ML17146A077

Cook, Units 1 and 2, EP-CALC-CNP-1601, Rev 2, Radiological Effluent EAL Threshold Values.

ML17146A077
Person / Time
Site:	Cook
Issue date:	03/22/2017
From:	McCain S American Electric Power
To:	Office of Nuclear Reactor Regulation
References
AEP-NRC-2017-02 EP-CALC-CNP-1601, Rev 2
Download: ML17146A077 (38)

Text

{{#Wiki_filter:AMERICAN E1ECTRIC POWER Cook Nuclear Plant (CNP) Radiological Effluent EAL Threshold Values EP-CALC-CNP-1601 Revision 2 Document Author: Scott McCain Consultant, OSSI Technical Reviewer: Kevin Simpson EP Supervisor, D.C. Cook EPM Approval: Ron Sieber EP Manager, D.C. Cook Document Author: Technical Reviewer: EPM Approva l: 03/13/17 CNP EAL Technical Bas e s Calcul a tions -R x 1 Effluent S erie s Table of Contents 1. Purpose .............................................................................................. .......................... ......... 3 2. Development Methodology and B a ses ................ ................ .................. ................................ 3 2.1. Threshold Limits ............. ............................. ................................................................. 3 2.2. Effluent Release Points ................................................................................................ 6 2.3. Source Term ................................................................................................................. 7 2.4. Effluent Vent Flow ........................................................................................................ 9 2.5. Release Duration .......................................................................................................... 9 2.6. Meteorology ................................................................................................................ 10 3. Design Inputs ................................................................... ................ ................................... 12 3.1. General Constants and Conversion Factors ............................................................... 12 3.2. Liquid Effluent. .......................................................... ....................................... ........... 12 3.3. Gaseous Eff lu ent .................... ................ .................................................................... 13 4. Calculations .................... .............. ................................. ................... .................. ............. ... 15 4.1. RU 1.1 Liquid Release ................................................................................................. 15 4.2. RU 1.1 Gaseous Release ............................................................................................ 16 4.3. RA1.1, RS1.1 and RG1.1 Gaseous Release .......................... .................................... 17 5. Conclusions ........................... .............. ............ ........................................... ...................... .. 17 6. References .......................................................................................................................... 18 ATTACHMENTS Attachment 1, RU1 .1 Liquid Effluent EAL Calculations .............................................................. 19 Attachment 2, RU1 .1 Gaseous Effluent EAL Calculations ......................................................... 20 Attachment3, RA1.1, RS1.1 and RG1.1 MIDAS Calculations ........................................ ........... 21 EP-CALC-CNP-1601 Page 2 of 38 Revision 2 CNP EAL Technical Bases Calculations -Rx1 Effluent Ser ie s 1. PURPOSE 1.1. The Cook Nuclear Plant (CNP) Emergency Action Level (EA L) Technical Bases Manual contains background information, event declaration thresholds, bases and references for the EAL and Fission Product Barrier (FPB) values used to implement the Nuclear Energy Institute (NEI) 99-01 Revision 6 EAL guidance methodology. This calculation document provides additional technical detail specific to the derivation of the gaseous and liquid radiological effluent EAL values developed in accordance with the guidance in NEI 99-01 Revision 6. Documentation of the assumptions, calculations and results are provided for the CNP Rx1 series EAL effluent monitor values assoc iat ed the NEI 99-01 Revision 6 EALs listed below.

• NEI EAL AU1 .1 (gaseous and liquid) RU1.1 for CNP
• NEI EAL AA 1.1 (gaseous and liquid) RA 1.1 for CNP
• NEI EAL AS1 .1 (gaseous)

RS1 .1 for CNP

• NEI EAL AG1 .1 (gaseous)

RG1 .1 for CNP Scope of Revision 1 In Section 5 (Page 17), for the UE was taken to 'N/A'. The monitor range upper limit for SRA-1805/2805 is 5.0E-2 µCi/cc. The calculated UE threshold of 1.4E-1 µCi/cc is above the readable range. This is an administrative correction.

1.2. Scope

of Revision 2 Added units to tables in sections 2.3.2 and 2.4. This is an administrative correction.

2. DEVELOPMENT METHODOLOGY AND BASES 2.1. Threshold Limits 2.1.1. RU1 .1 Liquid Threshold Limits Gu idance Criteria The RU1 Initiating Condition (IC) addresses a release of gaseous or liquid radioactivity greater than 2 times the Offsite Dose Calculation Manual (ODCM) limits for 60 minutes or longer. CNP Bases ODCM Section 3.2.3 states that the limits for the concentration of radioactive liquid effluents released from the site to unrestricted areas are as follows:

• The concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases
• 2.0E-04 µCi/ml total activity for dissolved and entrained noble gases EP-CALC-CNP-1601 Page 3 of 38 Revision 2 CNP EAL Technical Bases Calculations

-Rx1 Eff luent Series The site specific RU1 .1 liquid eff l uent EAL threshold va l ues will equate to 2 times the ODCM limit. 2.1.2. RU1 .1 Gaseous Threshold Limits G uidance Criteria The RU1 Initiat i ng Condition (IC) addresses a release of gaseous or liquid radioactiv i ty greater than 2 times the Offsite Dose Calculation Manual (ODCM) limits for 60 minutes or longer. CNP Bases ODCM Section 3.2.4 states that the limits for the radioactive gaseous effluents released from the site to unrestricted areas are as follows:

• Less than or equal to 500 mrem/yr to the total body (Noble Gasses)
• Less than or equal to 3000 mrem/yr to the skin (Noble Gasses)
• Less than or equal to 1500 mrem/yr to any organ (radioiodines, radioactive materials in particulate form and radionuclides o ther than noble gases with half-lives > 8 days) The inhalation (internal organ) ODCM limit is not applicable for the Unusual Event EAL threshold determination since; (1) ind i vidual uptake dose assessment is highly variable and requires real time representative samp l es, and (2) a predominant Nob l e Gas source term (no core damage) is assumed for the unusua l event accident leve l. The site specific RU 1.1 gaseous eff l uent EAL threshold values wi ll equate to 2 times the ODCM limit for the lesser of the tota l body or skin exposure pathways.

2.1.3. RA 1.1 Liquid Threshold Limits Guidance Criteria The RA 1 Init i ating Condition (IC) addresses a release of radioactivity resulting in offsite dose greater than 10 mrem TEDE or 50 mrem thyroid COE. This is based on values at 1 % of the EPA Protective Action Guides (PAGs). Per NEI 99-01, the effluent monitor readings should correspond to the above dose limits at the " site-specific dose receptor point" (consistent with the calculation methodology employed) for one hour of exposure. CNP Bases The liquid effluent limits are based on the water concentration values given in 10 CFR 20 Appendix B Table 2 Column 2 (see Section 2.1.1 above). The 10 CFR 20 values are equivalent to the radionuclide concentrations which, if ingested continuously over the course of a year, would produce a total effective dose equivalent of 0.05 rem (50 mRem). The EPA PAGs are based on a TEDE dose from immersion, inhalation and deposition. The 10 CFR 20 limits and the EPA limits do not represent the same type of exposure and thus cannot be compared on a one to one basis. EP-CALC-CNP-1601 Page 4 of 38 Revision 2 CNP EAL Technical Bases Calculations -Rx1 Effluent Series Thus, the site specific EALs will not contain an RA 1.1 liquid effluent monitor threshold value that equates to 1 % of the EPA PAG. However, EALs RA 1.3 and RA 1.4 will remain applicable for liquid effluent releases that exceed the threshold based upon sample and field survey results. 2.1.4. RA 1.1 Gaseous Threshold Limits Guidance Criteria The RA 1 IC addresses a release of radioactivity resulting in offsite dose greater than 10 mrem TEDE or 50 mrem thyroid CDE. Per NEI 99-01, the effluent monitor readings are based on values at 1 % of the EPA Protective Action Guides (PAGs) at the "site-specific dose receptor point" (consistent with the calculation methodology employed) for one hour of exposure. CNP Bases The gaseous effluent limits for RA 1.1 are based on va l ues that equate to an offsite dose greater than 10 mrem TEDE or 50 mrem CDE thyroid, which are 1 % of the EPA PAGs. 2.1.5. RS1 .1 Gaseous Threshold Limits Guidance Criteria The RS1 IC addresses a release of radioactivity result i ng in offsite dose greater than 10 0 mrem TEDE or 50 0 mrem thyroid CDE. This is based on values at 10% of the EPA Protective Action Guides (PAGs) at the specific dose receptor point" (consistent with the calcu l ation methodology employed) for one hour of exposure. CNP Bases The gaseous effluent limits for RS1 .1 are based on values that equate to an offsite dose greater than 100 mrem TEDE or 500 mrem CDE thyroid, which are 10% of the EPA PAGs. 2.1.6. RG1 .1 Gaseous Threshold Limits Guidance Criteria The RG1 IC addresses a release of radioactivity resulting in offs i te dose greater than 1,000 mrem TEDE or 5,00 0 mrem thyroid CDE. This is based on values at 100% of the EPA Protective Action Guides (PAGs) at the " site-specific dose receptor point" (consistent with the calculation methodology emp l oyed) for one hour of exposure. CNP Bases The gaseous effluent limits for RG1 .1 are based on values that equate to an offsite d o se greater than 1,000 mrem TEDE or 5,000 mrem CDE thyroid, which are 10 0% of the EPA PAGs. EP-CALC-CNP-1601 Page 5 of 38 Revision 2 CNP EAL Technical Bases Calculations -Rx1 Effluent Series 2.2. Eff l uent Release Points Note -All effluent release points assume a background reading of zero to conservative l y account for all modes of operation applicable to the EALs. 2.2.1. Liquid Release Points Guidance Criteria Per NEI 99-01, the RU1 IC addresses normally occurring continuous radioactivity releases from monitored gaseous or liquid eff l uent pathways (EAL #1) and planned batch releases from non-continuous release pathways (EAL #2). Per NEI 99-01, the RA 1 IC includes events or conditions involving a radiological release, whether gaseous or liquid, monitored or un-monitored. Classification based on effluent monitor readings assumes that a release path to the environment is estab l ished. If the effluent flow past an eff l uent monitor is known to have stopped due to actions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes. The "site-specific monitor list and threshold values" should be determined with consideration of the selection of the appropriate installed gaseous and liquid effluent monitors. CNP Bases There are three monitored liquid eff l uent lines that discharge to the environment at CNP (O D CM Attachment 3.2) One monitor is used for batch liquid releases (ODCM 3.3.1.a.1 ): 1. Liquid Radwaste Effluent Line (RRS-1001) Eight monitors are used for continuous liquid releases (ODCM 3.3.1.b.1 ): 2. Steam Generator B l owdown Eff l uent Line (R-19, DRS-3101/4101)

3. Steam Generator B l owdown Treatment Effluent Line (R-24, DRS-3201/4201) 4. Essentia l Service Water System Effluent Line (R-2 0 , R-28) Under normal conditions, the service water stream does not contain any radioact i vity. The ESW monitors (R-20 and R-28) are only used for post LOCA leak detection (ODCM Attachme n t 3.2). Thus, the Service Water System Eff l uent Line pathway does not meet the NE I 99-01 criteria for use as an EAL threshold. EP-CALC-CN P-1601 Page 6 of 38 Rev i sio n 2 CNP EAL Technical Bases Calculations

