ML17095A118

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Monticello Nuclear Generating Plant - License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 4 of 5
ML17095A118
Person / Time
Site: Monticello  Xcel Energy icon.png
Issue date: 03/31/2017
From:
Northern States Power Company, Minnesota, Xcel Energy
To:
Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML17095A107 List:
References
L-MT-17-012 CA-04-199-001
Download: ML17095A118 (41)
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CA-04-199, "Methodology Used to Derive Radiation Monitor Readings for NEI 99-01, Rev 6," full calculation (41 total pages) Energy Compliance Consutrnnts Methodology Used to Derive Radiation Monitor Readings for NEI 99-01 Rev 6 Revision 1 to MNGP's CA-04-199-000 Prepared for: Xcel Energy Monticello Nuclear Generating Plant Project Number: 63259 Name and Date Preparer: March 9, 2017 Reviewer: March 9, 2017 02/28/2017 Calculation 04-199.001 Page 1of40 Table of Contents 1.0 DESCRIPTION OF REVISION ......................................................................................... 3 2.0 BACKGROUND .................................................................................................................. 4 2.1 2.2 3.0 3.1 ODCM SET POINTS .................................................................................................................. 4 Scope ........................................................................................................................................... 4 Methodology ........................................................................................................................ 5 Gaseous Effluent Monitors .......................................................................................................... 5 3.1.1 Gaseous NUE Set Points ..................................................................................................... 5 3.1.2 Gaseous Alert, SAE and GE Set Points ............................................................................... 5 3 .2 Liquid Effluent Monitors ............................................................................................................ 5 3 .2.1 Liquid NUE Set Points ........................................................................................................ 5 3 .2.2 Liquid Alert Set Points ........................................................................................................ 6 4.0 ACCEPTANCE CRITERIA .............................................................................................. 6 5.0 INPUTS ................................................................................................................................ 7 5.1 Gaseous Effluent Monitors .......................................................................................................... 7 5.1.1 NUE .................................................................................................................................... 7 5 .1.2 Alert, SAE and GE .............................................................................................................. 7 5.2 Liquid Effluent Monitors ............................................................................................................ 8 5.2.2 Alert .................................................................................................................................... 8 6.0 ASSUMPTIONS .................................................................................................................. 8 6.1 Gaseous Effluent Monitors .......................................................................................................... 8 6.1.1 Alert, SAE and GE .............................................................................................................. 8 6.2 Liquid Effluent Monitors ........................ : .................................................................................... 8 6.2.1 Alert .................................................................................................................................... 8 7 .0 ANALYSIS ......................................................................................................................... 9 7.1 Gaseous Effluent Monitors .......................................................................................................... 9 7.1.1 NUE .................................................................................................................................... 9 7 .1.2 Alert, SAE & GE ................................................................................................................. 9 7 .2 Liquid Effluent Monitors ........................................................................................................ 10 7 .2.1 Liquid NUE Set Points .................................................................................................... 10 7 .2.2 Liquid Alert Set Points ...................................................................................................... 10 7.2.3 Summary of Liquid Set Points .......................................................................................... 10

8.0 CONCLUSION

S ................................................................................................................ 11 02/28/2017 Calculation 04-199.001 Page 2 of 40

9.0 REFERENCES

................................................................................................................... 12 10.0 PLANT IMPACT ............................................................................................................... 12 11.0 APPENDICIES .................................................................................................................. 12 12.0 ATTACHMENTS .............................................................................................................. 12 Appendix A Source Term ......................................................................................................................... 14 Appendix B Liquid Dose Calculations ...................................................................................................... 18 Appendix C Impact of SBGT Off ............................................................................................................. 26 Attachment 1 Excerpt from EC 24037 ...................................................................................................... 28 Attachment 2 Excerpt from EC 26667 ...................................................................................................... 30 Attachment 3 RASCAL Run Reactor Building Vent ................................................................................ 33 Attachment 4 RASCAL Run for Plant Stack SBGT Off ........................................................................... 35 Attachment 5 RASCAL Run for Plant Stack SBGT On ........................................................................... 37 Attachment 6 Relationship of Reactor Building Exhaust Plenum Monitor Trip Point to Effluent Monitor Release Rate for FHA ......................................................................................................... 39 02/28/2017 Calculation 04-199.001 Page 3 of 40 1.0 DESCRIPTION OF REVISION Major revision 001 is being performed to update the radiation monitor values for notifications during emergency response events. This revision addresses: 1. the change in NEI 99.01 Revision 6 "Development of Emergency Action Levels for Passive Reactors." [ref3]; 2. a change from an ODCM based source term to an accident source term as specified in USAR § 14.7.2.4.2 [ref 8] for a Loss of Coolant Accident (LOCA) and§ 14.7.6.3 .2 [ref 9] for a Fuel Handling Accident (FHA); 3. a change in the meteorological data from 2010 data to that provided in USAR Tables 2.3-8 and -16[ref7]. 4. the impact of isolating the reactor building ventilation due to a high reactor building plenum monitor. The change in NEI 99.01 Rev 6 [ref3] impacts the methodology used to determine the Alert Emergency Action Level (EAL) set point. Prior to revision 6 ofNEI 99.01, the Alert EAL was a multiple of the ODCM set point for the effluent pathway. The current revision links the Alert EAL set point to a dose to a member of the public if exposed for one hour. The methodology used to establish the Notice of an Unusual Event (NUE) set point was not changed. The change from an ODCM based source term to an accident source term is limited to gaseous effluent monitors (i.e. the reactor building vent effluent monitor and plant stack effluent monitor) at the Alert, Site Area Emergency (SAE) and General Emergency (GE) EALs. As with minor revision OA, the computer program RASCAL was used to determine dose based set points for gaseous effluent monitors. The inputs into the RASCAL software were impacted by the change in the source term. This changed did not impact the inputs into the determination of the NUE set points for the gaseous effluent monitors, nor did it impact any liquid effluent monitor set points. The change in the meteorological data is limited to gaseous effluent monitors (i.e. the reactor building vent effluent monitor and plant stack effluent monitor) at the Alert, Site Area Emergency (SAE) and General Emergency (GE) EALs. The inputs into the RASCAL software were impacted by the change in the meteorological data. This changed did not impact the inputs into the determination of the NUE set points for the gaseous effluent monitors, nor did it impact any liquid effluent monitor set points. MNGP is equipped with a reactor building plenum monitor which is set to isolate and re-route the reactor building ventilation when a specified radiation level is reached. This action automatically takes place when the plenum monitor reaches or exceeds 26 mrem/hr. Because this reading corresponds to a release rate below the set point for an SAE, there is no need to establish an EAL set point for the reactor building vent effluent monitor corresponding to either an SAE or GE. Table 1 lists the current EAL set points, from Section 7 .2 of A.2-101 "Classification of Emergencies" [ref 1], and the proposed set points based on this calculation.

