))? )(NO
- YES See Section 4.2.1.2 of the RM
_x_ NO
- YES Emergency Plan (10CFR50.54(q))? -
- 3.
- Specific Exemptions (10CFR50.12)? _X_NO YES See Section 42.1.5 of the RM
- 4. Radiation Protection Program (1 OCFR20)? . . x_ NO - YES See Section 4.2.1.6 of the RM *
- 5. Fire Protection Program (applicable UFSAR or operating license _X_NO YES See Section 4.2.1. 7 of the RM condition)? -
- 6. Programs controlled by the Operating License or the ,Technical Specifications (such as the ODCM). _x_ NO - YES See Section 4.2~ 1.7 of the RM
- 7. Environmental Protection Program _X_NO YES See Section 4.2.1.7 of the RM
- a. Other programs controlled by other regulations. _X_NO YES See Section 4.2.1 of the RM
)
II. Does the proposed Activity involve maintenance which restores SSCs to their original condition or involve a temporary alteration supporting . maintenance that will be in effect during at-power operations for 90 days _X_NO - YES See Section 4.2.2 of the RM or less? l Ill. Does the proposed Activity involve a change to the:
- 1. UFSAR (including documents incorporated by reference) that is excluded from the requirement to perfonn a 50.59 Review by _x_ NO - YES See Section 4.2.3 of the RM NEI 96-07 or NEI 98-03?
- 2. Managerial or administrative procedures governing the conduct of _X_NO YES See Section 4.2.4 of the RM facility operations -
- 3. Procedures for performing maintenance activities (subject to 10 CFR
_X..;.NO YES See Section 4~2.4 of the RM 50.65(a)(4 ))? -
- 4. Regulatory commitment not covered by another regulation based _x_ NO - YES See Section 4.2.3/4.2.4 of the change process (see NEI 99-04)? RM IV. Does the proposed Activity involve a change to the Independent Spent _X_NO
- YES See Section 4.2.6 of the RM Fuel Storage Installation (ISFSI) (su.bject to control by 10 CFR 72.48) -
- v. Does the proposed Activity Involve a change to the Packaging & _x_ NO YES -
Transportation of Radioactive Material? (subject to oontrol by 10CFR71) - Vi. I s the proposed activity a Decommissioning Activity that does NOT _X_NO YES require a 50.59 Scref:)nlng, as described in Attachment 1 of ZS*EG-100? - Check one of the following: o If all aspects of the Activity are controlled by one or more of the above processes, then a 50.59 Screening -is not required and the Activity may be Implemented In accordance with its governing procedure. X ff any oortion of the Activity is not controlled by one or more of the above processes, then process a 50.59 Screening for the portion not covered by any of the above processes. The remaining portion of the activity should
. be implemented in accordance with its governing procedure.
his Exempt Change affects systems discussed in the DSAR that are Important to Defueled Condition.srgnoff: _// ~ 50.59 Screen& 50.59 Ewfualor: ?,;"",.,._ r: ~"'-"'"~ Sign: /<-,,./.~~' d/1 ..t11.L*/'$ (Circle (Print name) (Signature)
ZAP-100-06 Revision 25 Information Use ATTACHMENT D: 50.59 REVIEW COVERSHEET FORM* Station: Zion Activity/Document Number: EC 400576 and associated ECN 400577 Revision Number: O
Title:
Liquid Radioactive Waste System CLRWS) effluent dlscharae hose extension in Unit 2 Circulatfng Water Discharge Tunnel. NOTE: For 50.59 Evaluations, infonnation on this form will provide the basis for preparing the blennlal summary report submitted to the NRC in accordance with the requirements Of-10 CFR 50.59{d)(2). Description of Activity: (Provide a brief, concise description of what the proposed activity involves.) To minimize the further addition of LRWS effluent into the Unit 2 CW Discharge Tunnel extend the LRWS effluent discharge hose from the west end of the tunnel and route it to the east end
)f the tunnel. The hose extension will be routed in the U2 CW Discharge Tunnel and the ~ffluent release* point will be placed past the dilution source near the U2 CW Discharge solation Valve. This will minimize future LRWS effluent from ~eing released to the U2 CW Jischarge Tunnel. This will shorten the duration to remove the curr~iit LRWS effluent in the
.unnel while still meeting the TB demo and tunnel FSS milestones. u *
)on for Activity:
- _ .;USS why the proposed activity is being performed.)
mnimize LRWS effluent being deposited in the U2 CW Discharge Tunnel. ffect of Activity:
)iscuss how the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.)
his activity does not change any descriptions in the DSAR and ODCM. llmmary of Conclusion for the Activity's 50.59 Review: irovide justification for the conclusion, including sufficient detail to recognize and understand the essential:arguments leading the conclusion. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment
~quest, as applicable, is. not required.)
50.59 Screening will be' required because the LRWS is described in the DSAR. tachments: tach all 50.59 Reviewforms completed, as appropriate. OTE: if both a Screening and Evaluation are completed, no Screening No. is required.) rms Attached: (Check all that apply.) Appllcablfity Review x 50.59 Screening 50.59 Screening No. 2015-008 Rev. 0 I
.J 50.59 Evaluation 50.59 Evaluation No. Rev*
ZAP-100-06 Revision 25 Information Use ATTACHME1'1T F: 50.59 SCREENING FORM 50.59 Screening No. ____2=0....1__s..... -oo~s______ Rev. No. __.o__ Activity/Document Number: Exempt Change EC 400576 and ECN 400577 Revision Number:____o~__,_
- r. . 50.59 Screening Questions (Check correct response and provide separate written response providing the basis for the answer to each question) (See Section 5 of the Resource Manual (RM) for additional guidance):
- 1. Does the proposed Activity involve a change to an SSC that adversely affects an UFSAR YES _)(_NO, described design function? (See Section 5.2.2.1 of the RM)
The relocation LRWS discharge point Is within the licensing basis design function as described In the DSAR section 4.5.2 and Figure 4-1 The ODCM Section 10.2 does not describe where within the CW tunnel the LRWS discharges. The ODCM refers to the DSAR. The LRWS Is not discussed In the Technlcal Sj,eclflcatlons: Design Basis (LRWS excerpt from DSAR 4.5.2) The Liquid Waste Systems are designed to coilect, store, process, monitor, and dispose of liquid radioactive waste from the statjon. The principle design criteria. ) for the Liquid Waste Systems are as follows:
- 1. Ensure that the quantities of radioactive waste discharged from the plant during decommissioning are as low as practicable and, in any event, well within the allowable concentration limits; and
- 2. Limit the inadvertent release of radioactive material from the plant so that the resulting radiation exposure to the public is as low as practicable and, in any event, well within the allowable concentration limits.
The allowable concentration limits described above are defined as 1Otimes 10CFR20 limits for batch releases from the Lake Release Tanks (Boric Acid Tanks)..
- 2. Does the proposed Activity involve a change to a procedure that adversely affects how UFSAR YES _X_NO described SSC design functions are performed or controlled? (See Section 5.2.2.2 of the RM)
There are no procedures that are affected by the re-route of the hoses.
- 3. Does the proposed Activity involve an adverse change to an element of a UFSAR described _)'ES _X_NO evaluation methodology, or use of an alternative evaluation methodology, that is used in establishing the design bases or used in the safety analyses? (See Section 5.2.2.3 of the RM)
DSAR Section 4.5.2 does not Identify any methods of evaluation. Chapter 5 accidents do not Identify a LRWS release or spill as an accident that is evaluated. No methods of evaluation are changed.
ZAP-100-06 Revision 25
*Information Use
- 4. Does the proposed Activity involve a test or experiment not described in the UFSAR, where an YES _}(_NO SSC is utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is Inconsistent with analyses or descriptions In the UFSAR? (See Section 5.2.2.4 of the RM)
The proposed activity does not Involve an experiment or a test.
- 5. Does the proposed Activity require a change in the Technical Specifications or Operating License? YES _}(_NO (See Section 5.2.2.5 of the RM)
This proposed activity does not Involve a change to the Operating License or Tech Specs. II. List the documents (e.g., UFSAR, Technlcal Specifications, other licensing basis, technical, commitments, etc.) reviewed, including sections numbers where relevant infonnation was found (if not identified in the response to each question). DSAR Chapters 4 and 5 ODCM Section 10.2 Ill. Select the appropriate conditions: If all questions are answered NO, then complete the 50.59 Screening and implement the Activity per the applicable X governing procedure. If question 1, 2, 3, or 4 is answered YES and question 5 is answered NO, then a 50.59 Evaluation shall be performed.
- If questions 1, 2, 3, and 4 a~ answered NO and question 5 is answered YES, then a License Af!lendment is required
) prior to implementation of the Activity.
- If question 5 is answered YES for any portion of an Activity, then a License Amendment Is required prior t9 implementation of that portion of the Activity.. In addition, If question 1, 2, 3, or 4 is answered YES for the remaining portions of the Activity, then a 50.59 Evaluation shall be performed for the remaining portions of the Activity.
fV. Screening_j!gnoffs: ~/ 50.59Screener: /#""111.r S. /d~.lilJo# Sign:~~.-.t Date:P/ J.2/JJd/S (Print name) (Signature
*
- 50.59 Reviewer: :[::kµA.L.P ~ l17J:JlS (Print name)
)
ZAP 100-09 Revision 4 Information Use ATTACHMENT A DECOMMISSIONING IMPACT EVALUATION Activity: Exemot Change 400576: Extension of LRWS Discharge Hose from West End of Unit 2 CW Tunnel to East End. ECN 400577 (Work Order No., Procedure No., On Site Review No., Design Change No., etc) TRACKING#: 50.59 Screening 2015-008
- 1. Does the proposed decommissioning activity result in any of the following: *
- a. Foreclose the release of the site for possible unrestricted use;
[ ] YES [x] NO Provide justification: The proposed activity does not increase the potential for the spread of radioactive contamination. The controls in place for the LRWS discharges ) cover this control. The proposed activity will not change the design function of the LRWS as discussed in the DSAR; and the LWRS will still be capable of performing its DSAR design function.
- b. Result in significant environmental impacts not previously reviewed;
[ ] YES [x] NO Provide justification: AU- of the work associated with the proposed activity will be performed within the requirements of the DSAR and the NPDES permit.
- c. - Result in there no longer being reasonable assurance that adequate funds will be available for decommissioning.
[ ] YES [x] NO Provide justification: The proposed activity is regarded as a minor design change; and does not adversely impact the budget. The proposed activity will be funded by the
- decommissioning trust fund.
) 9of10
ZAP 100-09 Revision 4-lnformation Use ATTACHMENT A DECOMMISSIONING IMPACT EVALUATION (Continued) Activity: Exempt Change 400576: Extension of LRWS Discharge Hose from West End of Unit 2 CW Tunnel to East End
- 2. Review the answers to Step 1.a-c. !f the answer to any of the questions is YES, Then the actiVity can NOT be completed, without prior notification to the NRC.
NOTE In taking actions permitted under 10CFR50.59 following submittal of the PSDAR, the licensee may perform activities inconsistent with the PSDAR, including significan.t schedule changes or significant cost increases, provided prior written notification is made to the NRC, as well as a copy of the notification to the State of Illinois.
- 3.
- Is this activity incol'J,sistent with those actions described in the Post-Shutdown ~
J Decommissioning Activities Report or cause a significant schedule change or c0st increase? [ ] YES [x] NO lf the answer is YES, Then notify the NRC and the State of Illinois prior to performing the activity. jf the answer is NO, Then proceed without notification. Provide justification:
- This exempt change is a minor design change activity that does not conflict with any of the information provided in the DSAR. It has no impact on the decommissioning trust fun~.
Implement Changes - Based on this evaluation, I have determined that the proposed activity is not restricted by 10 CFR 50.82.
- P7rint name' '1/ln.11.s S: ,C:,,,.,t,,.4 Discipline: //,fr *
~- ../. if'~tf~ o,,.,.,,.,;e'/' . e,t, .2*/S Preparer Signature Date
- 4. Review - The reviewer agrees that the proposed activity is not restricted by 10 CFR 50.82.
)
- z;~~rm*: Vr:::'gil '.O,pM-P r:.:- R..'
Discipline: A. Ci l/Z1!J/Z(){5 J eviewer Signature Date 10of10
\ ZionSolutions LLC ZS-2016-0042: Attachments ATTACHMENT 3 ECN# 400657 Installing additional liquid effluent discharge flowmeters
Exhibit A NEP-08-01 Revision 1 Engineering Change Notice (Part 1) ECN No. 400657 ISSUANCE: 1:8:1 FOR CONSTRUCTION D FOR COMMENT Page: _1_ of .J.l_ Station: ZION D Safety Related Design Change No. 4006~6 Affected Unit: 00 181 Non-Safety Rel!lted Project No. (ifappl): NA Changes to a previously Approved ECN 181 D Regulatory Supp ID No. (ifappL): NA System: WD Description of Design Change Request: This ECN adds an additional flowmeter to the new liquid Waste Disposal system. Equipment identified as ABANDONED in this ECN will be de-energized and renioved via deconunissioning work orders. Reason for Design Change: Change 8Dd action required (Provide n:ason fur change, specific actions rcquiml. auach SllppOrting documents, as applicable). The current liquid waste system uses a flowmeter that has a minimum calibrated flowrate of 5 gpm. This ECN will allow
- the discharge of liquid waste at flowrates less than 5 gpm.
INTERFACING COMMENTS by: Design. Group or Discipline Name of Commenter (Printed) Signature of Commenter Date CorNC Elect./I&C Mechanical Structural Others Others Others Prepared by: A R. Adams 'J- . Reviewed by: t,,,OA.& ~A or Ne Approved b;.7~..11/?}Jj:;J?J
'Z.J t- 1'~'10 Date:*- ~/~LS Date: 2-~-lS Date:
All affected design documents revised by (date): verified by: Date:
Exhibit' A NEP-08-01 Revision 1 DESIGN CHANGE DOCUMENT - AFFECTED DOCUMENT LIST (Part2) Print Dllte: 02/18/~0lS BC NUmbe:.r : 0000400657 000
~
~Exelon.
s-:..tus/:>at.e : REGISTER 01/~l/2015 Facility : z:w 'I'YJ>e/ft.i:J- t;}'Pe I DCP NOD . . .
- (JlID,lll.lll,llllllJQtnlllll Pages 2of 13 KW2s MUter RC ':* H Wark. aroup = 'l'e8'10r.u"Y I N outage : .R Alert Groupt Ap.rd Reqd Data ~
wo Recr~ired : Ir.age ~ ,,** J!xp IIiavc Date.: Mv Wk .App'Wi1 Auto-Advil!Wc:e= Y.
.Alt Ref, Pd.Qrit:y r
J!:xpires On 11\1to-1'Sb\Jild :
~ .* :
Caveat .Outst: D*part.:ment : IJia:eipUne I R.esp E?'lg'r : FAlllmLL A LtJXXEN Loc*ticm. : ' 8\lb* ns, !la m! llOeUIUae Sil~ W, !!!f !.£!' ZIN J>KQC M-119S N Y l t'linor Rev: Maj 0% ReV* Updt DUe:
'l'itlei lllAGRAK OF CHEMICAL & VOLUME CONI'ROL: SYS'IEM (CRITICAL CoHTRoL. ROOM DRA zm DWGC* M-49 ;L N y N Minor Rev: Major tcev: Updt Due~
Title:
DJAGRAM OF WASTE D!SPOSAL SYSTEM CLIQUID} MON!TOR >>lD* DI:&POSJU.. SYSTEM ZIH OC "'11 Bqgipment : N/A WJ>OOOSA Minv't' Jtevf Coniponen~ : Majo.r Rev: Bquip. Tag; OY1-WD0005A States leviawe~? N 1~st/B11u Rev 'l'rackable: Inc: K N~ r RBI.BASS: TAN'K l'LON lND:tCA'l'OR ii 'l'Q'DU..!i:ZIR 4 1A ZIN 00 WT.t Bquipmut:. z 'II/A WOOOOU Mina~ Rev: COtapCDen~ ~ Ma'jor Rev; equip. Tag; OJ'l'-W'D0006A st.u~ :Reviewed? 1~ Xl:.8t/Rm1 Rev Trackables m Iner K Jfatne. : RBLBASE TANK FLOW IRDICM'Oll. ii. TODLIZER. # .2A
Exhibit A NEP-08-01 Revision 1 DESIGN CHANGE DOCUMENT - AFFECTED DOCUMENT LIST (Part 2) l'i'int Date: o'/11/2015 JtC Numbllr OC004006S7 000 ..,, .
~"Exelon .
l!l;atus/Date .IBGIS'!EI. 01/21/2015 h.dlit:y ZD Typ~/SUb-typc: DCP M'OD rmm*-**111111*1111 Page: 3of 13 ZIN 00 tt"D BqUipment i v...s l.l16A Minor ltev: CClq10rlent MA'ar :ReV:
&:qi.lip. Tag-: ' OWDJ.11'1\.
Stace: ~v.lewedl' :N 1net./Hn:i Jlev 'l"rR~able: w UK'; N Name I l\EL!AS! 'Tr.mt fi 2A DIBCJ:Wl.QE VLV Zl1i QO WD .
&:qWpmer.t : vi~ L117A Minor Rev*
camponent. : Mar.jar Rcv1
~:ip. 'l'ag1 OHD1.ll 7A Sta.te: :ReVieWed? :. I0&t/R11u uv ~rac:kable1 111 Ir.c1 I\'
Nilll!e 1 Rr...EllS!! TANK tt 1A l)ISCHA.~ V!..V
Exhibit A NEP-08-01 Revision 1 DESIGN CHANGE DOCUMENT - AFFECTED DOCUMENT LIST (Part 2) ECN No.: -.:.40=0=6=-57,___ _ __ Design Change No.: 400656 PageNo.: *4 of ---=-1=-3_ _ Back-Up Calculation Listing (Part2) Calculation/Analysis No. Revision No. Description None
Commonwealth Edison Company Engineering Change Notice
- ECNNo.: ___,4=00=6=-57..__ _ __
Design Change No.: 400656 Station: ZION Affected Unit: 1 & 2 Page No.: 6 of 13 Part4 Construction Support Information MECHANICAL PARTS LIST
*. Substitute parts may NOT be used without Eng Approval
# Item numbers reference the components of the isometric Figures
# DESCRIPTION MANUF. PART#
1 Pipe fitting, Tee, NPT, 1-1/2", SST 150 psi min 2 Pipe 1" Schedule 40 SST 3 Pipe fitting, elbow 90 degrees, 1" SST, 150 psi (min) 4* Valve, globe, SST or Bras~, 1", Milwaukee 590T ~ " NPTends 5 Pipe union, 1" NPT SST 6* l Flow Gauge & Totalizer Turbine Flow Met~ (see below) Valve, Check, 1", npt ends, Mcmaster carr PIN 7 4463K66 or 4708K55 or SST or brass or bronze, 150.psi min working pressure Similar 8 Pipe fitting, Male x female hex reducing bushing, NPT 1-1/2" x 1", SST 9 Pipe, 1-112", schedule 40, SST Pipe* fitting Reducing Bushing Male Mcmaster carr PIN 10 xFemale 1-1/2"MNPTx W'FNPT 4464K155 or 4452K186 or SST similar Pipe Fitting Female x Male street Mcmaster carr PIN 11 90 degree elbow, ~" FNPT x W' 4464K38 or 4453K474 or MNPT,SST similar
.,,.,._. a-~ .z,S Prepared By: A. R. Adamyj&Dedvia email q-- Date: 2-t-a-15 Reviewed By: (.IJ.IJw ~JRA.. Date;:iiiiiiiiiiiiiiiitiiii,.iiii~~'riiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiii-..!/
Commonwealth Edison Company Engineering Change Notice ECNNo.: ___..40=0=6=-57,__ _ __ Design Change No.: __,,4=-00=6=-56"---- Station: ZION Affected Unit: 1 & 2 Page No*.: 7 of 13 Part4 Construction Support Information MECHANICAL PARTS LIST Continued Pipe fitting, redueing coupling, 1 . Mcmaster carr PIN 12 FNPT x W' FNPT, SST 446K534 or 4458K263 or Similar 13 Pipe 1/2", schedule 40, SST 14 Pipe Fitting, Reducing coupling, :MCm.aster carr PIN female x female, 2" FNPT x 1" 4464K548 or 4452K277 or FNPT,SST Similar 15 Pipe fitting, tee, 1", SST Mcmaster carr PIN 4464K53 or 4452K2436 or Similar
*Cameron Flow Meter, Liquid Turbine style,, flow element with element mounted flow analyzer, Nuflo MC-II flow analyzer and flow element; range 0.75-7.5 gpm, standard grade, standard accuracy, gallon totalizer; gallon rate indicator, body material SST, process fluid is water, Process
- range 33 Fto 120F, process pressure 150 psi max, ambient temperature range 32 F to 120 F, 1/2 flow meter with 1" NPT x 1" NPT connections; with dated calibration certificates, flow element part number 9A-100003532 J-t~ ,, "
Prepared By: A. ~Adams signed via .mi Date:._ __.2=--.::.:~::;...-=15"------- Reviewed By: ~ 4c. L, fld .fc Date: tZ-z..f-K
FIGURE 1 Part4 ECN No. 400657 EC No~ 400656 Page _8_ of 13 Prepared By: A R Ad . +,pl~ ~~ ~
*
- ams srgned via ~r "l) a.L.-.*
- .r.>*15 Reviewed By: l, IJ./?tJJ #/i
FIGURE 2 Part4 ECN No. 400657 EC No. 400656 Page _9_ of _13_
-1~ /..CAif, 'l. . Z.1-14" Prepared By: A. R. Adams signed via Mulil-2 13 15-Reviewed By: l.(J..~1/, ~o!JA. 2
- Z,S-"'ltl'
(J Nil 2...
- \fo!ES:
I) (J<! TI Ui' - f)T;1rr1.,,:;f1;.t. 5kc.*tu N z) Fife..!) Ftr up A'.> Af o U.!:f\f: /) FIGURE 3 Part 4 ECN No. 400657 EC No. 400656 Page _10_ of _13_ d""'*... 2 -t-kr' Prepared By: A. R. Adams signed via..e~aU
- Ho 1-!r Reviewed By: LMow (LIJt [. 2f°-tll'
Remove check valve and attached pipe nipples. Discard all three. Replace with pipe FIGURE 4 Part4 ECN No. 400657 EC No. 400656 Page _11_ of _13_
-I.ft: f>* f._. ~'J-lf' Prepared By: A. R. Adams signed via e00 ail 2 13 !1:5
- Reviewed By: &;.,,,oP,4. l. /J,,,,f-tr 2..- 2. !'--~'
Commonwealth Edison Company Engineering Change Notice ECNNo.: ___,4=00=6=5_,_7_ _ _ __ Design Change No.: 400656 Station: ZION Affected Unit: 1 & 2 PageNo.: 5 of 13 Part4 Construction Support Information Note When disassembling hose and flow meter manifolds there is an estimated 15-20 gallons of water that could drain out. For contamination control insure the water can be collected.
~stall Unit 1 low flow ~sgnbly ~#)-lVith ~xis~g flow assemb~y .as sho~ in_ .
Figures 1 and 2 on pageS,K\ndf.' 'fliis~ reqmre disassembly of eX1sting Unit 1 piping; other configurations of installation are allowed with Engineering approval. The Unit 1 check valve located in the Unit 2 Lake Release Room will be removed and a new check valve is installed on the Unit 1 assembly as shown. The configuration control drawings M-49 andM-119Sareonpage~ and~.-
. 8_ ~)fl.
- 2. ~tall Unit 2 low flow ass~bly in RAT~/?.:and ~th e~isting flow ass~~ly as s~own in Fi~ 3 and 4 Oli pagesd md )-0!1this Will require disassembly of existing Unit 2 piping; other configurations of installation *are allowed with Engineering approval. The cqnfiguration control drawings M-49 and M-1195 are on pages)'! and,)1.
. r~.. 13 ~/
l'/S""
'Prepared By: A R. Adams signed via ~-'-~eemil
- 1-k> Date:._ ____.2=-..g.:.::...=15,.__
e.J ReviewedBy: ' - JJI;~ c.._atjo,G. Date: l* 2 fl .. /~
Unit 1
.ORWDOOOS 1VC0330 OWD1117 10PR04 1VC0329 Unit2
< "°""°'
IMUbt1. ( Part 5 ECN No. 400657 EC No. 400656 Page _12_ of _13_ Drawing No. M-1195 Rev. B
"'""'~ Z,'2."J-tr Prepared By: A. R. Adams*signed via email ~ a.a tS -
Reviewed By: '~ £. ~4 z . tzr,,,.r'
~LJ;;i I
I *.i.r' I I ..
. L..,
Part 5 ECN No. 400657 EC No. 400656 Page _13_ of _13_ Drawing No. M-49 Sht 1 Rev. B
-J-~°""' i- z,..,,i-Prepared By: A. R. Adams signed via eirrail 2 i3 i":5-Reviewed By: l. /)fi~/s .A. M+f 2-'L~'l'I
February 13, 2015 Iµ reply refer to CZE-15-004 To: Tony Oraweic
Subject:
Zion Station, Units 0, 1 & 2 Exempt Change No. 400656 Liquid Rad Waste System Code: WD, VC The Engineering Department has reviewed the subject exempt change in accordance with
. NEP-04-02 and applicable Zion *Solutions Quality Requirements. Design Input Requirements (DIRs) as identified in NEP 12-01 have been reviewed and are included in
- the design change approval letter as applicable.
Description of Change: This Design Change installs another flow control valve and flowmeter to the existing
- liquid rad-waste system to alfow low flow (less than 5 gpm) releases.
Exempt Change Design Package: The mechanical portion of the design for this Exempt Change is contained in ECN 400657 which is.issued For Construction" by this letter. There is no electrical portion for this Exempt Change. This Exempt Change installs components to the liquid. waste system installed by the previous Exempt Change 392999. ' 10CFR 50.59 Evaluation I Decommissioning Impact Evaluation: A 10CFRS0.59 Screening was performed in accordance with ZAP l 00-06 and is being transmitted along with this letter. This activity can be implemented without prior NRC approval. A Decommissioning Impact Evaluation was performed and it was concluded that the proposed activity is not restricted by 10CFRS0.82. .DSAR I ODCM Impact Review: DSAR Chapters 1 through 6 were reviewed for this exempt change. No changes to the DSAR are required. Additionally, a reyiew of the ODCM was conducted. Revisions to the ODCM are required as a result of this design change as identified in ZAP 510~02C, Attachment A. Attachment A is included in the DCP. 1
Febmary 13, 2015 In reply refer to CZE-15-004 Applicable Codes and Standards: This exempt change shall be installed in accordance with Zion Specification X-3646, which is the general work specification for mechanical, structural and electrical .work as well as applicable site and corporate procedures. Installation requirements identified in the ECN supersede X-3646 guidance. Basic Functions: This Design Change adds a second flow control valve and flowmeter in parallel to the existing flow control valve/flow meter assembly to expand the capability of the system. The existing flowmeter has a minllnum calibrated tlowrate of 5 gpm; the added components will allow flowrates of less than 5 gpm. Industrial Safety: This design change has no effect on the industrial safety of the plant. Installation Schedule I Outage Requirements: Installation of this exempt change will be scheduled via the site work schedule process. Technical Specification Changes: The existing Technical Specifications do not require revision as a result of this exempt change. ALARA Review: An ALARA review will not need to be performed for this exempt change. Fire Protection Review: No changes to the Fire Protection Report are required by this EC. Impact of Pending Modifications or Temporary Alterations: A review of pending design changes has been completed. This Exempt Change does not impact any pending design changes.
- 2
February 13, 2015 In reply refer to CZE-15-004 Construction Drawings: Construction is authorized to proceed in accordance with ECN 400657. Identification of the Installer: This Exempt Change will be performed by the D&D maintenance department with assistance from the other groups as required. Procurement Requirements: A Bill of Material has been included with the ECN. Spare parts should be ordered as needed. Training Requirements: Training will be required for the Operations Department and other associated plant personnel on the operation and limitations of the new portion of the system. Testing Requirements: None Operating Requirements: Existing Zion procedures will require revision as identified in ZAP 510-02C, Attachment A. Attachment A is included in the DCP. Due to the configuration of the flow path to the radiation monitor PR04, the actual release rates are at least 0.3 gpm less than shown on the flowm.eter. This reduction in actual release rate may be accounted for administratively within the procedures. 3
February 13, 2015 In reply refer to CZE-15-004 Technical Review: The Liquid Rad Waste system is considered Important to the Defueled Condition (ITDC). Therefore, this design change is subject to a Technical Review in accordance with the requirements of ZAP 500-08. A Technical Review (TR-06-2015) has been performed and
- submitted with this desigri package.
If there are any questions regarding this exempt change, please contact Arthur (Bob) Adams at extension 4010.
- Prepared By: signed vfaemtrit f-e.-k c....,, ~ l-27-es ...
Arthur R. Adams DesigIJ, Engineering Approved By: 1:Z!l_FJ{J
-'Don Roth D&D Engineering Supervisor cc:
MAL ECN 50.59. Central File 1 1 .1 Darcey Neuenfeldt originals Jim Denio 3 3 3 Mod Coordinator 1 1 1 J. Brandis 2 2 2 4
TECHNICAL REVIEW LETTER TR-006-2015
- To: Tony Orawiec Decommissioning Plant Manager
. Zion Station fl.
/"
Subject:
EC 40~ Low :Flow Meter For Liquid Waste System (i.S"h_' S~acy: J;f . This Technical Review documents the review of the technical basis for changes to the existing liquid Rad-Waste system, and installation of the new flow meter. The new flow meter will provide the capability of release flow rates of0.75 gpm to 7.5 gpm. v,;,, ~~- s Prepared By: Arthur R. Adams 1diUUt& Date:---""2""""'-Jj=-=-1=5_ _ __ Required Review Disciplines:_A....,.......B..,.._4; 9} ___ ,]2_"""-'~-* ~-- _"_T-i._.- _I/)_...* ..- EngSupv Qualified Technical Reviews 1110/}- l ZG~ fd'l/ 1 Discipline Date A,8,£Q, d~;_I~ *
~ ~
Signature Discipline Date Distribution: Decommissioning Plant Manager Operations Manager Engineering Supervisor RP Supervisor SRC Coordinator Master File
ZAP-100-06 Revision25 Information Use ATTACHMENT D: 50.59 REVIEW COVERSHEET FORM Station: ZION , _A_ ~\~\\'3 Activity/Document Number: .:E:.::C~N=-40.:..::.:.;*~65~71....-_ _ _ _ _ _ _ _Revislon Number: ,,.,o_ __
Title:
Install Additional Flowmeter and Flow Control Valve To Liq Waste Sys NOTE: For 50.59 Evaluations, lnfonnation on this fonn will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2). Description of Activity: (Provide a brief, concise description of what the proposed actiyity involves.) This activity installs an additional flowmeter and flow control valve to the liquid waste system. Reason for Activity: (Discuss why the proposed activity is being performed.) The existing flowmeter has a minimum calibrated flowrate of 5 gpm. The additional flowmweter and flow control valve will allow flowrates of less than 5 gpm to be released. Effect of Activity: . . . (Discuss how the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.) There is no change associated with the design bases, or safety analyses d~scribed in the UFSAR. Summary of Conclusion for the Activity's 50.59 Review: (Provide justification for the .conclusion, including sufficient detail to recognize and understand the essential arguments leading to the conclusion. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment Request, as applicable, is not required.) No changes to the release path from the site or controls associated with releases are changed by this revision. As such, the design function of "controlling liquid release concentrations to less than the allowablen is not changed.
- Attachments:
Attach all 50.59 Review forms completed, as appropriate. (NOTE: if both a Screening and Evaluation are completed, no Screening No. is required.) Forms Attached: (Check all that apply.) Applicability Review x 50.59 Screening 50.59 Screening No. 2015-023 50.59 Evaluation 50.59 Evaluation No. 22.of26
ZAP 100-06 Revision25 Information Use ZAP 100-06 ATTACHMENT F: 50.59 SCREENING FORM 50.59 Screening No:.---J'2~0__1__ 5-__0=23..___ _ _ _ _ _ _.....;Rev No: 0 . Activity/Document No: =E=C'--4"""0"""0=65"""'6..___ _ _ _ _Revision No: _JL I. 50.59 Screening Questions (Check correct response and provide separate written response providing the basis for the answer to each question) (See Section 5 of the Resource Manual (RM) for additional guidance):
- 1. Does the proposed Activity involve a change to an SSC that adversely affects an UFSAR YES ..X.NO described designfunctio_n? (See Section 5.2.2.l ofthe RM)
Design Change 392999 installed a new liquid rad-waste system and abandoned portions of the existing system. This change adds an additional flow control valve and flowm.eter that allows release rates of less than 5 gpm. The existing flowmeter has a minimum calibrated flowrate of 5 gpm. The dedicated release path from the site to Lake Michigan and associated control methods for monitoring releases is not changed such that the concentrations of effluent are maintained well within the allowable limits of 10CFR20 and the limits of the ODCM.
- 2. Does the proposed Activity involve a change to a procedure that adversely affects how YES _K_NO UFSAR described SSC design functions are peiformed or controlled? (See Section 5.2.2.2,ofthe RM) *
- Procedures* associated with the operation of the Liquid Waste systems will be revised under_ a separate 50.59.
ZAP 100-06 Revision25 Information Use ZAP 100-06 AITACHMENT F: 50.59 SCREENING FORM 50.59 Screening No:___,_2__0~15~---02=3..___ _ _ _ _ _ __;Rev No: 0 Activity/Document No: E=C-=---'4=0~06=5....6.__________Revision No: .JL
- 3. Does the proposed Activity involve an adverse change to an element ofa UFSAR - -
YES ..JLNO described evaluation methodology, or use ofan alternative evaluation methodology, that is used in establishing the design bases or used in the safety analyses? {See Section 5.2.2.3 ofthe RM) The Liquid Waste system is used to store, process and release liquid effluent from the RCA to the release point of the plant. The release path is defined in the DSAR. This \) activity d0es not change or affect the dedicated release path from the site or the controls of the effluent such that the concentrations of the releases will remain within the limits of 10CFR20. This is due to the existing controls, which are not being affected by this change; (1) the release paths are controlled by plant personnel, (2) effluent flowrates are determined prior to release and controlled during release that ensures co:ncentrations less than the allowable, and (3) the existing rad monitor terminates the release in the event of a high radiation in the discharge line.
- 4. Does the proposed Activity involve a test or experiment not described in the UFSA.R, __ YES _x_ NO where an SSC is utilized or controlled in a manner that is outside the reference bounds of * --
the design for that SSC or is inconsistent with analyses or descriptions in the UFSAR? (See Section 5.2.2.4 ofthe RM) This change is not a test or experiment of the liquid waste system. The release path and controls of the release path associated with the new system has not changed. 5.. Does the proposed Activity require a change in the Technical Specifications or _-YES _A_NO Operating License? (See Section 5.2.2.5 ofthe RM) No Tech Specs are affected by this change.
ZAP 100-06 Revision25 Information Use ZAP 100-06 ATTACHMENT F: 50.59 SCREENING FORM 50.59 Screening No:.___;.2=0=1=-5-""""02=3.___ _ _ _ _ _ _ _Rev No: 0 Activity/Document No: =E""'C....4.....0.....06=5....6____-'--_ ______,Revision No: _JL II. List the documents {e.g., UFSAR, Technical Specifications, other licensing basis, technical, commitments, etc.) reviewed, including sections numbers where relevant information was found {if not identified in the response to each question). DSAR Chap 4 & 5 ODCM EC393000 Ill. Select the appropriate conditions: X If all questions are answered NO, then complete the 50.59 Screening and implement the Activity per the applicable governing procedure. H question 1~ 2, 3, or 4 is answered YES and question 5 is answered NO, then a 50.59 Evaluation shall be performed. H questions 1, 2, 3, and 4 are answered NO and question 5 is answered YES, then a License Amendment is required prior to implementation of the Activity. If question 5 is answered YES for any portion of an Activity, then a License Amendment is required prior to implementation of that portion of the Activity. In addition, if question l, 2, 3, or 4 is answered YES for the remaining portions of the Activity, then a 50.59 Evaluation shall be performed for the remaining portions of the Acti~ty. IV.:_SereenJng Signoffs: _,..,,1_..,,,,, ~fl,A Z'. 50.59 Screener: Arthur R Adams Sign: via emeii- Date: _2_/~/_15 (Print name) (Signature) S0.59Reviewer: ~!.IL,.,;( g~igo:~ (Print name) / (S' ature) Date:3:._J2'P//./
ZAP 100-09 Revision 4 Information Use ATTACHMENT A DECOMMISSIONING IMPACT EVALUATION Activity: EC 400656 (Work Order No., Procedure No., On Site Review No., Design Change No., etc) TRACKING#: ......2....0..... 1-...5-..--02=-3....___ _ _ _ __
- 1. Does the proposed decommissioning activity result in any of the following:
- a. Foreclose the release of the site for possible unrestricted use;
[ ] YES [ X] NO Provide justification: The proposed activity involves replacing an existing flow meter with a new more sensitive flow meter. The flow meter is installed in the Crib House Forebay which is not part of the Radiologically Controlled Area (RCAl of the plant. Therefore. this. activity does not increase the potential for spread of radioactive contamination and will not foreclose release of the site for possible unrestricted use.
- b. Result in significant environmental impacts not previously reviewed;
[ ] YES [X] NO Provide justification: All the work associated with this activitv will be performed within the envelope of the station's double fence former Resticted Area. Therefore. this activity will not have any impact on NUREG 0586 Supplement 1 criteria of land use. aquatic ecology, terrestrial ecology. threatened and endangered species. environmental justice. or cultural impacts. The amount of water used will be non-detectable. so there will be no imoact on NUREG 0586 Supolement 1 criteria for water use or water quality.
- c I
The new flow meter will be installed along the eastern edge of the plant which borders *on Lake Michigan but will be shielded from the lake by a concrete wall. Therefore. this activity will have no impact on NUREG 0586 Supplement 1 criteria for aesthetics or noise. As stated above. the work will not be performed in the RCA. therefore the activity will have no impact on radiological criteria.
- Finallv. this modification does.not change the requirements fot effluent Releases.
- 9
ZAP 100-09 Revision 4 Information Use
- c. Result in there no longer being reasonable assurance that adequate funds will be available for decommissioning.
[ ] YES [X] NO Provide justification: This is minor modification to an existing svstem with minimal associated costs.
- 10
ZAP 100-09 Revision 4 Information Use ATTACHMENT A DECOMMISSIONING IMPACT EVALUATION (Continued) Activity:
- EC 400656
- 2. Review the answers to Step 1.a-c. jf the answer to any of the questions is YES, Then the activity can NOT be completed, without prior notification to the NRC.
NOTE In taking actions permitted under 10CFR50.59 following submittal of the PSDAR, the licensee may perform activities inconsistent with the PSDAR, including significant schedule changes or significant cost increases, provided prior written notification is made to the NRC, as well as a copy of the notification to the State of Illinois.
- 3. Is this activity inconsistent with those actions described in the Post-Shutdown Decommissioning Activities Report or cause a significant schedule change or cost increase?
[ ] YES [X] NO Jf the answer is YES, Then notify the NRC and the State of Illinois prior to performing the activity.
!f the answer is NO, Then proceed without notification.
Provide justification: This is minor modification to an existing system.
- 4. Implement Changes - Based on this evaluation, I have determined that the proposed activity is not restricted by 10 CFR 50.82.
Preparer print name: Arthur R. Adams Discipline: A B. C. G
~J.
signed via envU: r~ta~.,.,, ~ ~ 24if15 Preparer Signature Date
- 5. Review - The reviewer agrees that the proposed activity is not restricted by 10CFR 50.82.
~print nam~Donald F. Roth Discipline: _A_,._<.i____
.. M£~f. ~/20/iatf
""R:eviewer Signature Oat~ '
11
ZionSolutions LLC ZS.:.2016-0042: Attachments ATTACHMENT 4 ECN# 400986 Increased capacity dilution water pump of 10,000 gpm and associated flow1neters
'Exhibit A NEP-08-01 Revision 1 Engineering Change Notice (Part 1)
ECN No. 400986 ISSUANCE: ~FOR CONSTRUCTION 0 FOR COMMENT .. Page: _I_ of ..%1_ Station: ZION D Safety Related Design Change No. 400985 Affected Unit: 00 181 Non-Safety Related Project No. (ifappl.): NIA Changes to a previously Approved ECN D [j -Regulatory Supp ID No. (ifsppl): NIA System: SW Description of Design Change Request: This change will add a higher capacity SW dilution pump (OB) in the Forebay in parallel With pump OA installed under EC396794. A new SW flow meter (OFIT-SWS4B) and flow control valve (OFCV-SWS4B) will also be installed. The Unit l & 2 Oil Separators Will be capped and the Unit l & 2 Oil Separator Composite Samplers will be removed from service.
\
Reason for Design Change: Change and action required (Provide reason for change, specific actions requiJed. attach supporting documents, as applicable). Decommissioning schedules along With the high boron concentrations in the SFP and other LRWS discharge streams will require a higher dilution flow rate than can be achieved With the present pump. The capping.of the Oil Separator inputs Will allow removal of the Oil Separator Composite Samplers allowing for the space needed for the new dilution pump discharge path. INTERFACING COMMENTS by: Design Group or Discipline Name of Commenter (Printed) Signature of Commenter Date CorNC Elect./l&C NIA Mechanical ..... - Structural
- Dave Carter 1/JdJ:J- $-17-1..!i" .NC-.
Others NIA Prepared by: IJDuBois Reviewed by: PJBeinecke~ Approved b; j ~ .~~£Bd Date: ~eiM.r c@ Date: - ~1ee/zois-3-1 ?-1~- Date: a/18L16"' ' r AU affected design documents revised by (date): verified by: Date: W~ ca~ lM'lS ec.N ge4A.t--' B~l2e 3/t'-/zat~ So tT USeS OLP ~t:2.M.S... rt-{ 12&J.LSE0 l:Of2i'JlS 'DO NOT R..e. tJCrcafJAt-t...~ Otfl_ ""TGO-fa-..l<CALL'"f APF6Cf ""t1:fe wod211<, .
~/ F~ 3/10/~ots
Exhibit A NEP-08-01 .( Revision 1 DESIGN CHANGE DOCUMENT -AFFECTED DOCUMENT LIST (Part 2) ECN No. 400986 Design Change No. 400985
. ll~!Jtt: IJl.;t~u 03/U/2015 EC~;t a OOOGC00916 DO() ....,
~Exelon, SC.tu/Date , JWGJS'l'ER 02/0t/2015 J.ID.c.1 Hty : %:IN Type/Sub-type:
DCP MOD llBlllElllrSlllill*- BC ~it.le: sat .. ttisiAU A HIGJlft Pl.ON' SW' llll.>>tlON ~ H!mlf lHr.ALl:aTIOR IW2: Kil41
!9, !XU Iii!
*u- !MJ!!Mt !lt!U 211 ID !!! J!e ZDI nMGC M-100 g y H Mimiir aev~ ~or MV1 VpGt Puea.
Title 1 CIRC!Ut-l'IHG WAmR elPDTG PLR.11 - 1DltfS 1 .- 2 zm DUGC 11-31 ll y N iunor b'1': Majo:r Rev: 11pclt Dtiie: I Title 1 JJlMRNil or c~ WA'J'JIR P:i::PIW - tmJTs 1 " ' . ZiR SJlllGC M* 32 t N Y 1 Minor Rev-: Hll..jar Rw: Ugdt Duet
'tit.le' J)JMJWI! OP "1t\1%Ct NATa CCIU'!"IQI, t:mn'ROJ.i ROOM DJWrUIC) "Lrt.~ fJwG c: fll.40( !TH 00 SN Zqui9f11mt : *Fl' SWS4B Mino&' bVi CC!lllOIWlt
- Ma'or Rev:
Bqu,p. Tag; OFI'l'-stf5U 8t.ate l llev.le-4? N Dltl/MD: 1te1r 1'redcUlei II Xl\ru II
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Exhibit A NEP-08-01 Revision 1 / DESIGN CHANGE DOCUMENT -AFFECTED DOCUMENT LIST {Part 2) ECN No. 400986 Design Change No. 400985 Print ~tes OJ/11/2015 BC Numb~r ~ DD00tOO!J86 ltOD Stat.-us/D~te l'iitilUty JtBGrSTICR 02/0>>/2015 Int IE,xelon. Type/sub-type: DCI" MOil' . . llDlHlllllDllllll~llllM Page~ pof27 ,, ZlN 00 BqW.pment : B/A lOtllB ampon~t ~ V25 c: EljF.ip. Tag: 0Stf1001B stab:; MViewed?
