ML13133A345: Difference between revisions

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: i. Tech Spec Whole Body:          500 mrem/year ii. Tech Spec Skin:              3000 mrem/year
: 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:
: b. Particulates with half-lives > 8 days, tritium and Iodine:
: i. Tech Spec Organ:              1500 mrem/year ii. 1OCFR50 Organ:                7.5 mrem/quarter, 15 mrem/year
: i. Tech Spec Organ:              1500 mrem/year ii. 10CFR50 Organ:                7.5 mrem/quarter, 15 mrem/year
: c. Liquid Effluents:
: c. Liquid Effluents:
: i. 1OCFR50 Whole body:          1.5 mrem/quarter, 3mrem/year ii. 1OCFR 50 Organ:              5 mrem/quarter, 10 mrem/year
: i. 10CFR50 Whole body:          1.5 mrem/quarter, 3mrem/year ii. 10CFR 50 Organ:              5 mrem/quarter, 10 mrem/year
: 2. Effluent Concentration Limits (ECL): Limits used in determining allowable release rates or concentrations.
: 2. Effluent Concentration Limits (ECL): Limits used in determining allowable release rates or concentrations.
: a. Gaseous Effluents: I0CFR20 Appendix B Table 2 Column 1.
: a. Gaseous Effluents: I0CFR20 Appendix B Table 2 Column 1.
Line 93: Line 93:
Summary of Changes - 2012: ZS-WM-123 Rev 1:
Summary of Changes - 2012: ZS-WM-123 Rev 1:
: 1. Provided additional guidance on Radioactive Waste Requirements - The following are the steps included:
: 1. Provided additional guidance on Radioactive Waste Requirements - The following are the steps included:
Step 4.1.3 - Radioactive Waste Requirements: The basis for the functionality of the radioactive waste system is to ensure the system will be available for use whenever radioactive waste requires processing and packaging prior to being shipped offsite. These radioactive waste requirements implement the requirements of IOCFR §50.36a and General Design Criteria 60 of Appendix A to 1OCFRPart
Step 4.1.3 - Radioactive Waste Requirements: The basis for the functionality of the radioactive waste system is to ensure the system will be available for use whenever radioactive waste requires processing and packaging prior to being shipped offsite. These radioactive waste requirements implement the requirements of IOCFR §50.36a and General Design Criteria 60 of Appendix A to 10CFRPart
: 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste/liquid/solidification agent/catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.
: 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste/liquid/solidification agent/catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.


