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Vermont Yankee - Calculation ENTGVY036-CALC-001, Revision 1, Curie Limits in Support of an ISFSI-Only EAL Scheme at Plant
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CALCNO. ENTGVY036-CALC-001 0 ENERCON CALCULATION COVER SHEET REVISION 1 tArt'"./r*1rt>-I**(1, PAGE NO. 1 of 55 Curie Limits in Support of an ISFSl-Only EAL Client: ENTERGY Title: Scheme at VYNPS Project Identifier:

ENTGVY036 Item Cover Sheet Items Yes No 1 Does this calculation contain any open assumptions, including preliminary D 1'81 information, that require cqnfirmation? (If YES, identify the assumptions.)

2 Does this calculation serve as an *Alternate Calculation"? (If YES, identify the design 0 1'81 verified calculation.)

Design Verified Calculation No. 3 Does this calculation supersede an existing Calculation? (If YES, identify the design D 1'81 verified calculation.)

Superseded Calculation No. Scope of Revision:

Initial Issue Revision Impact on Results.:

Initial Issue Study Calculation D Final Calculation

[8] Safety-Related D Non-Safety-Related l8J (Print Name and Sign) Originators:

-;,..;.;

Dominic Napolitano, Ph. D Date: r: 'bp Oig!tally by Drew Blackwell (RG1.109.xlsm)

Date /)/Jdl 15:59:40,<<00' Design Verifier 1 (Reviewer if NSR): Caleb Trainor Date: .-*

'2*-:p***

c'" ... i* ......

Approver:

Curt Lindner Date: Curt D-lf'1'11.G-l.Ul41t*1'°'W Note 1: For non-safety-related calculation, design verification can be substituted by review. CSP 3.03 Attachment A Rev.2 CALCULATION CALC NO. ENTGVY036-CALC-001 Q ENERCON REVISION STATUS SHEET Excellem:e-_fvery proj"ect.

Every day. REVISION 1 CALCULATION REVISION STATUS REVISION DATE DESCRIPTION 0 4/12/2017 Initial Issue 1 See Signoff Page Resolved roundoff issue in Tables 2.;.1, 2-2, 9-1 and 9-2, and added clarification in Examples PAGE REVISION STATUS PAGE NO. REVISION PAGE NO. REVISION 1-55 0 10,29,37,53-55 1 APPENDIX/ATTACHMENT REVISION STATUS APPENDIX NO. NO.OF REVISION ATTACHMENT NO.OF REVISION PAGES NO. NO. PAGES NO. A 10 0 B 8 0 c 4 0 CSP 3.03 Attachment B Page 2 of 53 Rev. 2 Q ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at Excellence-Every project. Every day. WNPS REVISION 1 Table of Contents 1.0 Introduction

.....................................................................................................................

6 1.1 Purpose and Scope .............................................................................................

6 1.2 Discussion

...........................................................................................................

6 2.0 Summary of Results and Conclusions

.............................................................................

8 3. O References

....................................................................................................................

11 4.0 Assumptions

..................................................................................................................

12 4.1 Material Activities

...............................................................................................

12 4.2 Initiating Event ...................................................................................................

15 4. 3 Release Pathway ...............................................................................................

15 4.4 Release Fractions

..............................................................................................

15 4.5 Activity ...............................................................................................................

16 4.6 Applicability

........................................................................................................

16 5.0 Design Inputs ................................................................................................................

16 5.1 Shutdown Date ..................................................................................................

16 5.2 Dispersion and Ground Deposition Factors ........................................................

16 5.3 Site Specific Critical Organ Dose Rate Conversion Factors ...............................

17 5.4 Release Time .....................................................................................................

19 5. 5 Release Fractions

..............................................................................................

19 5.6 Conversion Factors Applied ...............................................................................

21 6.0 Methodology

..................................................................................................................

22 6.1 Decayed Activities

..............................................................................................

22 6.2 Determination of Nuclide Activity Limits .............................................................

22 7.0 Calculations

...................................................................................................................

24 7.1 Decayed Activities

..............................................................................................

24 7.2 Activity Limits .....................................................................................................

29 8.0 Computer Software ........................................................................................................

51 9.0 Results and Conclusion

.................................................................................................

51 9.1 Activity Limits Summary .....................................................................................

51 9.2 Examples of Application

.....................................................................................

54 CSP 3.03 Attachment D Page 3 of 55 Rev. 2 D Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ENERCON ISFSl-Only EAL Scheme at . . . fxcellence-f:very project. Every day. VYNPS REVISION 1 Appendix A -Calculation of Additional VYNPS Dose Rate Conversion Factors ......................

A-1 Appendix B -Verification of RG1 .109.xlsm

..............................................................................

B-1 Appendix C -Verification of ENTGVY036-CALC-001.xlsm

.....................................................

C-1 List of Tables Table 2-1 Activity Limits (Ci) for Core Internals Steel Based on Core Shroud Activities

.............

10 Table 2-2 Activity Limits (Ci) for Bio-Shield Concrete Based on Bio-Shield Edge Activities

....... 1 O Table 4-1 Material Activities

......................................................................................................

13 Table 5-1 VYNPS Ground Release Coefficients

........................................................................

17 Table 5-2 Ground Release Site Specific Dose Conversion Factors ...........................................

18 Table 5-3 Release Fractions

.....................................................................................................

20 Table 5-4 Conversion Factors ...................................................................................................

21 Table 7-1 Decayed Activities for Core Shroud (Ci/g) .................................................................

25 Table 7-2 Decayed Activities for Edge of Bio-Shield (Ci/g) ........................................................

27 Table 7-3 Detailed Summary of Curie Limit Calculation for Core Shroud at 2 yr. .......................

30 Table 7-4 Summary of Curie Limit Calculation for Core Shroud at 16 yr ...................................

31 Table 7-5 Summary of Curie Limit Calculation for CS as a Function of Time ............................

33 Table 7-6 Summary of Curie Limit Calculation for VC as a Function of Time ............................

35 Table 7-7 Detailed Summary of Curie Limit Calculation for Bio-shield Inner Edge at 2yr ...........

38 Table 7-8 Detailed Summary of Curie Limit Calculation for Bio-shield Inner Edge at 16 yr ........ 39 Table 7-9 Summary of Curie Limit Calculation for BS-IE as a Function of Time ........................

41 Table 7-10 Summary of Curie Limit Calculation for BS-10 as a Function of Time ......................

43 Table 7-11 Summary of Curie Limit Calculation for BS-20 as a Function of Time .....................

.45 Table 7-12 Summary of Curie Limit Calculation for BS-30 as a Function of Time .....................

.47 Table 7-13 Summary of Curie Limit Calculation for BS-60 as a Function of Time .....................

.49 Table 9-1 Activity Limits (Ci) for Core Internals Steel Based on Core Shroud Activities

.............

53 Table 9-2 Activity Limits (Ci) for Bio-Shield Concrete Based on Bio-Shield Edge Activities

....... 53 Table A-1 RG1.109.xlsm Variables

.........................................................................................

A-3 Table A-2 Additional Dose and Dose Rate Factors for VYNPS .............................................

A-13 Table B-1 GASPAR II Dose Factors -Adult Total Body ..........................................................

B-2 Table B-2 Comparison GASPAR II and RG1.109.xlsm -Adult Total Body Dose Factors ........ B-3 Table B-3 Comparison GASPAR II and RG1.109.xlsm

-Child Bone Dose Factors ................

B-4 CSP 3.03 Attachment D Page 4 of 55 Rev. 2 El Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ENERCON ISFSl-Only EAL Scheme at u,. Excellence-Every project. Every day. VYNPS REVISION 1 Table B-4 Comparison of RG1.109.xlsm and Reference 4 for a Ground Release ...................

B-6 Table C-1 Core Shroud Activity Decay Verification

.................................................................

C-1 Table C-2 Core Shroud Activity Limit Verification at 1. 75 Years Post Shutdown .....................

C-3 List of Figures Figure A-1 RG1 .109.xlsm Worksheet Parameters Options List.. .............................................

A-2 CSP 3.03 Attachment D Page 5 of 55 Rev. 2 Q ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at Excellence-Every project Every day. VYNPS REVISION 1 1.0 Introduction 1.1 Purpose and Scope The purpose of this calculation is to develop a method for establishing curie limits for open containers or other packages containing filters, resins, and other materials generated during decommissioning activities at Vermont Yankee Nuclear Power Station (VYNPS). The scope of this calculation is focused on activated reactor vessel (RV) cladding and/or RV internals stainless steel and surrounding bio-shield concrete, which will be cut up during decommissioning activities.

The dispersal of this material is treated in accordance with the VYNPS Offsite Dose Calculation Manual (ODCM) as a gaseous release of iodines, tritium, and particulate material with half-lives greater than 8 days. The methodology can be applied to other solid waste streams, but is not applicable to liquid waste streams. The broader purpose of such methodology is to support administrative controls over any solid waste stream. The calculation is assigned a quality assurance rating of non-safety related because the results will be used to develop curie limits in support of the development of an Independent Spent Fuel Storage Installation (ISFSl)-only Emergency Action Level (EAL) scheme, rather than to establish the design or the design basis of a safety-related Structure, System, or Component (SSC) or to establish or to confirm that a safety-related SSC meets its design bases. 1.2 Discussion For gaseous effluents, the VYNPS ODCM annual dose rate limits are given in Specification 3.3.1 as: L ____ _ The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:

a. For noble gases: less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and Page 6 of 55 o Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ENERCON ISFSl-Only EAL Scheme at Exceilence-Every project. Every day. VYNPS REVISION 1 b. For lodine-131, lodine-133, tritium, and all radioactive materials in particulate form with half-lives greater than 8 days: less than or equal to 1500 mrem/yr to any organ. The current VYNPS EAL scheme, detailed in the VYNPS EAL Technical Bases Manual, includes the lowest EAL, PD-AU1, addressing a low-level radiological release that exceeds regulatory commitments; specifically, a release of liquid or gaseous radioactivity greater than 2 times the ODCM limit for 60 minutes or longer given in Specifications 3.2.1 and 3.3.1, respectively.

The EAL is based on the guidance specific to permanently defueled stations presented in Appendix C of NEI 99-01, "Development of Emergency Action Levels for Non-Passive Reactors," Rev. 6 [1]; specifically, EAL PD-AU1 addressing a release of gaseous or liquid radioactivity greater than 2 times the site-specific effluent release controlling document limits. For gaseous releases, the current basis for the above EAL is the count rate or vent concentration alarm set-point on the effluent monitor which is correlated to a dose rate equal to the ODCM noble gas dose rate limit of either 500 mrem/yr total body or 3000 mrem/yr skin (3.3.1.a).

When all of the spent fuel has been moved from the spent fuel pool to dry storage in the ISFSI, a dose rate limit based on the effluent monitors will not be an effective basis for the Unusual Event initiating condition, as there will be no significant source of noble gases remaining within the plant. U.S. Nuclear Regulatory Commission (NRC)-endorsed industry guidance [1] does not explicitly address an emergency classification scheme for this plant condition.

Rather, it addresses the use of an Unusual Event and Alert for a permanently defueled plant with spent fuel in the spent fuel pool. Thus, it is proposed that administrative controls on the Curie content of materials accumulated during decommissioning operations be implemented based on the VYNPS ODCM Specification 3.3.1.b, which limits the dose rate to 1500 mrem/yr to any organ for radio-iodines, tritium, and particulates with half-lives greater than 8 days. By ensuring that an instantaneous dose rate from decommissioning operations cannot exceed twice Page 7 of 55 IQ) ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001

..J..., ISFSl-Only EAL Scheme at Excellence-Every project. Every day. VYNPS REVISION 1 the ODCM through administrative controls, the current EALs are no longer necessary and can be eliminated.

For a permanently defueled plant with no spent fuel in the spent fuel pool, it is unlikely that the initiating conditions for Unusual Event or Alert would occur given the programmatic controls (radiation protection, fire protection, safety, chemical control, etc.) which will continue as needed until license termination.

Administrative controls to further reduce the potential release of radioactive materials can be demonstrated so that it is not reasonably possible to reach the Unusual Event and Alert initiating conditions.

2.0 Summary of Results and Conclusions It has been demonstrated that appropriate Curie limits can be determined for VYNPS reactor core internal

activated stainless steel and surrounding activated bio-shield concrete to preclude the offsite dose, currently taken as the Exclusion Area Boundary (EAB) dose per the ODCM, from exceeding twice the ODCM specification 3.3.1.b dose rate limit, or 3000 mrem/yr to any organ for all radionuclides including radio-iodines, tritium, and all radioactive materials in particulate form with half-lives greater than 8 days. In the case of core internal activated stainless steel, 99% of the dose and activity limits are primarily determined by Co-60, Ni-63, and Fe-55. These are the key radionuclides for sample characterization and for limiting radioactivity accumulation in open containers and filters from decommissioning operations involving reactor core internals.

Based on the approach shown in Section 6.0 and the initial activities for steel given in Section 4.1, recommended activity limits as a function of time from shutdown for such activated steel are shown in Table 2-1. In the case of activated bio-shield concrete, 99% of the dose and activity limits are primarily determined by H-3, Ca-41, Co-60, Fe-55, Eu-152, and Eu-154. 80 to 90% of the dose is from Ca-41 and Eu-152, while 90% of the activity is from H-3 and Fe-55. These are the key radionuclides for sampling and for limiting radioactivity accumulation in open containers and filters from decommissioning operations involving bio-shield concrete up to 60 cm in depth. Based on the approach shown in Section 6.0 Page 8 of 55 a ENERCON Curie Limits in Support of an CALC NO. ENTGVYOJG-CALC-001

& ISFSl-Only EAL Scheme at fxcellence-Evel)'

project. Every day. VYNPS REVISION 1 and the initial activities for concrete given in Section 4.1, recommended activity limits as a function of time from shutdown for such bio-shield concrete are shown in Table 2-2. Section 9.2 shows examples on the application of the recommended activity limits. In planning/preparation for actual decommissioning/dismantlement work, representative samples must be obtained and analyzed to provide source term characterization for use with the methodology presented in this calculation. Page 9 of55 lt'J ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-001

= Scheme at VYNPS lix<ellence-fvery project. Every day. REVISION 1 Table 2-1 Activity Limits (Ci) for Core Internals Steel Based on Core Shroud Activities Time (yr) Radio-nuclide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 Fe-55 1.013 0.522 0.416 0.330 0.261 0.206 0.162 0.128 0.101 0.079 0.062 0.049 0.038 Co-60 0.706 0.530 0.478 0.430 0.385 0.345 0.308 0.275 0.245 0.218 0.194 0.172 0.153 Ni-63 0.161 0.176 0.179 0.183 0.186 0.188 0.190 0.192 0.194 0.195 0.197 0.198 0.199 Total 1.880 1.228 1.073 0.943 0.832 0.739 0.660 0.595 0.540 0.492 0.453 0.419 0.390 Table 2-2 Activity Limits (Ci) for Bio-Shield Based on Bio-Shield Edge Activities Time (yr) Radio-nuclide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 H-3 4.785 4.867 4.838 4.789 4.723 4.644 4.554 4.454 4.348 4.237 4.121 4.003 3.883 Ca-41 0.012 0.014 0.015 0.016 0.017 0.017 0.018 0.019 0.019 0.020 0.020 0.021 0.021 Fe-55 1.895 1.057 0.859 0.696 0.562 0.452 0.363 0.290 0.232 0.185 0.147 0.117 0.093 Co-60 0.235 0.191 0.176 0.161 0.148 0.135 0.122 0.111 0.101 0.091 0.082 0.074 0.066 Eu-152 0.236 0.243 0.243 0.241 0.239 0.236 0.232 0.228 0.224 0.219 0.214 0.209 0.203 Eu-154 0.044 0.042 0.041 0.039 0.038 0.036 0.035 0.033 0.032 0.030 0.029 0.027 0.026 Total 7.207 6.414 6.172 5.942 5.727 5.520 5.324 5.135 4.956 4.782 4.613 4.451 4.292 Page 10 of 55 0 ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at project. Every day. VYNPS REVISION 3.0 References

1. NEI 99-01 Rev 6, Development of Emergency Action Levels for Non-Passive Reactors, November 2012, Nuclear Energy Institute.

1 2. Document E11-1685-001, Rev. 0, Vermont Yankee Nuclear Power Station Site Specific Decommissioning Cost Estimate, Section 4 Schedule.

3. VYNPS ODCM, Revision 37 issued 12/1/16. 4. Areva Document 32-9066572-000, VYNPS ODCM -Updated Gaseous Release Dose Factors for 2002-2006 Meteorology and Updated Main Stack Flow Rate, December 5, 2007. 5. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix I, Revision 1, U.S. NRC, 1977. 6. EPA-402-R-93-081, Federal Guidance Report No. 12, "External Exposure to Radionuclides in Air, Water, and Soil", September 1993. 7. NUREG/CR-3474, Long-Lived Activation Products in Reactor Materials, J.C. Evans et.al. August 1984. 8. NUREG-0172, Age-Specific Radiation Dose Commitment Factors for A One-Year Chronic Intake, G.R. Hoenes and J. K. Soldat, Novermber 1977. 9. NUREG-1940, RASCAL 4: Description of Models and Methods, J. V. Ramsdell, et.al. December 2012. 10. NUREG-1140, A Regulatory Analysis on Emergency Preparedness for Fuel Cycle and Other Radioactive Material Licensees, S. A. McGuire, January 1988. 11. NUREG/CR-4653, GASPAR II Technical Reference and User Guide, D. L Strenge, T. J. Bander and J. K. Soldat, March 1987. 12. WMG Report 13-150-RE-169, Rev.1, Table 1-1. Page 11of55 El ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at Excellence-Every project. fvery day. WNPS REVISION 1 4.0 Assumptions 4.1 Material Activities In the absence of detailed radionuclide VYNPS material characteristics other than Co-60 for in-vessel material, core shroud/vessel cladding 304 stainless steel and surrounding bio-shield concrete activities are taken from Reference 7, Tables 5.1, 5.3, and 5.4 for a BWR with 30 effective full power years of irradiation, and with updated half-lives from Reference

6. These are shown in Table 4-1. It is assumed that these are applicable to the VYNPS reactor vessel internals and the surrounding concrete bio-shield.

VYNPS is a BWR which operated for approximately 42 years at an approximately 83% capacity factor, or approximately 35 effective full power years. These activities are based on detailed activation calculations sponsored by the USNRC. It is deemed that the computed distribution of activities are still applicable.

A comparison to WMG estimated total and Co-60 activities

[12] shows the Reference 7 activities are conservative.

See Sheet WMG-Comparison in Excel work book, CALC-001.xlsm.