-Rx1 Effluent Se ries 2.2.2. Gaseous Release Points Guidance Criteria Per NEI 99-01 , the RU1 IC addresses normally occurring continuous radioactivity releases fro m monitored gaseous or liquid effluent pathways (EAL #1) and planned batch releases from non-continuous release pathways (EAL #2). Per NEI 99-01 , the RA 1 IC includes events or conditions involving a radiological release, whether gaseous or liquid, monitored or un-monitored. Classification based on effluent monitor readings assumes that a release path to the environment is established. If the effluent flow past an effluent monitor is known to have stopped due to actions t o is olate the release path, then the effluent monitor reading is no longer valid for classification purposes. Per NEI 99-01, t he RS1 and RG1 IC s address monitored and un-monitored releases of gaseous radioactivity. Classification based on effluent monitor readings assumes that a release path to the environment is established. If the effluent flow past an effluent monitor is known to have stopped due to act ions to isolate the release path, then the effluent monitor reading is no longer valid for classification purposes. The "site-specific monitor list and threshold values" should include the effluent monitors described in emergency plan and emergency dose assessment procedures. CNP Bases There are three monitored gaseous effluent lines that discharge to the environment at CNP (ODCM Attachment 3.14) 1. Unit Vent (VRS-1500/2500)

2. Gland Seal Co ndens er Exhaust (SRA-1800/2800)

3. Condenser Air Ejector System (SRA-1900/2900)

2.3. Source

Term 2.3.1. RU1 .1 Liquid Source Term Guidance C riteria NEI 99-01 does not provide specific guidance for AU1 liqu id source term assumptions. CNP Bases The 10 CFR 20 Appendix B, Table 2, Column 2 Sr-90 limit of 5E-7 µCi/ml is used as the most restrictive liquid effluent release value for an unknown mix per ODCM 3.3.1.b.4. EP-CALC-CNP-1601 Page 7 of 38 Revision 2 CNP EAL Technica l Bases Calculations -Rx1 Effluent Series 2.3.2. RU1 .1 Gaseous Source Term Gu idan ce Criteria NEI 99-01 does not prov id e spec ific guidance for AU1 gaseous source term assumptions. CNP Bases The unusual event gaseous source term is derived from a 1 O year average of the continuous and batch Kr and Xe releases occurring in 2006 through 2015, which are taken from the annual rad ioac tive effluent release reports. Kr-85 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) 2015 8.69E-01 O.OOE+OO O.OOE+OO 4.21 E-01 O.OOE+O O 1.32E-03 2014 1.54E+OO O.OOE+OO O.OOE+O O 2.52E-01 O.OOE+OO 2.64E-05 2013 1.84E+O O 7.96E-03 4.17E-03 9.59E-01 1.60E-03 2.39E-02 2012 6.51 E-01 1.73E-03 5.9 0 E-04 6.8 6E-01 O.O O E+OO 1.96E-03 2011 5.67E-01 4.76E-04 8.93E-05 5.53E-01 O.OOE+OO 4.24E-04 2010 3.42E+OO 2.14E-04 2.29E-05 1.72E+OO O.OOE+OO 1.61 E-02 2009 4.36E+OO O.OO E+OO O.OOE+OO 7.97E-02 O.OO E+OO 1.04E-03 2008 1.64E+OO 7.41 E+OO 3.72E-02 1.13E+01 O.OOE+OO 3.36E-01 2007 2.88E+OO 9.70E-03 3.84E-04 1.88E+OO O.O OE+OO 7.42E-03 2006 4.47E+01 6.32E-02 4.74E-02 5.12E+OO O.O OE+OO 2.47E-02 Total 6.25E+01 7.49E+OO 8.99 E-02 2.30E+01 1.60E-03 4.13E-01 Fraction 66.87% 8.02% 0.10% 24.57% 0.00% 0.44% A 1 O year average of the continuous and batch Kr and Xe releases is used as a basis for the EAL thresho lds to provide a reasonable input , with the understanding that variations inherent to emergency events impact the thresholds both higher and lower. Thus, any change in the 10 year average based on future annua l radioactive effluent re le ase reports does not require a redetermination of this input. 2.3.3. RA 1.1, RS1 .1 and RG1 .1 Gaseous Source Terms Guidance Criteria NEI 99-01 specifies that the calcu l ation of monitor readings will require use of an assumed release isotopic mix; t he selected mix should be the same for I Cs AA 1, AS 1 and AG1. CNP Bases The source term utilized in the M I DAS dose model is based upon NUREG-1228 (System Acceptance Test Plan and Procedures for Accident Dose Calculations at the Cook Nuclear Station Test Control Sheet #13) with the following release paths se l ected: Containment Gap Release Norma l F i ltration Unit Vent Env Bypass SGTR Normal RCS Partitioned Gland Sea l Env SGTR Norma l RCS Part i tioned Condenser Air Env Ejector EP-CALC-CNP-1601 Page 8 of 38 Revis i on 2 CNP EAL Technical Bases Calculations -Rx1 Effluent Ser ies A normal RCS source term was se l ected for the GS and SJAE re l ease paths as an event that inv ol ves core o r clad da m age woul d result in a trip and isolation of the turbine and condenser. A 1 hour time after s hutdown (TAS) was chosen for the source decay per iod as i t i s long enough for plant conditions to deteriorate to the point that core damage may occur and a sign i ficant re l ease cou l d start. 2.4. Eff l uent Gaseous Vent Flow Guidance Cr iteria NEI 99-01 does not provide specific guidance for effluent vent flow assumptions. CNP Bases Unit vent flow for a LOCA event accounts for both exhaust fans in each unit operating simultaneously. This would occur when a containment isolation phase B signal starts both exhaust fans. Unit vent flow rate is derived from the 10 year average flow for each unit covering 2006 through 2015. Unit 1 vent f l ow average is typically greater than Unit 2 due to operation of a Fue l Handling Exhaust Fan. 2015 2014 2013 2012 2011 2010 2009 2008 2007 2006 10 Year Average: Two AES Fans in Operation: U 1 (CFM) 7.45E+04 6.76E+04 7.2 1 E+0 4 7.74E+04 7.0 7E+04 8.10E+04 7.82E+04 8.10E+04 7.83E+04 8.85E+04 7.69E+04 1.02E+oS U 2 (CFM) 3.66E+04 4.77E+04 4.74E+04 4.49E+04 4.41E+04 4.53E+04 3.41E+04 3.35E+04 3.78E+04 2.97E+04 4.01E+04 6.51E+04 A 1 0 year ave r age unit vent flow which includes various modes i s used as a basis for the EAL thresholds to provide a reasonable input, with the understanding that variations from different operating modes impact the selected threshold both higher and lower. Thus, any future changes in the 10 year average unit vent flow does not require a redetermination of this input. 2.5. Release Durat i on Guidance Criteria Per NE I 99-0 1, the eff l uent monitor readings for RA 1.1, RS 1.1 and RG 1.1 gaseous EA L threshold values should correspond to a dose at the " site-specific dose receptor point" (consistent w i t h the ca lcul ation methodolog y employed) for one hour of exposure. CNP Bases The effluent monitor readings for RA 1.1, RS 1 .1 and RG 1.1 gaseous EAL threshold va l ues are ca l culated fo r a release duration of one hour. EP-CALC-CNP-1601 Page 9 of 38 Revision 2 CNP EAL Technical Bases Calculations -Rx.1 Effluent Ser ie s 2.6. Meteorology Guidance Criteria The effluent monitor readings s hould correspond to the applicable dose limit at the "s itespecific dose receptor point." The " site-specific dose receptor point" is the distance(s) and/or locations used by the licensee to distinguish between on-site and offsite doses. The selected distance(s) and/or locations should ref lect the content of the emergency plan, and the procedural methodology used to determine offsite doses and protective action recommendations. This is typically the boundary of the Owner Controlled Area. Monitor readings will be calculated using a set of assumed meteorological data or atmospheric dispersion factors; the data or factors selected for use should be the same for I Cs AA1, AS1 and AG1. CNP Bases The site spec ific meteorology used for selections and inputs in the MIDAS dose assessment model is based upo n the UFSAR as documented be low. 2.6.1. Stability Class (UFSAR Tables 2.2-3 through 2.2-9) The predominant stability class of 'D' is determined from the 2005 annual joint frequency distribution tables as follows. Class Hours % A 2072 23.8% B 393 4.5% c 47 0 5.4% D 2451 28.1% E 1710 19.6% F 762 8.7% G 851 9.8% Previous UFSAR information contained the joint frequency tab les for 1992 which also demonstrated class D as the predominant stab ili ty class (with 33%). Long term historical meteorological stability is used as a basis for the EAL thresholds to provide a reasonable inpu t. Any changes in annual stability results do not require a redetermination of this input. EP-CALC-CNP-1601 Page 10 of 38 Revision 2 CNP EAL Technical Bases Calculations -Rx1 Eff luent Ser i es 2.6.2. Wind Speed (UFSAR Section 2.2.3.5) Meteorological data used to compute non-accident doses to a member of the public is maintained current within the ODCM. For purposes of EALs thresholds a wind speed input of 7 mph is used which is based upo n the high v a lue from the UFSAR. The UFSAR states, " The predominant wind speed range is 4-7 mph category." UFSAR Table 2.2-20 Speed Ranqe (mph) 1-3 4-7 >8 10m 1992 (h rs) 2195 4175 2382 10m 1992 (%) 25.1% 47.7% 27.2% UFSAR Tables 2.2-3 -2.2-9 Speed Ranqe (mph) 1.1-4.0 4.1-8.0 >8 1 Om 2005 (h rs) 1551 3652 3499 10m 2005 (%) 17.8% 4 2.0% 4 0.2% The UFSAR his torica l meteorological wind speeds are used as a basis for EALs thresholds. Any differences between historic and current annua l predominant wind speed results do not require a recalculation of this input. 2.6.3. Wind Direction (UFSAR Section 2.2.3.5 and Figure 2.2-3) The wind direction at the main tower varied, with the largest frequencies occurring both from the North and from the South (south being the greater of the two). A wind direction (from) 180° is determined to be the appropriate input for the EAL threshold. 2.6.4. ODCM Gaseous Dispersion Factor (ODCM Attachment 3.16) The highest ground level X/Q at site boundary (594 meters) of 1.4 1 E-05 sec/m 3 is taken from the 10 year average of 1995 to 2004 data at a wind direction from the South sector (180°). 2.6.5. Other Parameters No precipitation is assumed to occur for the duration of the release and plume transport across the EPZ. EP-CALC-CNP-1601 Page 11 of 38 Revision 2

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CNP EAL Technical Bases Calculations -Rx1 Effluent Series 3. DESIGN INPUTS 3.1. General Constants and Conve rsi on Factors 3.1.1. 4 72 cc/sec per cfm 3.1.2. 10 6 µCi per Ci 3.2. Liquid Effluent 3.2.1. Liquid Effluent Monitor Ranges 1) Liquid Radwaste Effluent

• RRS-1001 (UFSAR Table 11.3-1) ..............