ZionSolutions, LLC ZS-2013-0176: Attachment 1 - Supplemental Information Attachment 1-Supplemental Information (continued)
ZionSolutions, LLC ZS-2013-0176: Attachment 1 - Supplemental Information Attachment 1-Supplemental Information (continued)
Step 4.14 - Liquid LLRW Requirements for Vendors: ZionSolutions requires that all vendors who process liquid LLRW meet all EnergySolutions quality standards and shall use an NRC approved PROCESS CONTROL PROGRAM Topical report. Furthermore, the vendor solidification/stabilization media must be approved by the licensed burial sites.
Step 4.14 - Liquid LLRW Requirements for Vendors: ZionSolutions requires that all vendors who process liquid LLRW meet all EnergySolutions quality standards and shall use an NRC approved PROCESS CONTROL PROGRAM Topical report. Furthermore, the vendor solidification/stabilization media must be approved by the licensed burial sites.
Step 4.1.5 - The process control activities described in this program and the high integrity containers (HICs) and liners referenced in the NRCs radioactive waste packaging Certificate of Compliance (C of C) are QA approved. Process or equipment failures are subject to the requirements of 1OCFR21, "Reporting of Deficiencies and Noncompliance."
Step 4.1.5 - The process control activities described in this program and the high integrity containers (HICs) and liners referenced in the NRCs radioactive waste packaging Certificate of Compliance (C of C) are QA approved. Process or equipment failures are subject to the requirements of 10CFR21, "Reporting of Deficiencies and Noncompliance."
Step 4.1.6 - During the processing or dewatering of Class B or C waste, deviations from the process control parameters or acceptable waste form properties shall be evaluated for reportability as "mishaps". Failures during qualification testing are not considered "mishaps" and are not reportable events.
Step 4.1.6 - During the processing or dewatering of Class B or C waste, deviations from the process control parameters or acceptable waste form properties shall be evaluated for reportability as "mishaps". Failures during qualification testing are not considered "mishaps" and are not reportable events.
Mishaps shall be reported to the NRC within 30 days of knowledge of the event and approval from the disposal site shall be.
Mishaps shall be reported to the NRC within 30 days of knowledge of the event and approval from the disposal site shall be.
obtained prior to shipment.
obtained prior to shipment.
Step 4.1.7 - Liquid wastes will be solidified in accordance with the NRC Technical Position on Waste Form, Rev. 1, January 1999; Waste Form Technical Position, Rev. 1, and the applicable disposal site criteria prior to disposal. (See Attachment 2 for details).
Step 4.1.7 - Liquid wastes will be solidified in accordance with the NRC Technical Position on Waste Form, Rev. 1, January 1999; Waste Form Technical Position, Rev. 1, and the applicable disposal site criteria prior to disposal. (See Attachment 2 for details).
Step 4.1.8 - Containers, shipping casks, and methods of packaging will meet applicable federal regulations, e.g., 1OCFR71 and 49CFR173, Subpart I.
Step 4.1.8 - Containers, shipping casks, and methods of packaging will meet applicable federal regulations, e.g., 10CFR71 and 49CFR173, Subpart I.
Step 4.1.9 - Waste classification will meet the requirements of 1OCFR61 and disposal site criteria.
Step 4.1.9 - Waste classification will meet the requirements of 10CFR61 and disposal site criteria.
Step 4.1.10 - Procedures or other administrative controls/documents shall assure that the radioactivity content transferred to any one liner or HIC will not result in exceeding the design basis site boundary dose calculated in Reference 5.16 (Zion Corrective Action 295-201-97-CAQD- 121605).
Step 4.1.10 - Procedures or other administrative controls/documents shall assure that the radioactivity content transferred to any one liner or HIC will not result in exceeding the design basis site boundary dose calculated in Reference 5.16 (Zion Corrective Action 295-201-97-CAQD- 121605).
: 2. Discussion of ZionSolutions not planning on performing any solidification processes for waste from ZionSolutions. If any solidification is required, it will be an off-site vendor performing the activity.
: 2. Discussion of ZionSolutions not planning on performing any solidification processes for waste from ZionSolutions. If any solidification is required, it will be an off-site vendor performing the activity.
: 3. Provide when a High Integrity Container (HIC) is to be used.
: 3. Provide when a High Integrity Container (HIC) is to be used.
: 4. Provide a list of reportable events based on 1OCFR21 and Generic NRC letter 91-02.
: 4. Provide a list of reportable events based on 10CFR21 and Generic NRC letter 91-02.
: 5. Detail Cartridge Filter Elements and their use.
: 5. Detail Cartridge Filter Elements and their use.
: 6. Detail Demineralizer Resins and their use/disposal.
: 6. Detail Demineralizer Resins and their use/disposal.
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: 5.    % Max exposed organ                            5.52E-02 % child liver (1.84E-02 % thyroid)
: 5.    % Max exposed organ                            5.52E-02 % child liver (1.84E-02 % thyroid)
Quarter 1        Quarter 2            Quarter 3            Quarter 4          Total TEDE            1.68E-05          1.81E-05              1.15E-05              1.38E+00          1.38E+00 mrem              mrem                  mrem                mrem                mrem B. Maximally Exposed Receptor:
Quarter 1        Quarter 2            Quarter 3            Quarter 4          Total TEDE            1.68E-05          1.81E-05              1.15E-05              1.38E+00          1.38E+00 mrem              mrem                  mrem                mrem                mrem B. Maximally Exposed Receptor:
: 1. Airborne Yearly limit  Total Dose  % of Qtr Obj I1 Qtr        2nd Qtr        3P1Qtr      41hQtr        1OCFR 50    2012        Yearly App. I                  limit Gamma air (mrad)    5.0    0.OOE+00      0.OOE+00      0.OOE+00    0.OOE+00      0.0        0.OOE+00    O.OOE+00 Beta Air (mrad)      10.0  O.OOE+00      O.OOE+00      O.OOE+00    0.OOE+00    20.0          O.OOE+00    O.OOE+00 Total Body (mrem)    7.5    1.68E-05      1.81E-05      1.15E-05    1.63E-05      15.0        6.25E-05    4.17E-06 Skin (mrem)          7.5    O.OOE+00      O.OOE+00      O.OOE+00    O.OOE+00      15.0        0.OOE+00    O.OOE+00 Organ (mrem)        7.5    1.68E-05      1.81E-05      1.15E-05    1.63E-05      15.0        6.25E-05    4.17E-06 Critical Organ              Child liver  Child liver  Child liver  Child liver                Child liver Child liver
: 1. Airborne Yearly limit  Total Dose  % of Qtr Obj I1 Qtr        2nd Qtr        3P1Qtr      41hQtr        10CFR 50    2012        Yearly App. I                  limit Gamma air (mrad)    5.0    0.OOE+00      0.OOE+00      0.OOE+00    0.OOE+00      0.0        0.OOE+00    O.OOE+00 Beta Air (mrad)      10.0  O.OOE+00      O.OOE+00      O.OOE+00    0.OOE+00    20.0          O.OOE+00    O.OOE+00 Total Body (mrem)    7.5    1.68E-05      1.81E-05      1.15E-05    1.63E-05      15.0        6.25E-05    4.17E-06 Skin (mrem)          7.5    O.OOE+00      O.OOE+00      O.OOE+00    O.OOE+00      15.0        0.OOE+00    O.OOE+00 Organ (mrem)        7.5    1.68E-05      1.81E-05      1.15E-05    1.63E-05      15.0        6.25E-05    4.17E-06 Critical Organ              Child liver  Child liver  Child liver  Child liver                Child liver Child liver
: 2. Aquatic Yearly limit  Total Dose    %of Qtr Obj 1" Qtr      2nd Qtr        3r" Qtr    411Qtr        IOCFR 50    2012          Yearly App. I                      limit Total Body (mrem)    1.5    0.OOE+00    0.OOE+00      0.OOE+00    0.OOE+00    3.0          0.OOE+00      0.OOE+00 Organ (mrem)        5.0    0.OOE+00    0.OOE+00      0.OOE+00    0.OOE+00      10.0        0.OOE+00      0.OOE+00 Critical Organ              NA          NA            NA          NA                        NA            NA
: 2. Aquatic Yearly limit  Total Dose    %of Qtr Obj 1" Qtr      2nd Qtr        3r" Qtr    411Qtr        IOCFR 50    2012          Yearly App. I                      limit Total Body (mrem)    1.5    0.OOE+00    0.OOE+00      0.OOE+00    0.OOE+00    3.0          0.OOE+00      0.OOE+00 Organ (mrem)        5.0    0.OOE+00    0.OOE+00      0.OOE+00    0.OOE+00      10.0        0.OOE+00      0.OOE+00 Critical Organ              NA          NA            NA          NA                        NA            NA
: 3. Direct
: 3. Direct
Line 253: Line 253:


ZionSolutions, LLC ZS-2013-0176: Attachment 4 - Radiological Impact on Man Attachment 4.3 - Unit 2 II. Unit 2 (Docket Number -304)
ZionSolutions, LLC ZS-2013-0176: Attachment 4 - Radiological Impact on Man Attachment 4.3 - Unit 2 II. Unit 2 (Docket Number -304)
C. 10 CFR20 & 40CFRI90 Compliance Assessment: The demonstration of compliance with 40CFRI190 will be used to demonstrate compliance with 1OCFR20.
C. 10 CFR20 & 40CFRI90 Compliance Assessment: The demonstration of compliance with 40CFRI190 will be used to demonstrate compliance with 10CFR20.
: 6. Total Effective Dose Equivalent                  1.38E+00 mrem/year
: 6. Total Effective Dose Equivalent                  1.38E+00 mrem/year
: 7. 40 CFR 190 Whole body limit                      25 mrem/year
: 7. 40 CFR 190 Whole body limit                      25 mrem/year

Revision as of 15:04, 11 November 2019

Radioactive Effluent Release Report for 2012, Offsite Dose Calculation Manual for 2012, and Process Control Program for 2012
ML13133A345
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 04/30/2013
From: Bouchard G
ZionSolutions
To:
Document Control Desk, Office of Nuclear Reactor Regulation, NRC/FSME
References
ZS-2013-0176
Download: ML13133A345 (22)


Text

ZIONSOLUTIONS, An E.*lrWSot~ww Comp"ny April 30, 2013 ZS-2013-0176 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Zion Nuclear Power Station, Unit 1 and 2 Facility Operating License Nos. DPR-39 and DPR-48 NRC Docket Nos. 50-295 and 50-304

Subject:

Radioactive Effluent Release Report for 2012, Offsite Dose Calculation Manual for 2012, and Process Control Program for 2012.

In accordance with Technical Specification 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 2012. The report is required to be submitted prior to May 1, 2013 and is provided as attachments 1-6 to this letter. A listing of commitments contained in this submittal is provided in the 1st Attachment.

Pursuant to 10 CFR 50.4 and Technical Specification 5.6.1 .c. there were changes made to the Zion Station Offsite Dose Calculation Manual (ODCM) during the period of January through December 2012. The 7th Attachment provides the changes made to the ODCM during the calendar year of 2012. Also pursuant to 10 CFR 50.4, Technical Specification 5.6.1 .c., and Section 12.7.2 of Zion Station ODCM there were changes made to the Zion Station Process Control Program (PCP) during the period of January through December 2012. The changes made to the PCP are included in the 8th Attachment.

Technical Specification 5.6.1 for the Zion Nuclear Power Station requires a copy of the entire ODCM be submitted to the NRC as part of, or concurrent with, the Radioactive Effluent Release Report. A copy of the entire Zion Station ODCM, current as of December 31, 2012 is enclosed.

If you have any questions about this submittal please contact Mr. Christopher Keene at (224)789-4073.

Respectfully,

&yB uchard 0 Decommissioning Plant Manager ZionSolutions, LLC 101 Shiloh Boulevard, Zion IL 60099 s (224) 789-4016 - Fax: (224) 789-4008 -www.zionsolutionscompany.com

ZionSolutions, LLC ZS-2013-0176 Page 2 of 2 Attachments:

I. 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 4.1 40CFR 190 Compliance summary 4.2 Unit 1 4.3 Unit 2 4.4 Combined 40CFR190 report
5. Meteorology Data
6. Errata Data from previous years
7. Zion Station ODCM
8. ZS-WM-123 Process Control Program Requirements cc: John Hickman, U.S. NRC Senior Project Manager Service List

Zion Nuclear Power Station, Unit 1 and 2 License Transfer Service List cc:

Patrick T. Daly Dan Shrum Senior VP and General Manager Senior VP Regulatory Affairs ZionSolutions, LLC EnergySolutions 101 Shiloh Boulevard 423 West 300 South, Ste. 200 Zion, IL 60099 Salt Lake City, UT 84101 (Cover letter only, no attachments) (Cover letter only, no attachments)

Patrick Thurman, Esq. Russ Workman VP Regulatory Affairs, Licensing & General Counsel Document Control EnergySolutions ZionSolutions, LLC 423 West 300 South, Ste. 200 101 Shiloh Boulevard Salt Lake City, UT 84101 Zion, IL 60099 (Cover letter only, no attachments)

(Cover letter only, no attachments)

Illinois Department of Nuclear Safety Gary Bouchard Office of Nuclear Facility Safety VP Engineering, Ops & Nuclear Security and 1035 Outer Park Drive Decommissioning Plant Manager Springfield, IL 62704 ZionSolutions, LLC (Cover letter only, no attachments) 101 Shiloh Boulevard Zion, IL 60099 Kent McKenzie (Cover letter only, no attachments) Emergency Management Coordinator Lake County Emergency Management Alan Parker Agency President Projects Group 1303 N. Milwaukee Avenue EnergySolutions Libertyville, IL 60048-1308 1009 Commerce Park Drive, Ste. 100 (Cover letter only, no attachments)