02/28/2017 Calculation 04-199.001 Page 4 of 40 Table 1 Comparison of Current to Proposed EAL Set Points NOEU Alert SAE GE Monitor Current Proposed Current Proposed Current Proposed Current Proposed Reactor Building 2.16 E+04 3 E+04 2.16E+06 6 E+05 1.5E+07 N/A 1.5E+08 N/A Vent (uCi/sec) Plant Stack w/ 7.3 E +05 7 E +05 1.46E+07 8 E+05 2.1E+08 8 E+06 2.1E+09 8 E+07 SBGT (uCi/sec) Discharge Canal 930 900 93,000 2000 N/A N/A N/A N/A (cps) Service Water 314 300 31,400 700 N/A N/A N/A N/A (cps) TBNDS 37,752 4 E+04 900,000 . 9 E+04 N/A N/A N/A N/A (cpm) 2.0 BACKGROUND I The NEI 99-01 provides guidance to nuclear power plant operators for the development of a site-specific emergency classification scheme. The methodology described in NEI 99-01 is consistent with Federal regulations, and related US Nuclear Regulatory Commission (NRC) requirements and guidance. The Emergency Classification Levels refer to a set of four names established by the US NRC for grouping off-normal events or conditions according to potential or actual effects or consequences. The emergency classification levels, in ascending order of severity, are:

  • Notification of Unusual Event (NUE)
  • Alert
  • Site Area Emergency (SAE)
  • General Emergency (GE) Corresponding to each Emergency Action Classification are a series of Emergency Action Levels (EALs). These are site specific, pre-determined, observable threshold for an Initiating Condition that, when met or exceeded, places the plant in an emergency classification level. 2.1 ODCM SET POINTS MNGP's Offsite Dose Calculation Manual provides a methodology to calculate the dose to a member of the public as a result of normal gaseous and/or liquid releases. It also provides a method to establish effluent monitor alarm settings to assure routine effluent releases do not exceed federal guidelines or limits. To that end, EC24037 determined gaseous effluent monitor set points and EC6667 determined liquid alarm set points corresponding to 100% and 80 % of the ODCM limit. As NUE set points are directly related to the ODCM limit, pertinent excerpts from EC24037 and EC26667 are provided in Attachments 1 and 2, and are used as inputs when determining NUE set points. 2.2 Scope Regarding radiological effluents, NEI 99-01 defines initiating conditions for the EALs in general terms. This calculation translates the general terms into specific set point values corresponding to the initiating condition.

02/28/2017 Calculation 04-199.001 Page 5 of 40 Per NEI 99-01, the initiating condition for:

  • an Alert is the release of gaseous or liquid radioactivity resulting in an offsite dose greater than 10 mrem TEDE or 50 mrem thyroid CDE;
  • a Site Area Emergency is the release of gaseous radioactivity resulting in an offsite dose greater than 100 mrem TEDE or 500 mrem Thyroid CDE; and
  • for a GE is the release of gaseous radioactivity resulting in an offsite dose greater than 1,000 mrem TEDE or 5,000 mrem thyroid CDE. The scope of this document is limited to the EALs associated with gaseous effluent monitors on the Reactor Building Vent, and Plant Stack and the liquid effluent monitors in the Discharge Canal, and Service Water System. The Turbine Building Normal Waste Sump empties into the intake structure and does not release material to the Mississippi River. However, it is categorized as an effluent monitor and, therefore, included in the scope of this calculation. This calculation does not address Area Radiation Monitors such as those found in the Drywell or the I SF SI 3.0 Methodology 3.1 Gaseous Effluent Monitors. 3.1.1 Gaseous NUE Set Points The ODCM limits for the gaseous effluents monitors are documented as HHSP in EC2403 7 (Attachment 1). A simple multiplication of these values by 2 results in the NUE EAL set point. 3.1.2 Gaseous Alert, SAE and GE Set Points Per NEI 99-01 Rev 6 [ref 3], effluent monitor set points for an ALERT, SAE and GE are to be based on dose to a person exposed for one hour. To determine these set points, the Radiological Assessment System for Consequence Analysis (RASCAL), an NRC dose projection model, was utilized. A defined set of parameters was manually entered into RASCAL. The resultant dose was then used to determine the set points by using a simple ratio: RR1 = RR2 Dose1 Dose2 Equation 1 3.2 Liquid Effluent Monitors 3.2.1 Liquid NUE Set Points The ODCM related count rate limits for the liquid effluent monitors are documented in EC26667 (Attachment 2). These values contain a safety factor of 0.8. Determining the NUE set point of two times the ODCM limit, without a safety factor, value can be done by using Equation 2. NOUEd =CR; X2 0.8 Equation 2 02/28/2017 Calculation 04-199.001 Page 6of40 Where: NUEP = NUE EAL set point for detector ( d) in cps or cpm. CRi = ODCM count rate limit of detector as determined in EC26667 (cps or cpm). 3.2.2 Liquid Alert Set Points The liquid effluent monitor set points were determined using the equations found in Section 4.3.2 of the ODCM [ref 4] in conjunction with the source term provided in Appendix A. Equation 3 Where: Dj =Dose to whole body or thyroid (mrem). Aj = The site related ingestion dose commitment factor to the total body or thyroid G) for each isotope, (mrem/hr per µCi/ml). t =Length of release (hr). Ci = Concentration of isotope (i) (µCi/ml). F = The near field average dilution factor. This value was assumed to be 1 for all streams (i.e. no dilution other than the Mississippi River). The resultant dose was then used to determine the concentration of the effluent at the detector which corresponds to an Alert EAL by using a simple ratio: C1 =--Dose Alert Equation 4 Finally, the set point in counts per second, was determined using the following equation: Where: SP CAJert FHTD DE Equation 5 =Set point (cps or cpm). =Concentration of effluent at detector corresponding to an Alert EAL (µCi/ml). =Fraction of total activity due to Hard to Detect Nuclides. =Detector efficiency (µCi/ml per cps or µCi/ml per cpm). 4.0 ACCEPTANCE CRITERIA The resulting set points must be within the readable scale of the detector. If the calculated set point is below the readable scale of the detector, the lowest discernable value on the instrument's scale shall be chosen as the EAL set point. Conversely, if the calculated set point is above the readable scale of the detector, the highest discernable value on the instrument's scale shall be chosen as the EAL set point 02/28/2017 Calculation 04-199.001 Page 7 of 40 5.0 INPUTS 5.1 Gaseous Effluent Monitors 5.1.1 NUE As the set point for an NUB, is merely twice the value associated with the ODCM limit, the only input is the ODCM limit determined by EC24037 (Attachment 1). 5.1.2 Alert, SAE and GE 5.1.2.1 Reactor Building Vent Effluent Monitor A fuel handling accident, as described in Section 14.7.6 of the USAR [ref 9], was used as the basis for establishing the set point for the reactor building vent effluent monitor. The following parameters served as inputs into the RASCAL program:
  • The isotopic release rate as derived in Appendix A.
  • A release height of 10 meters. Per Section 14. 7 .6.3 .4 of the USAR [ref 9] the release from the Reactor Building Vent is a ground level release. This provides a bounding and representative release point.
  • A meteorological stability class ofD. Per Tables 2.3-12 of the USAR [ref7], Class Dis the most frequent meteorological stability class at 10 meters.
  • A wind speed of9.l mph. Derived from Table 2.3-8 "Wind Frequency Distribution at 10 Meter Level, Stability Class D" of the USAR [ref 7].
  • A wind direction from 337.5° (NNW). This is the most common direction in Table 2.3-8 of the USAR [ref 7].
  • A release duration of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. NEI 99-01 [ref3] stipulates that the set point be based on a one hour exposure. 5.1.2.2 Plant Stack Effluent Monitor A loss of coolant accident (LOCA), described in Section 14. 7.2 of the USAR [ref 8], with the effluent passing through the Standby Gas Treatment System was used as the basis for establishing the set point for the reactor plant stack effluent monitor. The following data served as input into the RASCAL program:
  • The isotopic release rate as derived in Appendix A. o Noble gases: 60.2 (Ci/sec) o Iodines: 7.9 (Ci/sec) o Particulates 0.2 (Ci/sec)
  • A release height of 100 meters.
  • A meteorological stability class of D. Per Tables 2.3-20 of the USAR [ref 7], Class Dis the most frequent meteorological stability class at 100 meters.
  • A wind speed of 14 mph. Derived from Table 2.3-16 "Wind Frequency Distribution at 100 Meter Level, Stability Class D" of the USAR [ref 7].
  • A wind direction from 337.5° (NNW). This is the most common direction in Table 2.3-16 of the USAR [ref7].
  • A release duration of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. NEI 99-01 [ref3] stipulates that the set point should be based on a one hour exposure.

