ML13133A345

From kanterella
Revision as of 22:23, 11 May 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
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 H
ZionSolutions
To:
Document Control Desk, Office of Nuclear Reactor Regulation, NRC/FSME
References
ZS-2013-0176
Download: ML13133A345 (22)
v • d • e


Text

ZIONSOLUTIONS, An 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 1 st 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,&y B uchard 0 Decommissioning Plant Manager ZionSolutions, LLC 101 Shiloh Boulevard, Zion s IL 60099 (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 Senior VP and General Manager ZionSolutions, LLC 101 Shiloh Boulevard Zion, IL 60099 (Cover letter only, no attachments)

Patrick Thurman, Esq.VP Regulatory Affairs, Licensing

&Document Control ZionSolutions, LLC 101 Shiloh Boulevard Zion, IL 60099 (Cover letter only, no attachments)

Gary Bouchard VP Engineering, Ops & Nuclear Security and Decommissioning Plant Manager ZionSolutions, LLC 101 Shiloh Boulevard Zion, IL 60099 (Cover letter only, no attachments)

Alan Parker President Projects Group EnergySolutions 1009 Commerce Park Drive, Ste. 100 Oak Ridge, TN 37830 (Cover letter only, no attachments)

John Christian President of Logistics, Processing and Disposal (LP& D) Group EnergySolutions 1750 Tysons Boulevard, Suite 1500 Mclean, VA 22102 (Cover letter only, no attachments)

Dan Shrum Senior VP Regulatory Affairs EnergySolutions 423 West 300 South, Ste. 200 Salt Lake City, UT 84101 (Cover letter only, no attachments)

Russ Workman General Counsel EnergySolutions 423 West 300 South, Ste. 200 Salt Lake City, UT 84101 (Cover letter only, no attachments)

Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, IL 62704 (Cover letter only, no attachments)

Kent McKenzie Emergency Management Coordinator Lake County Emergency Management Agency 1303 N. Milwaukee Avenue Libertyville, IL 60048-1308 (Cover letter only, no attachments)

Regional Administrator U.S. NRC, Region III 2443 Warrenville Road Lisle, IL 60532-4352 John E. Matthews Morgan, Lewis & Bockius LLP 1111 Pennsylvania Avenue, NW 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. 1 OCFR50 Organ: 7.5 mrem/quarter, 15 mrem/year c. Liquid Effluents:

i. 1OCFR50 Whole body: 1.5 mrem/quarter, 3mrem/year ii. 1OCFR 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 1OCFRPart 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 1OCFR21, "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., 1OCFR71 and 49CFR173, Subpart I.Step 4.1.9 -Waste classification will meet the requirements of 1OCFR61 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 1OCFR21 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 Fission and Activation

1. Total Release 2. Avg. Release Rate Units Gases Ci uCi/sec QTR 1 QTR 2 QTR 3 QTR 4 YEAR<LLD<LLD Iodine-131
1. Total Release Ci <LLD 2. Avg. Release Rate uCi/sec <LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD Particulates Half Life 1. Total Release 2. Avg. Release Rate>= 8 days Ci <LLD uCi/sec <LLD Tritium 1. Total Release Ci 2. Avg. Release Rate uCi/sec 1.32E-02 1.42E-02 9.OOE-03 1.28E-02 4.92E-02 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 GASEOUS EFFLUENTS

-GROUND RELEASES -CONTINUOUS MODE REPORT FOR 2012 Fission and Activation Iodines Particulates Half Life Tritium H-3 Totals for Period Units QTR 1 Gases <LLD<LLD>= 8 days<LLD Ci 1.32E QTR 2<LLD<LLD<LLD 1.42E-02 1.42E-02 QTR 3<LLD<LLD<LLD 9. OOE-03 9. OOE-03 QTR 4<LLD<LLD<LLD 1.28E-02 1.28E-02 YEAR<LLD<LLD<LLD 4. 92E-02 4. 92E-02-02 1. 32E-02 Ci GASEOUS EFFLUENTS

-GROUND RELEASES -BATCH MODE REPORT FOR 2012 Units No Batch Releases.QTR 1 QTR 2 QTR 3 QTR 4 YEAR 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 Fission and Activation

1. Total Release 2. Avg. Release Rate Units QTR 1 Gases Ci <LLD uCi/sec <LLD QTR 2 QTR 3 QTR 4 YEAR Iodine-131
1. Total Release Ci <LLD 2. Avg. Release Rate uCi/sec <LLD Particulates Half Life >= 8 days 1. Total Release Ci <LLD 2. Avg. Release Rate uCi/sec <LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD Tritium 1. Total Release Ci 2. Avg. Release Rate uCi/sec 1.32E-02 1.42E-02 0.OOE+00 0.OOE+00 9.OOE-03 1.28E-02 4.92E-02 0.OOE+00 0.OOE+00 0.OOE+00 GASEOUS EFFLUENTS