Oak Ridge, TN 37830 (Cover letter only, no attachments) Regional Administrator U.S. NRC, Region III John Christian 2443 Warrenville Road President of Logistics, Processing and Lisle, IL 60532-4352 Disposal (LP& D) Group EnergySolutions John E. Matthews 1750 Tysons Boulevard, Suite 1500 Morgan, Lewis & Bockius LLP Mclean, VA 22102 1111 Pennsylvania Avenue, NW (Cover letter only, no attachments) Washington, DC 20004 (Cover letter only, no attachments)

ZionSolutions, LLC ZS-2013-0176: Attachment 1 - Supplemental Information Attachment 1 - Supplemental Information

1. Regulatory Limits: The dose to a member of the public from 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. 10CFR50 Whole body: 1.5 mrem/quarter, 3mrem/year ii. 10CFR 50 Organ: 5 mrem/quarter, 10 mrem/year
2. Effluent Concentration Limits (ECL): Limits used in determining allowable release rates or concentrations.
a. Gaseous Effluents: I0CFR20 Appendix B Table 2 Column 1.
b. Liquid Effluents: 10 X 10CFR20 Appendix B Table 2 Column 2.
3. Measurements and Approximations 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.
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. Tritium activity in gaseous releases from evaporation of water in the spent fuel pool and water filled reactor cavities.
c. Liquid effluents are continuously monitored and isotopic analysis performed weekly.
4. Batch Releases:
a. Liquid: There were no liquid batch releases in 2012
b. Gaseous: There were no gaseous batch releases in 2012.
5. Abnormal Releases:
a. Liquid: There were no liquid abnormal releases in 2012.
b. Gaseous: there were no gaseous abnormal releases in 2012.

ZionSolutions, LLC ZS-2013-0176: Attachment 1 - Supplemental Information Attachment 1 - Supplemental Information (continued)

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.

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.

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.

There are no such occurrences

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 abandoned in place.

No liquid holdup tanks exceeded the limits of Permanently Defueled Technical Specifications 5.6.3 during 2012.

ZionSolutions, LLC ZS-2013-0176: Attachment I - Supplemental Information Attachment 1 - Supplemental Information (continued)

9. Offsite Dose Calculation Manual (ODCM)

Changes to the ODCM 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 summary of changes made to the ODCM during 2012 and an entire copy of the ODCM, current as of December 31, 2012 are required to be submitted.

Revisions to ODCM and Process Control Program are listed below:

a. ODCM Revisions:

Page/Section Change Summary 10-10/Table 10-2 1A,1B purge exhaust fan maximum allowed flow rate changed to 45,000 cfm 12-28/Table 12.4-la Modified daily samplining requirements to reflect requirement to sample during decommissioning activities.

12-28/Table 12.4-1h Change to allow short duration interruptions to facilitate filter changeout without deviating from continuous sampling requirements.

12-28/Table 12.4-1i Changed Unit 1 purge exhaust fan maximum allowed flowrate to 45,000 cfm.

b. Process Control Program (PCP)

Summary of Changes - 2012: ZS-WM-l123 Rev 0:

Complete re-write of procedure.

Summary of Changes - 2012: ZS-WM-123 Rev 1:

1. Provided additional guidance on Radioactive Waste Requirements - The following are the steps included:

Step 4.1.3 - Radioactive Waste Requirements: The basis for the functionality of the radioactive waste system is to ensure the system will be available for use whenever radioactive waste requires processing and packaging prior to being shipped offsite. These radioactive waste requirements implement the requirements of IOCFR §50.36a and General Design Criteria 60 of Appendix A to 10CFRPart

50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste/liquid/solidification agent/catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.

ZionSolutions, LLC ZS-2013-0176: Attachment 1 - Supplemental Information Attachment 1-Supplemental Information (continued)

Step 4.14 - Liquid LLRW Requirements for Vendors: ZionSolutions requires that all vendors who process liquid LLRW meet all EnergySolutions quality standards and shall use an NRC approved PROCESS CONTROL PROGRAM Topical report. Furthermore, the vendor solidification/stabilization media must be approved by the licensed burial sites.

Step 4.1.5 - The process control activities described in this program and the high integrity containers (HICs) and liners referenced in the NRCs radioactive waste packaging Certificate of Compliance (C of C) are QA approved. Process or equipment failures are subject to the requirements of 10CFR21, "Reporting of Deficiencies and Noncompliance."

Step 4.1.6 - During the processing or dewatering of Class B or C waste, deviations from the process control parameters or acceptable waste form properties shall be evaluated for reportability as "mishaps". Failures during qualification testing are not considered "mishaps" and are not reportable events.

Mishaps shall be reported to the NRC within 30 days of knowledge of the event and approval from the disposal site shall be.

obtained prior to shipment.

Step 4.1.7 - Liquid wastes will be solidified in accordance with the NRC Technical Position on Waste Form, Rev. 1, January 1999; Waste Form Technical Position, Rev. 1, and the applicable disposal site criteria prior to disposal. (See Attachment 2 for details).

Step 4.1.8 - Containers, shipping casks, and methods of packaging will meet applicable federal regulations, e.g., 10CFR71 and 49CFR173, Subpart I.

Step 4.1.9 - Waste classification will meet the requirements of 10CFR61 and disposal site criteria.

Step 4.1.10 - Procedures or other administrative controls/documents shall assure that the radioactivity content transferred to any one liner or HIC will not result in exceeding the design basis site boundary dose calculated in Reference 5.16 (Zion Corrective Action 295-201-97-CAQD- 121605).