However, it is important to understand that the methodology provided in this calculation is not dependent on the absolute magnitude of the starting activities, but on the relative distribution of activities as a function of decay time. Further comparisons to detailed WMG radionuclide estimates and actual sampled activities are warranted to validate the proposed activity limit tables. Final activity limits should be derived from samples of actual VYNPS stainless steel and concrete bio-shield prior to beginning decommissioning work. Page 12 of 55 ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at ex,ellence-fvery project fl.rery day. VYNPS REVISION 1 Table 4-1 Material Activities Activity (Ci/g) 304 Stainless Steel Bio-shield Concrete Radionuclide Half Life Shroud Vessel Inner lOcm 20cm 30cm 60cm (yr) Cladding Edge H-3 l.2350E+Ol 1.30E-05 2.SOE-08 4.90E-07 8.60E-07 6.50E-07 3.40E-07 l.73E-08 C-14 5.7300E+03 7.30E-06 4.90E-09 1.70E-10 2.90E-10 2.20E-10 l.lOE-10 5.78E-12 Cl-36 3.0100E+05 l.60E-07 l.OOE-10 1.lOE-11 1.60E-11 l.20E-11 6.00E-12 3.15E-13 Ar-39 2.6900E+02 l.90E-08 5.30E-11 4.70E-09 l.90E-09 8.30E-10 3.20E-10 2.65E-11 Ca-41 1.4000E+05 1.40E-09 9.lOE-13 l.lOE-09 2.00E-09 l.50E-09 7.60E-10 3.91E-11 Mn-53 3.7000E+06 4.60E-10 1.40E-12 3.80E-15 l.50E-15 6.70E-16 2.50E-16 2.14E-17 Mn-54 8.5558E-01 8.30E-04 2.00E-06 4.90E-09 2.00E-09 8.70E-10 3.30E-10 2.76E-11 Fe-55 2.7000E+OO 5.90E-02 4.lOE-05 2.90E-07 4.90E-07 3.60E-07 l.90E-07 9.66E-09 Ni-59 7.5000E+04 4.30E-05 3.20E-08 l.60E-12 2.70E-12 2.00E-12 1.lOE-12 5.47E-14 Co-60 5.2710E+OO 3.20E-02 2.40E-05 2.80E-08 3.50E-08 2.SOE-08 l.30E-08 6.41E-10 Ni-63 9.6000E+Ol 5.70E-03 4.00E-06 2.00E-10 3.40E-10 2.50E-10 l.30E-10 6.81E-12 Zn-65 6.6776E-01 l.lOE-04 7.lOE-08 2.00E-09 2.50E-09 l.70E-09 8.70E-10 4.49E-11 Se-79 6.5000E+04 l.OOE-10 l.70E-13 3.20E-16 3.30E-16 2.20E-16 l.lOE-16 6.16E-18 Kr-81 2.1000E+05 1.60E-11 9.40E-18 7.20E-19 4.50E-19 1.60E-19 3.40E-20 8.69E-23 Kr-85 l.0720E+Ol 5.80E-08 9.00E-12 6.30E-12 4.60E-12 2.90E-12 1.40E-12 8.06E-14 Sr-90 2.9120E+Ol l.50E-07 2.50E-11 4.30E-12 7.40E-12 5.60E-12 2.90E-12 1.49E-13 Nb-92m 3.7000E+07 4.50E-14 3.80E-16 3.70E-19 2.lOE-19 6.50E-20 2.40E-20 2.lOE-21 Zr-93 1.5300E+06 l.OOE-11 l.20E-14 2.90E-15 2.90E-15 2.00E-15 9.70E-16 5.07E-17 Mo-93 3.5000E+03 7.70E-08 7.70E-11 9.40E-14 4.SOE-14 2.00E-14 7.20E-15 3.56E-16 Nb-94 2.0300E+04 6.31E-08 4.90E-11 6.lOE-13 4.70E-13 2.90E-13 l.30E-13 6.72E-15 Tc-99 2.1300E+05 l.50E-08 l.50E-11 2.20E-14 l.lOE-14 5.20E-15 2.00E-15 9.90E-17 Ag-108m 1.2700E+02 2.00E-08 l.50E-11 3.lOE-13 3.lOE-13 2.lOE-13 l.OOE-13 5.13E-15 Sn-121m 5.5000E+Ol 7.60E-10 2.00E-12 l.20E-13 7.40E-14 4.30E-14 2.00E-14 1.23E-15 1-129 1.5700E+07 4.20E-14 7.60E-18 l.30E-18 2.30E-18 l.70E-18 8.90E-19 4.58E-20 Ba-133 l.0740E+Ol 7.40E-07 6.00E-10 l.30E-10 2.lOE-10 1.SOE-10 7.80E-11 4.03E-12 Cs-134 2.0620E+OO 2.40E-06 l.70E-09 8.50E-10 l.70E-09 l.30E-09 6.60E-10 3.41E-11 Cs-135 2.3000E+06 2.70E-12 6.40E-16 9.90E-17 l.50E-16 1.lOE-16 5.70E-17 2.97E-18 Cs-137 3.0170E+Ol 1.SOE-07 3.SOE-11 5.30E-12 8.00E-12 5.90E-12 3.00E-12 1.58E-13 Pm-145 1.7700E+Ol 3.lOE-10 2.30E-13 5.80E-13 l.OOE-12 7.60E-13 4.00E-13 2.04E-14 Sm-146 l.0300E+08 2.90E-17 7.90E-20 8.20E-20 3.30E-20 l.50E-20 5.SOE-21 4.61E-22 Sm-151 9.0000E+Ol 3.80E-09 3.lOE-11 1.20E-10 1.30E-10 8.50E-11 4.20E-11 2.14E-12 Eu-152 1.3330E+Ol 2.20E-14 6.70E-09 2.40E-08 4.20E-08 3.20E-08 l.60E-08 8.44E-10 Eu-154 8.8000E+OO 9.lOE-07 8.00E-10 4.70E-09 4.50E-09 3.00E-09 l.40E-09 7.35E-11 Eu-155 4.9600E+OO 3.60E-07 2.90E-11 1.40E-10 1.20E-10 7.lOE-11 3.30E-11 1.69E-12 Page 13 of 55 0 ENERCON

project..

Every day. Radionuclide Half Life (yr) Tb-158 1.5000E+02 Ho-166m 1.2000E+03 Hf-178m 3.lOOOE+Ol Pb-205 1.4300E+07 U-233 1.5850E+05 Pu-239 2.4065E+04 Total Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 Activity (Ci/g) 304 Stainless Steel Bio-shield Concrete Shroud Vessel Inner lOcm 20cm 30cm 60cm Cladding Edge 3.80E-10 1.lOE-12 4.80E-14 2.00E-14 8.60E-15 3.20E-15 2.71E-16 2.80E-08 1.90E-11 5.lOE-12 3.30E-12 1.80E-12 8.lOE-13 4.09E-14 3.70E-08 7.SOE-11 2.70E-11 1.SOE-11 7.60E-12 3.lOE-12 1.56E-13 2.90E-13 4.SOE-16 3.40E-17 3.00E-17 2.00E-17 9.SOE-18 5.20E-19 1.60E-10 2.20E-13 2.20E-13 1.SOE-13 8.lOE-14 3.60E-14 l.80E-15 2.70E-09 5.80E-12 3.lOE-12 1.30E-12 5.20E-13 1.60E-13 7.81E-15 9.77E-02 7.llE-05 8.51E-07 1.44E-06 1.08E-06 5.64E-07 3.41E+11 Page 14 of 55 C) EN_ERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at E>cellence-fvety project. Every day. VYNPS REVISION 1 4.2 Initiating Event Various initiating events can be postulated leading to the dispersal of material.

However, the driving force for the release of material tends to be a fire following such events. So, even though the materials under evaluation, i.e. steel and concrete, do not burn, the dispersal by a fire (airborne release) would appear to be the worst case situation.

Thus, the material release fractions for a fire scenario are used in this evaluation.

It is important to note that all cutting will be underwater or with water flush of debris and in appropriately engineered facilities so the most significant material accumulation is from filters associated with the clean-up of water containing debris from these materials, rather than the materials in normal form. 4.3 Release Pathway The VYPNS ODCM allows two gaseous release pathways:

Stack and North Warehouse (Ground).

Of the two, the ground release pathway has the most conservative dispersion and deposition factors. Thus, the ground release pathway is evaluated in this calculation.

4.4 Release Fractions Release fractions are taken from References 9 and 10 which provide guidance on the radiological assessment of fuel cycle accidents.

These release fractions are assumed on a radionuclide-by-radionuclide basis with no regard for packaging and form. Actual evaluations should consider if the filter/resin media is flammable as well as whether the filter/resin housing is robust enough to withstand a fire. In actual practice, lower release fractions may be more applicable (e.g. mixed corrosion products or irradiated solid noncombustible as discussed in NUREG-1140 (Reference 9)). In the absence of detailed operation and packaging information, the assumed release fractions are a simplifying and conservative assumption.

Page 15 of 55 0 ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at fxcellence-f'lfery project. Every day, VYNPS REVISION 1 4.5 Activity Most of the activity will come from activated components, although there will be significant surface contamination on many primary components.

Source term characterization at the time of dismantlement should encompass both types of activity.

The scope of this evaluation addresses only activation nuclides from reactor internals and bio-shield concrete.

4.6 Applicability It is assumed that this evaluation applies to open containers, filters, and radioactive materials generated during and at the location of active decommissioning operations at VYNPS. This evaluation does not apply to closed, appropriate containers stored elsewhere on site. 5.0 Design Inputs 5.1 Shutdown Date VYNPS shut down permanently on December 29, 2014. Decommissioning activities could begin as early as July 2021 after a 6.5 year period of SAFSTOR. However, the shortest decay period is taken to be the present (late December 2016), approximately 2 years from the shutdown date. Additional evaluations are performed in at 5 years and 1 year increments out to 2040 to cover the period of SAFSTOR and decommissioning operations.

5.2 Dispersion and Ground Deposition Factors The VYNPS EAB dispersion and ground deposition factors for dose to the critical organ are taken from Reference 3 Table 6.10.1 and are shown in Table 5-1. These are also given in Reference 4 Table 4-4. While the ground level release point for these release coefficients is the North Warehouse, according to the VYNPS ODCM these release coefficients and the associated dose rate factors are conservative for other potential ground release points such as the Turbine Building and Reactor Building.

It is important to note that the VY site-specific dose rate conversion factors include the dispersion and Page 16 of 55 ID ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at Excellence-Every project. Every day. WNPS REVISION 1 ground deposition factors in a full pathway evaluation, i.e. inhalation, ground shine, and ingestion, in accordance with RG 1.109 [5]. This is discussed further in the next section and in Appendix A. Table 5-1 VYNPS Ground Release Coefficients IQ sec/m 3 3.44E-05 D/Q 1/m 2 6.40E-08 5.3 Site Specific Critical Organ Dose Rate Conversion Factors Several VYNPS site-specific ground release isotopic critical organ (DCG' g,i,co) dose rate conversion factors are taken from Reference 3, Table 1.1.12 and/or Reference 4 Table 5-2. Critical organ dose rate conversion factors for several additional activated isotopes were computed in accordance RG 1.109 [5], NUREG-0172

[8] and with the VYNPS specific parameters given in Reference

4. Details of this computation are given in Appendix A The final set of VYNPS site specific dose conversion factors is shown in the "Used" column of Table 5-2, below. Except for a few radionuclides, discussed in Appendix B, results computed in this calculation match or are very close to the VYNPS ODCM values. In the cases where the radionuclide results differed, a conservative approach is taken and the maximum of the two computed values is used in the calculation.

Page 17 of 55 Ct ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at ,_L .. EJu;ellence-Evety projecr. Every day. VYNPS REVISION 1 Table 5-2 Ground Release Site Specific Dose Conversion Factors DCG'g.1,co (mrem/yr per µCi/sec) Radionuclide VYODCM& Calculated per Used Ref. 4 RG 1.109 1 H-3 3.47E-01 1.85E-01 3.47E-01 C-14 2.11E+02 1.97E+02 2.11 E+02 Cl-36 n/a n/a O.OOE+OO Ar-39 n/a n/a O.OOE+OO Ca-41 n/a 2.87E+04 2.87E+04 Mn-53 n/a n/a O.OOE+OO Mn-54 1.95E+02 1.95E+02 1.95E+02 Fe-55 6.94E+01 6.94E+01 6.94E+01 Ni-59 n/a 3.16E+02 3.16E+02 Co-60 2.32E+03 2.26E+03 2.32E+03 Ni-63 5.24E+03 4.19E+03 5.24E+03 Zn-65 8.20E+02 8.20E+02 8.20E+02 Se-79 n/a 3.27E+03 3.27E+03 Kr-81 n/a n/a O.OOE+OO Kr-85 n/a n/a O.OOE+OO Sr-90 9.56E+04 1.40E+05 1.40E+05 Nb-92m n/a n/a O.OOE+OO Zr-93 n/a 2.73E+01 2.73E+01 Mo-93 n/a 3.76E+02 3.76E+02 Nb-94 n/a n/a O.OOE+OO Tc-99 n/a 8.89E+02 8.89E+02 Ag-108m n/a n/a O.OOE+OO Sn-121m n/a n/a O.OOE+OO 1-129 1.28E+05 1.28E+05 1.28E+05 Ba-133 n/a n/a O.OOE+OO Cs-134 3.63E+03 3.62E+03 3.63E+03 Cs-135 n/a 7.37E+02 7.37E+02 Cs-137 3.78E+03 3.79E+03 3.79E+03 Pm-145 n/a n/a O.OOE+OO Sm-146 n/a n/a O.OOE+OO Sm-151 n/a 5.32E+01 5.32E+01 1 VY specific RG 1.109 parameters taken from Table 4-2 of Reference 4 Page 18 of 55 11!) ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at E:xcellence-Every project. Every day. VYNPS REVISION 1 DCG 0 g,l,co (mrem/yr per µCi/sec) Radionuclide VYODCM& Calculated per Used Ref. 4 RG 1.109 1 Eu-152 n/a 1.51E+03 1.51E+03 Eu-154 n/a 1.56E+03 1.56E+03 Eu-155 n/a 6.00E+02 6.00E+02 Tb-158 n/a n/a O.OOE+OO Ho-166m nla 2.52E+03 2.52E+03 Hf-178m n/a n/a O.OOE+OO Pb-205 n/a n/a O.OOE+OO U-233 n/a 2.59E+04 2.59E+04 Pu-239 n/a 4.80E+05 4.80E+05 5.4 Release Time The release time of 60 minutes (3600 sec) is based on the minimum time given in NEI 99-01 page C-3 [1]. 5.5 Release Fractions A worst case scenario would involve a fire dispersing (airborne release) the radioactive materials from filters and open containers into the surrounding air and then drifting to the EAB. Thus, the release fractions are based on the fire scenario and, unless otherwise noted, are taken primarily from Reference 9 Table 3.12, and the others from Reference 9 Table 3.11, and Reference 10 Table 13, as shown in Table 5-3 below. Page 19 of 55 El A. ENERCON Excellence-Every project. Every day. 2 NUREG-1940 Table 3.11 3 NUREG-1140Table13 Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at VYNPS REVISION 1 Table 5-3 Release Fractions Radionuclide Fire Release Fraction H-3 0.5 C-14 0.01 Cl-36 0.5 Ar-39 2 1 Ca-41 0.01 Mn-53 0.01 Mn-54 0.01 Fe-55 0.01 Ni-59 3 0.01 Co-60 0.001 Ni-633 0.01 Zn-65 0.01 Se-79 0.01 Kr-812 1 Kr-852 1 Sr-90 0.01 Nb-92m 0.01 Zr-93 0.01 Mo-93 0.01 Nb-94 0.01 Tc-99 0.01 Ag-108m 0.01 Sn-121m 0.01 1-129 0.5 Ba-133 0.01 Cs-134 0.01 Cs-135 0.01 Cs-137 0.01 Pm-145 0.01 Sm-146 0.01 Sm-151 0.01 Eu-152 0.01 Page 20 of 55 If I Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ENERCON ISFSl-Only EAL Scheme at Excellence-Every project Every day. VYNPS REVISION 1 Radionuclide Fire Release Fraction Eu-154 0.01 Eu-155 0.01 Tb-158 0.01 Ho-166m 0.01 Hf-178m 0.01 Pb-205 0.01 U-233 0.001 Pu-239 0.001 5.6 Conversion Factors Applied The conversion factors applied in this analysis are provided in Table 5-4. Table 5a4 Conversion Factors pCi/µCi 1.00E+06 µCi/pCi 1.00E-06 µCi/Ci 1.00E+06 sec/yr 3.16E+07 hr/yr 8766 sec/hr 3.60E+03 Page 21of55 a Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ENERCON ISFSl-Only EAL Scheme at Excellence-Every project. Every day. WNPS REVISION 1 6.0 Methodology Using the steel and concrete activities given in Table 4-1, the maximum container activity limits are determined to obtain twice the ODCM limits at the EAB. The proposed ODCM limit is 1500 mrem/yr (Reference 3, Section 3.3.1.b), and the dose calculation is based on the methodology in Section 6.6.1. Activities are decayed from the shutdown date to the present and out to 2040 when D&D activities are anticipated to be completed.

The release is treated as a gaseous/particulate airborne release during a fire event with tritium and radioactive materials in a particulate form. The curie limits are determined by scaling the material activities to produce 3000 mrem/yr at the EAB. Details are provided in subsequent sections.

6.1 Decayed Activities The first step in the computations is to decay the material activities in Table 4-1 from the shutdown date to the present, approximately 2 years post-shutdown, and starting at 5 year in increments of 1 years out to 2040. Simple exponential decay, assuming no significant daughters, is applied, i.e. Eqn. 6-1 Where OiO initial activity (Ci/g) of Radionuclide I Oi(t) activity (Ci/g) of Radionuclide i at time t (yr) A.1 decay constant of Radionuclide i (yr 1) = ln(2)/ti112(yr) t time from shutdown (yr) 6.2 Determination of Nuclide Activity Limits The container or filter curie limits are determined in the following steps: 1. The annual dose, Di, to a critical organ is computed for each nuclide activity, assuming a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (3600 sec) release in a fire incident, by the following equation:

Page 22 of 55 Q ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at Excellence-Every project Every day. VYNPS REVISION 1 Q C" D -i *RF µ l i -3600 sec ifire RFien

RFi bld*1E+6 Ci *DFG'g,i,co Eqn. 6-2 Where, Di Dose to critical organ from radionuclide i (mrem/yr)4 Q;(t) Activity of radionuclide i at time t (Ci)4 DFG' 9 ,i,co Critical organ ground release dose rate conversion factor for radionuclide i [mrem/yr per µCi/sec] RFifire Radionuclide i release fraction from a fire Isotope i release fraction from enclosure to building = 1.0 RFibld Isotope i release fraction from building to environment

= 1.0 Note that Eqn. 6-2 allows for incorporating release fractions from an enclosure, presumably set up during decommission operations, and also from the reactor building.

However, credit is not taken for these in this evaluation.

2. Each nuclide curie limit is determined by scaling Oi to a total dose of 3000 mrem/yr by the following equation:

Eqn. 6-3 Where, Activity of Radionuclide i at time t (Ci)4 Oi3ooo Activity of Radionuclide i at time t (Ci)4 scaled to produce 3000 mrem/yr 3. The total filter or container activity limit, Oro1a1, in curies is computed by summing the scaled activities, Oi3ooo , by the following equation:

4 Dose and activity are normalized to a per gram basis. However, what matters is the total curies released, Page 23 of 55 Q ENERCON Ex<ellence-£very project Every day. QTotal =I Qi 3000 i Curie Limits in Support of an ISFSl-Only EAL Scheme at WNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 Eqn. 6-4 The final activity limits for steel and concrete are based on the material which produces the minimum limits and those nuclides which produce 99% of the activity and/or dose if released.