............ .............. 5E+OO to 5E+05 cpm 2) SG Blowdown

• R-19 (VDT-WEST-0381Section1

.8) ................................... 1E+01to1E+06 cpm

• DRS-3101/4101 (UFSAR Table 11.3-1) ............................... 5E+OO to 5E+05 cpm 3) SG Blowdown Treatment
• R-24 (VDT-WEST-0381 Section 1.8) ................

........... ........ 1 E+01 to 1 E+06 cpm

• DRS-3201/4201 (UFSAR Table 11.3-1) ............................... 5E+OO to 5E+05 cpm 3.2.2. Liquid Effluent Dilution Flow (F) Liquid Effluent Dilution Flow (ODCM 3.3.1.b.4) ........................................... 2.30E+05 gpm 3.2.3. Liquid Effluent Source Flow (f) -(ODCM Attachment 3.10) 1) Waste Disposal System (maximum input value) ......................

...................... 150 gpm 2) SG Blowdown (maximum input value) ........................... ............................ .... 580 gpm 3) SG Blowdown Treatment ............................................................. ................. ... 60 gpm 3.2.4. 10 CFR 20 Appendix B, Table 2 , Column 2 Source Term Limit (C;) Sr-90 .............. .................................. .............................................................. 5E-7 µCi/ml 3.2.5. Monitor Effic i ency Factor (Eff;} 1) Liquid Radwaste Effluent

• RRS-1001 for Cs-137 (ODCM Attachment 3.11) ................. 3.00 E+07 cpm/µCi/ml 2) SG Blowdown
• R-19 for Cs-137 (ODCM Attachment 3.12) .............................. .4.2E+6 cpm/µC i/ml
• DRS-3101/4101 for Cs-137 (ODCM Attachment 3.11) ........ 3.00 E+07 cpm/µCi/ml EP-CA LC-CNP-1601 Page 12 of 38 Revision 2 CNP EAL Technical Bases Calculations

-Rx1 Effluent Series 3) SG Slowdown Treatment

• R-24 for Mn-54 (ODCM Attachment 3.12) ...................

............. 7.5E+6 cpm/µCi/ml

• DRS-3201/4201 for Sr-90 (ODCM Attachment 3.11) ...........

3.00 E+07 cpm/µCi/ml

3.3. Gaseous

Effluent 3.3.1. Gaseous Effluent Monitor Ranges (UFSAR Table 11.3-1) 1) Unit Vent Monitors

• VRS-1505/2505 (low) ....................

...................................... 9E-07 to 5E-02 µCi/cc

• VRS-150712507 (mid) ...............................................

......... 2E-03 to 2E+03 µCi/cc

• VRS-1509/2509 (high) ....................................................... 1E-01to9E+04

µCi/cc 2) Gland Seal Monitors

• SRA-1805/2805 (l ow) ....................................

...................... 9E-07 to 5E-02 µCi/cc

• SRA-1807/2807 (mid) ........................................................

2E-03 to 2E+03 µCi/cc

• SRA-1809/2809 (high) ....................................................... 1E-01to9E+04

µCi/cc 3) Condenser Air Ejector Monitors

• SRA-1905/2905 (low) .............................

............................. 9E-07 to 5E-02 µCi/cc

• SRA-1907/2907 (mid) ........................................

................ 2E-03 to 2E+03 µCi/cc

• SRA-1909/2909 (high) .......................................................

1 E-01 to 9E+04 µCi/cc 3.3.2. Gaseous Effluent Source Flow (f} Note -Higher vent flow values results in lower monitor readings to obtain a fixed dose. 1) Normal Vent Flow -RU 1.1 (ODCM Attachment 3.15) U1 1.866E+05 cfm is selected based on the most limiting of the vent flow rates as follows:

• Unit 1 (max normal) ..............

............................................ ............. 1.866E+05 cfm

• Unit 2 (max normal) ...................

.................................................... 1.434E+05 cfm 2) Accident Mode Vent Flow -RA/S/G1 .1 U1 1.02E+05 cfm is selected based on the most limiting of the 10 year average vent f l ow rates (with two AES fans in operation) as follows:

• Unit 1 (Mode 2/Accident Mode) ............................................

............ 1.02E+05 cfm

• Unit 2 (Mode 2/Accident Mode) .......................

................................. 6.51E+04 cfm EP-CALC-CNP-1601 Page 13 of 38 Revision 2 CNP EAL Technical Bases Calculations -Rx1 Effluent Se ries 3) Gland Sea l Flow (ODCM Attachment 3.15) 5,508 cfm is selected based on the most limiting unit gland seal vent flow rates as follows:

• Unit 1 ................

............... ............................................. ................. 1.260E+03 cfm

• Unit 2 ...............................................

.................. ...................... ...... 5.508E+03 cfm 4) SJAE Flow (UFSAR 10.4.2) 60 cfm is selected based on the operation of four one stage elements at a design capacity of 15 cfm each. 3.3.3. RU1 .1 Dispersion Factor (X/Q) Dispers i on Factor (ODCM Attachment 3.16) ...................... ...................... 1.41 E-05 sec/m 3 3.3.4. ODCM Dose Factors (ODCM Attachment 3.18) ... ;:;--... _ .S E ..., 0..., ._ E -E CJ:::: o_ CJ--*-cu () CJ() cu*-LL() LL ::i cu ::i Q) ::i Q) ... LL ._ Ill ... Ill Q) Q) Q) 0 Q) 0 0. Ill 0. a o. a ... 0 ... ... a >-.!::: >i -c E -<:C 0 Q) Q) Q) cu cu Ill a::: Ill a::: Ea::: Cii E c: E E .§. --:;: = cu *-O*- Cl) ...J ('j ::E Kr-85 1.61 E+01 1.34E+03 1.72E+01 Xe-131m 9.15E+01 4.76E+02 1.56E+02 Xe-133m 2.51E+02 9.94E+02 3.27E+02 Xe-133 2.94E+02 3.06E+02 3.53E+02 Xe-135m 3.12E+03 7.11 E+02 3.36E+03 Xe-135 1.81E+03 1.86E+03 1.92E+03 EP-CALC-CNP-1601 Page 14 of 38 Revision 2 CNP EAL Technical Bases Calculations -Rx1 Effluent Series 4. Ca lculation s 4.1. RU1 .1 Liquid Release 4.1.1. ODCM Liquid Release Limit (ODCM Section 3.3.1.b.4) Where: SP radiation monitor setpoint equivalent to the ODCM limit (cpm) C; concentration of radionuclide 'i' in the liquid effluent (µCi/ml) Eff; detector efficiency ( cpm per µCi/ml) MRP Multiple Release Point factor such that when all the release points are operating at one time the limits of 10 CFR 20 will not be exceeded (Not used for EAL calculations) F dilution flow (gpm) S F Safety Factor of 0.9 (Not used for EAL calculations) f undiluted flow from the source of the release (gpm) 4.1.2. RU1 .1 Liquid Release EAL Threshold RU1 .1 liquid is two times the calcu l ated ODCM limit setpoint. See Attachment 1 for the spreadsheet calculations that develop the RU1 .1 liquid effluent EAL threshold values for each applicable monitor. EP-CAL C-CNP-16 01 Page 15 of 38 Revision 2 C NP E AL Te c hni ca l Bases Ca l c ul a ti o n s -Rx 1 E fflu ent Se ri es 4.2. RU 1.1 Gaseous Release 4.2.1. ODCM Gaseous Release Limit (ODCM Section 3.3.2.a.1) SP = [S F xM RP x SOO] to/E l body 4 7 2 xfxX xK Q I S P _ [ SFxM RP x30 00 l Skin -472xfx x (L; +1.1MJ Wher e: S P radiation monitor setpoint equivalent to t he ODCM limit (µC i/cc) S F an administrative operation safety factor , less than 1 (Not used for EAL calcul a tions) MRP Multiple Release Point factor such that when all the release points are operating at one time the l i mits of 10 CFR 20 will not be exceeded (Not used for EAL calculations) 500/3000 ODCM Limit -500 total body or 3000 skin (mrem/yr) 472 conversion factor (cc/ft 3 per sec/min) f vent flow (cfm) XIQ most limiting 10 year average meteorologica l dispersion to the controlling site b ound a ry location (s e c/m 3) K; total body dose factor (mrem/yr per µCi/m 3) L; + 1.1 M; skin dose factor (mrem/yr per µCi/m 3) 4.2.2. R U 1.1 Gaseous Release EAL Threshold RU 1.1 gaseous is two times the lesser of the calculated total body or skin ODCM limit setpoint. See Attachment 2 for the spreadsheet calculations that develop the RU1 .1 gaseous effluent EAL threshold values for each applicable mon i tor. EP-CALC-CNP-1601 P a ge 16 of 38 Revis i on 2 CNP EAL Technical Bas es Calculation s -R x 1 Effluent S erie s 4.3. RA 1.1, RS 1.1 and RG 1.1 Gaseous Release The RA 1.1, RS 1.1 and RG 1.1 gaseous release EAL thresholds are developed using the site specific M I DAS dose assessment models with the inputs described in Section 2 above. Note -MIDAS ca l culat io ns were performed for each unit using identical inputs to verify internal source term and dispersion calculations were the same. There was no difference in results between units. Refer to Attachment 3 for the results of the MIDAS gaseous effluent EAL threshold calculations.

5. Conclu s ions Release Point Monitor GE SAE Alert UE VRS-1509/2509 3.3E+O 3.3E-1 N/A N/A __________ (lj_i_g_b) _______ --__

....... ----**-****-**-*-*

• • • • --**-***-***-*
  • --*-**--*---

Unit Vent VRS-15 0 7 /2507 3.3E+O 3.3E-1 3.3E-2 4.2E-3 __ _J Medium J___ _ ___ _ __ (µg_!/cc) _ VRS-1505/2505 N/A N/A 3.3 E-2 4.2E-3 <ll (low) (µCi/cc) (µCi/cc) CJ) SRA-18 0 9/2809 1.6E+2 1.6E+1 1.6E+O 1.4E-1 Cll <ll ______ __ JljigbL_ _ ________ --__ Qi *******-***

• 0:: SRA-18 0 7/2807 1.6E+2 1.6E+1 1.6E+O 1.4E-1 CJ) Gland Seal _____

_____ ___ _ __ (ggi/cc)_ _ _ __ _ _ _Jµ9i/cc)___ :I 0 <ll SRA-1805/2805 N/A N/A N/A N/A CJ) (low) Cll (!) SRA-1909/2909 1.5E+4 1.5E+3 1.5E+2 1.3E+1 _ _ _____ (lj i g __ b_L ________ __ JE_C i/c<::)__ _____ ___ .. ,_, ..... _ Condenser Air SRA-1907 /2907 N/A 1.5E+3 1.5E+2 1.3E+1 Ejectors i------------****-* __ (!:!:.9-iLc: _<::) ____ _ SRA-1905/2905 N/A N/A N/A N/A (low) Radwaste Effluent RRS-1001 N/A N/A N/A 4.6E+4 (cpm) <ll 1.7E+3 CJ) R-19 N/A N/A N/A Cll ___ <ll SG Slowdown ---*-****----*----* ... ------**-*-*---