2. Discussion of ZionSolutions not planning on performing any solidification processes for waste from ZionSolutions. If any solidification is required, it will be an off-site vendor performing the activity.
3. Provide when a High Integrity Container (HIC) is to be used.
4. Provide a list of reportable events based on 10CFR21 and Generic NRC letter 91-02.
5. Detail Cartridge Filter Elements and their use.
6. Detail Demineralizer Resins and their use/disposal.
7. Detail Dry Active Waste (DAW) generation, prohibited items, and packaging.
8. Detail Irradiated Metal/Hardware description and packaging guidance.
9. Detail Incinerable Fluids - Description of how generated and disposal.

ZionSolutions, LLC ZS-2013-0176: Attachment 1 - Supplemental Information Attachment 1-Supplemental Information (continued)

10. Detail Sludges/Bottoms: When generated and process requirements.
11. List Prohibited Waste Constituents: Specific details regarding no materials capable of detonation or explosive decomposition. Also no radioactive waste capable of generating toxic gases, vapors, fumes, or pyrophoric shall be shipped for disposal.
12. Detail Mixed Waste Generation - Control and Treatment for disposal.
13. Detail Waste Characterization: Requirement to characterize waste in accordance with 10CFR61.55.
14. Detail PCP Document and Procedure Control - Establishes the requirements for the PCP records review, changes to the PCP, and retention of records for 10 years past license termination.
15. Elimination of the quarterly PCP review of the solid waste system and only perform the review/verification annually.
16. Submittal of the annual radioactive effluent report on May Ist of each year.
17. Establish Attachment 2 - Minimum Review Criteria for Solidification Process
18. Establish Attachment 3 - Waste Types suitable for dewatering: requirements when dewatering resins and activated hardware/metal.
19. Establish Attachment 4 - Prohibited Materials - specifically for loading a HIC.

Summary of Changes: 2013: ZS-WM-123 Rev 2:

This revision has been included though the effective date was in 2013 because the Process Control Program solid waste data included in this report is based on Rev 2.

Updated list of references to revision of regulatory guide revisions as described in the ODCM. Updated references to reflect new procedural guidance. Edited wording of reporting requirements to reflect requirements of Rev 1 of Regulatory Guide 1.21.

Two minor editorial changes.

ZionSolutions, LLC ZS-2013-0176: Attachment 2 - Effluent & Waste Disposal Summary Attachment 2.1 - Unit 1 Gaseous Releases GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit 1 Vent Stack REPORT FOR 2012 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 <LLD <LLD <LLD <LLD <LLD
2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Tritium
1. Total Release Ci 1.32E-02 1.42E-02 9.OOE-03 1.28E-02 4.92E-02
2. Avg. Release Rate uCi/sec 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases <LLD <LLD <LLD <LLD <LLD Iodines <LLD <LLD <LLD <LLD <LLD Particulates Half Life >= 8 days<LLD <LLD <LLD <LLD <LLD Tritium H-3 Ci 1.32E -02 1.42E-02 9. OOE-03 1.28E-02 4. 92E-02 Totals for Period Ci 1. 32E-02 1.42E-02 9. OOE-03 1.28E-02 4. 92E-02 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR No Batch Releases.

LLD values are listed on attachment 2.5

ZionSolutions, LLC ZS-2013-0176: Attachment 2 - Effluent & Waste Disposal Summary Attachment 2.2 - Unit 2 Gaseous Releases GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit 2 Vent Stack REPORT FOR 2012 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 <LLD <LLD <LLD <LLD <LLD
2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Tritium
1. Total Release Ci 1.32E-02 1.42E-02 9.OOE-03 1.28E-02 4.92E-02
2. Avg. Release Rate uCi/sec 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR Fission and Activation Gases <LLD <LLD <LLD <LLD <LLD Iodines <LLD <LLD <LLD <LLD <LLD Particulates Half Life >= 8 days<LLD <LLD <LLD <LLD <LLD Tritium H-3 Ci 1.32E-02 1.42E-02 9.OOE-03 1.28E-02 4.92E-02 Totals for Period Ci 1.32E-02 1.42E-02 9.OOE-03 1.28E-02 4.92E-02 GASEOUS EFFLUENTS - GROUND RELEASES - BATCH MODE REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR No Batch Releases.

LLD values are listed on attachment 2.5

ZionSolutions, LLC ZS-2013-0176: Attachment 2 - Effluent & Waste Disposal Summary Attachment 2.3 - Liquid Effluent Releases LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2012 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 <LLD <LLD <LLD <LLD <LLD
2. Avg. Release Rate uCi/sec <LLD <LLD <LLD <LLD <LLD Volume of liquid waste liters 2.63E+06 3.56E+06 3.12E+06 2.97E+06 1.23E+07 Volume of dil. water liters 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 LIQUID EFFLUENTS - BATCH MODE REPORT FOR 2012 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR No batch releases.

LLD values are listed in attachment 2.5

ZionSolutions, LLC ZS-2013-0176: Attachment 2 - Effluent & Waste Disposal Summary Attachment 2.4 - Direct Radiation 2012 40cfrl90 evaluation of Dose From container ESUU # 500031 _

  • I
  • Survey's indicate 40'_Sealand was moved between 9-12 to 9-24 of 2012 I jThe first working day after 9-12-12 was 9-13-12 and dose will be calculated as of this date since Survey on 9-24-12 does not indicate the survey was performed when the sealand was moved _

'only what the current survey results are. * ,

,Days from 9-12-12to 12-31-12 - __i ___

_12/31/121 . . . . . _. I___

-1 9/13/121 i -- /_...

i 1091days : - I I J Exposure rate based on microshield, 8.OOE-03!mR/hr. I _ __....

..... ,At real person location on beach area East of RRA 258' From sealand.____ . _i ..