7.0 Calculations Radionuclide decayed activities, doses, and curie limits for in-core activated steel and bio-shield concrete are computed with the macro enabled Excel workbook ENTGVY036-CALC-001.xlsm and are compiled in worksheet Computations-B.

A description and verification of ENTGVY036-CALC-001.xlsm is provided in Appendix C. 7 .1 Decayed Activities Decayed activities for the core shroud and the edge of the bio-shield are shown in Table 7-1 and Table 7-2, respectively.

Activities are listed in this document out to 16 years post shutdown, i.e. end of 2030, but the spreadsheet contains additional times out to 26 years post shutdown or end of 2040. The other stainless steel and concrete decayed activities can be found in worksheet Computations-C columns GF through HC for each material as a function of shutdown time. Page 24 of 55 f Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-001 ENERCON Scheme at VYNPS Excellence-£wiry project £very day. REVISION 1 Table 7-1 Decayed Activities for Core Shroud (Ci/g) Time (yr) Isotope 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 H-3 1.16E-05 9.82E-06 9.28E-06 8.78E-06 8.30E-06 7.84E-06 7.42E-06 7.01E-06 6.63E-06 6.27E-06 5.93E-06 5.60E-06 5.30E-06 C-14 7.30E-06 7.30E-06 7.29E-06 7.29E-06 7.29E-06 7.29E-06 7.29E-06 7.29E-06 7.29E-06 7.29E-06 7.29E-06 7.29E-06 7.29E-06 Cl-36 1.60E-07 1.60E-07 1.60E-07 1.60E-07 1.60E-07 1.60E-07 1.60E-07 1.60E-07 1.60E-07 1.60E-07 1.60E-07 1.60E-07 1.60E-07 Ar-39 1.89E-08 1.88E-08 1.87E-08 1.87E-08 1.86E-08 1.86E-08 1.85E-08 1.85E-08 1.84E-08 1.84E-08 1.83E-08 1.83E-08 1.82E-08 Ca-41 1.40E-09 1.40E-09 1.40E-09 1.40E-09 1.40E-09 1.40E-09 1.40E-09 1.40E-09 1.40E-09 1.40E-09 1.40E-09 1.40E-09 1.40E-09 Mn-53 4.60E-10 4.60E-10 4.60E-10 4.60E-10 4.60E-10 4.60E-10 4.60E-10 4.60E-10 4.60E-10 4.60E-10 4.60E-10 4.60E-10 4.60E-10 Mn-54 1.64E-04 1.44E-05 6.43E-06 2.86E-06 1.27E-06 5.66E-07 2.52E-07 1.12E-07 4.98E-08 2.21E-08 9.85E-09 4.38E-09 1.95E-09 Fe-55 3.53E-02 1.63E-02 1.26E-02 9.78E-03 7.57E-03 5.85E-03 4.53E-03 3.50E-03 2.71E-03 2.10E-03 1.62E-03 1.25E-03 9.70E-04 Ni-59 4.30E-05 4.30E-05 4.30E-05 4.30E-05 4.30E-05 4.30E-05 4.30E-05 4.30E-05 4.30E-05 4.30E-05 4.30E-05 4.30E-05 4.30E-05 Co-60 2.46E-02 1.66E-02 1.45E-02 1.27E-02 1.12E-02 9.80E-03 8.59E-03 7.53E-03 6.60E-03 5.79E-03 5.08E-03 4.45E-03 3.90E-03 Ni-63 5.62E-03 5.50E-03 5.46E-03 5.42E-03 5.38E-03 5.34E-03 5.30E-03 5.26E-03 5.23E-03 5.19E-03 5.15E-03 5.11E-03 5.08E-03 Zn-65 1.38E-05 6.13E-07 2.17E-07 7.69E-08 2.72E-08 9.64E-09 3.41E-09 1.21 E-09 4.28E-10 1.52E-10 5.37E-11 1.90E-11 6.74E-12 Se-79 1.00E-10 1.00E-10 1.00E-10 1.00E-10 1.00E-10 1.00E-10 1.00E-10 1.00E-10 1.00E-10 1.00E-10 1.00E-10 1.00E-10 1.00E-10 Kr-81 1.60E-11 1.60E-11 1.60E-11 1.60E-11 1.60E-11 1.60E-11 1.60E-11 1.60E-11 1.60E-11 1.60E-11 1.60E-11 1.60E-11 1.60E-11 Kr-85 5.10E-08 4.20E-08 3.93E-08 3.69E-08 3.46E-08 3.24E-08 3.04E-08 2.85E-08 2.67E-08 2.50E-08 2.35E-08 2.20E-08 2.06E-08 Sr-90 1.43E-07 1.33E-07 1.30E-07 1.27E-07 1.24E-07 1.21 E-07 1.18E-07 1.15E-07 1.13E-07 1.10E-07 1.07E-07 1.05E-07 1.02E-07 Nb-92m 4.50E-14 4.50E-14 4.50E-14 4.50E-14 4.50E-14 4.50E-14 4.50E-14 4.50E-14 4.50E-14 4.50E-14 4.50E-14 4.50E-14 4.50E-14 Zr-93 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 1.00E-11 Mo-93 7.70E-08 7.69E-08 7.69E-08 7.69E-08 7.69E-08 7.69E-08 7.68E-08 7.68E-08 7.68E-08 7.68E-08 7.68E-08 7.68E-08 7.68E-08 Nb-94 6.31E-08 6.31E-08 6.31E-08 6.31E-08 6.31E-08 6.31E-08 6.31E-08 6.31E-08 6.31E-08 6.31E-08 6.31E-08 6.31E-08 6.31E-08 Tc-99 1.50E-08 1.50E-08 1.50E-08 1.50E-08 1.50E-08 1.50E-08 1.50E-08 1.50E-08 1.50E-08 1.50E-08 1.50E-08 1.50E-08 1.50E-08 Ag-108m 1.98E-08 1.95E-08 1.94E-08 1.93E-08 1.91E-08 1.90E-08 1.89E-08 1.88E-08 1.87E-08 1.86E-08 1.85E-08 1.84E-08 1.83E-08 Page 25 of 55 I -

C) ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-001 Scheme at VYNPS lixcel!ence-frery projecr. Every day. REVISION 1 Time (yr) Isotope 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 Sn-121m 7.41E-10 7.14E-10 7.05E-10 6.96E-10 6.87E-10 6.79E-10 6.70E-10 6.62E-10 6.53E-10 6.45E-10 6.37E-10 6.29E-10 6.21 E-10 1-129 4.20E-14 4.20E-14 4.20E-14 4.20E-14 4.20E-14 4.20E-14 4.20E-14 4.20E-14 4.20E-14 4.20E-14 4.20E-14 4.20E-14 4.20E-14 Ba-133 6.50E-07 5.36E-07 5.02E-07 4.71E-07 4.42E-07 4.14E-07 3.88E-07 3.64E-07 3.41E-07 3.20E-07 3.00E-07 2.81E-07 2.63E-07 Cs-134 1.22E-06 4.47E-07 3.19E-07 2.28E-07 1.63E-07 1.16E-07 8.32E-08 5.95E-08 4.25E-08 3.04E-08 2.17E-08 1.55E-08 1.11E-08 Cs-135 2.70E-12 2.70E-12 2.70E-12 2.70E-12 2.70E-12 2.70E-12 2.70E-12 2.70E-12 2.70E-12 2.70E-12 2.70E-12 2.70E-12 2.70E-12 Cs-137 1.43E-07 1.34E-07 1.31 E-07 1.28E-07 1.25E-07 1.22E-07 1.19E-07 1.17E-07 1.14E-07 1.11E-07 1.09E-07 1.06E-07 1.04E-07 Pm-145 2.87E-10 2.55E-10 2.45E-10 2.36E-10 2.27E-10 2.18E-10 2.10E-10 2.02E-10 1.94E-10 1.86E-10 1.79E-10 1.72E-10 1.66E-10 Sm-146 2.90E-17 2.90E-17 2.90E-17 2.90E-17 2.90E-17 2.90E-17 2.90E-17 2.90E-17 2.90E-17 2.90E-17 2.90E-17 2.90E-17 2.90E-17 Sm-151 3.74E-09 3.66E-09 3.63E-09 3.60E-09 3.57E-09 3.55E-09 3.52E-09 3.49E-09 3.46E-09 3.44E-09 3.41E-09 3.39E-09 3.36E-09 Eu-152 1.98E-14 1.70E-14 1.61E-14 1.53E-14 1.45E-14 1.38E-14 1.31E-14 1.24E-14 1.18E-14 1.12E-14 1.06E-14 1.01 E-14 9.57E-15 Eu-154 7.77E-07 6.14E-07 5.67E-07 5.24E-07 4.85E-07 4.48E-07 4.14E-07 3.83E-07 3.54E-07 3.27E-07 3.02E-07 2.79E-07 2.58E-07 Eu-155 2.72E-07 1.79E-07 1.56E-07 1.35E-07 1.18E-07 1.02E-07 8.90E-08 7.74E-08 6.73E-08 5.85E-08 5.09E-08 4.43E-08 3.85E-08 Tb-158 3.77E-10 3.71E-10 3.70E-10 3.68E-10 3.66E-10 3.65E-10 3.63E-10 3.61 E-10 3.60E-10 3.58E-10 3.56E-10 3.55E-10 3.53E-10 Ho-166m 2.80E-08 2.79E-08 2.79E-08 2.79E-08 2.79E-08 2.79E-08 2.78E-08 2.78E-08 2.78E-08 2.78E-08 2.78E-08 2.78E-08 2.77E-08 Hf-178m 3.54E-08 3.31E-08 3.24E-08 3.16E-08 3.09E-08 3.03E-08 2.96E-08 2.89E-08 2.83E-08 2.77E-08 2.71E-08 2.65E-08 2.59E-08 Pb-205 2.90E-13 2.90E-13 2.90E-13 2.90E-13 2.90E-13 2.90E-13 2.90E-13 2.90E-13 2.90E-13 2.90E-13 2.90E-13 2.90E-13 2.90E-13 U-233 1.60E-10 1.60E-10 1.60E-10 1.60E-10 1.60E-10 1.60E-10 1.60E-10 1.60E-10 1.60E-10 1.60E-10 1.60E-10 1.60E-10 1.60E-10 Pu-239 2.70E-09 2.70E-09 2.70E-09 2.70E-09 2.70E-09 2.70E-09 2.70E-09 2.70E-09 2.70E-09 2.70E-09 2.70E-09 2.70E-09 2.70E-09 Total 6.58E-02 3.85E-02 3.27E-02 2.80E-02 2.42E-02 2.11 E-02 1.85E-02 1.64E-02 1.46E-02 1.31E-02 1.19E-02 1.09E-02 1.00E-02 Page 26 of 55 0 ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-001 Scheme at VYNPS lixcellence-Ewry project Every day. REVISION 1 Table 7-2 Decayed Activities for Edge of Bio-Shield (Ci/g) Time (yr) Isotope 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 H-3 4.38E-07 3.70E-07 3.50E-07 3.31E-07 3.13E-07 2.96E-07 2.80E-07 2.64E-07 2.50E-07 2.36E-07 2.23E-07 2.11 E-07 2.00E-07 C-14 1.70E-10 1.70E-10 1.70E-10 1.70E-10 1.70E-10 1.70E-10 1.70E-10 1.70E-10 1.70E-10 1.70E-10 1.70E-10 1.70E-10 1.70E-10 Cl-36 1.10E-11 1.10E-11 1.10E-11 1.10E-11 1.10E-11 1.10E-11 1.10E-11 1.10E-11 1.10E-11 1.10E-11 1.10E-11 1.10E-11 1.10E-11 Ar-39 4.68E-09 4.64E-09 4.63E-09 4.62E-09 4.60E-09 4.59E-09 4.58E-09 4.57E-09 4.56E-09 4.55E-09 4.53E-09 4.52E-09 4.51E-09 Ca-41 1.10E-09 1.10E-09 1.10E-09 1.10E-09 1.10E-09 1.10E-09 1.10E-09 1.10E-09 1.10E-09 1.10E-09 1.10E-09 1.10E-09 1.10E-09 Mn-53 3.80E-15 3.80E-15 3.80E-15 3.80E-15 3.80E-15 3.80E-15 3.80E-15 3.80E-15 3.80E-15 3.80E-15 3.80E-15 3.80E-15 3.80E-15 Mn-54 9.68E-10 8.53E-11 3.79E-11 1.69E-11 7.51E-12 3.34E-12 1.49E-12 6.61E-13 2.94E-13 1.31E-13 5.81 E-14 2.59E-14 1.15E-14 Fe-55 1.73E-07 8.03E-08 6.22E-08 4.81E-08 3.72E-08 2.88E-08 2.23E-08 1.72E-08 1.33E-08 1.03E-08 7.97E-09 6.17E-09 4.77E-09 Ni-59 1.60E-12 1.60E-12 1.60E-12 1.60E-12 1.60E-12 1.60E-12 1.60E-12 1.60E-12 1.60E-12 1.60E-12 1.60E-12 1.60E-12 1.60E-12 Co-60 2.15E-08 1.45E-08 1.27E-08 1.12E-08 9.78E-09 8.57E-09 7.52E-09 6.59E-09 5.78E-09 5.07E-09 4.44E-09 3.89E-09 3.41E-09 Ni-63 1.97E-10 1.93E-10 1.92E-10 1.90E-10 1.89E-10 1.87E-10 1.86E-10 1.85E-10 1.83E-10 1.82E-10 1.81E-10 1.79E-10 1.78E-10 Zn-65 2.50E-10 1.11E-11 3.95E-12 1.40E-12 4.95E-13 1.75E-13 6.21E-14 2.20E-14 7.79E-15 2.76E-15 9.77E-16 3.46E-16 1.23E-16 Se-79 3.20E-16 3.20E-16 3.20E-16 3.20E-16 3.20E-16 3.20E-16 3.20E-16 3.20E-16 3.20E-16 3.20E-16 3.20E-16 3.20E-16 3.20E-16 Kr-81 7.20E-19 7.20E-19 7.20E-19 7.20E-19 7.20E-19 7.20E-19 7.20E-19 7.20E-19 7.20E-19 7.20E-19 7.20E-19 7.20E-19 7.20E-19 Kr-85 5.54E-12 4.56E-12 4.27E-12 4.01E-12 3.76E-12 3.52E-12 3.30E-12 3.09E-12 2.90E-12 2.72E-12 2.55E-12 2.39E-12 2.24E-12 Sr-90 4.10E-12 3.82E-12 3.73E-12 3.64E-12 3.55E-12 3.47E-12 3.39E-12 3.31E-12 3.23E-12 3.16E-12 3.0SE-12 3.01E-12 2.94E-12 Nb-92m 3.70E-19 3.70E-19 3.70E-19 3.70E-19 3.70E-19 3.70E-19 3.70E-19 3.70E-19 3.70E-19 3.70E-19 3.70E-19 3.70E-19 3.70E-19 Zr-93 2.90E-15 2.90E-15 2.90E-15 2.90E-15 2.90E-15 2.90E-15 2.90E-15 2.90E-15 2.90E-15 2.90E-15 2.90E-15 2.90E-15 2.90E-15 Mo-93 9.40E-14 9.39E-14 9.39E-14 9.39E-14 9.39E-14 9.38E-14 9.38E-14 9.38E-14 9.38E-14 9.38E-14 9.37E-14 9.37E-14 9.37E-14 Nb-94 6.10E-13 6.10E-13 6.10E-13 6.10E-13 6.10E-13 6.10E-13 6.10E-13 6.10E-13 6.10E-13 6.10E-13 6.10E-13 6.10E-13 6.10E-13 Tc-99 2.20E-14 2.20E-14 2.20E-14 2.20E-14 2.20E-14 2.20E-14 2.20E-14 2.20E-14 2.20E-14 2.20E-14 2.20E-14 2.20E-14 2.20E-14 Ag-108m 3.07E-13 3.02E-13 3.00E-13 2.98E-13 2.97E-13 2.95E-13 2.94E-13 2.92E-13 2.90E-13 2.89E-13 2.87E-13 2.86E-13 2.84E-13 Sn-121m 1.17E-13 1.13E-13 1.11E-13 1.10E-13 1.08E-13 1.07E-13 1.06E-13 1.04E-13 1.03E-13 1.02E-13 1.01 E-13 9.93E-14 9.81E-14 1-129 1.30E-18 1.30E-18 1.30E-18 1.30E-18 1.30E-18 1.30E-18 1.30E-18 1.30E-18 1.30E-18 1.30E-18 1.30E-18 1.30E-18 1.30E-18 Page 27 of 55

,, ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-001 JI. Scheme at VYNPS lixce!lence-'frery project. E<*ery day. REVISION 1 Time <vr\ lsotooe 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 Ba-133 1. 14E-10 9.41E-11 8.83E-11 8.27E-11 7.76E-11 7.27E-11 6.82E-11 6.39E-11 5.99E-11 5.62E-11 5.27E-11 4.94E-11 4.63E-11 Cs-134 4.34E-10 1.58E-10 1.13E-10 8.08E-11 5.77E-11 4.13E-11 2.95E-11 2. 11E-11 1.51E-11 1.08E-11 7.68E-12 5.49E-12 3.92E-12 Cs-135 9.90E-17 9.90E-17 9.90E-17 9.90E-17 9.90E-17 9.90E-17 9.90E-17 9.90E-17 9.90E-17 9.90E-17 9.90E-17 9.90E-17 9.90E-17 Cs-137 5.06E-12 4.72E-12 4.62E-12 4.51 E-12 4.41E-12 4.31 E-12 4.21 E-12 4.12E-12 4.02E-12 3.93E-12 3.84E-12 3.75E-12 3.67E-12 Pm-145 5.36E-13 4.77E-13 4.59E-13 4.41E-13 4.24E-13 4.08E-13 3.92E-13 3.77E-13 3.63E-13 3.49E-13 3.35E-13 3.22E-13 3. 10E-13 Sm-146 8.20E-20 8.20E-20 8.20E-20 8.20E-20 8.20E-20 8.20E-20 8.20E-20 8.20E-20 8.20E-20 8.20E-20 8.20E-20 8.20E-20 8.20E-20 Sm-151 1. 18E-10 1. 15E-10 1. 15E-10 1.14E-10 1. 13E-10 1.12E-10 1.11E-10 1.10E-10 1.09E-10 1.09E-10 1.08E-10 1.07E-10 1.06E-10 Eu-152 2.16E-08 1.85E-08 1.76E-08 1.67E-08 1.58E-08 1.50E-08 1.43E-08 1.35E-08 1.29E-08 1.22E-08 1.16E-08 1.10E-08 1.04E-08 Eu-154 4.01E-09 3.17E-09 2.93E-09 2.71E-09 2.50E-09 2.31E-09 2. 14E-09 1.98E-09 1.83E-09 1.69E-09 1.56E-09 1.44E-09 1.33E-09 Eu-155 1.06E-10 6.96E-11 6.05E-11 5.26E-11 4.58E-11 3.98E-11 3.46E-11 3.01 E-11 2.62E-11 2.28E-11 1.98E-11 1.72E-11 1.50E-11 Tb-158 4.76E-14 4.69E-14 4.67E-14 4.65E-14 4.63E-14 4.60E-14 4.58E-14 4.56E-14 4.54E-14 4.52E-14 4.50E-14 4.48E-14 4.46E-14 Ho-166m 5.09E-12 5.09E-12 5.08E-12 5.08E-12 5.08E-12 5.07E-12 5.07E-12 5.07E-12 5.06E-12 5.06E-12 5.06E-12 5.06E-12 5.05E-12 Hf-178m 2.58E-11 2.41E-11 2.36E-11 2.31E-11 2.26E-11 2.21E-11 2.16E-11 2. 11E-11 2.06E-11 2.02E-11 1.97E-11 1.93E-11 1.89E-11 Pb-205 3.40E-17 3.40E-17 3.40E-17 3.40E-17 3.40E-17 3.40E-17 3.40E-17 3.40E-17 3.40E-17 3.40E-17 3.40E-17 3.40E-17 3.40E-17 U-233 2.20E-13 2.20E-13 2.20E-13 2.20E-13 2.20E-13 2.20E-13 2.20E-13 2.20E-13 2.20E-13 2.20E-13 2.20E-13 2.20E-13 2.20E-13 Pu-239 3.10E-12 3. 10E-12 3.10E-12 3.10E-12 3. 10E-12 3.10E-12 3.10E-12 3.10E-12 3. 10E-12 3. 10E-12 3.10E-12 3. 10E-12 3. 10E-12 Total 6.67E-07 4.93E-07 4.52E-07 4.16E-07 3.84E-07 3.57E-07 3.32E-07 3.10E-07 2.90E-07 2.72E-07 2.55E-07 2.40E-07 2.26E-07 Page 28 of 55 g ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at Excel/ence-fvety pmjecl. Every day. VYNPS REVISION 1 7.2 Activity limits 7.2.1 Vessel Internals Stainless Steel Components Using the equations shown in Section 6.2, activity limits are determined for the core shroud (CS) and vessel cladding (VC). Table 7-3 and Table 7-4 show a detailed summary of the computation for the CS at 2 and 16 years post-shutdown decay, respectively.