02/28/2017 Calculation 04-199.001 Page 8 of 40 Note: the impact of isolating the SBGT system on the EAL set points for the Plant Stack is provided in Appendix C and provided as a point of interest only. 5.2 Liquid Effluent Monitors 5.2.1.1 NUE As the set point for an NUE, is merely twice the value associated with the ODCM limit, the only input is the ODCM limit determined by EC26667 (Attachment 2). 5.2.2 Alert The following input parameters were used in Equations 2 and 4 to determine the Alert set point for the liquid effluent monitors are as follows:

  • Aij, the site related ingestion dose commitment factor to the total body or thyroid G) for each isotope (mrem/hr per µCi/ml), are from Table 2 ofODCM-04.01 [ref 4] "Aii Values for the Monticello Nuclear Generating Plant mrem/hr per µCi/ml)". The values used are provided in AppendixB.
  • C, the isotopic concentration (µCi/ml) is based on the ODCM and provided in Appendix B.
  • Per EC26667 the fraction of the total activity due to hard to detect nuclides (FHTn) is 0.877.
  • Per EC26667 the detectors' efficiency (DE) are: o 1.3E-07 (µCi/ml per cps) for the Discharge Canal; o 4.3E-07 (µCi/ml per cps) for the Service Water; and
  • Per TBNWS Efficiency Report under EC28274 [ref2] the TBNWS efficiency is 3.42E-09 (µCi/ml per cpm). 6.0 ASSUMPTIONS 6.1 Gaseous Effluent Monitors 6.1.1 Alert, SAE and GE The following validated assumptions were made regarding data entered into RASCAL:
  • A release duration of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Per the developer's notes associated with AAl, AS 1 and AG 1 of NEI 99-01 [ref 3] the set point should be based on a one hour exposure 6.2 Liquid Effluent Monitors 6.2.1 Alert The following validated assumptions were made regarding data used in Equations 2 and 4 to determine the Alert set point for the liquid effluent monitors:
  • Per the developer's notes associated with AA 1 of NEI 99-01 Rev 6 [ref 3 ], effluent monitor set points for an ALERT, are to be based on dose to a person exposed for one hour. Thus t, the length of the release equals 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
  • No dilution occurs between the monitor and the Mississippi River. This results in a lower calculated EAL set point.