  • Occupancy factor:

-- ] ] t I

II !I 1 1 1 1200ihrs/y,(1200hrs/8760hrs)

___

___ __

_

8.OOE-O3!mRx 0.O6lmRemx 1 24 hrx . . _io91daysx,

.. 12000hrs-- I2.75E+00!mrem

...-. I I

I

_-

h r. mR I I I day

__ __

_ý_--

_ _ i 876010hrs

_ _ _

I_ _ _ _ _

Dose assigned to each unit:

Unit 1: 1.38E+00 mrem Unit 2: 1.38E+00 mrem

ZionSolutions, LLC ZS-2013-0176: Attachment 2 - Effluent & Waste Disposal Summary Attachment 2.5-LLD's Liquid Gaseous Isotope LLD Isotope LLD (uCi/ml) (uCi/ml)

Tritium <1.0OE-05 Tritium <I.00E-06 Ar-41 3.75E-08 Ar-41 1.OOE-08 Mn-54 3.49E-08 Kr-85 2.51E-06 Co-58 3.43E-08 Kr-85m 9.14E-09 Co-60 4.27E-08 Kr-87 1.67E-08 Zn-65 7.58E-08 Kr-88 2.58E-08 Kr-85 6.78E-06 Xe-131m 3.53E-07 Kr-85m 3.18E-08 Xe-133 2.48E-08 Kr-87 5.47E-08 Xe-133m 6.48E-08 Kr-88 9.70E-08 Xe-135 8.03E-09 Nb-95 2.82E-08 Xe-135m 1.61E-08 Zr-95 5.37E-08 Xe-138 3.25E-08 Xe-131m 1.33E-06 Gross Beta <I.OE-06 Xe-133 9.64E-08 Gross Alpha <1.GE-11 Xe-133m 2.36E-07 Cs-134 3.55E-08 Xe-135 3.16E-08 Xe-135m 4.14E-08 Cs-137 3.40E-08 Xe-138 1.14E-07 Ce-141 5.07E-08 Ce-144 2.21E-07 Gross Alpha <1.OE-07 Notes:

Gross Beta/Gross Alpha/Tritium: LLD's are calculated each week during composite sample analysis and verified to be less than LLD required by ODCM Tech Spec limit.

The same detector was not used for each sample analysis. Therefore the most limiting LLD of each different instrument for each isotope are the values listed above.

ZionSolutions, LLC ZS-2013-0176: Attachment 2 - Effluent & Waste Disposal Summary Attachment 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%

SamDle 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-2013-0176: Attachment 3 - Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

1. Types of Waste Total Total Est. Total Types of Waste Quantity Activity Period Error %

(m) (Ci)

a. Spent resins, filter sludges, evaporator bottoms, etc. 5.83E+00 9.48E+00 2012 2.50E+01
b. Dry compressible waste, contaminated equip, etc. 2.16E+03 2.23E+01 2012 2.50E+01
c. Irradiated components, control rods, etc. 4.96E+01 1.22E+03 2012 2.50E+01
d. Other (describe) 0.OOE+00 0.OOE+00 2012 0.OOE+00

ZionSolutions, LLC ZS-2013-0176: Attachment 3 - Solid Waste and Irradiated Fuel Shipments Attachment 3 - Solid Waste and Irradiated Fuel Shipments (continued)

2. Estimate of major nuclide composition (by waste type)

Major Waste Type a. Waste Type b. Waste Type c. Waste Type d.

Nuclide Resins, sludges DAW contam. Irradiated Other %

Composition bottoms % equipment % components %

Ag-1 10m O.OOE+00 3.71E-06 0.OOE+00 0 .OOE+OO Am-241 6.52E-04 6.38E-02 8.16E-06 0.OOE+00 C-14 2.80E-03 1.83E-01 4.94E-02 0.OOE+OO Ce-144 6.92E-03 4.72E-0 1 0.OOE+00 0.OOE+00 Cm-242 1.54E-05 1.24E-01 1.40E-08 O.OOE+00 Cm-243 3.27E-04 2.29E-02 4.67E-06 0.OOE+00 Cm-244 O.OOE+00 O.OOE+00 4.60E-06 O.OOE+OO Co-60 1.62E+01 2.34E+01 5.45E+01 0.OOE+00 Cs-134 0.OOE+00 0.00E+00 7.17E-06 O.OOE+00 Cs-137 1.70E+00 3.03E+01 2.11E-03 O.OOE+0O Fe-55 5.95E-02 1.24E+01 9.49E+00 0.OOE+0O H-3 1.08E-02 2.29E-01 1.20E-01 O.OOE+00 1-129 2.86E-04 2.59E-02 9.24E-07 0.OOE+00 Mn-54 0.OOE+00 O.OOE+00 3.49E-03 0.OOE+O0 Nb-94 3.61 E-02 7.50E-02 8.59E-04 0.OOE+00 Ni-59 9.62E-01 4.94E-0 1 3.05E-01 O.OOE+O0 Ni-63 8.09E+01 2.59E+01 0.OOE+00 O.OOE+00 Ni-63am 0.OOE+00 0.OOE+00 3.56E+O1 O.OOE+00 Pu-238 1.57E-04 4.94E+00 5.0 1E-06 O.OOE+00 Pu-239 6.67E-05 2.72E-02 1.23E-06 0.OOE+00 Pu-240 O.OOE+00 O.OOE+00 1.23E-06 0.OOF+00 Pu-241 7.89E-02 1.93E-01 3.52E-05 0.OOE+00 Pu-242 1.11E-05 5.43E-03 1.55E-08 O.OOE+O0 Ra-226 0.OOE+00 0.OOE+00 8.08E-05 0.OOE+00 Sb-125 6.88E-03 3.05E-01 5.47E-05 O.OOE+OO Sr-89 8.84E-04 1.15E-01 O.OOE+00 0.OOE+0O Sr-90 8.29E-02 2.48E-01 3.03E-05 0.OOE+0O Tc-99 1.72E-03 2.43E-01 1.48E-04 0.OOE+O0 Zn-65 5.25E-03 2.49E-0 1 O.OOE+00 0.OOE+00