Activity limit calculations are listed in this document out to 16 years post shutdown, i.e. end of 2030, but the spreadsheet contains additional times out to 26 years post shutdown or end of 2040. The other stainless steel activity limit computations can be found in worksheet Computations-C starting at row 7 columns B through FE as a function of shutdown time. It is important to note that for stainless steel, 99% of the dose and activity limits are primarily determined by Co-60, Ni-63, and Fe-55. These are the key nuclides for reactor internals stainless steel. Activity limit summaries for the reactor in-core and vessel cladding stainless steels as a function of time are provided in Table 7-5 and Table 7-6. 5 5 Note that component activities in these table don't necessarily add up to the indicated total due to rounding and the number of significant digits shown. Page 29 of 55 g ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at Exi:effence-frery project. Every day. VYNPS REVISION 1 Table 7-3 Detailed Summary of Curie Limit Calculation for Core Shroud at 2 yr Activity Dose i % of Act. %of Radionuclide (Ci) (mremfyr)

Dose Limit Limit H-3 1.16E-05 5.60E-04 0.001 3.33E-04 0.018 C-14 7.30E-06 4.27E-03 0.004 2.09E-04 0.011 Cl-36 1.60E-07 O.OOE+OO 0.000 4.59E-06 0.000 Ar-39 1.89E-08 O.OOE+OO 0.000 5.42E-07 0.000 Ca-41 1.40E-09 1.12E-04 0.000 4.02E-08 0.000 Mn-53 4.60E-10 O.OOE+OO 0.000 1.32E-08 0.000 Mn-54 1.64E-04 8.87E-02 0.085 4.71E-03 0.249 Fe-55 3.53E-02 6.80E+OO 6.506 1.0lE+OO 53.679 Ni-59 4.30E-05 3.78E-02 0.036 1.23E-03 0.065 Co-60 2.46E-02 1.58E+01 15.126 7.06E-01 37.406 Ni-63 5.62E-03 8.17E+01 78.142 1.61E-01 8.545 Zn-65 1.38E-05 3.14E-02 0.030 3.95E-04 0.021 Se-79 1.00E-10 9.09E-07 0.000 2.87E-09 0.000 Kr-81 1.60E-11 O.OOE+OO 0.000 4.59E-10 0.000 Kr-85 5.lOE-08 0.00E+OO 0.000 1.46E-06 0.000 Sr-90 1.43E-07 5.55E-02 0.053 4.lOE-06 0.000 Nb-92m 4.SOE-14 O.OOE+OO 0.000 1.29E-12 0.000 Zr-93 1.00E-11 7.58E-10 0.000 2.87E-10 0.000 Mo-93 7.70E-08 8.03E-05 0.000 2.21E-06 0.000 Nb-94 6.31E-08 0.00E+OO 0.000 1.81E-06 0.000 Tc-99 1.SOE-08 3.71E-05 0.000 4.30E-07 0.000 AQ-108m 1.98E-08 0.00E+OO 0.000 5.68E-07 0.000 Sn-121m 7.41E-10 0.00E+OO 0.000 2.13E-08 0.000 1-129 4.20E-14 7.45E-07 0.000 1.20E-12 0.000 Ba-133 6.SOE-07 O.OOE+OO 0.000 1.87E-05 0.001 Cs-134 1.22E-06 1.23E-02 0.012 3.51E-05 0.002 Cs-135 2.70E-12 5.53E-09 0.000 7.75E-11 0.000 Cs-137 1.43E-07 1.51E-03 0.001 4.llE-06 0.000 Pm-145 2.87E-10 O.OOE+OO 0.000 8.22E-09 0.000 Sm-146 2.90E-17 O.OOE+OO 0.000 8.32E-16 0.000 Sm-151 3.74E-09 5.53E-07 0.000 1.07E-07 0.000 Eu-152 1.98E-14 8.29E-11 0.000 5.69E-13 0.000 Eu-154 7.77E-07 3.37E-03 0.003 2.23E-05 0.001 Eu-155 2.72E-07 4.54E-04 0.000 7.81E-06 0.000 Tb-158 3.77E-10 O.OOE+OO 0.000 1.08E-08 0.000 Ho-166m 2.80E-08 1.96E-04 0.000 8.02E-07 0.000 Page 30 of 55 lfj; ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at Excellence-Every projecr. Every day. VYNPS REVISION 1 Activity Dose_i % of Act. % of Radionuclide (Ci) (mrem/yr)

Dose Limit Limit Hf-178m 3.54E-08 O.OOE+OO 0.000 1.02E-06 0.000 Pb-205 2.90E-13 O.OOE+OO 0.000 8.32E-12 0.000 U-233 1.60E-10 1.15E-06 0.000 4.59E-09 0.000 Pu-239 2.70E-09 3.60E-04 0.000 7.75E-08 0.000 Total 0.065752 104.5644 100 1.886453 100 Table 7-4 Summary of Curie Limit Calculation for Core Shroud at 16 yr Activity Dose_i % of Act. % of Radionuclide (Ci) (mrem/yr)

Dose Limit Limit H-3 5.30E-06 2.55E-04 0.000 2.07E-04 0.053 C-14. 7.29E-06 4.26E-03 0.006 2.85E-04 0.073 Cl-36 1.60E-07 0.00E+OO 0.000 6.26E-06 0.002 Ar-39 1.82E-08 0.00E+OO 0.000 7.14E-07 0.000 Ca-41 1.40E-09 1.12E-04 0.000 5.48E-08 0.000 Mn-53 4.60E-10 0.00E+OO 0.000 1.80E-08 0.000 Mn-54 1.95E-09 1.05E-06 0.000 7.63E-08 0.000 Fe-55 9.70E-04 l.87E-01 0.244 3.80E-02 9.696 Ni-59 4.30E-05 3.78E-02 0.049 1.68E-03 0.430 Co-60 3.90E-03 2.51E+OO 3.275 1.53E-01 38.996 Ni-63 5.08E-03 7.39E+Ol 96.370 1.99E-01 50.740 Zn-65 6.74E-12 1.53E-08 0.000 2.64E-10 0.000 Se-79 1.00E-10 9.09E-07 0.000 3.91E-09 0.000 Kr-81 1.60E-11 0.00E+OO 0.000 6.26E-10 0.000 Kr-85 2.06E-08 0.00E+OO 0.000 8.07E-07 0.000 Sr-90 1.02E-07 3.98E-02 0.052 4.0lE-06 0.001 Nb-92m 4.50E-14 O.OOE+OO 0.000 1.76E-12 0.000 Zr-93 1.00E-11 7.58E-10 0.000 3.91E-10 0.000 Mo-93 7.68E-08 8.0lE-05 0.000 3.00E-06 0.001 Nb-94 6.31E-08 0.00E+OO 0.000 2.47E-06 0.001 Tc-99 1.50E-08 3.71E-05 0.000 5.87E-07 0.000 Ag-108m 1.83E-08 O.OOE+OO 0.000 7.17E-07 0.000 Sn-121m 6.21E-10 O.OOE+OO 0.000 2.43E-08 0.000 1-129 4.20E-14 7.45E-07 0.000 1.64E-12 0.000 Ba-133 2.63E-07 O.OOE+OO 0.000 1.03E-05 0.003 Cs-134 1.llE-08 1.12E-04 0.000 4.34E-07 0.000 Cs-135 2.70E-12 5.53E-09 0.000 1.06E-10 0.000 Cs-137 1.04E-07 1.09E-03 0.001 4.07E-06 0.001 Page 31 of 55 Q ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at Excellence-Every project Every day. VYNPS REVISION 1 Activity Dose_i % of Act. % of Radionuclide (Ci) (mrem/vr)

Dose Limit Limit Pm-145 1.66E-10 O:OOE+OO 0.000 6.49E-09 0.000 Sm-146 2.90E-17 O.OOE+OO 0.000 1.14E-15 0.000 Sm-151 3.36E-09 4.96E-07 0.000 1.32E-07 0.000 Eu-152 9.57E-15 4.00E-11 0.000 3.75E-13 0.000 Eu-154 2.58E-07 1.12E-03 0.001 1.0lE-05 0.003 Eu-155 3.85E-08 6.42E-05 0.000 1.SlE-06 0.000 Tb-158 3.53E-10 O.OOE+OO 0.000 1.38E-08 0.000 Ho-166m 2.77E-08 1.95E-04 0.000 1.09E-06 0.000 Hf-178m 2.59E-08 O.OOE+OO 0.000 1.0lE-06 0.000 Pb-205 2.90E-13 O.OOE+OO 0.000 1.14E-11 0.000 U-233 1.60E-10 1.lSE-06 0.000 6.26E-09 0.000 Pu-239 2.70E-09 3.60E-04 0.000 1.06E-07 0.000 Total 0.010008 76.63544 100 0.391784 100 Page 32 of 55 ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-001 Scheme at VYNPS lixcelfence-frery project. £very day. REVISION 1 Table 7-5 Summary of Curie Limit Calculation for CS as a Function of Time Time lvrl Radionu-elide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 H-3 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 C-14 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Cl-36 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ar-39 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ca-41 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mn-53 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mn-54 0.005 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Fe-55 1.013 0.522 0.416 0.330 0.261 0.206 0.162 0.128 0.101 0.079 0.062 0.049 0.038 Ni-59 0.001 0.001 0.001 0.001 0.001 0.002 0.002 0.002 0.002 0.002 0.002 0.002 0.002 Co-60 0.706 0.530 0.478 0.430 0.385 0.345 0.308 0.275 0.245 0.218 0.194 0.172 0.153 Ni*63 0.161 0.176 0.179 0.183 0.186 0.188 0.190 0.192 0.194 0.195 0.197 0.198 0.199 Zn-65 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Se-79 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Kr-81 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Kr-85 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sr-90 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Nb-92m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Zr-93 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mo-93 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Nb-94 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Tc-99 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ag-108m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Page 33 of 55 t) ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-001 6xcellence-EYery project. tl'ery day. Scheme at VYNPS REVISION 1 Time (yr) Radionu-elide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 Sn-121m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 1-129 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ba-133 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Cs-134 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Cs-135 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Cs-137 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pm-145 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sm-146 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sm-151 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Eu-152 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Eu-154 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Eu-155 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Tb-158 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ho-166m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Hf-178m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pb-205 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 U-233 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pu-239 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Total 1.886 1.230 1.075 0.944 0.834 0.741 0.663 0.597 0.542 0.494 0.455 0.421 0.392 Page 34 of 55 g) ENERCON *xi:el/ence-livery project. Every day. Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 Table 7-6 Summary of Curie Limit Calculation for VC as a Function of Time Time (vr) Radio nu-elide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 H-3 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 C-14 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Cl-36 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ar-39 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ca-41 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mn-53 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mn-54 0.016 0.002 0.001 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Fe-55 0.991 0.513 0.409 0.325 0.257 0.203 0.160 0.126 0.099 0.078 0.061 Ni-59 0.001 0.001 0.001 0.002 0.002 0.002 0.002 0.002 0.002 0.002 0.002 Co-60 0.745 0.562 0.507 0.456 0.410 0.367 0.328 0.293 0.261 0.232 0.207 Ni-63 0.159 0.174 0.178 0.182 0.185 0.187 0.189 0.191 0.193 0.195 0.196 Zn-65 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Se-79 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Kr-81 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Kr-85 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sr-90 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Nb-92m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Zr-93 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mo-93 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Nb-94 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Tc-99 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ao-108m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sn-121m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Page 35 of 55 15.00 16.00 0.001 0.001 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.048 0.038 0.002 0.002 0.184 0.163 0.197 0.198 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 (j ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-001 lixcellence-li¥<ry project £very day. Scheme at VYNPS REVISION 1 Time (yr) Radio nu-elide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 1-129 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ba-133 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Cs-134 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Cs-135 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Cs-137 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pm-145 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sm-146 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sm-151 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Eu-152 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Eu-154 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Eu-155 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.600 0.000 0.000 0.000 0.000 0.000 Tb-158 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ho-166m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Hf-178m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pb-205 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 U-233 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pu-239 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Total 1.915 1.254 1.098 0.966 0.854 0.760 0.681 0.613 0.556 0.508 0.467 0.432 0.402 Page 36 of 55 El Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ENERCON ISFSl-Only EAL Scheme at 8'cellence-Every projecr. Every day. VYNPS REVISION 1 7.2.2 Bio-shield Concrete Using the equations shown in Section 6.2, activity limits are determined for the bio-shield concrete inner edge (BS-IE), 10 cm depth (BS-10), 20 cm depth (BS-20), 30 cm depth (BS-30), and 60 cm depth (BS-60). Table 7-7 and Table 7-8 show a detailed summary of the computation for the BS-IE at 2 and 16 years post-shutdown decay periods, respectively.

The other concrete activity limit computations can be found in worksheet Computations-a starting at row 106 columns B through FE as a function of shutdown time. It is important to note that for the bio-shield, the dose and activity limits are primarily determined by H-3, Ca-41, Fe-55, Co-60, Eu-152, and Eu-154. These are the key nuclides for bio-shield concrete.

80 to 90% of the dose is from Ca-41 and Eu-152, while 90% of the activity is from H-3 and Fe-55. Activity limit summaries for the bio-shield concretes as a function of time are provided in Table 7-9, Table 7-10, Table 7-11, Table 7-12, and Table 7-13.6 6 Note that component activities in these table don't necessarily add up to the indicated total due to rounding and the number of significant digits shown. Page 37 of 55 D ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at Exce//ence-fvery project. Every day. VYNPS REVISION 1 Table 7-7 Detailed Summary of Curie Limit Calculation for Bio-shield Inner Edge at2yr Radionuclide Activity Dose_i % of Act. %of (Ci) (mrem/yr)

Dose Limit Limit H-3 4.38E-07 2.11 E-05 7.685 4.78E+OO 65.679 C-14 1.70E-10 9.95E-08 0.036 1.86E-03 0.025 Cl-36 1.10E-11 O.OOE+OO 0.000 1.20E-04 0.002 Ar-39 4.68E-09' O.OOE+OO 0.000 5.11E-02 0.701 Ca-41 1.10E-09 8.77E-05 31.926 1.20E-02 0.165 Mn-53 3.80E-15 O.OOE+OO 0.000 4.15E-08 0.000 Mn-54 9.68E-10 5.24E-07 0.191 1.06E-02 0.145 Fe-55 1.73E-07 3.34E-05 12.178 1.90E+OO 26.018 Ni-59 1.60E-12 1.41E-09 0.001 1.75E-05 0.000 Co-60 2.15E-08 1.38E-05 5.040 2.35E-01 3.228 Ni-63 1.97E-10 2.87E-06 1.044 2.15E-03 0.030 Zn-65 2.50E-10 5.71E-07 0.208 2.74E-03 0.038 . Se-79 3.20E-16 2.91 E-12 0.000 3.50E-09 0.000 Kr-81 7.20E-19 O.OOE+OO 0.000 7.87E-12 0.000 Kr-85 5.54E-12 O.OOE+OO 0.000 6.05E-05 0.001 Sr-90 4.10E-12 1.59E-06 0.579 4.48E-05 0.001 Nb-92m 3.70E-19 O.OOE+OO 0.000 4.04E-12 0.000 Zr-93 2.90E-15 2.20E-13 0.000 3.17E-08 0.000 Mo-93 9.40E-14 9.81 E-11 0.000 1.03E-06 0.000 Nb-94 6.10E-13 0.00E+OO 0.000 6.66E-06 0.000 Tc-99 2.20E-14 5.44E-11 0.000 2.40E-07 0.000 Ag-108m 3.07E-13 O.OOE+OO 0.000 3.35E-06 0.000 Sn-121m 1.17E-13 O.OOE+OO 0.000 1.28E-06 0.000 1-129 1.30E-18 2.3'1 E-11 0.000 1.42E-11 0.000 Ba-133 1.14E-10 O.OOE+OO 0.000 1.25E-03 0.017 Cs-134 4.34E-10 4.37E-06 1.591 4.74E-03 0.065 Cs-135 9.90E-17 2.03E-13 0.000 1.08E-09 0.000 Cs-137 5.06E-12 5.33E-08 0.019 5.53E-05 0.001 Pm-145 5.36E-13 O.OOE+OO 0.000 5.86E-06 0.000 Sm-146 8.20E-20 O.OOE+OO 0.000 8.96E-13 0.000 Sm-151 1.18E-10 1.75E-08 0.006 1.29E-03 0.018 Eu-152 2.16E-08 9.04E-05 32.931 2.36E-01 3.244 Eu-154 4.01E-09 1.74E-05 6.337 4.39E-02 0.602 Eu-155 1.06E-10 1.76E-07 0.064 1.16E-03 0.016 Tb-158 4.76E-14 O.OOE+OO 0.000 5.20E-07 0.000 Page 38 of 55 a Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ENERCON ISFSl-Only EAL Scheme at face/fence-Every projecr. Every day. VYNPS REVISION 1 Radionuclide Activity Dose_i %of Act. % of (Ci) (mrem/yr)

Dose Limit Limit Ho-166m 5.09E-12 3.57E-08 0.013 5.57E-05 0.001 Hf-178m 2.58E-11 O.OOE+OO 0.000 2.82E-04 0.004 Pb-205 3.40E-17 O.OOE+OO 0.000 3.71E-10 0.000 U-233 2.20E-13 1.58E-09 0.001 2.40E-06 0.000 Pu-239 3.10E-12 4.13E-07 0.151 3.39E-05 0.000 Total 6.67E-07 0.000275 100 7.284725 100 Table 7-8 Detailed Summary of Curie Limit Calculation for Bio-shield Inner Edge at 16 yr Radionuclide Activity Dose_i %of Act. %of (Ci) (mrem/vr)

Dose Limit Limit H-3 2.00E-07 9.62E-06 6.236 3.88E+OO 88.421 C-14 1.70E-10 9.93E-08 0.064 3.30E-03 0.075 Cl-36 1.10E-11 0.00E+OO 0.000 2.14E-04 0.005 Ar-39 4.51E-09 O.OOE+OO 0.000 8.77E-02 1.998 Ca-41 1.10E-09 8.77E-05 56.833 2.14E-02 0.487 Mn-53 3.80E-15 O.OOE+OO 0.000 7.39E-08 0.000 Mn-54 1.15E-14 6.22E-12 0.000 2.24E-07 0.000 Fe-55 4.77E-09 9.19E-07 0.596 9.28E-02 2.113 Ni-59 1.60E-12 1.40E-09 0.001 3.11E-05 0.001 Co-60 3.41E-09 2.20E-06 1.424 6.64E-02 1.513 Ni-63 1.78E-10 2.59E-06 1.680 3.47E-03 0.079 Zn-65 1.23E-16 2.79E-13 0.000 2.38E-09 0.000 Se-79 3.20E-16 2.91 E-12 0.000 6.22E-09 0.000 Kr-81 7.20E-19 O.OOE+OO 0.000 1.40E-11 0.000 Kr-85 2.24E-12 O.OOE+OO 0.000 4.35E-05 0.001 Sr-90 2.94E-12 1.14E-06 0.739 5.71E-05 0.001 Nb-92m 3.70E-19 O.OOE+OO 0.000 7.20E-12 0.000 Zr-93 2.90E-15 2.20E-13 0.000 5.64E-08 0.000 Mo-93 9.37E-14 9.78E-11 0.000 1.82E-06 0.000 Nb-94 6.10E-13 O.OOE+OO 0.000 1.19E-05 0.000 Tc-99 2.20E-14 5.44E-11 0.000 4.28E-07 0.000 Ag-108m 2.84E-13 O.OOE+OO 0.000 5.53E-06 0.000 Sn-121m 9.81E-14 O.OOE+OO 0.000 1.91E-06 0.000 1-129 1.30E-18 2.31E-11 0.000 2.53E-11 0.000 Page 39 of 55 C) ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at Ex1.:eltence-fvery projec.r.

