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Calculation No. NEE-323-CALC-005, Revised Gaseous Radiological EALs Per NEI 99-01 Rev. 06
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Site:	Duane Arnold
Issue date:	12/14/2017
From:	; NextEra Energy Duane Arnold
To:	; Office of New Reactors
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CALC NO. NEE-323-CALC-005 CALCULATION COVER JI ENERCON SHEET REV. 00 E..xcellence- Eve,y project. Every doy.

PAGE NO. 1 of 34 Client: Duane Arnold Energy Center Revised Gaseous Radiological EALs per NEI

Title:

99-01 Rev. 06 Project Identifier: NEE-323 Item Cover Sheet Items Yes No 1 Does this calculation contain any open assumptions, including preliminary D ~

information, that require confirmation? (If YES, identify the assumptions.)

2 Does this calculation serve as an "Alternate Calculation"? (If YES , identify the design D ~

verified calculation .)

Design Verified Calculation No. - -

3 Does this calculation supersede an existing Calculation? (If YES , identify the design D ~

verified calculation.)

Superseded Calculation No. - -

Scope of Revision:

Initial Issue Revision Impact on Results:

Initial Issue Study Calcu lation D Final Calculation t8J Safety-Related D Non-Safety-Related t8J (Print Name and Sign)

Originator: Ryan Skaggs Date: 12/14/17 Design Verifier1 (Reviewer if NSR): Jay Bhatt Date: 12/14/17 Approver: Zachary Rose Date: 12/14/17 Note 1: For non-safety-related calcu lation, design verification can be substituted by review.

I CALC NO. NEE-323-CALC-005 I ENERCON CALCULATION Excellenc~Every proj<<t Every day. REVISION STATUS SHEET REV. 00 CALCULATION REVISION STATUS REVISION DATE DESCRIPTION 00 12/14/1 7 Initial Issue PAGE REVISION STATUS PAGE NO. REVISION PAGE NO. REVISION All 00 APPENDIX/ATTACHMENT REVISION STATUS APPENDIX NO. NO.OF REVISION ATTACHMENT NO. OF REVISION PAGES NO. NO. PAGES NO.

A 8 00 1 4 00 Page 2 of 34

CALC NO. NEE-323-CALC-005 ENERCON TABLE OF CONTENTS Excellence-Every project. Every day.

REV. 00 Section Page No.

1.0 Purpose and Scope

4 2.0 Summary of Results and Conclusions 4 3.0 References 6 4.0 Assumptions 7 5.0 Design Inputs 8 6.0 Methodology 13 7.0 Calculation 19 8.0 Computer Software 33 9.0 Impact Assessment 34

of List of Appendices Pages Appendix A - Dose Spreadsheet Output 8

of List of Attachments Pages Attachment 1 - Calculation Preparation Checklist 4 Page 3 of 34

CALC N EE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Excellence-Every project. Every day. EALs per NEI 99-01 Rev . 06 REV. 00

1.0 Purpose and Scope

The DAEC site is implementing new requirements of Revision 6 to the Document NEI 99-01 , "Development of Emergency Action Levels for Non-Passive Reactors ." One of the changes included in Revision 6 to NEI 99-01 is a new basis for the Emergency Action Level (EAL) RA 1. The requirements for RS1 and RG1 did not change from NEI 99-01 Rev. 05 with the implementation of NEI 99-0 1, Rev. 06 .

The following table is extracted from Section 6 of Revision 6 to NEI 99-01:

ALERT SITE AREA EMER- GENERAL EMER-GENCY GENCY AA 1 Release of gaseous AS1 Release of gaseous AG1 Release of gase-or liquid radi oactivity re- radi oactivity resulting in ous rad ioactivity result-suiting in offsite dose offs ite dose gre ater than ing in offsite dose greater than 10 mrem 100 mrem TEDE or 500 greater than 1,000 mrem TEDE or 50 mrem thy- mrem thyroid CDE. TEDE or 5,000 mrem roid CDE . Op. Modes: All thyroid CDE.

Op. Modes: All Op. Modes: All AA1 , AS1 , AG1 compares to DAEC terminology RA1 , RS1, RG1 , respectively . This calculation determines the effluent radiation monitor readings that correspond to the RA 1, RS1 , and RG1 thresholds .

2.0 Summary of Results and Conclusions The results below show the RA 1 EAL release concentration thresholds and associated dose rates for each release point for a decay time of five hours and 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The highlighted dose indicates which threshold was met at the release concentration .

Table 1 - RA 1 EAL Release Concentration Thresholds (Decay = 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months (Mode 1, 2, 3))

Release Point Release Concentration CEDE EDE TEDE CDE Thyroid

µCi/cc mrem mrem mrem mrem Turbi ne Buildi ng l .58E-02 2.38 0.39 2.77 50.0 Rea cto r Building l .22 E-02 2.37** 0.39 2.76 49.8**

Offgas Stack 4.39 E+Ol 1.96 8.05* 10.00 41.1 Low-Level Radwaste Processing an d 1.SlE-02 2.37 0.39 2.76 49.7 Storage Facil ity (LLRPSF)

Calculation of this value was demonstrated in Section 7.3

- Calculation of this value was demonstrated in Section 7.4 Table 2 - RA 1 EAL Release Concentration Thresholds (Decay= 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (Mode 4, 5))

Release Point Release Concentration CEDE EDE TEDE COE Thyroid

µCi/cc mrem mrem mrem mrem Turbin e Bu ilding l .30E-02 2.59 0.07 2.67 49 .7 Reactor Bu ilding 1.0lE-02 2.60 0.07 2.68 49 .9 Offgas St ack 4.52E+Ol 2.61 1.41 4.02 50.0 LLRPSF l.25 E-02 2.60 0.07 2.67 49.8 Page 4 of 34

CALC N EE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Exc~flence-Every project Every doy. EALs per NEI 99-01 Rev. 06 REV. 00 Resultant EAL thresholds:

The tables below show the release concentration threshold for RA 1, RS1, and RG1 based on the results above for both a decay time of five hours and a decay time of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

From Section 1.0:

RS 1 thresholds are 10 times larger than those for RA 1 RG1 thresholds are 100 times larger than those for RA 1 Table 3- Recommended RA 1, RS1, and RG1 EAL Thresholds (Modes 1, 2, 3)

Release Point RAl RS1 RGl

µCi/cc µCi/cc µCi/cc Turbine Building 1.58E-02 1.58E-01 l.58E+OO Rea ctor Building l. 22E-02 l .22E-01 1.22E+OO Offgas Stac k 4.39E+Ol 4. 39E+02 4 .39E+03 LLRPSF l .SlE-02 l.SlE-01 1.SlE+OO*

RAl Table 4 - Recommended-RA 1, RS1, and RG 1 EAL Thresholds (Modes 4, 5)

Release Point RS1 RGl

µCi/cc µCi/cc µCi/cc Turbine Building l.30E-02 l .30E-01 l.30E+OO Reactor Building l. OlE-02 l .OlE-01 l.OlE+OO Offgas Stack 4.52E+Ol 4.52E+02 4 .52E+03 LLRPSF l.2 5E-02 l .25E-01 l.25E+OO*

Per Design Input 5.8 the results in EAL threshold values exceed the range of the monitor.

Page 5 of 34

CALC N EE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Excellenc~Every project £very doy. EALs per NEI 99-01 Rev. 06 REV. 00 3.0 References 3.1 NEI 99-01 , Revision 6, "Development of Emergency Action Levels for Non-Passive Reactors", Nuclear Energy Institute, November 2012.

3.2 NUREG-1940, RASCAL 4: Description of Models and Methods, United States Nuclear Regulatory Commission, Office of Nuclear Security and Incident Response, 2012 .

3.3 NUREG-1940 Supplement 1, RASCAL 4.3: Description of Models and Methods, United States Nuclear Regulatory Commission , Office of Nuclear Security and Incident Response , 2015.

3.4 NUREG-1228, Source Term Estimation During Incident Response to Severe Nuclear Power Plant Accidents , United States Nuclear Regulatory Commission ,

Division of Operational Assessment , 1988.

3.5 NUREG-1465, Accident Source Terms for Light-Water Nuclear Power Plants, United States Nuclear Regulatory Commission , Office of Nuclear Regulatory Research, 1995.

3.6 DAEC UFSAR, Chapter 15-0.

3.7 DAEC UFSAR, Chapter 15-2.

3.8 DAEC Offsite Dose Assessment Manual (ODAM) .

3.9 Plant Chemistry Procedure PCP 8.3, Alarm Setpoints and Background Determination for KAMAN Normal Range Monitors.

3.11 DAEC Emergency Plan , Section 'I', Rev . 27.

3.12 Federal Guidance Report No. 11 , Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation , Submersion and Ingestion Office of Radiation and Indoor Air, 1999.

3.13 Federal Guidance Report No. 12, External Exposure to Radionuclides in Air, Water, and Soil , 1993.

3.14 Table of Nuclides, http:llatom.kaeri.re.kr:8080/ton!index.html. retrieved 10/10117.

Page 6 of 34

CALC N EE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

ExceTlence-Every pro}ecr. Every day. EALs per NEI 99-01 Rev. 06 REV. 00 4.0 Assumptions The following are assumptions about the receptor:

No credit is taken for radiation shielding provided by structures .

No decay in-transit is assumed during the time elapsed between the release point and the receptor.

Both of the above assumptions are acceptable because they will result in a higher dose to the receptor and conservatively lower thresholds.

Page 7 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Exct flence-Evtry project Every day. EALs per NEI 99-01 Rev. 06 REV. 00 5.0 Design Inputs 5.1 Core Inventory The assumed isotopic mixture in Table 5 is taken from Table 1-1 of NUREG-1940.

The core inventory (curies per megawatts thermal) in the table is based on calculations made by the NRC staff in December 2003 using the SAS2H control module of SCALE (Standardized Computer Analyses for Licensing Evaluation) ,

Version 4.4a.

Table 5 - Isotopic Mixture NUCLIDE CORE INVENTORY NUC LIDE CORE INVENTORY NUCLIDE CORE INVENTORY (Ci/MWt) (Ci/MWt) (CUMWt)

Ba-139 4.74E+04 La-141 4.33E+04 Te-127 2.36E+03 Ba-140 4.76E+04 La-142 4.21E+04 Te-1 27m 3.97E+02 Ce-141 4.39E+04 Mo-99 5.30E+04 Te-1 29 8.26E+03 Ce-143 4.00E+04 Nb-95 4.50E+04 Te-129m 1.68E+03 ee-144* 3.54E+04 Nd-147 1.75E+04 Te-131m 5.41E+03 Cm-242 1.12E+03 Np-239 5.69E+05 Te-132 3.81E+04 Cs-134 4.70E+03 Pr-143 3.96E+04 Xe-131m 3.65E+02 Cs-136 1.49E+03 Pu-241 4.26E+03 Xe-133 5.43E+04 Cs-137* 3.25E+03 Rb-86 5.29E+01 Xe-133m 1.72E+03 1-131 2.67E+04 Rh-105 2.81E+04 Xe-135 1.42E+04 1-132 3.88E+04 Ru-1 03 4.34E+04 X.e-135m 1.15E+04 1-133 5.42E+04 Ru-1 05 3.06E+04 Xe-138 4.56E+04 1-134 5.98E+04 Ru-106' 1.55E+04 Y-90 2.45E+03 1-135 5.18E+04 Sb-127 2.39E+03 Y-91 3.17E+04 Kr-83m 3.05E+03 Sb-129 8.68E+03 Y-92 3.26E+04 Kr-85 2.78E+02 Sr-89 2.41E+04 Y-93 2.52E+04 Kr-85m 6.17E+03 Sr,90 2.39E+03 Zr-95 4.44E+04 Kr-87 1.23E+04 Sr-91 3.01 E+04 Zr-97~ 4.23E+04 Kr-88 1.70E+04 Sr-92 3.24E+04 La-140 4.91E+04 T c-99m 4.37E+04 Page 8 of 34

CALC N EE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Excelknce-Every project Every day. EALs per NEI 99-01 Rev . 06 REV. 00 5.2 Release Fraction Table 6 displays release fractions as a function of time taken from Table 1-4 which references Table 3-12 of NUREG-1465.

Table 6 - Release Fraction N UCLIDE GROUP BWR CORE INVENTORY RELEASE FRACTION Cladding Failure Core Melt Phase Postvessel (Gap Release (In-Vessel Phase) Melt-Through Phase Phase) (Ex-Vessel Phase )

(1.5-hour duration)

(0.5-hour duration) (3.0-hour duration)

Noble gases (Kr, Xe) 0.05 0.95 0 Halogens (I, Br) 0.05 0.25 0.30 Alkali metals (Cs, Rb) 0.05 0.20 0 .35 Tellurium group (Te, Sb. Se) 0 0.05 0.25 Barium . strontium (Ba. Sr) 0 0.02 0.1 Noble metals (Ru, Rh , Pd, Mo. 0 0.0025 0.0025 Tc, Co)

Cerium group (Ce, Pu, Np) 0 0.0005 0.0 05 lanthanides (La, Zr, Nd. Eu, Nb, 0 0.0002 0.005 Pm, Pr, Sm, Y, Cm. Am)

"Retercnce: Table 3-11 li omNUREG-1 465.