02/28/2017 Calculation 04-199.001 Page 9 of 40 7.0 ANALYSIS 7.1 Gaseous Effluent Monitors 7.1.1 NUE The ODCM limit, as calculated in EC26667, and the resultant NUE EAL using Equation 2, are provide in Table 2. The NUE values were rounded to 1 significant figure. Table 2 Gaseous Effluent Monitor Set Points for an NUE .*.** . *.* ODCM Set Point EAL Reactor Building Vent . 1.3 E+04 µCi/sec 3.0 E+04 µCi/sec Plant Stack 3.65E+05 µCi/sec 7.0 E+05 µCi/sec 7.1.2 Alert, SAE & GE The RASCAL results are provided in Attachments 3 through 5. Because the NEI set point is based on a one hour exposure, the TEDE dose to be used for set point determination is the sum of the Inhalation CEDE and Cloudshine, not the Total EDE listed on the document. 7.1.2.1 Reactor Building Vent Effluent Monitor Table 3 provides the pertinent results from the RASCAL runs for a total release rate of l .OE+8 uCi/sec via the reactor building vent. Table 3 One Hour Dose from a Fuel Handling Accident (rem) Distance (miles} ;0.1 ;I 0.2 .I 0.3 I 0.5 I 0.7 I 1 I 1.5 I 2 ThyroidCDE 5.80E+Ol l.60E+Ol 7.70E+OO 3.00E+OO l.70E+OO 8.60E-Ol 4.20E-Ol 2.40E-Ol TEPE l.87E+OO 5.35E-Ol 2.62E-Ol l.03E-Ol 5.82E-02 3.0lE-02 l.51E-02 8.60E-03 Inhalation CEDE l.80E+OO 5.00E-01 2.40E-01 9.20E-02 5.lOE-02 2.60E-02 1.30E-02 7.40E-03 Cloudshirte 6.SOE-02 3.50E-02 2.20E-02 l.lOE-02 7.20E-03 4.lOE-03 2.lOE-03 l.20E-03 As the site boundary SSW of the reactor building vent is approximately 0.32 miles, the TEDE and Thyroid dose projections at 0.3 miles and beyond are the value of interest. Because the Thyroid CDE is more restrictive (i.e. is a larger percentage of its 5 rem action level vs. TEDE dose compared to its 1 rem action level), the set points were determined using Equation 1 with Dose2 equal to 7. 7 rem. The set points were rounded to one significant figure and are provided in Table 4. Table 4 Reactor Building Vent Effluent Monitor Set Points for an FHA Set Point Dose2 RR1 Dose2 (µCi/sec) (rem) (µCi/sec) * (rem) ALERT 6E+05 0.05 SAE 6E+06 0.5 1.0 E+8 7.7 GE 6E+07 5 02/28/2017 Calculation 04-199.001 Page 10 of 40 7.1.2.2 Plant Stack Effluent Monitor Table 5 provides the pertinent results from the RASCAL runs for a total release rate of 100 Ci/sec via the plant stack with SBGT operating. Table 5 One Hour Dose from a LOCA with SBGT On (rem) Distance (miles) 0.1 0.2 0.3 0.5 0.7 1 1.5 2 Thyroid CDE 5.5E-01 3.9E+OO 6.2E+OO 4.9E+OO 3.lE+OO l.6E+OO l.OE+OO TEDE 4.5E-02 6.9E-02 l.8E-01 2.9E-01 2.lE-01 l.5E-01 7.8E-02 5.lE-02 Inhalation CEDE l.7E-02 l.2E-Ol 2.0E-01 l.6E-01 9.9E-02 5.2E-02 3.2E-02 Cloudshihe 4.5E-02 5.2E-02 6.0E-02 8.7E-02 5.2E-02 4.6E-02 2.6E-02 l.9E-02 As the site boundary SSW of the plant stack is approximately 0.25 miles, the TEDE and Thyroid dose projections at 0.2 miles and beyond are the value of interest. The maximum dose occurs at 0.5 miles. Because the Thyroid CDE is more restrictive (i.e. is a larger percentage of its 5 rem action level vs. TEDE dose compared to its 1 rem action level), the set points, were determined using Equation 1 with Dose2 equal 6.2 rem. The set points were rounded to one significant figure and are provided in Table 6. Table 6 Plant Stack Effluent Monitor Set Points for a LOCA with SBGT On Set Point Dose2 RR1 Dose2 (µCi/sec) (rem) (uCi/sec) (rem) ALERT 8 E+05 0.05 SAE 8 E+06 0.5 1.0 E+08 6.20 GE 8 E+07 5 7.2 Liquid Effluent Monitors 7.2.1 Liquid NUE Set Points The ODCM limit, as calculated in EC26667, contains a safety factor of 0.8. Equation 2 removes this safety factor and determines the actual value of 2 times the ODCM limit. The ODCM limit with the safety factor and the resultant NUE EAL are provide in Table 7. The NUE values were rounded to 1 significant figure. 7.2.2 Liquid Alert Set Points The details of the calculation to determine the set points for an Alert EAL using Equation 2 are provided in Appendix B. These values are converted from a concentration (uCi/ml) to a detector reading using Equation 5. As with the NUE set points, these were rounded to one (1) significant figure. The values are also provided in Table 7. 7.2.3 Summary of Liquid Set Points The liquid effluent monitor set points associated with NEI 99-01, are presented in Table 7.

02/28/2017 Calculation 04-199.001 Page 11of40 Table 7 Liquid Effluent Monitor Set Points Monitor ODCM . NUE Alert Discharge Canal (cps) ; 379 900 2000 Service Water (cps) 115 300 700 TBNWS (cpm) 1.41 E+04 4E+04 9E+04

8.0 CONCLUSION

S The EAL set points for the six effluent monitors are summarized in Table 8. Table 8 Effluent Monitor Set Points Corresponding to NEI 99-01 EALs NUE Alert SAE GE . 10 mrem TEDE or 100 mrem TEDE or 1 rem TEDEor 2times ODCM 50 mrem Thyroid 500 mrem Thyroid 5 rem Thyroid Monitor CDE CDE CDE ReactorBuilding Vent* 3 E+4 µCi/sec 6 E+05 µCi/sec 6 E+06 µCi/sec 6 E+07 µCi/sec Plant Stack 7 E +5 µCi/sec 8 E+05 µCi/sec 8 E+06 µCi/sec 8 E+07 µCi/sec Discharge Canal *' 900 cps 2000 cps NA NA

  • Service Water 300 cps 700 cps NA NA JBNWS 4 E+04 cpm 9 E+04 cpm NA NA The Plant Stack Effluent Monitor NUB and Alert EAL set points are virtually identical. This is primarily due to the isotopic mix during a LOCA vs. normal operation. It is recommended that the NUB set point be established at the ODCM limit rather than the NEI recommendation of two times this value. The reactor building ventilation system is equipped with an effluent monitor and an exhaust plenum monitor. The exhaust plenum monitor is independent of the effluent monitor and designed to automatically isolate and re-route the reactor building exhaust in the event of a high radiation signal. The isolation occurs when the plenum exhaust monitor exceeds 26 mrem/hr. Using the methodology presented in Attachment 8 of Root Cause Evaluation 01537833[ref 6], this corresponds to a Fuel Handling Accident release rate of l .08E+06 µCi/sec (see Attachment 6). Because the reactor building ventilation automatically isolates prior to reaching the SAE or GE set points, these set points are not applicable. To implement NEI 99.01 Rev 6, it is recommended that the values provided in Table 9 be adopted.

02/28/2017 Calculation 04-199.001 Page 12 of 40 Table 9 Proposed Effluent Monitor EAL Set Points NUE Alert SAE GE 10 mrem WB or 100 mrem WB or 1 rem WB or Multiple ofODCM 50 mrem Thyroid 500 mrem Thyroid 5 rem Thyroid Monitor CDE CDE CDE Reactor Building Vent 3 E+4 µCi/sec 6 E+05 µCi/sec NIA NIA Plant Stack 4 E +5 µCi/sec 8 E+OS µCi/sec 8 E+06 µCi/sec 8 E+07 µCi/sec Discharge Canal 900 cps 2000 cps NA NA Service Water 300 cps 700 cps NA NA TBNWS 4E+04 cpm 9 E+04 cpm NA NA