• Qi 1.2E+4 0:: DRS-3101/4101 N/A N/A N/A (cpm) 3:! :I 2.9E+4 C" R-24 N/A N/A N/A :J SG Slowdown ****-***-*****

..................................................................... .................................. ,_ ............ .. ******-********* --****** ................. ........ (C:Pr:!l) ______ Treatment DRS-3201 /4201 N/A N/A N/A 1.2E+5 (cpm) EP-CALC-CNP-1601 Page 17 of 38 Revis i on 2 ---------------

---

CNP E AL Technical Ba ses C a lcul a tions -R x 1 E fflu e nt Se ri es 6. Reference s 6.1. NEI 99-01 Rev i sion 6, Methodology for Development of Emergency Action Levels, November 2012 6.2. 10 CFR 20 Appen d ix B Table 2 Column 2 6.3. EPA-400-R-92-001, Manual of Protective Actions for Nuclear Incidents, May 1992 6.4. NUREG-1228, Source Term Estimation During Incident Response to S e vere Nuclear Power Plant Accidents , Octob e r 1988 6.5. PMP-6010-0SD-001 , Offsite Dose Calculation Manual (ODCM), Revision 25 6.6. Donald C. Cook Nuclear Plant Units 1 and 2 Annual Radioactive Effluent Release Report

• 2006: AEP:NRC: 7691-01, March 30 , 2007
• 2007: AEP:NRC: 8691-01, March 28 , 2008
• 2008: AEP-NRC-2009-29 , April 29 , 2009
• 2009: AEP-NRC-2 010-3 8, April 2 9, 2 0 1 0
• 2010: AEP-NRC-2011-27, April 29, 2011
• 2 0 11: AEP-NRC-2012-20, April 26, 2012
• 2012: AEP-NRC-2013-25 , Apri l 29, 2013
• 2013: AEP-NRC-2014-30 , April 29 , 2014
• 2014: AEP-NRC-2015-34, Apri l 28, 2015
• 2015: AEP-NRC-2016-32 , Apri l 28 , 2016 6.7. Cook Updated Final Safety Analysis Report, Revision 26
• Section 2.2.3.5
• Tables 2.2-3 through 2.2-9
• Tables 2.2-3, t hrough 2.2-9 and 2.2-20
• Figure 2.2-3
• Section 10.4.2
• Table11.3-1 6.8. ABS Consulting, System Acceptance Test P l an and Procedures for Accident Dose Calculations at the Cook Nuclear Station, July 2009 6.9. SOD-02801 B-001, Aux Building V entilation, Revision 4, 04/27/09 6.10. VTD-WEST-0381, Technical Manual -Radiation Monitoring System for Indiana & Michigan Electric Company Dona ld C. Cook Nuclear Generating Station Units 1 & 2 EP-CALC-CNP-1601 Page 18 of 38 Rev ision 2 Attachment 1 -RU1.1 Liquid Effluent EAL Ca lculations

<II 0.. :::s !E Cl) c;; I > w ...., "'C c: Ci >. -*c; .r. IJ.. I c. I/) c: -...., <II .!!:! E <II .... CJ ::: 0 Cl) .r. !E () ii: .... I-0 0 w :::s.. ii: .J "'C <t ........ $ c: 0 <II c: 0 w ...., c.

iE ..... lil E E = E "'C E .,...: E ...., c. -= c. "'C c. IV C. ::> c. Monitor .!:!. *-Cl c: Cl 0-::> -lk: .!:!. lk: .!:!. Li uid Radwaste Effluent RRS-1001 3.00E+07 2.30E+05 150 2.30E+04 SG S lowdown R-19 4.20E+06 2.3 0E+05 580 8.33E+02 DRS-3101/4101 3.00E+07 2.3 0E+05 580 5.95E+03 SG S lowdown Treatment

.... -.................. ........ .. ......... ..... ""' ... ,.,_§9........ ... . .. .. .. .,.!... **m* " ... .. DRS-3201/4201 3.00E+07 2.30E+05 6 0 5.75E+04 1.15E+05 Sr-90 10 CFR 20 Limit -Ci (µCi/m l): I 5.00E-07 1 EP-CALC-C NP-1601 Page 19 of 38 Revision 2 ,---*-*--------------------------------------- Attachment 2 -RU1 .1 G a s eous E ffluent EAL C alculations !i: I .... -M E LL ::: Cl) (.) Ill ::I.. 0 .... c Cl) >o a. "C .... m E -Cl) So:: o E I--Kr-85 1.61 E+01 Xe-131m 9.15E+01 Xe-133m 2.51E+02 Xe-133 2.94E+02 Xe-135m 3.12E+03 Xe-13 5 1.81E+03 EP-CALC-CNP-1601 :J I I .... .... 0 OM t> M ti E E cu ::: L1. (.) Q) :::: Cl) ::I.. Ill (.) Ill .... 0 ::I.. 0 Cl) c .... c a. .... Cl) *-a. s ;, <( .... Cl) -ra m E E "C .: &! E &! .II: E ra E (/) -(!) -§ I c: M' M' 0 u u :::-u ra .... ::I.. :::!: ::I.. L1. .... ..... .... E Cl)

• Cl) .... a. ..... a. Cl) .... + .... I->o Cl) !i: E d.e u .... )( &! )( &! :::I 0 *-E *-E (/) 1.34E+03 1.72E+01 66.87% 1.08E+01 9.09E+02 4.76E+02 1.56E+02 8.02E-02 7.34E+OO 5.19E+01 9.94E+02 3.27E+02 9.62E-0 4 2.41 E-01 1.30E+OO 3.06E+02 3.53E+02 2.46E-01 7.22E+01 1.71E+02 7.11E+02 3.36E+03 1.71E-05 5.34E-02 7.54E-02 1.86E+03 1.92E+03 4.42E-0 3 7.99E+OO 1.75E+01 1.00E+OO 9.86E+01 1.15E+03 Calculation Constants Unit Vent G S S JAE Flow (CFM): I 1.87E+05 I 5.51 E+03 I 6.00E+01 I Tota l Body-ODE (mRem/yr): 500 Skin Dose-SOE (mRem/yr):

3 000 XIQ (sec/m3): 1.41 E-05 UCF (CFM to cc/sec): 472 DCF (mRad to mRem): 1.1 Calculation Results Unit Vent GS SJAE SP-TB (µCi/cc): 4.0SE-0 3 1.38E-01 1.27E+01 SP-Skin (µCi/cc): 2x ODCM: Page 20 of 38 2.10E-03 4.20E-03 7.12E-02 6.53E+OO 1.421!-01 1.31E+01 Revision 2 Attachment 3 R RA1.1, RS1.1 and RG1.1 MIDAS Calculations Plant Vent -Alert El.\-ID-32b MICHIGANSTA1EPouCE Nuclear Plant Event Technical Data I D Acn1al event Drill Plant Contact Iofol'matloo D Nuclear Power Plant: D.C. Cook Plant Conununicator: Simpson Calling from: D Control Room D TSC D Other IE! EOF Call Back Telephone Nrunber: 269-465-5901-1088 Plant Message number Meteorological Data Wind direction (in degrees): From 180 To 360 Wmd Speed (in MPH): 7 Stability Class: D Precipitation: D Yes ml No Reactol' Information Reactor Shutdown U11it-l Ye.s D No Unit-2 D Yes !Bl No If yes, time of slmtdown: 9/19/2016 09:23 If yes, time of shutdo\\n: Additional Information: CJ SeeAttached Refoase/Offsite Dose Data Cul'l'ent Release Rates Release Pathway: !Bl Airborne D Waterborne Noble Gas {Ci/Sec) 1.6E+OO Remaining Duration {hrs): Ecmivalent 1-131 fCil:sec) 1.2E-03 1.00 Particulate (Ci/sec) 1.SE-04 D Actual D Potential Time of calculation: 9/19/2016 10:23 Based on: !Bl Monitor (in plant) D Sample (in plant) D Back Calculation of Field Data D Other Projected Dose Rate P1*ojected Dose Distance IEDE Thyrnicl Distance TEDE (mJ"em/IU") CDE<mrem/hr) <mreml CDE(mreml Site Botmdary 9.9E+OO 5.0E+Ol Site Boundary 1.0E+ol 4.9E+o1 2 Miles O.OE+OO O.OE+OO 2 I'vfiles 2.3E+OO 6.SE+OO 5 l\ililes O.OE+OO O.OE+OO 5 Miles 7.SE-01 1.SE+OO 10 Miles O.OE+OO O.OE+oo 10 Miles 1.9E-01 5.SE-01 Miles Miles Measured Offsite Radiation Levels Distance Time ffighest reading(mr/lu*) Iodine Ca11lidge(NetCPl\f) Sector Site Boundary O.OE+OO O.OE+OO Miles Miles l\tiiles EP-CALC-CNP-1601 Page 21 of 38 Revision 2 -RA1.1, RS1.1 and RG1.1 MIDAS Calculations

• Version: 1.5.16.090915 Met & Rad Input Summary for Calculation at 09119116 10:30 -First Exposure Period SIT.E: AEP COOK lJ?iTI: CA l\IE?-<-U:

B REPORT DATE: 09/19/16 10::!4 lJA1WAL DAIA DATE: 09/19116 10 :30 START DATE OF RUN: 09/1911610:23 START OF RELEASE: 09119116 10:23 TIME OF TRIP: 09119/16 09:23 START OF EXPOSURE: 09/19/1610:23 EVENT TREE l\JIX SELECTIONS: Jilli ID# 172: CONTAINMENT BYPASS RELEASE, GAP RELEASE, 660 RJhr to 1325 Rlhr on VR.\ 1310/1410 or 231012410, NORMAL FILTRATION, Total Total Release Release Monito1* ConYersion NG Concentrntion Flow Rate ::.\lonito1* ID Pt Filter Reading Status Units to uCifcc ----__ ___ Adi. __ (_uc_il_* c_c_)_ Reading Status Units (uCitsec) \'NT 1500 l On 3.3E-02 0 uCilcc l.OE+-01) 1.004 3.3E-02 l.OE+05 0 CFM l.6E+o6 (nCi1'.sec2 KR,.85JII KR-85 KR,.87 KR.-88 XE--131M XE-133111 XE-133 XE--13ill XE-135 XE-138 1-131 1-132 I-133 1-134 1-135 CS-134 CS-136 CS-137 Total Noble Total Iodine Total Panicolate Adjusted Ground Speed (mph) Ground Direction (Deg.from) Ground Stabilitf Class Ground Temperatm-e (Deg.I) Adjusted Elernted Speed (mph) :Elevated DiRCtion (Deg.from) Dm1ted Stability O.*m Elevated Temperature (Deg.F) Rain (wchesllS min) PJmne Fmdion at Ground Final Plume Height (ft) Release Point 1 GRNDREL Release Fradilln Rate of Total UlE+o5 2.8E+o3 L7E-03 l.3E+05 8.5E-02 2.IIBi-05 l.7E-Ol 4.91:+03 3.IE-03 2.9E+04 l.SE-02 8.ID-05 5.3£.-01 1.IE-H>> 7.lE-03 l.6fii-05 9.SE-02 4.5E+04 2.SE-02 8.4E+o2 5.3E-04 8.8E+o2 S.5E-04 l.6Ei-03 l.OE-03 8.6E+o2 S * .fE-04 L3E+o3 8 * .fE-04 7.-f.E+Ol 4.7E-05 3.0lif-Ol l.9E-05 4.7E+ol 2.!lE-05 L6E+06 5.6E+03 l.SB+-02 ReLPt.l GRND REL Status 7.0 180 D 5?.0 o.o 0 o.o 0.00 1.00 32.8 OP OP OP {)D 2 2 2 2 0 l)"I.UUS: 0 = Good, l = Questionable, 2 =Bad, 3 =Unsteady Winds, 4 =Calm, 5 = Flat, 6 =Rain Reset, 7=Manual Onrride of Raw Data, 8=lfanual!Enrry ofFunn*e Data D-.\TASOURCE: P = Ist. S = 2nd. T =3rd. 2\1 = lHannaL D =Default. L =Last EP-CALC-CNP-1601 Page 22 of 38 Revision 2 Attachment 3 RA1.1, RS1.1 and RG'i.1 MIDAS Calculations Plant Vent -SAE EMD-32b MICHIGANsTATEPOUCE Nuclear Plant Event Technical Data I D Actual event !Bl Drill Plaut Contact Information D Nuclear Power Plant: D.C. Cook Plant Communicator: Simpson Calling from: D Control Room D TSC D Other !Bl EOF Call Back Telephone Numbe1:: 269-465-5901-1088 Plant Message mmiber Meteorological Data Wind direction (in degrees): From 180 To 360 Wmd Speed(inMPH): 7 Stability Class: D Reactor Slmtdown Additional Information: 0 SeeAttached Release Pathway: Unit-1 !Bl Yes If yes, time of s!mtdown: Precipitation: D Yes !Bl No Reac.to1* Information Unit-2 D Yes !Bl No 0 No 911912016 09:09 If yes, time of slmtdown: R.elease/Offsite Dose Data Current Release Rates !Bl Airborne D Waterbome Noble Gas (Ci/Sec) 1.6E+Ol Remaining Duration (hrs): Eonivalent I-131 (Ci/sec) 1.lE-02 1.00 1.SE-03 Particulate (Ci/sec) D Actual D Potential Time of calculation: 9/19/2016 10:09 Based on: IE Monitor (in plant) D Sample (in plant) D Back Calculation of Field Data D Other Projected Dose Rate Projected Dose Distance TEDE Thyroid Distance TEDE Thyrnid fmrem!b1*) CDEfmrem/br) fmreml CDEfmrem\ Site Bounda1y 9.2E+Ol 4.6E+o2 Site Boundary 1.0E+02 4.9E+02 2 Miles O.OE+OO O.OE+OO 2 I\files 2.3E+Ol 6.8E+01 5 Miles O.OE+OO O.OE+OO 5 Miles 7AE+OO 1.SE+ol lOMiles O.OE+OO O.OE+-00 10 Miles 1.9E+OO 5.SE+OO __ l\files __Miles Measm.*ed Offsite Radiation Levels Di'Stance Time Wgbest nading(m1*1h1*) Iodine Cal'flidge(NetCPM) Sector Site Boundmy O.OE+OO O.OE+OO Miles Miles Miles EP-CALC-CNP-1601 Page 23 of 38 Revision 2 Attachment 3 = RA1.1, RS1.1 and RG1.1 MIDAS Calculations Version: 1.5.16.090915 Met & Rad Input Summary for Calculation at 09/19/1610:15 -First E:q>osure Pel"iod SUE: AEP COOK lil'UT: CA l\IENU: B REPORT DATE: 09/19/16 10:10 l\IANUAL DATA DATE: 09/19/16 10:15 START DATE OF RUN: 09/19/1610:09 START OF RELEASE: 09/19/1610:09 TIME OF TRIP: 09119116 09:09 START OF EXPOSURE: 0911911610:08 EVENT TREE l\IIX SELECTIONS: l\Ib: ID# 172: CONTAINMEJ."\'T BYPASS RELEASE, GAP RELEASE, 660 Rfhl* to 1325 Rlhl* on VRA 1310/1410 or 231012'10, NOlUIAL FILTRUION, Total Total Release Release Monitor Conversion NG :Monitor ID Pt Filter Reading Status Units to uCifcc ----__ ___ Adi. Vl\'T 1500 I On 3.3Ml 0 uCUcc l.OE+'DO 1.004 Isotope (uCi!sec) KR-851\I KR.-85 :KR-87 Klt-88 XE-1311\I XE-l33M XE-133 XE-13:51\1 XE-135 XE-138 I-131 I-132 I-133 I-134 I-13:5 CS-IM CS-136 C'>-137 T-0ta1Noble Total Iodine Total Particulate Adjusted Ground Speed (mph) Ground Dir<<lion (Deg.from) Ground Stabilily Oass Ground Tempuatm*e {Deg.F) Adjusted:Elernted Speed {mph) Elevated Dim:tion (Deg.from) Elevated Stability CL15S Elevated Temperatm*e (Deg.F) Rain (inchesll5 min) Plmne Fi-action at Ground Final Plume Height (ft) Release Point 1 GRNDREL Release Fmciion Rate of Total l.o:E+oo 6.4E-02 2.SE+o.t l.7L-03 l.3.E+o6 8.5.E-02 ?.6.E+06 1.7£-01 4.9E+o4 3;IE-03 2.9E-!--05 l.8E-02 UE-!--06 5.3E-Ol l.IE+o:5 7.lE-03 l.6E-!--0Ci 9.8.E-02 4,.:)'"E+o:5 2.SE-02 8..IE+o3 S.3E-04 8.8E+o3 5.:5.E-04 I.6E+o.t l.OE-03 S.6E+o3 5.4E-04 l.3E+64 8.4£-04 7.4E+02 4.7.E-05 3.0.E+ol l.9.E-05 4.i'£+o2 2.9.E-0:5 UE+o7 5.<iEf-04 l.5E+03 Rel Pt.I GRND REL Status 7.0 OP 180 OP D OP 52.0 OD 0.0 2 0 2 2 0.0 2 0.00 0 LOO 32.8 Concentl'ation Flow Rate __ <n_c_u_c_c_)_ Reading Status Units (uCi/sec) 3.31:-01 l.OE+05 0 CTM l.6E+07 STATUS: 0 = Go-0d, I =Questionable, 2 = Ba<l, 3 = Winds, 4 =Calm, 5 =flat, 6 =Rain Reset, 7=Mannal Ovenide of Raw Data, 8=11lanoal Entry of Futm*e Data DATA SOURCE: P = bt. S =2nd. T = 3nl. lH = l\IanuaL D =Default. L =Last EP-CALC-CNP-1601 Page 24 of 38 Revision 2 Attachment 3 R RA1.1, RS1.1 and RG1.1 MIDAS Calculations Plant Vent -GE EMD-32b MicmaANsTATEPoucE Nuclear Plant Event Technical Data I D Actual event Drill Plant Contact Info1'Jllation [] Nuclear Power Plant: D.C. Cook Plant Communicator: Simpson Calling from: D Control Room D TSC !El EOF D Other Call Back Telephone Number: 269-465-5901-1088 Plant Message number Meteorological Data Wind clfrection (in degrees); From 180 To 360 Wind Speed (in MPH): 7 Stability Class: D Precipitation: D Yes Im No Reactor Infonnation Reactor Slmtdovm Unit-1 !El Yes O No Unit-2 D Yes No If yes, time of shutdown: 9/19/2016 08:53 If yes. time of shutdown: Addittonal Information: D SeeAttached Release/Offsite Dose Data Cnnent Release Rates Release Pathway: !Bl Airborne D Waterborne Noble Gas (Ci/Seel 1.6E+02 Remaining Duration (hrs): Eouivalentl-131 (Ci/sec) 1.2E-{}1 1.00 PartictUate(Ci/sec) 1.5E-02 D Actual D Potential Time of calculation: 9/19/2016 09:53 Based on: ml Monitor (in plant) O Sample (in plant) D Back Calculation ofField Data D Other Projected Dose Rate P1:ojected Dose Distance 'IEDE Thyroid Distance 'IEDE Thyroid rmrem/hrl CDEfmremfh1*) lmrem) CDE<m1-em) Site Bounda1y 9.9E+02 5.0E+03 Site Boundacy 1.0E+o3 4.9E+o3 2Miles O.OE+OO O.OE+oO 2 :Miles 2.3E+02 6.8E+02 5 Miles O.OE+OO O.OE+OO 5 Miles 7.5E+o1 1.8E+02 10 Miles O.OE+OO O.OE+OO 10 A-files 1.9E+01 5.8E+01 ___Ivliles __.Miles .Measured Offsite Radiation Levels Distance Time Highest reacling(mr/hr) Iodine Cal"hidge(NetCPM) Sectol' Site Boundary O.OE+OO O.OE+oO Miles Miles Miles ** .,, '-;. * -.->, .-* EP-CALC-CNP-1601 Page 25 of 38 Revision 2 r I I I !

• i. I I Attachment 3 -RA1.1, RS1.1 and RG1.1 MIDAS Calculations Version:.