Every day. WNPS REVISION 1 Radionuclide Activity Dose_i %of Act. %of (Ci) (mrem/yr)

Dose Limit Limit Ba-133 4.63E-11 O.OOE+OO 0.000 9.00E-04 0.021 Cs-134 3.92E-12 3.95E-08 0.026 7.63E-05 0.002 Cs-135 9.90E-17 2.03E-13 0.000 1.93E-09 0.000 Cs-137 3.67E-12 3.87E-08 0.025 7.14E-05 0.002 Pm-145 3.10E-13 O.OOE+OO 0.000 6.03E-06 0.000 Sm-146 8.20E-20 O.OOE+OO 0.000 1.59E-12 0.000 Sm-151 1.06E-10 1.57E-08 0.010 2.06E-03 0.047 Eu-152 1.04E-08 4.37E-05 28.312 2.03E-01 4.626 Eu-154 1.33E-09 5.78E-06 3.745 2.59E-02 0.590 Eu-155 1.50E-11 2.50E-08 0.016 2.91 E-04 0.007 Tb-158 4.46E-14 O.OOE+OO 0.000 8.67E-07 0.000 Ho-166m 5.05E-12 3.54E-08 0.023 9.83E-05 0.002 Hf-178m 1.89E-11 O.OOE+OO 0.000 3.67E-04 0.008 Pb-205 3.40E-17 O.OOE+OO 0.000 6.61E-10 0.000 U-233 2.20E-13 1.58E-09 0.001 4.28E-06 0.000 Pu-239 3.10E-12 4.13E-07 0.268 6.03E-05 0.001 Total 2.26E-07 0.000154 100 4.391028 100 Page 40 of 55

<<:J ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-OO 1 6xcel!ence-frery projecr. £very day. Scheme at VYNPS REVISION 1 Table 7-9 Summary of Curie Limit Calculation for BS-IE as a Function of Time Time (vrl Radionu-elide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 H-3 4.785 4.867 4.838 4.789 4.723 4.644 4.554 4.454 4.348 4.237 4.121 4.003 3.883 C-14 0.002 0.002 0.002 0.002 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 Cl-36 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ar-39 0.051 0.061 0.064 0.067 0.070 0.072 0.075 0.077 0.079 0.082 0.084 0.086 0.088 Ca-41 0.012 0.014 0.015 0.016 0.017 0.017 0.018 0.019 0.019 0.020 0.020 0.021 0.021 Mn-53 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mn-54 0.011 0.001 0.001 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Fe-55 1.895 1.057 0.859 0.696 0.562 0.452 0.363 0.290 0.232 0.185 0.147 0.117 0.093 Ni-59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Co-60 0.235 0.191 0.176 0.161 0.148 0.135 0.122 0.111 0.101 0.091 0.082 0.074 0.066 Ni-63 0.002 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 Zn-65 0.003 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Se-79 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Kr-81 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Kr-85 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sr-90 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Nb-92m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Zr-93 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mo-93 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Nb-94 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Tc-99 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ao-108m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Page 41 of 55 fl ENERCON ..__ 6xcellence-frery project. Every day. Radio nu-elide 2.00 5.00 Sn-121m 0.000 0.000 1-129 0.000 0.000 Ba-133 0.001 0.001 Cs-134 0.005 0.002 Cs-135 0.000 0.000 Cs-137 0.000 0.000 Pm-145 0.000 0.000 Sm-146 0.000 0.000 Sm-151 0.001 0.002 Eu-152 0.236 0.243 Eu-154 0.044 0.042 Eu-155 0.001 0.001 Tb-158 0.000 0.000 Ho-166m 0.000 0.000 Hf-178m 0.000 0.000 Pb-205 0.000 0.000 U-233 0.000 0.000 Pu-239 0.000 0.000 Total 7.285 6.488 Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS Time (yr) 6.00 7.00 8.00 9.00 10.00 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.001 0.001 0.001 0.001 0.002 0.001 0.001 0.001 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.002 0.002 0.002 0.002 0.002 0.243 0.241 0.239 0.236 0.232 0.041 0.039 0.038 0.036 0.035 0.001 0.001 0.001 0.001 0.001 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 6.248 6.021 5.807 5.603 5.409 Page 42 of 55 CALC NO. ENTGVY036-CALC-001 REVISION 1 11.00 12.00 13.00 14.00 15.00 16.00 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.001 0.001 0.001 0.001 0.001 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.002 0.002 0.002 0.002 0.002 0.002 0.228 0.224 0.219 0.214 0.209 0.203 0.033 0.032 0.030 0.029 0.027 0.026 0.001 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 5.223 5.045 4.874 4.708 4.547 4.391 D ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-001 fixcellence-£very projecr. £very day. Scheme at VYNPS REVISION 1 Table 7-10 Summary of Curie Limit Calculation for BS-10 as a Function of Time Time (yr) Radio nu-elide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 H-3 4.980 5.020 4.976 4.913 4.832 4.739 4.635 4.523 4.405 4.283 4.157 4.030 3.901 C-14 0.002 0.002 0.002 0.002 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 Cl-36 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ar-39 0.012 0.014 0.015 0.016 0.016 0.017 0.017 0.018 0.019 0.019 0.019 0.020 0.020 Ca-41 0.013 0.015 0.016 0.017 0.018 0.018 0.019 0.020 0.020 0.021 0.021 0.022 0.022 Mn-53 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mn-54 0.003 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Fe-55 1.899 1.049 0.851 0.687 0.553 0.444 0.355 0.284 0.226 0.180 0.143 0.113 0.090 Ni-59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Co-60 0.174 0.140 0.129 0.118 0.108 0.098 0.089 0.080 0.073 0.065 0.059 0.053 0.048 Ni-63 0.002 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 Zn-65 0.002 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Se-79 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Kr-81 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Kr-85 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sr-90 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Nb-92m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Zr-93 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mo-93 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Nb-94 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Tc-99 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ag-108m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sn-121m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 1-129 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Page 43 of 55 fl ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-001 lixcellence-<very project Every day. Scheme at VYNPS REVISION 1 Time (yr) Radio nu-elide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 Ba-133 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 Cs-134 0.006 0.002 0.002 0.001 0.001 0.001 0.001 0.000 0.000 0.000 0.000 0.000 0.000 Cs-135 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Cs-137 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pm-145 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sm-146 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sm-151 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 Eu-152 0.245 0.250 0.249 0.247 0.244 0.240 0.236 0.231 0.226 0.221 0.215 0.209 0.204 Eu-154 0.025 0.023 0.023 0.022 0.021 0.020 0.019 0.018 0.018 0.017 0.016 0.015 0.014 Eu-155 0.001 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Tb-158 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ho-166m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Hf-178m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pb-205 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 U-233 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pu-239 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Total 7.366 6.523 6.269 6.029 5.802 5.586 5.380 5.183 4.995 4.814 4.640 4.471 4.308 Page 44 of 55 0 ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-OO 1 lixrellence-frery project. £very day. Scheme at VYNPS REVISION 1 Table 7-11 Summary of Curie Limit Calculation for 85-20 as a Function of Time Time Cvrl Radio nu-elide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 H-3 5.032 5.063 5.017 4.951 4.868 4.773 4.667 4.554 4.434 4.310 4.184 4.055 3.925 C-14 0.002 0.002 0.002 0.002 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 Cl-36 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ar-39 0.007 0.008 0.009 0.009 0.010 0.010 0.010 0.010 0.011 0.011 0.011 0.012 0.012 Ca-41 0.013 0.015 0.016 0.017 0.018 0.018 0.019 0.019 0.020 0.021 0.021 0.022 0.022 Mn-53 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mn-54 0.001 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Fe-55 1.865 1.028 0.834 0.673 0.542 0.435 0.348 0.278 0.221 0.176 0.140 0.111 0.088 Ni-59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Co-60 0.166 0.134 0.123 0.112 0.102 0.093 0.084 0.076 0.069 0.062 0.056 0.050 0.045 Ni-63 0.002 0.002 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 Zn-65 0.002 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Se-79 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Kr-81 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Kr-85 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 . 0.000 0.000 Sr-90 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Nb-92m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Zr-93 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mo-93 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Nb-94 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Tc-99 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ag-108m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Page 45 of 55

() ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-001 iixcellence-/ivery project. E<*ery day. Scheme at VYNPS REVISION 1 Time <vr\ Radionu-elide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 Sn-121m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 1-129 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ba-133 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 Cs-134 0.006 0.002 0.002 0.001 0.001 0.001 0.001 0.000 0.000 0.000 0.000 0.000 0.000 Cs-135 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Cs-137 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pm-145 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sm-146 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sm-151 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 Eu-152 0.250 0.254 0.253 0.251 0.248 0.244 0.239 0.235 0.229 0.224 0.218 0.212 0.206 Eu-154 0.022 0.021 0.020 0.019 0.019 0.018 0.017 0.016 0.016 0.015 0.014 0.013 0.013 Eu-155 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Tb-158 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000. 0.000 Ho-166m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Hf-178m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pb-205 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 U-233 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pu-239 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Total 7.371 6.534 6.281 6.042 5.815 5.599 5.394 5.197 5.009 4.828 4.653 4.484 4.321 Page 46 of 55 ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-001 project. Every day. Scheme at VYNPS REVISION 1 Table 7-12 Summary of Curie Limit Calculation for BS-30 as a Function of Time Time (yr) Radionu-elide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 H-3 5.186 5.229 5.185 5.118 5.035 4.937 4.829 4.712 4.588 4.460 4.329 4.196 4.062 C-14 0.002 0.002 0.002 0.002 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 Cl-36 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ar-39 0.005 0.006 0.007 0.007 0.007 0.008 0.008 0.008 0.008 0.008 0.009 0.009 0.009 Ca-41 0.013 0.015 0.016 0.017 0.018 0.018 0.019 0.020 0.020 0.021 0.021 0.022 0.022 Mn-53 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mn-54 0.001 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Fe-55 1.940 1.072 0.870 0.702 0.565 0.454 0.363 0.290 0.231 0.184 0.146 0.116 0.092 Ni-59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Co-60 0.171 0.137 0.126 0.115 0.105 0.096 0.087 0.079 0.071 0.064 0.058 0.052 0.046 Ni-63 0.002 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 Zn-65 0.002 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Se-79 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Kr-81 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Kr-85 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sr-90 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Nb-92m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Zr-93 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mo-93 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Nb-94 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Tc-99 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ag-108m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sn-121m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Page 47 of 55 (J ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-OO 1 lixcellence-f:very project E<'ery day. Scheme at VYNPS REVISION 1 Time (vr) Radio nu-elide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 1-129 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ba-133 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 Cs-134 0.006 0.003 0.002 0.001 0.001 0.001 0.001 0.000 0.000 0.000 0.000 0.000 0.000 Cs-135 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Cs-137 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pm-145 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sm-146 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sm-151 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 Eu-152 0.246 0.251 0.250 0.248 0.245 0.241 0.237 0.232 0.227 0.221 0.216 0.210 0.204 Eu-154 0.020 0.019 0.019 0.018 0.017 0.017 0.016 0.015 0.014 0.014 0.013 0.012 0.012 Eu-155 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Tb-158 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ho-166m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Hf-178m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pb-205 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 U-233 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pu-239 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Total 7.596 6.741 6.481 6.235 6.001 5.779 5.567 5.364 5.169 4.981 4.800 4.625 4.456 Page 48 of 55 I Q ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-001 lixcel/ence-frery project Every day. Scheme at VYNPS REVISION 1 Table 7-13 Summary of Curie Limit Calculation for BS-60 as a Function of Time Time (vr) Radio nu-elide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 H-3 5.099 5.137 5.092 5.026 4.944 4.848 4.741 4.627 4.506 4.381 4.252 4.122 3.991 C-14 0.002 0.002 0.002 0.002 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 Cl-36 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ar-39 0.009 0.010 0.011 0.011 0.012 0.012 0.012 0.013 0.013 0.013 0.014 0.014 0.014 Ca-41 0.013 0.015 0.016 0.017 0.018 0.018 0.019 0.019 0.020 0.021 0.021 0.022 0.022 Mn-53 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mn-54 0.002 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Fe-55 1.906 1.052 0.853 0.689 0.555 0.445 0.356 0.284 0.227 0.180 0.143 0.114 0.090 Ni-59 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Co-60 0.162 0.131 0.120 0.110 0.100 0.091 0.083 0.075 0.068 0.061 0.055 0.049 0.044 Ni-63 0.002 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 0.003 Zn-65 0.002 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Se-79 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Kr-81 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Kr-85 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sr-90 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Nb-92m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Zr-93 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Mo-93 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Nb-94 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Tc-99 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ai:i-108m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sn-121m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Page 49 of 55 (j ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-001 EX<ellence-Every project Every day. Scheme at VYNPS REVISION 1 Time (yr) Radio nu-elide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 1-129 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ba-133 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 Cs-134 0.006 0.002 0.002 0.001 0.001 0.001 0.001 0.000 0.000 0.000 0.000 0.000 0.000 Cs-135 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Cs-137 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pm-145 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sm-146 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Sm-151 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 0.001 Eu-152 0.251 0.256 0.255 0.252 0.249 0.245 0.241 0.236 0.231 0.225 0.220 0.214 0.208 Eu-154 0.021 0.019 0.019 0.018 0.018 0.017 0.016 0.015 0.015 0.014 0.013 0.012 0.012 Eu-155 0.000 0.000 a.boo 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Tb-158 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Ho-166m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Hf-178m 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pb-205 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 U-233 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Pu-239 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Total 7.477 6.631 6.376 6.134 5.904 5.686 5.478 5.279 5.088 4.904 4.727 4.556 4.390 Page 50 of 55 Q ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at Extellence-Every project. Every day. VYNPS REVISION 1 8.0 Computer Software Microsoft Excel Visual Basic (VB) software was used to calculate the results in this evaluation.

Two macro-enabled workbooks RG1.109.xlsm and ENTGVY036-CALC-001.xlsm were utilized.

RG1.109.xlsm was used to compute activated radio-nuclide dose conversion factors not provided in the VYNPS ODCM. This is discussed and verified in Appendix A and B, respectively.

In Appendix B, a comparison is made to GASPAR II [11] provided output, but the software itself was not utilized.

Curie limits for in-core activated steel and bio-shield concrete were computed with ENTGVY036-CALC-001.xlsm which is verified by standard Excel cell based equations in Appendix C. 9.0 Results and Conclusion 9.1 Activity Limits Summary Curie limits have been determined for VYNPS reactor core internal activated stainless steel and surrounding activated bio-shield concrete to preclude the EAB dose from exceeding twice the ODCM dose rate limit, or 3000 mrem/yr. The final activity limits for steel and concrete are based on the material which produces the minimum limits and those nuclides which produce 99% of the activity and/or dose if released.

In the case of core internal activated stainless steel, 99% of the dose and activity limits are primarily determined by Co-60, Ni-63, and Fe-55. These are the key radionuclides for sample characterization and for limiting radioactivity accumulation in open containers and filters from decommissioning operations involving reactor core internals.

Recommended activity limits for such activated steel as a function of time from shutdown is shown in Table 9-1, below. These are based on the key radionuclides and the core shroud activities given in Table 7-5, which produces the minimum activity limits for activated in-core stainless steel. In the case of activated bio-shield concrete, 99% of the dose and activity limits are primarily determined by H-3, Ca-41, Co-60, Fe-55, Eu-152, and Eu-154. 80 to 90% of the dose is from Ca-41 and Eu-152, while 90% of the activity is from H-3 and Fe-55. Page 51of55 Kl Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ENERCON ISFSl-Only EAL Scheme at Excellence-E.Yery project. Every day, VYNPS REVISION 1 These are the key radionuclides for sample characterization and for limiting radioactivity accumulation in open containers and filters from decommissioning operations involving bio-shield concrete up to 60 cm in depth. Recommended activity limits as a function of time from shutdown for such bio-shield concrete are shown in Table 9-2, below. These are based on the key radionuclides and the bio-shield edge activities given in Table 7-9, which produces the minimum activity limits for bio-shield concrete.