-GROUND RELEASES -CONTINUOUS MODE REPORT FOR 2012 Fission and Activation Iodines Particulates Half Life Tritium H-3 Totals for Period Units QTR 1 Gases <LLD<LLD>= 8 days<LLD Ci 1.32E-02 Ci 1.32E-02 QTR 2<LLD<LLD<LLD QTR 3<LLD<LLD<LLD QTR 4<LLD<LLD<LLD 1.28E-02 1.28E-02 YEAR<LLD<LLD<LLD 1.42E-02 1.42E-02 9.OOE-03 9.OOE-03 4.92E-02 4.92E-02 GASEOUS EFFLUENTS

-GROUND RELEASES -BATCH MODE REPORT FOR 2012 No Batch Releases.Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR 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 Fission and Activation

1. Total Release 2. Avg. Release Rate Iodine-131
1. Total Release 2. Avg. Release Rate Particulates Half Life 1. Total Release 2. Avg. Release Rate Units QTR 1 Gases Ci <LLD uCi/sec <LLD Ci <LLD uCi/sec <LLD>= 8 days Ci <LLD uCi/sec <LLD QTR 2 QTR 3 QTR 4 YEAR<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD<LLD Volume of liquid waste liters 2.63E+06 Volume of dil. water liters 0.OOE+00 3.56E+06 3.12E+06 2.97E+06 1.23E+07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 LIQUID EFFLUENTS

-BATCH MODE REPORT FOR 2012 No batch releases.Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR 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: I 1200ihrs/y,(1200hrs/8760hrs)

___ _-- ] ] t II !I 1 1 1 ___ __I 8.OOE-O3!mRx 0.O6lmRemx 1 24 hrx .... ...-. _io91daysx, 12000hrs--

I2.75E+00!mrem I h r. mR I day _ý_-- 876010hrs I_- I I _ _ _ _ _ _ i 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 Isotope LLD (uCi/ml)Tritium <1.0OE-05 Ar-41 3.75E-08 Mn-54 3.49E-08 Co-58 3.43E-08 Co-60 4.27E-08 Zn-65 7.58E-08 Kr-85 6.78E-06 Kr-85m 3.18E-08 Kr-87 5.47E-08 Kr-88 9.70E-08 Nb-95 2.82E-08 Zr-95 5.37E-08 Xe-131m 1.33E-06 Xe-133 9.64E-08 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 Gaseous Isotope LLD (uCi/ml)Tritium <I.00E-06 Ar-41 1.OOE-08 Kr-85 2.51E-06 Kr-85m 9.14E-09 Kr-87 1.67E-08 Kr-88 2.58E-08 Xe-131m 3.53E-07 Xe-133 2.48E-08 Xe-133m 6.48E-08 Xe-135 8.03E-09 Xe-135m 1.61E-08 Xe-138 3.25E-08 Gross Beta <I.OE-06 Gross Alpha <1.GE-11 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 Calibration Error Counting Statistics Error SamDle Volume Error 5%10%17%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 Am-241 C-14 Ce-144 Cm-242 Cm-243 Cm-244 Co-60 Cs-134 Cs-137 Fe-55 H-3 1-129 Mn-54 Nb-94 Ni-59 Ni-63 Ni-63am Pu-238 Pu-239 Pu-240 Pu-241 Pu-242 Ra-226 Sb-125 Sr-89 Sr-90 Tc-99 Zn-65 O.OOE+00 6.52E-04 2.80E-03 6.92E-03 1.54E-05 3.27E-04 O.OOE+00 1.62E+01 0.OOE+00 1.70E+00 5.95E-02 1.08E-02 2.86E-04 0.OOE+00 3.61 E-02 9.62E-01 8.09E+01 0.OOE+00 1.57E-04 6.67E-05 O.OOE+00 7.89E-02 1.11E-05 0.OOE+00 6.88E-03 8.84E-04 8.29E-02 1.72E-03 5.25E-03 3.71E-06 6.38E-02 1.83E-01 4.72E-0 1 1.24E-01 2.29E-02 O.OOE+00 2.34E+01 0.00E+00 3.03E+01 1.24E+01 2.29E-01 2.59E-02 O.OOE+00 7.50E-02 4.94E-0 1 2.59E+01 0.OOE+00 4.94E+00 2.72E-02 O.OOE+00 1.93E-01 5.43E-03 0.OOE+00 3.05E-01 1.15E-01 2.48E-01 2.43E-01 2.49E-0 1 0.OOE+00 8.16E-06 4.94E-02 0.OOE+00 1.40E-08 4.67E-06 4.60E-06 5.45E+01 7.17E-06 2.11E-03 9.49E+00 1.20E-01 9.24E-07 3.49E-03 8.59E-04 3.05E-01 0.OOE+00 3.56E+O1 5.0 1E-06 1.23E-06 1.23E-06 3.52E-05 1.55E-08 8.08E-05 5.47E-05 O.OOE+00 3.03E-05 1.48E-04 O.OOE+00 0 .OOE+OO 0.OOE+00 0.OOE+OO 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+OO 0.OOE+00 O.OOE+00 O.OOE+0O 0.OOE+0O O.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOF+00 0.OOE+00 O.OOE+O0 0.OOE+00 O.OOE+OO 0.OOE+0O 0.OOE+0O 0.OOE+O0 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)