5.3 Gaseous Dispersion Factors The dispersion factors are taken from the ODAM Section 3.

Table 7 - Dispersion Factors Dose due to Organ Dose Due to Plume/Submersion Particulates and Iodine ODAM Sections 3.5 .2.1 and ODAM Section 3.8 3.9 Offgas Stack 2.8E-7 sec/m 3 3.1E-7 sec/m 3 Building Vents 4.3E-6 sec/m 3 3.9E-6 sec/m 3 5.4 Isotopic half-lives Isotopic half-lives are taken from NUREG-1940, Supplement 1. For those isotopes missing from that list, denoted by*, half-lives were obtained from the following website which is maintained by the Korea Atomic Energy Research Institute:

http://atom.kaeri.re. kr: BOBO/ton/index. html Page 9 of 34

CALC N EE-323-CALC-005 ENERCON Revised Gaseous Radiolog ical NO.

I Exceflenc~Every project. Evr:ry day. EALs per NEI 99-01 Rev. 06 REV. 00 Table 8 contains the half-lives and calculated A (lambda) values .

Table B - Half-lives and Decay Constants Decay T 1/2 T 1/2 Isotope T 1/2 Lambda units Hours hrs*1 Ba -139 0.0574 days l .38E+OO 5.03E-01 Ba -140

-- 12.7 days 3.05E+02 2.27E-03 i

I I Ce-141 32.5 days 7.80E+02 8.89E-04 Ce-143 1.38 days 3.31E+Ol 2.09E-02 Ce-144 284 I days 6.82E+03 l.02E-04 Cm-242 163 days 3.91E+03 l.77E-04 Cs-134 753 days 1.81E+04 3.84E-05 Cs-136 3.14E+02 2.2 0E-03 Cs-137

-13.1 11000 days days 2.64E+05 2.63E-06 1-131 8.04 days I l .93E+02 3.59E-03 1-132 0.0958 days t 2.30E+OO 3.0lE-01 1- --

1-133 0.867 days I 2.08E+Ol 3.33E-02 1-134 I 0.0365

- - days 8. 76E-01

- 7.91E-01 1-135 0.275 days 6.60E+OO 1.05E-01 Kr-83m*

-1.83 hou rs l.83E+OO 3.79E-01 Kr-85 3910 days 9.38E+04 7.39E-06 Kr-85m 0.187 days 4.49E+OO 1.54E-01 Kr-87 0.053 days 1.27E+OO 5.45E-01 Kr-88 0.118 days 2.83E+OO 2.45E-01 La-140 1.68 days 4.03E+Ol l .72E-02 La-141 0.164 days 3.94E+OO l .76E-01 La -142 0.0642 days l .54E+OO 4.50E-01 Mo-99 2.75 days 6.60E+Ol l.05E-02 Nb-95 35.2 days 8.45E+02 8.20E-04 Nd-147 11 days 2.64E+02 2.63E-03 Np-239 2.36 days 5.66E+Ol l.22E-02 Pr-143 13.6 days 3.26E+02 2.12E-03 Pu-241 5260 days 1.26E+05 5.49E-06 Rb-86 18.7 days 4.49E+02 l.54E-03 Rh-105 1.47 days 3.53E+Ol l.96E-0 2 Ru -103 39.3 days 9.43E+02 7.35E-04 Ru-105 0.185 days 4.44E+OO 1.56E-0 1 Ru-106 368 days 8.83E+03 7.85E-05 Sb-127 3.85 days 9.24E+Ol 7.50E-03 Sb-129* 4.4 hours 4.40E+OO l.58E-01 Sr-89 50.5 days 1.21E+03 5.72E-04 Sr-90 10600 days 2.54E+05 2.72E-06 Sr-91 0.396 days 9.SOE+OO 7.29E-02 Sr-92 0.113 days 2.71E+OO 2.56E-01 Tc-99m 0.251 days 6.02E+OO l .15E-01 Te-127 0.39 days 9.36E+OO 7.41E-02 Te-127m 109 days 2.62E+03 2.65E-04 Te-129 0.0483 days 1.16E+OO 5.98E-01 Te-129m 33.6 days 8.06E+02 8.60E-04 Page 10 of 34

CALC N EE-323-CALC-005

'l ENERCON Revised Gaseous Radiological NO.

E.xcellenc~Every project. Every doy. EALs per NEI 99-01 Rev. 06 REV. 00 Decay T 1/2 T 1/2 Isotope T 1/2 Lambda units Hours hrs*1 Te-131m 1. 25 days 3.00E+Ol 2.31E-02 Te-132 3.26 days 7.82E+Ol 8.86E-03 Xe-131m* 11.934 days 2.86 E+02 2.42E-03 Xe-133 5.25 days l .26E+02 S.SOE-03 Xe-133 m* 2.19 days S.26E+Ol l .32E-02 Xe-135 0.379 days 9.lOE+OO 7.62E-02 Xe-13Sm* 15.29 minutes 2.SSE-01 2.72E+OO Xe-138* 14.08 minutes 2.3SE-01 2.9SE +OO Y-90 2.67 days 6.41E+Ol l.08E-02 Y-91 58.S days 1.40E+03 4.94E-04 Y-92 0.148 days 3.SSE+OO l.9SE-01 Y-93 0.4 21 days l. OlE+Ol 6.86E-02 Zr-95 64 days 1.54E+03 4.S lE-04 Zr-97 0.704 days l.69E+Ol 4.lOE-02 5.5 Reduction Factor for Sprays NUREG-1940 Table 1-11 states that when sprays are used for longer than 1.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months (but less than 2.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months ), the following factor is applied to reduce all of the particu late and iodine species.

RFs =Exp(-D.64t)

Where t = the amount of times sprays are in service.

Note : This reducti on factor does not apply to the noble gases.

For this ca lculation , sprays are used for a total of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months as described in Section 6.1.

The reduction factor is:

RFs = e(-o.54*2> = 0.278 5.6 Standby Gas Treatment Filters NUREG-1940 allows a reduction factor of 0.01 for filters like the standby gas treatment (SBGT) system. This factor is only applied to releases from the Offgas Stack.

RFF= 0.01

5. 7 Secondary Contain ment NUREG-1228 provides a reduction factor for natural removal through settling and plate-out in the secondary conta inment. For a 0.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months holdup period, that reduction factor is 0.4. This factor is applied to the bui lding vent releases but not the re lease from the Offgas Stack.

RFsc = 0.4 Page 11 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Exctllence-Evtry project Every day. EALs per NEI 99-01 Rev. 06 REV. 00 5.8 Monitor Range and Exhaust Flow Rates Table 9 is developed from the DAEC Emergency Plan Section "I ",

ODAM Figure 3-1 , and Procedure PCP 8.3.

Table 9 - Monitor Range and Exhaust Flow Rates Monitor Monitor Release Release Point Common Equipment ID Range Flow Name µCi/cc CFM KA MAN RE-5945 / RE- lE-7 to Turbine Buildi ng 72,000 1/ 2 5946 1E+5 KA MAN RE-7645, RE-3/ 4 7644 KA MAN RE-7647, RE- lE-7 to Reactor Buildin g 93,000 5/ 6 7646 1E+5 KAMAN RE-7649, RE-7/ 8 7648 KAMAN RE-4176, RE- lE-7 to Offgas St ack 10,000 9/10 4175 1E+5 lE-7 to LLRPS F KAMAN 12 RE-8801 75,000 3E-1 5.9 Breathing Rate From NUREG-1940 and FGR11 , the breathing rate is 3.33E-4 m 3/second .

5.10 Exposure-to-Dose Conversion Factors for Inhalation The "Exposure-to-Dose Conversion Factors for Inhalation" by radionuclide provided in FGR11 Table 2.1 allow the determination of the committed dose equivalent to the thyroid and the effective dose equivalent per unit per unit intake ,

and are shown in Table 11 .

5.11 Dose Coefficients for Air Submersion The dose coefficients in Sv/Bq*s*m-3 from being submersed in air for each radionuclide to an effective dose are taken from Table 111.1 of FGR12 , and are shown in Table 11.

Page 12 of 34

CALC N EE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Exceflence---Every project Every day; EALs per NEI 99-01 Rev . 06 REV. 00 6.0 Methodology This calculation will equate a radioactive material release rate as measured at the gaseous effluent radiation monitors with the dose received to a member of the public at an offsite location . The relationship is highly influenced by the mixture of radioisotopes in the effluent and the dispersion of gases after they have left the facility. Primary guidance is provided by NUREG-1940 and NUREG-1228.

6.1 Scenario The following generalized timeline is used to determine the phenomenon that can affect the mixture of radioisotopes in effluent. This scenario is realistic, but bounds an event that could occur in a shorter total time frame:

T= 0 hr. Major recirculating system line break occurs. Reactor is shut down .

T= 1 hr. Core is uncovered.

T= 1 hr. Sprays are initiated.

T = 2 hrs . Core is covered.

T= 4.5 hrs. A catastrophic event causes damage to the drywell and the sec-ondary containment.

o The gaseous mixture from the Drywell spreads into the Reactor Build-ing , Turbine Building, and LLRPSF.

o Mean average holdup time of the gas in these buildings is 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

Scenario timing will affect the mixture of radioisotopes and is summarized here:

The core is uncovered for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Core/Drywell Sprays are running for a total of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Primary Containment integrity is maintained for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Source holdup time in secondary containment is 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

Source decay time from shutdown to the release point is 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

When the reactor is in mode 4 or 5, the total decay time is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Other Factors :

The flow rates from the effluent exhaust points are listed in Design Input 5.8.

The gaseous effluent radiation monitors are equally efficient for the monitor-ing of noble gases, particulates, and iodines .

All releases from the Offgas Stack are filtered by the Standby Gas Treatment system .

Removal of particulates and iodines by natural process during holdup in sec-ondary containment are credited for releases from the building vents only.

6.2 Receptor The receptor is an adult located at the ODAM-described location of minimal dispersion who is exposed to the radioactive release for one hour. Due to this relatively short duration, the only exposure pathways are inhalation and submersion.

Assumptions related to the receptor are found in Section 4.0.

Page 13 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Exceflence-Every project. Every day. EALs per NEI 99-01 Rev. 06 REV. 00 6.3 General Approach With a given mixture of radionuclides , the dose received by an individual offsite is a function of the gross activity present in the gaseous mixture .

The resultant dose received by an offsite receptor is dependent not only on the gross radioactivity levels of the effluent but also upon the isotopic mixture present in the gas . This calculation predicts the relative contribution of each radionuclide to the gross radiation monitored by the effluent monitor.

With the fractionation of the mixture of radionuclides understood , a given gross output reading (µCi/cm 3) from an effluent radiation monitor can be scaled to determine the concentration of each isotope present in the effluent.

The calculation then uses default dispersion factors described in the Offsite Dose Assessment Manual to determine the resultant concentration of radionuclides to which an individual offsite would be exposed .

Dose conversion factors provided in Federal Guidance Report 11 (FGR11) and 12 (FGR12) are used to determine the dose (mrem) to an individual offsite due to their exposure to the gaseous mixture of radionuclides .

With the given radionuclide mixture and dispersion factors understood , an iterative process can be used to relate the effluent monitor reading to a target offsite dose.

Two types of radiation dose are calculated: 1) TEDE and 2) COE Thyroid.

COE or Committed Dose Equivalent is the radiation dose to a specific organ due to an uptake of radioactive material. In this case , the uptake is limited to inhalation of radioactive material in the plume.

TEDE or Total Effective Dose Equivalent is the summation of the Effective Dose Equivalent (EDE) and the Committed Dose Equivalent (CEDE) .

TEDE = EDE + CEDE.

EDE is the dose due to an individual being directly exposed (by submersion) to the radiation present in the gaseous release (shine) .

CEDE is the sum of the COE for each organ of the body with weighting factors applied for each organ. In this calculation, only contributions from the inhalation pathway are considered .

An iterative process is used to determine the gross radiation monitored by the effluent monitors that correspond to the threshold doses.

6.4 Source Term This calculation will not analyze for the total activity released from the core. It will only analyze for the ratios of the isotopic species that are released from the core .

Various phenomena will act to change the composition of the isotopic mixture in the time between reactor shutdown and release from the facility. In summary the removal phenomena addressed here include:

Page 14 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiolog ical NO.

Excellence-Every project. Every day. EALs per NEI 99-01 Rev. 06 REV. 00 RF, = Fraction of the activity released from the inventory of damaged fuel described in Section 6.5.

RFs = Fraction of the activity remaining after reduction by containment spray from Section 5.5.

RFR = Fraction of activity remaining after 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months or 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months of radioactive decay described in Section 6.6.

RFF = Fraction of the activity remaining after filter by SBGT filters from Section 5.6.

RFsc = Fraction of activity remaining after natural removal processes in secondary containment from Section 5.7.

Combining these factors provides a single fraction to derive a depleted source:

RFTotal = RF,

RFs *RFR

RFF

RFsc 6.5 Fuel Damage Release Fractions Table 6 contains release fractions for three time periods representing the total amount of time the core has been assumed to be uncovered . They are: 0 to 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , 0.5 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and 2 to 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . For this calculation , the core is assumed to be uncovered for one hour. A spreadsheet is used to scale the release fraction between the 0.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months point and the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months point.