- Inst/llm:
NAM ~ 08 SW DILU'l'lOll WAn.R l1UMP ZDI 00 SW squ1pawmt PCVA 6"541! ~-- le\t: Comp<ment : vis ~ Major uv: Bqu.ip. Tag: OFCV*SNOOSfB s~ate1 R.eVieweci? w ln*t/Rmi MY ~le: N Inc: Ii' Jlame : Oll SW D:Ilt'U'l'JON PUMP ftaOW COR'l'JIOI. VAS.VB
Exhibit A NEP-08-01 Revision 1 ( ECN No.: ___,_40=0=9-=86"------ Design Change No.: 400985 PageNo.: 4 of --=2-=-7_ _ Back-Up Calculation Listing (Part2) Calculation/.Analysis No. Revision No. Description None
Commonwealth Edison Company Engineering Change Notice ECN No.: __.....:.40=0=9=86"------ Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 5 of -=27""---- Prerequisite
- 1. At the direction of Environmental Manager and Waste Operations Manager remove all oil stored on clean and dirty oil storage pad on north side of Turbine Building or protect it from oil release to the environment, RefB-803
- 2. W allc down the site with Environmental Manager to determine if any mitigating actions need to be taken for any oils stored outside. Reference drawing B-803, 804, and B-876 for areas that feed the Oil Separators.
- 3. Verify Storm Water Pollution Prevention Plan and associated procedures and guidelines are implemented for the rem.oval of the Oil Separators with Environmental Manager.
. 4. Verify the Spill Prevention Control and Countermeasures Plan and associated procedures and guidelines are implemented for the removal of the Oil Separators with Environmental Manager.
Notes:
- 1. This Installation is laid out in sections.
- 2. Section 1 Unit 2 Oil Separator needs to be completed prior to starting Section 2 Step2 Section 1: Capping Inputs to Unit 1 and Unit 2 Storm Water Oil Separator
- 1. At Fuel Building Car Shed (Truck Wash Down Area) verify sealed or install mechanical plumbers plugs in floor drains. A total of 7 drains shown on drawing.
Reference B-492
- 2. At Outdoor Clean and Dirty Oil Storage pads (North of TB) install mechanical plumbers plugs in drains. Remove manhole cover, cut a W' steel plate to fit manhole, seal plate to manhole, install manhole cover over plate seal plate. See Sketch 3. Ref B-803, B-876.
- 3. Use plumbers plugs or similar to plug input and outputs to Man Hole 2-15. Reference drawiJ!g B-803, two 4", two 24" See Sketch 3.
- 4. Fill Man Hole 2-15 with concrete or grout to a minimum of 1 ft above the top of the highest internal pipe. See Sketch 3.
- 5. Discontinue periodic sampling of the Unit 2 Storm Drain Oil Separator eftluent.
Notify/Contact Environmental Manager, RP Technical and Chemistry Supervisor.
- 6. Use plumbers plugs or similar to plug input and outputs to Man Hole 1-17 Reference drawtng B-803, two 10"~ two 24", See.Sketch 3 Prepared By: Date: '3-17 Date: !1~/lr
Commonwealth Edison Company Engineering Change Notice .( ECN No.: . ___,,4=00=9-=86=------ Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 6 of --=27..____
- 7. Fill Man Hole 1-17 with concrete or grout to a minimum of 1 ft above the top of the highest internal pipe. See Sketch 3.
- 8. Discontinue periodic Sampling of Unit 1 Strom Water Oil Separator Eftluent.
Notify/Contact Environmental Manager, RP Technical and Chemistry Supervisor.
- 9. Verify electrically gap the Unit 1 Storm Water Oil Separator Composite Sampler and heat tracing per ECN 400987.
- 10. Electrically gap the Unit 2 Storm Water Oil Separator Composite ~ampler and heat tracing per ECN 400987.
Bill Of Material Quantity Description (MinReq'd) 7 Car Shed Mechanical Plumbers Plug, Field to determine size, capable ofl psi.
.3 Clean and dirty oil storage pad drain mechanical plumbers plugs, 6" 2 4" inflatable plumbers plug. Capable of2 psi 4 24" inflatable plum.hers plug, capable o£2 psi 2 1O" inflatable plumbers plug. Capable of 2 psi 4 Cu Yards of concrete 1 W' steel plate, 24" x 24" 1 Silicone sealant or similar, Tube Section 2-Unit 2 CW Discharge Isolation Valve House Preparations
- 1. Verify Section 1 capping of Unit 2 Oil Separator Inputs are complete.
- 2. Remove Unit 2 Oil S_eparator Composite Sampler. Cut back electrical cables, sample lines, supports* and heat trace as required clearing the area for a hole in the floor. See Photo 2 and Electrical ECN 400987.
- 3. Verify relocated electrical box on south wall to west wall per ECN 400987. See Photo 3 of this ECN.
- 4. Remove abandon ml\terials (conduits, cables, cameras, etc) as required in preparation to remove a portion of the south wall. See Photo 2, 4 and 6.
Prepared By: ~~ Reviewed Bv:
":'.li Commonwealth Edison Company Engineering Change Notice
( 40=0=9=86~---- ECN No.: _____ Design Change No.: 400985 Station: ZION Affected Unit: 00 PageNo.: 7
- of --=2_,_7_ _
- 5.
- Cut hole. in south wall. Leave 2 courses of block along door and along east wall.
See Photos 2 and 6.
- 6. Cut a hole in the floor approximately 4 ft x 4 ft. Floor is 2 ft thick and has re-inforcing bar (rebar), RefB-39. See Photo 2, Sketch 1 and Sketch 8.
- 7. Dive and cut relief windows in CW Discharge pipe downstream of 2MOV-CW-0006. There shall be 1 ft of pipe remaining circumferentially between each window.
See M-101 Part 5 ofthiseC~ ,_,,....,,
- 8. If installed per ECN 40oi'77 then Relocate LRWS discharge hose from entering in front of 2MOV-CW-0006 into new relief windows otherwise NIA. Ensure hose is at least 5 feet on lake side of relief window. See Sketch 2 and M-101inPart5 of this ECN.
Section 3-Installation of Piping
- 1. Verify beach construction equipment traverse route with Environmental Manager.
- 2. Remove interference-as required (i.e. conduits, yard lights, razor ribbon on aft bay wall, conduit, etc.). Coordinate with Security removal of the razor ribbon and*
barbed wire on the aft bay east wall. Security will determine if the security features need to be replaced. See Photo 4, 5 and 6.
- 3. Per Sketches 4A, 4B and Pipe Fabrication Vendor drawing and instructions install piping and pipe supports (Engmeerlng to review and approve vendor drawings and instructions). Install all piping from Unit 2 CW Discharge Valve house to riser on the pump. Pipe does not need to be sloped for this application. See photos 4, 5, 6 and7.
- 4. Install the flow meter and program meter per the vendor manual. Flow meter may be mounted at a convenient location, (i.e..next to the pump control switches)
Bill of Material Quantity D~scription (MinReq'd) 1 24" throttle valve(or equivalent). Lake Michigan Water service, 33F-85F process temperature, max system pressure 85 ft/37 psi. Part of lot 1 below. Reference Sketch 4A and 4B 1 Flexible boot assembly. Geneial Rubber 1101-0240-100-0EE (1101 OJA 24 x 10" F/F EPDM, Open Arch, Rated for 130 psi, 30 in Hg Vacuum, 250 F, Standard 150# Drilling, with PPRS-0240~CSG (R/R Set 24 in. CSG) Set of Split Retaining rings for 24" expansion joint with standard 150# drillin , 3/8" thick, Carbon Steel Galvanized or Prepared By: Date: ~-
~: 5};1//J /-
Commonwealth Edison Company Engineering Change Notice ECN No.: ___,,40=0=9=86..___ _ __ Design Change No.: 400985 . Station: ZION Affected Unit: 00 Page No.:
- 8 of ~27~--
similar Provided with Lot 1 Reference Sketch 4A and 4B 1 lot Prefabricated and spooled HDPE 24" piping, UV protected; Piping to including all flange bolting, backing rings, gaskets, valve and flexible joint. Process is Lake Michigan Water, 33F-85F process temperature, max system pressure 85 ft/3 7 psi, ambient temperature -10 F to 100 F. This lot will include 24" throttle valve and flexible boot above. Reference Sketch 4A and 4B. Pipe vendor/fabricator to provide engineering, layout, supports and installation requirements. (ZS Engineering to review and approve vendor drawings and instructions) 1 Ultrasonic Flow Meter with dated calibration certificate. Application 24" HPDE piping, DR-17, 4,000-15,000 gpm, process fluid is fresh lake Michigan water, temperature range of process fluid 33-85F, outdoor applications ambient -1 OF to +105 F; Omega FDH-1-50FT-NIST Hybrid Ultrasonic Flow Meter with dated calibration certificate with 50 ft leads. Section 4 Installation Pump
- 1. Verify that the thickness of the pump mounting plate is' greater than or equal to 0.7 5 inches. If not replace plate with one greater than or equal to 0.75 inches.
- 2. Cut pump access hole (34" +/-1 ") in the center of the pump mounting plate.
- 3. Lower pump onto pump mounting plate and face discharge nozzle in the North direction. (Cascade-I Stage 20MF Mixed Flow Pump, ref Drawing 3MS7633A) using manufacturer's instructions and good work practices. *
- 4. Shim pump as required to level pump head.
- 5. Drill and tap holes (3/4 - 10) in pump deck plate for pump discharge head mounting bolts. *
- 6. Illstall hold down bolts and tighteii.
- 7. Recheck pUm.p level and adjust as necessary.
- 8. Install motor using manufacturer's instructions and good work practices.
- 9. Coupling alignment shall be done using a straight edge (or equivalent) method.
PreparedBy. g_, o£6v. Date: "J-11-1r
!leviewedBy: * ~- Date: Jbt'lS
Commonwealth Edison Company Engineering Change Notice ECN No.: __._40=0=9=86::..___ _ __ Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 9 of --=2""-7_ _
- 10. Install flexible boot to pump per Sketch 4A, photo 7.
- 11. Install riser pipe per Sketches 4A, 4B and Pipe Fabrication Vendor drawing and instructions. (Engineering to review and approve vendor drawings and instructions)
- 12. Install pipe anchor per Sketches 5, 6 and 7.
Bill Of Material Quantity l,)escription 1 Pump and motor assembly Cascade-I Stage 20MF Mixed Flow Pump, ref Drawing 3MS7633A 4 Studs, %-10 UNC x 4" long 4 Washers, %" 4 Nuts, %-lOUNC 1 Fiexible boot assembly. General Rubber 1101-0240-100-0EE (1101 O/A 24 x 10" F/F EPDM, Open Arch, Rated for 130 psi, 30 in Hg Vacuum, 250 F, Standard 150# Drilling, with PPRS-0240-CSG (R/R Set 24 in. CSG) Set of Split Retaining rings for 24" expansion joint with standard 150# drilling, 3/8" thick, Carbon Steel Galvanized or similar Provided with Lot 1 in Piping Installation section. 20 Bolts, 1 1/4-7 UNC by 8" long 20 Nuts, 1 ~-7 UNC 10 ft Structural Steel HSS 5x5x5/16 12 Hilti Kwik Bolt 3, 3/4" . 2 Plate, Steel,%" x l '-6" x 2'-3" 4 Plate Steel, %" x 6" x l '-8" 1 Plate, Steel, W' x 3' x 4' Prepared By: ~ SL;""". Date:
~~ Date:
Commonwealth Edison Company Engineering Change Notice ECNNo.: _40..:.=0=-9=86_ _ __ Design Change No. : 400985 Station: ZION Affected Unit: 00 PageNo.: 10 7_ _ of __.2......... P~'t Photo 2 Cut Hole in wall, top to bottom. Leave 2 course of block along door and east wall Date: Reviewed By: Date:
Commonwealth Edison Company Engineering Change Notice ( ECNNo.: _4"'""'0=09=.= 86~--- Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 11 of __.2......... 7__ Photo 3 Inside Unit 2 CW Discharge Va1ve House Looking South Prepared By: ___A--'--~--- _-L Date:
*~
Reviewed By: Date:
Commonwealth Edison Company Engineering Change Notice ECNNo.: _4~0~09~86'----- Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 12 of ~2~7_ _ Photo 4 Remove Door, hand rails and kick plates as required Prepared By: Date: n -..:-......- ..3 n .. . a
Commonwealth Edison Company Engineering Change Notice ECNNo.: _4=00~98""--6_ __ Design Change No. : 400985 Station: ZION Affected Unit: 00 Page No.: 13 of -=2,_.,_7_ Photo 5 Pipe route on ground and up to Aft Bay plate'form. Approxima.e location of control valve 1 PreparedBy: ~~ Date: RevicwedBy: ZLP~- Date: .l#Ms~
Commonwealth Edison Company Engineering Change Notice ECNNo.: _4o...:.,=.00"-""'986...___ _ Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 14 of --=2"'---7_ Photo 6 Remove ~all section. Leave 2 block courses on east and an along door. Remove electrJcal conduits and boxes. Remove light pole and camera if required. Approximate location of throttle valve Approximate .pipe routing on ground. Pipe goes into valve house and down through hole in floor Prepared By: Date: ~ t?-f~ n -.:---*- .JI "D- ** Oato* .Jtd~J,..--
Commonwealth Edison Company Engineering Change Notice ECN No.: ___:.:40:<..:::-09=8~6_ _ __ Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 15 of -=27'---_ Photo 7 New Pump Location Prepared By: ~ ol9A Date: Reviewed Bv: ~/.f'~ - Date:
Commonwealth Edison Company Engineering Change Notice ECNNo.: _:40~0!2.£98~6_ _ _ Design Change No. : 400985 Station: ZION Affected Unit: 00 Page No.: 16 of 27 __ _
} ioNTRACTOA.
~~-~--- - ~-~- ~ - ,.
INSTAt _i_ CGYR~ -...--..,. High Capacity
- Dilution Pump Unit2 CW
** Loc _:tion . 'Discharge Tunn.el
...-....::~..._.* .....
~~~ Isolation Vafv-e 1;
J1
~
~~......, .11 s
PotentaH locations
- Unit 2 I
- for Flow l.ndicator, c.w
*Pipe Mounted Oischarg E * *Tunnel oca ion r---.. . Lake Side Prepared By:
- . *~
Commonwealth Edison Company Engineering Change Notice ECN No.: -"-"40=-=09'""'"'86"----- Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 17 of __,2=<..7_ _ Sketch 2 111111<(-----.I 1:ast J West 5~DJA.MAN .ENTRY Hose Route
- through tunnel Per Wrtit l!LlND 'RAN~-------....
- iiii _ .....u
ECN400577
*. ;s.9£0*
Existing 364' access manway I r---._.__. pipe to cw tunnel
~~~*,--~-----===~
Route LRWS Dischaige Hose route after access wtnoow is cut If. in CW pipe do!Nnstream Of CW
... Diseharge isolation Valve and t VaJve is dosed. Must be a .
,. minimum of 5 ft past dflution point c,*_* --
If inslaHed Under ECN 400577
.-ct EL L..V Hose Gang route Per ECN 400577 Prepared By: 4cl9Atr? Date: y t?vl'f
£d,?4--- Date: .~bRILS
Commonwealth Edison Company Engineering Change Notice ECN No.: ---'4-=-00=9~8=6_ _ _ __ Design Change No.: 400985 Station: ZION Affected Unit: 00 PageNo.: 18 of --=2'-'-7_ _ _ Sketch 3 iT T i
,_______ ....,_. -~ .... ---
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(. 111 I
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Prepared By: Date: Date :
Commonwealth Edison Company Engineering Change Notice ECNNo.: 400986 Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.; 19 of --=2:.<.7_ __ VAL.VE HCXISE FLAt\IOES.F~ OIIFICE ~NSTALLATION PLAN VIE!
~ Pllh!P 10'-0" 2' .. i a*-11 1, * *I I I
I I I I 24" HPDE PIPE
;z-4" tPDE PIPE
- EDGE Or CONCRETE T FLEX JOI~ __
<GENERA£ IWl!BER MAXI JOINT STYLE 1101 OR SI~ILARI t 5U'-&"
I ___ ,......_...............K PUMP DISCHARGE HEAD rSEE DETAIL 1 ~ EL. 584' -51'2" 2~-h: FUT FACED DISCHARGE FLANGE 150# SECTION C LOCIKINC WEST SECTION A LOO(ItiliG SOUTH SECTION B LOOKJNG WEST
-'SOTES:
- 1. Ziii! " HPDE P JPE, UV PROTECTED
- 2. PRDtESS FLUID1 WATER DESIGN PRESSURE:
NORMAL 1JPSI PWP DEAD HEAD IMAXI a'rPS1 GRADE EL 592 * -0" FLPlf RATE 4000-1-4000 GAi PROCESS T9PERATlJIE.r 33' F-SS*F UJlllENT TEiil'ERATURE.: -!i"F TD 10o*F SERVICE LIFEt 1 ~EAR 3* i\LL DIE~SIONS ARE REFERENCE. DIWTJON PUMP
~. PIPE FABRI~ATOR SHALL fALKDOWN THEN PIPING LA~OUT SIZE PIPE* LAYOUT AJIO RECO\!MEND DETAJL I SUPPORT JNlPVALS.
- 5. ELEClRJCAL PD'llER LINE OVER PIPE ROIITE
~~lrx-vliTI:AL C9i1ERL.Ih'E lHAT LIMIT OVERHEAD CLEAJANCE FOR INSTALLATION*
'SECTION C
&. PIPE FABRltATOR TO PROVIDE ALL PIPING+
JOINT HARDWARE, tAiKETS, VALVE AND FLEX JOINT. LOOkJNG iEST 1. BUTTERFLl VALVE SHALL HAVE A MANUAL OPERATOR. Prepared By: Date: }.--17-1~
'T"\_ .. _ .. J!tt;Jh~
Commonwealth Edison Company Engineering Change Notice ECN No.: ---.:.40=0=9....,86,.___ _ __ Design Change No.: __,4=00=9-=85~-- Station: -=Z=IO=N~- Affected Unit: 00 Page No.: 20 of 27
@ lS<METRIC Prepared By: Date:
Re"iewed By: Date:
Commonwealth Edison Company Engineering Change Notice ECNNo.: _4..!..><.00=9=86_ _ __ ( Design Change No.: 400985 Station: ZION Affected Unit: 00 PageNo.: 21 of _..2....._7_ _ N~ I 3'-0" t+"(mil)
--1~~~~--~~~~~--1-~~--~-r-~-1---.
1* I Sketcl1 5 On pump Platform
,Flex Joi*nt Side of Pump*
~Ref B-14.38 l ..
Prepared By: Date: Reviewed Bv: Date:
Commonwealth Edison Company Engineering Change Notice ECNNo.: --'-=40~09'-""'86,,__ __ . ( Station: ZION Affected Unit: 00 Design Change No.: 400985 Page No.: 22 of __,2...._7_ _ pJfir*'1. 314" plate - - - - - Detail 1 {typ.) r 1"-7112" 1'-7112'" Section A-A Prepared By: Date: 7rt7-ff Reviewed By: Date:
Commonwealth Edison Company Engineering Change Notice '(J.*~-" I
*' '. '_J,., :*it'
( ECNNo.: _4~0~09=86<---- ' ;*~ - .J' ~-- Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 23 of __.2=-=-7_ _
.._,. E=3116
q I
Detail 1 Sketc:i1 7:* On pump platform
*on pump side of flex
. . t.*
101*n
~-*
Section 8:8 Section C::C Prepared By: Date: ~t7~~ Reviewed Bv: Date: &f 1d .('
Commonwealth Edison Company Engineering Change Notice Station: ZION Affected Unit: 00 Prepazec!By: ~ . rf),/j_ Date: '7J-r7- /~ RP.ViP.Wf'.d Rv'. ~.L.l~,-1/3.----- Date: ~tf(a-
Commonwealth Edison Company Engineering Change Notice ECNNo.: _4=00=986=---- Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 25 of ___..2~7_ Parts., NOTES:
- 1. iO PURCHASERS FOREBAY BUBBLER TUBES
- 2. PURCHASERS SUCTIONMMY SIPHON tUBES
- 3. . : PIPl~C TO. ANO l.NCWOIY ICH. e.o. SHALL BE
.* IN ACCORDANCE WITH TABLE G__J .
'
- ALL PIPING LARGER THAN JI INCH. 0.0. SHALL BE INS
. WITH CORK FILLED MASTIC AS INDICATED
- IN THE. SPEC
- 5. PIPING 1'1 OJ>" AND SMAirWt SHALL BE INSULATED IN ACCOROANCE WITH TABLE CQ)
ECN 6. ALL OTHER PIPING SHALL BE INSULATED WITH *vzMASa 400986 INDICATED IN THE SPECIF'ICATION.
- 7. FOR DETAILS or MISC. PIPINC S£E (D-2) OF THIS ORA OVO JCM JAD DIGRAM OF CIRCULATIN RFD JCM JRD WATER PIPING
-- -- -- :NONE MTE .
Prepared By:
Commonw.ealth Edison Company Engineering Change Notice ( ECNNo.: _40~0~98_6_ __ Design Change No.: 400985 Station: ZION Affected Unit: 00 Page No.: 26 of ~2~7_ Part5
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Prepared By: Date: 1-fltr R P.ViP.wPA Rv* Date: _g/rf)/t.5
Commonwealth Edison Company Engineering Change Notice . _. _.. . ___ , Station: ZION Affected Unit: 00
~.;~4:.~6 400985 .(#r" Page No.: 27 of 27
---=..!----
*E: .. *i~q
- Cut 4' (min) x 4'(rmn) hote in
* ~!'DIA I MAN f.NTRV ~"
lloor on soulh-south east side of I ',
/ii**~. . .~
WITit 8.JND R...*ClE.:----__..~ - 7
- Vatite fOr dilution i water fiOW pipe.
lnstaD hand rans a::.;a ,ECN for safety.
-~- t ..
400986 PORT. DE.TAIL *a~. I * *
,Cut 4 Windows in CW pipe .
11-611 (min) x 3' (min) tor -* . tr dHUtion water loW. one I h<>le neects to be located . ; .
- l:P..1' ._. --~---1 at top. one hole needs to * ;, **
.t'~=='
windowS are in CW pipe. cut *-** I-Bi_;;_a_-** ii
~
,!ii_ ___ .-..-~li.I be located-on south side *
!!: . . . . . . -45 degrees off verticat
. one fOOt minimum
* . between holes along ttae
' circurnfe~(lce of the pipe.
MinimUm 5 ft past pipe WindoW.
.. ,_ ... ~.
t LRWS Discharge
- Hose Route Per ill " i: ECN 4005T7 Cl Re; ,
'i ~ -
PL<<N*4M~101 Unit 2 CW Dis a j Valve House struciure Cross Section. I I Lookin SOUlh Prepared By: Date: 77-17-tr-Reviewed Bv: Date; 1/11'/!~
( March 17, 2014 In reply refer to CZE-15-005 To: Tony Orawiec
Subject:
Zion Station, Unit 0 and 2 Exempt Change No. 400985 OB Dilution Water Pump The Engineering Deparbnent h~ reviewed the subject Exempt Change in accordance with ZAP 510-02C and the applicable Zion Solutions Quality Requirements. The applicable Design Input Requirements are discussed in this letter. System Code: SW, CW Description of Change: This activity will add an additional SW dilution water pump (OB) in the Forebay and the flow will run in parallel to the OA SW dilution water pump to the discharge tunnel. This activity will also abando.n (cap inputs to) the Unit 1 and Unit 2 Storm Drain Oil** Separators. Exempt Change Design Package: The design for this exempt change will be contained in ECNs 400986 and 400987 are issued "For Construction" by this letter. 10 CFR 50.59 Evaluation I Decommissioning Impact Evaluation:
~~11-lC, ~3/ri{ZP~. -
A 10 CFR 50.59 B11al1:1&tiee. was performed in accordance with ZAP 100-06 and is being transmitted along with this letter. This activity can be implemented without prior NRC approval. A Decommissioning Impact Evaluation was performed and it was concluded that the proposed activity is not restricted by 10 CPR 50.82. DSAR I ODCM Impact Review: There is no impact to the DSAR or the ODCM as a result of this Exempt change.
CZE-15-005 Applicable Codes and Standards: This exempt change shall be installed in accordance with Zion Specification X-3646, which is the general work specification for mechanical, structural and electrical work as well as applicable site, vendor and corporate procedures. Installation requirements identified in ECN 400896 and 400897 supersede X-3646 specifications. Installation Schedule I Outage Reauirements: Installation of this exempt change does NOT require *an outage and therefore will be* scheduled via the site work schedule process. . Technical Specification Changes: The existing Technical Specifications do not require revisions as a result of this exempt change. - ALARA I Fire Protection Review: This exempt change is NOT being performed in a radiological area. Therefore, an ALARA review will NOT be performed as a part of the work package preparation. There are minor additional combustibles being added. These combustibles (cable and motor oil) will not be near any critical equipment. Construction Drawings: Construction is authorized to proceed in accordance with ECN 400896 and 400897 ,_. Identification of the Installer: D & D will perform this exempt change. Procurement Reauirements: Procurement is the responsibility of the installing organization other than the pump/motor which will be procured by Engineering. Procedures: Operations, Chemistry, Radiation Protection and Environmental have identified affected procedures and are responsible for updating the required procedures prior to declaring this modification Operable. Page2of4
CZE-15-005 Traiiiing Requirements: There are no training requirements as a result of this exempt change. Testing Requirements: There are no testing requirements as a direct result of this exempt change. However, the new valve, flange and piping should be checked for no visible leakage and any leakage identified should be evaluated by engineering as acceptable. Operating Requirements: None required. Technical Review: The SW system is mentioned in the DSAR; therefore this modification is subject to a Technical Review in accordance with the requirements of ZAP 500-08 and the ZNPS. A Technical Review was completed under the ECNs and found to be acceptable. Other Considerations Engineering considerations are documented in ECN engineering document files. They are found to be acceptable. Page3 of4
CZE-15-005 / Environmental Considerations The removal of the Oil Separators was evaluated. As part of this activity the site will be transitioning to the Storm Water Pollution Protection Plan for storm water management. Roof drains from major buildings (Fuel Building, Auxiliary Building and Turbine Building) will now be discharged to the ground through the existing yard man ways. Oil and Grease storage will be at the guidance of the Environmental M~ager. If there are any questions regarding this exempt change, please contact Lee DuBois at 224-789-4065. PreparedB}" ~ J. L. DuBois J)~~ Design Engineering ApprovedBy~,;-JZd,
- on Roth Design Engineering Supervisor cc:
MAL ECN 50.59 Central File I I 1 Tara Pratt originals Dennis Gruh/Jam.es Gaskill 2 2 2' tony Orawiec .1 *I 1 Page4 of4
TECHNICAL REVIEW LITTER TR-010-2015 I To: Anthony Orawiec r Decommissioning Plant Manager Zion Station
Subject:
Installing an additional Service Water (SW) Dilution Pump (Pp) with increased flow rates. The purpose of this letter is to document the Technical Review of the Design Change Package for Exempt Change EC# 400985 and associated ECNs 400986 and 400987. Our conclusion, the proposed exempt change does not impact the operation of any system which may be credited in any DSAR evaluation, the methodology used to establish the design bases or in the safety analyses as described.in DSAR Chapters 3 or 5 in support of the safe storage of nuclear fuel. In conclusion, the proposed Exempt Change does not affect the design or the design function of the SW System; as well, the proposed Exempt Change does not affect the ability of SW to perform that design function. o...,is'---~---"""'~------- Prepared By:_.=Le=e....D=-u=B.... Date: 03/11/2015 Required Review Disciplines: A/ ~ ~ GJ Engineering Supervisor Qualified Technical Reviews 3-17-ltf Discipline Date
&Bfo-e-Signature Discipline Date Date Distribution:
Decommissioning Plant Manager Operations Supervisor Engineering Supervisor SRC Coordinator Master File Page 1of1
ZAP 100-06 Revision25 Infopnation Use ( ATTACHMENT D: 50.59 REVIEW COVERSHEET FORM Activity/Document Number: Design Change 400986 Revision Number: 0----
Title:
Increase the SW Pump Capacity and Elimination of the Ul & U2 Storm Drain Oil Separators NOTE: For 50.59 Evaluations, information on this form will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2). Description of Activity: (Provide a brief, concise description of what the proposed activity involves.) Design Change 400985 adds a higher capacity SW pump and eliminates the Ul & U2 Oil Seoarators. Reason for Activity: (Discuss why the proposed activity is being performed.) fncreased capacity is needed to sgpport RCA dewatering efforts and decommissioning schedules. Effect of Activity: (Discuss how the activity impacts plant operations, design bases, or safety analyses descnbed in the UFSAR.) L activity merely increases the capacity of the SW system so as to allow for quicker removal of LRW. Removal of the oil seoarators is a nanagement discretion activity and under the control of the Environmental Manager. Summary of Conclusion for the Activity's 50.59 Review: (Provide justification for the conclusion, including sufficient detail to recogniie and understand the essential arguments leading to the conclusioll. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation. or a License Amendment Request, as applicable, is not required.) The SW system and the Oil Sq?arators are not credited for any design function nor are they credited for any accident mitigation in the DSAR. Additionally. this activity merely adds capacity and does not change the design :function of the SW system. The Oil Separator
- function is being transition to the Storm Water Pollution Protection Plan.
Attachments: Attach all 50.59 Review forms completed, as appropriate. (NOTE: ifboth a Screening and Evaluation are completed, no Screening No. is required.) FM-jxxT~,:::=y.) 50.59 Screening No. Rev. 50.59 Screening
-2015-041 50.59 Evaluation 50.59 Evaluation No. Rev.
* \JJ~ o..,J -n+tS SOLS~ SC-ReE'lJLt.J~ BEGA~ 8~ 3/c~/l~ so lT UTt.Ll;cES OL'D \:D~S .. T~ i<at£SU::> 'f=D~S Do N.OT1CC\-l)..ll~'f 0 e,_ Hiµ 0\1.0~ALL~ AP-F6Cl TI4t t.N 012.tL, p~ h~ ~fte/zolS
ZAP-100-06 Revision 25 Information Use ATTACHMENT E: 50.59 APPLICABILITY REVIEW FORM Activity/Document Number: EC 400985 and ECN 400986 ECN 400987 Revision Number: 0 Address the questions below for all aspects of the Activity. tf the answer is yes for any portion of the Activity, apply the identified process(es) to that portion of the Activity. Note that it is not unusual to have more than one process apply to a given Activity. See Section 4 ofthe Resource Manual (RM)'for additional guidance. I. Does the proposed Activity involve a change:
- 1. Technical Specifications or Operating License (10CFR50.90)? X NO YES See Section 4.2.1.1 of the RM
- 2. Conditions of License Quality Assurance program (10CFR50.54(a))?
Security Plan (10CFR50.54(p))? _X_NO _X_NO -- YES YES See Section 4.2.1.2 of the RM Emergency Plan (10CFR50.54(q))? _}(_NO YES
- 3. Specific Exemptions (10CFR50.12)? _X_NO YES See Section 4.2.1.5 of the RM
- 4. . Radiation Protection Program (10CFR20)? _X_NO YES See Section 4.2.1.6 of the RM
- 5. Fire Protection Program (applicable UFSAR or operating license
_X_NO YES See Section 4.2.1.7 of the RM condition)? -
- 6. Programs controlled by the Operating License or the Technical Specifications (such as the ODCM). _X_NO - YES See Section 4.2.1.7 of the RM
- 7. Environmental Protection Program _X_NO YES See Section 4.2.1.7 of the RM
- 8. Other programs controlled by other regulations. _)(_NO YES See Section 4.2.1 of the RM II. Does the pr:oposed Activity involve maintenance which restores SSCs to their origlnal condition or involve a temporary alteration supporting maintenance that will be in effect during at-power operations for 90 days _X_NO YES See Section 4.2.2 of the RM or less?
Ill. Does the proposed Activity involve a change to the:
- 1. UFSAR (including documents incorporated by reference) that is excluded from the requirement to perfonn a 50.5~ Review by _X_NO YES See Section 4.2.3 of the RM NEI 96-07 or NEI 98-03? -
- 2. Managerial or administrative procedures governing the conduct of
_X_NO YES See Section 4.2.4 of the RM facility operations -
- 3. Procedures for performing maintenance activities (subject to 10 CFR 50.65(a)(4))? _X_NO - YES See Section 4.2.4 of the RM
- 4. Regulatory commitment not covered by another regulation based See Section 4.2.3/4.2.4 of the
_X_NO YES change process (see NEI 99-04)? - RM IV. Does the proposed Activity Involve a change to the Independent Spent Fuel Storage Installation (ISFSI) (subject to control by 10 CFR 72.48) _X_NO - YES See Section 4.2.6 ofttie RM
- v. Does the proposed Activity involve a change to the Packaging &
Transportation of Radioactive Material? (subject to control by 10CFR71) _X_NO - YES Vi. Is the proposed activity a Decommissioning Activity that does NOT require a 50.59 Screening, as described in Attachment 1 of ZS-EG-100? _X_NO - YES Check one of the following: D If all asoects of the Activity are controlled by one or more of the above processes, then a 50.59 Screening is not required and the Activity may be implemented in accordance with Its governing procedure. x If any portion of the Activity is not controlled by one or more of the above processes, then process a 50.59 Screening for the portion not covered by any of the above processes. The remaining portion of the activity should be implemented In accordance with its governing procedure. This Exempt Change affects systems discussed in the DSAR that are Important to Defueled
- l. Condition.Signoff:
50.59Screener~r:~LJ: ~~tr (Circle 6~ (Print name)
- S~n:~ ~ . (Sl9li8tllre)
Date: Lf ti""" 1'.JlJ...
~1 2f ?4
ZAP 100-06 Revision25 Information Use ( ZAP 100-06 ATTACHMENT F: 50.59 SCREENING FORM 50.59 Screening No:___,.2~0. .1~5-
. . . .04
. .__1...___ _ _ _ _ _ _.Rev No:_~o_ _
Activity/Document No: Design Change 400985 Revision No: 0- - - I. 50.59 Screening Questions (Check correct response and provide separate written response providing the basis for the answer to each question) (See Section 5 of the Resource Manual (RM) for adQitional guidance):
- 1. Does the proposed Activity involve a change to an SSC that adversely affects an - YES X NO UFSAR described design function? (See Section S.2.2.1 of the RM)
Neither the SW system nor the Storm Drain Oil Separators are required SSC per the DSAR. There are no described design functions for these systems.
- 2. Does the proposed Activity involve a change to a procedure that adversely affects
- YES _X_NO how UFSAR described SSC design functions are performed or controlled? (See Section S.2.2.l of the RM)
Procedure changes associated with this design acticity will be reviewed under a separate 50.59.
- 3. Does the proposed Activity involve an adverse change to an element of a UFSAR - YES _X_NO described evaluation methodology, or use of an alternative evaluation methodology, that is used in establishing the design bases or used in the safety analyses? (See Section 5.2.2.3 of the RM)
This activity does not involve a change to an element of a DSAR described evaluation methodology, or use of an alternative evaluation methodology, that is used in establishing the design bases or used in the safety analyses.
- 4. Does the proposed Activity involve a test or experiment not described in the
- YES _X_NO UFSAR, where an SSC is utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is inconsistent with analyses or descriptions in the UFSAR? (See Section S.2.2.4 of the.RM)
The change activity is not a test or experiment.
.*5. Does the proposed Activity require a change in the Technical Specifications or
- YES _x_NO Operating License? (S~ Section 5.2.2.5 of the RM)
No changes are required to the Zion Technical Specifications. II. List the documents (e.g., UFSAR, Technical Specifications, other licensing basis, technical, commitments, etc.) reviewed, including sections numbers where relevant information was found (if not identified in the response to each question).
ZAP 100-06 i: Revision25 Information Use ZAP 100-06 ATTACHMENT F: 50.59 SCREENING FORM 50.59 Screening No;__.;;2--=0--.1=-5-.....0.41=----------'Rev
... No:___o~-
Activity/Document No: Design Change 400985 Revision No:_O_ __ Zion DSAR 3, 4.6, ODCM, FPR Ill. Select the appropriate conditions: x If all qµestions are answered NO, then complete the 50.59 Screening and implement the Activity per the applicable governing procedure. . If question 1, 2, 3, or 4 is answered YES and question 5 is answered NO, then a 50.59 Evaluation shall be performed. If questions 1, 2, 3, and 4 are answered NO and question 5 is answered YES, then a License Amendment is required prior to implementation of the Activity.
)
If question 5 is answered YES for any portion of an Activity, then a License Amendment is . required prior to implementation of that portion of the Activity. In addition, if question 1, 2, 3, or 4. is answered YES for the remaining portions of the Activity~ then a 50.59 Evaluation shall be performed for the remaining portions of the Activity. IV. Screening Signotfs: 50.59 Screener: Paul i. Beinecke Sign: u~ Dare: 3 I 11 !?s>t5 2015 (Print riame) (Signature) 50.59 Reviewer:~ (Print name) F-"k'o"Y-tJ SignP~FC.d
. (Signature)
Date: ~~2.ols-
') . ZionSolutions LLC ZS-2016-0042: Attachments ATTACHMENT-5 ECN# 2015-04 Installation of new liquid effluent radiation monitor for ORT-PR04 and dilution flow permissive for lake discharge valve OSOV-WDO 10
I' DCP2015-04 ECNlOlS-04 Attachment 4 ZS-WC-100 Design :Changes - DCPs, ECNs, FCRs, and DCRs Revision 10
\I 1-----~~~~~~~~~~~~~~~~~~~~~~~~~~~-'-~~...;.;...._:__.....:....:;~;.;____...;_s Information Use.
Exhibit A (page* At) ENGINEERING CHANGE NOTICE (Part 1) ECNNo.~ ISSUANCE: f I FOR CONSTRUCTION [ ] FOR COMMENT Page: I or 1-r Station: ZiQ!! [ J Safety Related DesignChangeNo. 2015-04 [X] Non-Sl!fety Related . Project No.(1toppLl Affected Unit: 0 [ ] Regulatmy Supp IO No. (itlJllll~ a Changes to previollllly Approved ECN [ ] System: lS Delcription of Desiga Change Request: _ Install new radiation monitor for ORT-PR04 .and_ add a dilution flow permissive for lake discharge valve OSOV-WDOlO. Reason for J;>i!iign CbllllgC: Change and action required (Provide reason for change, specific actions required, attach supporting documents, as applicable).
) The existing sensor"for ORT-PR04 has failed and compatible parts are unavailable. The dilution flow pertnissive iS an enhancement to the existing, system to ensure adequate dilution flow is maintained for lake releases.
INTERFACING COMMENTS by Design Group or. Name ofCommcmtm" (Printed) Signature of Ccmmmter Date CorNC Discipline - - Elect.II&C Mcehanical Structural \ D&D Operations - Olbars Prepared by: it ,,,71
._4,..,~l~
l..~
-=>rAzlJ:;7~ -
Approved.by: .J.2,UJ£JM .. - . Date: Date: "-17-1. Date: aft7/2Df.s All affected design docummits revised by (date): Vmifiedby; Date: Page I of 11
*DCP 2015-04 ECN2015-04 Attachment4 ZS-WC;-100 Design Changes - DCPs, ECNs, FCRs, and DCRs Revision 10 ) L-~~~~~-----~~~~---~-~~~~~-~~----L~~-===~~~~ fu~~~
Exhibit A (pageA2) . DESIGN CHANGE DOCUMENT-AFFECTED DOCUMENT LIST
. (Part 2)
Associated With: ECN - Comment DCP Number: 2015-04 X ECN - Construction
~_FCR Other:
Part 1 - General Information :_optional fur FCR Date Prepared: 16 June 2015
) Originator: James Hausser W.O. Number:._....::2~0~1~5-=03~1~-----
Description:
_ Install new radiation monitor for ORT-PR04 and add a dilution flow pemtissive for lake discharge valve OSOV-WDOlO Part 2 - Related Design Change Documents (i.e.. ECN,FCRl Ref. Re£ No. ~ Number No. J:Y.ru! Number
- 1. DCP .,- 2015-04::- s.
- 2. ECN 2015-04 6.
- 3. -;;. 7.
- 4. 8.
Prepaml By; ~ 7~ Dato &/11{/j ReviewedBy: ~
- Date ~-o~r.:-
Page2 of It 7
DCP2015-04
-~**
ECN 2015--04 Attachment 4 ZS-WC-100 Design Changes - DCPs, ECNs, FCRs, and DCRs Revision 10 Information Use Part 2 - Affected Design Documents DESIGN DOCUMENT (DD) n Related DCDs lncorp. Rev.
~ ~* (Ref# from Part or
* ** 2 Date (Optional)
Type Number Sheet Rev. Rev Code /Page No. Date (1-Dwg I 2-Calc 3-0ther) ECN Drawings Part 4
)
*'C' for Consttuetlon m: 'R' fur Record l
**'F for Funct1.onal .!!I 'D fur Detailed
) PreparedBy: f;;Ji.c 14--nate 6/11/ls ReviewedBy: ..... .~ D_ate t- n-1.;- Pa¥e3 of /7
.. DCP2015-04 ECN2015-04 Attachment 4 ZS-WC*lOO
.Design Changes -DCPs, ~CNs, FCRs, and DCRs Revision 10
) 1..-~~~~---~~~~~~~~~~~~~~~~~~~J.._~-=Info==nn==ati=*o~n~U~s.=....re Exhibit A (pageA3)
;Baek~~p -Cal~ulation Listing (Part 2) .
- ~-,~~*A~:~*~Ti'S.J~~-~~ :; .
v~""WAU0D/~~ 8 0 -*--.*~-
, H.SJl"'
*~ ' .. ,.~~;,,;.<*i-'-IT1 1 a~':1~,fii~'l'~=~ ~:'.t:~r: -**
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.*;:,,;.%,,,ni~"" ~,;,*;, ,,.,, ..7.-11<;:;:* ,~'C' 1
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~~--~-;~-;~:.~-~* L .~:~ . ;X'fl'f~;,~~c-w:,'Jf:"~":;-\ *,.* 1 'l*~:
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None PreparedBy: ~ .c~ Date t/17./1.r Reviewed By:~ . Date t, ** 12 ~ /.J-
. 7
DCP2015-04 ECN2015-04 Attachment 4 ZS-WC-100 Design Changes - DCPs, ECNs, FCRs, and DCRs Revision 10 Information Use Exhibit A (pageA4) CERrmICATION PAGE (Part 3)
*ECN No: 2015-04 Design Change No.: 2015-04
. Page 5 of . \ll
-_.-**-- ~---~ -- ----*
CERTIFICATION OF ECN NO. _ _ __;;;N--./A.. . . .___ _ _ _ ___;_
)
I certify that this Engineering Change Notice was prepared by me or under my supervision and that I am a registered Professional Engineer under the laws of the State of Illinois.
'l Certified by:_ _ _ _---:..:N=/A-=-----------Date:_*_ _ _ _ __
Seal
.PreparedBy: ~?~ Date t/t'-1/IS Reviewed By: ------' j;r Datet... 17- ,.;-
Pa~e S of 11
Station: Zion DCP2015-04 Affected Unit: 0 ECN2015-04 Part 4 - Construction Support Information
- 1. ORT-PR04/0SOV-WD010 Control Panel Construction Note:
Steps in Section 1 can be performed in any logical order at the discretion ~ ** of the responsible work group. \ I .a. Install components and wire according to Sketch 7 1.b. , Obtain PR04 electronics module from Engineering and mount on right side of control panel as shown on Sketch 1. 1.c. Request Engineering to program the Pico control relay. I .d. With Engineering assistance, apply power to the control panel and verify proper operation of the control relay, control switches, and indicating lights.