9.0 REFERENCES

1. A.2-101 "Classification of Emergencies" Rev 5 0 2. TBNWS Efficiency Report under EC-28274 "Acceptance of Primary Calibration Report for TBNWS RM-7992A/B" 3. NEI 99-01 Rev 6 "Development of Emergency Action Levels for Non-Passive Reactors." 2012 4. ODCM-04.01 Offsite Dose Calculation Manual "Liquid Effluent Calculations" Rev 3 5. ODCM-05.01 Offsite Dose Calculation Manual "Gaseous Effluent Calculations" Rev 10 6. Root Cause Evaluation 01537833, "Past RBV WRGM Settings Prevented Transition to Mid/High Range" Feb, 2016 7. USAR 2.3 Updated Safety Analysis Report "Site and Environs" Rev 25 8. USAR § 14. 7 .2 Updated Safety Analysis Report "Loss of Coolant Accident" Rev 32P 9. USAR §14.7.6 Updated Safety Analysis Report "Refueling Accident Analysis" Rev 32P 10. USAR Table 17.7-13 "LOCA Radiological Consequences Analysis Inputs and Assumptions Rev32P" 11. Table 14.7-21 "FHA Radiological Consequences Analysis Inputs and Assumptions" Rev 32P 12. Table 14.7-24 "Core Inventory@ T = 0 Hours in Ci/MWt" Rev 32P 10.0 PLANTIMPACT There is no plant impact. The purpose of this calculation was to provide set points to aid the plant in identifying when off normal conditions warranted the declaration of an EAL. The set points do not control any processes or systems. 11.0 APPENDICIES A. Source Term B. Liquid Dose Calculations C. Impact of SBGT Off 12.0 ATTACHMENTS 1. Excerpt from EC 2403 7 02/28/2017 Calculation 04-199.001 Page 13 of 40 2. Excerpt from EC 26667 3. RASCAL Run for Reactor Building Vent 4. RASCAL Run for Plant Stack SBGT Off 5. RASCAL Run for Plant Stack SBGT On 6. Relationship of Reactor Building Exhaust Plenum Monitor Trip Point to Effluent Monitor Release Rate for FHA.

02/28/2017 Calculation 04-199.001 Page 14 of 40 Appendix A Source Term Gaseous Effluents The source term used to determine the gaseous effluent monitor readings corresponding to an Alert, Site Area Emergency and General Emergency is derived from Table 14.7-24 of the USAR [ref 12] "Core Inventory@ T = 0 Hours in Ci/MWt". As the core inventory for each isotope is directly proportional to thermal power, the relative core inventory can be expressed in µCi, rather than Ci/MWt. To calculate an offsite dose, a release rate in µCi/sec must be entered into the RASCAL program. To simplify the calculation, the expected isotopic mix released was normalized to a total of 1 µCi/sec. Reactor Building Vent The set points for the reactor Building Vent are based on a Fuel Handling Accident (FHA). The isotopes released in such an accident are limited to noble gasses and halogens. Table 14.7-21 of the USAR [ref 11] "FHA Radiological Consequences Analysis Inputs and Assumptions" provides the necessary assumptions to convert a core inventory into an isotopic release rate. The relative core inventory at t = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the assumed time of the accident, is obtained using Equation Al The relative release rate is obtained using Where: RRRi EquationA2 = the Relative Release Rate of Isotope I (µCi/sec). (As with the relative core inventory any unit of time can be assigned to the release rate.) = the Relative Core Inventory of isotope I after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (µCi). =Fraction of the core inventory released from the GAP (From Table 14.7-21 ofUSAR). 0.08 forl-131; 0.05 for other halogens; 0.1 for KR-85; 0.05 for other noble gases DE =Decontamination Factor (From Table 12.7-21 ofUSAR). 200 for Iodine 1 for all other species. The relative release rate was then normalized to a total value of 100 Ci/sec (l.Oe+08µCi/sec ). This was done to generate meaningful RASCAL results. Table A-1 provides the release rate of the isotopes entered into RASCAL for a FHA. All intermediary values are also presented in the table.

02/28/2017 Calculation 04-199.001 Page 15 of 40 Table A-1 Release Rate for a FHA Relative Core Relative Cote Decay Inventory @t=24 Relative Release Normalized Inventciry @ t='O Constant hrs Rate Release Rate Nuclide (µCi) (I/sec) (µCi) {µCi/sec) .. * {µCi/sec) Xe-133***** 5.48E+04 1.53E-06 4.80E+04 2.40E+03 8.99E+07 Xe-135 2.53E+04 2.12E-05 4.07E+03 2.04E+02 7.62E+06 Kr-85 3.33E+02 2.0SE-09 3.33E+02 3.33E+Ol l.25E+06 Kr-85m 7.38E+03 4.30E-05 l.80E+02 9.0lE+OO 3.38E+05 Kr-87 l.42E+04 l.52E-04 2.92E-02 1.46E-03 5.48E+Ol Kr-88 2.01E+04 6.78E-05 5.74E+Ol 2.87E+OO l.07E+05 I-131 2.68E+04 9.98E-07 2.46E+04 9.82E+OO 3.68E+05 I-132 3.90E+04 8.37E-05 2.82E+Ol l.13E-02 4.22E+02 I-133 5.51E+04 9.25E-06 -2.48E+04 9.92E+OO 3.71E+05 I-134 6.09E+04 2.20E-04 3.38E-04 l.35E-07 5.07E-03 5.17E+04 2.92E-05 4.15E+03 l.66E+OO 6.22E+04 Total 2.67E+03 l.OOE+08 Plant Stack The set points for the reactor Plant Stack are based on a Loss of Coolant Accident (LOCA). Table 14. 7 -13 of the USAR [ref 10] "LOCA Radiological Consequences Analysis Inputs and Assumptions" provides the necessary assumptions to convert a core inventory into an isotopic release rate. Because the standby gas treatment system could be utilized or not, two differ RASCAL release rates were developed. The relative release rate is detennined using the following equation: EquationA3 Where: RE =Release fraction (sum of the gap release fraction and early in-vessel release fractions listed in Table 14.7-13 ofUSAR). 1.0 for Noble Gases (Xe, Kr); 0.3 for Halogens (I, Br); 0.25 for Alkali metals (Cs, Rb); 0.05 for Tellurium Metals (Te, Sb, Se, Ba, Sr); 0.02 for Ba & Sr ' 0.0025 for Noble Metals (Ru, Rh, Pd, Mo, Tc, Co); 0.0005 for Cerium Group (Ce, Pu, Np); and 0.0002 for Lanthanides (La, Zr, Nd, Eu, Nb, Pm, Pr, Sm, Y, Cm, Am). SBGTRFi =the Standby Gas Treatment Release Fraction, derived from Table 14.7-13, are: 1.0 for Noble Gases; 0.15 for Iodine; and 0.02 for particulates. The relative release rate was then normalized to a total value of 100 Ci/sec. This was done to produce meaningful RASCAL results.