The Reduction Factor, RF,. due to the release fraction is 100% of the release expected in the first 0.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months PLUS 1/3 of the amount released as expected in the period between 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

05 05 Example for Alkali Metals: 0.05 * (

hr)+

0.5 hr 0.2 * (

hr = 0.1167

hr) 1.5 Table 10- Release Fractions by Time Step (Hours)

Group Time (h) by step 0.5 1.5 Cumulative Alkali Metals 0.050 0.2000 0.1167 Barium Group 0.000 0.0200 0.0067 Cerium Group 0.000 0.0005 0.0002 Halogen 0.050 0.2500 0.1333 Lanthanides 0.000 0.0002 0.0001 Noble Gas 0.050 0.9500 0.3667 Noble Metals 0.000 0.0025 0.0008 Tellurium group 0.000 0.0500 0.0167 Page 15 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

E.tcellence-Evtry project Every doy. EALs per NEI 99-01 Rev. 06 REV. 00 6.6 Radioactive Decay The total amount of time the radioactive source is allowed to decay before being exhausted as an effluent is 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months or 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months depending on the reactor mode per Section 6.1 .

The generalized equation for radioactive decay is:

A= Aoe(-M)

Where:

A = decayed activity Ao = initial activity A = isotopic decay constant t = elapsed time and A= ln2 / t%

With an end goal of a total reduction factor RFTota1, a radiation decay factor RFR is derived from the general equation above:

RFR = e(-M) 6.7 Effective Dose Equivalent - Noble Gas Submersion Submersion dose from noble gases is calculated with guidance provided in FGR12.

The concentration of an isotope i present in the plume at the receptor is calculated :

Xir= Xiv

v * ( ~ )

With the isotopic concentration at the receptor known , the dose (mrem) at the receptor is calculated :

Dose = I /x ir

hEs oi)

Where concentration of radionuclide i present at the receptor (Ci/m 3 )

Note: Ci/m 3 = µCi/cc volume of gas released (m 3) concentration of radionuclide i released from the stack or building vent.

(Ci/m 3) i= each isotope present in the gaseous release

(~) = dispersion factor for that release point (sec/m3) hEs oi= factor converting the gas concentration to effective dose equivalent.

mremcm 3 )

( µCi sec Page 16 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Excellenc~-Every project. Every day. EALs per NEI 99-01 Rev. 06 REV. 00 As described in Section 7.3, a spreadsheet is used to determine the EDE dose contribution for each isotope in the mixture .

6.8 Committed Dose Equivalent: Thyroid Organ dose from airborne particulates and iodines is calculated with guidance provided in FGR11.

The concentration of an isotope i present in the plume at the receptor is calculated:

Xir= Xiv* v * ( ~ )

With the isotopic concentration at the receptor known , the dose (mrem) at the receptor can be calculated:

Dose = L(Xir

B

t

hrs oi)

Where xir = concentration of radionuclide i present at the receptor (Ci/m 3)

Note: Ci/m 3 = µCi/ cm 3 v= volume of gas released (m 3) xiv = concentration of radionuclide i released from the stack or building vent.

(Ci/m 3) i= each isotope present in the gaseous release

(~) = dispersion factor for that release point (sec/m 3)

B= breathing Rate (cm 3/sec) hrs oi= factor converting the gas concentration to effective dose equivalent.

(mrem/µCi) t = time the dose is to be integrated (sec)

As described in Section 7.4 , a spreadsheet is used to determine the thyroid COE dose contribution for each isotope in the mixture .

6.9 Committed Effective Dose Equivalent Committed Effective Dose Equivalent from airborne particulates and iodines is calculated with guidance provided in FGR11 .

The concentration Xir Of an isotope i present in the plume at the receptor is calculated:

Xir = Xiv* v* ( ; )

With the isotopic concentration at the receptor known, the dose (mrem) at the receptor can be calculated:

Dos e = L (Xir

B

t

hEsoa Where Page 17 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

E.xceflence-Every project Every doy. EALs per NEI 99-01 Rev. 06 REV. 00 X ir = concentration of rad ionuclide i present at the receptor (Ci/m 3)

Note: Ci/m 3 = µCi/ cm 3 v= volume of gas released (m 3) xiv = concentration of radionuclide i released from the stack or building vent.

(Ci/m 3) i= each isotope present in the gaseous release (i) = dispersion factor for that release point (sec/m 3)

B= breathing Rate (cm 3/sec) hEs oi= factor converting the gas concentration to effective dose equivalent.

(mrem/µCi) t = time the dose is to be integrated (sec)

As described in Section 7.4, a spreadsheet is used to determine the CEDE dose contribution for each isotope in the mixture .

Page 18 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiolog ical NO.

E.xcellence-Evtry project Every doy. EALs per NEI 99-01 Rev . 06 REV. 00 7 .0 Calculation All calculations were completed using Microsoft Excel. Sample ca lculations are shown in the subsections that follow .

7 . 1 Dose Factors FGR11 and FGR 12 dis pl ay dose factors in the SI units of Sv/Bq and Sv m 3/ Bq sec, respectively. Traditional units of mrem/µCi and mrem cm 3/µCi sec are desired .

FGR11:

1 ~ lE+OS mre m 3.70E+09 mrem

= - - - - + -- --

2.7E-11 8 1.00E+6 µCi µCi The conversion factor from Sv/Bq to mrem/µCi is 3.70E+09.

FGR 12:

1 ~ ffi~ lE+OS mrem 1 BEi 1E+06 ml 8 3.70E+l5 mre m cm3 BEi sec ~ 2.7E-11 8 ffi~ 1E+06 µCi µCi sec The convers ion factor from Sv m 3/Bq sec to mrem cm 3/µCi sec is 3.70E+15.

The thyroid, CEDE , and submersion dose factors in the t raditiona l units for each isotope are calculated in the table below . Column C , D , and H are dose fa ctors from Sections 5 . 1 0 and 5.11 and Columns E and I are the conversion fact o rs fro m a b o v e .

Column F , G , and J are the h Tsoi, h Esoi , and h Esoi factors as described in Sections 6 .8 ,

6.9 , and 6 .7 , respective ly. Line 6 of Table 11 illustrates the formulas for Ba-139.

Table 11 - Isotopic Dose Factors FGRll FGRll Units Thyroid CEDE FGR 12 : Units Submersio n Thyroid CEDE Isotope Conversion mrem mrem Sv m3 Conversion mrem cc Sv Sv Factor µC i µCi Bq sec Factor µCi sec Bq Bq

=l6* H6 Ba-139 2.40E-12 4.64E-11 3.70E+09 8.88E-03 1.72E-01 2.17E-15 3.7E+l 5 8.03E+OO Ba-140 2.56E-10 1.0l E-09 3.70E+09 9.47E-01 3.74E+OO 8.58E-15 3.7E+15 3.17E+Ol Ce-141 4.61E-11 2.42 E-09 3.70E+09 1.71E-01 8.95E+OO 3.43E-15 3.7E+15 1.27E+Ol Ce-143 1.21E-11 9.16E-10 3.70E+09 4.48E-02 3.39E+OO 1.29E-14 3.7E+l5 4.77E+Ol Ce-144 1.88E-09 1.0lE-07 3.70E+09 6.96E+OO 3.74E+02 8.53E-16 3.7E+l5 3.16E+OO Cm-242 9.41E-1D 4.67E-06 3.70E+09 3.48E+D0 1.73E+04 5.69E-18 3.7E+15 2.llE-02 Cs-134 1.llE-08 1.25E-08 3.7DE+09 4.llE+Ol 4.63E+Ol 7.57E-14 3.7E+15 2.80E+02 Cs-136 1.73E-09 1.98E-09 3.7DE+09 6.40E+OO 7.33E+OO l .06E-13 3.7E+l5 3.92E+02 Cs-137 7.93E-09 8.63E-09 3.70E+D9 2.93 E+Ol 3.19E+Ol 7.74E-18 3.7E+15 2.86E-02 1-131 2.92E-07 8.89E-09 3.70 E+09 1.08E+03 3.29E+Ol 1.82E-14 3.7E+l5 6.73E+Ol 1-132 1.74E-09 1.03E-10 3.70E+09 6.44E+OO 3.81E-01 1.12E-13 3.7E+l5 4.14E+02 1-133 4.86E-08 1.58E-09 3.70E+09 1.80E+D2 5.85E+OO 2.94E-14 3.7E+15 1.09E+02 Page 19 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radi ological NO.

Excellence--Every project £very doy. EALs per NEI 99-0 1 Rev . 06 REV. 00 FGRll FG Rll Units Thy roid CEDE FGR 12: Un its Submersion Thyroid CEDE Isotope Conversion mrem mrem Sv m 3 Conversion mrem cc Sv Sv Factor µCi µC i Bq sec Factor µCi sec Bq Bq 1-134 2.88 E-10 3.SSE-11 3.70E+09 l.07E+OO l.31E-01 l .3E-13 3.7E+l5 4.81E+02 1-135 8.46E-09 3.32E-10 3.70E+09 3.13E+Ol l. 23E+OO 7.98E-14 3.7E+l5 2.95E+02 Kr-83m 1.SE-18 3.7E+l5 5.SSE-03 Kr-85 1.19E-16 3.7E+15 4.40E-01 Kr-85m 7.48E-15 3.7E+l5 2.77E+Ol Kr-87 4 .12E-14 3.7E+l5 l .52E+02 Kr-88 l.02E-13 3.7E+l5 3.77E+02 La -140 l.22E-10 l.31E-09 3.70E+09 4.SlE-01 4. 85E+OO l.17E-13 3.7E+l5 4.33E+02 La-141 9.40E-12 l .57E-10 3.70E+09 3.48E-02 5.81E-01 2.39E-15 3.7E+l5 8.84E+OO La-142 8.74E-12 6.84E-11 3.70E+09 3.23E-02 2.53E-01 1.44E-13 3.7E+l5 5.33E+02 Mo-99 1.17E-10 l .07E-09 3.70E+09 4.33E-01 3.96E+OO 7.28E-15 3.7E+l5 2.69E+Ol Nb-95 3.58E-10 l .57E-09 3.70E+09 l.32E+OO 5.81E+OO 3.74E-14 3.7E+15 l.38E+02 Nd -147 l.94E-11 l .85E-09 3.70E+09 7.18E-02 6.85E+OO 6.19E-15 3.7E+l5 2.29E+Ol Np-239 7.62E-12 6.78E-10 3.70 E+09 2.82E-02 2.SlE+OO 7.69E-15 3.7E+l5 2.85E+Ol Pr-143 l.68E-18 2.19E-09 3.70E+09 6.22E-09 8.lOE+OO 2.lE-17 3.7E+l5 7.77E-02 Pu-241 l.24E-11 2. 23E-06 3.70E+09 4.59E-02 8.25E+03 7.25E-20 3.7E+l5 2.68E-04 Rb-86 l.33E-09 l .79E-09 3.70E+09 4.92E+OO 6.62E+OO 4.81E-15 3.7E+l5 l.78E+Ol Rh-105 2.57E-11 2.58E-10 3.70E+09 9.SlE-02 9.SSE-01 3.72E-15 3.7E+l5 l.38E+Ol Ru -103 5.97 E-10 2.42 E-09 3.70E+09 2. 21E+OO 8.95E+OO 2.25E-14 3.7E+l5 8.33E+Ol Ru -105 1.SOE-11 l .23 E-10 3.70E+09 5.SSE-02 4.SSE-01 3.81E-14 3.7E+l5 1.41E+02 Ru -106 l .37E-08 l.29E-07 3.70E+09 5.07E+Ol 4.77E+02 0 3.7E+l5 O.OOE+OO Sb-127 l .SOE-10 l.63E-09 3.70E+09 5.SSE-01 6.03E+OO 3.33E-14 3.7E+l5 l .23E+02 Sb-129 2.07E-11 1.74E-10 3.70E+09 7.66E-02 6.44E-01 7.14E-14 3.7E+l5 2.64E+02 Sr-89 4.16E-10 l.12 E-08 3.70 E+09 l.54E+OO 4.14E+Ol 7.73E-17 3.7 E+l5 2.86E-01 Sr-90 2.64E-09 3.SlE-07 3.70E+09 9.77E+OO l .30E+03 7.53E-18 3.7E+l5 2.79E-02 Sr-91 4.08E-11 4.49E-10 3.70E+09 l.SlE-01 l .66E+OO 3.45E-14 3.7E+l5 l.28E+02 Sr-92 2.19E-11 2.18E-10 3.70E+09 8.lOE-02 8.07E-01 6.79E-14 3.7E+l5 2.51E+02 Tc-99m 5.0lE-11 8.80E-12 3.70E+09 l.85E-01 3.26E-0 2 5.89E-15 3.7E+l5 2.18E+Ol Te-127 6.46E-12 8.60E-11 3.70E+09 2.39E-0 2 3.18E-01 2.42E-16 3. 7E+l5 8.95E-01 Te-127m 2.39E-10 5.81E-09 3.70 E+09 8.84E-01 2.lSE+Ol 1.47E-16 3.7E+l 5 5.44E-01 Te-129 l.63E-12 2.42E-11 3.70E+09 6.03E-03 8.95E-02 2.75E-15 3.7E+l5 l .02E+Ol Te-129m 3.95E-10 6.47E-09 3.70E+09 l.46E+OO 2.39 E+Ol 1.SSE-15 3.7E+15 5.74E+OO Te-131m 3.61E-08 l.73 E-09 3.70E+09 l.34E+02 6.40E+OO 7.0lE-14 3.7E+15 2.59E+02 Te-132 6.28E-08 2.SSE-09 3.70E+09 2.32E+0 2 9.44E+OO l.03E-14 3.7E+l5 3.81E+Ol Xe-131m 3.89E-16 3.7E+ l 5 l .44E+OO Xe-133 1.56E-15 3.7 E+l5 5.77E+OO Xe-133m l.37E-15 3.7E+l5 5.07E+OO Xe-135 l.19E-14 3. 7E+l5 4.40E+Ol Xe-135m 2.04E-14 3.7E+l 5 7.SSE+Ol Xe-138 5.77E-14 3.7E+ l 5 2.13E+02 Y-90 9.52E-12 2.28E-09 3.70 E+ 09 3.52E-02 8.44E+OO l.9E-16 3.7E+l 5 7.03E-01 Y-91 l .lOE-10 1.32 E-08 3.70E+09 4.07E-01 4.88E+Ol 2.6E-16 3.7E+l5 9.62E-01 Y-92 3.69E-12 2.ll E-10 3.70E+09 l.37E-02 7.81E-01 l.3E-14 3.7E+l5 4.81E+Ol Y-93 5.06E-12 5.82 E-10 3.70E+09 l .87E-02 2.lSE+OO 4.8E-15 3.7E+l 5 l .78E+Ol Zr-95 1.44E-09 6.39E-09 3.70E+09 5.33E+OO 2.36E+Ol 3.6E-14 3.7E+l 5 l .33E+02 Zr-97 9.56E-11 l. 17 E-09 3.70E+09 3.54E-01 4.33E+OO 9.02E-15 3.7E+l5 3.34E+Ol Page 20 of 34