- 2. Field Installation Note:
The steps of section 2 can be performed in any logical order at the discretion of the responsible work group. 2.a. At unit 2 boric acid tank room, determinate and remove the test cart associated with ORT-PR04. 2.b. At unit 2 boric acid tank room, install new PR04/WD010 control panel on wall. 2.c. At unit 2 boric.acid tank room, determinate and remove ca.hies from 120 Vac junction box. 2.d. At unit 2 boric acid tank room, install new 120 Vac jUJ;lction box and terminal strip as depicted in$ketch 1. 2.e. At unit 2 boric acid tank room, terminate cable 04264 at temrinal strip in. new junction box as shown in Sketch l. 2.f. At unit 2 boric acid tank room, field route and tenninate Cable C at new 120 Vac junction box and PR04/WD010 control panel as shown on Sketches 1 and 7. ~ 2.g. At unit 2 boric acid tank room, terminate cable "B" in PR04/WD010 control panel as shown in Sketch 7. 2.h. At unit 2 boric acid tank room, plug OPS into wall outlet supplied by 120 Vac jlln.ction box. 2.i. At unit 2 boric acid tank room, plug cable B" into UPS as. depicted in Sketch 1. .) 2.j. Above 480 V SWGR 232, connect cables 75316 and 75323 as shown on Sketch 9. Prepan:dBy: ~n... 6/1?/l.r ReviewedBy: ~~Date C**/7- /!>,. Page6ofJ1
Station: Zion DCP2015-04 Affected Unit: 0 ECN201S..04 Part 4 - Construction Support Information 2.k. At Unit 2 valve house, field route cable OSWOOS from OSW1001A starter to flow transmitter OFIT-SW054B. 2.1. Terminate cable OSWOOS at OSWl OOlA starter and flow transmitter OFIT-SW054B as shown on Sketch 9. 2.m. .At new PR04/WD010 control panel, terminate the following cables as shown on Sketch 7:
*- Cable "B" from PR04 UPS
** Cable "C" :from* 120 Vac Junction Box
.;-.' Cable 75323
- Wire pair associated with ADS Alarm Zone 505
- f
- Wire pair associated with ADS Alarm Zone 506
** Wire pair associated with ADS Alarm Zone 512
- Wire pair associated with ADS Alarm Zone 513
- 3. Functional Testing
)
Note: Engineering and RP:*'f.echnician assistance are required for the following steps. Note: The steps in Section 3 can be performed in any logical order at the direction of Engineering and RP Instrument Technician. 3.a.
- Isolate qsoV-WDOl 0 to allow cycling of the valve for testing pw:poses.
3.b. Verify Dilution Pumps OSWlOOlA and OSWlOOlB are shut off. 3.c. .At PR04/WD010 control panel, verify all five fuses are pulled out. 3.d. At PR04/WD010 contr,ol panel, insert Fuse Fl and verify 24 Vdc power supply and PR04 electronics module are both energized. 3.e. At PR04/WD010 control panel, insert Fuse FS and verify all four (4) red lights on the control panel illuminate. 3.f. At PR04/WD010 control panel, PRESS PR04 Alarm Reset Push Button and VERIFY relays PR04~RLY01 and PR04-RL02 energize and remain energized (Ref. Sketch 3). ) 3.g. At PR04/WD010 control pan~l, insert Fuse F2 and verify Pico relay energizes. Prepared By: ~~ Date 6/Jlf/.r Reviewed By:
- Date~ *fl- t!z ..--
Station: Zion DCP2015..04 Affected Unit: 0 ECN2015-04 Part 4 - Construction Support Information 3.h. At PR04/WD010 control panel, insert Fuses F3 and F4. 3.i. At Engineering and RP Instrument Tech direction, verify the following (Lift Leads and install jumpers as* necessary to simulate normal/alarm conditions. Reset logic and alarms as necessary). .__ o Open Fuse Fl and verify light indication and ADS alanns are received for both PR04 Inst. Alarm and Inst. Fail.
- Induce PR04 high radiation alann and verify proper light indication and ADS alarm.
- Using a jumper, CYCLE Dilution Pump Running/Trip alarm and verify proper light indication and ADS alarm.
- Using a jumper, CYCLE low dilution pump flow alarm and verify proper light indication and ADS Alarm.
ti With ORT-PR04 Test Switch in TEST, verify valve cycles with receipt of either PR04 radiation or instrument fail alarm. Verify this operates independently of control switch for OSOV-WDOI 0 position as well as other alarm conditions.
) e* With OSOV-WDOlO control switch in AUTO, verifyOSOV-WDOlO closes upon -* receipt of any of the individual alanns. Also verify that the valve will NOT open until the appropriate reset button is actuated.
- ci With OSOV-WDOlO control switch in OPEN~ verifyOSOV-WDOlO remains open regardless ofORT-PR04 alarm status. Al~o verify valve closes upon receipt of any alarm other than ORT-PR04.
4~ Post Installation Calibration 4.a. Request RP perform the appropriate calibration sunreillances to enable placing ORT-PR04-in service. } Prepared By: ~ ~ Date f/11/lf ReviewedBy: ~: ; . Date t.-{l-1.:,- Page8 of~11
r-----~-----~-----------------------------------1 I I I I I Cable 04264 I Cable "C" 1 1 I 3/C#14 I 3/C#14 I I 1 J 120Vac JB
.:.i; RLC #31 Ckt"L"
_In #2. BA J--------1-' ----t..,.....f---------------------,
- Tank Room :
I I I I I I I I .1 I I I I I ORT-PR04 ORT-PR04 Alarm ~ Alarm Reset a0 a : I ORT-PR04 lhst. Fail ~ au Normal I Test Dilution Pump Trip/Off~ 0
~
0 Dil~tion Low Flow ~ ORT-PR04 OSOV-WD010 Open~ TO PR04 Sensor Test Switch PR04 UPS 0 Existing Equipment I I Installed Per ECN 389831 and TA 15-004 I I f Auto j Close I Open I: 0 SOV~WD010 (/) Logic Reset Cable"E"
- e>
OSOV-WD010
©. 7/C.#18 Cable "B" OSOV-WD010 Test Points Control switch 3/C#14 Cable"D" 3/C#14 Cable From ADS Alarm System 4-Pair #16 --~
See EC 399569 Cable 75323n5316 4/C#12----- CABLE
- 00. See EC 400987 "0426411' Sllpplyto 00 Outlet Box/
00 00 UPS Sketch 1 00 Part4
. GROUND - - + - - - " - . J ECN No. 2015~04 Isolation Valve Page '1 of 11 OSOV-WD010 Mod. 'No. 2015-04 120VAC Prepared by: ~ ?~
JB Date: 6/11-/t.rP IN#2BA Reviewed by:...r-<ll'.qb. .. TANK ROOM Date: t- iz-rs
OSOV-WD010 ORT-PR04 ORT-PR04 Control Switch Test SWitch Dilution Pump Dilution Pump Low Flow Running Alarm Close Auto Alarm Fail Open Test Normal I
\/ ,~
)
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June 17, 2015 CZE-15-010 To: A. Orawiec
Subject:
Zion Station, Unit 1 & 2 Design Change No. 2015-004 System Codes: PR The Engineering Department has reviewed the subject design change in accordance with ZS-WC-100. Applicable design input requirements are included in the design change approval letter as applicable. *
- Description of Change:
This design change addresses the design issues required to replace ORT-PR04 with a new detector unit and electronics module. The functionality of the original equipment will be maintained. This design change also adds an interlock to ensure closure of OSOV-WDOl 0 due to inadequate dilution flow as measured by flow transniitter OFIT-SW054B. The logic for discharge valve OSOV:-WDOl 0 will be configured such that the valve will automatically close upon receipt of any of the following signals:
~* ORT-PR04 Alarm or Instrument Fail
- Trip of a dilution p~p or no dilution pump running e: U>w dilution flow from OFIT-SW054B Design Change Package:
The design for this Design Change is contained in ECN 2015-04 which is issued "For Construction" by this letter. 10 CFR 50.59 Evaluation I Decommissioning Impact Evaluation: 10CFR 50.59 screening 2015-066 was performed in accordance with AD-11 and is being transmitted along with this letter. This activity can be implemented without prior NRC approval. A Decommissioning Impact Evaluation was performed and it was concluded that the proposed activity is not restricted by 10 CFR 50.82. The ~valuation is also being transmitted along with this letter.
- DSAR I ODCM Impact Review:
DSAR Chapters 1 through 6 were reviewed for this design change. No DSAR changes are required as a result of this design change. Additionally, a review of the ODCM was conducted. No ODCM changes are planned as a result of this design change. ) Page 1of3
June 17, 2015 CZE-15-010 1 Applicable Codes and Standards: This design change shall be installed in accofdance with Zion Specification X-3646, which is the general work specification for mechanical, structural and electrical work as well as applicable site and Zion Solutions procedures. Installation requirements identified in ECN 2015-04 supersede X-3646 guidance. Basic Functions: ORT-PR04 monitors the liquid radiation waste release point to the service water system* and ultimately Lake Michigan. An alarm signal from ORT-PR04 will result in automatic closure of discharge valve OSOV-WDOl 0. The valve will also receive automatic closure signals due to either low dilution flow or trip of a running dilution pump. Industrial Safety: There are no industrial safety concerns associated with this design change. Installation Schedule I Outage Requirements: I Installation of this design change will require that valve OSOV*WDO 10 be out of service.
- ) Technical Specification Changes:
- The existing Technical Specifications do not require revision as a result of this design change. ,
ALARA I Fire Protection Review: Ali ALARA review was performed for this exempt change. The bulk of the work is being performed in the Unit 2 boric acid tank room. Any additional cable adds minimal combustibles and will not contn'bute significantly to the combustible loading. Impact of Pending Modifications or Temporary Alterations: A review of pending design changes has been completed. This design change does not impact any pending modifications. This Design Change Package (DCP) is being issued to document the installation of a new detector and electronics module for ORT-PR04 and to add an automatic closure of OSOV-WDOlO due to low flow in the dilution system. Identification of the Installer: This Design Change will be performed by Zion Solutions or an approved contractor. . } Page 2 of 3
June 17, 2015 CZE-15-010 Procurement Requirements: None Training Reguirements: None Security Requirements: None Technical Review: This design change is subject to a Technical Review in accordance with the requirements ofAD-1. A Technical Review has been performed and submitted with this design package (TR:.Ol 7-2015). If there are* any questions regarding this design change, please contact Jim Hausser at 224-789-4285. Prepared By: f~ l ~
/Jim Hausser
- Zion Solutions Engineering.
Approved By: ~F./2:t£
--D. Roth . . .
DrrectorofEngineering MAL ECN 50.59 50.82 Central File 1 1 1 1 D.Roth 1 l 1 1 J.Hausser 1 1 1 l T. Lukken 1 1 1. t Page 3of3
AD-11 RevisionO Information Use ATTACHMENT B-1 50.59 Review Coversheet Form
-=---=-----
Station: Zion
- Acth>ity/Document Number: DCP 2015--04._ _ _ _ _ _ _ _ _Revision Number: !!
Title:
Install New Radiation Monitor for ORT-PR04 NOTE: For SO.S9 Evaluations, information on this form will provide the basis for preparing the biennial summary report submitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2). Description of Activity: (Provide a briet; concise description of what the proposed activity involves.) This modification will replace the sensor and rate counting module for liquid radiation monitor ORT-PR04. A permissive signal requiring adequate dilution system flow to allow opening of lake discharge valve OSOV-WDOl 0 will also be added by this change.
- Reason for Activity:
(Discuss why the proposed activity is being performed.) The sensor for the existing radiation monitor has failed and compatible replacement parts are unavailable. The addition of the dilution flow pemnssive is a system enhancement.
- Effect of Activity:
(Discuss how the activity impacts plant operations, design bases, or safety analyses descn"bed in the UFSAR.) The radiation monitor will generate a signal to automatically close lake discharge valve OSOV-WD010 upon detection of a high radiation level. Likewise, the dilution flow permissive will cause an automatic closure of the lake discharge valve should dilution flow drop below prescn"bed levels. These automatic actions are enhancements to sampling and periodic ~onitoring to ensure compliance With the ODCM. The modification does not affect the accident evaluated in the DSAR. Summary of Conclusion for the Activity's 50.59 Review: (Provide justification for the conclusion, including sufficient detail to recognize and understand the essential arguments leading to the conclusion. Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment Request, as applicable, is not required.) The modification only changes the specific devices used to monitor the liquid radiation waste discharge. The function of the devices remains unchanged. This modification does not represent a change to the facility as described in the DSAR and it may be installed under 10CFRS0.59 without prior NRC approval. Attachments: Attach all S0.59 Review forms completed, as appropriate. (NOTE: if both a Screening and Evaluation are completed, no Screening No. is required.) Forms Attached: (Check all that apply.) Applicability Review 1------1 x 50.59 Screening 50.59 Sc~ No. 2015-066 Rev. 0 ) 50.59 Evaluation 50.59 Evaluation No. Rev.
AD-11 Revision 0 Information Use
.I ATTACHMENT C-1 50.59 APPLICABILITY REVIEW FORM Actfvlty/Doeument Number:_ DCP 201S..04_ _ _ _ _ _ _ _ _ _ _ _Revisioo Number:_o._ _ __
Address the questions be1ow for all aspects of the Activity. If the answer is yes for any portion of the Activity, apply the identified process(es) to that portion of the Activity. Note Chat it is not unusual to have more than one process apply to a given Activity. See Section 4 of the Resource Manual (RM) fur additional guidance. I. Does the proposed Actimymvolve* a chiDge:. -
- 1. Technical Snccifications or Operating License (10 CFR 50.90)? xNO YES Sec Section 4.2.1.1 of the RM
- 2. Conditions ofLicense
_xNO - YES . Quality Assurance program (10 CFR SO.S4(a))? _x NO - YES Sec Section 4.2.1.2 oftheRM* Security Plan (IO CFR S0.54(p))? _xNO YES Emergency Plan (10 CFR 50.S4(q))? -
- 3. Specific Exemptions (10 CFR 50.12)? _xNO - YES See Section 4.2.l.5 of the RM YES See Section 4.2.1.6 of the RM
- 4. Radiation Protection Program (10 CFR20)?
- 5. Fire Protection Program (applicable UFSAR or operating license
_xNO
.JoNO - YES See Section 4.2.1.7 of the RM condition)?
- 6. Programs controlled by the Operating License or fhe TcclmicaJ Specifications (such as the ODCM).
_xNO
- YES See Section4.2.l.7 oftheRM 7.*Environmental Protection Program _xNO - YES See Section 4.2.1.7 of the RM See Section 4.2.1 of the RM
- 8. Other programs control1ed by other regulations. _xNO - YES 10CFRS0.37
) Does the proposed Activity involve maintenance which restores SSCs to their original condition or involve a temporary alteration supporting II.
maintenance that will be in effect during at-power operations for 90 days _xNO
- YES See Section 4.2.2 of the RM or less?
Ill. Does the nrooosed Activity involve a change to the:
- 1. UFSAR (including documents incorporated by reference) that is excluded from the requirement to perform a 50.59 Review by _xNO - YES See Section 4.23 of the RM NEI 96-07 or NEI 98-03?
- 2. Mariagerial or administrative procedures governing the conduct of _xNO
- YES See Section 4.2.4 of the RM facility operations
- 3. Proeedures for performing maintenance activities (subject to l 0 CFR
_xNO - YES See Section 4.2.4 of the RM 50.6S(a)(4))?
- 4. Regulatmy commitment not covered by another regulation based change process (see NEI 99-04)?
_xNO
- YES See Section 4.2.3/4.2.4 of the RM Does the proposed Activity involve a change to the Independent Spent IV. Fuel Storage Installation (ISFSl) (subje¢ to control by 10 CFR 72.48) _xNO .,
YES See Section 4.2.6 of the RM Does the proposed Activity involve a change to the Packaging &
- v. Transportation of Radioactive Material? (subject to control by 10 CFR 71)
_xNO -YES Is the proposed activity a Decommissioning Activity that requires a _xNO VI. - YES Change to DSAR Chapter 3, 4 or 5 thereby requiring a 50.59 Screening. Check one of the following: CJ If a)I asnccts of the Activity are controlled by one or more of the above p~ the~ a 50.59 Screening is nm required and the Activity may be implemented in accordance with its governing procedure. X If anv portion of the Activity is not controlled by one or more of the above processes, Chen process a 50.59 Screening fur the portion not covered by any of the above processes. The remaining portion of the activity should be implemented in ) accordancewithits~. * , ~
- I"""
Signotr: S0.59 Scrc:cn 150.59 Evalua Garv F. Fanning Si * * ~: £' */ 7- ~ . (Circle (Print name) (Sign ~
AD-11 Revision 0 Information Use ATTACHMENT D-1 50.59 Screening Form 50.59 Screening No. _2015-066_ Rev. No. ~o__ Activity/Document Number:_DCP 2015-04_ _ _ _ _ _ _ _ _ Revislon Number:_ _o___ I. 50.59 Screening Questions (Check concct response and provide separate written response providing the basis for the answer to each question) (See Section 5 of the Resource Manual (RM) for additional guidance):
- 1. Does the proposed Activity involve a change to. an SSC that adversely affects YES _x_NO
~~"
an UFSAR descn"bed design function? (See Section 5.2.2.1 of the RM) The function of liquid radiation monitor ORT-PR04 is unchanged by this modification. The only change is to the actual equipment used to perform the design function. The addition of the dilution flow permissive for the lake discharge valve iS a system enhancement.
- 2. Does the proposed Activity involve a change to a procedure that adverseiy * '*=?_).'ES _x_NO affects how UFSAR dcscnoed SSC design functions are performed or controlled? (See Section 5.2.2.2 of the RM)
The only procedures affected by this change are those directly related to the
. physical device installed. The function of the radiation monitor and responses J to 81ann conditions are not altered by this design. change.
- 3. Does the proposed Activity involve an adverse change to an element of a ~- -. YES _x_NO UFSAR descnbed evaluation methodology, or use of an alternative evaluation methodology, that is used in establishing the design. bases or used in the safety
(} analyses? (See Section S.2.2.3 of the RM) There are no evaluation methods altered by this change. This change will only alter the equipment used to monitor lake releases. Methods for detemtining the alarm setpoints ~not affected by this change.
- 4. Docs the proposed Activity involve a test or experiment not descnbed in the . ..
YES _x_NO UFSAR. where an SSC is utilized or controlled in a manner that is outside the reference bounds of the design for that SSC or is inconsistent with analyses or descriptions in the UFSAR? (See Section 5.2.2.4 of the RM) The replacement of the radiation monitor and addition of the flow interlock do not represent a test or experiment not descnbed in the UFSAR. The function of the radiation monitor is not altered by this change.
- 5. Does the proposed Activity require a change in the Technical Specifications or ~YES* _x_NO Operating License? (See Section S.2.2.5 of the RM)
The new radiation monitor equipment will support operation of the liquid~ waste system as described in DSAR sections 4.5 and 4.6. The riew monitoring equipment will also support plant operations as described in ODCM section 10.2.2.l and tables 12.2-1and12.2-2. No changes to anyplant licensing ,.i documents are required for this design change.
AD*ll Revision 0 Information Use II. List the documents (e.g., UFSAR, Technical Specifications, other licensing basis, technical, commitments, etc.) reviewed, including sections numbers where relevant information was found (if not identified in the response to each question). DSAR Change 2013-010 DSAR Chapters 1 through 6 Zion Stadon Offsite Dose Calculation Manual (0DCM) Permanently Defueled Technical Specifications (PDTS) Zion Station Unit 1 and 2 Composite Licenses IIL Select the appropriate conditions: If all questions are answered NO, then complete the S0.59 Screening and implement the Activity per x the applicable governing procedure. If question 1, 2, 3, or4 is answered YES and question 5 is answered NO, then a 50.59 Evaluation shall be perfornied. If questions 1, 2, 3, and 4 are answered NO and question 5 is answered YES, then a License Amendment is required prior to implementatiOn of the Activity. If question 5 is answered YES for any portion of an Activity, then a License Amendment is required prior to implementation of that portion of the Activity. In addition, if question 1, 2, 3, or 4 is answered YES for the remaining portions of the Activity, then a 50.59 Evaluation shall be performed for the remaining portions of the Activity. *
) IV. Screening Slgnoffs:
50.59 Screener: Gaty F. Fanning Date: t, t/7 /rt~ *
. (Print ipupe) 50.S9 Reviewer: D~~ F: k'o'N Date:~ ll'"ll~ii;;
(Print name)
- J
TECHNICAL REVIEW LETTER TR/017/2015 To: T. Orawiec Decommissioning Plant Manager Zion Station
Subject:
DCP 2015-004. Replace ORT-PR04 Summary: The purpose of this Technical Review Is to provide basis and justification for replacing the original ORT-PR04 detector and electronics unit with new equipment. This design change package will also add logic to automatically close OSOV-WD010 due to low dilution flow measured by flow transmitter OFIT-SW054B. Prepared By: James C. Hausser 6//7//S" Date Required review Dlsclpllnes: A,8,' 6'
- JZJ/r:/U Engineering Supervisor Qualified Technical Reviewers
/
l-17-1~. Discipline Date G-1Z?:-15 Discipline Date Signature Discipline Date
- I Concur and Approve: -~-.ZS:._!ll_.,,;,~CZ------
Deco"1mlSSIOning Plant Manager Distribution: Decommissioning Plant Manager Operations Manager Engineering Manager SRc*coordinator Master File
ZionSolutions LLC ZS-2016-0042: Attachments ATTACHMENT 6 Zion Station ODCM, Rev. 5
Revision 5 Aug 31, 2015 Zion Station Offsite Dose Calculation Manual Docket Numbers: 50-295, 50-304 and 72-1037 Page 1of267
Revision 5 Aug 31, 2015 OFFS/TE DOSE CALCULATION MANUAL TABLE OF CONTENTS PAGE Chapter 1 Introduction 3 Chapter 2 Regulations and Guidelines 4 Chapter 3 Pathways 13 Chapter 4 Introduction to Methodology 16 Chapter 5 Measurement 27 Chapter 6 Implementation of Offsite Dose Assessment Program 28 Chapter 7 References 29 Chapter 8 Deleted 34 Chapter 9 Deleted 35 Chapter 10 Radioactive Effluent Treatment System and Monitoring 36 Chapter 11 Radiological Environmental Monitoring Program 44 Chapter 12 Radiological Effluent Technical Standards 54 Appendix A Compliance Methodology 99 Appendix B Models and Parameters for Airborne and Liquid Effluent Calculations 129 Appendix C Generic Data 159 Appendix D Deleted 176 Appendix E Deleted 177 Appendix F Station Specific Data 178 Appendix 0 ODCM Bases and Reference Document 251 Page 2 of 267
Revision 5 Aug 31, 2015 CHAPTER 1 INTRODUCTION
1.0 INTRODUCTION
The Offsite Dose Calculation Manual (ODCM) presents a discussion of the following:
- The basic concepts applied in calculating offsite doses from Zion Station effluents.
- The regulations and requirements for the ODCM and related programs.
- The methodology and parameters for the offsite dose calculations used to assess impact on the environment and compliance with regulations.
The methodology detailed in this manual is intended for the calculation of radiation doses during routine (i.e., non-accident) conditions. The calculations are normally performed using a computer program. Manual calculations may be performed in lieu of the computer program. The dose effects of airborne radioactivity releases predominately depend on meteorological conditions (wind speed, wind direction, and atmospheric stability). For airborne effluents, the dose calculations prescribed in this manual are based on historical average atmospheric conditions. This methodology is appropriate for estimating annual average dose effects and is stipulated in the Bases Section of the Radiological Effluent Technical Standards (RETS). 1.1 STRUCTURE OF THIS MANUAL Chapters 1 thru 7 provide a brief introduction and overview of Zion Stations offsite dose calculation methodology and parameters. Chapters 10 thru 12 provide specific requirements for the treatment and monitoring of radioactive effluents covered by the Radiological Environmental Monitoring Program (REMP) and the Radiological Effluent Technical Standards (RETS). Appendices A and B provide detailed information on specific aspects of the methodology. Appendix C contains tables of values of the generic parameters used in offsite dose equations. Appendix F contains tables of values for the parameters used in the offsite dose equations. Appendix 0 provides description of the bases for the methodology and parameters discussed in the ODCM. Page 3 of 267
Revision 5 Aug 31, 2015 CHAPTER2 REGULATIONS AND GUIDELINES
2.0 INTRODUCTION
This chapter of the ODCM serves to illustrate the regulations and requirements that define and are applicable to the ODCM. Any information provided in the ODCM concerning specific regulations are not a substitute for the regulations as found in the Code of Federal Regulations (CFR) or Quality Assurance Project Plan (QAPP). 2.1 CODE OF FEDERAL REGULATIONS Various sections of the Code of Federal Regulations (CFR) require nuclear power stations to be designed and operated in a manner that limits the radiation exposure to members of the public. These sections specify limits on offsite radiation doses and on effluent radioactivity concentrations and they also require releases of radioactivity to be "As Low As Reasonably Achievable". These requirements are contained in 10CFR20, 10CFR50, 10CFR72 and 40CFR190. In addition, 40CFR141 imposes limits on the concentration of radioactivity in drinking water provided by the operators of public water systems. 2.1.1 10CFR20, Standards for Protection Against Radiation The 10CFR20 dose limits are summarized in Table 2-1. 2.1.2 Design Criteria (Appendix A of 10CFR50) Section 50.36 of 10CFR50 requires that an application for an operating license include proposed Technical Specifications. Final Technical Specifications are developed through negotiation between the applicant and the NRC. The Technical Specifications are then issued as a part of the operating license, and the licensee is required to operate the facility in accordance with them. The remaining Defueled Technical Specification requirements have been relocated to the QAPP. Section 50.34 of 10CFR50 states that an application for a license must state the principal design criteria of the facility. Minimum requirements are contained in Appendix A of 10CFR50. 2.1.3 ALARA Provisions (Appendix I of 10CFR50) Sections 50.34a and 50.36a of 10CFR50 require that the nuclear plant design and the station RETS have provisions to keep levels of radioactive materials in effluents to unrestricted areas "As Low As Reasonably Achievable" (ALARA). Although 10CFR50 does not impose specific limits on releases, Appendix I of 10CFR50 does provide numerical design objectives and suggested limiting conditions for operation. According to Section I of Appendix I of 10CFR50, design objectives and limiting conditions for operation, conforming to the guidelines of Appendix I "shall be deemed a conclusive showing of compliance with the "As Low As Reasonably Achievable" requirements of 10CFR50.34a and 50.36a." An applicant must use calculations to demonstrate conformance with the design objective dose limits of Appendix I. The calculations are to be based on models and data such that the actual radiation exposure of an individual is "unlikely to be substantially underestimated" (see 10CFR50 Appendix I, Section 111.A.1 ). The guidelines in Appendix I call for an investigation, corrective action and a report to the NRC whenever the calculated dose due to the radioactivity released in a calendar quarter exceeds one-half of an annual design objective. The guidelines also require a surveillance program to monitor releases, monitor the environment and identify changes in land use. Page 4 of 267
Revision 5 Aug 31, 2015 2.1.3 10CFR72, Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste During normal operations and anticipated occurrences, the annual dose equivalent to any real individual who is located beyond the Controlled Area must not exceed 25 mrem to the whole body, 75 mrem to the thyroid and 25 mrem to any other critical organ as a result of exposure to:
- Planned discharges of radioactive materials, radon and its decay products excepted, to the general environment,
- Direct radiation from ISFSI or MRS operations, and
- Any other radiation from uranium fuel cycle operations within the region.
2.1.4 40CFR190, Environmental Radiation Protection Standards for Nuclear Power Operations Under an agreement between the NRG and the EPA, the NRG stipulated to its licensees in Generic Letter 79-041 that "Compliance with Radiological Effluent Technical Specifications (RETS}, NUREG-0472 (Rev.2) for PWR's or NUREG-0473 (Rev.2) for BWR's, implements the LWR provisions to meet 40CFR190". (See reference 103 and 49.) The regulations of 40CFR190 limit radiation doses received by members of the public as a result of operations that are part of the uranium fuel cycle. Operations must be conducted in such a manner as to provide reasonable assurance that the annual dose equivalent to any member of the public due to radiation and to planned discharges of radioactive materials does not exceed the following limits:
- 25 mrem to the total body
- 75 mrem to the thyroid
- 25 mrem to any other organ An important difference between the design objectives of 10CFR50 and the limits of 40CFR190 is that 10CFR50 addresses only doses due to radioactive effluents. 40CFR190 limits doses due to effluents and also to radiation sources maintained on site. See Section 2.4 for further discussion of the differences between the requirements of 10CFR50 Appendix I and 40CFR190.
2.1.5 40CFR141, National Primary Drinking Water Regulations The following radioactivity limits for community water systems were established in the July, 1976 Edition of 40CFR141:
- Combined Ra-226 and Ra-228: ~ 5 pCi/L.
- Gross alpha (particle activity including Ra-226 but excluding radon and uranium): ~ 15 pCi/L.
- The average annual concentration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annual dose equivalent to the total body or any internal organ greater than 4 mrem/yr.
The regulations specify procedures for determining the values of annual average radionuclide concentration which produce an annual dose equivalent of 4 mrem. Radiochemical analysis methods are also specified . . The responsibility for monitoring radioactivity in a community water system falls on the supplier of the water. However, Zion Station has requirements related to 40CFR141 in their specific RETS. For calculation methodology, see Section A.6 of Appendix A. Page 5 of 267
Revision 5 Aug 31, 2015 2.2 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS The Radiological Effluent Technical Standards (RETS) were formerly a subset of the Technical Specifications. They implement provisions of the Code of Federal Regulations aimed at limiting offsite radiation dose. The NRC published Standard Radiological Effluent Technical Specifications for PWRs (Reference 2) as guidance to assist in the development of technical specifications. These documents have undergone frequent minor revisions to reflect changes in plant design and evolving regulatory concerns. The Radiological Effluent Technical Specifications have been removed from the Technical Specifications and placed in the ODCM as the Radiological Effluent Technical Standards (RETS) (see Reference 90). The Zion Station RETS are similar, but not identical to the guidance of the Standard Radiological Effluent Technical Specifications. 2.2.1 Categories The major categories found in the RETS are the following:
- Definitions A glossary of terms (not limited to the ODCM).
- Instrumentation This section states the Operability Requirements (OR) for instrumentation performance as well as the associated Surveillance Requirements. The conservative alarm/trip setpoints ensure regulatory compliance for both liquid and gaseous effluents. Surveillance requirements are listed to ensure ORs are met through testing, calibration, inspection and calculation. Also included are the bases for interpreting the requirements. The Operability Requirement (OR) is the ODCM equivalent of a Limiting Condition for Operation (LCO) as defined in both the NRC published Standard Radiological Effluent Technical Specifications and the stations' Technical Specifications.
- Liquid Effluents This section addresses the limits, special reports and liquid waste treatment systems required to substantiate the dose due to liquid radioactivity concentrations to unrestricted areas. Surveillance Requirements and Bases are included for liquid effluents.
- Gaseous Effluents This section addresses the limits, special reports and gaseous radwaste and ventilation exhaust treatment systems necessary for adequate documentation of the instantaneous offsite radiation dose rates and doses to a member of the public. Surveillance Requirements and Bases are included for gaseous effluents.
- Radiological Environmental Monitoring Program
_ This section details the Radiological Environmental Monitoring Program (REMP) involving sample collection and measurements to verify that the radiation levels released are minimal. This section describes the annual land use census and participation in an interlaboratory comparison program. Surveillance Requirements and Bases are included for environmental monitoring.
- Reports and Records This section serves as an administrative guide to maintain an appropriate record tracking system. The management of procedures, record retention, review/audit and reporting are discussed.
Page 6 of 267
Revision 5 Aug 31, 2015 2.3 OFFSITE DOSE CALCULATION MANUAL The NRG in Generic Letter 89-01 defines the ODCM as follows (not verbatim) (see Reference 90): The Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs and (2) descriptions of the Information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports. Additional requirements for the content of the ODCM are contained throughout the text of the RETS. 2.4 OVERLAPPING REQUIREMENTS In 10CFR20, 10CFR50, 10CFR72 and 40CFR190, there are overlapping requirements regarding offsite radiation dose and dose commitment to the total body. In 10CFR20.1301 the total effective dose equivalent (or TEDE) to a member of the public is limited to 100 mrem per calendar year. In addition, Appendix I to 10CFR50 establishes design objectives on annual total body dose or dose commitment of 3 mrem per reactor for liquid effluents and 5 mrem per reactor for gaseous effluents (see 10CFR50 Appendix I, Sections II.A and ll.B.2(a)). Per 10CFR72, the annual dose equivalent to a real individual beyond the controlled area boundary is limited to 25 mrem whole body from both effluents and direct radiation combined. Finally, 40CFR190 limits annual total body dose or dose commitment to a member of the public to 25 mrem due to all uranium fuel cycle operations. While these dose limits/design objectives appear to overlap, they are different and each is addressed separately by the RETS. Calculations are made and reports are generated to demonstrate compliance to all regulations. Refer to Tables 2-1, 2-2 and 2-3 for additional information regarding instantaneous effluent limits, design objectives and regulatory compliance. 2.5 DOSE RECEIVER METHODOLOGY Table 2-2 lists the location of the dose recipient and occupancy factors, if applicable. Dose is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures with the exception of dose from contained sources. The dose calculation methodology is consistent with the methodology of Regulatory Guide 1.109 (Reference 6), NUREG 0133 (Reference 14) and NRG ISG-13 Rev. 0, Spent Fuel Project Office Interim Staff Guidance - 13 Real Individual, May 17, 2000 (Reference 108). The "maximum individual" is characterized as "maximum" with regard to food consumption, occupancy and other usage of the area in the vicinity of the plant site. Occupancy of a "maximum individual" is not used in dose assessments from contained sources. Such a "maximum individual" represents reasonable deviation from the average for the population in general. In all physiological and metabolic respects the maximum individual is assumed to have those characteristics that represent averages for their corresponding age group. When calculating dose attributed to contained sources for the "maximum individual" dose receptor location, occupancy is defined as a habit for a "real individual" at that location. 100% occupancy is not assumed when calculating dose from contained sources. Finally Table 2-3 relates the dose component (or pathway) to specific ODCM equations and the appropriate regulation. Page 7 of 267
Revision 5 Aug 31, 2015 Table 2-1 Regulatory Dose Limit Matrix REGULATION DOSE TYPE DOSE LIMIT(s) ODCM EQUATION Airborne Releases: (quarterly) (annual) 10CFR50 App. I~ Gamma Dose to Air due to Noble Gas 5 mrad 10 mrad A-1 Radionuclides (per reactor unit) Beta Dose to Air Due to Noble Gas 10 mrad 20 mrad A-2 Radionuclides (per reactor unit) Organ Dose Due to Specified Non-Noble 7.5 mrem 15 mrem A-7 Gas Radionuclides (per reactor unit) Total Body and Skin Total Body 2.5 mrem 5 mrem A-3 Dose {if air dose is exceeded} Skin 7.5 mrem 15 mrem A-4 QAPP Organ Dose Rate Due to Specified Non- 1,500 mrem/yr A-16 Noble Gas Radionuclides (instantaneous limit, per site) Liquid Releases: (quarterly) (annual) 10CFR50 App. I~ Whole (Total} Body Dose 1.5 mrem 3 mrem A-17 (per reactor unit) Orqan Dose (per reactor unit) 5 mrem 10 mrem A-17 QAPP The concentration of radioactivity in liquid Ten (10) times the effluents released to unrestricted areas concentration values A-21 listed in 10CFR20 Appendix B; Table 2, Column2 Total Doses ': 10CFR20.1301 (a)(1) Total Effective Dose Equivalent q 100 mrem/vr A-25 10CFR20.1301 (d}, Total Body Dose 25 mrem/yr A-25 10CFR72.104 (a} and 40CFR190 Thyroid Dose 75 mrem/vr A-25 Other Orqan Dose 25 mrem/vr A-25 Other Limits ;t: 40CFR141 Total Body Dose Due to Drinking Water 4 mrem/yr A-17 From Public Water Systems Organ Dose Due to Drinking Water From 4 mrem/yr A-17 Public Water Svstems 1 These doses are calculated considering all sources of radiation and radioactivity in effluents. 2 These limits are not directly applicable to nuclear power stations. They are applicable to the owners or operators of public water systems. However, the Zion Station RETS requires assessment of compliance with these limits. For additional information, see Section A.6 of Appendix A. 3 Note that 10CFRSO provides design objectives not limits. 4 Compliance with 10CFR20.1301 (a)(1) is demonstrated by compliance with 40CFR190. Note that it may be necessary to address dose from on-site activity by members of the public as well. Page 8 of 267
Revision 5 Aug 31, 2015 TABLE 2-2 DOSE ASSESSMENT RECEIVERS Location; Occupancy if Dose Component or Pathway Different than 100% "Instantaneous" concentration limits in liquid Point where liquid effluents enter the unrestricted effluents area Annual average concentration limits for liquid Point where liquid effluents enter the unrestricted effluents area Direct dose from contained sources Dose receptor location and occupancy with respect to the habits of a real individual as described in EH&S TSD 13-009, "Member of the Public Dose from all Onsite Sources." Direct dose from airborne plume Receiver is at the unrestricted area boundary location that results in the maximum dose. Dose due to tritium and particulates with half- Receiver is at the location in the unrestricted area lives greater than 8 days for inhalation, where the combination of existing pathways and ingestion of vegetation, milk and meat, and receptor age groups indicates the highest potential ground plane exposure pathways. exposures. Ingestion dose from drinking water The drinking water pathway is considered as an additive dose component in this assessment only if the public water supply serves the community immediately adjacent to the plant. Ingestion dose from eating fish The receiver eats fish from the receiving body of water (lake) Total Organ Doses Summation of ingestion/inhalation doses Total Dose Summation of above data (Note it may also be necessary to address dose from on-site activity by members of the public.) Page 9 of 267
Revision 5 Aug 31, 2015 TABLE 2-3 DOSE COMPONENT/REGULATION MATRIX Regulation in which dose component is utilized Dose Component or Reference equation; 10CFR50 Pathway Comments 10CFR20 10CFR72 40CFR190 App. I "Instantaneous" concentration A-21: limits in liquid effluents Ten times the limits of Table 2, Col. x(2J 2, 10CFR20, Appendix B to
§§20.1001 - 20.2402 Annual average concentration 10CFR20, Appendix B to limits for liquid effluents §§20.1001 - 20.2402( 2) x(3J Direct dose from contained Section A.3.1 x x x sources Direct dose from radioactivity deposited on the ground A-7 and A-8 x x x x Inhalation dose from airborne effluents A-7 and A-9 ( 1J x x x x Ingestion dose from vegetables A-7, A10 and A-11 (1J x x x x Ingestion dose from milk A-7, A-12 and A-13 (1J x x x x Ingestion dose from meat A-7, A-14 and A-15 (1J x x x x Ingestion dose from drinking 1J water A-17, A-18 and A-19 ( x x x x Ingestion dose from eating fish A-17, A-18 and A-20 ( 1J x x x x Total Organ Doses A-25 x x x Total Effective Dose Equivalent A-25\'+I x Ingestion/inhalation dose assessment is evaluated for adult/teen/child and infant for 10CFR50 Appendix I compliance and for 10CFR20/40CFR190 compliance. Ingestion/inhalation dose factors are taken from Reg.
Guide 1.109 (Reference 6). 2 With the relocation of fuel to the ISFSI, noble gas releases can no longer occur. 3 Optional for 10CFR20 compliance. 4 Compliance with the Total Effective Dose Equivalent limits of 10CFR20 is demonstrated by compliance with 40CFR190. It may also be necessary to address dose from on-site activity by members of the public. Page 10 of 267
Revision 5 Aug 31, 2015 Figure 2-1 2 Simplified Chart of Offsite Dose Calculations Frequency of Catego~ Radionuclides Pathwall Text Section Rece~tor Code and Limits Calculation 1 Airborne RETS: As required by Non-Noble Child lnhalationb A.1.5 1500 mrem/yr Station Releases: Gases: (Any Organ) Instantaneous Procedure Ground A.1.4.1 Total Body Depositionc lnhalationc A.1.4.2 3 Non-Noble 10CFR50 : Gases: Vegetationd A.1.4.3.1 Monthly and Annually Milkd Four Age Groups 7.5 mrem/qtr, 15 mrem/yr A.1.4.3.2 (All Organs) Meatd A.1.4.3.3 RETS, 10 times 10CFR20 As Required by All Water A.2.2 Not Applicable Appendix B; Table 2; Col. Station 2 Procedure Water* and 3 Non-No_ble 10CFR50 : A.2.1 Total Body Liquid Gases 1 1.5 mrem/qtr 3 mrem/yr Fish Monthly Releases: Water* and 3 Non-Noble All Organs (4 10CFR50 : A.2.1 Gases Fish 1 Age Groups) 5 mrem/qtr 10 mrem/yr Total Body and Non-Noble 40CFR141: When Required Water* A.6 All Organs Gases 4 mrem/yr by RETS (Adult) Total Body 40CFR190: Uranium All releases 25 mrem/vr plus direct 40CFR190: Fuel All radiation from A.4.2 Thyroid (Adult) Annually 75 mrem/yr contained Cycle: sources Any Other Organ 40CFR190: (Adult) 25 mrem/yr Total Body 10CFR72: 25 mrem/vr All releases ISFSI and plus direct 10CFR72: Thyroid (Adult) Uranium All radiation from A.4.2 75 mrem/yr Annually Fuel Cycle: ISFSI plus any other radiations Any Other 10CFR72: Critical Organ 25 mrem/yr (Adult) All Licensed Total Effective Total Body and 10CFR20: All Dose A.5 All Organs Annually Operations: 100 mrem/yr Eauivalent (Adult) Page 11 of 267
Revision 5 Aug 31, 2015 Figure 2-1 (Cont'd) Notes for Figure 2-1:
- 1. Definition: Monthly means at least once per 31 days or once per month. See station RETS for exact requirements.
- 2. Additional Calculations: In addition to the calculations shown in this figure, monthly projections of doses due to radioactive materials are required for gaseous and liquid effluents. See Sections A.1.6 and A.2.5 of Appendix A.
- 3. 10 CFR 50 prescribes design objectives not limits.
- 4. If the air dose is exceeded, doses to the total body and skin are calculated. Total body objectives are 2.5 mrem/qtr and 5.0 mrem/year; the skin dose objectives are 7.5 mrem/qtr and 15 mrem/year.
a Evaluated at the unrestricted area boundary. b Evaluated at the location of maximum offsite X/Q. c Ground plane and inhalation pathways are considered to be present at all offsite locations. d Evaluated at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures. If no real pathway exists then a hypothetical cow-milk producer is evaluated at 5 miles in the highest D/Q sector. e Evaluated for the nearest downstream community water supply as specified in Table A-3 of Appendix A. The flow and dilution factors specified in Table F-1 of Appendix F are used. Evaluated for fish caught in the near-field region downstream of plant using the flow and dilution factors specified in Table F-1 of Appendix F. Page 12 of 267
Revisions Aug 31, 2015 CHAPTER3 EXPOSURE PATHWAYS
3.0 INTRODUCTION
Figure 3-1 illustrates some of the potential radiation exposure pathways to humans due to routine nuclear power station activities. These exposure pathways may be grouped into three categories:
- 1. Airborne Releases - Exposures resulting from radioactive materials released with gaseous effluents to the atmosphere.
- 2. Liquid Releases - Exposures resulting from radioactive materials released with liquid discharges to bodies of water.
- 3. Radiation from Contained Sources - Exposures to radiation from contained radioactive sources.
When performing radiation dose calculations, only exposure pathways that significantly contribute (~ 10%) to the total dose of interest need to be evaluated. The radiation dose from air and water exposure pathways is routinely evaluated. (See Regulatory Guide 1.109, Reference 6.) 3.1 AIRBORNE RELEASES For airborne releases of radioactivity, the NRG considers the following pathways of radiation exposure of persons:
- External radiation from radioactivity airborne in the effluent plume.
- External radiation from radioactivity deposited by the plume on the ground.
- Ingestion of radioactivity on, or in, edible vegetation (from direct plume deposition).
- Ingestion of radioactivity that entered an animal food product (milk or meat) because the animal ingested contaminated feed, with the contamination due to direct deposition on foliage.
- Inhalation of radioactivity in the plume.
Dose for airborne releases is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures. 3.2 LIQUID RELEASES For liquid releases of radioactivity (Figure 3-1 ), the NRG considers the following pathways of radiation exposure of persons:
- Ingestion of aquatic food (e.g., fish or invertebrate) obtained from the body of water to which radioactive station effluents are discharged.
- Ingestion (drinking) of potable water contaminated by radioactive liquid effluents discharged from the station.
For the aquatic food pathway, only fish is considered since it is the only significant locally produced aquatic food consumed by humans. Zion Station omits the pathways involving irrigation and animal consumption of.contaminated water because these pathways were determined to be insignificant. Zion Station also omits the pathway of radiation exposure from shoreline sediment because this pathway was also found to be insignificant (see Appendix 0, Section 0.3.2). Zion Station has also verified that the dose contribution to people participating in water recreational activities (swimming and boating) is negligible. (See Appendix 0, Table 0-3.) This pathway was not addressed explicitly in Regulatory Guide 1.109. Thus, Zion Station also omits dose assessments for the water recreational activities pathway.