Page 52 of 55 (J ENERCON Curie Limits in Support of an ISFSl-Only EAL CALC NO. ENTGVY036-CALC-001 Scheme at VYNPS lixcef/ence-fvery project. Every day. REVISION 1 Table 9-1 Activity Limits (Ci) for Core Internals Steel Based on Core Shroud Activities Time (yr) Radionu-elide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 Fe-55 1.013 0.522 0.416 0.330 0.261 0.206 0.162 0.128 0.101 0.079 0.062 0.049 0.038 Co-60 0.706 0.530 0.478 0.430 0.385 0.345 0.308 0.275 0.245 0.218 0.194 0.172 0.153 Ni-63 0.161 0.176 0.179 0.183 0.186 0.188 0.190 0.192 0.194 0.195 0.197 0.198 0.199 Total 1.880 1.228 1.073 0.943 0.832 0.739 0.660 0.595 0.540 0.492 0.453 0.419 0.390 Table 9-2 Activity Limits (Ci) for Bio-Shield Concrete Based on Bio-Shield Edge Activities Time (yr) Radionu-elide 2.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 16.00 H-3 4.785 4.867 4.838 4.789 4.723 4.644 4.554 4.454 4.348 4.237 4.121 4.003 3.883 Ca-41 0.012 0.014 0.015 0.016 0.017 0.017 0.018 0.019 0.019 0.020 0.020 0.021 0.021 Fe-55 1.895 1.057 0.859 0.696 0.562 0.452 0.363 0.290 0.232 0.185 0.147 0.117 0.093 Co-60 0.235 0.191 0.176 0.161 0.148 0.135 0.122 0.111 0.101 0.091 0.082 0.074 0.066 Eu-152 0.236 0.243 0.243 0.241 0.239 0.236 0.232 0.228 0.224 0.219 0.214 0.209 0.203 Eu-154 0.044 0.042 0.041 0.039 0.038 0.036 0.035 0.033 0.032 0.030 0.029 0.027 0.026 Total 7.207 6.414 6.172 5.942 5.727 5.520 5.324 5.135 4.956 4.782 4.613 4.451 4.292 Page 53 of 55 g ENERCON Curie Limits in Support of an ISFSl-Only EAL Scheme at Excellence-Every pmject. Everyday.

VYNPS 9.2 Examples of Application Example 1 CALC NO. ENTGVY036-CALC-001 REVISION 1 A sample of core shroud fines from cutting operations shows the following activity distribution at 15 years after shutdown:

Radionuclide

µCi/g Fe-55 78.0 Co-60 90.2 Ni-63 23.2 Total 191.4 From Table 9-1, the activity limit for core internals including the shroud at 15 years decay is 0.419 Ci. Then the amount of material allowed in a container or filter is: "* µCi* 1

lkg _ 0.419 C1 1E+6 Ci 191.4 µCi/g 1000 g -2.19 kg Example 2 A sample of bio-shield concrete from cutting operations shows the following activity distribution at 1 O years post shutdown:

Radionuclide

µCi/g H-3 112.35 Ca-41 0.6 Co-60 1.65 Fe-55 3.15 Eu-152 5.7 Eu-154 0.9 Total 124.35 From Table 9-2, the activity limit for bioshield concrete 7 at 10 years decay is 5.324 Ci. Then the amount of material allowed in a container or filter is: 7 Table 9-2 is based on the bioshield edge activities which produce the minimum activity limits. Page 54 of 55 0 ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at Excellence-Every project. Every day. VYNPS REVISION 1 µCi 1 lkg 5.324 Ci*1E+6 Ci

124.35 µCi/g

1000 g 42.8 kg Example 3 At 16 years post shutdown, a material container contains 0.1 Ci of activated steel from cutting operations.

VYNPS operations wants to add concrete from bio-shield cutting. At 16 years of decay, the activity limis for steel and bioshield concrete are 0.390 Ci and 4.292 Ci from Table 9-1and Table 9-2, respectively.

Given the 0.1 Ci of activated steel already in the container, the amount of concrete activity allowed is: [ 0.1Ci-] 1-0.390 Ci *4.292 Ci=3.191 Ci The amount of concrete, in kg, is determined from the sample concrete activity and using a 3.191 Ci limit instead of 5.324 Ci as shown in Example 2. Page 55 of 55 Q ENERCON Curie Limits in Support of an CALC NO. ENTGVY036-CALC-001 ISFSl-Only EAL Scheme at Excellence-Every project. Every day. VYNPS REVISION 1 Appendix A Calculation of Additional VYNPS Dose Rate Conversion Factors Additional dose rate conversion factors were computed for several radionuclides generated from activated in-core vessel steel and activated bio-shield concrete not available in the VYNPS ODCM [3] and Areva calculation 32-9066572-000

[4]. An Excel Visual Basic Application (VBA), RG1 .109.xlsm, was developed to compute VYNPS site specific dose and dose rate conversion factors (DFG) based on: the methodology of RG 1.109 [5], the age specific radiation dose commitment factors given in NUREG-0172

[8], and the site XJQ and D/Q either for a ground or stack release. However, only the ground release is evaluated in this calculation.

The DFGs to a particular organ from inhalation of radionuclides, exposure from contamination on the ground plane, and ingestion of radionuclides are calculated for different age ranges, i.e. infant, child, teenage, and adult. The DFG from ingestion includes exposure pathways from produce, leafy vegetables, cow's milk, goat's milk, and meat. In addition, the VYNPS site specific maximum combined DFG for all pathways over all age groups and critical organs is computed as well. The VBA coding was verified against GASPAR II [11] output and VYNPS-specific dose rate conversion factors available in the References 3 and 4. See Appendix B of this calculation.

Details of the VBA code and data tables are provided in the subsequent section. A.1 Description of RG1.109.xlsm Worksheets Summary Parameters Worksheet:

Parameters worksheet is the main worksheet from which to perform computations for either comparison to GASPAR II DCFs or for generation of VYNPS DCFs. See Figure A-1. The "Calculate Generic Dose Tables" button calls the "main" subroutine.

This subroutine calculates the generic dose factors for each of the age-organ combinations.

Page A-1 of A-13 Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 ENERCON Excellence-Every projecr. Every day. REVISION 1 The " Calculate VY ODCM Tables" applies the X/Q and D/Q values (listed below the button) to the generic dose factors calculated prev i ously. To calcu l ate the VY ODCM dose rates select " VYNPS" from the pulldown option and run the " Calculate Generic Dose Tables" before applying the X/Q factors. The radionuclide list consists of two columns with the element in the first column and mass number in the second column. This is done for ease in looking up data in the reference tables. To add or remove radionuclides simply type them in or delete them , then press the " Modify Radionuclide list" button. This prompts the user to highlight the updated Radionuclide list column. Simply highlight the new radionuclide table , mak i ng sure there are not blanks between radionuclides and that only two columns are highlighted , and press okay. This redefines the name range that the VBA iterates through. The " VYNPS" or " GASPAR" pulldown option cycles the variables on the right through the values used in each option. To compare the generic dose factors to GASPAR , select " GASPAR" from the pulldown and click the " Calculate Generic Dose Tables" button. To compute the VYNPS dose factors VYNPS is selected. The parameters in the table on the right show several the differences between GASPAR and VY. IM!orl h t "' <>* , ... , ..... .... ..... """ ""' ""' '"' .... ""' "'°" ., .. '"" ""' C'11> 1 11 C*lnlhlf*Y'IOO(MT*llt**

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' t .. uc-o1 .,, .. , I OA .. I .,,..., "" ' ., .. ' u ' " .,. ll .... .. " " ' " l " lO " .. " . .. ,. ,. " *'"' UUtOI I " "' I ...,..., "" "' ' ' .,. I u I ' " "' .... 0 " "" ..,.,. lllll Lpoiil;QIS tn4.4'r c:anlbttnl.c

"'"' .. .., .. -,1),. .. ...... --IA."f:-Gt WlJ 6.lilQ.tli-Figure A-1 RG1.109.xlsm Worksheet Parameters Options List Pa g e A-2 o f A-1 3 ENERCON E.xcellence-fvery project Every d<Jy. Variables Worksheet:

Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 In this worksheet, every var i able is listed that is used in the calculations along with the value , or the subroutine that fetches the value (if it is a function of an element).

The variables that are linked with the " parameters" sheet are highlighted in blue. See Table A-1. Table A-1 RG1.109.xlsm Variables RG 1.109 Variable Definition Value Units Eqn. 1. Ground C-1 Plane ground plane concentration of radionu-C G(i) elide , i calculated oCilm2 Q(i) annual release of nuclide i 1 uCi/s time period over accumulation i s evalu-tb ated , which is 15 years 4.73E+08 s annual average deposition of nuclide i considering depletion 1 1/m2 A(i) decay constant of nuclide , i , decav Iookuo 1/s c conversion factor 1 OOE+06 pCi/uCi C-2 annual dose resulting from direct expo-sure to ground plane for nuclide i and mrem per uCi/(y D G(i , j) organ j calculated m2) SF shieldinq factor 1 ground exposure dose conversion factor mrem/h per DFG(i ,il for Radionuclide i and ornan i E6 Jookuo oC i/m2 c conversion factor 8760 hrs/y 2. Inhalation C-3 annual average ground level concentra-xCil tion in air of radionuclide , i (assumed) 1 uCi/m3 C-4 annual dose from inhalation from nu-elide ,i , to to organ ,j, for a person in age mrem/h per D(i ,i , al qrouo. a calculated uCi/m3 inhalation rate for person in age group , R(a) a ES lookuo m3/v in halation dose conversion factor for Radionuclide ,i, organ ,j , and age group , DFA(i , j,a) a inh lookup mrem per pCi c conversion factor 1.00E+06 pCi/uCi 3. Ingestion C-6 a.) nuclide con-centrations d(i) deoos i t ion rate from the plume calculated oCi/m2-h Page A-3 of A-1 3 ENERCON Excellence-miy p10j<<:r. Eveiy doy. RG 1.109 Eqn. in forage, pro-duce , and leafy veqetables C-5 b.) nuclide con-centrations in animal feed + milk C-10 Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 Variable Definition Value Units annual average deposition of nuclide i c'.i(i) considering depletion 1 1/m2 Q(i) annual release of nuclide i 1 uCi/s c conversion factor 1.00E+06 pCi/uCi cl elemental iodine deposition factor 0.5 (iodine only) concentration of radionuclides i n ve-gatables , (man-produce, man-LV, ani-CV(i , path) mal-forage , animal-feed) calculated pC i/kg d(i) deposition rate from the plume Eqn. C-6 pCi/m2-h fraction of Radionuclides retained on r crops 0.2 effective removal constant (decay+ decay_lookup

+ ,\E(i) weathering)

AW 1/s >.W weathering removal constant 5.83E-07 1/s time period that crops are exposed to contamination during growing (crop-t. man) E15 lookup hrs* concentration factor for uptake of radio-B1 v nuclides from soil by edible part of crops E1 lookup time period over accumulation is evalu-tb ated , which is 15 years 4.73E+08 s ,\(i) rad i oactive decay constant decay lookup 1/s agricultural productivity yield -garden Yw vegetables 2 kg/m2 agricultural productivity yield -pasture Yvp grass 0.7 kg/m2 Yvf agricultural productivity yield -feed 2 kg/m2 p effective surface density of soil 240 kg/m2 holdup time between harvest and con-th sumption E15 lookup h* Concentration of nuclide, I , in animal Cm milk calculated pCi/L Concentration of nuclide , I , in animal's Cv feed Eqn. C-11 PCi/kg average fraction of animal's int ake of E1_1ookup

& Fm nuclide I that appears in milk E2 lookup tota l amount of feed consumed by the Qf animal per day E3 lookuo ko/d average transport time from feed into tf milk to receptor 2 days ,\(i) rad i oact i ve decay constant decav lookuo 1/s Page A-4 of A-13 ENERCON RG 1.109 Eqn. C-11 c.) nuclide con-C-12 centrations in meat 4. Dose calcula-lions C-13 Carbon-14 spe-cific calcula-tions C-8 Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 Variable Definition Value Units concentration of nuclide I on pasture Cp grass eq C-5 pCi/kg Cs concentration of nuclide I in stored feed eq C-5 pCi/kq fraction of the year the animal grazes on fp pasture 0.5 fraction of daily feed that is pasture fs grass when animal grazes on pasture 1 Cf (i) concentrat ion of nuclide I in animal flesh calculated pC i/kg Fraction fo the animal's daily i ntake of Ff nuclide I that appears in kg flesh Et lookup day/kg average time from slaughter to con-ts sumption 20 days concentrat ion of nuclide I , in animals Cv feed Eon. C-11 PC ilk a total amount of feed consumed by the Qf animal per dav E3 lookup kg/d ,\(i) radioactive decay constant decay lookup 1/s DFI dose conversion factor for ingestion ina lookup mrem/y per pC i Consumption rate of food group by indi-u vidual in age group , a E5 lookup kg/y fraction of produce grown in garden of fg interest 0.76 fraction of leafy vegetables grown in fl aarden of interes t 1 cc concentration of C-14 in vegetation calculated pCi/kq Qc release rate of C-1 4 1 uC i/s X(i)/Q airborne dispersion coeffic ient 1 sedm3 p fractional eauilibrium rat io 1 fraction of total plant mass that is natu-f1 ral carbon 0.11 concentration of natura l carbon in the f2 atmosohe re 0.16 a/m3 c1 conversion factor 1.00E+06 pCi/uC i c2 convers ion factor 1.00E+03 g/kg Page A-5 of A-13 ENERCON Excellence-£-;f:ry proj<<t. Every day. RG 1.10 9 Eq n. Tri t ium Spec i f i c Calcu l at i ons C-9 Goat Va ri able C-11 B eef Cow Varia-bl e C-10 1.109 Data Worksheet:

Curi e Lim it s in Su pport of an IS FS l-O nly EAL Scheme a t VYN PS CALC NO. EN T GVY036-CALC-001 REV I SION 1 Va r ia b le Def i n i t i on V a lue Un its CT concentrat i on of tr i tium i n veaetation calculated oCi/ka H abso l ute humid i ty of the atmosphere 5.6 g/m3 Qt re l ease rate of tri tium 1 uC i/s l((i)/Q a i rborne dispe r sion coeffic i ent 1 sedm3 r at i o of trit i um co n ce n t r ation in p l a n t wa-ter to t ri t iu m concentrat i on i n atmos-f1 phere 0.5 f2 f raction of total plant mass that is water 0.7 5 c1 convers i on factor 1.00E+06 p Ci/uC i c2 convers i on factor 1.00E+03 g/kg fpg fractio n of i n take f r om past u re for goats 1 fra c t i on o f in ta k e from pas t ure for beef fpb cow 1 This wo r ksheet includes the parameter data from RG 1.109 , nuclide dose factors from NUREG-0172 and extended elemental t r ansfer facto r s from the GASPAR II. The tables that are highligh t ed with a green outline a r e named ranges in EXCEL. The n a m ed ranges are used t o selec t th e tables u s i ng lookup functions. Th ere are se v eral values highlighted on the RG 1.109 d a t a worksheet.

These are values w here GASPAR d i ffe r s fr om the VY recommended pa r ameters. Page A-6 of A-1 3 ENERCON btcellence-fvery pro}<cl. Every day. VY Tables Worksheet:

Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 This worksheet contains the output of the VY specific dose factor calculations.

The values are generated by the "Calculate VY ODCM Tables" macro, which reference the generic dose factors in the Age-Organ worksheets.

Age-Organ Worksheets:

These worksheets contain the generic dose factors that are calculated from the " Calculate Generic Dose Tables." VBA Macro/Procedure Summary: Sub main () This procedure is called by the " Calculate Generic Dose Tables" button. It declares all of the data ranges for the 1.109 data tables , as well as sets up integer loops for age , organ , and radionuclide. All of the generic dose factors are calculated in other functions , which are called by this main subroutine. Refer to Figure A-1 and Table A-1 for detailed variable descriptions and values. Note that the generic dose factors are normalized to X/Q = 1.0 sec/m 3 and D/Q = 1.0 1/m 2. The final set of site specific dose factors are computed by procedure Sub VY (). Function Inhalation (age, organ, radionuclide)

This function returns the inhalation generic dose factors using age group a and organ j as integer inputs as well as radionuclide i as a string and using Equation C-4 of RG 1.109. This is coded based on the following equation:

Eqn. A-1 Where: x Q is the annual dispersion factor (sec/m 3) R a is the annual breathing rate for age group a (m 3/yr) Page A-7 of A-1 3 ENERCON Excellence-Every project. Every day. Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 DFA 1 ai i is the annual inhalation dose factor for age group a and organ j and radionucl i de i Function Ground (organ, radionuclide)

This function returns the ground exposure dose factors using organ j and radionuclide i as inputs and using Equations C-1 and C-2 of RG 1.1.09. This is coded based on the following equation: Where: D is the annual deposition factor (1/m 2) Q DFG 1 ii is the annual ground shine dose factor for organ j and radionuclide i A.i is the radionuclide i decay constant (1/sec) Sp is a shield factor tb is time period over which accumulation is evaluated (sec) 8760 is hours per year Eqn. A-2 In this case, all age groups are treated the same , and the only organs evaluated are skin and total body. The annual dose to all other organs is taken to be equivalent to the total body dose. Note for the iodines only 1/2 is deposited.

Sub Ingestion (age, organ, radionuclide)

This procedure returns all of the ingestion dose factors (milk , goat milk , meat , and vegetables) using age , organ , and radionuclide as inputs and using Equations C-5 , C-6 , C-10 , C-11 , C-12 and C-13 of RG 1.109. This is coded based on the following equations. For all radionucl i des and particulates , except H-3 and C-14 , the concentration of radionuclide i on vegetation i s: Page A-8 of A-13 Curie Limits in Support of an ISFSl-Only EAL Scheme at WNPS CALC NO. ENTGVY036-CALC-001 ENERCON E.xcellence-&ery pFOJ"Ct Every day. REVISION 1 Eqn. A-3 Where: er is the concentration of nuclide i in and on vegetation (pCi/kg) % is the annual deposition factor (1/m 2) A.i is the radionuclide i decay constant (1/sec) A.5 i is effective removal constant (decay +weathering)

(1 /sec) t e is period of crop , leafy vegetable or pasture grass exposure (sec) tb is period of long term buildup (sec) th is period of time between harvest and ingestion (sec) r is the fraction of deposited activity retained on crop, leaf vegetable or grass Biv is the concentration factor for uptake of radionuclides from soil by edible part of crops Yi is the agricultural product yield (kg/m2) P is the effective surface density of soil (kg/m2) All nuclides, except noble gases , H-3 , C-14 and the iodines , are treated as particulates with a retention factor of 0.2. For radio-iodines , the deposition factor is half since measurement indicate that only half is elemental.