CALC N EE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

bcellence-Every project. £very day. EALs per NEI 99-01 Rev. 06 REV. 00 7.2 Source Term A spreadsheet is used to determine the total reduction factor RFTota1 for each isotope present in the source term as described in Section 6.4 . The activity per megawatt thermal from Section 5.1 is multiplied by RFTota1 to find the source term for each isotope . The spreadsheet for the Offgas Stack release is presented in Table 13.

The relative activity released from damaged fuel (RF,) was determined in Section 6.5.

Table 12 - 2 Hours Reduction Fa ctor (RF,)

Cumulative 2 Hour Al kal i M eta ls 0.1167 Barium Group 0.0067 Ceriu m Group 0.0002 Halogen 0.1333 Lanthanides 0.000 1 Noble Gas 0.3667 Noble Metals 0.0008 Tellurium group 0.01 67 A Spray Reduction factor of 0.278 for primary containment sprays (RFs) was derived in Section 5.5.

Determination of the Radiation Decay fractions (RFR) was demonstrated in Section 6.6. In the spreadsheets below, the source decay time is 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

Page 21 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Excellence-Ev~ry projut Evtry day. EALs per NEI 99-01 Rev. 06 REV. 00 7.2.1 Offgas Stack For the Offgas Stack release, credit is taken for filtering (RFF) by the Standby Gas Treatment system but not for the natural removal processes that occur in secondary containment (RFsc).

Table 13- Isotopic Depletion and Release for Offgas Stack RF1 RFs RFsc RFF RFR RFrotal

+ 0.25 hr Q Re lease Secondary SBGT Decay Total Release Form Isotope Sprays MWTh Fraction Con- Filter Fraction Depletion Ci/MWTh Reduction tainment Barium Group Ba-139 4.74E+04 0.0067 0.2780 1.0000 0.01 0.0808 l.50E-06 7.lOE-02 Barium Group Ba-140 4.76E+04 0.0067 0.2780 1.0000 0.01 0.9887 l.83E-05 8.72E-01 Cerium Group Ce-141 4.39E+04 0.0002 0. 2780 1.0000 0.01 0.9956 4.61E-07 2.03E-02 Cerium Group Ce-143 4.00E+04 0.0002 0.2780 1.0000 0.01 0.9006 4.17E-07 1.67E-02 Cerium Group Ce-144 3.54E+04 0.0002 0.2780 1.0000 0.01 0.9995 4.63E-07 l .64E-02 Lanthanides Cm-242 1.12E+03 0.0001 0.2780 1.0000 0.01 0.9991 l .85E-07 2.07E-04 Alkali Metals Cs-134 4.70E+03 0.1167 0.2780 1.0000 0.01 0.9998 3.24E-04 1.52E+OO Alkali Metals Cs-136 1.49E+03 0.1167 0.2780 1.0000 0.01 0.9890 3.21E-04 4.78E-01 Alkali Metals Cs-137 3.25E+03 0.1167 0.2780 1.0000 0 .01 1.0000 3.24E-04 1.05E+OO Ha logen 1-131 2.67E+04 0.1333 0.2780 1.0000 0.01 0.9822 3.64E-04 9.72E+OO Halogen 1-132 3.88E+04 0.1333 0.2780 1.0000 0.01 0.2215 8.21E-05 3.19E+OO Halogen 1-133 5.42E+04 0.1333 0.2780 1.0000 0.01 0.8466 3.14E-04 1.70E+Ol Halogen 1-134 5.98E+04 0.1333 0.2780 1.0000 0.01 0.0191 7.09E-06 4.24E-01 Halogen 1-135 5.18 E+04 0.1333 0.2780 1.0000 0.01 0.5915 2. 19E-04 l .14E+Ol Noble Gas Kr-83m 3.05E+03 0.367 1.0 1.0 1.0 0.1505 5.52E-02 1.68E+02 Noble Gas Kr-85 2.78E+02 0.367 1.0 1.0 1.0 1.0000 3.67E-01 l .02E+02 Noble Gas Kr-85m 6.17E+03 0.367 1.0 1.0 1.0 0.4620 l .69E-01 l .05E+03 Noble Gas Kr-87 l .2 3E+04 0.367 1.0 1.0 1.0 0.0656 2.40E-02 2.96E+02 Noble Gas Kr-88 1.70E+04 0.367 1.0 1.0 1.0 0.2941 1.08E-01 1.83E+03 Lanthanides La -140 4.91E+04 0.0001 0.2780 1.0000 0.01 0.9176 1.70E-07 8.35E-03 Lanthanides La-141 4.33E+04 0.0001 0.2780 1.0000 0.01 0.4146 7.68E-08 3.33E-03 Lanthanides La-142 4.21E+04 0.0001 0.2780 1.0000 0.01 0.1055 l .96E-08 8.23E-04 Noble Metals Mo-99 5.30E+04 0.0008 0.2780 1.0000 0.01 0.9488 2.20E-06 l .17E-01 Lanthanides Nb-95 4.50E+04 0.0001 0.2780 1.0000 0.01 0.9959 1.85E-07 8.31E-03 Lanthanides Nd-147 l .75E+04 0.0001 0.2780 1.0000 0.01 0.9870 1.83E-07 3.20E-03 Cerium Group Np-239 5.69E+05 0.0002 0.2780 1.0000 0.01 0.9406 4.36E-07 2.48E-01 Lanthanides Pr-143 3.96E+04 0.0001 0.2780 1.0000 0.01 0.9894 1.83E-07 7.26E-03 Cerium Group Pu-241 4. 26E+03 0.0002 0.2780 1.0000 0.01 1.0000 4.63E-07 l .97E-03 Alkali Metals Rb-86 5.29E+Ol 0.1167 0.2780 1.0000 0.01 0.9923 3.22E-04 1.70E-02 Nob le Metals Rh-105 2.81E+04 0.0008 0.2780 1.0000 0.01 0.9064 2.lOE-06 5.90E-02 Noble Metals Ru -103 4.34E+04 0.0008 0.2780 1.0000 0.01 0.9963 2.31E-06 1.00E-01 Noble Metal s Ru -105 3.06E+04 0.0008 0.2780 1.0000 0.01 0.4581 1.06E-06 3.25E-02 Noble Metals Ru -106 1.55E+04 0.0008 0.2780 1.0000 0.01 0.9996 2.32E-06 3.59E-02 Tellurium group Sb-127 2.39E+03 0.0167 0.2780 1.0000 0.01 0.9632 4.46E-05 l .07E-01 Te llurium group Sb-129 8.68E+03 0.0167 0.2780 1.0000 0.01 0.4549 2.llE-05 l .83 E-01 Barium Group Sr-89 2.41E+04 0.0067 0. 2780 1.0000 0.01 0.9971 1.85E-05 4.45E-01 Barium Group Sr-90 2.39E+03 0.0067 0.2780 1.0000 0.01 1.0000 1.85E-05 4.43E-02 Page 22 of 34

CALC N EE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Excellence- Every project Every doy. EALs per NEI 99-01 Rev. 06 REV. 00 RF1 RFs RFsc RFF RFR RFrotal

+ 0.25 hr Q Release Secondary SBGT Decay Total Release Form Isotope Sprays MWTh Fraction Con- Filter Fraction Depletion Ci/MWTh Reduction tainment Barium Group Sr-91 3.01E+04 0.0067 0.2780 1.0000 0.01 0.6944 l .29E-05 3.87E-01 Barium Group Sr-92 3.24E+04 0.0067 0.2780 1.0000 0.01 0.2786 5.16E-06 l.67E-01 Noble Metals Tc-99m 4.37E+04 0.0008 0.2780 1.0000 0.01 0.5625 l.30E-06 5.70E-02 Tellurium group Te-127 2.36E+03 0.0167 0.2780 1.0000 0.01 0.6905 3.20E-05 7.55E-02 Tellurium group Te-127m 3.97E+02 0.0167 0.2780 1.0000 0.01 0.9987 4.63E-05 l.84E-02 Tellurium group Te-129 8.26E+03 0.0167 0.2780 1.0000 0.01 0.0503 2.33E-06 l .93E-02 Tellurium group Te-1 29m l.68E+03 0.0167 0.2780 1.0000 0.01 0.9957 4.61E-05 7.75E-02 Tellurium group Te-131m 5.41E+03 0.0167 0.2780 1.0000 0.01 0.8909 4.13E-05 2.23E-01 Tellurium group Te-132 3.81E+04 0.0167 0.2780 1.0000 0.01 0.9567 4.43E-05 l.69E+OO Noble Gas Xe-131m 3.65E+02 0.367 1.0 1.0 1.0 0.9880 3.62E-01 l.32E+02 Noble Gas Xe-133 5.43E+04 0.367 1.0 1.0 1.0 0.9729 3.57E-01 l .94E+04 Noble Gas Xe-13 3m l .72E+03 0.367 1.0 1.0 1.0 0.9362 3.43E-01 5.90E+02 Noble Gas Xe-135 1.42E+04 0.367 1.0 1.0 1.0 0.6832 2.SOE-01 3.56E+03 Noble Gas Xe-135m l.15E+04 0.367 1.0 1.0 1.0 0.0000 *4.55E-07 5.23E-03 Noble Gas Xe-138 4.56E+04 0.367 1.0 1.0 1.0 0.0000 l.41E-07 6.45E-03 Lanthanides Y-90 2.45E+03 0.0001 0.2780 1.0000 0.01 0.9474 1.76E-07 4.30E-04 Lanthanides Y-91 3.17E+04 0.0001 0.2780 1.0000 0.01 0.9975 l.85E-07 5.86E-03 Lanthanides Y-92 3.26E+04 0.0001 0.2780 1.0000 0.01 0.3769 6.99E-08 2.28E-03 Lanthanides Y-93 2.5 2E+04 0.0001 0.2780 1.0000 0.01 0.7096 1.32E-07 3.31E-03 Lanthanides Zr-95 4.44E+04 0.0001 0.2780 1.0000 0.01 0.9977 l.85E-07 8.21E-03 Lanthanides Zr-97 4. 23E+04 0.0001 0.2780 1.0000 0.01 0.8145 1.SlE-07 6.39E-03 Page 23 of 34

CALC NEE-323-CALC-005 ENERCON Revi sed Gaseou s Radiolog ical NO.