- Page 13 of 267
Revision 5 Aug 31, 2015 Periodically, the Illinois Army Corps of Engineers dredges silt and debris from the river beds near Zion Station. As a part of the land use census, Zion Station will determine if the Corps performed dredging within one mile of the discharge point. If so, Zion Station Will obtain spoils samples, through its REMP vendor, for analysis. The impact to the offsite dose will be evaluated on a case by case basis and added to the ODCM when applicable. In addition, to assure that doses due to radioactivity in liquid effluents will be ALARA, concentrations will be limited to ten times (1 Ox) the values given in 10CFR20 Appendix B, Table 2; Column 2. 3.3 RADIATION FROM CONTAINED SOURCES Radioactivity contained within waste containers, including those present at the ISFSI, can produce radiation at offsite locations. Annual offsite radiation doses near Zion Station due to such sources have the potential to challenge annual dose limits to members of the public dLie to direct radiations. Additions or rearrangements of waste storage locations that may impact the offsite dose through increases to the direct radiation levels are monitored through site administrative processes and procedures. Page 14 of 267
Revision5 Aug 31, 2015 Figure 3*1 Radiation Exposure Pathways to Humans Nuclear Power Plant Contained Sources Ingestion of Potable Water Liquid Effluent Releases Ingestion of Aquatic Food Inhalation Ingestion Deposition onto Vegetation Ingestion by Ingestion of Animals Milk and Meat Airborne Effluent Deposition onto Direct Radiation Soil Exposure Direct Radiation Exposure Human Page 15 of 267
Revision 5 Aug 31, 2015 CHAPTER4 METHODOLOGY
4.0 INTRODUCTION
This chapter provides an introduction to the methodology used at the Zion Station to calculate offsite radiation doses. Additional explanation and details of the methodology are provided in Appendices A and B. Appendix A discusses each dose limit in the RETS and provides the associated assessment equations. Appendix B describes methods used to determine values of parameters included in the equations. 4.1 IMPORTANT CONCEPTS AND PARAMETERS 4.1.1 Dose The dose calculation equations contained in the ODCM are based on two types of exposure to radiation; external and internal exposure. The first type of exposure is that resulting from radioactive sources external to the body (including radiation emanating from an effluent plume, radiation emanating from radioactivity deposited on the ground and radiation emanating from contained sources (also referred to as direct radiation)). Exposure to radiation external to the body only occurs while the source of the radioactivity is present. It should be noted that with the relocation of the fuel from the Spent Fuel Pool to the ISFSI there is no longer an exposure pathway from noble gases which affects the dose impacts at the Zion Station. Although noble gases are no longer included as an effluent from Zion Station activities, the associated information included in this chapter of the ODCM will remain at this time for historical purposes. Internal exposure occurs when the source of radioactivity is inside the body. Radiation can enter the body by breathing air containing the radioactivity, or by consumption of food or drinking water containing radioactivity. Once radioactivity enters the body and becomes internal radiation, a person will continue to receive radiation dose until the radioactivity has decayed or is eliminated by biological processes. The dose from this type of exposure is also termed dose commitment, meaning that the person will continue to receive dose even-though the plume containing the radioactivity has passed by the individual, or even-though the individual is no longer drinking water containing radioactivity. The regulations addressed by the ODCM may require assessment of either type of exposure to radiation or of both types in summation. The term dose is used instead of the term "dose equivalent," as defined by the International Commission on Radiological Units and Measurements {ICRU). When applied to the evaluation of internal deposition of radioactivity, the term "dose," as used in the ODCM, includes the prospective dose component arising from retention in the body beyond the period of environmental exposure, i.e. the dose commitment. The dose commitment is evaluated over a period of 50 years. 4.1.2 Exposure Pathways All of the exposure pathways are discussed in Chapter 3. This section presents the exposure pathways addressed by Zion Station in the ODCM and associated software. For releases of radioactivity in airborne effluents the primary pathways are the following:
- Direct radiation from an effluent plume.
- Direct radiation from radioactivity deposited on the ground by a plume.
- Inhalation of radioactivity in a plume.
- Ingestion of radioactivity that entered the food chain from a plume that deposited radioactivity on vegetation.
For releases of radioactivity in liquid effluents, the exposure pathways considered are human consumption of water and fish. Page 16 of 267
Revision 5 Aug 31, 2015 When determining total doses, as required by 10CFR20, 10CFR72 and 40CFR190, Zion Station considers exposure to radiation emanating from onsite radioactive waste. 4.1.3 Categories of Radioactivity Radionuclide content of effluent releases from Zion Station can be categorized according to the characteristics of the radionuclides. In evaluating doses associated with a particular pathway, only those categories of radionuclides that significantly contribute to the dose need to be included in the dose calculations (See Section 3.0). The categories of radionuclides considered by Zion Station for each of the airborne pathways are summarized in Table 4-1. Selection of the significant airborne pathways was based on the following:
- The requirements in the RETS (see discussion in Appendix A),
- Applicable regulatory guidance (References 6 and 14), and
- A study of the potential radiological implications of nuclear facilities in the upper Mississippi River basin (Reference 20).
4.1.4 Atmospheric Release Point Classifications The dose impact from airborne release of radioactivity is determined by the height of the release of the effluent plume relative to the ground and by the location of the dose recipient. The height an effluent plume maintains as it travels above the ground is related to the elevation of the release point and to the height of structures immediately adjacent as follows:
- If the elevation of the release point is sufficiently above the height of any adjacent structures, the plume will remain elevated for considerable distances.
- If the elevation of the release point is at or below the heights of adjacent structures, the plume is likely to be caught in the turbulence of the wakes created by wind passing over the buildings. The plume elevation would then drop to ground level.
- If the elevation of the release point is not significantly above the heights of adjacent structures, then the plume may be elevated or at ground level.
For the calculations of this manual, each established release point has been designated as belonging to one of three release point classifications: Stack (or Elevated) Release Points (denoted by the letter Sor subscripts) These are release points approximately twice the height of adjacent solid structures. Releases are treated as elevated releases unaffected by the presence of the adjacent structures. Ground Level Release Points (denoted by the letter G or subscript g) These are release points at ground level or lower than adjacent solid structures. Releases are considered drawn into the downwind wake of these structures and are treated as ground level releases. Vent (or Mixed Mode) Release Points (denoted by the letter V or subscript v) These are release points as high or higher than adjacent solid structures but lower than twice the structure's heights. These releases are treated as a mixture of elevated and ground level releases. The proportion of the release attributed to either elevated or ground level in a vent release is determined by the ratio of stack exit velocity to the wind speed (see Section B.1.2.4 of Appendix B). The definitions of these classifications are based on Regulatory Guide 1.111 (Reference 7). Zion Station has no Stack (Elevated) or Vent (Mixed Mode) release points, therefore; all releases at Zion Station are considered Ground Level. Page 17 of 267
Revision 5 Aug 31, 2015 4.1.5 Historical Average Atmospheric Conditions The dispersion characteristics of airborne effluents from a nuclear power station are dependent on weather conditions. Meteorological factors that directly affect the concentration of airborne radioactivity in c;i plume include the following:
- Wind Direction The concentration of radioactivity is highest in the direction toward which the wind is blowing.
- Wind Speed Greater wind speeds produce more dispersion and consequently lower concentrations of radioactivity.
- Atmospheric Turbulence The greater the atmospheric turbulence, the more a plume spreads both vertically and horizontally.
For calculations in this manual, the degree of turbulence is classified by use of seven atmospheric stability classes, designated A (extremely unstable) through G (extremely stable). The seven classes and some of their characteristics are listed in Table C-4 of Appendix C. Meteorological conditions strongly impact the values of various parameters applied in the dose calculations of this manual. These include:
- The Relative Concentration Factors x/Q and gam ma-x!Q (Section 4.1.6)
- The Relative Deposition Factor D/Q (Section 4.1. 7)
The bases sections of the Standard Radiological Effluent Technical Specifications (guidance documents NUREGs 0472, 0473, 1301 and 1302) and the RETS specify that dose calculations be based on "historical average atmospheric conditions". Therefore, this manual provides values for the,above parameters that are based on Zion Station historical average meteorological conditions. These values were obtained by averaging hourly values of the parameters over a long-term, several-year period of record. The averaging period was based on calendar years in order to avoid any bias from weather conditions associated with any one season. The period of record is identified in each of the tables providing the values (see Appendix F). 4.1.6 Relative Concentration Factors xJQ and Gamma-x/Q A person immersed in a plume of airborne radioactivity is exposed to radiation from the plume and may also inhale some of the radioactivity from the plume. The concentration of radioactivity in air near the exposed person must be calculated to adequately evaluate doses resulting from any inhalation. The relative concentration factor xlQ (referred to as "chi over Q") is used to simplify these calculations. xfQ is the concentration of radioactivity in air, at a specified location, divided by the radioactivity release rate. x!Q has the following units: 3 Units of xJQ = (µCi/m ) I (µCi/sec)= sec/m 3 Zion Station values of x!Q are provided in Table F-5 of Appendix F. These values.are based on historical average atmospheric conditions (see Section 4.1.5). For each of the release point classifications (eg. stack, vent and ground level) and for the 16 compass-direction sectors (N, NNE, etc.), Table F-5 provides the maximum value of xlQ for locations at or beyond the unrestricted area boundary. The value of x!Q for each sector reflects the fraction of time that the wind blew into that sector and the distribution of wind speeds and atmospheric stability classes during that time. Note that the value would be zero if the wind never blew into the sector. Page 18 of 267
Revision 5 Aug 31, 2015 The gamma-x/Q provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. It is used in place of the semi-infinite plume model that tends to underestimate gamma air dose for elevated plumes. Use of the gamma-X/Q also corrects for the tendency of the semi-infinite plume model to overestimate gamma air dose for mixed mode and ground level releases. The methodologies for determining x/Q and gamma-x/Q are discussed in detail in Section B.3 of Appendix B. 4.1.7 Relative Deposition Factor D/Q As a plume travels away from its release point, portions of the plume may touch the ground and deposit radioactivity on the ground and/or on vegetation. Occurrences of such deposition are important to model since any radioactivity deposited on the ground or on vegetation may directly expose people and/or may be absorbed into food products which can ultimately be ingested by people. The relative deposition factor is used to simplify the dose calculations for these pathways. The relative deposition factor D/Q is the rate of deposition of radioactivity on the ground divided by the radioactivity release rate. Its value was determined for specific conditions. In this manual it has the following units: Units of D/Q =[(pCi/sec)/m 2
] I (pCi/sec) =1/m 2 The values of D/Q are affected by the same parameters that affect the values of x!Q: release characteristics, meteorological conditions and location (see Section 4.1.6). Zion Station values of D/Q are provided in Appendix F Tables F-5 and F-6. These values are based on historical average atmospheric conditions (see Section 4.1.5).
For each release point classification and for each of the 16 compass-direction sectors {N, NNE, etc.), Table F-5 provides the maximum value of D/Q for locations at or beyond the unrestricted area boundary. In Table F-6, values of D/Q are given for the locations of the nearest milk and meat producers within 5 miles of Zion Station. The methodology for determining D/Q is discussed in Section B.4 of Appendix B. 4.1.8 Dose Factors Various dose factors are used in this manual to simplify the calculation of radiation doses. These factors are listed in Table 4-2. Definitions of these factors are given in the remainder of this chapter. Methods of determining their values are addressed in Appendix B. 4.2 AIRBORNE RELEASES 4.2.1 Gamma Air Dose The term 'gamma air dose' refers to the component of dose absorbed by air resulting from the absorption of energy from photons emitted during nuclear and atomic transformations, including gamma rays, x-rays, annihilation radiation, and Bremsstrahlung radiation (see foetnote on page 1.109-19 of Regulatory Guide 1.109). The noble gas dose factors of Reg. Guide 1.109, Table B-1 are based upon assumption of immersion in a semi-infinite cloud. For ground level and mixed mode releases this tends to overestimate the gamma air dose arising from a plume that is actually finite in nature. For elevated releases, the Reg. Guide 1.109 noble gas dose factors will underestimate exposure as they consider only immersion and not that portion of exposure arising from sky shine. At distances close in to the point of elevated release, the ground level co~ncentration as predicted by xJQ will be essentially zero. In such a case, the sky shine component of the exposure becomes significant and must be considered. The gamma-x/Q provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. The methodology of Reg. Guide 1.109, Section C.2 and Appendix B provide the methodology for calculating finite cloud gamma air dose factors from which the gamma-x/Q values can be derived. Section B.5 addresses the calculation of these dose factors." Page 19 of 267
Revision 5 Aug 31, 2015 Three gamma-x/Q values are defined: (x/Q)/, (x/Q)/ and (x/Q)9Y for stack, vent and ground level releases, respectively. Section B.3.5 addresses the calculation of the gamma-x/Q values. 4.2.1.1 Finite Cloud Gamma Air Dose Factor The finite cloud gamma air dose factor is determined by calculating the gamma dose rate to air (at a specific location and corresponding to a given release rate) and dividing that dose rate by the corresponding release rate: Finite Cloud Gamma Air Dose Factor= [(mrad/yr)/(µCi/sec)] The methodology for this calculation is discussed in Section B.5 of Appendix B. The calculation is complex because the dose rate at any given point is affected by the radioactivity concentration and distance. Calculation of the finite cloud gamma air dose factor takes into consideration release characteristics, meteorological conditions and location (see Section 4.1.6). Additionally, the value is affected by radiological parameters: the distribution of energies and intensities for gamma emissions from each specific radionuclide and the photon attenuation characteristics of air. In the ODCM, station-specific values of gamma dose factors are provided for Zion Station in Appendix F, Table F-7. These values are based on historical average atmospheric conditions (see Section 4.1.5). For the release point classification and for each of the 16 compass-direction sectors, Table F-7 provides the maximum value of the gamma air dose factor for noble gas radionuclides at the unrestricted area boundary. The value includes a correction for radioactive decay during transport of the radionuclide from the release point to the dose calculation location. 4.2.1.2 Semi-Infinite Cloud Gamma Air Dose Factor The semi-infinite cloud gamma dose factor is the gamma air dose rate divided by the concentration of radioactivity in air at the dose calculation location. Values of these gamma dose factors are radionuclide specific and are provided in Appendix C, Table C-9. The semi-infinite cloud gamma dose factor is used in conjunction with gamma-x/Q to calculate noble gas gamma air dose and dose rate for elevated and finite noble gas plumes. The gamma-x/Q is defined such that for a given finite cloud the semi-infinite cloud methodology will yield the same gamma air dose as the finite cloud methodology. 4.2.2 Beta Air Dose The term 'beta air dose' refers to the component of dose absorbed by air resulting from the absorption of energy from emissions of beta particles, mono-energetic electrons and positrons during nuclear and atomic transformations (see the footnote on Page 1.109-20 of Regulatory Guide 1.109). The Beta Air Dose Factor The beta air dose factor is the beta air dose rate divided by the concentration of radioactivity in air at the dose calculation location. Values of the beta air dose factor are radionuclide specific and are provided in Appendix C Table C-9. 4.2.3 Total Body Dose and Dose Rate Total Body Dose Equation A-3 of Appendix A is used to calculate dose to the total body from noble gas radionuclides released in gaseous effluents. The total body dose equation is similar to that used to calculate gamma air dose (Equation A-1 of Appendix A). Page 20. of 267
Revision 5 Aug 31, 2015 Total Body Dose Rate Equation A-5 of Appendix A is used to calculate dose rate to the total body. The assumptions used for this equation are the same as those used in the calculation of total body dose (Equation A-3 of Appendix A) except that any shielding benefit (dose attenuation) provided by residential structures is not applied. Since the calculation is for the maximum instantaneous dose rate, the dose recipient may be out of doors when exposed and would not be shielded from the exposure by any structural material. The Total Body Dose Factor The total body dose factor is the total body dose rate divided by the radioactive release rate. Values for the total body dose factor are site specific and are provided in Table C-9 of Appendix C. 4.2.4 Skin Dose and Dose Rate Skin Dose Equation A-4 of Appendix A is used to calculate dose to skin from noble gas radionudides released in gaseous effluents. The skin dose is the summation of dose to the skin from beta and gamma radiation. The equation for beta dose to skin is similar to that used to calculate beta dose to air (Equation A-2 of Appendix A) except that beta skin dose factors are used instead of beta air dose factors. The beta skin dose factor differs from the beta air dose factor by accounting for the attenuation of beta radiation by the dead layer of skin. The dead layer of skin is not susceptible to radiation damage and therefore is not of concern. The beta dose to the skin from non-noble gases is insignificant and is not calculated for the reason described in Section 4.1.3. When calculating the beta contribution to skin dose, no reduction is included in the calculations due to shielding provided by occupancy of residential structures. The equation for gamma dose to skin is similar to that used to calculate gamma dose to air except for the following:
- Equation A-4 of Appendix A includes a unit's conversion factor 1.11 rem/rad to convert from units of gamma air dose (rad) to units of tissue dose equivalent (rem).
- Equation A-4 of Appendix A includes a dimensionless factor of 0.7 to account for the shielding due to occupancy of residential structures.
Equation A-4 of Appendix A uses gamma air dose factors not gamma total body dose factors. When calculating gamma dose to skin, no reduction is applied for the attenuation of radiation due to passage through body tissue (dead layer of skin). Skin Dose Rate Equation A-6 of Appendix A is used to calculate dose rate to skin. The assumptions are the same as those used in the calculation of skin dose (Equation A-4 of Appendix A) except that no credit is taken for shielding of gamma radiation by residential structures. The dose recipient may be outdoors when exposed and the maximum instantaneous dose rate is of concern. The Skin Dose Factor Values of the beta air dose factors and skin dose factors are nuclide specific and are provided in Table C-9 of Appendix C for 15 noble gas radionuclides. 4.2.5 Ground Radiation Equations A-7 and A-8 of Appendix A are used to calculate the total body dose due to non-noble gas radionuclides released in gaseous effluents and deposited on the ground. Page 21 of 267
Revision 5 Aug 31, 2015 Comment Note that if there is no release of radionuclide i during a given time period, then the deposition rate is zero, the ground plane concentration is zero and the resulting dose due to ground deposition is zero. If there is a release of radionuclide i, the ground concentration is computed as if that release had been occurring at a constant rate for the ground deposition time period. The Ground Plane Dose Conversion Factor The ground plane dose conversion factor is the dose rate to the total body per unit of radioactivity concentration on the ground. Values of the ground plane dose conversion factor that are calculated by assuming constant concentration over an infinite plane are provided for various radionuclides in Table C-10 of Appendix C. 4.2.6 Inhalation Dose Radioactivity from airborne releases of particulate and tritium can enter the body through inhalation. Equations A-7 and A-9 of Appendix A are used to calculate dose commitment to the total body or organs due to inhalation of non-noble gas radionuclides released in gaseous effluents. The Inhalation Dose Factor Values for the inhalation dose commitment factor are nuclide specific and are taken from Reg. Guide 1.109 (Reference 6) Tables E-7, 8, 9 and 10. These tables include data for four age groups (adult, teenager, child and infant) and seven body organs. Dose Rate The inhalation dose rate is the rate at which dose is accrued by an individual breathing contaminated air. Equation A-16 of Appendix A is used to calculate dose commitment rate to an organ due to inhalation of non-noble gas radionuclides. The assumptions are the same as used in the calculation of inhalation dose. The dose rate is determined for the child age group in accordance with the guidance found in NUREGs 0472, 0473, 1301and1302 (References 2, 3, 105 and 106). 4.2.7 Ingestion Airborne releases of particulate and tritium can enter the food chain through deposition on vegetation. The radioactivity can be ingested by humans who consume the vegetation or who consume products (e.g., milk or meat) of animals who have fed on the contaminated vegetation. Zion Station may consider the following ingestion pathways:
- Vegetables
- Milk
- Meat Equations A-7 and A-1 O through A-15 of Appendix A are used to calculate the dose due to ingestion of food containing non-noble gas radionuclides released in gaseous effluents. Dose is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposures.
Values _of the ingestion dose commitment factors are taken from Reg. Guide 1.109 Tables E-11, 12, 13 and 14: These tables include data for four age groups and seven organs. The equations used for radioactivity concentration on vegetation and in milk, and meat are discussed in Appendix A. Page 22 of 267
Revision 5 Aug 31, 2015 4.3 LIQUID RELEASES The evaluation of dose due to releases of radioactivity in liquid effluents is required to confirm compliance with the provisions of RETS related to 10CFR50 Appendix I. The ODCM, Section 3.2 and Figure 3-1 list some of the pathways by which radioactivity in liquid effluents can impact man. The pathways used by Zion Station to calculate dose from liquid effluents are ingestion by drinking water and by eating fish from the body of water receiving station liquid discharges. Zion Station obtains the dose commitment due to radioactivity in liquid effluent releases by summing the dose commitments from the drinking water and fish pathways depending upon their presence. Equations A-17 through A-20 of Appendix A are used to calculate dose for the member of the public due to consumption of drinking water and fish. The radioactivity concentration in water is obtained by dividing the quantity of radioactivity released by the volume of water in which the release is diluted. The result can be modified by a factor to represent any additional dilution that might occur. The radioactivity concentration in fish is the product of the radioactivity concentration in water and a bioaccumulation factor. The dilution factors for fish may be different from those for water. (The fish may be caught at a location different from where drinking water is drawn.) The bioaccumulation factor accounts for the fact that the quantity of radioactivity in fish can build up with time to a higher value relative to the concentration of the radioactivity in the water they consume. The bioaccumulation factor is the equilibrium ratio of the concentration of radionuclide i in fish to its concentration in water. The same values are used for the bio-accumulation factor at Zion Station. These values are provided in Appendix C, Table C-8. 4.4 CONTAINED SOURCES OF RADIOACTIVITY In addition to the total body, skin and single organ dose assessments previously described, an additional assessment is required. The additional assessment addresses radiation dose due to radioactivity contained within the nuclear power station and its structures. 4.4.1 Deleted 4.4.2 Onsite Radioactive Waste and Radioactive Material Storage Facilities Low-level radioactive waste and radioactive material may be stored at Zion Station in the following types of locations:
- Concrete Rad Vaults
- Miscellaneous Shipping Containers
- Existing and temporary support structures Spent Fuel is stored at the Independent Spent Fuel Storage Installation. Administrative controls are implemented by Zion Station to ensure compliance to applicable regulations. The impact to the offsite dose from contained sources shall be documented in site Technical Support Documents. In addition, a 10CFR50.59 analysis may be required for selected radwaste storage facilities.
4.5 TOTAL DOSE REQUIREMENTS 4.5.1 Total Effective Dose Equivalent Limits; 10CFR20 and 40CFR190 10CFR20 requires compliance to dose limits expressed as "Total Effective Dose Equivalent" (TEDE). Although annual dose limits in 10CFR20 are now expressed in terms of TEDEs, 40CFR190 limits remain stated as organ dose. The NRC contim1es to require 10CFR50 Appendix I and 40CFR190 doses to be reported in terms of organ dose and not TEDE. Due to the fact that organ dose limits set forth in 40CFR190 are substantially lower than those of 10CFR20 (25 mrem/yr vs. 100 mrem/yr), the NRC has stated that demonstration of compliance with the dose limits in 40CFR190 will be deemed as demonstration of compliance with the dose limits of 10CFR20 for most facilities (Reference 104). Page 23 of 267
Revision 5 Aug 31, 2015 In addition to compliance with 40CFR190, it may be necessary for a nuclear power plant to address dose from on-site activity by members of the public. 4.5.2 Total Dose For Uranium Fuel Cycle Zion Station is required to determine the total dose to a member of the public due to all uranium fuel cycle sources in order to assess compliance with 40CFR190 as part of demonstrating compliance with 10CFR20. The total dose for the uranium fuel cycle is the sum of doses due to radioactivity in airborne and liquid effluents and the doses due to direct radiation from contained sources at the Zion Station. When the evaluation of total dose is required for the Zion Station, the following contributions are summed:
- Doses due to airborne and liquid effluents.
- Doses due to liquid effluents from nuclear power stations upstream
- Doses due to any onsite radioactive waste storage facilities; if applicable.
Section A.5.2 of Appendix A discusses the details of evaluations. Page 24 of 267
Revision 5 Aug 31, 2015 Table 4-1 Radionuclide Types Considered For Airborne Effluent Exposure Pathways External Radiation Internal Radiation Category Plume Ground Inhalation Ingestion Noble Gases X Tritium (H-3) x x Particulate8 x x x a Only particulates with half-life greater than 8 days need be considered. For details, see Generic Letter 89-01 and the RETS. Page 25 of 267
Revision 5 Aug 31, 2015 Table 4-2 Radiation Dose Factors Name and Symbol Units Definition Table Gamma Air Dose mrad/yr Gamma air dose rate per RG 1.109 Factor per unit of radioactivity Table B-1, 3 Mi µCi/m concentration for Column 4 radionuclide i. Total Body Dose mrem/yr Total body dose rate per RG 1.109 Factor: per unit of radioactivity Table B-1, 3 Ki µCi/m concentration for Column 5 radionuclide i. Beta Air Dose mrad/yr Beta air dose rate per RG 1.109 Factor Ni per unit of radioactivity Table B-1, 3
µCi/m concentration for Column 2 radionuclide i.
Beta Skin Dose mrem/yr Beta skin dose rate per RG 1.109 Factor Li per unit of radioactivity Table B-1, 3
µCi/m concentration for Column 3 radionuclide i.
Ground Plane Dose mrem/hr Dose rate per unit RG 1.109 Conversion Factor per of ground radioactivity Table E-6, 2 DFGi pCi/m concentration for Column 2 radionuclide i. Inhalation Dose mrem Dose to organ j of age RG 1.109 Commitment Factor per group a per unit of Tables; DFAiia pCi radioactivity inhaled E-7, E-8, for radionuclide i. E-9, E-10 (see Note 1) Ingestion Dose mrem Dose to organ j of age RG 1.109 Commitment Factor per group a per unit of Tables; DFhia pCi radioactivity ingested E-11, E-12, for radionuclide i. E-13, E-14 (see Note 1) Note 1: Dose assessments for 10CFR20, 10CFR72 and 40CFR190 compliance are made for an adult only. Dose assessments for 10CFR50 Appendix I are made using dose factors of Regulatory Guide 1.109 (Reference 6) for all age groups. Page 26 of 267
Revision 5 Aug 31, 2015 CHAPTER 5 MEASUREMENT
5.0 INTRODUCTION
Zion Station has two measurement programs associated with offsite dose assessment:
- Measurement of releases of radioactivity at the site.
- Measurement of levels of radiation and radioactivity in the environs surrounding the site.
5.1 EFFLUENT AND PROCESS MONITORING Radioactivity in liquid and gaseous effluents is measured in order to provide data for calculating radiation doses and radioactivity concentrations in the environment. Measurement of effluent radioactivity is required by 10CFR20.1302 and 10CFR50. The RETS provides detailed requirements for monitoring the effluents from the Zion Station. Relevant Regulatory Guides are 1.21 (Reference 4) and 4.15 (Reference 13). Chapter 10 of the ODCM includes brief descriptions of the systems. The RETS requires submission to the NRC of reports of effluent radioactivity releases and environmental measurements. 5.2 METEOROLOGICAL MONITORING A historical average of meteorological measurements is used at the Zion Station in lieu of real time monitoring. 5.3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) Zion Station has a REMP that provides representative measurements of radiation and radioactive material in the environment. The program provides verification that measurable radiological impacts from the station on the environment are within expectations derived from effluent measurements and calculations. The REMP is required by 10CFR50 (see Appendix I, Sections IV.B.2 and IV.8.3). General requirements of the program are prescribed in Zion Stations RETS and more precise details (such as specific monitoring locations) are specified in the ODCM Chapter 11. 5.3.1 lnterlaboratory Comparison Program The laboratory which performs the REMP analyses is required by the RETS to participate in an interlaboratory comparison program. The purpose is to provide an independent check on the laboratory's analytical procedures and to alert it to potential problems (e.g. accuracy). In order to assess the measurements of radioactivity in environmental media, an independent agency supplies participating laboratories with samples of environmental media containing unspecified amounts of radioactivity. The laboratories measure the radioactivity concentrations and report the results to the agency. At a later time, the agency informs the participating laboratories of the actual concentrations and associated uncertainties. Any significant discrepancies are investigated by the participating laboratories. A similar process is used to assess measurements of environmental radiation by passive thermoluminescent dosimeters. Page 27 of 267
Revision 5 Aug 31, 2015 CHAPTERS IMPLEMENTATION OF OFFSITE DOSE ASSESSMENT PROGRAM 6.1 NUCLEAR POWER STATION Zion Station staff is responsible for effluent monitoring. The staff determines effluent radioactivity concentration and flow rate. These data are used to determine the radioactivity release information required for the Radioactive Effluent Release Report and to perform monthly calculations and projections of offsite radiation dose. Zion Station staff is also responsible for control of effluent radioactivity. Procedures are implemented for determining, calculating and implementing monitor setpoints. Liquid and gaseous radwaste treatment systems and ventilation exhaust treatment systems are utilized when appropriate. Zion Station staff implements the Process Control Program (PCP) for solid radwaste and measures tank radioactivity. Zion Station staff maintains instrumentation associated with these activities and demonstrates operability of the instrumentation in accordance with the surveillance requirements of the RETS. In the event that any RETS requirements are violated, Zion Station staff is responsible for taking one of the actions allowed by the RETS and issuing any required reports to the NRC. Zion Station assembles and distributes the Annual Radioactive Effluent Release Report. 6.2 REMP CONTRACTOR The radiological environmental contractor collects environmental samples and performs radiological analyses as specified in the Zion Station REMP (see ODCM Chapters 11 and 12). The contractor issues reports of results to appropriate points of contact. The contractor participates in an interlaboratory comparison program and reports results in the Annual Radiological Environmental Operating Report. The contractor performs the annual land use census and assembles the Annual Radiological Environmental Operating Report. Page 28 of 267
Revision 5 Aug 31, 2015 CHAPTER 7 REFERENCES
- 1. Deleted
- 2. U.S. Nuclear Regulatory Commission, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors, NUREG-0472, Rev. 3, Draft, January 1983 (frequently revised).
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- 5. U.S. Nuclear Regulatory Commission, Onsite Meteorological Programs, Regulatory Guide 1.23, Safety Guide 23, February 17, 1972.
- 6. U.S. Nuclear Regulatory Commission, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix I, Regulatory Guide 1.109, Rev. 1, October 1977.
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- 11. U.S. Nuclear Regulatory Commission, Preparation of Environmental Reports for Nuclear Power Stations, Regulatory Guide 4.2, Rev. 2, July 1976.
- 12. U.S. Nuclear Regulatory Commission, Environmental Technical Specifications for Nuclear Power Plants, Regulatory Guide 4.8, Rev. 1, December 1975. (See also the related Radiological Assessment Branch Technical Position, Rev. 1, November 1979.)
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- 14. U.S. Nuclear Regulatory Commission, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, edited by J. S. Boegli et al. NUREG-0133, October 1978.
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NUREG/CR-2919, PNL-4380, September 1982.
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Meyer, NUREG/CR-3332, ORNL-5968, September 1983.
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Page 29 of 267
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- 18. U.S. Atomic Energy Commission, Meteorology and Atomic Energy 1968, edited by D. H. Slade, TID-21940, July 1968.
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Randerson, DOE/TIC-27601, 1984.
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Turner, Office of Air Programs Publication No. AP-26, 1970.
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- 26. U.S. Environmental Protection Agency, Environmental Analysis of the Uranium Fuel Cycle, EPA-520/9-73-003-C, November 1973.
- 27. American Society of Mechanical Engineers, Recommended Guide for the Prediction of the Dispersion of Airborne Effluents, 1973.
- 28. Eisenbud, M., Environmental Radioactivity, 3rd Edition, (Academic Press, Orlando, FL, 1987).
- 29. Glasstone, S., and Jordan, W. H., Nuclear Power and Its Environmental Effects (American Nuclear Society, LaGrange Park, IL, 1980).
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Predicting the Transport. Bioaccumulation. and Uptake by Man of Radionuclides Released to the Environment, NCRP Report No. 76, March 15, 1984.
- 32. American National Standards Institute, Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities, ANSI N13.1-1969, February 19, 1969.
- 33. Institute of Electrical and Electronics Engineers, Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N13.10-1974, September 19, 1974.
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Page 30 of 267
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- 39. Deleted
- 40. Deleted
- 41. U.S. Nuclear Regulatory Commission, Branch Technical Position, Radiological Assessment Branch, Revision 1, November 1979. (This is a branch position on Regulatory Guide 4.8.)
- 42. Deleted
- 43. U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code),
NUREG-0017, April 1976.
- 44. Deleted
- 45. Deleted
- 46. Deleted
- 47. Deleted
- 48. Deleted
- 49. U.S. Nuclear Regulatory Commission, Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190), NUREG-0543, February 1980.
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- 58. Deleted
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Page 31 of 267
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- 60. Deleted
- 61. Deleted
- 62. Deleted
- 63. Deleted
- 64. "Verification of Environmental Parameter Used for Commonwealth Edison Company's Offsite Dose Calculations," NUTECH Engineering Group, 1992.
- 65. Deleted
- 66. Deleted
- 67. Deleted
- 68. Deleted
- 69. Deleted
- 70. D. C. Kocher, Radioactivity Decay Data Tables, DOE/TIC-11026, 1981.
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- 72. Commonwealth Edison Company, Information Relevant to Keeping Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonably Achievable, Zion Station. Units 1 and 2, June 4, 1976.
- 73. Deleted
- 74. Deleted
- 75. Sargent & Lundy, METWRSUM, S&L Program Number 09.5.187-1.0.
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- 82. Deleted
- 83. Deleted
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- 85. U.S. Environmental Protection Agency, Environmental Analysis of the Uranium Fuel Cycle. Part I - Fuel Supply, EPA-520/9-73-003-8, October 1973.
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- 89. Deleted
- 90. U.S. Nuclear Regulatory Commission, Generic Letter 89-01, "Guidance For The Implementation of Programmatic Controls For RETS In The Administrative Controls Section of Technical Specifications and the Relocation of Procedural Details of Current RETS to the Offsite Dose Calculation Manual or Process Control Program", January 1989.
- 91. Deleted
- 92. Deleted
- 93. Deleted
- 94. Deleted.
- 95. U.S. Nuclear Regulatory Commission, Standards for Protection Against Radiation (10CFR20).
- 96. U.S. Nuclear Regulatory Commission, Licensing of Production and Utilization Facilities (10CFR50).
- 97. Federal Register, Vol. 57, No. 169, Monday, August 31, 1992, page 39358.
- 98. Miller, Charles W., Models and Parameters for Environmental Radiological Assessments, U.S.
Dept. of Energy, DE8102754, 1984, pages 32, 33, 48, and 49.
- 99. Kocher, D. C., "Dose-Rate Conversion Factors For External Exposure To Photons and Electrons", Health Physics Vol. 45, No. 3 (September), pp. 665-686, 1983.
100. U.S. Department of Health, Education and Welfare Public Health Service, Radiological Health Handbook, January 1970. 101. Deleted 102. Deleted 103. U.S. Nuclear Regulatory Commission, Generic Letter 79-041, September 17, 1979. 104. Federal Register, Vol. 56, No. 98, Tuesday, May 21, 1991, page 23374, column 3. 105. U.S. Nuclear Regulatory Commission, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, NUREG-1301, April 1991. 106. Deleted 107. U.S. Nuclear Regulatory Commission, LADTAP 11- Technical Reference and Users Guide, NUREG-4013, April 1986. . 108. NRC ISG-13 Rev. 0, Spent Fuel Project Office Interim Staff Guidance -13 Real Individual, May 17,2000 Page 33 of 267
Revision 5 Aug 31, 2015 CHAPTER 8 Deleted Page 34 of 267
Revision 5 Aug 31, 2015 CHAPTER9 Deleted Page 35 of 267
Revision 5 Aug 31, 2015 CHAPTER 10 RADIOACTIVE EFFLUENT TREATMENT SYSTEM AND MONITORING 10.1 AIRBORNE RELEASES 10.1.1 System Description During operation of the ventilation systems, the principal release points for potentially radioactive airborne effluents are the two auxiliary building ventilation stacks (Unit 1 and Unit 2). Each is classified as a ground level release. These ventilation systems maintain acceptable ambient air temperatures for equipment operation and personnel habitability, they provide air flow as needed for contamination control purposes, from lesser contamination potential to areas of greater contamination potential, and they provide bulk exhaust flow for ease of effluent control, sampling, and quantification. The Unit 2 Aux Bldg (AB) ventilation st~ck provides the release point for airborne effluent from the Aux Bldg, Fuel Building, and the Containments (when the Containment Purge Fans are not in operation). Operation of the AB ventilation system is administratively controlled to ensure that at least one (of 3) exhaust fan is operating when a supply fan is running. During times when the Containment Purge Fans are operating; the Unit 1 AB ventilation stack provides the release point for airborne effluent from the Unit 1 Containment, and the Unit 2 AB ventilation stack provides the release point for airborne effluenffrom the Unit 2 Containment. Gaseous effluent system and ventilation systems are described in the Defueled Safety Analysis Report (DSAR) and Section 10.4. 10.1.1.1 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce radioactive material in particulate form in gaseous effluents by passing ventilation through HEPA and/or pre-filters prior to release to the environment for ALARA reasons. 10.1.2 Radiation Monitors Pertinent information is provided in the DSAR and Section 10.4. 10.1.2.1 Auxiliary Building Ventilation Stack Effluent Monitors 2RIA-PR49 (Unit 2) continuously monitors the final effluent from the Aux Bldg, Fuel Bldg, and Unit 2 containment for beta, particulate and provides an alarm function. 10.1.2.2 Containment Purge Effluent Monitors 1RIA-PR49 (Unit 1) continuously monitors the final effluent from the Unit 1 containment when the associated Purge Fan is in operation for beta particulate and provides an alarm function. 2RIA-PR49 (Unit 2) continuously monitors the final effluent from the Unit 2 containment when the associated Purge Fan is in operation for beta particulate and provides an alarm function. 10.1.3 to 10.1.3.4 Deleted Page 36 of 267
Revision 5 Aug 31, 2015 10.1.3.5 HVAC Flow Rates Flow rates for aux vent stack release are provided by flow measuring instrumentation. However, flow rates out of the vent stack can be calculated based on the number of operating fans in the monitored flow path. FM = (10-4) FM = Total Flow In Monitored Flow Path [cc/sec] Fip = Flow from fan i in path p. [cc/sec] Ni = Number of fans, in operation The maximum flow for each fan is used for setpoint calculations because this maximizes the flow, establishing a conservative, "worst case" release rate/concentration for setpoint determination. Pertinent data for the fans is provided in Table 10-2. HVAC flows for the remaining monitors are conservatively fixed at upper bound values. 10.2 LIQUID RELEASES 10.2.1 System Description The liquid waste system description is provided in the DSAR and Section 10.4. The liquid radwaste treatment system is designed and installed to allow for a reduction if needed, in the concentration of radioactive liquid effluents by filtration, providing for retention or holdup and/or providing for treatment by demineralizers. The overall purpose is to ensure releases to the lake do not exceed any concentration release limit and liquid effluent releases to the public are ALARA. 10.2.1.1 Lake Release Tanks There are two Lake Release Tanks which receive processed liquid waste before discharge to Lake Michigan. 10.2.1.2 Holdup Tanks There are three Holdup Tanks (120,000-gallon capacity each) which receive and store liquid waste from the Containments, AB and FB. The Holdup Tanks (HUTS) will store the liquid waste water until it can be processed for release to Lake Michigan or removed from the site. 10.2.2 Radiation Monitors 10.2.2.1 Lake Release Tank Monitors If the option is used, ORT-PR04 monitors releases from the Lake Release Tanks. On high alarm, the monitor automatically initiates closure of a valve to prevent further releases. The monitor and valve are located in an arrangement that allows closure prior to exceeding release limits. The monitor setpoints are found by solving Equation 10-5 for release setpoint P. Available information is provided in the DSAR and Section 10.4. Page 37 of 267
Revision 5 Aug 31, 2015 10.2.3 Alarm and Trip Setpoints 10.2.3.1 Setpoint Calculation Alarm and trip setpoint of liquid effluent monitor at the principal release points is established to ensure that the concentration limits of the QAPP and 10 CFR 20 are not exceeded in the unrestricted area. The monitor setpoint is found by solving Equation 10-5 for a conservative mixture of radionuclides found in liquid effluents. (10-5) P Release Setpoint [µCi/ml] The alarm setpoint for radioactivity to be released in liquid effluents. Cmpc Maximum Permissible Concentration [µCi/ml] Fd Dilution Flow Rate [gpm] The flow rate of the radwaste dilution stream. Fr Discharge Flow Rate [gpm] The flow rate from the Lake Release Tank. K Factor of conservatism K = 0.5 for Lake Release Tank 10.2.3.2 Discharge Flow Rates 10.2.3.2.1 Lake Release Tank Discharge Flow Rate Prior to each batch release, the water is recirculated, sampled, and analyzed. (1) The results of the analysis of the waste sample determine the discharge rate of each batch as follows: Frmax= (Cmpc)(Fd actfC) (10-6) Frmax Maximum Permitted Discharge Flow Rate [gpm] The maximum permitted flow rate from the Lake Release Tank. [gpm] Fd act Actual Dilution Flow Rate [gpm] The actual flow rate of the radwaste dilution stream. 1
<> C Sample Radioactivity Concentration [µCi/ml]
The concentration of radioactivity in the Lake Release Tank, based on measurements of a sample drawn from the tank. Cmpc has the same definition as in Equation 10-5. 10.2.3.2 Release Limits Release limits are determined from 10 CFR 20. Page 38 of 267
Revision 5 Aug31, 2015 10.2.3.3 Release Mixture The release mixture used for setpoint determination is based on a composition of 100% of a nuclide with a conservative concentration discharge limit to the lake (e.g. Sr90) 1 ( > A more conservative discharge rate may be calculated based on concentration limits for NPDES constituents (e.g., boron concentration). In either case, discharge procedures verify that all discharge limits to the lake are below applicable limits. 10.2.4 Allocation of Effluents from Common Release Points Radioactive liquid effluents released from the Lake Release Tanks are comprised of contributions from both units. Under normal site conditions, it is difficult to apportion the radioactivity between the units. Consequently, allocation is based on the unit discharge canal used for dilution. 10.3 SOLIDIFICATION OF WASTE/PROCESS CONTROL PROGRAM The process control program (PCP) contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is ensured. 10.4 Radioactive Effluent Radiation Monitoring Systems 10.4.1 Design Bases The Radiation Monitoring System is designed to detect, indicate and alarm based on the radiation levels at selected locations in the facility. The system consists of the process radiation monitoring system, which includes the effluent monitors which are designed to provide early warning of increasing radiation activity due to a malfunction of plant equipment, and to monitor radioactive discharges to the environment to ensure concentrations do not exceed specified limits. In the decommissioning state, radioactive material exists in the form of particulates. As such, the instrument channels in the radiation monitoring system monitor only particulates. None of the radiation monitors are relied upon to initiate an accident mitigation function for the radioactive waste handling event described in Chapter 5.0 of the DSAR. In the decommissioning configuration, the source term continues to be reduced as the buildings are prepared for decontamination and demolition. Based on this, pote_ntial radiological events of concern are limited, but will focus on major structures with radioactive material and liquid releases to the lake. The process radiation monitoring system provides general radiological monitoring, as well as specific information on the concentration of radioactivity in the event of a radiological event or an abnormal liquid release to the lake. This enables personnel to evaluate and respood to an event accordingly. 10.4.2 System Description The Process Radiation Monitoring System consists of several channels which primarily give early warning of an unexpected elevated release. Effluent Radiation Monitors are controlled in accordance with Chapter 12 to ensure an "as low as reasonably achievable" site boundary dose is obtained. This is consistent with the design characteristics of the monitoring equipment, and acceptable operating considerations. The Process Radiation Monitoring System provides radiological monitoring of key areas and activities at the station. The primary areas of focus for the current radiation monitoring system are: Gaseous effluents through the vent stacks and the litjuid effluent pathways. As decommissioning progresses, these monitors will no longer be needed and will be removed from service. Page 39 of 267
Revision 5 Aug 31, 2015 10.4.3 Containment Purge System Effluent Monitoring Unit 1 Containment Purge Exhaust is monitored for radiation by the Unit 1 Auxiliary Building vent stack particulate Air Monitor. Unit 2 Containment Purge Exhaust is monitored for radiation by the Unit 2 Auxiliary Building vent stack particulate Air Monitor. 10.4.4 Fuel Building Exhaust Air Monitor The Fuel Building Ventilation exhaust is monitored via the Unit 2 Auxiliary Building ventilation stack effluent monitor. 10.4.5 Waste Disposal System Liquid Effluent Monitor The liquid radiation monitor PR-04 remains an option for lake Water discharges. It is a self-contained monitor and is used to measure radioactivity levels in liquid effluent being discharge to site effluent discharge point. Detector outputs are transmitted to the Radiation Monitoring alarms. High radioactivity-alarms are communicated so that actions can be implemented in accordance with approved procedures. The accuracy of these monitors will be maintained to provide a highly reliable backup to the multiple sample analyses prior to discharge. A single monitor is provided on each discharge line and is considered adequate since the tank sample analyses are the primary method for determination of allowable discharge volume and flow. The release of liquid waste is performed under administrative control and these channels provide continuous monitoring during the release. An additional option exists to complete lake water radioactive effluent discharges to alternate controls as described in Chapter 12. 10.4.6 Calibration and Testing Each channel employs a check source for channel testing. Check source testing is performed as defined in Chapter 12. All radiation monitors are calibrated by exposing the detectors to an isotope(s) of known activity. By changing the distance or placing filters between detector and the standard isotope, the field intensity is varied thereby allowing for a multi-point calibration. The waste disposal system liquid effluent monitors are calibrated by the use of two (2) isotopic standards of different intermediate activity levels. The standards are monitored during calibration in a configuration similar to that of the monitored sample during normal operation. This method allows for an accurate isotopic calibration without contamination of the system. The method of calibration of laboratory radiation counting instrumentation is in accordance with the vendor's manual. Complete documentation of calibration checks is maintained. 10.4.7 Effluent Monitoring and Sampling The methods used in quantifying routine effluent releases to the environment consist of continuous Radiation Monitoring Systems and/or laboratory analyses. Laboratory analyses are conducted on either grab samples or composite samples. All liquid and gaseous effluents sample results are recorded/saved in some form to provide a complete history of abnormal occurrences for evaluation; high radiation level alarms are sent to an on-shift individual when effluent releases are in progress. The high radiation alarm setpoints are based upon a value of activity which is sufficiently low to be in conformance with the concentration limit requirements. Laboratory instrumentation used for radiation analysis of effluent grab samples are as described in the Chapter 12. The calibration of counting equipment will be maintained by the use of sources certified against the National Institute of Standards and Technology (NIST) certificates. Page 40 of 267
Revision 5 Aug 31, 2015 Effluent monitors will be calibrated at frequencies established in the Chapter 12. The multi-channel gamma analyzer will be performance checked when in use. Sources are used to verify against known energy lines and activity. Geometry factors will be checked in accordance with approved procedures. The liquid scintillation counter will be checked in accordance with approved procedures when in use, Complete documentation of all calibration checks will be maintained. Effluent discharge line waste monitors will be checked against laboratory analyzed or established known portable sources. Page 41 of 267
Revision 5 Aug 31, 2015 TABLE 10-1 DELETED Page 42 of 267
Revision 5 Aug 31, 2015 TABLE 10-2 HVAC EXHAUST FAN CAPACITIES FAN CC/SEC CFM CFH
- 2 Aux. Bldg.