3. Solid Waste Disposition (continued)

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 OCFR20.1.2.3.Total Effective Dose Equivalent 40 CFR 190 Whole body limit 40 CFR 190 Max exposed organ 1.38E+00 mrem/year 25 mrem/year 25 mrem (75 mrem thyroid)5.52E-02 %5.52E-02 % child liver (1.84E-02

% thyroid)4. % Whole body limit 5. % Max exposed organ Quarter 1 TEDE 1.68E-05 mrem Quarter 2 1.81E-05 mrem Quarter 3 1.15E-05 mrem Quarter 4 1.38E+00 mrem Total 1.38E+00 mrem B. Maximally Exposed Receptor: 1. Airborne 2.3.Yearly limit Total Dose % of Qtr Obj I 1 Qtr 2nd Qtr 3P1 Qtr 41h Qtr 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 Aquatic Yearly limit Total Dose %of Qtr Obj 1 " Qtr 2nd Qtr 3r" Qtr 411 Qtr 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 Direct% of Qtr Obj I " Qtr 2d Qtr Pr Qtr 41 Qtr Yearly limit Total Dose Yearly 40CFRI90 2012 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 1 OCFR20.6. Total Effective Dose Equivalent

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

% thyroid)Quarter 1 TEDE 1.68E-05 mrem Quarter 2 1.81E-05 mrem Quarter 3 1.15E-05 mrem Quarter 4 1.38E+00 mrem Total 1.38E+00 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'Gas Receptor ............

5 Coi Distance (meters) .....Compass Point ...........

NA orical mposite Crit. Receptor -IP 0.00=== MAXIMUM PERIOD DOSE Dose Age Period Group Organ Quarter 1 CHILD LIVER Quarter 2 CHILD LIVER Quarter 3 CHILD LIVER Quarter 4 CHILD LIVER Annual CHILD LIVER=== MAXIMUM PERIOD DOSE Dose Age Period Group Organ Quarter 1 CHILD TBODY Quarter 2 CHILD TBODY Quarter 3 CHILD TBODY Quarter 4 CHILD TBODY Annual CHILD TBODY TO LIMIT Dose (mrem)3.35E-0 3.62E-0 2. 29E-0 3.26E-0 1.25E-0 TO LIMIT Dose (mrem)3. 35E-0 3.62E-0 2.29E-0 3.26E-0 1.25E-0 (Any Organ)Limit Admin Admin % T.Spec T.Spec %Period Limit of Limit Limit of Limit 5 Quarter 5.63E+00 5.96E-04 7.50E+00 4.47E-04 5 Quarter 5.63E+00 6.43E-04 7.50E+00 4.82E-04 5 Quarter 5.63E+00 4.07E-04 7.50E+00 3.05E-04 5 Quarter 5.63E+00 5.79E-04 7.50E+00 4.34E-04 4 Annual 1.13E+01 1.11E-03 1.50E+01 8.35E-04 (Tot Body))Limit Admin Admin % T.Spec T.Spec %Period Limit of Limit Limit of Limit-Quarter 5.25E+00 6.39E-04 7.505+00 4.47E-04 5 Quarter 5.25E+00 6.89E-04 7.50E+00 4.82E-04 5 Quarter 5.25E+00 4.36E-04 7.50E+00 3.05E-04 5 Quarter 5.25E+00 6.20E-04 7.50E+00 4.34E-04 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 ...................

From Unit ..............

To Unit ................

Liquid Receptor .......Coefficient Type ......Gas Receptor ..........

Distance (meters) .....Compass Point .........2012 1 2 Historical 5 Composite Crit. Receptor -IP 0.00 NA=== MAXIMUM PERIOD DOSE Dose Age Period Group Organ Quarter 1 CHILD LIVER Quarter 2 CHILD LIVER Quarter 3 CHILD LIVER Quarter 4 CHILD LIVER Annual CHILD LIVER=== MAXIMUM PERIOD DOSE Dose Age Period Group Organ Quarter 1 CHILD TBODY Quarter 2 CHILD TBODY Quarter 3 CHILD TBODY Quarter 4 CHILD TBODY Annual CHILD TBODY TO LIMIT (2 Dose (mrem)3. 35E-05 3.62E-05 2. 29E-05 3.26E-05 1.25E-04 TO LIMIT (I Dose (mrem)3.35E-05 3.62E-05 2. 29E-05 3.26E-05 1.25E-04 Any Organ)Limit Period Quarter Quarter Quarter Quarter Annual Percent Limit of Limit 6.25E+00 5.37E-04 6.25E+00 5.79E-04 6.25E+00 3.79E-04 6.25E+00 5.21E-04 2.50E+01 5.01E-04 rot Body))Limit Period Quarter Quarter Quarter Quarter Annual Percent Limit of Limit 6.25E+00 5.37E-04 6.25E+00 5.79E-04 6.25E+00 3.79E-04 6.25E+00 5.21E-04 2.50E+01 5.01E-04

Retrieved from "https://kanterella.com/w/index.php?title=ML13133A345&oldid=1606490"