ExcefJence- Every project. Every day. EALs per NEI 99-01 Rev. 06 REV . 00 7.2 .2 Bu ilding Vents For releases from Building Ven ts, no credit is taken for filtering (RFF) by th e Standby Gas Treatment system. Credit is taken for the natural removal processes that occurs in secondary conta in ment (RFsc). T his source term also has radioactive decay occu rring for 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

Table 14 - Isotopic Depletion and Release for Building Vents RF1 RFs RFsc RFF RFR RFTotal

+ 0.25 hr Q Re lease Secondary SBGT Decay Total Release Form Isotope Sprays MWTh Fraction Con- Filter Fraction Depletion Ci/MWTh Reduction tainment Barium Group Ba -139 4.74E+04 0.0067 0.2780 0.4000 1.00 0.0808 5.99E-05 2.84E+OO Barium Group Ba-140 4.76E+04 0.0067 0.2780 0.4000 1.00 0.9887 7.33E-04 3.49E+Ol Cerium Group Ce-141 4.39E+04 0.0002 0.2780 0.4000 1.00 0.9956 l .85E-05 8.lOE-01 Cerium Group Ce-143 4.00E+04 0.0002 0.2780 0.4000 1.00 0.9006 l .67E-05 6.68E-01 Cerium Group Ce-144 3.54E+04 0.0002 0.2780 0.4000 1.00 0.9995 l .85E-05 6.56E-01 Lanthanides Cm -242 l.12E+03 0.0001 0.2780 0.4000 1.00 0.9991 7.41E-06 8.30E-03 Alkali Metals Cs-134 4.70E+03 0.1167 0.2780 0.4000 1.00 0.9998 l.30E-02 6.lOE+Ol Alkali Metals Cs-136 1.49E+03 0.1167 0.2780 0.4000 1.00 0.9890 1.28E-02 l.91E+Ol Alka li Metals Cs-137 3.25E+03 0.1167 0.2780 0.4000 1.00 1.0000 l .30E-02 4.22E+Ol Halogen 1-131 2.67E+04 0.1333 0.2780 0.4000 1.00 0.9822 1.46E-02 3.89E+02 Halogen 1-132 3.88E+04 0.1333 0.2780 0.4000 1.00 0.2215 3.28E-03 l.27E+02 Halogen 1-133 5.42E+04 0.1333 0.2780 0.4000 1.00 0.8466 1.26E-02 6.80E+02 Halogen 1-134 5.98E+04 0.1333 0.2780 0.4000 1.00 0.0191 2.84E-04 l .70E+Ol Halogen 1-135 5.18E+04 0.1333 0.2780 0.4000 1.00 0.5915 8.77E-03 4.54E+02 Noble Gas Kr-83m 3.05E+03 0.367 1.0 1.0 1.0 0.1505 5.52E-02 l.68E+02 Noble Gas Kr-85 2.78E+02 0.367 1.0 1.0 1.0 1.0000 3.67E-01 1.02E+02 Noble Gas Kr-85m 6.17E+03 0.367 1.0 1.0 1.0 0.4620 l.69E-01 l .05E+03 Noble Gas Kr-87 l.23E+04 0.367 1.0 1.0 1.0 0.0656 2.40E-02 2.96E+02 Noble Gas Kr-88 l.70E+04 0.367 1.0 1.0 1.0 0.2941 l .08E-01 l .83E+03 Lanthanid es La-140 4.91E+04 0.0001 0.2780 0.4000 1.00 0.9176 6.80E-06 3.34E-01 Lanthanides La-141 4.33E+04 0.0001 0.2780 0.4000 1.00 0.4146 3.07E-06 l.33E-01 Lanthanides La -142 4.21E+04 0.0001 0.2780 0.4000 1.00 0.1055 7.82E-07 3.29E-02 Noble Metals Mo-99 5.30E+04 0.0008 0.2780 0.4000 1.00 0.9488 8.79E-05 4.66E+OO Lanthanides Nb-95 4.50E+04 0.0001 0.2780 0.4000 1.00 0.9959 7.38E-06 3.32E-01 Lanthanides Nd-147 l .75E+04 0.0001 0.2780 0.4000 1.00 0.9870 7.32E-06 l.28E-01 Cerium Group Np-239 5.69E+05 0.0002 0.2780 0.4000 1.00 0.9406 1.74E-05 9.92E+OO Lanth anides Pr-143 3.96E+04 0.0001 0.2780 0.4000 1.00 0.9894 7.34E-06 2.91E-01 Cerium Group Pu -241 4.26E+03 0.0002 0.2780 0.4000 1.00 1.0000 l.85E-05 7.90E-02 Alkali Metals Rb-86 5.29E+Ol 0.1167 0.2780 0.4000 1.00 0.9923 l .29E-02 6.81E-01 Noble Metals Rh -105 2.81E+04 0.0008 0.2780 0.4000 1.00 0.9064 8.40E-05 2.36E+OO Noble Metals Ru-103 4.34E+04 0.0008 0.2780 0.4000 1.00 0.9963 9.23E-05 4.0lE+OO Noble Metals Ru -105 3.06E+04 0.0008 0.2780 0.4000 1.00 0.4581 4.25E-05 l.30E+OO Noble Metals Ru -106 l.SSE+04 0.0008 0.2780 0.4000 1.00 0.9996 9.26E-05 1.44E+OO Te ll urium group Sb-127 2.39E+03 0.0167 0.2780 0.4000 1.00 0.9632 l .79E-03 4.27E+OO Tellurium group Sb-129 8.68E+03 0.0167 0.2780 0.4000 1.00 0.4549 8.43E-04 7.32E+OO Barium Group Sr-89 2.41E+04 0.0067 0.2780 0.4000 1.00 0.9971 7.39E-04 l.78E+Ol Page 24 of 34

CALC N EE-323-CALC-005

[ ENERCON Revised Gaseous Radiological NO.

E.xcellenct-Every project Every day. EALs per NEI 99-01 Rev. 06 REV. 00 RF1 RFs RFsc RFF RFR RFrotal

+ 0.25 hr Q Re lease Secondary SBGT Decay Total Release Form Isotope Sprays MWTh Fraction Con- Filter Fraction Depletion Ci/MWTh Reduction ta in ment Barium Group Sr-90 2.39E+03 0.0067 0.2780 0.4000 1.00 1.0000 7.41E-04 l.77E+OO Barium Group Sr-91 3.01E+04 0.0067 0.2780 0.4000 1.00 0.6944 5.15E-04 l.55E+Ol Barium Group Sr-92 3.24E+04 0.0067 0.2780 0.4000 1.00 0.2786 2.07E-04 6.69E+OO Nob le Meta ls Tc-99m 4.37E+04 0.0008 0.2780 0.4000 1.00 0.5625 5.21E-05 2.28E+OO Te ll urium group Te-127 2.36E+03 0.0167 0.2780 0.4000 1.00 0.6905 l.28E-03 3.02E+OO Te ll urium group Te-127m 3.97E+02 0.0167 0.2780 0.4000 1.00 0.9987 l.85E-03 7.35E-01 Te llu rium group Te-129 8.26E+03 0.0167 0.2780 0.4000 1.00 0.0503 9.32E-05 7.70E-01 Tel lurium group Te-129m l.68E+03 0.0167 0.2780 0.4000 1.00 0.9957 l.85E-03 3.lOE+OO Te ll urium group Te-131m 5.41E+03 0. 0167 0.2780 0.4000 1.00 0.8909 l.65E-03 8.93E+OO Te llurium group Te-13 2 3.81E+04 0.0167 0.2780 0.4000 1.00 0.9567 l .77E-03 6.76E+Ol Noble Gas Xe-131m 3.65E+02 0.367 1.0 1.0 1.0 0.9880 3.62E-01 l .32E+02 Noble Gas Xe-13 3 5.43E+04 0.367 1.0 1.0 1.0 0.9729 3.57E-01 l.94E+04 Noble Gas Xe-133 m l.72E+03 0.367 1.0 1.0 1.0 0.9362 3.43E-01 5.90E+02 Noble Gas Xe -135 l.42E+04 0.367 1.0 1.0 1.0 0.6832 2.SOE-01 3.56E+03 Nob le Gas Xe-135m l.15E+04 0.367 1.0 1.0 1.0 0. 0000 4.55E-07 5.23E-03 Noble Gas Xe-138 4.56E+04 0.367 1.0 1.0 1.0 0.0000 1.41E-07 6.45E-03 Lanthanides Y-90 2.45E+03 0.0001 0.2780 0.4000 1.00 0.9474 7.02E-06 l.72E-02 Lanthanides Y-91 3.17E+04 0.0001 0.2780 0.4000 1.00 0.9975 7.40E-06 2.34E-01 Lanthanides Y-92 3.26E+04 0.0001 0.2780 0.4000 1.00 0.3769 2.79E-06 9.llE-02 Lanthanides Y-93 2.52E+04 0.0001 0.2780 0.4000 1.00 0.7096 5.26E-06 l .33E-Ol Lanthanides Zr-95 4.44E+04 0.0001 0.2780 0.4000 1.00 0.9977 7.40E-06 3.28E-Ol Lanthanides Zr-97 4.23E+04 0.0001 0.2780 0.4000 1.00 0.8145 6.04E-06 2.55E-01 7.3 Effective Dose Equivalent - Noble Gas Submersion Spreadsheets are used to calculate isotopic concentration at the receptor and the resultant radiation dose to the receptor for each of the isotopes in the mixture .

For the example Effective Dose Equivalent calculation , the release point is the Offgas Stack at five hours since shutdown , and a gross concentration of 43.9 µCi/cm 3 (this concentration was determined iteratively to produce 10 mrem TEDE) . The secondary containment holdup hours is set at <0.5 because the natural removal process in the Secondary Containment does not occu r with the Offgas Stack.

In Table 15, the column labeled "hE5 oi Submersion mrem cm 3/µCi sec," is the dose factor for air submersion dose and is calculated in Section 7.1 .

The column labeled "Depleted Mix Ci/MWTh" is the "Release Ci/MWTh" calculated in Section 7.2 for each isotope .

The "Fraction" column determines the fraction each isotope contributes to the gross activity and is used to scale the activity for each isotope .

Page 25 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Excellence-Every project Every day. EALs per NEI 99-01 Rev . 06 REV. 00 The column "x ;v Release Cone. µCi/cm 3" contains a calculation that scales the "Depleted Mix Ci/MWTh" column to a user entered gross concentration based on the "Fraction". In this case, the gross concentration entered was 43.9 µCi/cm 3 (4.39E+1 ).

Values in the "x;, Receptor Cone. µCi/cm 3" column are calculated by multiplying the release concentration by the applicable dispersion factor, the volume of the release ,

and requisite conversion factors . The basic equation is from Section 6.7:

Xir = Xiv* v* ( ~ )

For isotope 1-131 , an example is presented:

Xiv Release Recept or Cone. Flow (X/Q) Cone.

l.57E-02 µCi 10,000 4* 2.83E-02 m* 1 mifl 2.80E-07 see 2.08E-08 µCi cm 3 mifl 1 4* 60 see m* cm' Where:

v = 10,000 ft 3/min is the rated flow from the Offgas Stack from Design Input 5.8 .

(XIQ) = 2.80E-07 is the Noble Gas Dispersion coefficient (XIQ) for the Offgas Stack from Design Input 5.3 .

2.83E-2 converts ft 3 to m 3 Values in the "Submersion Dose mrem" (hEso;) column are calculated by multiplying the factors "x;, Receptor Cone. µCi/cm 3 ", a time-units conversion factor, and the dose conversion factor calculated in Section 7.1. The basic equation for a one hour time period is shown in Section 6.7.

Dose= L/Xir

hEsoa For isotope 1-131 , an example is presented :

Subm ers ion Xir Receptor h esoi Dose Cone. Su bmers ion m re m 2.0SE-08 ttG 6.73E+Ol m rem ffi6 3600 SE! 5.04E-03 mre m ffi6 ttG SE!

Page 26 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Exce fle~-Evtry project Every day. EALs per NEI 99-01 Rev. 06 REV. 00 For ease of comparison , the spreadsheet row for 1-131 is shown here :

X;v X;r hESOi De pl eted Re lease Recepto r Subm e r sion Submersio n Mix N ucl ide Fract ion Cone. Co n e. Dose mrem cc Q gQ gQ m rem

µCi sec MWTh cm 3 cm 3 1-131 6. 73E+l 9.72E+O 3.582E-4 l.57E-2 2. 08E-8 S.04E-3 Table 15 - Submersion Dose for Offgas Stack X;v X;r hESOi D e plete d R e le ase Receptor Subm e rs ion S ubme rsion Mix Nuclide Fra ction Cone. Cone. Dose m re m cm 3 Ci MWTh gg gg mre m