7 OD Exh. Fan 3.16 x 10 6.70x10 4 4,020,000 7 4 OE Exh. Fan 3.16 x 10 6.70x10 4,020,000 7 4 OF Exh. Fan 3.16 x 10 6.70 x 10 4,020,000
- 1 Purge Exh.
7 4 1A Purge Fan 2.12 x 10 4.50 x 10 2,700,000 7 4 1B Purge Fan 2.12 x 10 4.50 x 10 2,700,000 6 3 U1 Mini-Purge Fan 1.42 x 10 3:00 x 10 180,000 H2 Purge Fan 1A 1.70 x 10 5 3.60 x 102 21,600 5 2 H2 Purge Fan 1B 1.75 x 10 3.40 x 10 22,200
- 2 Purge Exh.
7 2A Purge Fan 1.65 x 10 3.50 x 104 2,102,400 7 4 2B Purge Fan 1.72 x 10 3.65 x 10 2,188,800 6 3 U2 Mini-Purge Fan 1.42 x 10 3.00 x 10 180,000 2 H2 Purge Fan 2A 1.82 x 105 3.85 x 10 23,100 5 2 H2 Purge Fan 2B 1.75 x 10 3.71x10 22,260 6 3 Hot Lab Exh. OA 1.50 x 10 3.18 x 10 191,000 6 3 Hot Lab Exh. OB 1.18 x 10 2.51x10 150,600 Page 43 of 267
Revision 5 Aug 31, 2015 CHAPTER 11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The parameters of the radiological environmental monitoring program for the environs around Zion Station are given in Table 11-1. Figures 11-1 a, 11-1 band 11-2 show sampling and monitoring locations. Page 44 of 267
Revision 5 Aug 31, 2015 Table 11-1 Radiological Environmental Monitoring Program Exposure Pathway Sampling or Monitoring Sampling or Collection Frequency Type and Frequency of Analysis And/or Sam pie Locations
- 1. Airborne
- a. Indicators - Near Field Particulate Sam pier:
Z-01 Onsite No. 1 South side, Continuous sam pier operation with Gross beta analysis following 2 0.2 mi S (0.3 km J) particulate filter collection weekly or weekly filter change and 3 Z-02 Onsite No. 2 West side, more frequently if required by dust gamma isotopic analysis 0.2 mi W (0.3 km N) loading. quarterly on composite filters by location. Z-03 Onsite No. 3 North side, 0.20 mi NNE (0.3 km B)
- b. Control- Far Field Z-13 Pleasant Prairie Wisconsin 10 mi NW (15 km Q)
Page 45 of 267
Revision 5 Aug 31, 2015 Table 11-1 Radiological Environmental Monitoring Program - Cont. Exposure Pathway Sampling or Monitoring Sam piing or Collection Frequency Type and Frequency of Analysis And/or Sam pie Locations
- 2. Direct Radiation a. Indicators - Inner Ring 5 Quarterly Gamma dose on each TLD quarterly Z-101-1 and 2 0.2 mi N (0.3 km A)
Z-102-1 and 2 0.2 mi NNE (0.3 km B) Z-103-1 and2 0.15 mi NE (0.25 km C) Z-104-1 and2 0.13 mi ENE (0.2 km D) Z-105-1 and2 0.1 mi E (0.15 km E) Z-106-1 and 2 0.1 mi ESE (0.15 km F) Z-107-1 and 2 0.1 mi SE (0.15 km G) Z-108-1 and2 0.13 mi SSE (0.2 km H) Z-109-1 and 2 0.2 mi SSE (0.3 km H) Z-112-1 and 2 0.7 mi WSW (1.1 km M) Z-113-1 and 2 0.6 miW (1.0 km N) Z-114-1 and 2 0.6 mi WNW (1.0 km P) Z-115-1 and 2 0.4 mi NW (0.6 km Q) Z-121-1 and 2 0.2 mi NNW (0.3 km R) Z-124-1 and 2 0.5 mi SW (0.8 km L) Z-125-1 and 2 0.4 mi SSW (0.6 km K) Z-129-1 and 2 0.2 mi NW (0.3 km P) Z-130-1 and 2 0.2 mi WNW (0.3 km N) Quarterly Gamma dose on each TLD Z-131-1 and 2 0.2 mi WSW (0.3 km L) quarterly
- b. Other One at each airborne location given in 1.a.
Z01-1 and 2 0.2 mi S (0.3 km J) Z02-1 and 2 0.2 mi E (0.3 km N) Z03-1 and 2 0.2 mi NNE (.3 km B) One control at control airborne location Z13-1thru6 10 mi NW (15 km Q) Page 46 of 267
Revision 5 Aug 31, 2015 Table 11-1 Radiological Environmental Monitoring Program - Cont. Exposure Pathway Sam piing or Monitoring Sampling or Collection Frequency Type and Frequency of Analysis And/or Sam pie Locations
- 2. Direct Radiation - d. Indicators - Outer Ring Quarterly Gamma dose on each TLD Cont. quarterly Z-209-1 and 2 5.1 mi S (8.2 km K)
Z-211-1 and 2 4.7 mi SW (7.6 km L) Z-212-1 and 2 5.1 mi WSW (8.2 km M) Z-213-1 and2 5.1 miW (8.2 km N) Z-214-1 and 2 4.6 mi WNW (7.4 km P) Z-215-1 and 2 4.0 mi NW (6.4 km Q) Z-216-1 and2 3.0 mi NNW (4.8 km R) Gamma dose on each TLD quarterly Page 47 of 267
Revision 5 Aug 31, 2015 Table 11-1 Radiological Environmental Monitoring Program - Cont. Exposure Pathway Sampling or Monitoring Sampling or Collection Frequency Type and Frequency of Analysis And/or Sam pie Locations
- 3. Waterborne 6
- a. Drinking Water lndicator Z-15 Lake County Water Works, Gross beta and gamma isotopic3 1.4 mi NNW (2.2 km R) Weekly grab samples. analysis on monthly composite; Z-16 Waukegan Water W arks, tritium analysis on quarterly 6.1 mi S (9.8 km J) composite.
- b. Control 6 Z-14 Kenosha Water Works, 10.0 mi N Gross beta and gamma isotopic3 (1.60.km A) Weekly grab samples. analysis on monthly composite; Z-18 Lake Forest Water Works, 12.9 mi tritium analysis on quarterly S (20.8 km J) composite.
- c. Sediments Z-25 Lake Michigan, Illinois Beach Semiannually Gamma isotopic3 analysis State Park, 2.0 mi S (3.2 km J) semiannually.
Page 48 of 267
Revision 5 Aug 31, 2015 Table 11-1 Radiological Environmental Monitoring Program - Cont. Exposure Pathway Sampling or Monitoring Sam piing or Collection Frequency Type and Frequency of Analysis And/or Sam pie Locations
- 4. Ingestion a. Fish Indicator Semiannually Z-26, Lake Michigan in vicinity of station Discharge 3
Gamma isotopic analysis on
.. b. Fish Control edible portions.
Z-27, Lake Michigan, 10.0 mi N (16.0 km A)
- 5. Vegetation a. Vegetation Indicator Annual (during growing season)
Z-QUAD 3, Pleasant Prairie market, 4 mi Gamma isotopic3 analysis on NNW (6.4 km R) edible portions. Z-QUAD 4, Sheridan Road Zion Farmers market, 1.1 mi W (1.7 km N)
- b. Vegetation Control Z-Control, Kenosha Farmers Market, 11 mi NNW (18 km R}
Page 49 of 267
Revision 5 Aug 31, 2015 Table 11-1 Radiological Environmental Monitoring Program - Cont.
- 1. Deleted - No longer applicable.
- 2. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in any individual air particulate sample is greater than 10 times the 1999 mean of control samples, then, a gamma isotopic analysis shall be performed on that elevated individual sample.
- 3. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the station.
- 4. Deleted - No longer applicable.
- 5. Limited TLD placements due to Lake Michigan and location of air samplers.
- 6. The closest drinking water locations (North/South) chosen for drinking water indicators; two other locations beyond 6.2 miles (North/South) chosen for control sam pies.
Page 50 of 267
Revision 5 Aug 31 , 20 15 Figure 11-1a Airborne and Direct Radiation Sample Locations - Inner Ring
- TLD Monitoring Location A. Air Sampling Location Page 51 of 267
Revision 5 Aug 31, 20 15 Figure 11-1 b Direct Radiation Sample Locations - Outer Ring Page 52 of 267
Revision 5 Aug 31, 2015 Figure 11-2 Location of Waterborne and Ingestion Sampling Sites Kenosha Waterworks Z-14
*Z-27
---~~~~----------- Zion Lake County Water Works
- Z-15 Zion*
- 2 -26 LAKE Illinois Beach Z-25 State Park MICHIGAN Waukegan Water Works North Chicago Water Works
- Sampling Locations Page 53 of 267
Revision 5 Aug 31, 2015 CHAPTER12 Radiological Effluent Technical Standards (RETS) SPECIAL NOTE The requirements of Quality Assurance Project Plan (QAPP) Appendix B shall take precedence over this chapter, should any differences occur. Page 54 of 267
Revision 5 Aug 31, 2015 12.1 DEFINITIONS 12.1.1 A BATCH RELEASE is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling. 12.1.2 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds with the necessary range and accuracy to known values of input. The CHANNEL CALIBRATION shall encompass the entire channel including the sensors (where possible), alarm interlock and/or trip functions (if applicable) and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated. 12.1.3 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent INSTRUMENT CHANNELS measuring the same parameter. 12.1.4 A CHANNEL FUNCTIONAL CHECK shall be:
- a. Instruments-The injection of a simulated signal(s) into the channel as close to the primary sensor(s) as practicable to verify OPERABILITY, including all channel outputs, as appropriate.
- b. Logics-The application of input signals, or the operation of relays or switch contacts, in all the combinations required to produce the required decision outputs including the operation of all ACTUATION DEVICES. Where practicable, the test shall include the operation of the ACTUATED EQUIPMENT as well (i.e. pumps will be started, valves operated, etc.).
12.1.5 A COMPOSITE SAMPLE is one in which the quantity of liquid sample is proportional to the quantity of liquid waste discharged and in which the method of sampling employ~d results in a specimen which is representative of the liquids released. 12.1.6 A CONTINUOUS RELEASE is the discharge of liquid or gaseous wastes of a nondiscrete volume (e.g. from a volume or system that has an input flow during the release). 12.1.7 CONTINUOUS SAMPLING is uninterrupted sampling with the exception of sampling interruptions of short duration for routine activities (e.g. filter replacements). 12.1.8 MEMBER OF THE PUBLIC means any individual except when that individual is receiving an occupational dose. 12.1.9 OCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation and/or radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include dose from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the public. 12.1.10 OPERABLE -A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function(s) are also capable of performing their related support function(s). 12.1.11 OPERATING is defined as performing the intended function in the intended manner. Page 55 of 267
Revision 5 Aug 31, 2015 12.1.12 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste. 12.1.13 PURGE OR PURGING is the controlled process of discharging air from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner, that replacement air or gas is required to purify the confinement. 12.1.14 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by the licensee. 12.1.15 SOLIDIFICATION shall be the conversion of radioactive liquid, resin and sludge wastes from liquid systems into a form that meets shipping and burial site requirements. 12.1.16 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. 12.1.17 SURVEILLANCE shall be those parts of the sections which prescribe remedial measures required under designated conditions, activities required to demonstrate instrument operability, and activities performed to ensure applicable offsite dose limits are not exceeded. 12.1.18 The SURVEILLANCE FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 12.1-1. 12.1.19 UNRESTRICTED AREA means an area, access to which is neither limited nor controlled by the licensee. 12.1.20 UNVENTILATED BUILDING RELEASE means A building that is not negative pressure controlled with presence of radioactive that could potentially become airborne that has a pathway to be released to the environment. 12.1.21 GASEOUS EFFLUENT TREATMENT SYSTEM shall be any system designed and installed to reduce radioactive material in particulate form in effluents by passing ventilation through HEPA filters for the purpose of removing particulates from the gaseous exhaust stream prior to the release to the environment 12.1.22 VENTING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air is not provided or required during venting. Vent, used in system names, does not imply a venting process. Page 56 of 267
Revision 5 Aug 31, 2015 TABLE 12.1-1 SURVEILLANCE FREQUENCY NOTATIONS NOTATION FREQUENCY* s (Shiftly) At least once per 12 hours D (Daily) At least once per 24 hours w (Weekly) At least once per 7 days M (Monthly) At least once per 31 days Q (Quarterly) At least once per 92 days SA (Semiannually) At least once per 184 days A (Annually) At least once per 366 days R At least once per 18 months p (Prior) Complete prior to start of release N/A Not Applicable
- Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.
Page 57 of 267
Revision 5 Aug 31, 2015 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Plant Monitoring Instrumentation Operability Requirements 12.2.1.A The radioactive liquid plant monitoring instrumentation channels shown in Table 12.2-1 shall be OPERABLE AND, the radioactive liquid effluent monitoring instrumentation channels shall have their alarm/trip setpoints set to ensure that the limits of Section 12.3.1.A are met. Applicability: As indicated in Table 12.2-3.
- 1. With a radioactive liquid effluent monitoring instrument channel trip setpoint less conservative than the value necessary to prevent violating the limits of Section 12.3.1.A, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.
- 2. With one or more radioactive liquid plant monitoring instrumentation channels inoperable, initiate the SURVEILLANCE requirement delineated in Table 12.2-1.
- 3. Restore the inoperable effluent monitor to OPERABLE status within 30 days, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report the reasons as detailed in Section 12.7.2 and perform a review to determine course of action to restore to OPERABLE status.
Surveillance Requirements 12.2.1.B.1 The liquid effluent monitor setpoints shall be determined in accordance with procedures as described in the ODCM. 12.2.1.B.2 Each radioactive liquid plant monitoring instrumentation channel shall be demonstrated OPERABLE by performance of a CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-2. 12.2.1.C The radioactive liquid plant monitoring instrumentation is provided to indicate abnormal radiological conditions, AND, The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive materials in liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of RETS. The OPERABILITY and use of this instrumentation is consistent with the requirements of Appendix A to 10CFR Part 50. Page 58 of 267
Revision 5 Aug 31, 2015 TABLE 12.2-1 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE# CONDITION
- 1. Liquid Effluent Monitors Providing Automatic Termination of Release A. Lake Release Tanks
- 1. OR-PR04 1 1* Liquid Release through this Pathway
- 2. Effluent Continuous Composite Sampler A. WWTF 1 4 During Release via this pathway
- 3. Effluent Flow Rate Monitor A. Lake Release Tank #1
- 1. OFl-WD005 1 3 Liquid Release through this Pathway
- 2. OFl-WD005A 1 3 Liquid Release through this Pathway B. Lake Release Tank #2
- 1. OFl-WD006 1 3 Liquid Release through this Pathway
- 2. OFl-WD006A 1 3 Liquid Release through this Pathway C. Common discharge pathway
- 1. OFl-WD007 1 3 Liquid Release from Either LRT #1 or #2
- 4. Plant System Monitors A. Dilution Flow Pressure Indication
- 1. OPl-SW01A 1** 3 Liquid Release from Either LRT #1 or #2
- 2. OPl-SW01 1** 3 Liquid Release from Either LRT #1 or #2
- - The Surveillance 1 may be used as an equivalent alternative to the use of OR-PR04.
- -Minimum Channels Operable for Dilution flow Pressure Indication is one channel from OPl-SW01 OR one channel from OPl-SW01A during LRT releases.
Page 59 of 267
Revision 5 Aug 31, 2015 TABLE 12.2-1 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION (Cont'd) SURVEILLANCE 1 If the monitor is inoperable, effluent releases from the tank may continue provided that prior to initiating the release:
- 1. At least two independent samples of the tank's contents are analyzed, in accordance with Section 12.3.1.B.1, and
- 2. At least two technically qualified members of the facility staff independently verify the release-rate calculations and discharge flow path valving; and
- 3. Approval by the Plant Manager.
- 4. Restore the inoperable effluent monitor to OPERABLE status within 30 days, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report the reasons as detailed in Section 12.7.2 and perform a review to determine course of action to restore to OPERABLE status.
Otherwise, suspend release of radioactive effluents via this pathway. SURVEILLANCE 2 Deleted. SURVEILLANCE 3 For the applicable flowpath at least one of the listed flowmeters within the flowpath must be operable to monitor flow provided the monitored flowrate falls within the calibration range of the flowmeter. With the no flow channels OPERABLE within the flowpath, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves may be used to estimate flow. SURVEILLANCE 4 If the composite sampler is inoperable, effluent releases via this pathway may continue, provided that at least once per day grab samples are taken. The samples shall be analyzed in accordance with Section 12.3.1.B.3. Page 60 of 267
Revision 5 Aug 31, 2015 TABLE 12.2-2 RADIOACTIVE LIQUID PLANT MONITORING INSTRUMENTATION SURVEILLANCE CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION (1) TEST (2)
- 1. Liquid Effluent Monitors Providing Automatic Termination Of Release A. Lake Release Tanks
- 1. OR-PR04 p p R Q
- 2. Effluent Continuous Composite Sampler A. WWTF N/A N/A N/A N/A
- 3. Effluent Flow Rate Monitor A. Lake Release Tank #1
- 1. OFl-WD005 D{3) N/A R N/A
- 2. OFl-WD005A D{3) N/A R N/A B. Lake Release Tank #2 1 . OFl-WD006 D(3) N/A R N/A
- 2. OFl-WD006A D{3) N/A R N/A C. Common Discharge pathway
- 1. OFl-WD007 D{3) N/A R N/A
- 4. Plant System Monitors A. Dilution Flow Pressure Indication
- 1. OPl-SW01A D(4) N/A R N/A
- 2. OPl-SW01 D(4) N/A R N/A (1) CHANNEL CALIBRATION shall include performance of a CHANNEL FUNCTIONAL TEST.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that any automatic isolation of this pathway occurs and that control room alarm annunciation occurs if any of the following conditions exist. (if the capability is installed): a) Instrument indicates levels above the alarm setpoints. b) Circuit failure. c) Instrument indicates a downscale failure. d) Instrument controls not set in operate mode. (3) CHANNEL CHECK shall consist of verifying indications of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or BATCH RELEASES are made. (4) Dilution Flow Pressure Gauge OPl-SW01A OR OPl-SW01 may be used. The pressure gauge being used shall be verified operating at least daily during Lake Release Tank Batch discharge And pump curves used to estimate flow once per day based on the readings. Page 61 of 267
Revision 5 Aug 31, 2015 12.2.2 Radioactive Plant Monitoring Instrumentation Operability Requirements 12.2.2.A The radioactive plant monitoring instrumentation channels shown in Table 12.2-3 shall be OPERABLE, AND, the radioactive gaseous effluent monitoring instrumentation shall have their alarm/trip setpoints set in accordance with the method prescribed in the ODCM to ensure that the limits of Section 12.4.1.A are met. Applicability: As indicated in Table 12.2-3.
- 1. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above Section, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.
- 2. With one or more radioactive plant monitoring instrumentation channels inoperable, initiate the SURVEILLANCE requirement as delineated in Table 12.2-3.
- 3. Restore the inoperable effluent monitor to OPERABLE status within 30 days, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report the reasons as detailed in Section 12. 7.2 and perform a review to determine course of action to restore to OPERABLE status.
Surveillance Requirements 12.2.2.B.1 The effluent monitor setpoints shall be determined in accordance with procedures as described in the ODCM. 12.2.2.B.2 Each radioactive plant monitoring instrumentation channel shall be demonstrated OPERABLE, when in its APPLICABLE CONDITION, by performance of a CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 12.2-4. 12.2.2.C The radioactive plant monitoring instrumentation is provided to indicate abnormal radiologi_cal conditions. The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20. Page 62 of 267
Revision 5 Aug 31, 2015 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE INSTRUMENT OPERABLE SURVEILLANCE CONDITION
- 1. Effluent Containment Purge or Vent A. Particulate Monitor
- 1. 1R-PR49 1 11 Gaseous Release through this Pathway
- 2. 2R-PR49 1 11 Gaseous Release through this Pathway B. Flow Rate Monitor
- 1. 1LP-084 1 8 Gaseous Release through this Pathway
- 2. 2LP-084 1 8 Gaseous Release through this Pathway
- 2. Aux Building Effluent Monitoring A. DELETED B. Particulate Monitor
- 1. 2R-PR49 1 11 Gaseous Release through this Pathway C. Flow Rate Monitor
- 1. 2LP-084 1 8 Gaseous Release through this Pathway Page 63 of 267
Revision 5 Aug 31, 2015 TABLE 12.2-3 RADIOACTIVE PLANT MONITORING INSTRUMENTATION - (Cont'd) TABLE NOTATIONS SURVEILLANCE 6 DELETED SURVEILLANCE 7 DELETED SURVEILLANCE 8 Effluent releases via this pathway may continue provided: 1 . The effluent flow rate is estimated at least once per day while a release is in progress.
- 2. Continuous sampling is maintained with either inline sample pump or air sampling at locations that input into the gaseous effluent system.
- 3. A Channel Check is performed daily
- 4. Restore the inoperable effluent monitor to OPERABLE status within 30 days, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report the reasons as detailed in Section 12.7.2 and perform a review to determine course of action to restore to OPERABLE status.
SURVEILLANCE 9 DELETED SURVEILLANCE 10 DELETED SURVEILLANCE 11 With the number of OPERABLE channels less than the minimum number required:
- 1. Effluent releases via this pathway may continue provided samples are continuously collected as required in Table 12.4-1.
- 2. Restore the channel to OPERABLE status within 30 days or conduct a review to determine a plan of action to restore the channel to OPERABLE status.
Compensatory sampling does not return the monitor to an OPERABLE status. SURVEILLANCE 12 DELETED. SURVEILLANCE 13 DELETED SURVEILLANCE 14 DELETED Page 64 of 267
Revisions Aug 31, 2015 TABLE 12.2-4 RADIOACTIVE PLANT MONITORING INSTRUMENTATION SURVEILLANCE CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL CHECK CHECK CALIBRATION (1) TEST (2)
- 1. Effluent Containment Purge or Vent A. Particulate Monitor
- 1. 1R-PR49 D M R Q
- 2. 2R-PR49 D M R Q B. Flow Rate Monitor
- 1. 1LP-084 D N/A R Q
- 2. 2LP-084 D N/A R Q
- 2. Aux Building Effluent Monitoring A. DELETED B. Particulate Monitor
- 1. 2R-PR49 D M R Q C. Flow Rate Monitor
- 1. 2LP-084 D N/A R Q Page 65 of 267
Revision 5 Aug 31, 2015 Table 12.2-4 RADIOACTIVE PLANT MONITORING INSTRUMENTATION SURVEILLANCE (Cont'd) TABLE NOTATIONS (1) CHANNEL CALIBRATION shall include performance of a CHANNEL FUNCTIONAL TEST. (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that any automatic isolation occurs; and that alarms occur if any of the following conditions exist (if the capability is installed): a) Instrument indicates measured levels above the alarm setpoint. b) Circuit failure. c) Instrument indicates a downscale failure. d) Instrument controls not set in "operate" mode. Page 66 of 267
Revision 5 Aug 31, 2015 12.3 LIQUID EFFLUENTS 12.3.1 Concentration Operability Requirements 12.3.1.A.1 The concentration of radioactive material released from the site to UNRESTRICTED AREAS (see Appendix F, Figure F-1) shall be limited to 10 times the concentrations specified in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402 12.3.1.A.2 During the release of radioactive liquid wastes, the combination of dilution water flow and waste water discharge flow shall be established to ensure the discharge concentration limits of 12.3.1.A.1 are not exceeded. Applicability: At all times.
- 1. With the concentration of radioactive materials released from the site to UNRESTRICTED AREAS exceeding the limits specified in Section 12.3.1.A.1 immediately decrease the release rate of radioactive materials and/or increase the dilution flow rate to restore the concentration to within the above limits.
Surveillance Requirements 12.3.1.B.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 12.3-2. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1.A.1. 12.3.1.B.2 Post-release analyses of samples composited from BATCH RELEASES shall be performed in accordance with Table 12.3-2. The results of the previous post-release analyses shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1. 12.3.1.B.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 12.3-2. The results of the analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Section 12.3.1.A.1. 12.3.1.B.4 Appropriate discharge and dilutions flows for each batch radioactive liquid release shall be determined with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Section 12.3.1 .A.1. 12.3.1.C This Section is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to UNRESTRICTED AREAS will be less than ten (10) times the concentration levels specified in Appendix B, Table 2, Column 2 to 10CFR 20.1001-20.2402. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10CFR20.1301. Page 67 of 267
Revision 5 Aug 31, 2015 TABLE 12.3-1 DELETED Page 68 of 267
Revision 5 Aug 31, 2015 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE MINIMUM ANALYSIS LOWER LIMIT OF LIQUID RELEASE SAMPLING FREQUENCY TYPE OF DETECTION (LLD) TYPE FREQUENCY ACTIVITY ANALYSIS (µCi/ml) (a,e) A. Lake Release Prior to Each Release Prior to Each Principal Gamma 5E-7 (c) Release Emitters (e) p M Tritium 1E-5 Each Batch (c) Composite (b) Gross Alpha 1E-7 p Q Sr-90 5E-8 Each Batch ( c) Composite (b) Fe-55, Ni-63 1E-6 B. WWTF (f) Continuous During W when discharging Principal Gamma 5E-7 Release (d) Emitters(e) Continuous During M Tritium 1E-5 Release(d) Composite (b) Gross Alpha 1E-7 Continuous During Q Sr-90 5E-8 Release (d) Composite (b) Fe-55, Ni-63 1E-6 C. Waste Prior to each Release Prior to each Release Principal Gamma 5E-7 Neutralizing Tank Emitters (e) p M Tritium 1E-5 Each Batch (c) Composite (b) Gross Alpha 1E-7 D. Groundwater Prior to each Release Prior to each Release Principal Gamma 5E-7 Emitters (e) p M Tritium 1E-5 Each Batch (c) Composite (b) E. Groundwater (f) Continuous During w Principal Gamma 5E-7 Release (d) Emitters( e) Continuous (d) M Tritium 1E-5 Composite (b) Page 69 of 267
Revision 5 Aug 31, 2015 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd) TABLE NOTATIONS
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95%
probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): LLD= 4.66 sb A* E
- V
- 2.22
- Y *exp (-Mt)
Where: LLD is the lower limit of detection as defined above in picocuries (pCi) per unit mass or volume, sb is the square root of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), A is the number of gamma rays emitted per disintegration for gamma ray radionuclide analysis (A= 1.0) for gross alpha, strontium, and tritium measurement. Eis the counting efficiency (as counts per gamma), Vis the sample size (in units of mass or volume), 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield when applicable (otherwise Y = 1.0)
'A is the radioactive decay constant for the particular radionuclide, and L\t is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental sample).
The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and L\t shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be within+/-. one FWHM (Full Width at Half Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radionuclide. Page 70 of 267
Revision5 Aug 31, 2015 TABLE 12.3-2 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS SURVEILLANCE (Cont'd) TABLE NOTAT IONS For certain mixtures of gamma emitters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using observed ratios with those radionuclides which are measurable.
- b. A COMPOSITE SAMPLE is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.
- 1) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
- 2) The weekly and monthly Proportional Composite samples are not required provided that (1) the analysis required for each of these composite samples has been run on each batch discharged, and (2) a monthly record of radionuclides discharged (isotope and quantity) is maintained.
- c. A BATCH RELEASE is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
- d. A CONTINUOUS RELEASE is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.
- e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Nb-94, Co-60, Cs-137 and Sb-125. This list does not mean that only these nuclides are
.to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD, and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations.
- f. If the composite sampler is inoperable, grab samples shall be taken from the discharge stream once per day during system operation.
Page 71 of 267
Revision 5 Aug 31, 2015 12.3.2 Dose Operability Requirements 12.3.2.A The dose or dose commitment to a MEMBER OF THE PUBLIC above background from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS (see Appendix F, Figure F-1) shall be limited:
- 1. 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
- 2. 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.
Applicability: At all times.
- 1. With the calculated dose from the release of radioactive materials in liquid effluents exceeding twice the limits specified in Section 12.3.2.A, limit the subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cyele sources is limited to less than or equal to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) ovE)r 12 consecutive months. Demonstrate that radiation exposures to all MEMBERS OF THE PUBLIC from all u_ranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40CFR Part 190 and 40CFR Part 141 Standard, otherwise obtain a variance from the Commission to permit releases which exceed the 40CFR Part 141 or 190 Standard.
The radiation exposure analysis shall use methods prescribed in the ODCM. Surveillance Requirements 12.3.2.B Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodologies and parameters of the ODCM at least once per 31 days. 12.3.2.C This Section is provided to implement the requirements of Sections II.A, Ill.A and IV.A of Appendix I, 10CFR Part SQ. The limiting Condition of Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required OPERATING flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites_ with drinking water supplies, which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are excess of the requirements of 40CFR 141 . The dose calculations in the ODCM implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the dose due to the actual release rate of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109; Calculation of Annual Doses to Man from Routine Releases of Radioactive Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guides 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. Page 72 of 267
Revision 5 Aug 31, 2015 This Section applies to the release of liquid effluents from each unit at the site. For shared radwaste treatment systems, the liquid effluents from the shared systems are proportioned among the units sharing the system. 12.3.3 Liquid Radwaste Treatment System Operability Requirements 12.3.3.A The Liquid Radwaste Treatment System shall be OPERABLE* and appropriate portions of the system shall be used to reduce the radioactive materials in liquid effluents prior to discharge when the projected doses due to liquid effluent, from each unit, to UNRESTRICTED AREAS (see Appendix F, Figure F-1) would exceed 0.06 mrem to the total body or 0.20 to any organ in a 31-day period.
*The liquid Radwaste Treatment System shall be considered OPERABLE, if liquid waste can be held up and/or discharged within applicable limits.
Applicability: At all times. With the Liquid Radwaste Treatment System inoperable for more than 30 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, return the system to OPERABLE status and place the appropriate portions of the system in use. Surveillance Requirements 12.3.3.B Doses due to liquid releases from the.site to UNRESTRICTED AREAS, shall be projected at least once per 31 days in accordance with the methodologies and parameters of the ODCM when the Liquid Radwaste Treatment System is not being fully utilized. 12.3.3.C The OPERABILITY of the Liquid Radwaste Treatment System ensures that the system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This Section implements the requirements of 10CFR Part 50.36a, General Design Criterion of Appendix A to 10CFR Part 50 and the design objective given in Section 11.D of Appendix I to 10CFR Part 50. The specified limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a 2% fraction of the dose design objectives set forth in Section II.A of Appendix I, 10CFR Part 50, for liquid effluents. Page 73 of 267
Revision 5 Aug 31, 2015 12.4 GASEOUS EFFLUENTS 12.4.1 Dose Rate Operating Requirements 12.4.1.A The dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY (see Appendix F, Figure F-1 ), shall be limited to the following:
- 1. DELETED
- 2. For tritium and all radionuclides in particulate form with half-lives greater than 8 days the limit is less than or equal to 1500 mrem/yr to any organ.
Applicability: At all times. With a release exceeding the above limits, immediately reduce the release rate to within the above limits. Surveillance Requirements 12.4.1.B The dose rate due to radioactive materials in gaseous effluents shall be determined to be within the prescribed limits in accordance with the methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 12.4-1. 12.4.1.C This Section is provided to ensure that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an Unrestricted Area, either at or beyond the Site Boundary in excess of the design objectives of appendix I to 10 CFR part 50. This section is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.A and II design objectives of appendix I to 10 CFR part 50. These release-rate limits also restrict, at all times, the corresponding organ dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year. For purposes of calculating dose resulting from airborne releases, the stack is considered a ground-level release. The Sampling and Analysis Program requirements prescribed in Table 12.4-1 are established to provide representative and appropriate sampling of the radiologically controlled areas. The method and frequency of sampling is based on the effluent flowrate. Continuous Releases are defined for areas with forced ventilation release points. Unventilated Building Releases are defined for areas with no specific release point. Page 74 of 267
Revision 5 Aug 31, 2015 TABLE 12.4-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM MINIMUM TYPE OF LOWER LIMIT OF GASEOUS RELEASE SAMPLING ANALYSIS ACTIVITY DETECTION (LLD) TYPE METHOD FREQUENCY ANALYSIS (µCi/cc) (f) A. Deleted B. Continuous Continuous (b)(h) Weekly(c) Particulate 1E-11 Releases <1> Daily( a) Principal Gamma Containment Vent Emitters (e) and Purge C. Continuous Releases< 1> Aux Building Unit 2 Composite Quarterly Sr-90 Particulate 1E-11 Ventilation Stack Unit 1 Vent Stack, Modular HEPA Fe-55 Particulate 3E-11 Ventilation discharge (if Ni-63 Particulate 1E-11 applicable) Gross Alpha 1E-11 (1) The requirements listed in this table for Continuous Releases are applicable for release paths that are available. Page 75 of 267
Revision 5 Aug 31, 2015 TABLE 12.4-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM (Cont'd} MINIMUM TYPE OF LOWER LIMIT OF GASEOUS RELEASE SAMPLING ANALYSIS ACTIVITY DETECTION (LLD} TYPE METHOD FREQUENCY ANALYSIS (µCi/cc} (f} D. Unventilated Building Releases< 1> Continuous (h} Daily(c) Particulate 1 E-11 Principal Gamma Emitters (e) Composite Quarterly Sr-90 Particulate 1E-11 Fe-55 Particulate 3E-11 Ni-63 Particulate 1 E-11 Gross Alpha 1E-11 1 This requirement sampling point may be used for any release point that is unventilated and will be tracked as an abnormal gaseous discharge point.TABLE 12.4-1 Page 76 of 267
Revision 5 Aug 31, 2015 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS PROGRAM (Cont'd) TABLE NOTATIONS
- a. The daily sampling requirement is applicable when 1RIA-PR49 or 2R-PR49A is inoperable AND decommissioning activities that can create airborne radioactivity are in progress in the associated building (Containment and/or AB).
- b. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period in Section 12.4.1.
- c. The particulate filter(s) shall be saved for a quarterly composite analysis for Sr-90, Ni-63, Fe-55 and gross alpha.
- d. DELETED
- e. For particulate emissions, the principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Nb-94, Co-60, Cs-137 and Sb-125. Other peaks which are measurable and identifiable by gamma-ray spectrometry, together with the above nuclides, shall also be identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being at the LLD level for that nuclide.
- f. The LLD is defined in Notation a. of Table 12.3-2.
- g. DELETED
- h. Sampling interruptions of short duration for routine activities, e.g. filter replacement or opening/closing of the construction door, do not constitute a deviation from the requirements for continuous sampling.
- i. DELETED Page 77 of 267
Revision 5 Aug 31, 2015 12.4.2 DELETED 12.4.3 Dose - Tritium and Radioactive Material in Particulate Form Operability Requirements 12.4.3.A The dose to a MEMBER OF THE PUBLIC from tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas at or beyond the SITE BOUNDARY (see Appendix F, Figure F-1) shall be limited to the following:
- 1. During any calendar quarter: Less than or equal to 7 .5 mrem to any organ, and
- 2. During any calendar year: Less than or equal to 15 mrem to any organ.
Applicability: At all times. With the calculated dose from the release of tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents exceeding twice the limits of Section 12.4.3.A:
- 1. Limit subsequent releases such that the dose or dose commitment to a MEMBER OF THE PUBLIC from all uranium fuel cycle sources to less than or equal to 25 mrem to the total body or organ (except the thyroid which is limited to less than or equal to 75 mrem) over 12 consecutive months.
- 2. Prepare an analysis which demonstrates that radiation exposures to all MEMBERS OF THE PUBLIC from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40CFR Part 190 Standard. Otherwise, request a variance from the Commission to permit release which exceeds the 40CFR Part 190 Standard. The radiation exposure analysis shall use the methods prescribed in the ODCM.
Surveillance Requirements 12.4.3.B Cumulative dose contribution for the current calendar quarter and current calendar year for tritium, and all radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodologies and parameters in the ODCM at least once per 31 days. 12.4.3.C This Section implements the requirements of Sections 11.C, Ill.A and IV.A of Appendix I, 10CFR Part 50. The Operability Requirements are the guides set forth in Section 11.C of Appendix I. The ACTION statements provide the required operating flexibility and at the same time, implement the guides set forth in Section IV.A of Appendix I to assare that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculation methods specified in the Surveillance Requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The release-rate specifications for radioactive material in particulate form are dependent on the existing radionuclide pathways to man, at or beyond the SITE BOUNDARY. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) disposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man. Page 78 of 267
Revision 5 Aug31, 2015 12.4.4 Gaseous Effluent Treatment System Operability Requirements 12.4.4.A The GASEOUS EFFLUENT TREATMENT SYSTEM shall be OPERABLE* and appropriate portions of these systems shall be used to reduce radioactive materials in gaseous effluents when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at or beyond the SITE BOUNDARY (see Appendix F, Figure F-1) would exceed 0.3 mrem to any organ.
*The GASEOUS EFFLUENT TREATMENT SYSTEM shall be considered OPERABLE by meeting Sections 12.4.1 and/or 12.4.3, as applicable.
Applicability: At all times. Action: With the Gaseous Effluent Treatment System inoperable for more than 30 days or with radioactive gaseous waste being discharged without treatment and in excess of the above limits, return the system to OPERABLE status and place the appropriate portions of the system in use. Surveillance Requirements 12.4.4.B Doses due to gaseous releases from each unit to areas at or beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodologies and parameters in the ODCM when the Gaseous Effluent Treatment Systems are not beirig fully utilized. 12.4.4.C The OPERABILITY of the GASEOUS EFFLUENT TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to the release to the environment. he requirement that the appropriate portions of this system be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This section implements the requirement of 10CFR50.36a, General Design Criterion 60 of Appendix A to 10CFRSO and the design objective given in Section 11.D of Appendix I to 10CFR50. The specified limits governing the use of appropriate portions of the Gaseous Effluent Treatment System were specified as a 2% fraction of the dose design objectives set forth in Section 11.B and 11.C of Appendix I, 10CFR50, for gaseous effluents. Page 79 of 267
Revision 5 Aug 31, 2015 12.5 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.5.1 Monitoring Program Operability Requirements 12.5.1.A The Radiological Environmental Monitoring Program shall be conducted as specified in Table 12.5-1. Applicability: At all times.
- 1. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 12.5-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting a program as required and the plans for preventing a recurrence.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditjons, seasonal unavailability, malfunction of sampling equipment, if a person who participates in the program goes out of business or no longer can provide sample, or contractor omission which is corrected as soon as discovered. If the equipment malfunctions, corrective actions shall be completed as soon as practical. If a person/business supplying samples goes out of business, a replacement supplier shall be found as soon as possible. All deviations from the sampling schedule $hall be described in the Annual Radiological Environmental Operating Report.
- 2. With the level of radioactivity as a result of plant effiuents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 12.5-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose* to a MEMBER OF THE PUBLIC is less than the calendar year limits of Section 12.3.2or12.4.3. When more than one of the radionuclides in Table 12.5.2 are detected in the sampling medium, this report shall be submitted if:
concentration (1) + concentration (2) + ... ~ 1.0 reporting level (1) reporting level (2) When radionuclides other than those in Table 12.5-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Section 12.3.2 or 12.4.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.
- The methodology and parameters used to estimate the potential dose to a MEMBER OF THE PUBLIC shall be indicated in the report.
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- 3. If the sample type or sampling location(s) required by Table 12.5-1 become(s) permanently unavailable, identify suitable alternative sampling media for the pathway of interest and/or specific locations for obtaining replacement samples and add them to the Radiological Environmental Monitoring Program as soon as practicable. The specific locations from which samples were unavailable may then be deleted from the program.
Prepare and submit a controlled version of the ODCM within 180 days including a revised figure(s) and table reflecting the new location(s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of new location(s) for obtaining samples. Surveillance Requirements 12.5.1.B.1 The Radiological Environmental Monitoring samples shall be collected from the locations specified in the ODCM and analyzed pursuant to Table 12.5-1 and the detection capabilities required by Table 12.5-3. 12.5.1.C The Radiological Environmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10CFR50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements anc! modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The specified monitoring program is based on baseline/historical conditions for direct radiation measurements, soil, biota, and sediments established over years of operational experience and current site conditions/operating activities. The REMP need only be re-evaluated for major changes to site conditions/configuration (e.g., prior to site decommissioning, if a significant release occurs, changing baseline data ... ). Program changes may be initiated at any time based on operational experience. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLD}. The LLDs required by Table 12.5-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA., "Limits for Qualitative Detection and Quantitative Determination-Application to Radiochemistry," Anal. Chem. 40, 586-93 {1968), and Gartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). Interpretations 12.5.1.D Table 12.5-1 requires "one sample of each community drinking water supply downstream of the plant within 1O kilometers (6.2 miles)." Drinking water supply is defined as water taken from river, lakes, or reservoirs (not well water) which is used for drinking. Since Lake Michigan has no designated downstream or upstream direction, two drinking water locations (one north/one south} within 10 kilometers shall be sampled as drinking water indicator locations, and two other locations (one north/one south) beyond 10 kilometers shall be sampled as control locations. Page 81 of 267
Revision 5 Aug 31, 2015 TABLE 12.5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONs< 1> FREQUENCY ANALYSIS . G '**
- 1. Airborne Samples from a total of three locations: Particulate Sam~ler:
Continuous sampler operation Gross beta analysis following
- a. Indicator- Near Field with particulate sample collection 3 weekly filter chan~e< >and gamma weekly (or more frequently if isotopic analysis< quarterly on Three samples from locations within 4 km required due to dust loading).
composite filters by location on (2.5 mi) in different sectors. near field samples.
- b. Control- Far Field One sample from location 15-25 km (10-17 mi) in minimal D/Q sector.
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Revision 5 Aug 31, 2015 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1 EXPOSURE NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLE LOCATIONs< > SAMPLING AND TYPE AND PATHWAY COLLECTION FREQUENCY OF AND/OR FREQUENCY ANALYSIS SAMPLE
- 2. Direct Thirty-one routine monitoring stations with thermoluminescent dosimeters (TLD),
Radiationt 5l placed with at least one monitoring location in each meteorological sector, as follows:
- a. Indicator- Inner Ring (100 Series TLD) in the general area of the SITE BOUNDARY (0.1 to 1.5 mi);
- b. Other- One at each Airborne location given in part 1.a. Including 1 control TLD location located at control air sample station given in part 1.b. Quarterly Gamma dose on each TLD quarterly.