ZionSolutions, LLC ZS-2013-0176: Attachment 3 - Solid Waste and Irradiated Fuel Shipments Attachment 3 - Solid Waste and Irradiated Fuel Shipments (continued)

(continued)

3. Solid Waste Disposition Number of shipments Mode of Transportation Destination 45 Truck Clive CWF 33 Rail Clive CWF I Truck WCS Texas B. Irradiated Fuel Shipments (disposition)

Number of shipments Mode of Transportation Destination 0 N/A N/A C. Changes to the Process Control Program:

Changes to the PCP are included in Attachment 7.

ZionSolutions, LLC ZS-2013-0176: Attachment 4 - Radiological Impact on Man Attachment 4.1 - 40 CFR 190 Compliance Summary UNIT I & 2 (DOCKET Numbers 50-295 & 50-304)

EXECUTIVE

SUMMARY

A review of 2012 effluent data indicates that the activity released from the station was far below any regulatory limit. There was no noble gas released in 2012. This trend can be attributed to the shutdown of units since 1996 and 1997.

Airborne Dose to Maximally Exposed Dose to Maximally Exposed Receptor from Unit 1 Receptor from Unit 2 Gamma Air 0.OOE+00 mrad 0.OOE+00 mrad Beta Air 0.OOE+00 mrad 0.OOE+00 mrad Total Body 0.OOE+00 mrem 0.OOE+00 mrem Skin 0.OOE+00 mrem 0.OOE+00 mrem Organ 6.25E-05 mrem (Child Liver) 6.25E-05 mrem (Child Liver)

Aquatic There was NO Aquatic release of radioactivity from Zion Station during 2012:

Dose to Maximally Exposed Dose to Maximally Exposed Receptor (Any) from Unit 1 Receptor (Any) from Unit 2 Total Body 0 mrem 0 mrem Organ 0 mrem 0 mrem Direct Radiation Dose to Maximally Exposed Dose to Maximally Exposed Member of the public from Member of the public from Unit Unit 1 2 Total Body 1.38E+00mrem 1.38E+00mrem

4 ZionSolutions, LLC ZS-2013-0176: Attachment 4 - Radiological Impact on Man Attachment 4.2 - Unit I I. Unit 1 (Docket Number 50-295)

A. 10 CFR20 & 40CFR190 Compliance Assessment: The demonstration of compliance with 40CFRI 90 will be used to demonstrate compliance with 1 OCFR20.

1. Total Effective Dose Equivalent 1.38E+00 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 5.52E-02 %
5.  % Max exposed organ 5.52E-02 % child liver (1.84E-02 % thyroid)

Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total TEDE 1.68E-05 1.81E-05 1.15E-05 1.38E+00 1.38E+00 mrem mrem mrem mrem mrem B. Maximally Exposed Receptor:

1. Airborne Yearly limit Total Dose  % of Qtr Obj I1 Qtr 2nd Qtr 3P1Qtr 41hQtr 10CFR 50 2012 Yearly App. I limit Gamma air (mrad) 5.0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0 0.OOE+00 O.OOE+00 Beta Air (mrad) 10.0 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 20.0 O.OOE+00 O.OOE+00 Total Body (mrem) 7.5 1.68E-05 1.81E-05 1.15E-05 1.63E-05 15.0 6.25E-05 4.17E-06 Skin (mrem) 7.5 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 15.0 0.OOE+00 O.OOE+00 Organ (mrem) 7.5 1.68E-05 1.81E-05 1.15E-05 1.63E-05 15.0 6.25E-05 4.17E-06 Critical Organ Child liver Child liver Child liver Child liver Child liver Child liver
2. Aquatic Yearly limit Total Dose %of Qtr Obj 1" Qtr 2nd Qtr 3r" Qtr 411Qtr IOCFR 50 2012 Yearly App. I limit Total Body (mrem) 1.5 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.0 0.OOE+00 0.OOE+00 Organ (mrem) 5.0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 10.0 0.OOE+00 0.OOE+00 Critical Organ NA NA NA NA NA NA
3. Direct

% of Qtr Obj I " Qtr 2d Qtr Pr Qtr 41 Qtr Yearly limit 40CFRI90 Total 2012 Dose Yearly limit Total body (mrem) 6.25 0.OOE+00 0.OOE+00 0.OOE+00 1.38E+00 25.0 1.38E+00 5.52E-02

ZionSolutions, LLC ZS-2013-0176: Attachment 4 - Radiological Impact on Man Attachment 4.3 - Unit 2 II. Unit 2 (Docket Number -304)

C. 10 CFR20 & 40CFRI90 Compliance Assessment: The demonstration of compliance with 40CFRI190 will be used to demonstrate compliance with 10CFR20.