µ C i sec cm 3 cm 3 Ba-139 8.03E+O 7.lOE-2 2.62E-6 1.lSE-4 1.52E-10 4.39E-6 Ba-140 3.17E+l 8.72E-1 3.21E-5 1.41E-3 1.86E-9 2.13E-4 Ce-141 1.27E+l 2.03E- 2 7.46E-7 3.28E-5 4.33E-11 1.98E-6 Ce-143 4.77E+l 1.67E-2 6.lSE-7 2.70E-5 3.57E-11 6.13E-6 Ce-144 3.16E+O 1.64E-2 6.04E-7 2.65E-5 3.SOE-11 3.98E-7 Cm-242 2.llE-2 2.07E-4 7.64E-9 3.35E-7 4.43E-13 3.36E-11 Cs-134 2.80E+2 1.52E+O 5.62E-5 2.47E-3 3. 26E-9 3.28E-3 Cs-136 3.92E+2 4.78E-1 1.76E-5 7. 73E-4 1.02E-9 1.44E-3 Cs-137 2.86E-2 1.0SE+O 3.BBE-5 l. 70E-3 2.25E-9 2.32E-7 1-131 6.73E+l 9.72E+O 3.582E-4 1.57E-2 2.0BE-8 S.04E-3 1-132 4.14E+2 3.19E+O 1.17E-4 5.lSE-3 6.BlE-9 1.02E-2 1-133 1.09E+2 1.70E+l 6.27E-4 2.75E-2 3.64E-8 1.42E-2 1-134 4.81E+2 4.24E-1 1.56E-5 6.86E-4 9.07E-10 1.57E-3 1-135 2.95E+2 1.14E+l 4.lBE-4 1.84E-2 2.43E-8 2.SBE- 2 Kr-83m S.SSE-3 1.68E+2 6.20E-3 2.72E-1 3.60E-7 7.19E-6 Kr-85 4.40E-1 1.02E+2 3.76E-3 1.65E-1 2.lBE-7 3.45E-4 Kr-BSm 2.77E+l 1.0SE+3 3.BSE-2 1.69E+O 2.23E-6 2.23E-1 Kr-87 1.52E+2 2.96E+2 1.09E-2 4.78E-1 6.32E-7 3.47E-1 Kr-88 3.77E+2 1.83E+3 6.75E-2 2.97E+O 3.92E-6 S.3 2E+O La-140 4.33E+2 8.35E-3 3.0BE-7 1.35E-5 1.78E-11 2.78E-5 La-141 8.84E+O 3.33E-3 1.23E-7 S.38E-6 7.llE-12 2.26E-7 La-142 S.33E+2 8.23E-4 3.03E-8 1.33E-6 1.76E-12 3.37E-6 Mo-99 2.69E+l 1.17E-1 4.29E-6 1.BBE-4 2.49E-10 2.41E-5 Nb-95 1.38E+2 8.31E-3 3.06E-7 1.34E-5 1.78E-11 8.84E-6 Nd-147 2.29E+l 3.20E-3 1.lBE-7 5.lBE-6 6.84E-12 S.64E-7 Np-239 2.BSE+l 2.48E-1 9.14E-6 4.0lE-4 S.30E-10 S.43E-5 Pr-143 7.77E- 2 7.26E-3 2.68E-7 1.17E-5 1.SSE-11 4.34E-9 Pu-241 2.68E-4 1.97E-3 7.27E-8 3.1 9E-6 4.22E-12 4.07E-12 Rb-86 1.78E+l l.70E- 2 6.27E-7 2. 75E-5 3.64E-11 2.33E-6 Rh-105 1.38E+l S.90E-2 2.17E-6 9.54E-5 1.26E-10 6.25E-6 Ru-103 8.33E+l 1.00E-1 3.69E-6 1.62E-4 2.14E-10 6.42E-5 Ru-105 1.41E+2 3.25E-2 1.20E-6 S.25 E-5 6.94E-11 3.52E-5 Ru-106 0.00E+O 3.59E-2 1.32E-6 S.Bl E-5 7.67E-11 O.OOE+O Sb-127 1.23E+2 1.07E-1 3.93E-6 1.73E-4 2.28E-10 1.0lE-4 Sb-129 2.64E+2 1.83E-1 6.74E-6 2.96E-4 3.91E-10 3.72E-4 Sr-89 2.86E-1 4.45E-1 1.64E-5 7.20E-4 9.52E-10 9.BOE-7 Sr-90 2.79E-2 4.43E- 2 1.63E-6 7.16E-5 9.47E-11 9.SOE-9 Sr-91 1.28E+2 3.87E-1 1.43E-5 6.27E-4 8.28E-10 3.BlE-4 Sr-92 2.51E+2 1.67E-1 6.16E-6 2.71E-4 3.SBE-10 3.23E-4 Tc-99m 2.18E+l 5.70E-2 2.lOE-6 9.21E-5 1.22E-10 9.SSE-6 Page 27 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Excellence- Every project Every day. EALs per NEI 99-01 Rev. 06 REV. 00 Xiv Xir h ESOi Depleted Release Receptor Submersion Submersion Mix Nuclide Fracti on Cone. Cone. Dose mrem cm 3 Ci yQ yQ mrem

µCi sec MWTh cm 3 cm 3 Te-127 8.95E-1 7.SSE-2 2.78E-6 1.22E-4 1.61E-10 5.20E-7 Te-127m 5.44E-1 1.84E-2 6.77E-7 2.97E-5 3.93E-11 7.69E-8 Te-129 1.02E+1 1.93E-2 7.09E-7 3.llE-5 4.llE-11 1.SlE-6 Te-129m 5.74E+O 7.75E-2 2.86E-6 1.25E-4 1.66E-10 3.42E-6 Te-131m 2.59E+2 2.23E-1 8.23E-6 3.61E-4 4.77E-10 4.46E-4 Te-132 3.81E+1 1.69E+O 6.22E-5 2.73E-3 3.61E-9 4.95E-4 Xe-131m 1.44E+O 1.32E+2 4.87E-3 2.14E-1 2.83E-7 1.46E-3 Xe-133 5.77E+O 1.94E+4 7.14E-1 3.13E+1 4.14E-5 8.60E-1 Xe-133m 5.07E+O 5.90E+2 2.18E-2 9.SSE-1 1.26E-6 2.30E- 2 Xe-135 4.40E+1 3.56E+3 1.31E-1 5.75E+O 7.60E-6 1.20E+O Xe-135m 7.SSE+l 5.23E-3 1.93E-7 8.46E-6 1.12E-11 3.04E-6 Xe-138 2.13E+2 6.45E-3 2.37E-7 1.04E-5 1.38E-11 1.06E-5 Y-90 7.03E-1 4.30E-4 1.58E-8 6.96E-7 9.19E-13 2.33E-9 Y-91 9.62E-1 5.86E-3 2.16E-7 9.48E-6 1.25E-11 4.34E-8 Y-92 4.81E+1 2.28E-3 8.39E-8 3.68E-6 4.87E-12 8.43E-7 Y-93 1.78E+1 3.31E-3 1.22E-7 5.36E-6 7.08E-12 4.53E-7 Zr-95 1.33E+2 8.21E-3 3.03E-7 1.33E-5 1.75E-11 8.42E-6 Zr-97 3.34E+1 6.39E-3 2.35E-7 1.03E-5 1.36E-11 1.64E-6 2.71E+04 100.00% 4.39E+01 5.80E-5 8.05 4.39E+1 mrem Given a radiation effluent monitor reading of 43.9 µCi/cm 3 , and the assumptions of the scenario, the EDE value is 8.05 mrem.

Spreadsheet cases are run for all four release points. See Section 2.0 for resu lts.

Page 28 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Excellenco-E,try project. Every day. EALs per NEI 99-01 Rev . 06 REV. 00 7.4 CEDE and COE Thyroid For the example CEDE and COE Thyroid calculation , the release point is the Reactor Building at five hours since shutdown , and a gross concentration of 1.22E-2 µCi/cc ,

with a Secondary Containment Holdup time of 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months per Design Input 5.7 (this concentration was determined iteratively to produce 49 .8 mrem Thyroid COE).

In Table 16, the columns labeled "hrsoiThyroid mrem/µCi" and "hEsoi CEDE mrem/µCi" are the dose factors developed in Section 7 .1 .

The column labeled "Depleted Mix Ci/MWTh " is the "Release Ci/MWTh" calculated above in Section 7.2 for each isotope.

The "Fraction" column determines the fraction each isotope contributes to the gross activity, and is used to scale the activity for each isotope .

The column "Xiv Release Cone. µCi/cm 3" contains a calculation that scales the "Depleted Mix" column to a user entered gross concentration based on the "Fraction" and is the variable Xiv in the equation below. In th is case , the gross concentration entered was 1.22E-2 µCi/cc.

Values in the "x;, Receptor Cone. µCi/cm 3" column are calculated by multiplying the release concentration by the applicable dispersion factor, the volume of the release ,

and requisite conversion factors. The basic equation from Section 6.8:

Xir= x IV*

v* ( ~)Q For isotope 1-131 , an example is presented:

Receptor Release Cone. Flow (X/Q) Cone.

1.63E-04 µCi 93,000 4

2.83E-02 m* 1 mill 3.90E-06 see 2.79E-08 µCi

- - - - - - + - - - t -- -+-- + - -- + - - - + - - - t - - + - - - - + - - = - - - - + - -

cm' 1 4* 60 see m* cm' Where :

v = 93,000 ft 3/min is the rated flow from the Reactor Building from Design Input 5.8 .

(XIQ) = 3.90E-06 is the Particulate and Iodine dispersion coefficient for the Reactor Building from Design Input 5.8 .

Values in the column labeled "Inhalation Thyroid Dose mrem" are calculated by multiplying the following factors: concentration at the receptor, the breathing rate , the time , and the dose conversion factor. The basic equation is shown in Section 6.8.

Dose = L/Xir

B

t

hrsoJ For isotope 1-131 , an example is presented :

Page 29 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Excellence-Every project. Every day. EALs per NEI 99-01 Rev. 06 REV. 00 xir B Inhalatio n hrsoi Receptor Breathing Thyroid Cone. Time Rate Th yro id D o se

2. 79E-08 t*fi 1 flf l .20 E+06 em* l .08E+03 mrem 3.62 E+Ol mrem

= ----+---

em* flf t*fi Where:

hTso; is the thyroid dose factor for each isotope from Section 7.1.

B = 1.20E+06 cm 3/hr is the breathing rate . This value is equal to 3.33E-4 m 3/sec from Design Input 5.9.

Values in the "Inhalation CEDE Dose mrem" co lumn are calculated by multiplying the following factors : concen tration at the receptor, the breathing rate , the time , and the dose conversion factor. The basic equation comes from Section 6.9 .

Dose = L/Xir

B

t

hEsoa For isotope 1-131 , an example is presented :

X;r B Inhalation Breathing hESOi Recepto r CEDE Cone Time Rate CEDE Dose

2. 79E-08 t*fi 1 flf l .20E+06 em* 3.29E+Ol m rem 1.lOE+OO mrem em* flf t*fi For ease of comparison , the tab le row for 1-131 is shown here:

X;v X ;r hrsoi hESOi De p leted Inhalation Inhalati o n CEDE R e le a se Receptor Thyroid Mix Thyro id CEDE Nuclide Fractio n C one. Con e.

mrem mrem Ci D ose Dose gQi gQi

µCi µCi MWTh mrem m rem cm 3 cm 3 1-131 1.08E+3 3.29 E+l 3.89E+2 l.34E-2 l.63 E-4 2.79E-8 3.62E+l l .l OE+O Table 16- Inhalation Thyroid and CEDE Dose for Reactor Building Xiv Xir hrsoi hESOi De p leted Inhalation Inhalation Relea se Recepto r Thyro id CEDE Mix Thyroid CEDE N uclid e Fra ction C one. Cone.

mrem mrem Ci Dose Dose gQi gQi

µC i µCi MWTh mrem m re m cm3 cm 3 Ba-139 8.88E-3 1.72E-1 2.84E+O 9.76E-5 l.19E-6 2.04E-10 2.17E-6 4.20E-5 Ba-140 9.47E-1 3. 74E+O 3.49E+l l.20E-3 1.46E-5 2.SOE-9 2.85E-3 1.12E-2 Ce-141 l.71E-1 8.95E+O 8.lOE-1 2.78E-5 3.40E-7 5.82E-11 l.19E-5 6.25E-4 Ce-143 4.48E-2 3.39E+O 6.68E-1 2.30E-5 2.80E-7 4.79E-11 2.58E-6 1.95E-4 Ce-144 6.96E+O 3.74E+2 6.56E-1 2.25E-5 2.75E-7 4.71E-11 3.93E-4 2.11E-2 Page 30 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Exi:ellenct-Ev~ry project. EVt!,Y day. EALs per NEI 99-01 Rev. 06 REV. 00 X;v Xir hrso, hESOi Depleted Inhalation Inhalati on Thyroid CED E Mix Release Receptor Thyroid CED E Nuclide Fraction Cone. Cone.