- c. Indicator- Outer Ring (100 Series TLD) in the general area of the 5 mile ring.
(2.0 to 10 mi); Other TLDs may be placed at special interest locations beyond the Restricted Area where either a MEMBER OF THE PUBLIC or Commonwealth Edison employees have routine access. Page 83 of 267
Revision 5 Aug 31, 2015 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS( 1l FREQUENCY ANALYSIS
- 3. Waterborne
- a. Drinking Water lndicator(6l One Sample from each community Gross beta and gamma isotopic drinking water supply that could be analyses( 4l on monthly composite; Weekly grab samples. tritium analysis on quarterly affected by the station discharge within 10 km (6.2 mi) of discharge (north/south). composite.
- b. Control(6>
Gross beta and gamma isotopic One sample upstream and downstream Weekly grab samples. analyses(4> on monthly composite; (north/south) of discharge. tritium analysis on quarterly composite.
- c. Sediments At least one sample within 10 km (6.2 mi) Semiannually. Gamma isotopic analysis (4l of discharge semiannually.
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Revision 5 Aug 31, 2015 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES SAMPLING AND COLLECTION TYPE AND FREQUENCY OF AND/ OR SAMPLE AND SAMPLE LOCATIONS( 1> FREQUENCY ANALYSIS
- 4. Ingestion
- a. Fish Indicator Representative samples of commercially and recreationally important species in Semiannually Gamma isotopic analysis(4l on discharge area. edible portions.
- b. Control Representative samples of commercially Semiannually Gamma isotopic analysis on edible and recreationally important species not portions.
influenced by plant discharge.
- 5. Vegetation
- a. Vegetation Indicator 3 Different types of broadleaf vegetation grown in the local area at publicly available vegetable markets. 2 Different types of root Annual (during growing season) Gamma isotopic analysis( 4l on vegetables grown in the local area at edible portions.
publicly available vegetable markets.
- b. Vegetation Control 3 Different types of broadleaf vegetation Annual {during growing season) Gamma isotopic analysis(4l on grown in the local area at publicly available edible portions.
vegetable markets. 2 Different types of root vegetables grown in an area >8 mi (12 km) from publicly available vegetable markets. Page 85 of 267
Revision 5 Aug 31, 2015 TABLE 12.5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every sample location in Table 11-1 of the ODCM Station Annexes. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. (2) Deleted - No longer applicable. (3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thorium daughter decay. If gross beta activity in any individual air particulate sample is greater than 10 times the 1999 mean of control samples, then, a gamma isotopic analysis shall be performed on that elevated individual sample. (4) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station. or identification of nuclides that are same type but not attributable to station effluents in the case of 'control' samples (5) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The number of locations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., If a station is adjacent to a lake (i.e. Zion), some sectors may be over water thereby reducing the number of dosimeters which could be placed at the indicated distances. The frequency of analysis or readout for TLD systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. (6) Refer to Section 12.5.1.D for interpretation on the applicability of "downstream" and "upstream". If no community drinking water supply exists within 6.2 miles of the discharge, surface water sampling shall be performed.
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Revision 5 Aug 31, 2015 TABLE 12.5-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES* ANALYSIS WATER (pCi/L) AIRBORNE FISH (pCi/kg, wet) Vegetation (pCi/kg, PARTICULATE OR wet) GASES (pCi/m 3) H-3 20,000 \II Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 Cs-134 30 10 1,000 Cs-137 50 20 2,000 2,000 Ba-La-140 200 (1) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.
*This table contains reporting levels for analyses beyond the requirements of Table 12.5-1.
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Revision 5 Aug 31, 2015 TABLE 12.5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYS1s<1l LOWER LIMIT OF DETECTION (LLD)<2 > AIRBORNE Vegetation WATER PARTICULATE FISH (pCi/kg, wet) SEDIMENT ANALYSIS (pCi/L) OR GASES (pCi/kg, wet) (pCi/kg, dry) (pCi/m 3) Gross Beta 4 0.01 1000 H-3 2,000\;j) Mn-54 15 130 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 Cs-134 15 0.01 100 150 Cs-137 18 0.01 100 80 180 Page 88 of 267
Revision 5 Aug 31, 2015 TABLE 12.5-3 (Continued) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS (1) This table contains lower limits of detection for analyses beyond the requirements of Table 12.5-1. This table does not imply that only these nuclides are to be detected and reported; other peaks which are measurable and identifiable in the analyses required by Table 12.5-1 shall be reported in the Annual Radiological Environmental Operating Report. (2) The Lower Limit of Detection (LLD} is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation, the LLD is defined as follows: LLD = (E) (V) (2.22) (Y) (exp (-A~t)) LLD - (E) (V) (2.22) (Y) (exp (-Mt)) Where: 4.66 Sb >> 3/tb
- LLD =the "a priori" Lower Limit of Detection (picocuries per unit mass or volume),
sb = the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (counts per minute),
.J Total Counts
=
E =the counting efficiency( counts per disintegration}, V =the sample size (units of mass or volume), 2.22 =the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular ra-dionuclide (sec*1), tb =counting time of the background or blank (minutes), and Page 89 of 267
Revision 5 Aug 31, 2015 TABLE 12.5-3 (Continued) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS TABLE NOTATIONS
~t = the elapsed time between sample collection, or end of the sample collection period, and the time of counting (sec).
Typical values of E, V, Y, and ~t should be used in the calculation. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report. (3) This is the minimum required LLD; however, environmental samples analyzed off-site will be required to use 200 pCi/I. Page 90 of 267
Revision 5 Aug 31, 2015 12.5.2 LAND USE CENSUS Operability Requirements 12.5.2.A. A Land Use Census shall be conducted and shall identify within a distance of 10 km (6.2_mi.) the location, in each of the following meteorological sectors, A, J, K, L, M, N, P, Q, and R**, the nearest residence. For dose calculation, a garden will be assumed at the nearest will residence .. For REMP purposes, aerial phographs or equivalent method shall be used to determine the nearest garden/farm >500 sq. ft (50sq meters) in each sector within 10 mi. (15km) Applicability: At all times. Action: With a Land Use Census identifying location(s) that yields a calculated dose or dose commitment, via the same exposure pathway 20% greater than at a location from which samples are currently being obtained in accordance with Section 12.5.1, add the new location(s) within 30 days to the Radiological Environmental Monitoring Program given in Chapter 11 of the ODCM Station Annexes. The sampling location(s), excluding the control location, having the lowest calculated dose or dose commitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this Land Use Census was conducted. Submit in the next Annual Radiological Environmental Operating Report documentation for a change in the ODCM including revised figure(s) and table(s) for the ODCM reflecting the new location(s) with information supporting the change in sampling locations.
** The nearest industrial facility shall also be documented if closer than the nearest residence.
Surveillance Requirements 12.5.2.B The Land Use Census shall be conducted, between June 1 and October 1, at least once_per calendar year using that information that will provide the best results, such as by a door-to-door survey or aerial survey. The result of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report. 12.5.2.C This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Page 91 of 267
Revision 5 Aug 31, 2015 12.5.3 INTERLABORATORY COMPARISON PROGRAM Operability Requirements 12.5.3.A Analyses shall be performed on radioactive materials supplied as part of an interlaboratory comparison program that correspond to samples required by Table 12.5.1. Applicability: At all times.
- 1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.
Surveillance Requirements 12.5.3.B A summary of the results obtained as part of the above required interlaboratory comparison program shall be included in the Annual Radiological Environmental Operating Report. 12.5.3.C The requirement for participation in an interlaboratory comparison program is provided to ensure that independent checks on the preci$ion and accuracy of the measurements of radioactive material in environmental samples matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the resultS are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50. Page 92 of 267
Revision 5 Aug 31; 2015 12.6 PROCESS CONTROL PROGRAM (PCP) 12.6.1 PCP Program Requirements Contains the requirements and methodology for the current formulas, sampling, analyses, tests, and determinations performed to ensure the processing and packaging of solid radioactive wastes based on actual or simulated wet solid wastes is accomplished in compliance with:
- 10CFR Parts 20, 61, and 71
- State Regulations
- Burial Site Requirements
- Other Requirements Governing the Shipping and Burial of Radioactive Waste 12.6.2 Changes to the PCP Changes to the PCP include those changes that affect the process or methodology, by which wastes are solidified, packaged to meet burial site form requirements, classified, or dewatered.
12.6.2.1. Shall be documented and records of reviews performed shall be retained, and Shall contain sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s), and Shall contain a determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations, and Shall become effective after review and approval by the Decommissioning Plant Manager. Page 93 of 267
Revision 5 Aug 31, 2015 12.7 REPORTING REQUIREMENTS 12.7.1 Annual Radiological Environmental Operating Report* Routine Annual Radiological Environmental Operating Report covering the operation of the Unit(s) during the previous calendar year shall be submitted according to the Permanently Defueled Technical Specifications. The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including, as found appropriate, a comparison of preoperational studies with operational controls or with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The Annual Radiological Environmental Operating Report shall include the results of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in the Chapter 11 of the ODCM Station Annexes, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units; reasons for not conducting the Radiological Environmental Monitoring Program as required by Section 12.5.1, and discussion for all deviations from the sampling schedule of Table 11.1-1; a Table of Missed Samples and a Table of Sample Anomalies for all deviations from the sampling schedule of Table 11.1-1; discussion of environmental sample measurements that exceed the reporting levels of Table 12.5-2 but are not the result of plant effluents; discussion of all analyses in which the LLD required by Table 12.5-3 was not achievable; results of the Land Use Census required by Section 12.5.2; and the results of licensee participation in an interlaboratory comparison program and the corrective actions being taken if the specified program is not being performed as required by Section 12.5.3. The Annual Radiological Environmental Operating Report shall also include an annual summary of hourly meteorological data collected over the applicable year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radiological Environmental Operating Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
- A single submittal may be made for a multiple unit station.
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Revision 5 Aug 31, 2015 The Annual Radiological Environmental Operating Report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This report shall also include an assessment of radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM and in compliance with 10 CFR 20 and 40 CFR Part 190, "Environmental Radiation Protection Standards for Nuclear Power Operation." 12.7.2 Annual Radioactive Effluent Release Report** The Annual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Material in Liquid and Gaseous Effluent from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. The Annual Radioactive Effluent Release Report shall include a list and description of unplanned releases of radioactive material in liquid effluents from the site to UNRESTRICTED AREAS and of unplanned releases of radioactive material in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY during the reporting period. The Annual Radioactive Effluent Release Report shall include any changes made during the reporting period to the Process Control Program as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12. 7.4. The Annual Radioactive Effluent Release Report shall also include the following: an explanation as to why the inoperability of liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified in Section 12.2.1 or 12.2.2, respectively; and description of the events leading to liquid holdup tanks exceeding the limits of the Quality Assurance Project Plan App.B. 12.7.2.1 Exceptions to Regulatory Guide 1.21 Reporting Requirements:
- a. All references to "semiannual" are not applicable. The report will be submitted according to Quality Assurance Project Plan (QAPP).
- b. Hourly meteorological data is recorded for all periods throughout the year, and quarterly summaries will be reported. Separate meteorological data for periods of batch releases are not required to be included.
- c. Total body and significant organ doses to the maximally exposed individual from receiving-water-related exposure pathways will be provided. Associated population dose is not required to be included.
- d. Organ doses to the maximally exposed individual in unrestricted areas from radioactive material in particulate form from all exposure pathways will be provided. Associated population dose is not required to be included.
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Revision 5 Aug 31, 2015
- e. Total body doses to the maximally exposed individual in unrestricted areas from direct radiation from the facility should be included in the report. Associated population dose is not required to be included.
- f. Total body doses to the population and average doses to individuals in the population from all receiving-water-related pathways are not required to be included.
- g. Total body doses to the population and average doses to individuals in the population from gaseous effluents to a distance of 50 miles from the site and beyond will not be included.
- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
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Revision 5 Aug 31, 2015 12.7.3 Offsite Dose Calculation Manual CODCM) 12.7.3.1 Changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be retained as required by QAPP. This documentation shall contain:
- 1. Sufficient Information to support the change together with the appropriate analyses or evaluations justifying the change( s); and
- 2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- 3. Documentation of the fact that the change has been reviewed and found acceptable by a Qualified Technical Review.
- b. Shall become effective after the approval of the Decommissioning Plant Manager on the date specified by the Qualified Technical Review.
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,
month/year) the change was implemented. 12.7.4 Major Changes to Liquid and Gaseous Effluent Treatment Systems*** Licensee-initiated major changes to the Effluent Treatment Systems (liquid and gaseous):
- a. Shall be reported to the Commission in the Annual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by a Qualified Technical Review. The discussion of each change shall contain:
- 1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;
- 2) Sufficient detailed information to totally support the reason for the change without benefit of additional and supplemental information;
- 3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.
- 4) An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents that differ from those previously predicted in the License application and amendments thereto;
- 5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC and to the general population that differ from those previously estimated in the License application and amendments thereto; Page 97 of 267
Revision 5 Aug 31, 2015
- 6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents, to the actual releases for the period prior to when the changes are to be made;
- 7) An estimate of the exposure to plant operating personnel as a result of the change; and
- 8) Documentation of the fact that the change was reviewed and found acceptable by a Qualified Technical Review.
- b. Shall become effective upon review and acceptance by the Qualified Technical Review.
- Licensees may choose to submit the information called for in this standard as part of the biennial DSAR update.
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Revision 5 Aug 31, 2015 APPENDIX A COMPLIANCE METHODOLOGY Page 99 of 267
Revision 5 Aug 31, 2015 APPENDIX A COMPLIANCE METHODOLOGY A.O INTRODUCTION This appendix reviews the offsite radiological limits applicable to Zion Station' and presents in detail the equations and procedures used to assess compliance with these limits. An introduction to the calculation approach used here is given in Chapter 4. The approach incorporates simplifications such as the following: Use of pre-calculated atmospheric transport parameters based on historical average atmospheric conditions (see Section 4.1.5). These atmospheric dispersion and deposition factors are defined in Chapter 4. The equations and parameters of this appendix are for use in calculating offsite radiation doses during routine operating conditions. They are not for use in calculating doses due to non-routine releases (e.g., accident releases). This section of the ODCM provides the methodological details for demonstrating compliance with the 10CFR20, 10CFR50 Appendix I, 10CFR72.104 and 40CFR190 radiological limits for liquid and gaseous effluents. An overview of the required compliance is given in Tables 2-1, 2-2, and 2-3. In Table 2-1, the dose components are itemized and referenced, and an indication of their regulatory application is noted. A more detailed compliance matrix is given in Table 2-3. Additionally, the locations of dose receivers for each dose component are given in Table 2-2. The following sections detail the required radiological dose calculations. A.1 AIRBORNE RELEASES A.1.1 Release Point Classifications The pattern of dispersion of airborne releases is dependent on the height of the release point relative to adjacent structures. For the equations of this appendix, each release point is classified as one of the following three height-dependent types, which are defined in Section 4.1.4:
- Stack (or Elevated) Release Point (denoted by the letter Sor subscripts)
- Ground Level Release Point {denoted by the letter G or subscript g)
- Vent (or Mixed Mode) Release Point (denoted by the letter V or subscript v)
The release point classifications of routine release points at Zion Station are stated in Table A-2. A.1.2 Dose Due to Noble Gas Radionuclides A.1.2.1 Gamma Air Dose Requirement RETS limit the gamma air dose due to noble gas effluents released from each reactor unit to areas at and beyond the unrestricted area boundary to the following:
- Less than or equal to 5 mrad per calendar quarter.
- Less than or equal to 10 mrad per calendar year.
Page 100 of 267
Revision 5 Aug 31, 2015 Equation The gamma air dose due to noble gases released in gaseous effluents is calculated by the following expression: Dr = (3.17E - 8 )L M; { (x/Qt i A;s + (x/Q)~ A;v + (x/Q)~ A; 0 } (A-1) The summation is over noble gas radionuclides i. Gamma Air Dose [mrad] Dose to air due to gamma radiation from noble gas radionuclides released in gaseous effluents. 3.17E-8 Conversion Constant (seconds to years) [yr/sec] M; Gamnia Air Dose Conversion Factor [(mrad/yr)/(µCi/m 3 )] Gamma air dose rate factor per unit of radioactivity release rate for radionuclide i. From Table B-1 of Reg Guide 1.190. (x/Q)~' (x/Q)~' (x/Q)~ Gamma-x/Q Factor Radioactivity concentration based on finite cloud methodology at a specific location per unit of radioactivity release rate from a stack, vent or ground level release, respectively. See Section B.3.5 and Table F-5b of appendix F. Cumulative Radionuclide Release [µCi] Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively. Application RETS require determination of cumulative and projected gamma air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days (see Sections 12.4 of Zion Station' RETS or Technical Specifications). Gamma air dose is calculated for the sector with the highest offsite (x/Qf and is compared with the RETS limits on gamma air dose. For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10. Page 101 of 267
Revision 5 Aug 31, 2015 A.1.2.2 Beta Air Dose Requirement RETS limit the beta air dose due to noble gases in gaseous effluents released from each reactor unit to areas at and beyond the unrestricted area boundary to the following:
- Less than or equal to 10 mrad per calendar quarter.
- Less than or equal to 20 mrad per calendar year.
Equation The beta air dose due to noble gases released in gaseous effluents is calculated by the following expression: Dp =(3.17E- s)L {N;((x/Q)sAis + (x/Q)vAiv + (x/Q)9 A; 9 ]} (A-2) i The summation is over noble gas radionuclides i. Beta Dose [mrad] Dose to air due to beta radiation from noble gas radionuclides released in gaseous effluents. 3.17E-8 Conversion Constant (seconds to years) [yr/sec] 3 N; 13eta Air Dose Conversion Factor [(mrad/yr)/(µCi/m )] Beta air dose rate per unit of radioactivity concentration for radionuclide i. Take from Table C-9 of Appendix C. (x/Q)s Relative Concentration Factor (x/Q)v
<xtQ)g Radioactivity concentration based on semi-infinite cloud methodology at a specified location per unit of radioactivity release rate for a stack, vent, or ground level release, respectively. See Section 4.1.6, Section B.3 of Appendix B, and Table F-5 of Appendix F.
Cumulative Radionuclide Release [µCi] Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively. Application RETS require determination of cumulative and projected beta air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days (see Section 12.4
- of Zion Station RETS or Technical Specification).
Beta air dose is calculated for the sector with the highest offsite (x/Q) and is compared with the RETS limit on beta air dose. For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10. Page 102 of 267
Revision 5 Aug 31, 2015 A.1.2.3 Total Body Dose Requirement The total body dose, to any receiver is due, in part, to gamma radiation emitted from radioactivity in airborne effluents. This component is added to others to demonstrate compliance to the requirements of 40CFR190 and 10CFR20. Equation The total body dose component due to gamma radiation from noble gases released in gaseous effluents is calculated by the following expression: Dre =(3.17E-8}LK;{(x/Q)~A;s +{x/Q)~A;v +{x;onA;9 } (A-3) i The summation is over noble gas radionuclides i. Drs Total Body Dose [mrem] Dose to the total body due to gamma radiation from noble gas radionuclides released in gaseous effluents. 3.17E-8 Conversion Constant (seconds to years) [yr/sec] K; Gamma Total Body Dose Conversion Factor [(mrem/yr)/(uCi/m3)] Gamma total body dose factor due to gamma emissions for noble gas radionuclide i released from a stack, vent or ground level release point, respectively. Taken from Table C-9 of Appendix C. A;s, A;v. A;g Cumulative Radionuclide Release [µCi] Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively. Application The total body dose is also calculated for the 40CFR190 and 10CFR20 compliance assessments. In some cases, the total body dose may be required in 10CFR50 Appendix I assessments (See Table 2-1 ). A.1.2.4 Skin Dose Requirement There is no regulatory requirement to evaluate skin dose. However, this component is evaluated for reference as there is skin dose design objective contained in 10CFR50 Appendix I. Note that in the unlikely event that if beta air dose guideline is exceeded, then the skin dose will require evaluation. Equation The part of skin dose due to noble gases released in gaseous effluents is calculated by the following expression: DsK = (3.17E - 8} L {L; [ {x/Q} A; 5 5 + {x/Q}v A;v + {x/Q}9 A, 9 ] i (A-4)
+ (1.11)M, [ (x/Q)~Ais +{x/Q)~Aiv +{x/Q)~A;g]}
Page 103 of 267
Revision 5 Aug 31, 2015 The summation is over noble gas radionuclides i. DsK Skin Dose [mrem] Dose to the skin due to beta and gamma radiation from noble gas radionuclides released in gaseous effluents. 3 Beta Skin Dose Conversion Factor [(mrem/yr)/(µCi/m )] Beta skin dose rate per unit of radioactivity concentration for radionuclide i. Taken from Table C-9 of Appendix C. 1.11 Conversion Constant (rads in air to rem in tissue) [mrem/mrad] All other terms have been previously defined. Application The skin dose is calculated for reference only. A.1.3 Dose Rate Due to Noble Gas Radionuclides A.1.3.1 Total Body Dose Rate Requirement RETS limit the total body dose rate due to noble gases in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to 500 mrem/yr at all times. (see Section 12.4 of Zion Station RETS and Technical Specifications) Equation The total body dose rate due to noble gases released in gaseous effluents is calculated by the following expression: ihe = LK; ((x/Q)~Qis +{x/Q)~Qiv +{x/0)~0; 9 } (A-5) i The summation is over noble gas radionuclides i. D10 Total Body Dose Rate [mrem/yr] Dose rate to the total body due to gamma radiation from noble gas radionuclides released in gaseous effluents. Release Rate [µCi/sec] Measured release rate of radionuclide i from a stack, vent or ground level release point, respectively. All other terms have been previously defined. Page 104 of 267
Revision 5 Aug 31, 2015 Application RETS require the dose rate due to noble gases in gaseous effluents be determined to be within the above limit in accordance with methodology specified in the ODCM (see Section 12.4 of Zion Stations RETS and Technical Specifications). To comply with this specification, Zion Station uses an effluent radiation monitor setpoint corresponding to an offsite total body dose rate at or below the limit (see Chapter 10). In addition, Zion Station assesses compliance by calculating offsite total body dose rate on the basis of periodic samples obtained in accordance with station procedures. A.1.3.2 Skin Dose Rate Requirement RETS limit the skin dose rate due to noble gases in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to a dose rate of 3000 mrem/yr at all times. (See Section 12.4 of Zion Stations RETS and/or Technical Specifications) Equation The skin dose rate due to noble gases released in gaseous effluents is calculated by the following expression: DsK = L{L;[(x/Q)sQis +{x/Q)vQiv +{x/0) 0; 9 9] i (A-6)
+ (1.11) M; [ (x/Q)~O;s +{x/Q)~O;v +{x/Q)~0; 9 ]}
The summation is over noble gas radionuclides i. DsK Skin Dose Rate [mrem/yr] Dose rate to skin due to beta and gamma radiation from noble gas radionuclides released in gaseous effluents. Release Rate [µCi/sec] Measured release rate of radionuclide i from a stack, vent or ground level release point, respectively. All other terms been previously defined. Application RETS require the dose rate due to noble gases in gaseous effluents to be determined to be within the above limit in accordance with methodology specified in the ODCM. (See Section 12.4 of ZionSolutions' RETS and Technical Specifications.) To comply with this specification, Zion Station uses an effluent radiation monitor setpoint corresponding to an offsite skin dose rate at or below the limit (see Chapter 10). In addition, ZionSo/utions' assesses compliance by calculating offsite skin dose rate on the basis of samples obtained periodically in accordance with site procedures. Page 105 of 267
Revision 5 Aug 31, 2015 A.1.4 Dose Due to Non-Noble Gas Radionuclides Requirement RETS provide the following limits, based on 10CFR50 Appendix I, on the dose to a member of the public from specified non-noble gas radionuclides in gaseous effluents released from each reactor unit to areas at and beyond the unrestricted area boundary: Less than or equal to 7.5 mrem to any organ during any calendar quarter. Less than or equal to 15 mrem to any organ during any calendar year. The individual dose components are also required as part of the 40CFR190 assessments and combined as part of the 10CFR20 assessment (See Section A.4 ). The dose due to radionuclides deposited on the ground is considered to be a component of the deep dose equivalent for 10CFR20 compliance and an organ (and total body) dose component for 10CFR50 Appendix I and 40CFR190 compliance. In accordance with the definition of dose in Regulatory Guide 1.109, the term "dose" in this document when applied to individuals, is used instead of the more precise term "dose equivalent," as defined by the International Commission on Radiological Units and.Measurements (ICRU). When applied to the evaluation of internal deposition of radioactivity, the term "dose" as used here, includes the prospective dose component arising from retention in the body beyond the period of environmental exposure, i.e., the dose commitment. The dose commitment is evaluated over a period of 50 years. Assessments for 10CFR50 Appendix I compliance are made for 4 age groups (adulUteenager/child/infant) using Regulatory Guide 1.109 (Reference 6) dose conversion factors. Equation The dose is calculated for releases in the time period under consideration. Specifically, the dose is calculated as follows: D~NG = (3.17E-8)_'L_'L[WsRaipiAis + WvRaipiAiv + W 9 RaipiA; 9 ] (A-7) p i The summation is over pathways p and non-noble gas radionuclides i. Dose Due to Non-Noble Gas Radionuclides [mrem] Dose due to non-noble gases (tritium and particulates) to age group a, and to organ j. 3.17E-8 Conversion Constant (seconds to years) [yr/sec] Relative Concentration Factor Radioactive concentration at a specific location per unit of radioactivity release rate or concentration for stack, vent or ground level release, respectively. Ws, Wv, or W 9 = (x/O)s, (x/O)v or (x/0)9 for immersion, inhalation and all tritium pathways. W 5 , Wv, or W 9 =(D/0) 5 , (D/O)v or (D/Q) 9 for ground plain and all ingestion pathways. Page 106 of 267
Revision 5 Aug 31, 2015 3 (x/Q)s, (x/Q)v. (x/Q)g Relative Concentration Factor [sec/m ] Radioactivity concentration based on semi-infinite cloud model at a specified location per unit of radioactivity release rate for a stack, vent, or ground level release, respectively. See Section 4.1.6, Section B.3 of Appendix B, and Table F-5 of Appendix F. (D/Q)s. (D/Q)v. (D/Q)g Relative Deposition Factor Radioactivity concentration at a specified location per unit of radioactivity release concentration for a stack, vent, or ground level release, respectively. See Section 4.1.6, Section B.3 of Appendix B, and Table F-6 of Appendix F. 2 Raipi Site-Specific Dose Factor [(m mrem/yr)/(µCi/sec)] 3 or [(mrem/yr)/(µCi/m )] Site-specific dose factor for age group a, nuclide i, pathway p and organ
- j. Pathway included are ground plane exposure, inhalation, vegetation inge~tion, milk ingestion and meat ingestion. Values of Raipi are provided in Appendix F.
Cumulative Radionuclide Release [µCi] Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively. Application RETS require cumulative and projected dose contributions for the current calendar quarter and the current calendar year for the specified non-noble gas radionuclides in airborne effluents to be determined at least once per 31 days (see Section 12.4 of Zion Stations' RETS and Technical Specifications). To comply with this specification, Zion Station obtains and analyzes samples in accordance with the radioactive gaseous waste or gaseous effluent sampling and analysis program in its RETS. In accordance with NUREG 0133 (Reference 14), dose due to non-noble gases is assessed at the location in the unrestricted area where the combination of existing pathways and receptor age groups indicates the maximum potential exposure. The inhalation and ground plane exposure pathways are considered to exist at all locations. The food ingestion pathways at a specific location are considered based on their existence as determined by land use census. The values used for (x/Q) and (D/Q) correspond to the applicable pathway location. For a release attributable to a processing or effluent system shared by more than one reactor, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10. The dose evaluated is also included as part of the 10CFR20 and 40CFR190 assessment (See Section A.4). A.1.4.1 Ground Deposition The site-specific dose factor for ground deposition of radioactivity is considered to be a total body dose component and is calculated by the following expression: Page 107 of 267
Revision 5 Aug 31, 2015 (A-8) 2 Rai(GP)i [D/Q] Ground Plane Deposition Dose Factor [(m mrem/yr)/(µCi/sec)] Site-specific ground plane dose factor for age group a, nuclide i and organ j. The ground plane dose is calculated using (D/Q). K' Conversion Constant (1 E6 pCi per µCi) [pCi/µCi] K" Conversion Constant (8760 hr/yr) [hr/yr] 0.7 Shielding Factor; a factor which accounts for dimensionless shielding due to occupancy of structures. 2 Ground Plane Dose Conversion Factor [(mrem/hr)/(pCi/m )] Dose rate to the total body per unit of surface radioactivity concentration due to standing on ground uniformly contaminated with radionuclide i. Taken from Table C-10 of Appendix C. Note that ground plane dose factors are only given for the total body and no age group. Doses to other organs are assumed to be equal to the total body dose. All age groups are assumed to receive the same dose. Radiological Decay Constant Radiological decay constant for radionuclide i. See Table C-7 of Appendix C. Time Period of Ground Deposition [hr] Time period during which the radioactivity on the ground is assumed to have been deposited. See Table C-1 of Appendix C. Application The ground plane exposure pathway is considered to exist at all locations. A.1.4.2 Inhalation The site-specific dose factor for inhalation is calculated by the following expression: (A-9) 3 Rai(lnhal)j [x/Q] Inhalation Pathway Dose Factor [(mrem/yr)/(µCi/m )] Site-specific inhalation dose factor for age group a, nuclide i and organ j. The inhalation dose is calculated using (x/Q). K' Conversion Constant (1 E6 pCi per µCi) [pCi/µCi] 3 BRa Individual Air Inhalation Rate [m /yr] Page 108 of 267
Revision 5 Aug 31, 2015 The air intake rate for individuals in age group a. See Table C-2 of Appendix C. DFAaii Inhalation Dose Conversion Factor [mrem/pCi] Dose commitment to an individual in age group a to organ j per unit of activity of radionuclide i inhaled. Taken from Tables E-7 through E-10 of Regulatory Guide 1.109. The value for H-3 is taken from NU REG 4013 (Reference 107). Application The inhalation exposure pathway is considered to exist at all locations. A.1.4.3 Food Ingestion Pathway Dose Factors Application Food ingestion pathway doses are calculated at locations indicated by the land use census survey. If no real pathway exists within 5 miles of the station, the cow-milk pathway is assumed to be located at 5 miles. Food pathway calculations are not made for sectors in which the offsite regions near the station are over bodies of water. A.1.4.3.1 Vegetation Ingestion Pathway Dose Factor The dose factor for consumption of vegetables is calculated by the following expression: (A-10) 2 Vegetation Ingestion Pathway Dose Factor [(m mrem/yr)/(µCi/sec)] Site-specific vegetation ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3, the vegetation dose is calculated using (D/Q). K' Conversion Constant (1 E6 pCi per µCi) [pCi/µCi] r Vegetation Retention factor dimensionless Agricultural Productivity Yield Radiological Decay Constant [1/sec] Radiological decay constant for radionuclide i. See Table C-7 of Appendix C. Weathering Decay C<?nstant [1/sec] Removal constant for physical loss of activity by weathering. See Table C-1 of Appendix C. DFLaii Ingestion Dose Conversion Factor [mrem/pCi] Ingestion dose conversion factor for age group a, nuclide i and organ j. Converts pCi ingested to mrem. Taken from Tables E-11 though E-14 of Page 109 of 267
Revision 5 Aug 31, 2015 Regulatory Guide 1.109. The value for H-3 is taken from NUREG 4013 (Reference 107). Consumption Rate for Fresh Leafy Vegetation [kg/yr] Consumption rate for fresh leafy vegetation for age group a. Consumption Rate for Stored Vegetation [kg/yr] Consumption rate for stored vegetation for age group a. Local Leafy Vegetation Fraction dimensionless Fraction of the annual intake of fresh leafy vegetation which is grown locally. Local Stored Vegetation Fraction dimensionless Fraction of the annual intake of stored vegetation which is grown locally. Environmental Transport Time - Fresh Vegetation [sec] Average time between harvest of leafy vegetation and its consumption. Environmental Transport Time - Stored Vegetation [sec] Average time between harvest of stored vegetation and its consumption. The tritium dose from the vegetation pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium vegetation pathway is: (A-11) Ra(H-3)(vee)i [x/Q] Tritium Vegetation Ingestion Pathway Dose Factor [(mrem/yr)/(µCi/m 3l] Site-specific tritium vegetation ingestion dose factor for age group a and organ j. The tritium vegetation dose is calculated using x/Q. K"' Conversion Constant (1 E3 gm per Kg) [gm/Kg] H Absolute Atmospheric Humidity [gm/m 3] 0.75 Water Fraction dimensionless The fraction of total vegetation that is water. 0.5 Specific Activity Ratio dimensionless Page 110 of 267
Revision 5 Aug 31, 2015 A.1.4.3.2 Milk Ingestion Pathway Dose Factor The dose factor for consumption of milk is calculated by the following expressions: (A-12) 2 Rai(Milk)j [D/Q] Milk Ingestion Pathway Dose Factor [(m mrem/yr)/(µCi/sec)] Site-specific milk ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3, the milk dose factor is calculated using (D/Q). K' Conversion Constant (1E6 pCi per µCi) [pCi/µCi] Feed Co_nsumption [Kg/da] Amount of feed consumed by milk animal each day. See Table C-1 of Appendix C. Milk Consumption Rate [I/yr] Milk consumption rate for age group a. Stable Element Transfer Coefficient for Milk [da/I] Fraction of animal's daily intake of a particular chemical element which appears in each liter of milk (pCi/I in milk per pCi/da ingested by animal). See Table C-3 of Appendix C. Pasture Time Fraction dimensionless Fraction of year that animal is on pasture. Pasture Grass Fraction dimensionless Fraction of animal feed that is pasture grass while animal is on pasture. Agricultural Productivity Yield - Pasture Grass The agricultural productivity by unit area of pasture feed grass. Ys Agricultural Productivity Yield - Stored Feed The agricultural productivity by unit area of stored feed. Environmental Transport Time - Stored Feed [sec] Average time between harvest to consumption of stored feed by milk animal. Page 111 of 267
Revision 5 Aug 31, 2015 Environmental Transport Time - Pasture to Consumption [sec] Average time from pasture, to milk animal, to milk, to consumption. All other terms have been previously defined. The tritium dose from the milk pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium milk pathway is: (A-13) 3 Tritium Milk Ingestion Pathway Dose Factor [(mrem/yr)/(µCi/m )] Site-specific tritium milk ingestion dose factor for age group a and organ
- j. The tritium milk dose is calculated using x/Q.
K"' Conversion Constant (1 E3 gm per Kg) [gm/Kg] H Absolute Atmospheric Humidity [gm/m 3] 0.75 Water Fraction dimensionless The fraction of total vegetation that is water. 0.5 Specific Activity Ratio dimensionless All other terms have been previously defined. A.1.4.3.3 Meat The dose factor for consumption of meat is calculated by the following expression: (A-14) 2 Rai(Meat)j [D/Q] Meat Ingestion Pathway Dose Factor [(m mrem/yr)/(µCi/sec)] Site-specific meat ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3, the meat dose factor is calculated using (D/Q). Meat Consumption Rate [I/yr] Meat consumption rate for age group a. Stable Element Transfer Coefficient for Meat [da/Kg] Fraction of animal's daily intake of a particular chemical element which appears in each liter of meat (pCi/Kg in meat per pCi/da ingested by animal). See Table C-3 of Appendix C. Page 112 of267
Revision 5 Aug 31, 2015 Environmental Transport Time - Stored Feed [sec] Average time between harvest to consumption of stored feed by meat animal. Environmental Transport Time - Pasture to Consumption [sec] Average time from pasture, to meat animal, to meat, to consumption. All other terms have been previously defined. The tritium dose from the meat pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factor for the tritium meat pathway is: (A-15) R a(H:-3 )(Meat )i fx/ Q] Tritium Meat Ingestion Pathway Dose Factor [(mrem/yr)/(µCi/m 3
)]
Site-specific tritium meat ingestion dose factor for age group a and organ
- j. The tritium meat dose is calculated using x/O.
K"' Conversion Constant (1 E3 gm per Kg) [gm/Kg] 3 H Absolute Atmospheric Humidity [gm/m ] 0.75 Water Fraction dimensionless The fraction of total vegetation that is water. 0.5 Specific Activity Ratio dimensionless All other terms have been previously defined. A.1.5 Dose Rate Due to Non-Noble Gas Radionuclides Requirement RETS limit the dose rate to any organ, due to radioactive materials in gaseous effluents released from a site to areas at and beyond the site boundary, to less than or equal to a dose rate of 1500 mrem/yr (see Section 12.4 of ZionSolutions' RETS and Technical Specifications). Typically the child is considered to be the limiting receptor in calculating dose rate to organs due to inhalation of non-noble gas radionuclides in gaseous effluents. Equation The dose rate to any child organ due to inhalation is calculated by the following expression: (A-16) The summation is over non-noble gas radionuclides i. Page 113 of267
Revision 5 Aug 31, 2015
- NNG D (Child)i(lnhal)i Inhalation Dose Rate [mrem/yr]
Dose rate to the child age group from radionuclide i, via the inhalation pathway to organ j due to non-noble gas radionuclides. 3 R(Child)i(lnhal)j Inhalation Dose Factor [(mrem/yr)/(µCi/m )] Inhalation dose factor for child age group for radionuclide i, and organ j. This dose factor is defined by Equation A-9. Radionuclide Release Rate [µCi/sec] Measured release rate of radionuclide i from a stack, vent, or ground level release point, respectively. All other terms have been previously defined. Application RETS require the dose rate due to non-noble gas radioactive materials in airborne effluents be determined to be within the above limit in accordance with a sampling and analysis program specified in the RETS (see Section 12.4 of Zion Solutions' RETS and Technical Specifications). To comply with this specification, ZionSo/utions' obtains and analyzes samples in accordance with the sampling and analysis program in its RETS. The child organ dose rate due to inhalation is calculated in each sector at the location of the highest offsite x/O. The result for the sector with the highest organ inhalation dose rate is compared to the limit. A.1.6 Operability and Use of Gaseous Effluent Treatment Systems Requirement 10CFR50 Appendix I and the station RETS require that the ventilation exhaust treatment system and the waste gas holdup system be used when projected offsite doses in 31 days, due to gaseous effluent releases, from each reactor unit, exceed any of the following limits:
- 0.2 mrad to airfrom gamma radiation.
- 0.4 mrad to air from beta radiation.
- 0.3 mrem to any organ of a member of the public.
ZionSolutions' is required to project doses due to gaseous releases from the site at least once per 31 days. Equation Offsite doses due to projected releases of radioactive materials in gaseous effluents are calculated using Equations A-1, A-2 and A-7. Projected cumulative radionuclide releases are used in place of measured cumulative releases Ais* Aiv and Aig* Application For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in Chapter 10 of this manual. Page 114 of 267
Revision 5 Aug 31, 2015 A.2 LIQUID RELEASES A.2.1 Dose Requirement The design objectives of 10CFR50, Appendix I and RETS provide the following limits on the dose to a member of the public from radioactive materials in liquid effluents released from each reactor unit to restricted area boundaries: During any calendar quarter, less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ. During any calendar year, less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ. The organ doses due to radioactivity in liquid effluents are also used as part of the 40CFR190 compliance and are included in the combination of doses to determine the total dose used to demonstrate 10CFR20 compliance. (See Section A.4) Dose assessments for 10CFR50 Appendix I compliance are made for four age groups (adulUteenager/child/infant) using NU REG 0133 (Reference 14) methodology and Regulatory Guide 1.109 (Reference 6) dose conversion factors. Equation The dose from radioactive materials in liquid effluents considers the contributions for consumption of fish and potable water. All of these pathways are considered in the dose assessment unless demonstrated not to be present. While the adult is normally considered the maximum individual, the methodology provides for dose to be calculated for all four age groups. The dose to each organ (and to the total body) is calculated by the following expression: D~]q = F At LLAaipiC; (A-17) p i The summation is over exposure pathways p and radionuclides i. Organ and Total Body Dose Due to Liquid Effluents [mrem] Dose to organ j (including total body) of age group a due to radioactivity in liquid effluents. F Near Field Average Dilution Factor dimensionless Dilution in the near field averaged over the period of interest. Defined as: F= Waste Flow (A-18) Dilution Flow x Z Waste Flow Liquid Radioactive Waste Flow [gpm] The average flow during disposal from the discharge structure release point into the receiving water body. Dilution Flow Dilution Water Flow During Period of Interest [gpm] Page 115 of 267
Revision 5 Aug 31, 2015 z Discharge Structure Mixing Factor dimensionless Site-specific factor to account for the mixing effect of the discharge structure. The factor addresses the dilution which occurs in the near field between the discharge structure and the body of water containing the fish in the liquid ingestion pathway. From Table F-1, Appendix F. At Duration of Release [hrs] Average Radionuclide Concentration [µCi/ml] Average concentration of radionuclide i, in the undiluted liquid effluent during time period At. Aaipj Site-Specific Liquid Dose Factor [(mrem/hr)/(µCi/ml)] Site-specific dose factor for age group a, nuclide i, liquid pathway p and organ j. The pathways included are potable water and fish ingestion. Aaipi is defined for these pathways in the following sections. Values for Aaipi are provided in Appendix F. A 2.1.1 Potable Water Pathway The site-specific potable water pathway dose factor is calculated by the following expression: (A-19) Where: Aai(PW)j Site-Specific Dose Factor for Potable Water [(mrem/hr)/(µCi/ml)] Pathway Site-specific potable water ingestion dose factor for age group a, nuclide i and organ j. Conversion Constant (1.14E05) [(yr-pCi-ml)/(hr-µCi-1)] Units constant to convert years to hours, pCi to µCi and liters to ml. Potable Water Consumption Rate [I/yr] Potable water consumption rate for age group a. Taken from Table E-5 of Regulatory Guide 1.109. Potable Water Dilution Factor dimensionless Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake. From Table F-1, Appendix F. DFLaii Ingestion Dose Conversion Factor [mrem/pCi] Ingestion dose conversion factor for age group a, nuclide i and organ j. Converts pCi ingested to mrem. Taken from Tables E-11 though E-14 of Page 116 of 267
Revision 5 Aug 31, 2015 Regulatory Guide 1.109. The value for H-3 is taken from NU REG 4013 (Reference 107). A.2.1.2 Fish Ingestion Pathway The site-specific fish ingestion pathway dose factor is calculated by the following expression: (A-20) Where: Aai(Fish)j Site-Specific Dose Factor for Potable Water [(mrem/hr)/(µCi/ml)] Pathway Site-specific fish ingestion dose factor for age group a, nuclide i and organj. Fish Consumption Rate [kg/yr] Fish consumption rate for age group a. Taken from Table E-5 of Regulatory Guide 1.109. Bioaccumulation Factor [(pCi/kg)/(pCi/I)] Bioaccumulation factor for nuclide i in fresh water fish. Taken from Table C-8 of Appendix C. All other terms have been previously defined. Application RETS require determination of cumulative and projected dose contributions from liquid effluents for the current calendar quarter and the current calendar year at least once per 31 days. (see Section 12.3 of ZionSolutions' RETS and/or Technical Specifications). For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10. A.2.2 Liquid Effluent Concentrations Requirement Requirement One method of demonstrating compliance to the requirements of 10CFR20.1301 is to demonstrate that the annual average concentrations of radioactive material released in gaseous and liquid effluents do not exceed the values specified in 10CFR20 Appendix B, Table 2, Column 2. (See 10CFR 20.1302(b)(2).) However, as noted in Section A.5.1, this mode of 10CFR20.1301 compliance has not been elected. As a means of assuring that annual concentration limits will not be exceeded, and as a matter of policy assuring that doses by the liquid pathway will be ALARA; RETS provides the following restriction: "The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentration values in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402." This also meets the requirement of Station Technical Specifications and RETS. Page 117 of 267
Revision 5 Aug 31, 2015 Equation According to the footnotes to 10CFR20 Appendix B, Table 2, Column 2, if a radionuclide mix of known composition is released, the concentrations must be such that L( C; )<1 10ECL; - (A-21) where the summation is over radionuclide i. C; Radioactivity Concentration in [µCi/ml] Liquid Effluents to the Unrestricted Area Concentration of radionuclide i in liquid released to the unrestricted area. ECL; Effluent Concentration Limit in Liquid [µCi/ml] Effluents Released to the Unrestricted Area The allowable annual average concentration of radionuclide i in liquid effluents released to the unrestricted area. This concentration is specified in 10CFR20 Appendix B, Table 2; Column 2. Concentrations for noble gases are different and are specified in the stations' Technical Specifications/RETS. 10 Multiplier to meet the requirements of Technical Specifications. If either the identity or concentration of any radionuclide in the mixture is not known, special rules apply. These are given in the footnotes in 10CFR20 Appendix B, Table 2, Column 2. Application The RETS and Technical Specifications require a specified sampling and analysis program to assure that liquid radioactivity concentrations at the point of release are maintained within the required limits. To comply with this provision, ZionSo/(Jfions' obtains and analyzes samples in accordance with the radioactive liquid waste (or effluent) sampling and analysis program in its RETS. Radioactivity concentrations in tank effluents are determined in accordance with Equation A-22 in the next section. Comparison with the Effluent Concentration Limit is made using Equation A-21. A.2.3 Tank Discharges When radioactivity is released to the unrestricted area with liquid discharge from a tank (e.g., a radwaste discharge tank), the concentration of a radionuclide in the effluent is calculated as follows: Waste Flow C; = C~ Dilution Flow (A-22) Concentration in Liquid effluent to the unrestricted area. [µCi/ml] Concentration of radionuclide i in liquid released to the unrestricted area. Concentration in the Discharge Tank [µCi/ml] Measured concentration of radionuclide i in the discharge tank. All other terms have been previously defined. Page 118 of 267
Revision 5 Aug 31, 2015 A.2.4 Tank Overflow Requirement To limit the consequences of tank overflow, the quantity of radioactivity that may be stored in unprotected outdoor tanks is limited. Unprotected tanks are tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. The specific objective is to provide assurance that in the event of an uncontrolled release of a tank's contents, the resulting radioactivity concentrations beyond the unrestricted area boundary, at the nearest potable water supply and at the nearest surface water supply, will be less than the limits of 10CFR20 Appendix B, Table 2, Column 2. Application Table F-1 of Appendix F provides information on the limits for Zion Station. A.2.5 Operability and Use of the Liquid Radwaste Treatment System Requirement The design objectives of 10CFR50, Appendix I and RETS/Technical Specifications require that the liquid radwaste treatment system be operable and that appropriate portions be used to reduce releases of radioactivity when projected doses due to the liquid effluent from each reactor unit to restricted area boundaries exceed either of the following (see Section 12.3 of Zion Solutions' RETS or Technical Specifications);
- 0.06 mrem to the total body in a 31 day period.