1.5.16.090915 Met & Rael Input Snmmarv for Calculation at 09/19116 10:00 -Fh-st Exposure Period SITE: AEP COOK Ul'l"'IT: CA l\IENU: B REPORT DATE: 09/19/16 09:59 A*L\J.WALDATAD.ATE: 09/19/1610:00 START OF RELEASE: 09/19/16 09:53 START DATE OF RUN: 09/19116 09:53 TIME OF TRIP: 09Jl9/16 08:53 START OF EXPOSURE: 09119116 09:53 EVENT TREE i\IIX SELECTIONS: i\fu ID# 172: CONT.4.INMENT BYPASS RELEASE, GAP RELEASE, 660 Rlhr to 1325 R/hr on VR.A 1310/1410 01* 2310/2410, NORMAL FILTRATION, Total Total Release Release Monitor Con\*ersion NG :Monitor ID Pt Filtel' Reacling Status Units to uCi/cc Adi. \'NT 1500 1 On 3.3E+OO 0 uCl/cc l.OE+-00 Isotope (nCi/sec) ER-8:iM KR-85 KR.-87 KR-88 XE-13Ill XE-133M XE-133 XE-Hill XE-135 XE-138 I-131 1-lll I-13.l i:-u.t I-lli CS-134 CS-136 CS-137 Total Noble Total fodine Tora! Particulate Adjusted Ground Speed (mph) Ground D.irectlon (Deg.from) Ground Stability Class GrolD!d Iempemtnre (Deg.F) Adjusted Elernted Spero (mph) :Elm1ted Direclion (Deg.from) Eln-ated Stability Class Elm1ted (Deg.F) R..'lin (inches/IS min) Fraction 11t Gronnd Final Plume Height (ft) Release Point 1 GR.l-..,'DREL Release Fraction Rate of Total l.0E+07 6.4E-02 2.8E+o5 l.7E-03 l.3E+o7 8.SE-02 2.0"E+o7 I.7E-Ol 4.9E+05 3.IB-03 2.9E+06 l.SE-02 8.4E+07 5.3E-Ol LIE+oo 7.?E-03 l.6E+07 9.8E-02 4.5'E+-06 2.SE-02 8AE+04 5.3E-64 8.8E+64 S.sE-04 l.6E+o5 l.OE-03 8.6E+o.t 5.4E-O.t LlE+05 8..fE-04 7.4Ei-03 UE-05 3.0E+03 l.9E-05 4.'/E+03 2.9E-05 l.6E+08 5.6Ei-05 l.SE+o4 Rel Pt.I GRl\i"D REL Stains 7.0 OP 180 OP D OP 52.0 OD o.o 2 0 2 2 0.0 2 0.00 0 1.00 32.8 Concentration Faow R.1te __ (u_C_il_c_c_) _ Reading Status Units (uCi/sec) 3.3E+OO l.OE+o:i 0 cm l.6E+o8 SLUUS: 0 = Good, l = Qnestlonable, 2 = Bad, 3 =Unsteady Winds, .f =Calm, 5 = FL1t, 6 =Rain Reset, 7=Mannal Onnide of Raw Data, S=llfonual Entry of Future Data DATA SOURCE: P = 1st. S =2nd. 'I= 3nl, i\'l =Manual. D =Default. L =Last EP-CALC-CNP-1601 Page 26 of 38 Revision 2 Attachment 3 RA1.1, RS1.1 and RG1.'i MIDAS Calculations Version: 1.5.16.090915 Gland Seal -Alert Met & Rad Input Snmmarv for Calculation at 02/18/16 15:15 -Fh'st E:s:posw*e Period SITE: AEP COOK lJMT: CA l\IEl'<"U: B REPORT DAIE: 02il8/lo 15:21 :\L\NUAL DATADATE: 02/1811615:15 START DATE OF RUN: 02118116 15:17 START OF RELEASE: 02118/1615:17 Tii\'1E OF TRIP: 02/18/1614:17 START OF EXPOSURE: 02118/16 15:08 EVENT TREE MIX SELECTIONS: Mix ID# 141: STEAM Til"BE RUPTURE, NOR:\IAL COOL.\l.l;"T, <l R/hr on VRA 131011410 or 2310/2410, PARTITIO:NED, Total Total fu!lease Release 1\clonitor Conversion i\"G :i\fonitor ID Pt Filter Reading Status Units to uCi/cc ----__ ___ Acl!. GLD 1800 1 None l.6E+OO 0 uCl/cc l.OE+OO 1.000 Isotope (uCl/sec) H-3 KR..S:.'"AI filt.85 KR-87 KR-88 XE-1311\I XE-1331\I XE-133 XE-135M XE-135 XE-138 1-131 1-132 1-133 I-rn 1-135 SR-89 SR-90 SR-91 Y-91 :i\I0-9ll RU-103 TE-129ll TE-131M lE-132 CS-134 CS-136 CS-137 BA-1-10 L.\-1-10 CE-1.U NP-23!1 Total Noble Total Iodine Total Partirolate EP-CALC-CNP-1601 Release Point 1 GRJ\'DREL Release Fraction Rate of Total l.7E+o6 4.:?L-01 :UE+o4 5.8E-03 7.4E+o5 l.SE-01 l.7E+04 4.IB-03 2.4E+04 5.9E-03 l.3E+o6 3.lE-01 L2E+05 29E-02 5.0E+04 UE-02 LSE+o4 3.6E-03 LIE+05 2.6E-02 5.6E+03 l.4E-03 o.9E+Ol l.7E-05 l.5E+03 3.7E-04 8.7E+02 2.lE-04 L6.E+03 3.SE-04 L7E+03 4.?E-04 4.SE+oO UE-06 4.5.E-01 l.IE-07 3.IE+ol 7.5E-06 LSE-01 4 * .fE-08 2.2E+02 S.3E-05 2..CSE+02 6.3E-05 6.6E+o0 l.CiE-06 5.IL+Ol I.1E-05 5.SE+Ol 1.41:-05 UE+OO 3.lE-07 3.0E+Ol 7.JE-06 LSE+OO 4.5E-07 4.5E+02 l.IE-04 8.SBi-02 2.lE-04 UE+02 ME-05 7.5E+ol l.8E-05 2.4:E+o6 5.SE+03 l.7E+06 Page 27 of 38 Concentration Flow Rate __ C 1_1 c_11_* 'c_c_) _ Reading Status Units (uCitsec) l.6E+OO 5.5E+o3 0 cru -l.lE+06 Revision 2 Attachment 3 -RA1.1, RS1.1 and RG1.1 MIDAS Calculations EMD-32b

• Nuclear Plant Evei1t Technical Data MICHIGAN STATE POllCE lo Actual event rE Drill I ! Nuclea1* Po\\'er Plant: D.C.Cook Plant Contact Info1*mation D f Plant Communicator:

Simpson I Calling from: D Control Room 0 TSC fE EOF D Othe1* I ' ! Call Back Telephone Nmnber: 269-465-5901-1088 Plant Message number ! ! Meteorologteal Data I Wind direction (in degrees): From 180 To 360 Wind Speed (in MPH): 7 ! " Stability Class: D Precipitation: D Yes Im No I :: i Reactor Infonnation ! Reactor Shutdown Unit-1 rE Yes D No Unit-2 D Yes Im No 1 If yes, time of shutdown: 2118/2016 14:17 If yes, time of shutdown: ' ;. Additional Information: D SeeAttached \ Release/Offsite Dose Data Current Release Rates ! ' Release Pathway: !Bl Airborne D Waterborne Noble Gas (Ci/Sec) 2.4E+OO I ' Remaining Duration (hrs): Em1ivalent I-131 (Ci/sec) 2.SE-04 l 1.00 Particulate (Ci/sec) 1.7E+OO ' D Actual D Potential Time of calculation: 2/18/2016 15:17 l I ' o Other Based on: !Bl Monitor (in plant) D Sample (in plant) D Back Calculation ofField Data ' I Projected Dose Rate Projected Dose ! I Distance TEDE Th.)TOid Distance TEDE Thyroid ' <mremlba*) CDE<mremfb1*) <mi-em) CDECmrem) ! Site Boundazy 3.SE+OO 4.7E+o0 Site Boundaiy 1.0E+o1 1.2E+01 ' 2Miles O.OE+oO O.OE+oO 2Miles 1.7E+o0 1.6E+o0 ,, 5 Miles O.OE+OO O.OE+oO 5Miles 5.2E-01 4.2E-01 10 Miles O.OE+OO O.OE+OO 10 !vfiles 1.7E-01 1.3E-01 Miles Miles Measured Otisite Radiation Levels Distance Time Highest i*eading(mr/br) Iocline Cartriclge(NetCP:i\f) Sector Site Boundary O.OE+OO O.OE+OO Miles Miles Miles

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'-" ** *' -.:;r** ... * .;..-... .l". ., EP-CALC-CNP-1601 Page 28 of 38 Revision 2 Attachment 3 RA1.1, RS1.1 and RG1.1 MIDAS Calculations Version: 1.5.16.090915 Gland Seal -SAE l\iet & Rad Input Summary for Cakulation at 02/1811615:15 -Fh"st faposurn Period SITE: AEP COOK IDTI: CA MENU: B REPORT DATE: 02118/16 15:16 MANUAL DATA DATE: 02/lSno 15:15 START OF RELEASE: 02/18/lo 15:13 START DATE OF RUN: 0.2fl8/1615:13 Til\IE OF TRIP: 02118/1614:13 START OF EXPOSURE: 02118116 15:08 EVENT TREE MIX SELECTIONS: ?.:li:I: ID# 141: STEAM GENERATOR TUBE Rl!"PTURE, .NOR\HL COOLk'*ff, <l Rlhr on VRA 131011410 or 231012410, PARTITIONED, Total Total Release Release Monitor Coowrslon NG l\:lonito1* ID Pt Filte1* Reading Status Units to uCifcc ----_ __ Adj. Concentmtion Flow Rate __ (u_c_il_c_c_) _ Reading Statu.s Units (uCi/sec) GLD 1800 I None l.6Ei-Ol 0 uCifcc l.OE-t-00 1.000 l.6E+Ol 5.51:+03 0 C.'Ill -UEi-07 Release Point 1 IsotoEe (uCilsec) GRNDREL Relt:ase Fraction Rate of Total H-3 l.7E+07 ----uE-01 K&-85111 UE+OS 5.8E-03 KR-85 7..IE+-06 l.BE-01 l.7E+05 4.lE-03 filt.88 UEi-05 5.9E-03 XE-13lll UE+07 3.lE-01 XE-133111 LIE+Otl 2.9E-02 XE-133 5.0Ei-05 l.lE--02 XE-135111 l.SEi-05 3.6E-03 XE-135 LIE+o6 2.6E-Ol XE-138 5.6E+O.I l..IB-03 1-131 6.9E+ol l.7E-05 1-132 L5E+O.I 3.7E-O.J 1-133 8.7E+03 l.IE-04 1-13.J l.6E+o.J 3.BE-04 1-135 L"IE-!-0.J 4.lE-04 SR-89 4.SEi-01 l.2E-06 SR-90 4-"E+OO l.1.E-07 SR-91 3.IB+o? 75E-06 Y-91 l.SE+OO 4.4E-OS M0-99 l.2E-T03 5.3E-05 RU-103 2.6E+03 6.3E-05 T.E-U9M 6.6E+ol l.6E-06 TE-13IM 5.IE+02 LZE-05 TE-132 5.sE-l-02 UE--05 CS-134 LIE+ol 3.lE-07 CS-136 3.0E+O! 7.3E-06 CS-137 LSE+ol 4.5E-07 BA-UO .f..5E+o3 l.IE-0.J LA-UO 2.lE-0.J CE-1-14 l...t:Ei-03 3.4E-05 NP-239 7.5E+o2 I.SE-OS Total Noble !...t:E-!-07 Total Iodine 5.SE+o.t Total Particulate LIB-!-07 EP-CALC-CNP-1601 Page 29 of 38 Revision 2 Attachment 3 -RA1.1, RS1.1 and RG1.1 MIDAS Calculations EMD,32b MICHIGANSTATEPoucE Nuclear Plant Event Technical Data* j D Actual event !Bl Drill Plant Contact Infonnation [] Nucleai* Power Plant: D.C. Cook Plant Conumuiicator: Simpson Calling from: D Control Room D TSC lBI EOF D Othe1* Call Back Telephone Number: 269-465-5901-1088 Plant Message number l\fete01*0Jogical Data Wind direction (in degi*ees): From 180 To 360 Wmd Speed (in MPH): 7 Stability Class: D Reactor Shutdo\vn Additional Information: D See Attached Release Pathway: Unit-I !BJ Yes If yes, time of shutdown: Precipitation: 0 Yes !Bl No Reacto1* Information Unit-2 D Yes IE! No O No 2/18/2016 14:13 If yes, time of shutdown: Release/Offsite Dose Data Curl'ent Release Rates (Bl Airborne D Waterbome Noble Gas (Ci/Sec) 2.4E+Ol Remaining Duration (hrs): 1.00 Eauivalent 1-131 (Ci/sec) 2.SE-03 Pruiiculate (Ci/sec) 1.7E+01 D Actual D Potential Time of calculation: 2/18/2016 15:13 Based on: IB1 Monitor (in plant) D Sample (in plant) O Back Calculation of Field Data D Other Projected Dose Rate Projected Dose Distance TEDE Thyroid Distance TEDE TI1yroid fm1*emllul CDElm1-em/brl lmreml CDECmreml Site Boundary 6.3E+Ol 7.9E+o1 Site Boundary 1.0E+02 1.2E+02 2 Miles O.OE+OO O.OE+oO 2 1.7E+01 1.6E+01 5 Miles O.OE+OO O.OE+OO 5 Miles 5.2E+OO 4.2E+OO 10 Miles O.OE+OO O.OE+OO 10 l\files 1.7E+o0 1.3E+OO :___Miles __.Miles Measured Off.<iite Radiation Levels Di<>fance Time Highest reading(llll'ibt') Iodine Cai1ridge(NetCPM) Sector Site Boundmy O.OE+oO O.OE+oO Miles Miles Miles EP-CALC-CNP-1601 Page 30 of 38 Revision 2 Attachment 3 RA1.1, RS1.1 and RG1.1 MIDAS Calculations Version: 1.5.16.090915 Gland Seal -GE Met & Rael Input Summarv for Cnkulation at 02118116 15:00 -First Exposui*e Period SITE: AEP COOK fillo"IT: CA ?.IENU: B REPORT DATE: 02/18/1615:06 .MANU * .U. DATADATE: 02/1811615:00 START DATE OF RUN: 02118/1615:01 START OF RELEASE: 02/18/1615:01 Tll\IE OF TRIP: 02118/1614:01 START OF :EXPOSURE: 02118/16 14:53 EVENT TREE i\IIX SELECTIONS:

Mb: ID# 141: STEA:"\I GENERATOR TUBE Rlt"PIURE, NOK\L.\L

<l R/hr on VRA 131011410 ot* 2310/2410, PARTITIONED, Total Total Release Release :M:onito1* Conve1*sion NG :\Ionit01* ID Pt Filter Reading Status Units to uCi/cc Adi. GLD 1800 I None l.6Et-02 0 uCi/cc LOE+OO 1.000 Isotope{uCifsec) H-3 KR-35lI KR-85 Klt-87 KR.-88 XE-13ll1 XE-133M XE-133 XE-135M XE-135 SE-138 I-131 I-ill l-133 l-1.U 1-135 SR-89 SR-91 Y-91 M0-99 RU-103 'IE-l29M TE-13lll TE-132 CS-13-1 CS-136 CS-ll7 BA-UO L.\-UO CE-1-1-1 NP-239 Total Noble Total Iodine Total Particnlate EP-CALC-CNP-1601 Release Point 1 GRNDREL Release Fraction Rate of Total l.7E+08 4.?E-01 2.4E+06 5.SE-03 7.IBl-07 l.SE-01 l.'7.E+ll6 4.IE-03 2A.E+Oo 5.9E-03 UE+08 3.lE--01 l.2E+o7 2.9E-02 S.OEt-06 l.2E--02 L5E+06 3.6E--03 LIE+o7 2.6E--02 5.6E+05 l.4E-03 6..llE+03 l.7E--05 L5E+05 3.7E-O-I 8.7E+04 2.IE-04 1.6.E+OS 3.SE--04 l."IE+05 4.?E-0-1 4.S:Et-02 l.2E--06 -1.SE+Ol l.IE--07 3.lE+03 7.5E-06 l.SJ:+ol -l.-IE-08 UE+o4 5.3.E--05 2.6£+-64 6.3E--05 6.6£+02 l.6E-06 5.IE+o3 L2E-05 S.8E+o3 l.4E-05 l.3E+02 3.IE--07 3.0E+o3 7.3.E-06 l.8E+o2 4.5E-07 -l.SE+o4 I.IE-04 8.:.'"E+IU 2.IE--04 1AE+o4 3.-IE-05 7.SE+03 I.SE-OS 2.41:+08 5.8E+05 l.7E+08 Page 31of38 Concentration Flow Rate __ (u_c_11_* c_c_) _ Reading Status Units (uCi/sec) l.6E+02 5.5E+03 0 C.'fM 4.IEt-08 Revision 2 Attachment 3 -RA1.1, RS1.1 and RG1.1 MIDAS Calculations . EMD 7 32b. MicmGANsTATEPoucE Nuclear Pla11t Event Techi1ical Data I D Actual event !Bl Drill Plant Contact Information [] Nuclear Power Plant: D.C. Cook Plant Communicator: Simpson Calling from: D Control Room O TSC D Other IB) EOF Call Back Telephone Numbcr: 269-465-5901-1088 Plant Message number Meteornlogical Data Wind direction (in degrees): From 180 To 360 Wmd Speed (in MPH): 7 Stability Class: D P1-ecipitatioi1: D Yes No Reactor Info1'Jllation Reactor Slmtdovm Unit-1 1B1 Ye.s 0 No 2/18/201614:01 Unit-2 D Yes IBI No Additional Information: 0 See Att:lclled If yes, time of sl1utdown: If yes. time of shutdown: Release/0.ffsite Dose Data Cm*rent Rele.ase Rates Release Pathway: 1BJ Airborne D Waterborne Noble Gas (Ci/Sec) 2.4E+o2 Eauivalent I-131 (Ci/sec) 2.8E-02 Particulate {Ci/sec) 1.7E+02 Remaining Duration (lu:s): 1.00 -D Actual D Potential Time of calculation: 2/1Sn016 fa:Ol Based on: 181 Monitor (in plant) D Sample (in plant) O Back Calculation of Field Data D Other Projected Dose Rate Pl'ojected Dose Distance IEDE Thy1:oid lmrem/Jn*l CDE<mrem/hrl Distance TIDE Thyroid lmreml CDEOlll"em\ Site Boundary 4.4E+o2 5.5E+o2 Site Boundaty 1.0E+o3 1.2E+o3 2wllies O.OE+oO O.OE+OO 2Miles 1.7E+o2 1.6E+02 5Miles O.OE+oO O.OE+OO 5 Miles 5.2E+o1 4.2E+Ol 10 Miles O.OE+OO O.OE+OO IO Miles 1.7E+Ol 1.3E+o1 __ _Iv.Iii.es Miles Ml1asured Offsite Racliation Levels Distance Time Highest reading(ml'/ln:) Iodine Ca1*tiidge(NetCP::\I) Sector Site Boundary O.OE+oO O.OE+OO l\1iles Miles Miles EP-CALC-CNP-1601 Page 32 of 38 Revision 2 -RA1.1, RS1.1 and RG1.1 MIDAS Calculations Ve!Sion: 1.5.16.090915 SIT_E: .-\EP COOK Condenser Air Ejector -Alert Met & Rad Input Summary tor Cakulattou at 02118/16 15:00 -Fh'st Exposure Pedod UNIT: CA :MENU: B REPORT DATE: 02118/1615:00 l\IAiWAL DATA DATE: 02113/16 15:00 START DATE OF RUN: 02/18/16 14:57 START OF RELEASE: 02118116 14::57 Ili\IE OF TRIP: 02/18/1613:57 START OF EXPOSURE: 02118/1614:53 EVENT TREE MIX SELECTIONS: i\fu: ID# 141: STEAM G:El';LR.UOR TUBE RUPTURE, COOLANT, <I R/h1* on VRA1310/1410 or 2310/2410, PARTITIONED, Total Total Release Release i.\fonitor Conyersion NG :.\Iouitor ID Pt Filter Reading Status Units to uCilcc ----__ ___ Adi. Concentration Flow Rate __ (u_c_u_c_c_) _ Reading Status Units {uCi/sec) SJ.-\El900 I None l.5E+o2 0 uCUcc l.OE+oo l.000 l.SE+Ol 6.0E+Ol 0 CDI tiE+06 Release Point 1 Isoto2e {uCi/sec} GRNDREL Release Fmcliou Rate of Total H-3 L7E+o6 4.lE--01 KR-35.M 2..ffi+-0-i 5.SE--03 KR-85 7..tE+oS l.SE--01 KR--87 LIBl-0-t 4.lE--03 KR--88 2.4£+04 5.9E--03 XE-131JII l.3Et-06 3.IE-01 LIBt-05 2.9E-02 XE--133 S.OE+0-1 l.?E--02 XE-135JII L5E+04 3.6£-03 XE-135 LlE+oS 2.6E--02 XE-138 5.6E+o3 l.4E--03 I-131 6.9E+ol l.7E--05 I-132 l.5E+o3 3.7E--O.t I-133 8.7E+02 2.lE--04 l-13-1 L6E+o3 3.SE-04 I-135 L7.E+03 4.?E--04 SR-89 .f.SIE+OO l.?E--06 SR.--90 4.SE--01 l.lE--07 SR--91 3.IE+Ol 7.5E--06 Y--91 l.SE-01 UE--08 lI0--99 ?.2E+o2 5.3E-05 RU-103 2.6E+02 6.3E-05 TE-1291\1 6.6.E+OO l.6E--06 IE-13llI 5.IE+ol l.?E--05 TE--132 5..s:E+ol l.4E--05 CS-13-1 l.3E+OO 3.lE--07 CS-136 3.0E+Ol 7.3E-06 CS-137 Ll!E+oO 4.5E--07 BA-UO 4..5E+02 1.IE--04 L.-\-140 8.5E+o2 2.lE--04 CE--1-U Lm+o2 3.4E--05 NP-239 7.51:+01 l.SE--05 Total Noble 2.41:+06 Total Iodine 5.81:+03 Total PartirnJate I.7E+o6 \ -' .. .. .. -.. --.. -.. ... -.. ---, .. -:-------*-*--,- .... .. .. .. __ .. EP-CALC-CNP-1601 Page 33 of 38 Revision 2 Attachment 3 c RA1.1, RS1.1 and RG1.1 MIDAS Calculations EMD-37b. MicmGANsTATEPoucE Nuclear Plant EventTechnical Data I D Actual event !Bl Drill Plant Contact Infonnation D Nucleai* Powei* Plant: D.C. Cook Plant Communicator: Simpson Calling from: O Control Room D TSC 0 Other EOF Call Back Telephone Ntnnb.:r: 269-465-5901-1088 Plant Message number Meteorological Data Wind dil.'ection (in degrees): From 180 To 360 Wmd Speed (in MPH): 7 Stability Class: D Reactor Shutdown Additional Infonnation: 0 SeeAttached Release Pathway: Unit-1 ml Yes If yes, time of shutdown: Precipitation: 0 Yes !Bl No Reactor Information Unit-2 D Yes Im No 0 No 2/18/201613:57 If yes, time of shutdown: Release/Offsite Dose Data Cnr1*ent Release Rates ml Airborne D Waterborne Noble Gas (Ci/Sec) 2.4E+OO Remaiuing DtU"ation (Iu-s): 1.00 Eauivalent I-131 (Ci/sec) 2.SE-04 Particulate (Ci/sec) 1.7E+OO D Actual D Potential Time of calculation: 2/18/2016 14:57 Based on: ml Monitor (in plant) D Sample (in plant) D Back Calculation of Field Data 0 Other Pl'ojected Dose Rate P1*ojected Dose Distance TEDE Th}TOid Distance TEDE Thyroid illll*emfhrl CDE<mremibr) lmrem) CDElm1-em' Site Boundary 7.0E+OO 8.7E+tl0 Site Boundary 1.0E+ol 1.2E+01 2 Miles O.OE+OO O.OE+tlO 2Miles 1.7E+o0 1.6E+OO 5 Miles O.OE+OO O.OE+oO 5Miles 5.2E-01 4.2E-01 10 Miles O.OE+OO O.OE+OO 10 Miles 1.7E-01 1.3E-01 Miles !viiles Measm*ed OtTsife Racliation Levels Distance Time Highest reading(mr/hr) Iodine Cal'tlidge(NetCPl\1) Secto1* Site Boundary O.OE+oO O.OE+OO Miles Miles Miles EP-CALC-CNP-1601 Page 34 of 38 Revision 2 Attachment 3 R RA1.1, RS1.1 and RG1.1 MIDAS Calculations Version: 1.5.16.090915 Condenser Air Ejector -SAE Met & Rad Input Summa1*y for Calculation at 02118116 14:45 -First Exposure Pedod SITE: .IBP COOK UNIT: C..o\. l\IENU: B REPORTDATE: 02118/1614:55 MAl'lUALIIATADATE: 02/18/1614:45 START DATE OF RUN: 0211811614:43 START OF RELEASE: 02/18/1614:43 TIME OF TRIP: 02118116 13:43 SIART OF EXPOSURE: 0.211811614:38 EVENT TREE MIX SELECTIONS: i\lh: ID# 141: STEAM GE!NERATOR TUBE RUPTURE, NORMAL COOLANT, <l R/hr on VRA 1310/1410 01* 2310/2410, PARTITIONED, Total Total Release Release l\Ionitor Conversion NG Monitor ID Pt Fllter Reading Statns Units to uCi/cc ---------Adi. SJAE1900 1 None l.5E+03 0 uCl/cc l.OE+OO LOOO Isotope (uCi/sec) H-3 KR-891 KR.-85 KR-87 KR.-88 XE-1311\I XE-1331\I XE-133 XE-1351\l XE-135 XE-138 I-131 I-132 I-133 I-134 I-135 SR-8!> SR-90 SRc9l Y-91 l\£0-99 RU-103 T.E-12!>l\I TE-1311\1 TE-132 CS-134 CS-136 CS-137 BA-140 LA-140 CE-144 NP-239 Total Noble Total Iodine Total Pal1irn1ate EP-CALC-CNP-1601 Release Point 1 GRNDREL Release Fraction Rate of Total l.7E+07 UE-01 2.4E+05 5.SE-03 7.4E+06 l.SE-01 1.7E+OS UE-03 2.4E+05 S.9E-03 l.3E+o7 3.IE-01 l.2E+06 Z.9E-02 5.0E+o5 l.lE-02 l.SE+o5 3.6E-03 l.1E+06 2.CiE-02 5.6£+04 l.4E-03 6.9E+02 l.7E-OS u"'E+04 3.7£-04 8.7E+o3 2.IE-04 l.6E+04 3.SE-04 L7E+04 UE-04 4.9E+ol l.2E-06 4.5Ef-OO l.IE-07 3.U:+o2 7.5E-06 L8E+OO .UE-08 2.2E+03 S.3E-05 2.6£+03 6.3E-05 6.6E+Ol l.CiE-06 5.IE+02 l.2E-05 5.8.£+02 l.4E-05 l.3E+Ol 3.IE-07 3.0E+02 7.3E-06 1.SE+Ol 4.5£-07 4.5E+03 l.lE-04 8.5E+o3 2.lE-04 1.4E+o3 ME-05 7.SE+Ol l.SE-05 2.4E+o7 5.SE+O.t 1.7E+07 Page 35 of 38 Concentl'ation Flow Rate __ Cn_c_il_c_c_) _ Reading Status Units (uCilsec) l.SE+03 6.0E+Ol 0 CBI 4.IE+o7 Revision 2 Attachment 3 -RA1.1, RS1.1 and RG1.1 MIDAS Calculations EMD-32b Mict.rri1AN'stAT.EPouc'E