mrem mrem Ci Dose Dose

µCi µCi Mwrh .!&l .!&l mrem mrem cm 3 cm 3 Cm-242 3.48E+O l.73E+4 8.30E-3 2.85E-7 3.48E-9 5.96E-13 2.49E-6 l.23E-2 Cs-13 4 4 .llE+l 4 .63E+l 6.lOE+l 2.lOE-3 2.56E-5 4.38E-9 2.16E-1 2.43E-1 Cs-136 6 .40E+O 7.33E+O l.91E+l 6.57E-4 8.02E-6 l. 37E-9 l.OSE-2 1.21E-2 Cs-137 2.93E+l 3.19E+l 4 .22E+l l.45E-3 1.77E-5 3.03E-9 l.07E-1 1.16E-1 1-131 l.08E+3 3.29E+l 3.89E+2 1.34E-2 1.63E-4 2.79E-8 3.62E+l l.lOE+O 1-132 6.44E+O 3.81E-1 l.27E+2 4.38E-3 5.34E-5 9.lSE-9 7 .07E-2 4.18E-3 1-133 l.80E+2 5.85E+O 6.80E+2 2.34E-2 2.85E-4 4.88E-8 1.0SE+l 3.43E-1 1-134 1.07E+O 1.31E-1 l.70E+l 5.83E-4 7.12E-6 l.22E-9 1.56E-3 l.92E-4 1-135 3.13E+l l.23E+O 4.54E+2 l.56E-2 l.91E-4 3.26E-8 1.23E+O 4 .81E-2 Kr-83 m O.OOE+O O.OOE+O l.68E+2 5.79E-3 7.06E-5 l.21E-8 O.OOE+O O.OOE+O Kr-85 O.OOE+O O.OOE+O l.02E+2 3.SOE-3 4 .27E-5 7.32E-9 O.OOE+O O.OOE+O Kr-85m O.OOE+O O.OOE+O l.OSE+3 3.59E-2 4.38E-4 7.SOE-8 O.OOE+O O.OOE+O Kr-87 O.OOE+O O.OOE+O 2.96E+2 l.02E-2 l.24E-4 2.12E-8 O.OOE+O O.OOE+O Kr-88 O.OOE+O O.OOE+O l.83E+3 6.30E-2 7.69E-4 1.32E-7 O.OOE+O O.OOE+O La-140 4.SlE-1 4.8SE+O 3.34E-1 l.lSE-5 l.40E-7 2.40E-11 l.30E-5 1.39E-4 La-141 3.48E-2 5.81E-1 l.33E-1 4.58E-6 S.58E-8 9.SSE-12 3.99E-7 6.66E-6 La-142 3 .23E- 2 2.53E-1 3.29E-2 l.13E-6 l.38E-8 2.36E- 12 9 .17E-8 7.18E-7 Mo-99 4.33E- 1 3.96E+O 4.66E+O l.60E-4 l.95E-6 3.35E-10 l.74E-4 l.59E-3 Nb-95 l.32E+O S.81E+O 3.32E-1 1.14E-5 1.39E-7 2.39E- 11 3.79E-5 l.66E-4 Nd- 147 7.18E-2 6.8SE+O l.28E-1 4 .40E-6 5 .37E-8 9 .19E-12 7.92 E-7 7.SSE-5 Np-239 2.82E-2 2.51E+O 9.92E+O 3.41E-4 4.16E-6 7.12E- 10 2.41E-5 2.14E-3 Pr-143 6.22E-9 8.lOE+O 2.91E-1 9.99E-6 1.22E-7 2.09E-11 1.56E-13 2.03E-4 Pu-241 4.59E-2 8.25E+3 7.90E-2 2.71E-6 3.31E-8 5.67E-12 3 .12E-7 5.61E-2 Rb-86 4.92E+O 6.62E+O 6.81E-1 2.34E-5 2.86E-7 4.89E-11 2.89E-4 3.89E-4 Rh - 105 9.SlE-2 9.SSE-1 2.36E+O 8.llE-5 9 .90E-7 1.69E- 10 1.93E-5 l.94E-4 Ru -103 2.21E+O 8.9SE+O 4.0lE+O l.38E-4 1.68E-6 2.88E- 10 7.63E-4 3.09E-3 Ru-105 S.SSE- 2 4.SSE-1 l.30E+O 4.47E-5 5.45E-7 9.3 3E- 11 6.21E-6 S.09E-5 Ru-106 5 .07E+l 4 .77E+2 1.44E+O 4.94E-5 6.02E-7 l.03E-10 6.27E-3 S.90E-2 Sb-127 5.SSE- 1 6.03E+O 4.27E+O l.47E-4 1.79E-6 3.06E-10 2.04E-4 2.22E-3 Sb-129 7.66E-2 6 .44E-1 7.32E+O 2.52E-4 3.07E-6 5 .25E-10 4.83E-5 4 .06E-4 Sr-89 l.54E+O 4 .14E+l 1.78E+l 6 .12E-4 7.47E-6 l.28E-9 2.36E-3 6.36E- 2 Sr-90 9.77E+O l.30E+3 l.77E+O 6.09E-5 7.43E-7 1.27E-10 1.49E-3 l.98E-1 Sr-9 1 l.SlE-1 l.66E+O l.SSE+l 5.33E-4 6.SOE-6 1.llE-9 2.02E-4 2.22E-3 Sr-9 2 8.lOE-2 8.07E-1 6.69E+O 2.30E-4 2.81E-6 4.BOE-10 4 .67E-5 4.65E-4 Tc-99m l.85E-1 3.26E-2 2.28E+O 7.83E-5 9.SSE-7 l.64E-10 3.64E-5 6.39E-6 Te-127 2.39E- 2 3.18E- 1 3.02 E+O l.04E-4 1.27E-6 2.17E-10 6.22E-6 8.28E-5 Te-127m 8.84E- 1 2.15E+l 7.35E-1 2.53E-5 3.08E-7 5.28E-11 5 .60E-5 l.36E-3 Te-129 6.03E-3 8.95E-2 7 .70E-1 2.65E-5 3.23E-7 5.53E- 11 4.00E-7 5.94E-6 Te-129m 1.46E+O 2.39E+l 3 .lOE+O l.07E-4 1.30E-6 2.23E-10 3.90E-4 6.39E-3 Te-131m l.34E+2 6.40E+O 8.93 E+O 3.07E-4 3.75E-6 6.41E-10 1.03E- 1 4.93E-3 Te-132 2.32E+2 9.44E+O 6.76E+l 2.32E-3 2.83E-5 4 .85E-9 1.35E+O 5.49E-2 Xe-131m O.OOE+O O.OOE+O l.32 E+2 4.SSE-3 5.SSE-5 9 .49E-9 O.OOE+O O.OOE+O Xe-133 O.OOE+O O.OOE+O l.94E+4 6.66E-1 8.12E-3 1.39E-6 O.OOE+O O.OOE+O Xe-133m O.OOE+O O.OOE+O 5.90E+2 2.03E-2 2.48E-4 4 .24E-8 O.OOE+O O.OOE+O Xe-135 O.OOE+O O.OOE+O 3.5 6E+3 l.22E-1 l.49E-3 2.SSE-7 O.OOE+O O.OOE+O Xe-135m O.OOE+O O.OOE+O 5.23E-3 l.BOE-7 2.19E-9 3.75E- 13 O.OOE+O O.OOE+O Xe-138 O.OOE+O O.OOE+O 6.45E-3 2.22E-7 2.70E-9 4 .63E- 13 O.OOE+O O.OOE+O Y-90 3.52E-2 8.44E+O l.72E-2 5.92E-7 7 .22E-9 l.24E- 12 5.22E-8 1.25E-5 Y-91 4 .07E-1 4 .88E+l 2.34E-1 8.06E-6 9 .83E-8 l.68E- 11 8 .22E-6 9.86E-4 Y-92 l.37E-2 7 .81E-1 9 .llE-2 3 .13E-6 3.82E-8 6.54E-12 1.07E-7 6 .13E-6 Page 31 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Excellenc~Every project. Every doy. EALs per NEI 99-01 Rev. 06 REV. 00 X;v X;r hrso; heso; Depleted Inhalation Inhalation CEDE Release Receptor Thyroid CEDE Thyroid Mix Nuclide Fraction Cone. Cone.

mrem mrem Ci Dose Dose

µCi µCi MWTh !!Qi !!Qi mrem mrem cm 3 cm 3 Y-93 1.87E-2 2.lSE+O 1.33E-1 4.56E-6 5.56E-8 9.52E-12 2.14E-7 2.46E-5 Zr-95 5.33E+O 2.36E+l 3.28E-1 1.13E-5 1.38E-7 2.36E-11 1.SlE-4 6.69E-4 Zr-97 3.54E-1 4.33E+O 2.SS E-1 8.78E-6 1.07E-7 1.83E-11 7.78E-6 9.53E-5 2.91E+4 100.00% 1.22E-2 2.09E-6 50 2.37 1.22E-2 mrem mrem Thyroid CEDE Given a radiation effluent monitor reading of 1.22E-2 µCi/cm 3 , and the assumption s of the scenario , the COE thyroid value is 50 mrem and the CEDE is 2.37 mrem.

Spreadsheet cases are run for all four release points . See Section 2.0 for results.

Page 32 of 34

CALC N EE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Exceflence- Eve,y project. Cv,:ry day. EALs per NEI 99-01 Rev. 06 REV. 00 7.5 Resultant Dose Summary A single spreadsheet was used to calculate EDE, CEDE , and thyroid COE . With the given source term , when the user changes the effluent gross concentration value , the spreadsheet calculates resultant doses.

Results and variables for the reactor building case are shown below. As can be seen here , an effluent release rate of 1.22E-02 µCi/cc at the Reactor Building will result in an offsite dose of approximately 50 mrem COE thyroid. This value corresponds to the new RA 1 EAL entry threshold of 50 mrem COE thyroid .

Dose totals are taken from the tabular spreadsheet data presented on the preceding pages .

Inhalation CEDE: 2.37 mrem Submersion EDE: 0.39 mrem

===

TEDE : 2.76 mrem Inhalation Thyroid CDE: 49.8 mrem Release Point: Reactor Building SBGT ?: off Effluent Cone. : 1.22E*02 µC i/cc Release Flow CFM: 93,000 Release: Hrs. since Rx. Shutdown: 5 Hrs. Core Uncovered : 1 Exposure Time (hrs.) : 1 Secondary Containment Holdup Hrs.: 0.5 Hours w/ Sprays On: 2 cm3 pe r ft 3: 0.0283168 Submersion X/Q: 4.30E-06 sec/m 3 Inhalation X/Q: 3.90E-06 sec/m3 Breathing Rate 3.33E-4 m3/ sec = 1.20E+6 cm 3/h r Spreadsheet cases are run for all four release points and for decay times of five hours.

Cases were also run for all four release points for decay times of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months in consideration of EAL entry thresholds that are mode dependent.

The output for all release points and decay times are shown in Appendix 1.

See Section 2.0 for results .

8.0 Computer Software No computer software is used in this calculation .

Page 33 of 34

CALC NEE-323-CALC-005 ENERCON Revised Gaseous Radiological NO.

Excellence-Every project Every day. EALs per NEI 99-01 Rev. 06 REV. 00 9.0 Impact Assessment This calculation is based on "realistic" assumptions for the purpose of declaring EALs ,

rather than typical conservative "bounding" type design basis analyses. The calculation documents the EAL threshold values for specific plan monitors to assist Operations and Emergency Response personnel in determining the new basis for EALs RA1, RS1 , and RG1 in accordance with NEI 99-01 Rev. 6.

Page 34 of 34

CALC NEE-323-CALC-005 ENERCON Appendix A NO.

Excellence-Every project Every doy. Dose Spreadsheet Outputs REV. 00 Turbine Building: Modes 1, 2, and 3 Inhalation CEDE: 2.38 mRem Submersion EDE: 0.39 mRem

==

TEDE: 2.77 mRem Inhalation Thyroid CDE: 50.0 mRem Release Point: Turbine Building SBGT ?: off Effluent Cone.: I 1.58E-02 I uCi/cc Release Flow CFM: 72,000 VI QJ Release: Hrs. since Rx. Shutdown: I 5 Hrs. Core Uncovered: I 1

.c ltS ltS Exposure Time (hrs.): I 1 Secondary Containment Holdup Hrs. : I 0.5 Hours w/ Sprays On: I 2 cm 3 per ft3 : 0.0283168 Submersion X/Q: 4.30E-06 sec/m3 Inhalation X/Q: 3.90E-06 sec/m 3 Breathing Rate 3.33E-4 m3/ sec 1.20E+6 cm3/hr Page 1 of 8

CALC N EE-323-CALC-005 ENERCON Appendix A NO.

Excellence-Every profect f~,y day. Dose Spreadsheet Outputs REV. 00 Turbine Building: Modes 4 and 5 Inhalation CEDE: 2.59 mRem Submersion EDE: 0.07 mRem

==

TEDE: 2.67 mRem Inhalation Thyroid CDE: 49.7 mRem Release Point: Turbine Building SBGT ?: off Effluent Cone.: I 1.30E-02 I uCi/cc Release Flow CFM: 72,000 Ill (1) Release: Hrs. since Rx. Shutdown: I 36 Hrs. Core Uncovered : I 1

..0 n,

n, Exposure Time (hrs.): I 1 Secondary Containment Holdup Hrs.: I o.s Hours w/ Sprays On : I 2 cm3 per ft3 : 0.0283168 Submersion X/Q: 4.30E-06 sec/m3 Inhalation X/Q: 3.90E-06 sec/m 3 Breathing Rate 3.33E-4 m3/sec = 1.20E+6 cm3/hr Page 2 of 8

CALC N EE-323-CALC-005 ENERCON E.xceflence- Every project. Every day.

Appendix A Dose Spreadsheet Outputs NO.

REV. 00 Reactor Building: Modes 1, 2, and 3 Inhalation CEDE: 2.37 mRem Submersion EDE: 0.39 mRem

==

TEDE : 2.76 mRem Inhalation Thyroid CDE: 49.8 mRem Release Point: Reactor Building SBGT ?: off Effluent Cone.: I 1.22E-02 I uCi/cc Release Flow CFM: 93,000 VI Q) Release : Hrs. since Rx. Shutdown: I 5 Hrs. Core Uncovered : I 1

.c tO I..

tO Exposure Time (hrs.): I 1 Secondary Containment Holdup Hrs.: I 0.5 Hours w/ Sprays On: I 2 cm3 per ft3 : 0.0283168 Submersion X/Q: 4.30E-06 sec/m3 Inhalation X/Q: 3.90E-06 sec/m3 Breathing Rate 3.33E-4 m3/sec 1.20E+6 cm3/hr Page 3 of 8

CALC NEE-323-CALC-005

~

ENERCON Appendix A NO.