- 0.2 mrem to any organ in a 31 day period.
Equation Offsite doses due to projected releases of radioactive materials in liquid effluents are calculated using Equation A-17. Projected radionuclide release concentrations are used in place of measured concentrations, Ci. A.2.6 Drinking Water Zion Solutions' has requirements for calculation of drinking water dose that are related to 40CFR 141, the Environmental Protection Agency National Primary Drinking Water Regulations. These are discussed in Section A.6. A.2.7 Non-routine Liquid Release Pathways Cases in which normally non-radioactive liquid streams (such as the Service Water) are found to contain radioactive material are non-routine will be treated on a case specific basis if and when this occurs. Since Zion Station has sufficient capacity to delay a liquid release for reasonable periods of time, it is expected that planned releases will not take place under these circumstances. Therefore, the liquid release setpoint calculations need not and do not contain provisions for treating multiple simultaneous release pathways. A.3 DOSE DUE TO CONTAINED SOURCES There are multiple types of contained sourc~s of radioactivity which contribute to ZionSo/utions' offsite radiological dose assessments. When the ISFSI if fully loaded it will contain 61 Vertical Concrete Casks (VCCs) containing Spent Nuclear Fuel and 4 VCCs containing Greater Than Class C (GTCC) Waste. The GTCC waste is composed primarily of reactor internals segments from both Unit 1 and Unit 2. There is a waste staging area in the Southern region of the Radiological Restricted Area for 8-120 liners containing Waste Class A, B and C. Page 119 of 267
Revision 5 Aug 31, 2015 This waste is composed primarily of reactor internals segments from both Unit 1 and 2. These 8-120s are stored inside of concrete Rad Vaults then surrounded by several feet of soil above ground level. At various times throughout D&D, there will be various rail cars, lntermodals, Sealands, and various other waste containers staged onsite prior to shipment to a disposal facility. All of these various sources contribute to offsite dose from both directly emitted radiations and radiations due to skyshine from directly emitted radiations. A.3.1 Dose from Onsite Radioactive Waste Storage Low-level radioactive waste may be stored at Zion in the following types of containers and storage areas:
- Concrete vaults
- Butler buildings/warehouses
- Shipping containers while awaiting shipment
- Independent Spent Fuel Storage Installation (ISFSI) Facilities The dose rates resulting from these containers and storage areas will be monitored frequently as they are being utilized, and if necessary, a dose calculation performed to assess projected dose rates from such containers and storage areas. Dose calculations shall be documented in site specific Technical Support Documents and referenced in the ODCM.
A.4 Total Dose Limits (10CFR20, 10CFR72 and 40CFR190) The regulatory requirements of 10CFR20, 10CFR72 and 40CFR190 each limit total dose to individual members of the public without regard to specific pathways. The only significant exposure pathways for light water reactors included in 10CFR20, 10CFR72 and 40CFR190 not addressed by 10CFR50 Appendix I are the direct radiation pathway and exposure from on-site activity by members of the public. Sections A.1 and A.2 considered organ doses from the gaseous and liquid effluent streams for purposes of compliance with 10CFR50 Appendix I. Section A.3 addresses the direct radiation component that must be considered for 10CFR20, 10CFR72 and 40CFR190 compliance. The following sections will describe the methodology of assessing direct radiation dose and then the manner in which the various doses are combined to obtain the appropriate "total" for regulatory compliance purposes. Althbugh annual dose limits in 10CFR20 are now expressed in terms of Total Effective Dose Equivalent (TEDE) 40CFR190 limits are still stated as organ dose. The NRC continues to require 10CFR50 Appendix I, 10CFR72 and 40CFR190 doses to be reported in terms of organ dose. Due to the fact that organ dose limits set forth in 40CFR190 are substantially lower than those of 10CFR20 (25 mrem/yr vs 100 mrem/yr), the NRC has stated that demonstration of compliance with the dose limits in 40CFR190 will be deemed as demonstration of compliance with the dose limits of 10CFR20 for most facilities (Reference 104). In addition to compliance with 40CFR190 it may be necessary for a nuclear power plant to address dose from on-site activity by members of the public. A.4.1 External Total Body Dose The external total body dose is comprised of the following parts:
- 1) Total body dose due to noble gas radionuclides in gaseous effluents (Section A.1.2),
- 2) Dose due to radioactive waste and the ISFSI (Section A.3.1) and
- 3) Total body dose due to radioactivity deposited on the ground (Section A.1 .4.1 ).
The external total body dose due to radioactivity deposited on the ground is accounted for in the determination of the non-noble gas dose (See Equations A-7 and A-8) and is not considered here. Page 120 of 267
Revision 5 Aug 31, 2015 The total external total body dose, DEx, is given by: oEx= 0 Ts + 0 osF (A-23) Total External Total Body Dose [mrem] Total external~total body dose due to irradiation by external so1.irces at the location of interest. Noble Gas Total Body Dose [mrem] External total body dose due to gamma radiation from noble gas radionuclides released in gaseous effluents at the location of interest. See Equation A-3. Dose From On-Site Storage Facilities [mrem] External total body dose due to gamma radiation from on-site storage facilities at the location of interest. See Section A.3.1 . A.4.2 Total Dose The total dose, DTot, in the unrestricted area to a member of the public due to plant operations is given by: (A-24) where: 0Tot Total Dose To Member of Public [mrem] Total off-site dose to a member of public due to plant operations. Total External Total Body Dose [mrem] Total body dose due to external exposure to noble gases and on-site radioactive waste storage. Liquid Effluent Dose [mrem] Dose due to liquid effluents to age group a and organ j. The age group and organ with the highest dose from liquid effluents is used. Non-Noble Gaseous Effluent Dose [mrem] Dose due to non-noble gaseous effluents to age group a and organ j. The age group and organ with the highest dose from non-noble gas effluents is used. Page 121 of 267
Revision 5 Aug 31, 2015 A.5 COMPLIANCE TO TOTAL DOSE LIMITS A.5.1 Total Effective Dose Equivalent Limit -10CFR20 Compliance Requirement ZionSo/utions' RETS limits the Total Effective Dose Equivalent {TEDE) to an annual limit of 100 mrem, as required by 10CFR20.1301 (a)(1 ). Demonstration of compliance with the limits of 40CFR190 (per Section 4.5.2) will be considered to demonstrate compliance with the 100 mrem/year limit. A.5.1.1 Dose to a Member of the Public in the Unrestricted Area The NRC has stated that demonstration of compliance with the limits of 40CFR190 or with the design objectives of Appendix I to 10CFR50 will be deemed to demonstrate compliance with the limits of 10CFR20.1301{a}{1 ). Power reactors that comply with 10CFR50 Appendix I may also have to demonstrate that they are within the 25 mrem limit of 40CFR190 (See Reference 104). Zion Station ISFSI pad operations are required to demonstrate compliance with 10CFR72.104 limits. A.5.1.2. Dose to a Member of the Public in the Restricted Area In August of 1995, a revision to 10CFR20 was implemented that changed the definition of a member of the public. NUREG/CR-5569, "Health Physics Positions Database" Question 26(a) clarifies dose to a member of the public while inside the Restricted Area. "By definition, and with the exceptions given in the definitions of "occupational dose", any dose received by any individual in a "restricted area" is an "occupational dose." No one in a restricted area is a "member of the public."" Non-trained radiation workers are administratively restricted to less than 160 total hours on site property per year. Application Evaluation of the 40CFR190 dose is used to demonstrate compliance to 10CFR20, 10CFR72 and satisfy station RETS and Technical Specifications (see Chapter 12). A.5.2 Total Dose due to the Uranium Fuel Cycle (40CFR190) Requirement RETS, 40CFR190 and 10CFR72.104 limit the annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources to the following:
- Less than or equal to 25 mrem to the total body.
- Less than or equal to 25 mrem to any organ except the thyroid.
- Less than or equal to 75 mrem to the thyroid.
Total Dose Components This requirement includes the total dose from operations at the nuclear power station. This includes doses due to radioactive effluents (airborne and liquid) and dose due to direct radiation from non-effluent sources (e.g., sources contained in systems on site such as the ISFSI). The operations comprising the uranium fuel cycle are specified in 40CFR190.02(b). The following are included to the extent that they directly support the production of electrical power for public use utilizing nuclear energy:
- Milling of uranium ore.
- Chemical conversion of uranium.
Page 122 of 267
Revision 5 Aug 31, 2015
- Isotopic enrichment of uranium.
- Fabrication of uranium fuel.
- Generation of electricity by a light-watered-cooled nuclear power plant using uranium fuel.
- Reprocessing of spent uranium fuel.
Excluded are:
- Mining operations.
- Operations at waste disposal sites.
- Transportation of any radioactive material in support of these operations.
- The re-use of recovered non-uranium special nuclear and by-product materials from the cycle.
The different methods of Decommissioning, SAFSTOR, ENTOMB and DEGON, are not mentioned in 40CFR190. Zion was previously a light-water-cooled nuclear power plant that used uranium fuel to generate electricity, therefore, 40CFR190 is applied to the different methods of Decommissioning at Zion. When Compliance Assessment is Required Compliance with the 40CFR190 regulations is now required as part of demonstration of compliance to 10CFR20 regulations per 10CFR20.1301(d), and 10CFR72 regulations per 10CFR72.104. Equation The dose due to the uranium fuel cycle is determined by equation A-24. A.5.3 Summary of Compliance Methodology The required compliance is given in Tables 2-1, 2-2 and 2-3. In Table 2-1, the dose components are itemized and referenced, and an indication of their regulatory application is noted. A more detailed compliance matrix is given in Table 2-3. The locations of dose receivers for each dose component are given in Table 2-2. Further, Table 2-2 states the location of the receiver and occupancy factors, if applicable. In general, the receiver spends time in locations that result in maximum direct dose exposure and inhales and ingests radioactivity from sites that yield maximum pathway doses. Thus, the dose calculated is a very conservative one compared to the "average" receiver who does not go out of his way to maximize radioactivity uptakes. Occupancy as a habit of a "real individual" is applied to doses received from contained sources. Finally, the connection between regulations, the ODCM equations and the station RETS and Technical Specifications is given in Table 12-0. ISFSI 10CFR72.104 dose limits are the same as those specified by 40CFR190. ISFSI dose contribution is in the form of direct radiation as no liquid or gas releases are expected to occur. The report prepared in accordance with 10CFR72.212 requirements assumes a certain array of vertical concrete casks exists on the ISFSI. The dose contribution from this array of casks was analyzed to be within the 40CFR190 and 10CFR72.104 limits, and is documented in NAC International Calculation 630073-5501 ZION Site Boundary Skyshine Evaluation, Zion Technical Support Document TSD 13-008 "Evaluation of Independent Spent Fuel Storage Installation and Associated processes Dose Rates" and TSD 13-009 "Member of the Public Dose From All Onsite Sources". If the dose limits of 40CFR190 or 10CFR72.104 are exceeded, a special report to the NRC as well as an appropriate request for exemption/variance is required to be submitted to the NRC. Page 123 of 267
Revision 5 Aug 31, 2015 The requirement that the dose limits of 10CFR72.104 apply to any "real individual" is controlled for ISFSI activities in the ISFSI 72.212 report. Therefore, for the purposes of analyzing dose from the ISFSI, the member of the public as defined in 40CFR 190 is the same as the "real individual" identified in the ES&H TSD 13-008 "Evaluation of Independent Spent Fuel Storage Installation and Associated processes Dose Rates" and TSD 13-009 "Member of the Public Dose From All Onsite Sources". A.6 DOSE DUE TO DRINKING WATER (40CFR141) The National Primary Drinking Water Regulations, 40CFR141, contain the requirements of the Environmental Protection Agency applicable to public water systems. Included are limits on radioactivity concentration. Although these regulations are directed at the owners and operators of public water systems, Zion Station has requirements in their Technical Specifications related to 40CFR141. A.6.1 40CFR141 Restrictions on Manmade Radionuclides Section 141.16 states the following (not verbatim): (a) The average annual concentration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annual dose equivalent to the total body or any internal organ greater than 4 millirem/year. (b) Except for the radionuclides listed in Table A-0, the concentration of man-made radionuclides causing 4 mrem total body or organ dose equivalents shall be calculated on the basis of drinking 2 liter of water per day. (Using the 168 hour data listed in "Maximum Permissible Body Burdens and Maximum Permissible Concentration of Radionuclides in Air or Water for Occupational Exposure, "NBSHandbook 69 as amended August 1963, U.S. Department of Commerce.). If two or more radionuclides are present, the sum of their annual dose equivalents to the total body or any organ shall not exceed 4 millirem/year. Page 124 of 267
Revision 5 Aug 31, 2015 TABLEA-0 AVERAGE ANNUAL CONCENTRATIONS ASSUMED TO PRODUCE A TOTAL BODY OR ORGAN DOSE OF 4 MREM/YR Radionuclide Critical Oraan oCi/Liter Tritium Total Bodv 20,000 Strontium-90 Bone Marrow 8 A.6.2 Application The projection or calculation of dose due to the drinking water pathway is made using Equations A-17 and A-19. Projections are made using projected radionuclide releases in place of measured releases Ai. Doses calculated using Equations A-17 and A-19 may differ from doses determined by the methodology prescribed in 40CFR141.16. When required, Zion Station prepares a special report on radiological impact at the nearest community water system. This system is taken as the one listed in Table A-3 of this appendix. The report should include the following:
- The doses calculated by Equations A-17 and A-19.
- A statement identifying the dose calculation methodology (e.g., a reference to this manual).
- A statement that the doses calculated by the ODCM methodology are not necessarily the same as doses calculated by the methodology prescribed in 40CFR141.16.
- The data used to calculate the doses. This information includes the amounts of radioactivity released and the flow rate and dilution values used (see Table F-1). This information is provided to assist the operator of the community water system in performing its own dose assessment.
Page 1*25 of 267
Revision 5 Aug 31, 2015 Table A-1 COMPLIANCE MATRIX Regulation Dose to be compared to limit 10CFR50
- Gamma air dose and beta air dose due to airborne radioactivity in effluent Appendix I plume.
- Total body and skin dose due to airborne radioactivity in effluent plume are reported only if certain gamma and beta air dose criteria are exceeded.
- Dose for all organs and all four age groups due to particulate in effluent plume. Existing pathways are considered.
- Dose for all organs and all four age groups due to radioactivity in liquid effluents.
10CFR20
- Adherence determined by compliance with dose limits of 40CFR190 .
40CFR190
- Total body dose due to direct radiation, ground and plume exposure from all sources at a station.
- Organ doses to an adult due to all pathways .
RETS/ODCM * "Instantaneous" noble gas total body and skin dose rates and tritium and particulate inhalation dose rates to a child due to radioactivity in airborne effluents.
* "Instantaneous" concentration limits for liquid effluents .
10CFR72.104(a)
- During normal operations and anticipated occurrences .
Page 126 of 267
Revision 5 Aug 31, 2015 TableA-2 Release Point Classifications Release Release Point Station Point Classificationa Zion 1 & 2 Vent Stacks Ground Level aThe definitions of release point classifications (stack, vent and ground level) are given in Section 4.1.4. TableA-3 Nearest Downstream Community Water Systems Characteristics of Nearest Affected Downstream Community Water Supply Location and Station Distancea Zion Lake County Intake, 1.4 miles a Appendix 0 Table 0-2 provides the basis of the location and distance data. Page 127 of 267
Revision 5 Aug 31, 2015 TableA-4 40CFR190, 10CFR72.104(a) Compliance 40CFR190 Dose Annual Limit ODCM Dose and Equation Number (mrem) 10CFR72.104(a) Dose Total Body 25 Total Body Dose; A-24 evaluated for total body Thyroid 75 Thyroid Dose; A-24 evaluated for thyroid Other Organs 25 Organ Dose; A-24 evaluated for all organs except thyroid Notes:
- 1. The evaluation is made considering the following sources:
- a. Radioactivity in contained sources within the station;
- b. Radioactivity in station gaseous and liquid effluents; Page 128 of 267
Revision 5 Aug 31, 2015 APPENDIX B MODELS AND PARAMETERS FOR AIRBORNE AND LIQUID EFFLUENT CALCULATIONS Page 129 of 267
Revision 5 Aug 31, 2015 APPENDIX B MODELS AND PARAMETERS FOR AIRBORNE EFFLUENT CALCULATIONS B.O INTRODUCTION The equations used for calculation of doses due to radioactive airborne effluents are given in Section A.1 of Appendix A. The equations involve the following types of parameters:
- Meteorological Parameters These include xJQ, gamma-x/Q, D/Q and wind speed. Their values are based on historical average atmospheric conditions at a site for a selected multi-year historical period (see Section 4.1 .5).
- Dose Factors These parameters are used to provide a simple way to calculate doses and dose rates due to gamma and beta radiation. These parameters are independent of meteorological conditions and therefore generic (i.e., not station-specific).
- Measured Release Parameters These are measured values of radioactivity releases and release rates.
- Radiological Decay Constants These are used to account for the radioactive decay between the release of radioactivity to the environment and the exposure of persons to it.
- Production/Exposure Parameters These are parameters characterizing agricultural production (e.g., length of growing season, transport times) and human exposure patterns (e.g., exposure period, breathing rate, food consumption rates). These parameters affect the quantities of radioactivity to which persons may be exposed.
This appendix discusses the methodology used to determine values of these parameters. Section 8.1 addresses how the historical meteorology of a site is characterized by use of a function called the joint frequency distribution. Section 8.1 and Sections 8.3 through 8.5 present equations that use the joint frequency distribution to obtain values for site-specific meteorological parameters. These equations involve a mathematical model of a plume known as the Gaussian plume model. This model is developed in Section 8.2. Various generic dose factors are discussed in Sections 8.6 through B.10. The other parameters are discussed in the remaining sections. B.1 METEOROLOGICAL DATAAND PARAMETERS Predicting where airborne effluent will travel requires information on the following:
- Wind speed
- Wind direction
- Atmospheric turbulence The greater the atmospheric turbulence, the more an effluent plume will tend to broaden and the more dilute the concentration will be. Atmospheric turbulence is affected by the general condition of the atmosphere (e.g., the vertical temperature distribution) and by local features (e.g., objects that protrude into the wind stream). A commonly used classification scheme for the degree of atmospheric turbulence associated with the general condition of the atmosphere involves seven stability classes:
A Extremely Unstable 8 Moderately Unstable C Slightly Unstable D Neutral E Slightly Stable Page 130 of 267
Revision 5 Aug 31, 2015 F Moderately Stable G Extremely Stable This classification scheme is based on Reference 5, Table 1. Each class is associated with a particular range of wind direction fluctuations and of vertical temperature gradients in the atmosphere. These are specified in Table C-4 of Appendix C. 8.1.1 Data Historical atmospheric conditions at Zion Station were recorded by an instrumented meteorological tower that measured wind speed, wind direction, and temperature at various heights. Hourly average values of wind speed, wind direction, and stability class were determined. The difference in temperature between two heights was used to assign an atmospheric stability class based on the correlation between temperature gradient and stability class in Table C-4 of Appendix C. In obtaining the data, quality assurance checks and corrections were made. Also, corrections were applied to compensate for the limitations of wind sensors at low speeds. A calm was said to exist if the wind speed was less than that of the threshold of either the anemometer (wind speed meter) or the wind direction vane. For calm conditions, a wind speed equal to one-half of the higher threshold was assigned. For each stability class, the wind directions during calm conditions were assumed to be distributed in proportion to the observed wind direction distribution of the lowest non-calm wind speed class. 8.1.2 Joint Frequency Distribution The data for a particular historical period are summarized by developing a joint frequency distribution (JFD). Each such distribution specifies the fraction of time during the historical period that the following jointly occur: *
- Wind speed within a particular range (wind speed class).
- Downwind direction in one of the 16 sectors corresponding to the 16 principal compass directions (N, NNE, etc.).
- Atmospheric conditions corresponding to one of the seven atmospheric stability classes discussed in Section B.1. Table B-1 of this appendix displays a portion of an example JFD.
Different JFDs are associated with the different release classifications defined in Section 4.1.4. One JFD is defined for stack releases, and another JFD is defined for ground level releases. Two JFDs are associated with vent (mixed mode) releases, one for the portion of the time the release is treated as elevated and the other for the portion of the time the release is treated as ground level. 8.1.2.1 Downwind Direction Versus Upwind Direction Unless otherwise noted, any reference to wind direction in this document represents downwind direction, i.e., the direction in which the wind is blowing toward. _This is because the parameters developed in this document are used to calculate radioactivity concentration and radiation dose downwind of a release point. In contrast, it is conventional for meteorologists to provide JFDs based on upwind direction, the direction from which the wind is blowing. For example, the JFDs presented in the annual operating report of Zion Station are obtained from a meteorological contractor and the directions specified in the reports are upwind directions. Users of JFDs should always be careful to ascertain whether the directions specified are upwind or downwind. 8.1.2.2 Stack JFD For a stack release, the JFD is defined as follows: Page 131 of 267
Revision 5 Aug 31, 2015 l:f5 (n,0,c) Joint Frequency Distribution, Stack Release The fraction of hours during a period of observation that all of the following hold:
- The average wind speed is within wind speed class n.
- The downwind direction is within the sector denoted by 0.
- The atmospheric stability class is c.
This function is defined for application to a stack release point (see Section 4.1.4 ). Its value is based on hourly average wind data obtained at a height representative of the release point height. The stack JFD is normalized to 1: l: f 5 (n,0,c) =1 (B-25) The summation is over all wind speed classes n, all compass direction sectors 0, and all stability classes c. B.1.2.3 Ground Level JFD For a ground level release, the JFD fg(n, 0,c) is defined in the same way as for a stack release except that the wind data are obtained at a height representative of a ground level release point. This height is taken as about 10 meters. The ground level JFD is normalized to 1: l: t 9 (n,0,c) =1 (B-26) The summation is over all wind speed classes n, all compass direction sectors, and all stability classes c. B.1.2.4 VentJFDs In accordance with the approach recommended in Regulatory Guide 1.111 (Reference 7), the plume from a vent release is treated as elevated part of the time and as ground level the rest of the time. Two JFDs are determined:
- fv,elev(n,0,c) characterizes the plume during the part of the time that it is considered elevated;
- fv,gnd(n,0,c) characterizes the plume during the part of the time that it is considered ground level.
Their definitions are as follows: fv,elev(n,0,c) Joint Frequency Distribution, Elevated Portion of a Vent Release The fraction of hours during a period of observation that the plume is considered elevated and that all of the following hold:
- The average wind speed is within wind speed class n.
- The downwind direction is within the sector denoted by 0.
- The atmospheric stability class is c.
fv,gnd(n,0,c) Joint Frequency Distribution, Page 132 of 267
Revision 5 Aug 31, 2015 Ground Level Portion of a Vent Release The fraction of hours during a period of observation that the plume is considered ground level and that all of the following hold:
- The average wind speed is within wind speed class n.
- The downwind direction is within the sector denoted by 0.
- The atmospheric stability class is c.
The value of fv,elev(n, 0,c) is based on hourly average wind data at a height representative of the vent release point. Where the measurement height differed considerably from the release height, wind speed data for the release height was obtained by extrapolation. The value of fv,gnd(n, 0,c) is based on hourly average wind data obtained at a height representative of a ground level release point. This is taken as about 10 meters. The sum of these two JFDs is normalized to 1:
- t{ fv,elev(n, 0,c) + fv,gnd(n, 0,c) } =1 (B-27)
The summation is over all wind speed classes n, all compass direction sectors 0, and all stability classes c. The prescription of Regulatory Guide 1.111 is used in determining the fraction of time that the plume is considered elevated and the fraction of time that it is considered ground level. The fractions are obtained from the ratio of stack exit velocity W 0 to hourly average wind speed u at the height of the vent release point as follows:
*If W 0 /u > 5, then the plume is considered elevated for the hour.
*If W 0 /u ~ 1, then the plume is considered ground level for the hour.
*If 1 < W 0 /u ~ 5, the plume is considered to be a ground level release for a fraction Gt of the hour and an elevated release for a fraction (1 - Gt) of the hour where Gt is defined as follows:
Gt= 2.58 -1.58(W0 /u) for 1.0 < W 0 /u ~ 1.5 (B-28) Gt= 0.30 - 0.06(W0 /u) for 1.5 < W 0 /u ~ 5.0 (B-29) B.1.3 Average Wind Speed Using the joint frequency distribution, average wind speeds are obtained for Zion Station. Values are obtained for each downwind direction (N, NNE, etc.) and for various release point classifications (stack, vent, and ground level). B.1.3.1 Stack Release For a stack release, the following formula is used: u5 (0) = :t{ f5 (n; 0,c)un }/ :t{ f5 (n, 0,c)} (B-30) where th.e summations are over wind speed classes n and stability classes c. u5 (0) Average Wind Speed, Stack Release [m/sec] Page 133 of 267
Revision 5 Aug 31, 2015 The average wind speed in downwind direction 0 for a stack release. Un Wind Speed for Class n [m/sec] A wind speed representative of wind speed class n. For each wind speed class except the highest, Un is the average of the upper and lower limits of the wind speed range for the class. For the highest wind speed class, Un is the lower limit of the wind speed range for the class. The parameter fs is defined in Section 8.1.2.2. B.1.3.2 Ground Level Release For a ground level release, the following formula is used: ug(0) =~{ fg(n, 0,c)un }/ ~{ fg(n, 0,c)} (B-31) where the summations are over wind speed classes n and stability classes c. ug(0) Average Wind Speed, Ground Level Release [m/sec] The average wind speed in downwind direction 0 for a ground level release. The parameter fg is defined in Section 8.1.2.3. B.1.3.3 Vent Release For a vent release, the following formula is used: uy(0) =~ {[fv,elev(n, 0,c) + fv,gnd(n, 0,c)]un } (B-32) I~{ fv,elev(n,0,c) + fv,gnd(n,0,c) } where the summations are over wind speed classes n and stability classes c. uy(0) Average Wind Speed, Vent [m/sec] Release The average wind speed in downwind direction 0 for a vent release. The parameters fv,elev and fv,gnd are defined in Section 8.1.2.4. B.2 GAUSSIAN PLUME MODELS As a plume of airborne effluents moves away from an elevated release point, the plume both broadens and meanders. It has been found that the time-averaged distribution of material in an effluent plume can be well represented mathematically by a Gaussian function. Page 134 of 267
Revision 5 Aug 31, 2015 8.2.1 Mathematical Representation In a widely used form of the Gaussian plume model, the distribution of radioactivity in a plume is represented mathematically by the equation below: X(X,y,z) =[Q/(21t cry O'zU)]exp(-y2/2cr2y) X {exp[-(z-he)2/2cr2z] + exp[-(z+he)2/2cr2z]} (B-33) x(x,y,z) Radioactivity Concentration [µCi/m 3] The concentration of radioactivity at point (x,y,z). The x, y, and z axis are defined as follows: x Downwind Distance [m] Distance from the stack along an axis parallel to the wind direction. y Crosswind Distance [m] Distance from the plume centerline along an axis parallel to the crosswind direction. z Vertical Distance [m] Distance from the ground (grade level at the stack) along an axis parallel to the vertical direction. Q Release Rate [µCi/sec] Release rate of radioactivity. cry, crz Horizontal and Vertical Dispersion Coefficients [m] Standard deviations of the Gaussian distributions describing the plume cross-sections in they and z directions, respectively. The values of cry and crz depend on several parameters:
- Downwind distance x.
Because a plume broadens and meanders as it travels away from its release point, the values of cry and crz increase as x increases.
- Atmospheric stability class.
The plume is broadest for extremely unstable atmospheric conditions (Class A) and narrowest for extremely stable conditions (Class G).
- Time period of averaging plume concentration.
The values of cry and crz increase as the averaging period increases. u Average Wind Speed [m/sec] The average wind speed. The average speed of travel of the plume in the x direction. Page 135 of 267
Revision 5 Aug 31, 2015 he Effective Release Height [m] The effective height of effluent release above grade elevation. This may be greater than the actual release height (see Section B.3.1.1.1 ). The two exponential functions of z in the curly brackets of Equation B-9 represent the emitted and reflected components of the plume. The reflected component (represented by the exponential with (z + he) in its argument) arises from the assumption that all material in a portion of the plume that touches ground is reflected upward. This assumption is conservative if one is calculating airborne radioactivity concentration. 8.2.2 Sector-Averaged Concentration Sometimes, it is desired to determine the average concentration of radioactivity in a sector due to release at a constant rate over an extended period of time (e.g., a year). For such a case, it is reasonable to assume that the wind blows with equal likelihood toward all directions within the sector. From Equation B-9, the following equation for ground level radioactivity concentration can be derived: Xsector =[2.032 f Q/(o-z u x)]exp(-h2e/2o-2z) (B-34) XsectorSector-Averaged Ground Level [µCi/m3] Concentration The time-averaged concentration of airborne radioactivity in a sector at ground level at a distance x from the release point. 2.032 A dimensionless constant. f Sector Fraction The fraction of time that the wind blows into the sector. Q Release rate of radioactivity. [µCi/sec] The other parameter definitions are the same as for Equation B-9. Page 136 of 267
Revision 5 Aug 31, 2015 8.3 RELATIVE CONCENTRATION FACTOR xtQ The relative concentration factor xtQ (called "chi over Q") provides a simplified method of calculating the radioactivity concentration at a given point in an effluent plume when the release rate is known: x =Q <xtQ) (8-35) x Concentration of Radioactivity [µCi/m3] Concentration of radioactivity at point (x,y,z) in the atmosphere. Q Release Rate [µCi/sec] Release rate of radioactivity. xtQ Relative Concentration Factor Relative concentration factor for point (x,y,z). The airborne radioactivity concentration at (x,y,z) per unit release rate. Expressions for x!Q based on Gaussian plume models can be obtained from the equations for x concentration in Section B.2 simply by dividing both sides of each equation by the release rate Q. For example, from Equation B-10, we obtain the following expression for the sector-averaged x/Q: (XsectorfQ) =[2.032 f/(crz u x)]exp(-h2e/2a2z) (8-36) The values of x!Q used in ODCM calculations are both sector-averaged and time-averaged. The time averaging is based on the historical average atmospheric conditions of a specified multi-year time period (see Section 4.1.5) and is accomplished by use of the joint frequency distribution discussed in Section B.1.2. The formulas used to obtain the time- and sector-averaged xtQ are based on Equation B-12, but vary depending on whether the release is a stack, ground level, or vent release. The three cases are discussed below. 8.3.1 Stack Release For a stack release, the relative concentration factor is designated (x/Q)5 . Its value is obtained by the following formula: (x/Q)5 =(2.032/R) l:{ f 5 (n,0,c) x [exp (-h2e/2a2z)]/(un crz)} (8-37) The summation is over wind speed classes n and atmospheric stability classes c. (x/Q) 5 Relative Concentration Factor, Stack Release The time- and sector-averaged relative concentration factor due to a stack release for a point at ground level at distance R in downwind direction e. Page 137 of 267
Revision5 Aug 31, 2015 2.032 Constant A dimensionless constant. R Downwind Distance [m] The downwind distance from the release point to the point of interest. f 5 (n,0,c) Joint Frequency Distribution, Stack Release This function is defined in Section B.1.2.2. he Effective Release Height [m] The effective height of an effluent release above grade elevation. For a stack release, he is obtained by correcting the actual height of the release point for plume rise, terrain effects, and downwash as described in Section B.3.1.1, below. O"z Standard Vertical Dispersion Coefficient [m] A coefficient characterizing vertical plume spread in the Gaussian model for stability class cat distance R (see Table C-5 of Appendix C). Un Wind Speed [m/sec] A wind speed representative of wind speed class n. For each wind speed class except the highest, un is the average of the upper and lower limits of the wind
. speed range for the class. For the highest wind speed class, Un is the lower limit of the wind speed range for the class.
This expression is recommended by the NRC in Regulatory Guide 1.111 (Reference 7) and is based on a model designated there as the "constantmean wind direction model." In this model it is assumed that the mean wind speed, the mean wind direction, and the atmospheric stability class determined at the release point also apply at all points within the region in which airborne concentration is being evaluated. B.3.1.1 Effective Release Height For a stack release, the effective height of an effluent plume is the height of the release point corrected for plume rise and terrain effects: If (hs + hpr- ht)< 100 meters, then
- he =hs + hpr - ht (B-38)
If (hs + hpr - ht)~ 100 meters, then; he =100 meters (B-39) he Effective Release Height [m] The effective height of an effluent release above grade elevation. hs Actual Release Height [m] The actual height of the release above grade elevation. Page 138 of 267
Revision 5 Aug 31, 2015 Plume Rise [m] The rise of the plume due to its momentum and buoyancy. (See Section B.3.1.1.1.) ht Terrain Correction Parameter [m] A parameter to account for the effect of terrain elevation on the effective height of a plume. Taken as zero (see Section B.3.1.1.2}. B.3.1.1.1 Plume Rise Because nuclear power stations generally have plumes that are not significantly warmer than room temperature, plume rise due to buoyancy is neglected. The formulas used to calculate plume rise due to momentum are given below. Stability Classes A, B, C, and D For these stability classes (corresponding to unstable and neutral conditions), hpr is taken as the lesser of two quantities: hpr =Minimum of [(hpr)1. (hpr)2] (B-40) (hpr)1 =(1.44)(W0 /u)2/3(Rfd)1/3(d) - hd (B-41) (hpr)2 =(3)(W 0 /u)(d) (B-42) W0 Stack Exit Velocity [m/sec] The effluent stream velocity at the discharge point. uWind Speed [m/sec] R Downwind Distance [m] The downwind distance from the release point to the point of interest. d Internal Stack Diameter [m] The internal diameter of the stack from which the effluent is released. Downwash. Correction [m] A parameter to account for downwash at low exit velocities. The parameter hd is calculated by the following equations: hd =(3)(1.5 - W 0 /u)(d) if W 0 <1.5u (B-43) hd =Oif W0==.1.~u (B-44) Note that (hprh can increase without limit as R increases; thus, the effect of (hpr)2 is to limit calculated plume rise at large distances from the nuclear power station. Stability Classes E, F, and G Page 139 of 267
Revision 5 Aug 31,2015 For these stability classes (corresponding to stable conditions), hpr is taken as the minimum of four quantities: (B-45) (hpr)a =(4)(F/S)1/4 (B-46) (hpr) 4 =(1.5)(F/u)1/3(st116 (8~47) F Momentum Flux Parameter [m4/sec2] A parameter defined as: F =W0 2(d/2)2 (B-48) S Stability Par~meter [1/sec2] A parameter defined as follows: Stability Class s E 8.?0E-4 F 1.75E-3 G 2.45E-3 The quantities (hpr)1 and (hpr)2 are as defined by Equations B-17 and B-18. B.3.1.1.2 Terrain Effects Due to general flatness of the terrain in the vicinity of the Zion site, the terrain correction parameter ht was taken as zero in all calculations of meteorological dispersion and dose parameters for this Manual. B.3.2 Ground Level Release For a ground level release, the relative concentration factor is designated (x/Q)9 . Its value is obtained by the following formula: (x/Q)g = (2.032/R) :E{ f g(n,0,c)/(unSz) } (B-49) The summation is over wind speed classes n and atmospheric stability classes c. (x/Q)g Relative Concentration Factor, Ground Level Release The time- and sector-averaged relative concentration factor due to a ground level release for a point at ground level at distance R in downwind direction 0. fg(n,0,c) Joint Frequency Distribution, Ground Level Release This function is defined in Section B.1.2.3. Page 140 of 267
Revision 5 Aug 31, 2015 Sz Wake-Corrected Vertical Dispersion Coefficient [m] The vertical dispersion coefficient corrected for building wake effects. The correction is made as described below. The remaining parameters are defined in Section 8.3.1. Wake-Corrected Vertical Dispersion Coefficient The wake-corrected vertical dispersion coefficient Sz in Equation 8-25 is taken as the lesser of two quantities: (B-50) (B-51)
=(o-z)(3112) (B-52)
Wake-Corrected Vertical Dispersion Coefficient [m] The vertical dispersion coefficient corrected for building wake effects. O"z Standard Vertical Dispersion Coefficient [m] The coefficient characterizing vertical plume spread in the Gaussian model for stability class cat distance R (see Table C-5 of Appendix C). D Maximum Height of Neighboring Structure [m] The maximum height of any neighboring structure causing building wake effects (see Table F-2 of Appendix F). B.3.3 Vent Release For a vent release, the relative concentration factor is designated (x/Q)v. Its value is obtained by the following formula: (x/Q)v =(2.032/R) I:{ f v,elev(n,9,c) (B-53) 2 2 x [exp(-h el2cr z}]l(un O"z)
+ fv,gnd(n,9,c)/(unSz) }
The summation is over wind speed classes n and atmospheric stability classes c. (x/Q)v Relative Concentration [sec/m3] Factor, Vent Release The time and sector averaged relative concentration factor due to a vent release for a point at ground level at distance R in downwind direction 9. The parameters fv,elev(n,9,c) and fv,gnd(n,9,c) are defined in Section 8.1.2.4. The parameter Sz is defined in Section 8.3.2. The remaining parameters are defined in Section 8.3.1. Page 141 of 267
Revision 5 Aug 31, 2015 B.3.4 Removal Mechanisms In Regulatory Guide 1.111, the NRC allows various removal mechanisms to be considered in evaluating the radiological impact of airborne effluents. These include radioactive decay, dry deposition, wet deposition, and deposition over water. For simplicity, these removal mechanisms cited by the NRC are not accounted for in the evaluation or use of x!Q in this manual. This represents a conservative approximation as ignoring removal mechanisms increases the value of x!Q. B.3.5 Gamma-x/Q The noble gas dose factors of Reg. Guide 1.109, Table B-1 are based upon assumption of immersion in a semi-infinite cloud. For ground level and mixed mode releases this tends to overestimate the gamma air dose arising from a plume that is actually finite in nature. For elevated releases, the Reg. Guide 1.109 noble gas dose factors will underestimate exposure as they consider only immersion and not that portion of exposure arising from sky shine. At distances close iri to the point of elevated release, the ground level concentration as predicted by x!Q will be essentially zero. In such a case, the sky shine component of the exposure becomes significant and must be considered. The gamma-x/Q provides a simplified method of calculating gamma air dose and dose rates for a finite and/or elevated plume. The methodology of Reg. Guide 1.109, Section C.2 and Appendix B provides the methodology for calculating finite cloud gamma air dose factors from which the gamma-x/Q values can be derived. Section B.5 addresses the calculation of these dose factors. The gamma-x/Q is defined such that for a given finite cloud the semi-infinite cloud methodology will yield the same gamma air dose as the finite cloud methodology. Three gamma-x/Q values are defined: (x/Q)/, (x/Q)} and (x/Q)9r for stack, vent and ground level releases, respectively. These gamma-x/Q values are calculated as follows: For stack releases: (B-54) The summation is over all noble gas radionuclides i. Gamma-y/Q for Stack Releases [sec/m3] Noble Gas Nuclide Fraction dimensionless Fraction of total noble gas release that is due to radionuclide i. Values for fi are listed in Table B-0. Si Stack Release Gamma Air Dose Factor [(mrad/yr)/(µCi/sec)] Gamma air dose factor for radionuclide i for stack releases as defined in Section B.5.1. Taken from Appendix F, Table 7. 3 Semi-Infinite Cloud Dose Factor [(m rad/yr)/(µCi/m )] Dose factor for immersion exposure to a semi-infinite cloud of noble gas. Taken from Reg. Guide 1.109, Table B-1, Col 4. (Note that the units in Reg. Guide 1.109 must be multiplied by 1 E6 to convert pCi to µCi.) Page 142 of 267
Revision 5 Aug 31, 2015 For vent releases: Lf;V; {x/Q)~ = :ti f.M. I I (B-55) The summation is over all noble gas radionuclides i. Gamma-y/Q for Vent Releases [sec/m3] Vent Release Gamma Air Dose Factor [( mrad/yr)/(µCi/sec )] Gamma air dose factor for radionuclide i for stack releases as defined in Section B.5.3. Taken from Appendix F, Table 7. All other terms have been previously defined. For ground level releases: (B-56) The summation is over all noble gas radionuclides i. Gamma-y/Q for Ground Releases [sec/m3] G; Ground Level Release Gamma Air Dose Factor [(mrad/yr)/(µCi/sec)] Gamma air dose factor for radionuclide i for ground level releases as defined in Section B.5.2. Taken from Appendix F, Table 7. All other terms have been previously defined. The Noble Gas Nuclide Fraction, f; is determined from historical release data and defined as: (B-57) The summation is over all noble gas radionuclides i. A; Cumulative Radionuclide Release units of activity Cumulative release of noble gas radionuclide i over a period 9f time. 8.4 RELATIVE DEPOSITION FACTOR D/Q The quantity D/Q (called "Dover Q") is defined to provide the following simple way of calculating the rate of deposition of radioactivity at a given point on the ground when the release rate is known. d =Q (D/Q) (B-58) Page 143 of 267
Revision 5 Aug 31, 2015 d Deposition Rate [(µCi/m2)/sec] Rate of deposition of radioactivity at a specified point on the ground. Q Release Rate of radioactivity. [µCi/sec] D/Q Relative Deposition Factor [1 /m2] Relative deposition factor for a specified point on the ground. The deposition rate per unit release rate. The values of D/Q used in this manual are time-averaged. The time averaging is based on the historical average atmospheric conditions of a specified multi-year time period (see Section 4.1.5) and is accomplished by use of the joint frequency distribution described in Section B.1.2. The formulas used to obtain D/Q vary depending on whether the release is a stack, ground level, or vent release. The three cases are discussed below. B.4.1 Stack Release For a stack release, the relative deposition factor is designated (D/Q)5 . Its value is obtained by the following formula: (D/Q)5 =[1/(21tR/16)] l:{f5 (n,0,c) Dr(c,R,he)} (B-59) The summation is over wind speed classes n and stability classes c. (D/Q)5 Relative Deposition Factor, Stack Release The time-averaged relative deposition factor due to a stack release for a point at distance R in the direction 0. 21t/16 Sector Width [radians] The width of a sector over which the plume direction is assumed to be uniformly distributed (as in the model of Section B.2.2). Taken as 1/16 of a circle. R Downwind Distance [m] The downwind distance from the release point to the point of interest. f 5 (n,0,c) Joint Frequency Distribution, Stack Release This function is defined in Section B.1.2.2. Relative Deposition Rate, Stack Release The deposition rate per unit downwind distance [µCi/(sec-m)] divided by the source strength [µCi/sec] due to a stack release for stability class c, downwind distance R, and effective release height he. The value is based on Figures 7 to 9 of Regulatory Guide 1.111, which apply, respectively, to release heights of 30, 60, and 100 m. Linear interpolation is used to obtain values at intermediate release heights. If the Page 144 of 267
Revision 5 Aug 31, 2015 effective release height is greater than 100 meters, then the data for 100 meters are used. he Effective Release Height [m] The effective height of the release above grade elevation. See Section .B.3.1.1. B.4.2 Ground Level Release For ground level release, the relative deposition factor is designated (D/Q) 9 . Its value is obtained by the following formula: (D/Q)9 =[1/(27tR/16)] Dr(R) l:{ f 9 (n,0,c)} (B-60) The summation is over wind speed classes n and stability classes c. (D/Q)g Relative Deposition Factor, Ground Level Release The time-averaged relative deposition factor due to a ground level release for a point at distance R in the direction 0. fg(n,0,c) Joint Frequency Distribution, Ground Level Release This function is defined in Section B.1.2.3. Dr(R) Relative Deposition Rate, Ground Level The deposition rate per unit downwind distance [µCi/(sec-m)] divided by the source strength [µCi/sec] due to a ground level release for downwind distance R. The value is taken from Figure 6 of Regulatory Guide 1.111 and is the same for all atmospheric stability classes. The remaining parameters are defined in Section B.4.1. B.4.3 Vent Release For a vent release, the relative deposition factor is designated (D/Q)v. Its value is obtained by the following formula: (D/Q)v =[1/(21tR/16)] x [:E{ fv,elev(n,0,c) Dr(c,R,he)} + Dr(R) l:{ fv,gnd(n,0,c) }] (B-61) The summation is over wind speed classes n and stability classes c. (D/Q)v Relative Deposition Factor, Vent Release The time-averaged relative deposition factor due to a ground level release for a point at distance R in the direction 0. The parameters fv,elev(n,0,c) and fv,gnd(n,0,c) are defined in Section B.1.2.4. The remaining parameters are defined in Sections B.4.1 and B.4.2. Page 145 of 267
Revision 5 Aug 31, 2015 B.5 GAMMA AIR DOSE FACTORS (Sj, Vi, Gj) The gamma air dose factors provide a simple way of calculating doses and dose rates to air due to gamma radiation. For example, using a dose factor DFj, gamma air dose rate may be calculated as follows: (B-62) (B-63) The summations are over i radionuclides. D Gamma Air Dose Rate [mrad/yr] The gamma air dose rate due to all radionuclides released. Di Gamma Air Dose Rate Due to Radionuclide i [mrad/yr] Qi Release Rate of Radionuclide i [µCi/sec] DFi Gamma Air Dose Factor for [(mrad/yr)/ (µCi/sec)] Radionuclide i A factor used to calculate gamma air dose or dose rate due to release of radionuclide i. Gamma air dose rate at a particular location per unit release rate. Three gamma air dose factors are defined: Sh Vh and Gi. They are used for stack, vent, and ground level releases, respectively. These three release point classifications are defined in Section 4.1.4. The calculation of the three dose factors is discussed below. B.5.1 Stack Release For a stack release, the gamma air dose factor Si is obtained by a model similar to that of Equation 6 of Regulatory Guide 1.109 (Reference 6). A sector-averaged Gaussian plume is assumed and the dose factor is evaluated on the basis of historical average atmospheric conditions. The value of Si depends on distance R from the release point and on downwind sector 0. The following equation is used: (B-64) The summation is over wind speed classes n, atmospheric stability classes c, and photon group indices k. Si Gamma Air Dose Factor, Stack Release [(mrad/yr)/ (µCi/sec)] The gamma air dose factor at ground level for a stack release for radionuclide i, downwind sector 0, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period. Page 146 of 267
Revision 5 Aug 31, 2015 260 Conversion factor [(mrad-radians-m3-disintegrations)/(sec-MeV-Ci)] Reconciles units of Equation B-36. 21t/16 Sector Width [radians] The width of a sector over which the plume direction is assumed to be uniformly distributed (as in the model of Section B.2.2). Taken as 1/16 of a circle. fs(n,0,c) Joint Frequency Distribution, Stack Release This function is defined in Section B.1.2.2. A.i Radiological Decay Constant [hr-1] Radiological Decay Constant for radionuclide i (see Table C-7 of Appendix C). 3600 Conversion Factor [sec/hr] The number of seconds per hour. Used to convert wind speed in meters/sec to meters/hr. Ek Photon Group Energy [MeV/photon] An energy representative of photon energy group k. The photons emitted by each radionuclide are grouped into energy groups in order to facilitate analysis. All photons with energy in energy group k are assumed to have energy Ek. µ3(Ek) Air Energy Absorption Coefficient The linear energy absorption coefficient for air for photon energy group k. The fraction of energy absorbed in air per unit of distance traveled for a beam of photons of energy Ek. Distance is measured in units of linear thickness (meters). Aki Effective Photon Yield [photons/disintegration] The effective number of photons emitted with energy in energy group k per decay of nuclide i. On the basis of Section B.1 of Regulatory Guide 1.109 (Reference 6), the parameter Aki is calculated as follows: (B-.65) The summation in the numerator is over the index m. True Photon Yield [photons per disintegration] The actual number of photons emitted with energy Em per decay of nuclide i. Em Photon Energy [MeV/photon] Page 147 of 267
Revision 5 Aug 31, 2015 1 The energy of the m h photon within photon energy group k. J.la(Em) Air Energy Absorption Coefficient The linear energy absorption coefficient for air for photon energy Em. I(... ) I Function A dimensionless parameter obtained by numerical evaluation of integrals that arise in the plume gamma dose problem. The value of I depends on the arguments (...) listed in Equation B-40. A specific definition for I is given by Equation F-13 of Regulatory Guide 1.109. The integrals involved in calculating I arise from conceptually dividing up the radioactive plume into small elements of radioactivity and adding up the doses produced at the point of interest by all of the small elements. The distribution of radioactivity in the plume is represented by a sector-averaged Gaussian plume model like that discussed in Section B.2.2. The parameters R, he. Un, and O'z are defined in Section B.3.1. B.5.2 Ground Level Release The gamma air dose factor Gi for a ground level release is defined as follows: Gi Gamma Air Dose Factor, Ground Level Release [(mrad/yr)/(µCi/sec)] The gamma air dose factor at ground level for a ground level release for radionuclide i, downwind sector e, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period. The value of Gi is obtained by the same equation as used for a stack release, Equation B-36 of Section B.5.1, with the following modifications:
- The joint frequency distribution for a ground level release (f9 of Section B.1.2.3) is used in place of the one for a stack release (f5 ).