02/28/2017 Calculation 04-199.001 Page 16 of 40 To reduce the data input into RASCAL, the source term option of effluent releases by mixture was used. When using this option, three release rates are entered: noble gases, total iodine and particulates. Table A-2 provides the release rate of the isotopes entered into RASCAL for a LOCA with the standby gas treatment system on. The value of SBGTRFi in equation A3 was set according to the species. Isotopes other than noble gases and iodine were assumed to be in the particulate form. All intermediary values are also presented in the table. Table A-2 Release Rate for a LOCA with SBGT On. Relative Core ** Relative Core Inventory*@

  • Relative Normalized Inventory@ Relative Normalized t=O Release Rate Release Rate f=O Release Rate Release Rate Nuclide ECi/sec) (Ci/sec) Nuclide (Ci) (Ci/sec) . (Ci/sec) Co.-58 l.38E+02 6.90E-03 5.19E-06 Te-131m 3.84E+03 3.84E+OO 2.89E-03 Co-60 ' l.33E+02 6.65E-03 5.00E-06 Te-132 3.82E+04 3.82E+Ol 2.87E-02 Kr-85 3.33E+02 3.33E+02 2.50E-01 M31 2.68E+04 l.20E+03 9.07E-01 Kr-85m 7.38E+03 7.38E+03 5.56E+OO I-132 .* 3.90E+04 1.75E+03 l.32E+OO Kr-87 1.42E+04 1.42E+04 1.07E+Ol 1"133 5.51E+04 2.48E+03 1.87E+OO Kr-88 2.01E+04 2.01E+04 1.51E+Ol I I-134 6.09E+04 2.74E+03 2.06E+OO Rb-86 6.35E+Ol 3.17E-01 2.39E-04 I-135 5.17E+04 2.33E+03 1.75E+OO Sr-89 2.68E+04 1.07E+Ol 8.08E-03 Xe-133 .* 5.48E+04 5.48E+04 4.12E+Ol 2.64E+03 1.05E+OO 7.94E-04 Xe-135 2.53E+04 2.53E+04 1.91E+Ol Sr-91 3.37E+04 1.35E+Ol 1.0lE-02 Cs-134 5.35E+03 2.67E+Ol 2.0lE-02 Sr-92 3.62E+04 1.45E+Ol 1.09E-02 Cs-136 1.86E+03 9.32E+OO 7.0lE-03 Y-90 2.81E+03 l.12E-02 8.45E-06 Cs"l37 3.47E+03 1.74E+Ol l.31E-02 Y"91 3.44E+04 l.38E-01 1.04E-04 Ba-139 4.97E+04 1.99E+Ol 1.50E-02 3.64E+04 1.45E-01 1.09E-04 Ba-140 4.77E+04 1.91E+Ol 1.44E-02 Y*93 4.18E+04 1.67E-01 l.26E-04 La-140 4.92E+04 1.97E-01 1.48E-04 Zr-95 *.* 4.85E+04 1.94E-01 1.46E-04 La-141 4.53E+04 1.81E-01 l.36E-04 Zr-97 . 4.99E+04 2.00E-01 1.SOE-04 La-142 4.39E+04 1.76E-01 l.32E-04 Nb"95 .... 4.87E+04 1.95E-01 1.47E-04 Ce-141 4.53E+04 4.53E-01 3.41E-04 Mo-99 5.12E+04 2.56E+OO 1.93E-03 Ce-143 4.23E+04 . 4.23E-01 3.18E-04 Tc-99m 4.54E+04 2.27E+OO 1.71E-03 Ce-144 3.68E+04 3.68E-01 2.77E-04 Ru-103 4.05E+04 2.02E+OO 1.52E-03 Pr-143 4.13E+04 1.65E-01 1.24E-04 Ru-105 2.71E+04 l.35E+OO 1.02E-03 Nd-147 1.81E+04 7.23E-02 5.44E-05 Ru-106 1.41E+04 7.0SE-01 5.30E-04 Np-239 5.22E+05 5.22E+OO 3.93E-03 I* Rh-105 2.46E+04 l.23E+OO 9.26E-04 Pu-238 9.04E+Ol 9.04E-04 6.81E-07 Sb-127 2.80E+03 2.80E+OO 2.lOE-03 Pu-239 1.09E+Ol 1.09E-04 8.18E-08 Sb-129 8.52E+03 8.52E+OO 6.41E-03 Pu-240 ' 1.41E+Ol 1.41E-04 1.06E-07 Te-127 2.84E+03 2.84E+OO 2.14E-03 Pu-241 4.09E+03 4.09E-02 3.08E-05
  • 3.70E+02 3.70E-01 2.79E-04 Am-241 4.61E+OO 1.84E-05 l.39E-08 Te-129 8.38E+03 8.38E+OO 6.3 lE-03 Cm-242 1.09E+03 4.34E-03 3.27E-06 Te-l29m l.24E+03 1.24E+OO 9.36E-04 Cm-244 5.24E+Ol 2.lOE-04 1.58E-07 Sum ofNobel Gases: 91.9 Sum of Iodines: 7.9 Sum of Particulates: 0.2 02/28/2017 Calculation 04-199.001 Page 17 of 40 Liquid Effluents The source term used to determine the liquid effluent monitor readings corresponding to an Alert is derived from Table 1 of ODCM-04.01 [ref 4] "Liquid Source Terms". The data in this table is provided in Ci/yr. As the concentration of any isotope released would be directly proportional to curies released per year, the units on this table can merely be changed to provide the relative release concentration. These concentrations were then normalized to 1 µCi/ml. Table A-3 Release Rate for a Liquid Release Normalized Normalized Relative Release Release Relative Release Release Concentration Concentration Concentration Concentration Nuclide (µCi/ml) (µCi/ml) Nuclide (µCi/ml) (µCi/ml) H-3* 2.lOE+Ol 8.77E-01 Y-93 6.60E-02 2.76E-03 Na-24 1.70E-01 7.IOE-03 Mo-99 5.00E-02 2.09E-03 Mn-54 2.60E-03 1.09E-04 I-131 l.30E-01 5.43E-03 Mn-56 2.70E-Ol 1.13E-02 I-132 l.30E-01 5.43E-03 Fe-59 8.lOE-04 3.38E-05 I-133 4.00E-01 l.67E-02 Co-58 9.30E-03 3.88E-04 I-134 6.40E-02 2.67E-03 Co-60 2.00E-02 8.35E-04 I-135 2.50E-01 1.04E-02 Cu-64 5.40E-01 2.25E-02 Cs-134 8.30E-02 3.46E-03 Zn-65 5.30E-03 2.21E-04 Cs-136 . 2.60E-02 1.09E-03 Zn-69m 3.70E-02 1.54E-03 Cs-137 1.20E-01 5.0lE-03 Br-83 1.40E-02 5.84E-04 Cs-138 1.50E-01 6.26E-03 Sr-89* 2.80E-03 l.17E-04 Ba-140 1.IOE-02 4.59E-04 Sr-90* 1.70E-04 7.lOE-06 La-141 5.70E-03 2.38E-04 Sr-91 6.40E-02 2.67E-03 Ce-141 8.50E-04 3.55E-05 Sr-92 5.80E-02 2.42E-03 Ce-144 5.30E-03 2.21E-04 Y-92 1.00E-01 4.17E-03 Np-239 l.70E-01 7.lOE-03 Total 2.40E+Ol 1.00E+OO 02/28/2017 Calculation 04-199.001 Page 18 of 40 Appendix B Liquid Dose Calculations This appendix expands upon the Inputs & Assumptions and Analysis sections of this calculation. Inputs & Assumptions Isotopic Concentration The source term provided in Table A-4 serves as the parameter Ci in Equation 3. Ingestion Dose Commitment Factor The site related ingestion dose commitment factors to the total body and thyroid (Aj) listed in Table 2 of ODCM-04.01 [ref 4], "Aj Values for the Monticello Nuclear Generating Plant" are based on an adult. As these values are age dependent values for other age groups were determined using the equation in Section 2.3.2.B of the ODCM. Equation Bl Where: 1.14E+05 =Conversion factor (106 pCi per uCi) X (1000 ml per 1) I (8760 hrs per year). Uw =Age dependent water consumption rate (1/yr). From Table E-5 ofRG 1.109. = 730 (1/yr) for an adult = 510 (1/yr) for a teen = 510 (l/yr) for a child = 330 (l/yr) for an infant Dw =Dilution factor from the near field area to the potable water intake. (7 per ODCM-04.01 §2.3.2B). UF =Age dependent fish consumption rate (kg/yr) From Table E-5 ofRG 1.109. = 21 (kg/yr) for an adult = 16 (kg/yr) for a teen = 6.9 (kg/yr) for a child = 0 (kg/yr) for an infant BE = Bioaccumulation Factor for isotope(i) in fish (pCi/kg per pCi/l). From Table A-1 of Reg Guide 1.109. DFij =Dose Conversion factor for nuclide (i) for organ G). From RG 1.109. The age dependent ingestion dose commitment factors (Aij) used as input into Equation 3 are provided in Tables B-1 through B-4. The dose conversion factors from RG 1.109 are provided in Tables B-1 through B-4. The site related dose commitment factors obtained from using Equation B 1 are provided in Tables B-5 through B-8.