Exceflenc~Every projtct. Every day. Dose Spreadsheet Outputs REV. 00 Reactor Building: Modes 4 and 5 Inhalation CEDE: 2.60 mRem Submersion EDE: 0.07 mRem TEDE: 2.68 mRem Inhalation Thyroid CDE: 49.9 mRem Release Point: I Reactor Building I SBGT ?: off Effluent Cone.: I 1.0lE-02 I uCi/cc Release Flow CFM : 93,000 II)

C1' Release: Hrs. since Rx. Shutdow n: I 36 I Hrs. Core Uncovered: I 1 I

.c "i:

I I Exposure Time (hrs.): 1 I Secondary Containment Holdup Hrs.: 0.5 I Hours w/ Sprays On: I 2 I cm3 per ft3 : 0.0283168 Submersion X/Q: 4.30E-06 sec/m3 Inhalation X/Q: 3.90E-06 sec/m3 Breathing Rate 3.33E-4 m3/sec = 1.20E+6 cm3/hr Page 4 of 8

CALC N EE-323-CALC-005 ENERCON Appendix A NO.

Excellenct-Every project Every day. Dose Spreadsheet Outputs REV. 00 Offgas Stack: Modes 1, 2, and 3 Inhalation CEDE: 1.96 mRem Submersion EDE: 8.0S mRem TEDE : 10.00 mRem Inhalation Thyroid CDE: 41.1 mRem Release Point: IOffgas Stack SBGT ?: on Effluent Cone.: I 4.39E+Ol I uCi/cc Release Flow CFM: 10,000 II)

QJ Release: Hrs. since Rx. Shutdown: I 5 Hrs. Core Uncovered: I 1

.c n,

"i:

n, Exposure Time {hrs.) : I 1 Secondary Containment Holdup Hrs.: I <0.5 Hours w/ Sprays On : I 2 cm 3 per ft3 : 0.0283 168 Submersion X/Q: 2.SOE-07 sec/ m3 Inhalation X/Q: 3.lOE-07 sec/ m3 Breathing Rate 3.33E-4 m3/sec 1.20E+6 cm3/ hr Page 5 of 8

CALC N EE-323-CALC-005 ENERCON Appendix A NO.

Excellence-Evtry project. Evtry doy. Dose Spreadsheet Outputs REV. 00 Offgas Stack: Modes 4 and 5 Inhalation CEDE: 2.61 mRem Submersion EDE: 1.41 mRem

==

TEDE: 4.02 mRem Inhalation Thyroid COE: 50.0 mRem Release Point: IOffgas Stack SBGT ?: on Effluent Cone. : I 4.52E+Ol I uCi/cc Release Flow CFM: 10,000 VI Q) Release: Hrs. since Rx. Shutdown: I 36 Hrs. Core Uncovered: I 1

.c Exposure Time (hrs.): I 1 Secondary Containment Holdup Hrs.: I <0.5 Hours w/ Sprays On : I 2 cm3 per ft3 : 0.0283168 Submersion X/Q: 2.SOE-07 sec/m 3 Inhalation X/Q: 3.lOE-07 sec/m3 Breathing Rate 3.33E-4 m3/sec 1.20E+6 cm3/hr Page 6 of 8

CALC NEE-323-CALC-005 ENERCON Appendix A NO.

Exctllenc~Evtry project Every doy. Dose Spreadsheet Outputs REV. 00 LLRPSF: Modes 1, 2, and 3 Inhalation CEDE: 2.37 mRem Submersion EDE: 0.39 mRem

= = == = =

TEDE: 2.76 mRem Inhalation Thyroid CDE : 49.7 mRem Release Point: I LLRPSF SBGT ?: off Effluent Cone.: I 1.SlE-02 I uCi/cc Release Flow CFM : 7S,OOO VI Q) Release : Hrs. since Rx. Shutdown: I 5 Hrs. Core Uncovered: I 1

.c n,

"i:

n, Exposure Time (hrs.) : I 1 Secondary Containment Holdup Hrs.: I 0.5 Hours w/ Sprays On : I 2 cm3 per ft3 : 0.0283168 Submersion X/Q: 4.30E-06 sec/m 3 Inhalation X/Q: 3.90E-06 sec/m 3 Breathing Rate 3.33E-4 m3/ sec = 1.20E+6 cm3/hr Page 7 of 8

CALC NEE-323-CALC-005 ENERCON Appendix A Dose Spreadsheet Outputs NO.

Excellenco-Every project. Every day.

REV. 00 LLRPSH: Modes 4 and 5 Inhalation CEDE: 2.60 mRem Submersion EDE: 0.07 mRem

= == = = =

TEDE : 2.67 mRem Inhalation Thyroid CDE: 49.8 mRem Release Point : I LLRPSF SBGT ?: off Effluent Cone.: I 1.2SE-02 I uCi/cc Release Flow CFM : 7S,OOO Ill GJ Release: Hrs. since Rx. Shutdown : I 36 Hrs. Core Uncovered: I 1

.c n,

"i:

n, Exposure Time (hrs.): I 1 Secondary Containment Holdup Hrs.: I 0.5 Hours w/ Sprays On : I 2 cm3 per ft3 : 0.0283 168 Submersion X/Q: 4.30E-06 sec/m3 Inhalation X/Q: 3.90E-06 sec/ m3 Breathing Rate 3.33E-4 m3/ sec = 1.20E+6 cm3/ hr Page 8 of 8

CALC Attachment 1 N EE-323-CALC-005 ENERCON NO.

CALCULATION PREPARATION Exceflenc~-Every project. Every day.

CHECKLIST REV. 00 CHECKLIST ITEMS 1 YES NO N/A GENERAL REQUIREMENTS

1. If the calculation is being performed to a client procedure , is the procedure being used the latest revision? D D ~

The calculation is being prepared to ENERCON 's procedures .

2. Are the proper forms being used and are they the latest revision? ~ D D

3. Have the appropriate client review forms/checklists been completed? D D ~

The calculation is being prepared to ENERCON 's procedures .

4. Are all pages properly identified with a calculation number, calculation revision and page number consistent with the requirements of the client's procedure? ~ D D

5. Is all information legible and reproducible? ~ D D

6. Is the calculation presented in a logical and orderly manner? ~ D D

7. Is there an existing calculation that should be revised or voided? D ~ D This is a new calculation to support implementing NEI 99-01 Rev. 6

8. Is it possible to alter an existing calculation instead of preparing a new calculation for this situation? D ~ D

9. If an existing calculation is being used for design inputs, are the key design inputs, assumptions and engineering judgments used in that calculation val id and do they D ~ D apply to the calculation revision being performed.

10. Is the format of the calculation consistent with applicable procedures and expectations? ~ D D 11 . Were design input/output documents properly updated to reference this calculation? D D ~

12. Can the calculation logic, methodology and presentation be properly understood without referring back to the originator for clarification? ~ D D OBJECTIVE AND SCOPE

13. Does the calculation provide a clear concise statement of the problem and objective of the calculation? ~ D D

14. Does the calculation provide a clear statement of quality classification? ~ D D

15. Is the reason for perform ing and the end use of the calculation understood? ~ D D

16. Does the calcu lation provide the basis for information found in the plant's license basis? ~ D D

17. If so, is this documented in the calculation?

~ D D

18. Does the calculation provide the basis for information found in the plant's design basis documentation? D ~ D Page 1 of 4

CALC Attachment 1 NEE-323-CALC-005 ENERCON NO.

' CALCULATION PREPARATION Excellence-Every projtct. Every day.

CHECKLIST REV. 00 CHECKLIST ITEMS 1 YES NO N/A

19. If so, is this documented in the calculation? D D ~

20. Does the calculation otherwise support information found in the plant's design basis documentation? D ~ D

21. If so, is this documented in the calculation? D D ~

22. Has the appropriate design or license basis documentation been revised , or has the change notice or change request documents being prepared for submittal?

D D ~

DESIGN INPUTS

23. Are design inputs clearly identified? ~ D D

24. Are design inputs retrievable or have they been added as attachments? ~ D D

25. If Attachments are used as design inputs or assumptions are the Attachments traceable and verifiable? D D ~

26 . Are design inputs clearly distinguished from assumptions? ~ D D 27 . Does the calculation rely on Attachments for design inputs or assumptions? If yes ,

are the attachments properly referenced in the calculation?

D ~ D

28. Are input sources (including industry codes and standards) appropriately selected and are they consistent with the quality classification and objective of the calculation? ~ D D

29. Are input sources (including industry codes and standards) consistent with the plant's design and license basis?

~ D D 30 . If applicable, do design inputs adequately address actual plant conditions? ~ D D

31. Are input values reasonable and correctly applied? ~ D D

32. Are design input sources approved? ~ D D 33 . Does the calculation reference the latest revision of the design input source? ~ D D

34. Were all applicable plant operating modes considered? ~ D D ASSUMPTIONS

35. Are assumptions reasonable/appropriate to the objective? ~ D D

36. Is adequate justification/basis for all assumptions provided? ~ D D

37. Are any engineering judgments used? D ~ D

38. Are engineering j udgments clearly identified as such? D D ~

39. If engineering judgments are utilized as design inputs , are they reasonable and can they be quantified or substantiated by reference to site or industry standards , D D ~

engineering principles , physica l laws or other appropriate criteria?

Page 2 of 4

CALC Attachment 1 N EE-323-CALC-005 ENERCON NO.

CALCULATION PREPARATION Excellt!nce--Every project Every day.

CHECKLIST REV. 00 CHECKLIST ITEMS 1 YES NO N/A METHODOLOGY

40. Is the methodology used in the calculation described or implied in the plant's licensing basis? D ~ D 41 . If the methodology used differs from that described in the plant's licensing basis , has the appropriate license document change notice been in itiated? D D ~

42. Is the methodology used consistent with the stated objective? ~ D D

43. Is the methodology used appropriate when considering the quality classification of the calculation and intended use of the results? ~ D D BODY OF CALCULATION

44. Are equations used in the calculation consistent with recognized engineering practice and the plant's design and license basis? ~ D D

45. Is there reasonable justification provided for the use of equations not in common use? D D ~

46. Are the mathematical operations performed properly and documented in a logical fashion? ~ D D

47. Is the math performed correctly? ~ D D

48. Have adjustment factors, uncertainties and empirical correlations used in the analysis been correctly applied? ~ D D

49. Has proper consideration been given to results that may be overly sensitive to very small changes in input? ~ D D SOFTWARE/COMPUTER CODES

50. Are computer codes or software languages used in the preparation of the calculation? D ~ D 51 . Have the requirements of CSP 3.09 for use of computer codes or software languages, including verification of accuracy and applicability been met? D D ~

52 . Are the codes properly identified along with source vendor, orga nization , and revision level? D D ~

53. Is the computer code applicable for the analysis being performed? D D ~

54 . If applicable, does the computer model adequately consider actual plant conditions? D D ~

55. Are the inputs to the computer code clearly identified and consistent with the inputs and assumptions documented in the calculation? D D ~

56 . Is the computer output clearly identified? D D ~

57. Does the computer output clearly identify the appropriate units? D D ~

Page 3 of 4

CALC Attachment 1 NEE-323-CALC-005 ENERCON NO.

CALCULATION PREPARATION Exctllenct - Evtry projtct. Every day.

CHECKLIST REV. 00 CHECKLIST ITEMS 1 YES NO N/A

58. Are the computer outputs reasonable when compared to the inputs and what was expected? D D ~

59. Was the computer output reviewed for ERROR or WARNING messages that could invalidate the results? D D ~

RESULTS AND CONCLUSIONS

60. Is adequate acceptance criteria specified? D D ~

61 . Are the stated acceptance criteria consistent with the purpose of the calculation , and intended use? ~ D D 62 . Are the stated acceptance criteria consistent with the plant's design basis , applicable licensing commitments and industry codes , and standards? ~ D D

63. Do the calculation results and conclusions meet the stated acceptance criteria? ~ D D

64. Are the results represented in the proper units with an appropriate tolerance, if applicable? ~ D D

65. Are the calculation results and conclusions reasonable when considered against the stated inputs and objectives? ~ D D

66. Is sufficient conservatism applied to the outputs and conclusions? ~ D D 67 . Do the calculation results and conclusions affect any other calculations? D ~ D 68 . If so, have the affected calculations been revised? D D ~

69. Does the calculation contain any conceptual , unconfirmed or open assumptions requiring later confirmation? D ~ D

70. If so , are they properly identified? D D ~

DESIGN REVIEW 71 . Have alternate calculation methods been used to verify calculation results? D D ~

No, a Design Review was performed.

Note:

1. Where required , provide clarification/justification for answers to the questions in the space provided below each question. An explanation is required for any questions answered as "No' or "N/A".

Originator: Ryan Skaggs 12/14/17 Print Name and Sign Date Page 4 of 4

NG-18-0090, Calculation No. NEE-323-CALC-005, Revised Gaseous Radiological EALs Per NEI 99-01 Rev. 06

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NG-18-0090, Calculation No. NEE-323-CALC-005, Revised Gaseous Radiological EALs Per NEI 99-01 Rev. 06

Text

Title:

1.0 Purpose and Scope

1.0 Purpose and Scope

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