- In evaluating the I function, the effective release height he is taken as zero.
This corresponds to use of a finite plume model. B.5.3 Vent Release For a vent release, the gamma air dose factor is calculated as follows: Vj =[260/(21tR/16)] X l:{fv,elev(n,9,c)[exp(-A.iR/3600un)] X Ak1EkJ.1a(Ek) l(he,Un,C,O'z,Ek)/un (B-66)
+ fv,gnd(n,9,c)[exp(-A.iR/3600un)] X AkiEkJ.la(Ek) 1(0,UmC,O'z,Ek)/un}
The summation is over wind speed classes n, atmospheric stability classes c, and photon group indices k. Vi Gamma Air Dose Factor, Vent Release [( mrad/yr)/(µCi/sec )] Page 148 of 267
Revision 5 Aug 31, 2015 The gamma air dose factor at ground level for a vent release for radionuclide i, downwind sector 0, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period. The parameters fv,elev(n,0,c) and fv,gnd(n,0,c) are defined in Section 8.1.2.4. The parameter O"z is defined in Section 8.3.2. The remaining parameters are discussed in Section 8.5.1. 8.6 Gamma Total Body Dose Conversion Factor (Ki) . The gamma total body dose conversion factors (Ki) are used to calculate doses and dose rates due to gamma irradiation of the whole body. The gamma total body dose conversion factors are taken from Reg. Guide 1.109, Table 8-1, Column 5. The gamma total body dose conversion factors in Table 8-1 of Reg. Guide 1.109 are based upon the semi-infinite cloud model. B.7 BETAAIRAND BETA SKIN DOSE CONVERSION FACTORS (Nj,Lj) The beta air (Nj) and beta skin (Lj) dose conversion factors are used to calculate doses and dose rates due to noble gas beta exposure. The beta air dose conversion factors are taken from Reg, Guide 1.109, Table 8-1, Column 2. The beta skin dose conversion factors are taken from Column 5 of that same table. The values are based on a semi-infinite cloud model. B.8 GROUND PLANE DOSE CONVERSION FACTOR DFGi The ground plane dose conversion factor DFGi is used to calculate dose due to standing on ground contaminated with radionuclide i (see Equation A-8 of Appendix A). The units of DFGi are (mrem/hr) per 2 (pCi/m ). Values are provided (see Table C-10 of Appendix C) for dose to the whole body. The values are taken from Regulatory Guide 1.109 and are based on a model that assumes a uniformly contaminated ground plane. B.9 INHALATION DOSE COMMITMENT FACTOR DFAiia The inhalation_dose commitment factor DFAiia is used to calculate dose and dose rate to organ j of an individual of age group a due to inhalation of radionuclide i (see Equations A-7 and A-9 of Appendix A). Values of DFAiia for 10CFR50 compliance are taken from Regulatory Guide 1.109 (Reference 6). The units of DFAija-are mrem per pCi inhaled. Values are provided for seven organs, with the whole body considered as an organ (see Tables E-7, E-8, E-9 and E-10 in Reg. Guide 1.109). B.10 INGESTION DOSE COMMITMENT FACTOR DFLiia The ingestion dose commitment factor DFLiia is used to calculate dose to organ j of an individual of age group a due to ingestion of radionuclide i (see Equations A-7 and A10 through A20 of Appendix A). Values of DFLiia for 10CFR50 compliance are taken from Regulatory Guide 1.109 (Reference 6). The units of DFLiia:are mrem per pCi ingested. In Tables E-11, E-12, E-13 and E-14 of Reg. Guide 1.109, values are provided for seven organs, with the whole body considered as an organ. B.11 MEASURED RELEASE PARAMETERS Input parameters required for calculations of dose or dose rate due to airborne effluents include measured values of radioactivity release (A15 , Aiv* and Ai 9 ) or release rate (Qis* Qiv. and Qi9 ) (see Section A.1 of Appendix A). These are obtained per Zion station procedures. Page 149 of 267
Revision 5 Aug 31, 2015 B.12 RADIOLOGICAL DECAY CONSTANTS Values used for these are obtained from the literature and are specified in Table C-7 of Appendix C. B.13 PRODUCTION/EXPOSURE PARAMETERS These parameters characterize various aspects of agricultural production and human exposure. Values used for generic (site-independent) parameters are specified in Appendix C. Values of site-specific parameters are given in Appendix F. Many of the values are based on Reg. Guide 1.109, while others are based on site-specific considerations. Page 150 of 267
Revision 5 Aug 31, 2015 SECTION 2: MODELS AND PARAMETERS FOR LIQUID EFFLUENT CALCULATIONS B.14 INTRODUCTION Equations for radiation dose and radioactivity concentration due to liquid effluents are given in Section A.2 of Appendix A. The equations involve the following types of parameters:
- Flow and Dilution Parameters.
- Dose Factors.
- Measured Release Parameters.
- Transport/Consumption Parameters.
This section discusses the methodology used to determine these parameters. Section 8.15 addresses dose calculations and Section B.16 addresses concentration calculations for tank discharges. For dose calculations, flow and dilution parameters are discussed for the Lake Michigan Model, which is used for Zion. B.15 DOSE B.15.1 Drinking Water The radiation dose due to consumption of drinking water containing released radioactivity is calculated by Equations A-17, A-18 and A-19 of Appendix A: D~;q = F At LLAaipjci (A-17) p i F= Waste Flow (A-18) Dilution Flow x Z (A-19) The summation is over index i (radionuclides) and p (pathways). The parameters are defined in Section A.2.1 of Appendix A. This methodology addresses the following considerations:
- The duration of the release, Lit.
- The concentration of the activity released, Cj.
- The dilution that takes place in the environment is represented by the parameters F and Z.
- Receptor consumption rate, Uaw*
- Dilution which occurs from the near field discharge area to potable water intake as represented by Dw .
- The dose commitment per unit of ingested radioactivity is DFLaii*
B.15.2 Aquatic Foods (Fish) Near Zion station, the only aquatic food of significance for human consumption is fish. The liquid dose due to consumption of fish containing released radioactivity is calculated by Equations A-17, A-18 and A-20 of Appendix A. (A-20) Page 151 of 267
Revision 5 Aug 31, 2015 The parameters are defined in Section A.2.1 of Appendix A. This is similar to the methodolgy used for calculating the dose due to drinking water except for the addition of the bioaccumulation factor, BF1* This factor is the equilibrium ratio of the concentration of radionuclide i in fish (pCi/kg) to its concentration in water (pCi/L). It accounts for the fact that radioactivity ingested by fish can accumulate in their bodies to a higher concentration than in the waters in which the fish live. B.15.3 Parameters B.15.3.1 Flow and Dilution The values of dilution can differ for potable water and fish. The dilution for potable water will depends on where water is drawn, while that for fish will depends on where the fish are caught. Models used to determine these parameters are discussed below. The values used for Zion Station are summarized in Table F-1 of Appendix F. B.15.3.1.1 Lake Michigan Model Only (Zion) discharges liquid effluents into Lake Michigan. For Zion station, it is assumed that the dilution in the near-field (Z) is dictated by the initial entrainment dilution is a factor of 10. The potable water pathway dilution factor of 6 (Ow) is derived from the plume dilution (a factor of 3 over approximately 1 mile) and the current direction frequency (annual average factor of 2). B.15.3.2 Dose Factors Equations A-17 through A-20 of Appendix A determine dose due to ingested radioactivity using the same ingestion dose factor DFLija as used in the evaluation of airborne radioactivity which is ingested with foods. The units of DFLija are: (mrem) per (pCi ingested) For 10CFR50 Appendix I compliance, the data of Tables E-1, E-12, E-13 and E-14 of Reg. Guide 1.109, are used for four age groups and for seven organs, with the whole body considered as an organ. B.15.3.3 Measured Releases Calculations of dose due to liquid effluents require measured values of radioactivity concentration release (C 1) for input. These release values are obtained per ZionSo/utions' procedures. B.15.3.4 Consumption Equations A-19 and A-20 of Appendix A involve consumption rates for water and fish (Uaw and U/). The values used are specified for Zion Station in Table F-1 of Appendix F. B.16 CONCENTRATION IN TANK DISCHARGES The concentration of radioactivity in a release to the unrestricted area due to a tank discharge is calculated by Equation A-22 of Appendix A: C = C~ Waste Flow (A-22) 1
' Dilution Flow Page 152 of 267
Revision 5 Aug 31, 2015 The parameters are defined in Section A.2.3 of Appendix A. The radioactivity concentration released from the tank (cti at flow rate Fr) is diluted by mixing with the initial dilution stream (with flow rate Fd) to yield a lower concentration (Ci ) in the combined streams. Table B-0 Noble Gas Nuclide Fractions 1 Nuclide Zion Ar-41 O.OOE+OO Kr-83m 0.00E+OO Kr-85 1.00E+OO Kr-85m O.OOE+OO Kr-87 O.OOE+OO Kr-88 O.OOE+OO Kr-89 O.OOE+OO Kr-90 O.OOE+OO Xe-131m O.OOE+OO Xe-133 0.00E+OO Xe-133m O.OOE+OO Xe-135 O.OOE+OO Xe-135m O.OOE+OO Xe-137 O.OOE+OO Xe-138 O.OOE+OO Notes: (1) From Table 10-1. Page 153 of 267
Revision 5 Aug 31, 2015 Table B-1 Portion of an Example Joint Frequency Distribution S~ry Tabl* af P*rc8"t by Direction and Cl*** C1Bllll N NNE NE ENE E ESE 5£ SSE s A .289 .317 .301 .244 .249 .UK>
- tH .un .33&
B
- t90 .t87 *.t78
- tfi8
- t2!5 .065 .079 .t30 .t93 c .269 .226 .262 .218 .190
- t18 .162 .189 .302 D 3.298 2.327 2.338 2.684 1.192 1.334 t.365 2. t72 3.0t2 E t.466 t.198 .988 t.331 '. 86 f t.226 1.472 2.!553 3.G:?I F .!504 .318 .fBS .276 .6911 .848 *.103 1 .293 1. 7~2 G .202 .091 .061 .099 .2fi3 .2!50 .35!5 .400 .624 Total 6.217 4.663 4.304 &.Ott &.169 3.830 4.424 6.933 9.126 SU11111U1ry Tab1* of Percent by Dtr9CUon and Speed Speed N NNE NE ENE E ESE SE SSE s
.45 .098 .099 .078 -030 .009 .000 .Ot4 .032 .048 1.05 .308 .154 .125 .137 .121 .093 .090 .090 .t27 2.05 .939 -~02 .458 .594 .1143 .IO& .!598 .605 t.0011 3.05 1.164 1.030 .779 .981 t.468 t.075 t.093 t.4"18 t.982 4.05 1. t79 t .024 .178 .995 t. 243 .a3t 1.027 t. 727 2. tto !5.05 .839 .631 .858 .798 .724 .474 .152 1.2fi4 t.636 8.05 .612 .467 .496 .1589 .417 .313 .411 .803 1.1!53 B.05 .7155 .437 .812 .695 .3*10 .313 .405 .735 1.319 10.05 .253 .157 ** 183 .165 .032 .093 .103 .tao .374 13.0S .053 .061 .034 .021 .001 .031 .025 .028 .072 '8.00 .016 .001 .004 .ooo .ooo .oot .001 .002 .000 99.00 .ooo .000 .000 .ooo .OOQ .000 .000 .000 .ooo lot:al 6.217 4.&63 4.304 a.011 !5. 169 3.830 4.424 1.933 9.82&
Su_..ry Tabla of P*rcent by ~ and C\aaa Class A B c D E F G Speed
. .cs .O<M .()()1 .000 _095 .2!57 .275 .346 1.05 .018 .012 .027 .508 1.035 1.080 .780 2.05 .286 .171 .246 3.256 15.028 3.228 1.419 3.05 .7"44 .428 .816 6.2'58 7. 173 3.*272 .985 4.05 .992 . !581
- 781 8. 165 6.404 1.902 .400 15.05 .909 .W6 .908 7.302 4.357 .807 .077 6.05 .712 .388 .613 6. 167 2.938 .16.C .013 8.05 .819 .!500 .75!5 7.616 2.734 .081 .011 10.05 .230 . 1!50 .196 2.606 .867 .009 .000 13.05 .07!5 .032 .ass
- 7&!5
- 1111 .001 .000 ULOO .004 .000 .OUl
- 117 .012 .000 .000 99.00 .000 .000 .001 .001 .000 .000 .oo6 Page 154 of 267
Revision 5 Aug 31, 2015 Figure 8-1 Instantaneous View of Plume y Wind This figure represents a snapshot of a projection of a plume on the horizontal plane. As it moves downwind, the plume meanders about the average wind direction and broadens (adapted from Reference 18). Page 155 of 267
Revision 5 Aug 31, 2015 Figure 8*2 A Gaussian Curve 1.0 0.1 0.1 a.T 0.1 y *a * .;:;- 0.5 o.* G.3 o.z 0.1 O.D
-2 _, 0 .,
-s-T CJ (Adapted from Reference 24 of Chapter 9, Page 61.)
Page 156 of 267
Revision 5 Aug 31, 2015 Figure B-3 Effect of Observation Period on Plume Shape
*U.&Tlvl CO,.CtNU&Tle>>I This sketch represents the approximate outlines of a smoke plume observed instataneously and averaged over periods of 10 minutes and 2 hours. The diagram on the right shows the corresponding cross plume distribution patterns. The plume width increases as the period of observation increases (from Reference 18).
Page 157 of 267
Revision 5 Aug 31, 2015 Figure 8-4 A Gaussian Plume I x (x,-y,Z) This sketch illsutrates a plume characterized by Equation B-9. The plume is moving downwind in the x direction. Both the horizontal dispersion parameter sz increases as x increases. The reflected component has been omitted in this illustration (adapted from Reference 24). Page 158 of 267
Revision 5 Aug 31, 2015 APPENDIX C GENERIC DATA Page 159 of 267
Revision 5 Aug 31, 2015 APPENDIXC GENERIC DATA C.1 INTRODUCTION This appendix contains generic offsite dose calculation parameter factors, or values. Site specific factors are provided in the station annex Appendix F. The factors described in section C.2 are found in the prescribed references and are not repeated in this appendix. C.2 10CFR50 DOSE COMMITMENT FACTORS With the exception of H-3, the dose commitment factors for 10CFR50 related calculations are exactly those provided in Regulatory Guide 1.109 (Reference 6). The following table lists the parameters and the corresponding data tables in the RG 1.109: PATHWAY ADULT TEENAGER CHILD INFANT Inhalation RG 1.109:Table E-7 RG 1.109:Table E-8 RG 1.109:Table E-9 RG 1.109:Table E-10 Ingestion RG 1.109:Table E-11 RG 1.109:Table E-12 RG 1.109:Table E-13 RG 1.109:Table E-14 These tables are contained in Regulatory Guide 1.109 (Reference 6). Each table (E-7 through E-14) provides dose factors for seven organs for each of 73 radionuclides. For radionuclides not found in these tables, dose factors will be derived from ICRP 2 (Reference 50) or NUREG-0172 (Reference 51 ). The values for H-3 are taken from NUREG-4013 (Reference 107). Page 160 of 267
Revision 5 Aug 31, 2015 Table C-1 Miscellaneous Dose Assessment Factors - Environmental Parameters Parameter Value Comment Equation Basis a fn 0.76 A-10, A-11 A fl 1.0 A-10, A-11 A fo 1.0 A-12, A-14 A fs 1.0 A-12, A-14 A tb 262,800 hrs 30 years A-8 c tf 48 hrs Cow Milk Pathway A-12 A tf 480 hrs Cow Meat Pathway A-14 A th 1440 hrs 60 days for produce A-10 A th 2160 hrs 90 days for produce A-12, A-14 A tl 24 hrs 1 day for leafy veQetables A-10 A QF 50 Kg/da A-12, A-13, A-14, A-15 B r 0.2 For Particulates A-10, A-12, A-14 A Yo 0.7 Kg/m" A-12, A-14 A Ys 2.0 KQ/m" A-12, A-14 A Yv 2.0 Kg/m" A-10 A
'Aw 0.0021 h(' A-10, A-12, A-14 A H 8 gm/m;j Absolute Atmospheric Humidity A-11, A-13, A-15 D 8
8asis key: A: Reference 6, Table E-15. B: Reference 6, Table E-3. C: The parameter tb is taken as the midpoint of plant operating life {based upon an assumed 60 year plant operating lifetime). D: Reference 14, Section 5.3.1.3. Page 161 of 267
Revision 5 Aug 31, 2015 Table C-2 Miscellaneous Dose Assessment Factors - Consumption Parameters Type Variable Infant Child Teenager Adult BRa 1400 3700 8000 8000 Air (m3/yr) Milk Uam 330 330 400 310 (L/yr) Produce Ua~ 0 520 630 520 (Kg/yr) Leafy UaL 0 26 42 64 Vegetables (Kg/yr) Meat Uat 0 41 65 110 (Kg/yr) Water Uavv 330 510 510 730 (L/yr) Fish Uar 0 6.9 16 21 (Kg/yr) From Regulatory Guide 1.109, Table E-5. Page 162 of 267
Revision 5 Aug 31, 2015 Table C-3 Stable Element Transfer Data Ft FM( Cow) Element Meat (d/kg) Milk (d/L) Reference H 1.2E-02 1.0E-02 6 Be 1.5E-03 3.2E-03 Footnote 1 c 3.1 E-02 1.2E-02 6 F 2.9E-03 1.4E-02 Footnote 2 Na 3.0E-02 4.0E-02 6 Mg 1.5E-03 3.2E-03 Footnote 1 Al 1.5E-02 1.3E-03 Footnote 3 p 4.6E-02 2.5E-02 6 Cl 2.9E-03 1.4E-02 Footnote 2 Ar NA NA NA K 1.8E-02 7.2E-03 16 Ca 1.6E-03 1.1E-02 16 Sc 2.4E-03 7.5E-06 Footnote 4 Ti 3.4E-02 5.0E-06 Footnote 5 v 2.8E-01 1.3E-03 Footnote 6 Cr 2.4E-03 2.2E-03 6 Mn 8.0E-04 2.5E-04 6 Fe 4.0E-02 1.2E-03 6 Co 1.3E-02 1.0E-03 6 Ni 5.3E-02 6.7E-03 6 Cu 8.0E-03 1.4E-02 6 Zn 3.0E-02 3.9E-02 6 Ga 1.5E-02 1.3E-03 Footnote 3 Ge 9.1 E-04 9.9E-05 Footnote 7 As 1.7E-02 5.0E-04 Footnote 8 Se 7.7E-02 1.0E-03 Footnote 9 Br 2.9E-03 2.2E-02 Ft Footnote 2;FM from Ref. 16 Kr NA NA NA Rb 3.1 E-02 3.0E-02 6 Sr 6.0E-04 8.0E-04 6 y 4.6E-03 1.0E-05 6 Zr 3.4E-02 5.0E-06 6 Nb 2.8E-01 2.5E-03 6 Mo 8.0E-03 7.5E-03 6 Tc 4.0E-01 2.5E-02 6 Ru 4.0E-01 1.0E-06 6 Rh 1.5E-03 1.0E-02 6 Pd 5.3E-02 6.7E-03 Footnote 10 Cd 3.0E-02 2.0E-02 Footnote 11 In 1.5E-02 1.3E-03 Footnote 3 Sn 9.1 E-04 9.9E-05 Footnote 7 Sb 5.0E-03 2.0E-05 98 Ag 1.7E-02 5.0E-02 6 Te 7.7E-02 1.0E-03 6 I 2.9E-03 6.0E-03 6 Xe NA NA NA Cs 4.0E-03 1.2E-02 6 Ba 3.2E-03 4.0E-04 6 La 2.0E-04 5.0E-06 6 Ce 1.2E-03 1.0E-04 6 Pr 4.7E-03 5.0E-06 6 Nd 3.3E-03 5.0E-06 6 Page 163 of 267
Revision 5 Aug 31, 2015 Table C-3 (Cont'd) Stable Element Transfer Data Ft FM (Cow) Element Meat (d/kg) Milk (d/L) Reference Pm 2.9E-04 2.0E-05 16 Sm 2.9E-04 2.0E-05 16 Eu 2.9E-04 2.0E-05 16 Gd 2.9E-04 2.0E-05 16 Dy 2.9E-04 2.0E-05 16 Er 2.9E-04 2.0E-05 16 Tm 2.9E-04 2.0E-05 16 Yb 2.9E-04 2.0E-05 16 Lu 2.9E-04 2.0E-05 16 Hf 3.4E-02 5.0E-06 Footnote 5 Ta 2.8E-01 1.3E-03 FM - Ref.16; Fr -Footnote 6 w 1.3E-03 5.0E-04 6 Re 1.0E-01 1.3E-03 FM - Ref.16; Fr -Footnote 12 Os 2.2E-01 6.0E-04 Footnote 13 Ir 7.3E-03 5.5E-03 Footnote 14 Pt 5.3E-02 6.?E-03 Footnote 10 Au 1.3E-02 3.2E-02 Footnote 15 Hg 3.0E-02 9.?E-06 FM - Ref.16; Fr -Footnote 11 Tl 1.5E-02 1.3E-03 FM - Ref.16; Fr -Footnote 3 Pb 9.1 E-04 9.9E-05 98 Bi 1.?E-02 5.0E-04 98 Ra 5.5E-04 5.9E-04 98 Th 1.6E-06 5.0E-06 98 u 1.6E-06 1.2E-04 98 Np 2.0E-04 5.0E-06 6 Am 1.6E-06 2.0E-05 98 Notes:
- 1. NA= It is assumed that noble gases are not deposited on the ground.
- 2. Elements listed are those considered for 10CFR20 assessment and compliance.
Footnotes: There are numerous Ft and FM values that were not found in published literature. In these cases, the periodic table was used in conjunction with published values. The periodic table was used based on a general assumption that elements have similar characteristics when in the same column of the periodic table. The values of elements in the same column of the periodic table, excluding atomic numbers 58-71 and 90-103, were averaged then assigned to elements missing values located in the same column of the periodic table. This method was used for all columns where there were missing values except column 3A, where there was no data, hence, the average of column 2B and 4A were used.
- 1. Values obtained by averaging Reference 6 values of Ca, Sr, Ba and Ra.
- 2. Ft value obtained by assigning the Reference 6 value for I. FM value obtained by averaging l(Ref. 6) and Br (Ref.16).
- 3. Ft values obtained by averaging Zn (Ref.6) and Pb (Ref. 98); there were novalues for elements in the same column; an average is taken between values of columns 2B and 4A on the periodic table. FM values obtained by using the value for Tl from Reference 16.
- 4. Values obtained by averaging Reference 6 values of Y and La.
- 5. Values obtained by assigning the Reference 6 value for Zr.
- 6. Ft values obtained from Ref. 6 value for Nb. FM values obtained by averaging values for Nb (Ref.6) and Ta (Ref. 16).
- 7. Values obtained from the Reference 6 values for Pb.
- 8. Values obtained from the Reference 6 values for Bi.
- 9. Values obtained from the Reference 6 values for Te.
- 10. Values obtained from the Reference 6 values for Ni.
- 11. Ft values obtained from Ref. 6 values for Zn. FM values obtained by averaging the Reference 6 values for Zn and Hg.
- 12. Values obtained by averaging Reference 6 values for Mn, Tc, Nd and Reference 98 value for U.
- 13. Values obtained by averaging Reference 6 values from Fe and Ru.
- 14. Values obtained by averaging Reference 6 values from Co and Rh.
- 15. Values obtained by averaging Reference 6 values from Cu and Ag.
Page 164 of 267
Revision 5 Aug 31, 2015 Table C-4 Atmospheric Stability Classes Pasquill Temperature Change Stability a with Height cre Description Class (degrees) (°C/100 m) Extremely A >22.5 <-1.9 Unstable Moderately B 17.5 to 22.5 -1.9to-1.7 Unstable Slightly c 12.5 to 17.5 -1.7to-1.5 Unstable Neutral D 7.5to12.5 -1.5 to -0.5 Slightly E 3.8 to 7.5 -0.5 to 1.5 Stable Moderately F 2.1 to3.8 1.5 to 4.0 Stable Extremely G 0 to 2.1 >4.0 Stable acre is the standard deviation of horizontal wind direction fluctuation over a period of 15 minutes to 1 hour. From Regulatory Guide 1.21, Table 4B. Page 165 of 267
Revision 5 Aug 31, 2015 Table C-5 Vertical Dispersion Parameters Section 1 Vertical Dispersion Parameters cr2 cr2 (meters)= aRb+c with cr2 limited to a maximum of 1000 meters R =downwind range (meters) a, b and c have the values listed below: Stability 100 < R < 1000 R > 1000 Class g b Q g Q Q A * *
- 0.00024 2.094 -9.6 B * * * * *
- c 0.113 0.911 0.0 * *
- D 0.222 0.725 -1.7 1.26 0.516 -13.0 E 0.211 0.678 -1.3 6.73 0.305 -34.0 F 0.086 0.74 -0.35 18.05 0.18 -48.6 G 0.052 0.74 -0.21 10.83 0.18 -29.2 Basis: Reference 53, except for cases denoted by an asterisk. In these cases, the value of cr2 is obtained by a polynomial approximation to the data from Reference 53 (see Section 2 of this table). The functions given in Reference 50 are not used because they are discontinuous at 1000 meters.
Section 2 Polynomial Approximation for crz.;. 2 3 cr2 (meters)= exp [a 0 + a1P + a2 P + a3P ] with cr2 limited to a maximum of 1000 meters P = loge [R(meters)] ao, a1, az and a3 have the values listed below: Stability Class Range Coefficients A 100 ~ R~ 1000 ao = -10.50 a1 = 6.879 a2 = -1.309 a3= 0.0957 B 100 ~ R~ 1000 ao = -0.449 a1 = 0.218 a2 = 0.112 a3 = -0.00517 B R > 1000 ao = 319.148 a1 = -127.806 a2 = 17.093 a3= -0.750 c R > 1000 ao = 5.300 a1 = -1.866 a2= 0.3509 a3 = -0.01514 Page 166 of 267
Revision 5 Aug 31, 2015 Table C-6 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste Allowable Concentration (µCi/ml) 3 Nuclide Zion Kr85m 2E-4 Kr85 5E-4 Kr87 4E-5 Kr88 9E-5 Ar41 7E-5 Xe 131m 7E-4 Xe 133m 5E-4 Xe 133 6E-4 Xe 135m 2E-4 Xe 135 2E-4 3 Computed from Equation 17 of ICRP Publication 2 (Reference 50) adjusted for infinite cloud submersion in water, and R =0.01 rem/week, Pw =1.0 gm/cm , and Pw /P1 =1.0. 3 Page 167 of 267
Revision 5 Aug 31, 2015 Table C-7 Radiological Decay Constants p.,i) in hf1 Isotope Lambda Isotope Lambda lsotoQe Lambda H-3 6.44E-06 As-73 3.6E-04 Tc-104 2.31E+OO Be-7 5.4E-04 As-74 1.62E-03 Ru-97 9.96E-03 C-14 1.38E-08 As-76 2.63E-02 Ru-103 7.34E-04 F-18 3.78E-01 As-77 1.79E-02 Ru-105 1.56E-01 Na-22 3.04E-05 Se-73 9.69E-02 Ru-106 7.84E.:.05 Na-24 4.62E-02 Se-75 2.41E-04 Rh-106 8.33E+01 Mq-27 4.39E+OO Br-77 1.21 E-02 Pd-109 5.15E-02 Mg-28 3.31 E-02 Br-80 2.38E+OO Cd-109 6.22E-05 Al-26 1.10E-10 Br-82 1.96E-02 ln-111 1.02E-02 Al-28 1.85E+01 Br-83 2.90E-01 ln-115M 1.59E-01 P-32 2.02E-03 Br-84 1.30E+OO ln-116 7.66E-01 Cl-38 1.12E+OO Br-85 1.45E+01 Sn-113 2.51E-04 Ar-41 3.79E-01 Kr-79 1.98E-02 Sn-117M 2.12E-03 K-40 6.19E-14 Kr-81 3.77E-10 Sn-119M 9.85E-05 K-42 5.61 E-02 Kr-83M 3.79E-01 Sb-117 2.48E-01 K-43 3.07E-02 Kr-85M 1.55E-01 Sb-122 1.07E-02 Ca-47 6.37E-03 Kr-85 7.38E-06 Sb-124 4.80E-04 Sc-44 1.76E-01 Kr-87 5.44E-01 Sb-125 2.86E-05 Sc-46M 1.33E+02 Kr-88 2.44E-01 Sb-126 2.33E-03 Sc-46 3.44E-04 Kr-90 7.71 E+OO Aq-108M 6.23E-07 Sc-47 8.44E-03 Rb-84 8.78E-04 Ag-108 1.75E+01 Ti-44 1.67E-06 Rb-86 1.55E-03 Aq-110M 1.16E-04 V-48 1.81 E-03 Rb-87 1.67E-15 Ag-111 3.87E-03 Cr-51 1.04E-03 Rb-88 2.33E+OO Te-121 M 1.88E-04 Mn-52M 1.94E+OO Rb-89 2.69E+OO Te-121 1.72E-03 Mn-52 5.16E-03 Sr-85 4.45E-04 Te-123M 2.41 E-04 Mn-54 9.23E-05 Sr-87M 2.47E-01 Te-125M 4.98E-04 Mn-56 2.69E-01 Sr-89 5.71 E-04 Te-125 O.OOE+OO Fe-52 8.37E-02 Sr-90 2.77E-06 Te-127M 2.65E-04 Fe-55 2.93E-05 Sr-91 7.29E-02 Te-127 7.41 E-02 Fe-59 6.47E-04 Sr-92 2.56E-01 Te-129M 8.59E-04 Co-57 1.07E-04 Y-86 4.70E-02 Te-129 5.96E-01 Co-58 4.08E-04 Y-87 8.63E-03 Te-131M 2.31E-02 Co-60 1.50E-05 Y-88 2.71 E-04 Te-131 1.66E+OO Ni-63 7.90E-07 Y-90 1.08E-02 Te-132 8.86E-03 Ni-65 2.75E-01 Y-91M 8.35E-01 Te-134 9.93E-01 Cu-64 5.46E-02 Y-91 4.94E-04 1-123 5.28E-02 Cu-67 4.67E-04 Y-92 1.96E-01 1-124 6.91E-03 Cu-68 8.31 E+01 Y-93 6.86E-02 1-125 4.80E-04 Zn-65 1.18E-04 Zr-95 4.51 E-04 1-130 5.61 E-02 Zn-69M 5.04E-02 Zr-97 4.10E-02 1-131 3.59E-03 Zn-69 7.46E-01 Nb-94 3.90E-09 1-132 3.01E-01 Ga-66 7.37E-02 Nb-95 8.00E-03 1-133 3.33E-02 Ga-67 8.85E-03 Nb-97M 4.15E+01 1-134 7.89E-01 Ga-68 6.10E-01 Nb-97 5.76E-01 1-135 1.05E-01 Ga-72 4.91E-02 Mo-99 1.05E-02 Xe-127 7.93E-04 Ge-77 6.13E-02 Tc-99M 1.15E-01 Xe-129M 3.25E-03 As-72 2.67E-02 Tc-101 2.92E+OO Xe-131M 2.44E-03 Page 168 of 267
Revision 5 Aug 31, 2015 Table C-7 (Cont'd) Radiological Decay Constants (A.i) in hr"1 lsotooe Lambda lsotooe Lambda Xe-133M 1.32E-02 Yb-175 6.89E-03 Xe-133 5.51E-03 Lu-177 4.30E-03 Xe-135M 2.70E+OO Hf-181 6.81 E-04 Xe-135 7.61 E-02 Ta-182 2.52E-04 Xe-137 1.08E+01 Ta-183 5.78E-03 Xe-138 2.94E+OO W-187 2.91 E-02 Cs-129 2.16E-02 Re-188 4.08E-02 Cs-132 4.46E-03 Os-191 1.88E-03 Cs-134 3.84E-05 lr-194 3.62E-02 Cs-136 2.19E-03 Pt-195M 7.18E-03 Cs-137 2.62E-06 Pt-197 3.79E-02 Cs-138 - 1.29E+OO Au-195M 8.15E+01 Cs-139 4.41 E+OO Au-195 1.58E-04 Ba-131 2.45E-03 Au-198 1.07E-02 Ba-133M 1.78E-02 Au-199 9.20E-03 Ba-133 7.53E-06 Hq-197 2.91 E-02 Ba-135M 2.41E-02 Hg-203 6.20E-04 Ba-137M 1.63E+01 Tl-201 9.49E-03 Ba-137 O.OOE+OO Tl-206 9.90E+OO Ba-139 4.99E-01 Tl-208 1.36E+01 Ba-140 2.26E-03 Pb-203 1.33E-02 Ba-141 2.27E+OO Pb-210 3.55E-06 Ba-142 3.88E+OO Pb-212 6.51 E-02 La-140 1.72E-02 Pb-214 1.55E+OO La-142 4.35E-01 Bi-206 4.63E-03 Ce-139 2.10E-04 Bi-207 2.37E-06 Ce-141 8.88E-04 Bi-214 2.09E+OO Ce-143 2.10E-02 Ra-226 4.94E-08 Ce-144 1.02E-04 Th-232 5.63E-15 Pr-142 3.62E-02 U-238 1.77E-14 Pr-143 2.13E-03 Np-239 1.23E-02 Pr-144 2.40E+OO Am-241* 1.83E-07 Nd-147 2.63E-03 Nd-149 4.01E-01 (A.i) =Radiological Decay C onstant Pm-145 4.47E-06 = 0.693/Ti Pm-148M 6.99E-04 Pm-148 5.38E-03 Ti = Radiological Half-Life in hours Pm-149 1.31 E-02 (from Reference 70). Sm-153 1.48E-02 Except for Cu-68, Tc-104, Ba-137, Ta-183, TL-206, Eu-152 5.82E-06 Bi-206 which are fro m References 100. Eu-154 8.99E-06 Eu-155 1.59E-05 Gd-153 1.20E-04 Dv-157 8.60E-02 Er-169 3.07E-03 Er-171 9.22E-02 Tm-170 2.25E-04 Yb-169 9.03E-04 Page 169 of 267
Revision 5 Aug 31, 2015 Table C-8 Bioaccumulation Factors (BF;) to be Used in the Absence of Site-Specific Data BF; for Freshwater Fish Element {12Ci/kg per pCi/L} Reference H 9.0E-01 6 Be 2.8E+01 Footnote 2 c 4.6E+03 6 F 2.2E+02 Footnote 16 Na 1.0E+02 6 Mg 2.8E+01 Footnote 2 Al 2.2E+03 Footnote 13 p 1.0E+05 6 Cl 2.2E+02 Footnote 16 Ar NA NA K 1.0E+03 Footnote 1 Ca 2.8E+01 Footnote 2 Sc 2.5E+01 Footnote 3 Ti 3.3E+OO Footnote 4 v 3.0E+04 Footnote 5 Cr 2.0E+02 6 Mn 4.0E+02 6 Fe 1.0E+02 6 Co 5.0E+01 6 Ni 1.0E+02 6 Cu 5.0E+01 6 Zn 2.0E+03 6 Ga 2.2E+03 Footnote 13 Ge 2.4E+03 Footnote 12 As 3.3E+04 Footnote 14 Se 4.0E+02 Footnote 15 Br 4.2E+02 6 Kr NA NA Rb 2.0E+03 6 Sr 3.0E+01 6 y 2.5E+01 6 Zr 3.3E+OO 6 Nb 3.0E+04 6 Mo 1.0E+01 6 Tc 1.5E+01 6 Ru 1.0E+01 6 Rh 1.0E+01 6 Pd 1.0E+02 Footnote 9 Cd 2.0E+03 Footnote 11 In 2.2E+03 Footnote 13 Sn 2.4E+03 Footnote 12 Sb 1.0E+OO 98 Ag 2.3E+OO 56 Te 4.0E+02 6 I 1.5E+01 6 Xe NA NA Cs 2.0E+03 6 Ba 4.0E+OO 6 La 2.5E+01 6 Ce 1.0E+OO 6 Pr 2.5E+01 6 Nd 2.5E+01 6 Pm 3.0E+01 98 Sm 3.0E+01 Footnote 3 Page 170 of 267
Revision 5 Aug 31, 2015 Table C-8 (Cont'd) Bioaccumulation Factors (BFj) to be Used in the Absence of Site-Specific Data BFi for Freshwater Fish Element (pCi/kg per pCi/L) Reference Eu 1.0E+02 Footnote 3 Gd 2.6E+01 Footnote 3 Dy 2.2E+03 Footnote 3 Er 3.3E+04 Footnote 3 Tm 4.0E+02 Footnote 3 Yb 2.2E+02 Footnote 3 Lu 2.5E+01 Footnote 3 Hf 3.3E+OO Footnote 4 Ta 3.0E+04 Footnote 5 w 1.2E+03 6 Re 2.1E+02 Footnote 6 Os 5.5E+01 Footnote 7 Ir 3.0E+01 Footnote 8 Pt 1.0E+02 Footnote 9 Au 2.6E+01 Footnote 10 Hg 2.0E+03 Footnote 11 Tl 2.2E+03 Footnote 13 Pb 3.0E+02 98 Bi 2.0E+01 98 Ra 5.0E+01 98 Th 3.0E+01 98 u 1.0E+01 98 Np 1.0E+01 6 Am 3.0E+01 98 Footnotes: NA =It is assumed that noble gases are not accumulated. In Reference 6, see Table A-1. A number of bioaccumulation factors could not be found in literature. In this case, the periodic table was used in conjunction with published element values. This method was used for periodic table columns except where there were no values for column 3A so the average of columns 2B and 4A was assigned.
- 1. Value is the average of Reference 6 values in literature for H, Na, Rb and Cs.
- 2. Value is the average of Ref. 6 values in literature for Sr, Ba and Ref. 98 values for Ra.
- 3. Value is the same as the Reference 6 value used for Y.
- 4. Value is the same as the Reference 6 value used for Zr.
- 5. Value is the same as the Reference 6 value used for Nb.
- 6. Value is the average of Reference 6 values in literature for Mn and Tc.
- 7. Value is the average o}}