However, the retention factor , r, is 1.0. The radionuclide concentrations in milk is: Eqn. A-4 Where: e;n is the concentrat i on of nuclide i in milk (pC i/liter) Page A-9 of A-1 3 Curie Limits i n Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 ENERCON Excellence-&'<ry prOJ<"'I. Every day. REVISION 1 er is the concentration of nuclide i in feed (pCi/kg) Fm is the fraction of nuclide i which appears in each liter of milk QF is amount of feed consumed by animal per day (kg/day) A.i is the nuclide decay constant (1 /sec) t 1 is the average transport time to receptor (sec) The concentration of radionuclide i in the animal feed is: C[=fp*fs* er+ (1 -fp)* Cl+ fp * (1-fs)* Cl Eqn. A-5 Where er is the concentration of radionuclide i on pasture grass (pci/kg) cis is the concentration of radionuclide i in stored feeds (pci/kg) fp is the fraction of year that animals graze on pasture fs is the fraction of daily feed that is pasture grass when animal grazes on pasture The radionuclide concentrations in meat is: Eqn. A-6 Where CF is the concentration of nuclide i in meat (pCi/kg) er is the concentration of nuclide i i n feed (pCi/kg) Fm is the fraction of nuclide i which appears in each kg of meat Qp is amo un t of feed consumed by animal per day (kg/day) A.i is the nuclide decay constant (1/sec) ts i s the average from s l aughter to consumpt ion (sec) Page A-10 of A-13 Curie Limits i n Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 ENERCON Excellence-E¥ery p r op:r. Every day. REVISION 1 Finally , the annual dose for age group a to organ j from nuclide i resulting from the ingestion of produce , milk , meat and leafy vegetables is Eqn. A-7 Where: DFiaji is the annual dose to organ j of an individual in age group a from nuclide I (mrem/yr) u-;:-, U!, U/;, are the ingestion rates of produce (fruits and grains), milk , meat and leafy vegetables for individuals in age group a (kg/yr) f 9 is the fraction of produce grown f 1 is fraction of leafy vegetables grown The Ingestion procedure also calls Functions Tritium and Carbon. Tritium()

is a function that returns the specially calculated tritium concentration using Equation C-9 of RG 1.109. This is coded based on the following equation: x Ci= Q *O. 7 5*0.5 /H Eqn. A-8 Where: H is the absolute humidity of the atmosphere (g/m3) 0.5 is the ratio of tritium concentration in plant water to tritium concentration in atmospheric water 0.75 is the fraction of total plant mass that is water Carbon() is a function that returns the spec i ally calculated carbon concentrat i on us i ng Equation C-9 of RG 1.109. Th i s is coded based on t h e follow i ng equat i on: Page A-11 of A-1 3 Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 ENERCON btceilence

-ft'!!ty pr ojecr. fvety day. REVISION 1 Eqn. A-9 Where: C[4 is the concentration of C-14 in vegetation (pCi/kg) p is the fractional equilibrium ratio 0.11 is the fraction of total plant mass that is natural carbon 0.16 is the concentration of natural carbon in the atmosphere (g/m3) Sub VY() This procedure is called by the " Calculate VY ODCM Tables" button. It calculates the specific dose factors and prints them i n the " VY Tables" worksheet.

For all radio-iodines , and particulates , it adds the inhalation generic dose factor

X/Q and the sum of the milk +meat+ vegetable+

ground* D/Q. The maximum is tracked through the "for loops" , and is printed for comparison to the tables in the Areva calculation (Reference 4). Lookup Functions Each of the data tables in RG1.109.xlsm has a separate lookup function. Given a predefined table range , each function looks up values based on the input indices. These are explained for each table in the comments. This provides a cleaner way to pull values for the equations in the main subroutine.

A.2 Additional VYNPS Dose Conversion Factors The VYNPS site specific dose and dose rate factors combining all pathways as computed by RG1.109.xlsm are shown in Table A-2. In particular, Ca-41 , Ni-59, Se-79 , Zr-93, Mo-03 , Tc-99 , Cs-135 , Sm-15 1, Eu-152 , Eu-154 , Eu-155 , Ho-166m , U-233 and Pu-239 are computed for the radio-nucl i des required for activated material , and for comparison and cross check to Reference 4 , H-3 , C-14 , Mn-54 , Fe-55 , Co-60 , Ni-63 , Zn-65 , Sr-90 , 1-129 , Cs-134 and Cs-137 are included in Table A-2 as wel l. Page A-12 of A-1 3 ENERCON f.xcellern;e-Every project. Every day. Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 Table A-2 Additional Dose and Dose Rate Factors for VYNPS Dose Factor Dose Rate Factor, DFG DFG' Radionuclide Aqe Group Orqan (mrem/Ci) (mrem/y) per (uCi/s) H3 Child Liver 5.87E-03 1.85E-01 C14 Child Bone 6.23E+OO 1.97E+02 CA41 Teen Lung 9.10E+02 2.87E+04 MN54 Teen LunQ 6.17E+OO 1.95E+02 FE55 Child Bone 2.20E+OO 6.94E+01 Nl59 Child Bone 1.00E+01 3.16E+02 C060 Teen Lung 7.18E+01 2.26E+03 Nl63 Child Bone 1.33E+02 4.19E+03 ZN65 Infant Liver 2.60E+01 8.20E+02 SE79 Infant Kidney 1.04E+02 3.27E+03 SR90 Ch il d Bone 4.43E+03 1.40E+05 ZR93 Ch i ld Bone 8.65E-01 2.73E+01 M093 Child Liver 1.19E+01 3.76E+02 TC99 Adult Gl-LLI 2.82E+01 8.89E+02 1129 Adult Thyroid 4.05E+03 1.28E+05 CS134 Child Liver 1.15E+02 3.62E+03 CS135 Child Bone 2.34E+01 7.37E+02 CS137 Child Bone 1.20E+02 3.79E+03 SM151 Child Bone 1.69E+OO 5.32E+01 EU152 Adult G l-LLI 4.77E+01 1.51E+03 EU154 Child Bone 4.95E+01 1.56E+03 EU155 Teen GI-LU 1.90E+01 6.00E+02 H0166M Child Bone 8.01 E+01 2.52E+03 U233 Teen Lung 8.20E+02 2.59E+04 PU239 Teen Bone 1.52E+04 4.80E+05 Page A-13 o f A-1 3 ENERCON Curie Limits i n Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 Appendix B Verification of RG1.109.xlsm This append ix p r ov i des a v alidation of the Exce l Visua l Bas i c App li ca t ion (VBA}, RG1.109.xlsm , used to ca l c u late cr i t i ca l organ dose (DFG) and dose rate (DFG') conversion factors for rad i onuclides with the potential to be released during VYNPS decommissioning activities. The equations from RG 1.109 and data from NUREG-0172 are entered into a macro enabled Excel workbook , RG1.109.xlsm , and uses Visual Basic for automating the calculat i ons. The VBA macros generate generic dose factors fo r each exposure pathway fo r each age group and organ combinat i on. These generic dose factors are independent of plant specific atmospher i c dispersion (x/O i) or deposition (D/Q i) values. In addition , RG1.109.xlsm can also ca l c u late the s i te specific max i mum dose factor for each age group and organ using the generic dose factors and plant specific dispersion/deposit i on coefficients. The generic dose factors generated in the calculat i on are va l idated against a sample problem , SAMPLE3.0UT , from the airborne effluent dose code GASPAR II [11]. Sample problem 3 produces normalized dose factors independent of release rate and meteorological data (X/Q). In this sample , dose factors for 26 radionuclides are computed includ i ng: H-3 , C-14 , Co-60 , Sr-90 , 1-131 , and Pu-239. This sample problem output includes all of the RG 1.109 parameters used in the GASPAR II calculation , which allows for a direct comparison to the RG1.109.xlsm macro results. All of the age-organ tables are compared with the GASPAR II SAMPLE3. OUT output to ensure that the RG1.109.xlsm macros are produc i ng appropriate results. A comparison between the GASPAR II and RG1.109.xlsm generated dose factors is provided in this appendix for the adult-total body and child-bone combinations.

The SAMPLE3. OUT adult-total body dose fac t ors a r e provide d as a n exa m p l e i n Tab l e B-1 . The calculated pe r cent d i ffe r e n ces betwee n the GASPAR SAMPLE3. OUT res ul ts and th e RG1.109.xlsm generated resu l ts is prov i ded in Tab l e B-2 fo r Ad ul t-Total Body and Tab l e B-3 fo r C hil d-Bo n e. In gene r a l , the va l ues on ly d i ffe r b y a few pe r ce nt w i th a f ew betwee n Page B-1 of B-8 ENERCON Excellence-Every proj<<t. Every day. Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 4 t o 7% different.

This is likely due to round off , and the fact that the GASPAR II results are only known to two decimal places. Overall the comparison confirms that the RG1.109.xlsm programming i s correct and is acceptable for calculating generic dose factors. Table B-1 GASPAR II Dose Factors -Adult Total Body Inhalation Ground (mrem/y)/

Plane Cow-Milk Goat-Milk Animal-Meat Vegetables Nuclide (µCi/m 3) (µC i/s-m 2) (µCi/s-m 2) (µCi/s-m 2) (µCi/s-m 2) (µCi/s-m 2) H3 7.20E+02 O.OOE+OO 2.30E+02 4.80E+02 9.90E+01 6.50E+02 C14 O.OOE+OO O.OOE+OO 7.30E+04 7.30E+04 6.7 0E+04 1.70E+05 CR51 1.00E+02 5.00E+06 6.60E+03 1.50E+03 2.50E+03 4.80E+04 MN54 6.30E+03 1.50E+09 4.40E+05 7.80E+04 6.20E+05 3.10E+07 FE55 3.90E+03 O.OOE+OO 1.10E+06 2.10E+05 1.60E+07 1.60E+07 FE59 1.10E+04 2.90E+08 6.30E+06 1.50E+06 8.40E+07 9.00E+07 C058 2.10E+03 4.10E+08 2.60E+06 5.30E+05 1.40E+07 4.50E+07 C060 1.50E+04 2.50E+10 1.10E+07 1.80E+06 6.00E+07 1.80E+08 SR89 8.70E+03 2.30E+04 9.90E+06 3.70E+07 3.00E+06 2.20E+08 SR90 5.80E+0 5 O.OOE+OO 3.70E+08 1.00E+09 1.20E+08 8.90E+09 SR91 2.50E+OO 2.30E+06 2.90E+02 1.20E+03 2.30E-12 3.50E+03 ZR95 2.30E+04 2.60E+08 4.90E+01 1.00E+01 1.40E+05 1.70E+05 RU103 6.60E+02 1.20E+08 1.00E+02 2.30E+01 1.60E+07 1.80E+06 RU106 8.70E+03 4.50E+08 7.40E+02 1.30E+02 1.30E+08 1.30E+07 AG110m 5.90E+03 3.70E+09 9.60E+06 1.70E+06 1.40E+06 3.60E+06 TE125m 4.70E+02 1.70E+06 6.70E+05 1.40E+05 2.10E+07 1.40E+07 1131 2.00E+04 9.20E+06 6.00E+07 1.40E+08 3.50E+06 8.30E+07 1133 4.50E+03 1.30E+06 5.10E+05 1.20E+06 7.BOE-02 3.20E+05 1135 2.60E+03 1.40E+06 3.10E+03 7.30E+03 1.SOE-17 1.10E+04 CS137 4.30E+05 1.40E+10 2.10E+09 8.50E+09 3.00E+08 3.20E+09 NP237 5.50E+08 5.80E+09 6.20E+05 1.00E+05 1.10E+07 2.10E+09 PU239 6.20E+08 3.30E+06 8.20E+04 1.40E+04 2.50E+05 6.90E+08 PU240 6.20E+08 5.40E+06 8.20E+04 1.40E+04 2.50E+05 6.90E+08 PU241 1.00E+07 1.20E+07 1.40E+03 2.40E+02 4.40E+03 1.20E+07 AM24 1 5.40E+08 7.30E+08 5.80E+05 9.70E+04 1.00E+07 2.00E+09 Page B-2 of B-8 ENERCON Excellence-Every proj<<t. Every day. Curie Limits i n Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 Table B-2 Comparison GASPAR II and RG1.109.xlsm -Adult Total Body Dose Factors (Percent Differences)

GROUND COW-GOAT-ANIMAL-NUCLIDE INHALATION PLANE MILK MILK MEAT VEGETABLES H3 -0.22% 0.00% 0.89% -1.38% -0.47% -0.40% C14 0.00% 0.00% -0.50% -0.50% -0.63% -0.69% CR51 0.00% -0.32% 0.57% 2.05% 1.68% -0.18% MN54 -0.06% -1.15% 0.13% -0.24% -0.53% -0.17% FESS 1.13% 0.00% 0.52% -2.38% 1.35% -2.56% FE59 -4.00% 0.69% 0.06% -0.54% 0.12% 0.20% C058 -1.33% -0.73% -0.92% -0.33% 1.48% 0.73% C060 -1.33% -0.77% -4.02% -2.15% -0.48% 2.66% SR89 0.23% 0.61% 0.11% 0.68% 1.20% -2.05% SR90 -0.55% 0.00% 1.30% 3.93% -1.02% 0.29% SR91 0.16% -0.09% 0.45% 1.95% 4.93% 0.85% ZR95 1.22% 1.08% 0.89% 2.81% 1.00% 1.90% RU103 -0.24% -3.38% 3.45% -0.23% 0.84% -1.82% RU106 0.23% 0.46% -0.48% -1.62% -1.42% 1.40% AG110m 0.75% -0.12% -0.03% -1.28% 0.28% 0.43% TE125m -0.60% -1.98% -0.57% -2.96% -0.72% 2.60% 1131 2.40% 0.18% -0.57% 2.25% -0.95% -0.47% 1133 0.44% 1.08% 0.96% 2.98% 2.43% 0.02% 1135 -1.23% -3.57% -0.86% 1.04% 6.62% -2.69% CS137 -0.47% -0.31% 0.22% 0.20% 0.23% 0.02% NP237 -0.07% 0.07% -0.01% 2.75% -1.71% 1.91% PU239 0.00% -0.78% -0.01% -1.79% 0.89% -0.14% PU240 -0.26% -0.30% -0.01% -1.79% 0.89% -0.15% PU241 3.20% 1.92% 1.07% -0.72% -1.03% -0.87% AM241 -0.59% 0.60% 0.08% 0.36% 2.03% -2.45% Page B-3 of B-8 ENERCON Exceilence-£..ry proje<r. Every cloy. Cu ri e Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 Table B-3 Comparison GASPAR II and RG1.109.xlsm

-Child Bone Dose Factors (Percent Differences)

GROUND COW-GOAT-ANIMAL-NUCLIDE INHALATION PLANE MILK MILK MEAT VEGETABLES H3 0.00% 0.00% 0.00% 0.00% 0.00% 0.00% C14 0.00% 0.00% -3.1 1 % -3.11 % -0.25% -1.75% CR51 0.00% -0.32% 0.00% 0.00% 0.00% 0.00% MN54 0.00% -1.15% 0.00% 0.00% 0.00% 0.00% FE55 0.77% 0.00% -1.43% -0.61% -1.94% 0.67% FE59 -1.51% 0.69% 1.14% 0.03% 1.76% 0.03% C058 0.00% -0.73% 0.00% 0.00% 0.00% 0.00% C060 0.00% -0.77% 0.00% 0.00% 0.00% 0.00% SR89 -0.10% 0.61% -1.54% 0.36% -0.61% 0.59% SR90 1.26% 0.00% 0.63% 1.15% -0.36% 0.25% SR9 1 1.13% -0.09% 1.56% -2.51% 3.60% 0.1 9% ZR95 -0.10% 1.08% -0.54% 1.24% -0.39% -0.76% RU103 -0.23% -3.38% 1.00% 1.83% 0.28% 1.46% RU106 -2.74% 0.46% 1.38% -0.49% 0.37% 0.06% AG 11 0m -0.75% -0.1 2% -0.57% -0.4 1 % 0.2 7% 0.5 1% TE 1 25m 0.51% -1.98% -2.09% -0.17% -1.29% -0.34% 1131 0.21% 0.18% 0.10% -0.18% 0.27% -1.75% 1133 -2.49% 1.08% 0.22% 3.42% 1.80% 2.19% 1135 0.43% -3.57% 2.90% 0.33% 5.9 7% -1.22% CS137 -0.38% -0.31% 2.60% -1.14% 0.65% -1.53% NP237 0.64% 0.07% -1.61% 0.06% 1.38% -0.82% PU239 3.23% -0.78% -0.09% -0.15% -0.79% 0.01% PU240 3.23% -0.30% -0.86% 0.09% 0.00% 0.57% PU241 1.30% 1.92% -2.46% -1.44% -0.42% 1.65% AM241 -0.10% 0.60% -2.92% 0.20% -0.41 % 0.07% In order to demonstrate applicability to the VYNPS ODCM , plant-specific parameters are input i nto the RG 1.109 .xlsm calculat i ons. A summary of the parameters used i n the calculat i on is shown in Areva calculation 32-9066572-000 (Reference 4), " VYNPS ODCM -Updated Gaseous Release Dose Factors for 2002-2006 Meteorology and Updated Ma i n Stack Flow Rate" [4], Table 4-2 and Table 4-3. The results i n the VYNPS calculat i on are t h e max i mum dose factor for each Rad i onuclide across a ll age group and organ. P age B-4 of B-8

. ENERCON EJtcellence-Evety Every day. Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 T h erefore, the generic dose factors must be combined to calculate the total dose factor from all pathways to a spec ifi c organ. The inhalation dose factor is multiplied by the VYNPS-specific dispersion x t Q , and the ground and ingestion dose factors are multip li ed by the VYNPS-specific deposition value , D/Q. The dispersion and deposition values are provided in Table 4-4 of the Areva calculation for a ground and stack release. RG1.109.xlsm calculates the maximum dose factor for each age group and organ using the generic dose factors and dispersion/deposition coefficients discussed above. In order to validate the methodology and parameters used , the results of RG1.1 09.xlsm are compared to the results of the VYNPS analysis. Both the ground and stack release dose factors are compared. The VYNPS dose factors are shown in Table 5-2 and 5-3 of Reference 4 for ground and stack releases , respectively.