02/28/2017 Calculation 04-199.001 Page 19 of 40 Table B-1 RG 1.109 Adult Dose Conversion Factors (DFij) (mrem/µCi) Nuclide Whole Body DFii Thyroid Nudide WholeBodv DFii Thvroid H-3* l.05E-07 l.05E-07 Y-93 7.40E-ll O.OOE+OO Na-24 l.70E-06 l.70E-06 Mo-99 8.20E-07 0.00E+OO Mn-54 8.72E-07 O.OOE+OO I-131 3.41E-06 1.95E-03 Mn-56 2.04E-08 O.OOE+OO I-132 l.90E-07 l.90E-05 Fe-59 3.91E-06 O.OOE+OO I-133 7.53E-07 3.63E-04 Co-58 1.67E-06 0.00E+OO I-134 l.03E-07 4.99E-06 Co-60 4.72E-06 O.OOE+OO I-135 4.28E-07 7.65E-05 Cu-64 3.91E-08 O.OOE+OO Cs-134 l.21E-04 O.OOE+OO Zn-65 6.96E-06 O.OOE+OO Cs'-136 l.85E-05 O.OOE+OO Zn-69m 3.73E-08 O.OOE+OO 7.14E-05 O.OOE+OO Br-83 4.02E-08 O.OOE+OO Cs-138 5.40E-08 O.OOE+OO Sr-89* 8.84E-06 O.OOE+OO Ba-140 l.33E-06 O.OOE+OO Sr-90* l.75E-04 0.00E+OO La-141 l .62E-11 0.00E+OO Sr-91 2.29E-07 0.00E+OO Ce-141 7.18E-10 0.00E+OO Sr-92 9.30E-08 O.OOE+OO Ce-144 2.62E-08 O.OOE+OO Y-92 2.47E-11 O.OOE+OO Np-239 6.45E-ll O.OOE+OO Table B-2 RG 1.109 Teen Dose Conversion Factors (DFij) (mrem/µCi) Nuclide Who,JeBody DFijThvroid Nuclide Whole Body DFij Thyroid H-3* l.06E-07 l.06E-07 Y-93 l.05E-10 O.OOE+OO Na-24 2.30E-06 2.30E-06 Mo-99 l.15E-06 O.OOE+OO Mn-54 1.17E-06 O.OOE+OO 4.40E-06 2.39E-03 Mn-56 2.81E-08 O.OOE+OO I-132 2.62E-07 2.46E-05 Fe-59 5.29E-06 O.OOE+OO I-133 l.04E-06 4.76E-04 Co-58 2.24E-06 O.OOE+OO I-134 l.39E-07 6.45E-06 Co-60 6.33E-06 O.OOE+OO I-135 5.82E-07 l.OlE-04 Cu-64 5.41E-08 O.OOE+OO Cs-134 9.14E-05 O.OOE+OO Zn-65 9.33E-06 O.OOE+OO Cs-136 2.27E-05 O.OOE+OO Zn-69m 5.19E-08 O.OOE+OO Cs-137 5.19E-05 O.OOE+OO ' Br-83 5.74E-08 O.OOE+OO Cs-138 7.45E-08 O.OOE+OO Sr-89* l.26E-05 O.OOE+OO Ba-140 l.83E-06 O.OOE+OO Sr-90* 2.04E-04 O.OOE+OO La-141 2.31E-11 O.OOE+OO Sr-91 3.21E-07 0.00E+OO Ce-141 l.02E-09 O.OOE+OO Sr-92 l.30E-07 0.00E+OO Ce-144 3.74E-08 O.OOE+OO Y-92 3.50E-ll O.OOE+OO Np-239 9.22E-ll O.OOE+OO --___ ___J 02/28/2017 Calculation 04-199.001 Page 20 of 40 Table B-3 RG 1.109 Child Dose Conversion Factors (DFij) (mrem/µCi) Nuclide WholeBodY .** DFijThvroid Nuclide W]loleBodv DFii Thvroid H-3* 2.03E-07 2.03E-07 Y-93 3.13E-10 O.OOE+OO Na-24 5.80E-06 5.80E-06 Mo-99 3.29E-06 O.OOE+OO Mn-54 2.85E-06 O.OOE+OO I-131 9.83E-06 5.72E-03 Mn-56 7.54E-08 O.OOE+OO I-132 6.76E-07 6.82E-05 Fe-59 l.33E-05 O.OOE+OO I-133 2.77E-06 l.36E-03 Co-58 5.51E-06 0.00E+OO I-134 3.58E-07 l.79E-05 Co-60 l.56E-05 O.OOE+OO -* 1-135 1.49E-06 2.79E-04 Cu-64 1.48E-07 O.OOE+OO Cs-134 8.lOE-05 O.OOE+OO Zn-65 2.27E-05 0.00E+OO 4.18E-05 O.OOE+OO Zn-69m l.43E-07 O.OOE+OO Cs-137 4.62E-05 O.OOE+OO Br-83 l.71E-07 O.OOE+OO Cs-138 2.0lE-07 O.OOE+OO Sr-89* 3.77E-05 O.OOE+OO Ba-140 4.85E-06 O.OOE+OO Sr-90* 5.15E-04 O.OOE+OO La-141 6.88E-11 O.OOE+OO Sr-91 9.06E-07 O.OOE+OO Ce-141 2.94E-09 O.OOE+OO Sr-92 3.62E-07 O.OOE+OO Ce-144 l.llE-07 O.OOE+OO Y-92 l.03E-10 O.OOE+OO No-239 2.65E-10 O.OOE+OO Table