6. Total Effective Dose Equivalent 1.38E+00 mrem/year
7. 40 CFR 190 Whole body limit 25 mrem/year
8. 40 CFR 190 Max exposed organ 25 mrem (75 mrem thyroid)
9.  % Whole body limit 5.52E-02 %
10.  % Max exposed organ 5.52E-02 % child liver (1.84E-02 % thyroid)

Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total TEDE 1.68E-05 1.81E-05 1.15E-05 1.38E+00 1.38E+00 mrem mrem mrem mrem mrem D. Maximally Exposed Receptor:

4. Airborne Qtr Obj I "Qtr 2 d Qtr 3P Qtr 4" Qtr Yearly limit Total Dose  % of 10CFR 50 2012 Yearly App. I limit Gamma air (mrad) 5.0 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 10.0 0.OOE+00 0.00E+00 Beta Air Inrad) 10.0 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 20.0 0.00E+00 0.00E+00 Total Body (mrem) 7.5 1.68E-05 1.81E-05 1.15E-05 1.63E-05 15.0 6.25E-05 4.17E-06 Skin (mrem) 7.5 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 15.0 0.00E+00 0.00E+00 Organ (mrem) 7.5 1.68E-05 1.81E-05 1.15E-05 1.63E-05 15.0 6.25E-05 4.17E-06 Critical Organ I Child liver Child liver Child liver Child liver I Child liver Child liver 5.
6. Direct Qtr Obj IP "Qtr 2[ Qtr 3' Qtr 4 Qtr Yearly limit Total Dose %of 40CFR190 2012 Yearly limit Total body (mrem) 6.25 0.OOE+00 0.OOE+00 0.OOE+00 1.38E+00 25.0 1.38E+00 5.52E-02

ZionSolutions, LLC ZS-2013-0176: Attachment 4 - Radiological Impact on Man Attachment 4.4 - Combined 40 CFR 190 Report III. Combined 40CFR 190 Report:

40CFR190 URANIUM FUEL CYCLE DOSE REPORT GAS ANNUAL DOSE

SUMMARY

Year .................. 2012 From Unit ................ 1 To Unit ................... 2 Coefficient Type ....... Hist' orical Gas Receptor ............ 5 Coimposite 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 T.Spec %

Period Group Organ (mrem) Period Limit of Limit Limit of Limit Quarter 1 CHILD LIVER 5 Quarter 5.63E+00 5.96E-04 7.50E+00 4.47E-04 Quarter 2 CHILD LIVER 3.35E-0 5 Quarter 5.63E+00 6.43E-04 7.50E+00 4.82E-04 3.62E-0 5 Quarter 5.63E+00 4.07E-04 7.50E+00 3.05E-04 Quarter 3 CHILD LIVER

2. 29E-0 Quarter 4 CHILD LIVER 3.26E-0 5 Quarter 5.63E+00 5.79E-04 7.50E+00 4.34E-04 Annual CHILD LIVER 1.25E-0 4 Annual 1.13E+01 1.11E-03 1.50E+01 8.35E-04

=== MAXIMUM PERIOD DOSE TO LIMIT (Tot Body))

Dose Age Dose Limit Admin Admin  % T.Spec T.Spec %

Period Group Organ (mrem) Period Limit of Limit Limit of Limit Quarter 1 CHILD TBODY - Quarter 5.25E+00 6.39E-04 7.505+00 4.47E-04 Quarter 2 CHILD TBODY 3. 35E-0 5 Quarter 5.25E+00 6.89E-04 7.50E+00 4.82E-04 3.62E-0 Quarter 3 CHILD TBODY 5 Quarter 5.25E+00 4.36E-04 7.50E+00 3.05E-04 2.29E-0 Quarter 4 CHILD TBODY 3.26E-0 5 Quarter 5.25E+00 6.20E-04 7.50E+00 4.34E-04 Annual CHILD TBODY 1.25E-0 4 Annual 1.05E+01 1.19E-03 1.50E+01 8.35E-04

ZionSolutions, LLC ZS-2013-0176: Attachment 4 - Radiological Impact on Man Attachment 4.4 - Radiological Impact on Man (continued) 40CFR190 URANIUM FUEL CYCLE DOSE REPORT COMBINED MAXIMUM ANNUAL DOSE

SUMMARY

Year ................... 2012 From Unit .............. 1 To Unit ................ 2 Liquid Receptor .......

Coefficient Type ...... Historical Gas Receptor .......... 5 Composite Crit. Receptor - IP Distance (meters) ..... 0.00 Compass Point ......... NA

=== MAXIMUM PERIOD DOSE TO LIMIT (2Any Organ)

Dose Age Dose Limit Percent Period Group Organ (mrem) Period Limit of Limit Quarter 1 CHILD LIVER 6.25E+00 5.37E-04

3. 35E-05 Quarter Quarter 2 CHILD LIVER 6.25E+00 5.79E-04 3.62E-05 Quarter 6.25E+00 3.79E-04 Quarter 3 CHILD LIVER
2. 29E-05 Quarter Quarter 4 CHILD LIVER 6.25E+00 5.21E-04 3.26E-05 Quarter Annual CHILD LIVER 1.25E-04 Annual 2.50E+01 5.01E-04

=== MAXIMUM PERIOD DOSE TO LIMIT (Irot Body))

Dose Age Dose Limit Percent Period Group Organ (mrem) Period Limit of Limit Quarter 1 CHILD TBODY 6.25E+00 5.37E-04 3.35E-05 Quarter Quarter 2 CHILD TBODY 6.25E+00 5.79E-04 3.62E-05 Quarter Quarter 3 CHILD TBODY 6.25E+00 3.79E-04

2. 29E-05 Quarter Quarter 4 CHILD TBODY 6.25E+00 5.21E-04 3.26E-05 Quarter Annual CHILD TBODY 1.25E-04 Annual 2.50E+01 5.01E-04