A compar i son between the VYNPS dose factors and RG1.1 09.xlsm calculated dose and dose rate factors for a ground release is shown in Table B-4. The majority of the calculated radionuclide dose factors are very close to the values provided in the Areva calculation (Reference 4). There are six nuclides that have sign i ficant differences and these are highl i ghted in Table B-4. The differences are likely due to differences in dose conversion factors used for a particular radionuclide. It is important to note that both H-3 and C-14 are in agreement with GASPAR II. In addition , for other nuclides within an elemental group (see other nuclides in Co , Ni , Sr , Te , and La groups) agreement is very good. Thus, the general agreement between RG1.109.xlsm calculations and the Areva calculations indicates that the RG 1.109 methodology coded into RG1.109.xlsm is acceptable for adding add i tional nuclides related to activated in-core steel and bio-sh i eld concrete which maybe encountered in decommissioning. In the cases where the radionuclide results differed , a conservative approach is taken and the maximum of the tw o computed values is used in the ca l cu l ation. Page B-5 of B-8 ENERCON E.xcellence

-Every pr o}<<I. Eve ry day. Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 Table 8-4 Comparison of RG1.109.xlsm and Reference 4 for a Ground Release RG1.109.xlsm Areva Cale 32-9066572-000 Dose Rate Dose Rate Dose Factor , Factor, DFG' Dose Factor, Factor, DFG' Radio-Age DFG (mrem/y) per DFG (mrem/y) per nuclide Group Orcian (mrem/Ci)

(µCi/s) (mrem/Ci)

(µCi/s) % Diff H3 Child L i ver S.87E-03 1.8SE-01 1.1 0E-02 3.47E-01 46.63% C14 Child Bone 6.23E+OO 1.97E+02 6.68E+OO 2.11E+02 6.71% NA24 Child Bone 6.21E-02 1.96E+OO 6.21 E-02 1.96E+OO 0.00% P32 Infant Bone 1.61E+02 S.08E+03 1.61E+02 S.08E+03 -0.09% CRS1 Adult Gl-LLI 4.86E-02 1.S3E+OO 4.86E-02 1.S3E+OO 0.06% MNS4 Teen Lunq 6.17E+OO 1.9SE+02 6.17E+OO 1.9SE+02 -0.06% MNS6 Child Gl-LLI 1.37E-01 4.32E+OO 1.37E-01 4.32E+OO 0.03% FESS Child Bone 2.20E+OO 6.94E+01 2.20E+OO 6.94E+01 0.00% FES9 Adult Gl-LLI S.12E+OO 1.62E+02 S.16E+OO 1.63E+02 0.76% COS7 Teen Gl-LLI 1.36E+OO 4.28E+01 1.68E+OO S.30E+01 19.18% COS8 Adult Gl-LLI 2.89E+OO 9.11 E+01 2.89E+OO 9.12E+01 0.08% C060 Teen Lung 7.18E+01 2.26E+03 7.34E+01 2.32E+03 2.22% N163 Child Bone 1.33E+02 4.19E+03 1.66E+02 S.24E+03 19.99% Nl6S Child Gl-LLI 9.24E-02 2.92E+OO 9.2SE-02 2.92E+OO 0.06% CU64 Teen Gl-LLI 7.34E-02 2.31 E+OO 7.33E-02 2.31E+OO -0.10% ZN6S Infant Liver 2.60E+01 8.20E+02 2.60E+01 8.20E+02 O.OS% ZN69 Infant Gl-LLI 1.44E-02 4.S4E-01 1.44E-02 4.S4E-01 -0.07% BR83 Child TotalBody S.31 E-04 1.67E-02 S.30E-04 1.67E-02 -0.10% BR84 Child TotalBody 1.18E-03 3.74E-02 1.18E-03 3.72E-02 -0.38% RB86 Infant Liver 2.14E+01 6.74E+02 2.13E+01 6.72E+02 -0.28% RB88 Child Liver 7.09E-04 2.24E-02 7.09E-04 2.24E-02 -O.OS% RB89 Teen Liver 7.36E-04 2.32E-02 7.3SE-04 2.32E-02 -0.1 3% SR89 Child Bone 7.79E+01 2.46E+03 7.79E+01 2.46E+03 -0.01% SR90 Child Bone 4.43E+03 1.40E+OS 3.03E+03 9.S6E+04 -46.1 S% SR91 Teen Gl-LLI 2.92E-01 9.20E+OO 2.91 E-01 9.18E+OO -0.23% SR92 Child Gl-LLI 2.67E-01 8.41 E+OO 2.66E-01 8.39E+OO -0.20% Y90 Adult Gl-LLI 8.38E-01 2.64E+01 8.37E-01 2.64E+01 -0.17% Y9 1 Teen G l-LLI 7.1 1E+OO 2.24E+02 7.10E+OO 2.24E+02 -0.09% Y91 M Teen L un g 3.78E-03 1.1 9E-0 1 3.7 8E-03 1.1 9E-01 0.03% Y92 Ch i ld G l-LLI 2.6 1 E-0 1 8.24E+OO 2.62E-0 1 8.26E+OO 0.2 9% Y93 Teen G l-L LI 6.42E-0 1 2.02E+0 1 6.42E-0 1 2.02E+01 0.03% ZR9S Adult G l-L LI S.OSE+OO 1.S9E+02 S.OSE+OO 1.S9E+02 -0.03% ZR97 Teen G l-LLI 7.30E-0 1 2.30E+0 1 7.30E-0 1 2.30E+01 0.0 4% NB9S Ad ul t G l-LLI 9.02E+O O 2.8SE+0 2 9.0 3 E+OO 2.8SE+02 0.0 6% P age B-6 o f B-8 ENERCON &ceJ/ence-Every project. Every day. Radio-Age nuclide Group Organ M099 Teen Gl-LLI TC99M Teen Gl-LLI TC101 Infant Gl-LLI RU103 Adult Gl-LLI RU105 Child Gl-LLI RU106 Adult Gl-LLI AG110M Teen Gl-LLI TE125M Adult Gl-LLI TE127 Teen Gl-LLI TE127M Child Kidney TE129 Infant Gl-LLI TE129M Child Kidney TE131 Inf a nt Gl-LLI TE131M Teen Gl-LLI TE 132 Adult Gl-LLI 1 129 Adult Thyroid 1130 Child Thyroid 1 131 Infant Thyroid 1132 Chi l d Thyro i d 1133 Infant Thyroid 1 134 Chi l d Thyroid 1135 Ch il d Thyroid CS134 Child Liver CS136 Infant L i ver CS137 Child Bone CS138 Infant Gl-LLI BA139 Child Gl-LLI BA 1 40 Teen Lung BA141 Infant Gl-LLI BA142 Teen Lung LA140 Adu lt Gl-LLI LA141 Child G l-LLI LA 1 42 Child Gl-LLI CE141 Teen Gl-LLI CE143 Teen GI-LU Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS RG1.109.xlsm Dose Rate Dose Factor , Factor, DFG' DFG (mrem/y) per (mrem/Ci) (uCi/s) 4.06E-01 1.28E+01 7.24E-03 2.28E-01 9.79E-04 3.09E-02 1.31 E+01 4.15E+02 1.10E-01 3.48E+OO 2.28E+02 7.20E+03 4.94E+01 1.56E+03 2.70E+OO 8.50E+01 8.91E-02 2.81 E+OO 1.82E+01 5.73E+02 2.88E-02 9.08E-01 1.20E+01 3.79E+02 9.05E-03 2.85E-01 7.96E-01 2.51 E+0 1 9.73E-01 3.07E+01 4.05E+03 1.28E+05 2.35E+OO 7.42E+01 5.38E+02 1.70E+04 2.13E-01 6.71 E+OO 8.76E+OO 2.76E+02 5.59E-02 1.76E+OO 8.81 E-01 2.78E+01 1.15E+02 3.62E+03 6.17E+OO 1.95E+02 1.20E+02 3.79E+03 2.00E-03 6.30E-02 6.32E-02 1.99E+OO 2.28E+OO 7.18E+01 5.30E-03 1.67E-01 2.21E-03 6.99E-02 7.04E-0 1 2.22E+0 1 1.77E-01 5.57E+OO 8.48E-02 2.68E+OO 1.28E+OO 4.04E+01 3.28E-01 1.04E+01 Page B-7 of B-8 CALC NO. ENTGVY036-CALC-001 REVISION 1 Areva Cale 32-9066572-000 Dose Rate Dose Factor, Factor, DFG' DFG (mrem/y) per (mrem/Ci)

(µCi/s) % Diff 4.0?E-01 1.28E+01 0.15% 7.23E-03 2.2 8E-01 -0.08% 9.79E-04 3.09E-02 -0.04% 1.31 E+01 4.1 3E+02 -0.33% 1.11 E-01 3.50E+OO 0.46% 2.28E+02 7.19E+03 -0.09% 4.94E+01 1.56E+03 -0.05% 2.69E+OO 8.48E+01 -0.23% 8.91E-02 2.81E+OO 0.02% 1.82E+01 5.74E+02 0.17% 2.88E-02 9.08E-01 0.09% 1.21 E+01 3.82E+02 0.62% 1.00E-01 3.1 5E+OO 90.95% 7.95E-01 2.51 E+01 -0.10% 9.73E-01 3.07E+01 -0.01% 4.05E+03 1.28E+05 0.03% 2.36E+OO 7.44E+01 0.29% 5.38E+02 1.70E+04 -0.02% 2.15E-01 6.78E+OO 1.02% 8.76E+OO 2.76E+02 -0.04% 5.66E-02 1.79E+OO 1.21% 8.85E-01 2.79E+01 0.43% 1.1 5E+02 3.63E+03 0.1 4% 6.17E+OO 1.95E+02 0.03% 1.20E+02 3.78E+03 -0.24% 2.00E-03 6.31 E-02 0.10% 6.32E-02 1.99E+OO -0.06% 2.28E+OO 7.19E+01 0.20% 5.29E-03 1.67E-01 -0.11% 2.2 1E-03 6.97E-02 -0.22% 7.04E-01 2.22E+01 0.01% 7.16E-01 2.26E+01 75.35% 8.48E-02 2.67E+OO -0.04% 1.28E+OO 4.04E+01 -0.07% 3.28E-01 1.03E+01 -0.05%

ENERCON Ex c ellence-Every pr oject. Every day. Radio-Age nuclide Group Organ CE144 Teen GI-LU PR143 Adult GI-LU PR144 Infant GI-LU ND147 Adult GI-LU W187 Teen GI-LU NP239 Adult GI-LU Curie Limits in Support of an ISFSl-On l y EAL Scheme at VYNPS RG1.109.xlsm Dose Rate Dose Factor , Factor, DFG' DFG (mrem/y) per {mrem/Ci)

(µCi/s) 2.70E+01 8.53E+02 8.59E-01 2.71E+01 4.68E-03 1.47E-01 6.28E-01 1.98E+01 2.18E-01 6.88E+OO 1.93E-01 6.10E+OO P age B-8 of B-8 CALC NO. ENTGVY036-CALC-001 REVISION 1 Areva Cale 32-9066572-000 Dose Rate Dose Factor, Factor, DFG' DFG (mrem/y) per {mrem/Ci)

(µCi/s) % Diff 2.70E+01 8.52E+02 -0.16% 8.58E-01 2.71 E+01 -0.16% 4.68E-03 1.48E-01 0.08% 6.27E-01 1.98E+01 -0.23% 2.18E-01 6.88E+OO -0.08% 1.93E-01 6.09E+OO -0.17%

ENERCON Excellence-Every pr oject Every day. Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 Appendix C Verification of ENTGVY036-CALC-001.xlsm The macro enabled Excel workbook ENTGVY036-CALC-001

.xlsm contains three worksheets

Design Inputs , VY ODCM Data, and Computations. The Design Input worksheet contains the basic design inputs and associated references for the data used in this calculation. The VY ODCM Data worksheet contains VYNPS critical organ dose rate factors for a ground level release from the VYNPS ODCM as well as those generated by RG1.109.xlsm. The Computations worksheet contains the output from the VB procedures as well as manual verification. Two VBA procedures are contained in Module 1 of the workbook: Function decay and Sub dose. VBA procedure Function decay computes the decayed activity of a particular radio-nuclide given the Radionuclide ID , time (yr) and the materia l of interest.

It performs a vlookup of the half-life given the Radionuclide ID and a vlookup of activity at 0 time. Then computes the decay constant lambda and the decayed activity using Eqn. 6-1. This procedure is called repeatedly by procedure dose for the various materials and decay times evaluated from the Design Input worksheet.

The activities shown in Table 7-1 of this calculation are reproduced using standard Excel lookup , In and exp functions in worksheet Computations columns AQ through AV rows 7 through 49 and are shown in Table C-1 , below. This is identical to Table 7-1 and verifies Function decay. Table C-1 Core Shroud Activity Decay Verification Time (yr) Radionu-elide 1.75 25.00 50.00 60.00 H-3 1.178E-05 3.196E-06 7.856E-07 4.482E-07 C-14 7.298E-06 7.278E-06 7.256E-06 7.247E-06 C l-36 1.600E-07 1.600E-07 1.600E-07 1.600E-07 Ar-39 1.891 E-08 1.781E-08 1.670E-08 1.628E-08 Ca-41 1.400E-09 1.400E-09 1.400E-09 1.400E-09 Mn-53 4.600E-10 4.600E-10 4.600E-10 4.600E-10 Mn-54 2.003E-04 1.327E-12 2.1 23E-21 6.434E-25 Fe-55 3.760E-02 9.628E-05 1.57 1 E-07 1.206E-08 Page C-1 of C-4 ENERCON Excellenc e-Every pr oject. Eve ry day. Radionu-elide Ni-59 Co-60 Ni-63 Zn-65 Se-79 Kr-81 Kr-85 Sr-90 Nb-92m Zr-93 Mo-93 Nb-94 Tc-99 Ag-108m Sn-121m 1-129 Ba-133 Cs-134 Cs-135 Cs-137 Pm-145 Sm-146 Sm-151 Eu-152 Eu-154 Eu-155 Tb-158 Ho-166m Hf-178m Pb-205 U-233 Pu-239 Total Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 Time (yr) 1.75 25.00 50.00 60.00 4.300E-05 4.299E-05 4.298E-05 4.298E-05 2.541E-02 1.195E-03 4.463E-05 1.1 98E-05 5.628E-03 4.759E-03 3.973E-03 3.696E-03 1.779E-05 5.905E-16 3.170E-27 9.841E-32 1.000E-10 9.997E-11 9.995E-11 9.994E-11 1.600E-11 1.600E-11 1.600E-11 1.600E-11 5.178E-08 1.152E-08 2.288E-09 1.198E-09 1.439E-07 8.273E-08 4.563E-08 3.596E-08 4.500E-14 4.500E-14 4.500E-14 4.500E-14 1.000E-11 1.000E-11 1.000E-11 1.000E-11 7.697E-08 7.662E-08 7.624E-08 7.609E-08 6.310E-08 6.305E-08 6.299E-08 6.297E-08 1.500E-08 1.500E-08 1.500E-08 1.500E-08 1.981 E-08 1.745E-08 1.522E-08 1.441E-08 7.434E-10 5.546E-10 4.047E-10 3.568E-10 4.200E-14 4.200E-14 4.200E-14 4.200E-14 6.608E-07 1.474E-07 2.936E-08 1.540E-08 1.330E-06 5.376E-10 1.204E-13 4.1 77E-15 2.700E-12 2.700E-12 2.700E-12 2.700E-12 1.441 E-07 8.446E-08 4.756E-08 3.779E-08 2.894E-10 1.165E-10 4.375E-11 2.957E-11 2.900E-17 2.900E-17 2.900E-17 2.900E-17 3.749E-09 3.134E-09 2.586E-09 2.394E-09 2.008E-14 5.996E-15 1.634E-15 9.715E-16 7.925E-07 1.270E-07 1.773E-08 8.064E-09 2.817E-07 1.094E-08 3.324E-10 8.219E-11 3.769E-10 3.385E-10 3.016E-10 2.880E-10 2.797E-08 2.760E-08 2.720E-08 2.705E-08 3.558E-08 2.116E-08 1.210E-08 9.673E-09 2.900E-13 2.900E-13 2.900E-13 2.900E-13 1.600E-1 0 1.600E-10 1.600E-10 1.600E-10 2.700E-09 2.698E-09 2.696E-09 2.695E-09 6.892E-02 6.104E-03 4.069E-03 3.759E-03 Page C-2 of C-4 ENERCON Excellence-Every PT<>fr'Ct.

Every day. Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS CALC NO. ENTGVY036-CALC-001 REVISION 1 VB procedure dose computes the dose and activity limits for each material and each decay time. When invoked by Viewing Macros i n the developer menu , Dose loops over all materials (shroud , vessel cladding , b i o-shield at edge , 10, 20 , 30, and 60 cm), loops over all decay periods (1.75 and increments of 5 years to 60 years) and loops over all Radionuclides. It first computes the Radionuclide decay activity using Function decay. Then computes the dose from each radionuclide based on Eqn. 6-2 with a vlookup on the DCF and FRF for the particular radionuclide.

The individual doses are summed and the fractions are computed. The activities are scaled to 3000 mrem/yr based on Eqn. 6-3 , are summed based on Eqn. 6-4, and the fractions are computed.

Summary tables of decayed activities and activity limits are created as well. All computation results are recorded in spreadsheet Computations relative to the active cell selected at the time the procedure is invoked. The activity limit calculations shown in Table 7-3 of this calculation are reproduced using standard Excel lookup , multiplication and division functions in worksheet Computations co l umns AX through BC rows 7 through 49 and are shown in Table C-2 , be l ow. This is identical to Table 7-3 and verifies procedure dose. Table C-2 Core Shroud Activity Limit Verification at 1.75 Years Post Shutdown Radio-% of % of nuclide Activity Dose i Dose Act. Limit Limit H-3 1.178E-05 5.68E-04 0.001 3.34E-04 0.017 C-14 7.298E-06 4.27E-03 0.004 2.07E-04 0.011 Cl-36 1.600E-07 O.OOE+OO 0.000 4.54E-06 0.000 Ar-39 1.891 E-08 O.OOE+OO 0.000 5.37E-07 0.000 Ca-41 1.400E-09 1.12E-04 0.000 3.97E-08 0.000 Mn-53 4.600E-10 O.OOE+OO 0.000 1.31 E-08 0.000 Mn-54 2.003E-04 1.08E-01 0.102 5.68E-03 0.291 Fe-55 3.760E-02 7.25E+OO 6.856 1.07E+OO 54.558 N i-59 4.300E-05 3.78E-02 0.036 1.22E-03 0.062 Co-60 2.54 1 E-02 1.63E+0 1 15.455 7.21 E-01 36.863 Ni-63 5.628E-03 8.19E+0 1 77.436 1.60E-0 1 8.167 Zn-65 1.779E-05 4.05E-02 0.038 5.05E-04 0.026 Se-79 1.000E-1 0 9.09E-0 7 0.000 2.84E-09 0.000 Kr-8 1 1.600E-11 O.OOE+OO 0.000 4.54E-10 0.000 Page C-3 of C-4

, ENERCON E.>tcellence-Enry Every day. Radio-nuclide Kr-85 S r-90 Nb-92m Zr-93 Mo-93 Nb-94 Tc-99 Aq-108m Sn-121m 1-129 Ba-133 Cs-134 Cs-135 Cs-137 Pm-145 Sm-146 Sm-151 Eu-152 Eu-154 Eu-155 Tb-158 Ho-166m Hf-178m Pb-205 U-233 Pu-239 Total Curie Limits in Support of an ISFSl-Only EAL Scheme at VYNPS % of Activity Dose i Dose 5.178E-08 O.OOE+OO 0.000 1.439E-07 5.58E-02 0.053 4.500E-14 O.OOE+OO 0.000 1.000E-11 7.58E-10 0.000 7.697E-08 8.03E-05 0.000 6.310E-08 O.OOE+OO 0.000 1.500E-08 3.71 E-05 0.000 1.981 E-08 O.OOE+OO 0.000 7.434E-10 O.OOE+OO 0.000 4.200E-14 7.45E-07 0.000 6.608E-07 O.OOE+OO 0.000 1.330E-06 1.34E-02 0.013 2.700E-12 5.53E-09 0.000 1.441 E-07 1.52E-03 0.001 2.894E-10 O.OOE+OO 0.000 2.900E-17 O.OOE+OO 0.000 3.749E-09 5.54E-07 0.000 2.008E-14 8.40E-11 0.000 7.925E-07 3.44E-03 0.003 2.817E-07 4.70E-04 0.000 3.769E-10 O.OOE+OO 0.000 2.797E-08 1.96E-04 0.000 3.558E-08 O.OOE+OO 0.000 2.900E-13 O.OOE+OO 0.000 1.600E-10 1.15E-06 0.000 2.700E-09 3.60E-04 0.000 6.892E-02 105.71 100.00 Page C-4 of C-4 CALC NO. ENTGVY036-CALC-001 REVISION 1 % of Act. Limit Limit 1.47E-06 0.000 4.08E-06 0.000 1.28E-12 0.000 2.84E-10 0.000 2.18E-06 0.000 1.79E-06 0.000 4.26E-07 0.000 5.62E-07 0.000 2.11E-08 0.000 1.19E-12 0.000 1.88E-05 0.001 3.78E-05 0.002 7.66E-11 0.000 4.09E-06 0.000 8.21E-09 0.000 8.23E-16 0.000 1.06E-07 0.000 5.70E-13 0.000 2.25E-05 0.001 7.99E-06 0.000 1.07E-08 0.000 7.94E-07 0.000 1.01 E-06 0.000 8.23E-12 0.000 4.54E-09 0.000 7.66E-08 0.000 1.96 100.00

BVY 17-009, Vermont Yankee - Calculation ENTGVY036-CALC-001, Revision 1, Curie Limits in Support of an ISFSI-Only EAL Scheme at Plant

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