• Nuclear Plant Event Technical Data I D Actual event !Bl Drill Plant Contact Information D Nuclear Power Plant: D.C. Cook Plant Communicator:

Simpson Calling from: D Contl'ol Room D TSC 0 Other IB) EOF Call Back Telephone Number: 269-465-5901-1088 Plant Message number Meteorological Data Wind direction (in degrees): From 180 To 360 Wmd Speed (in !Y!PH): 7 Stability Class: D Precipitation: 0 Yes ml No Reactor Info11naiion Reactor Shutdown Unit-I !Bl Yes 0 No 2/18/2016 13:43 Unit-2 D Yes IRI No Additional Inform., lion: 0 See Attached If yes, time of shutdown: If yes, time of shutdown: Release/Offsite Dose Data Cm*1-ent Release Rates Release Pathway: ml Airborne 0 Waterborne Noble Ga<; (Ci/Sec) 2.4E+Ol Remaining Duration (hrs): 1.00 Eou.ivalentl-131 (Ci/sec) 2.SE--03 Particulate (Ci/sec) 1.7E+Ol D Actual D Potential Time of calculation: 2/18/2016 14:43 Based on: ml Monitor (in plant) D Sample (in plant) D Back Calculation of Field Data D Other Projected Dose Rnte P1*ojected Dose Distance TEDE Th} TO id (llll*em/lu:l CDE<mremlhrl Distance TEDE Thyroid lmreml CDEfJJll"eml Site Botuidary 6.3E+01 7.9E+o1 Site BolUldary 1.0E+o2 1.2E+o2 2 Miles O.OE+OO O.OE+OO 2Miles 1.7E+ol 1.6E+01 5Miles O.OE+OO O.OE+OO 51\.fil.es 5.2E+o0 4.2E+OO IO Miles O.OE+OO O.OE+oO 10 Miles 1.7E+OO 1.3E+o0 __ Miles _J,1iles Measw*ed Offsite Radiation Levels Distanc.e Time Highest reading(m1*/lu') Iodine Carhidge(NetCPM) Sectol' Site Boundary O.OE+-00 O.OE+oO lvliles Miles Miles EP-CALC-CNP-1601 Page 36 of 38 Revision 2 Attachment 3 RA1.1, RS1.1 and RG1.1 MIDAS Calculations Version: 1.5.16.090915 SITE: AEP COOK Condenser Air Ejector -GE Met & Rael Input Summarv for Cakulation at 02/lS/16 14:00 -Fb*st E-xposw*e Perlod illliTI: CA MENU: B REPORT D..\'.rE: . 02/lS/16 14:20 l\LLWAL DATA DATE: 0211811614:00 START DATE OF RUN: 62118116 14:02 START OF RELEASE: 02118/1614:02 Til\IE OF TRIP: 02118116 13:02 START OF EXPOSURE: 0211811613:53 EVE:NTTREE l\IIX SELEC.'TIONS:

a\10: ID# 141: STEAM GEi'U:R..\TOR TUBE RUPTURE, NOR.\,L.\L COOLAi'li-Y, :E+o?

l.2E-06 SR-90 .f.5E+ol l.IE-07 SR-91 3.n:+o3 75E-06 Y-91 1.S:E+ol .f.4E-il8 M0-99 l.2E+04 5.3E-05 RU-103 .?.6.E+04 6.3E-05 IE-129ll 6.6£+02 l.6E-06 TE-13L.'\f 5.IE+03 UE-05 TE-132 5.8:E+03 UE-05 CS-134 LlE+02 3.IE-07 3.0:E+03 7.3E-06 CS-137 I.8:E+o? 4.5E-07 BA-140 .f.5E+04 UE-04 LA-140 8.:."':E+04 2.IE-0.t CE-1.U IAE+o-1 UE-05 NP-239 7.5£+03 l.SE-05 Total Noble 2.4E+os Total Iodine S.SE+OS Total Particulate l.'1.E+OS ,. L-.-....* -,.-.-,,-.. -.... -.,-.. -.. -.... -,.-.. -.. ,.--.. -.. --, .. -_..-.,.-... -".-.... -._,---.... -.. -... ,-.-*.*. -... -.... -.*. -. ._-._,.-.* -,-.... -.* -... -... *. -.. -... -.-.-_,.-... -M._-,-* ..,. __ ,....,,,,.,.,..,...,,._,.,.,".-*,*--.-.-. . .--, .. ._..,.,._ . .,..., .. -.. -,.-......,...- .. -.,,,,-._ . ..,.,,.,.,,-, .. . ...IJ EP-CALC-CNP-1601 Page 37 of 38 Revision 2 -RA1.1, RS1.1 and RG1.1 MIDAS Calculations EMD-32b MicmG&"'{sTATEPoUCE Nuclear Plant Event Technical Data J D Actual event !Bl Drill Plant Contact Information [] Nuclear Power Plant: D.C. Cook Plant Communicator: Simpson Calling from: D Control Room D TSC D Other !Bl EOF Call Back Telephone Number: 269-465-5901-1088 Plant Message number l\'Ieteorologicat Data Wind d1rection (in degrees): From 180 To 360 Wind Speed (in MPH): 7 Stability Class: D Precipitation: D Yes !Bl No Reactoa* Jnformatiou Reactor Shutdown Unit-1 D No Unit-2 D Yes !Bl No If yes, time of shutdown: 2/18/201613:02 If yes, time ofshutdo'l'm: Additional lnfonnation: 0 SeeAttached Release Pathway: IEI Airborne Remaining Dll1'3tion (hrs): 1.00 Release/Off.site Dose Data D Waterbome Cunent Release Rates Noble Gas fCi/Sec) 2.4E+02 Enniyalentl-131 (Ci/sec) 2.8E-02 Particulate (Ci/sec) 1.7E+o2 0 Actual 0 Potential Time of calculation: 2/18/2016 14:02 Based on: IE! Monitor (in plant) D Sample (in plant) D Back Calculation of Field Data D Other Projected Dose Rate Projected Dose Distance TEDE Thyrnid (mrem/hrl CDE<mremlba*) Distance TEDE Thyroid lmrem\ CDE(mreml Site Bomidary 3.8E+o2 4.7E+o2 Site Bolllldary 1.0E+03 1.2E+03 2 l\.1iles O.OE+oO O.OE+oO 2Miles 1.7E+o2 1.6E+02 5Miles O.OE+oO O.OE+oO 5 Miles 5.2E+o1 4.2E+o1 1o:Miles O.OE+oO O.OE+OO 10 :Miles 1.7E+o1 1.3E+01 Miles Miles l\lleasm*ed Offsite Radiation Levels Distance Time Highest reading(nll'lhr) Iodine Calilidge(NetCP:J.\:l) Sector Site Bounda1y O.OE+OO O.OE+OO Miles Miles Miles EP-CALC-CNP-1601 Page 38 of 38 Revision 2}}