B-4 RG 1.109 Infant Dose Conversion Factors (DFij) (mrem/µCi) Nuclide WholeBody *. DFij Thyroid *. *. Nuclide Whole Body DFij Thyroid H-3* 3.08E-07 3.08E-07 Y-93 6.62E-10 O.OOE+OO Na-24 l.OIE-05 l.OIE-05 Mo-99 6.63E-06 0.00E+OO Mn-54 4.51E-06 O.OOE+OO 1-131 l.86E-05 l.39E-02 Mn-56 l.41E-07 O.OOE+OO 1-132 l.20E-06 l.58E-04 Fe-59 2.12E-05 O.OOE+OO 1-133 5.33E-06 3.31E-03 Co-58 8.98E-06 0.00E+OO 1-134 6.33E-07 4.15E-05 Co-60 2.55E-05 O.OOE+OO 1-135 2.64E-06 6.49E-04 Cu-64 2.82E-07 O.OOE+OO Cs-134 7.lOE-05 O.OOE+OO Zn-65 2.91E-05 O.OOE+OO Cs-136 5.04E-05 O.OOE+OO Zn-69m 2.79E-07 O.OOE+OO Cs-137 4.33E-05 O.OOE+OO Br-83 3.63E-07 O.OOE+OO Cs-138 3.79E-07 O.OOE+OO Sr-89* 7.20E-05 O.OOE+OO Ba-140* 8.81E-06 0.00E+OO Sr-90* 5.74E-04 O.OOE+OO La-141 1.46E-10 O.OOE+OO Sr-91 l.81E-06 O.OOE+OO Ce-141 5.65E-09 O.OOE+OO Sr-92 7.13E-07 O.OOE+OO Ce-144 l.67E-07 O.OOE+OO Y-92 2.15E-10 O.OOE+OO Np-239 5.61E-10 0.00E+OO 02/28/2017 Calculation 04-199.001 Page 21 of 40 Table B-5 Site Adult Ingestion Dose Commitment Factor (Aij) (mrem/hr per µCi/ml) Nuclide Whole Body Thyroid Nuclide WholeBodv Thyroid l.5E+OO l.5E-+OO Y-93 5.3E-03 O.OE+OO Na-24 4.3E+02 4.3E+02 Mo-99 2.9E+Ol O.OE+OO Mn-54 8.5E+02 O.OE+OO I-131 l.6E+02 9.3E+04 Mn-56 2.0E+OI O.OE+OO 9.IE+OO 9.1E+02 Fe-59 9.8E+02 O.OE+OO I-133 3.6E+Ol l.7E+04 Co-58 2.2E+02 O.OE+OO I-134 4.9E+OO 2.4E+02 Co-60 6.2E+02 O.OE+OO I-135 2.0E+Ol 3.7E+03 Cu-64 5.IE+OO O.OE+OO Cs-134 5.8E+05 O.OE+OO Zn-65 3.3E+04 O.OE+OO Cs-136 8.9E+04 0.0E+OO Zn..:69m l.8E+02 0.0E+OO Cs-137 3.4E+05 O.OE+OO Br-83 l.9E+02 O.OE+OO Cs-138 2.6E+02 O.OE+OO Sr-89* 7.4E+02 O.OE+OO Ba-140 2.9E+Ol 0.0E+OO Sr-90* l.5E+04 0.0E+OO La-141 l.2E-03 O.OE+OO Sr-91 l.9E+Ol O.OE+OO Ce-141 l.OE-02 O.OE+OO Sr-92 7.8E+OO O.OE+OO Ce-144 3.7E-01 O.OE+OO Y-92 l.8E-03 O.OE+OO Np-239 2.3E-03 O.OE+OO Table B-6 Site Teen Ingestion Commitment Factor (Aij) (mrem/hr per µCi/ml) Nuclide Whole Body Thyroid Nuclide Whole Body Thyroid H-3* 1.lE+Ol l.IE+Ol Y-93 5.7E-03 O.OE+OO Na-24 4.4E+02 4.4E+02 Mo-99 3.IE+Ol 0.0E+OO Mn-54 8.6E+02 O.OE+OO ' I-131 l.6E+02 8.5E+04 Mn-56 2.IE+Ol 0.0E+OO I-132 9.3E+OO 8.8E+02 Fe-59 l.OE+03 O.OE+OO I-133 3.7E+Ol l.7E+04 Co-58 2.2E+02 O.OE+OO 5.0E+OO 2.3E+02 Co-60 6.3E+02 O.OE+OO I-135 2.IE+Ol 3.6E+03 Cu-64 5.4E+OO O.OE+OO Cs-134 3.3E+05 O.OE+OO Zn-65 3.4E+04 O.OE+OO Cs-136 8.3E+04 O.OE+OO Zn-69m l.9E+02 O.OE+OO Cs-137 l.9E+05 O.OE+OO Br-83 2.1E+02 O.OE+OO Cs-138 2.7E+02 O.OE+OO Sr-89* 7.9E+02 O.OE+OO Ba-140 2.9E+Ol O.OE+OO Br-90* 1.3E+04 O.OE+OO La-141 l.2E-03 O.OE+OO Sr-91 2.0E+Ol O.OE+OO Ce-141 l.OE-02 O.OE+OO Sr-92 8.2E+OO O.OE+OO Ce-144 3.8E-01 O.OE+OO Y-92 l.9E-03 O.OE+OO 2.4E-03 O.OE+OO 02/28/2017 Calculation 04-199.001 Page 22 of 40 Table B-7 Site Child Ingestion Commitment Factor (Aij) (mrem/hr per µCi/ml) Nuclide Whole Body Thyroid Nuclide Whole Body Thyroid H-3* 1.8E+OO 1.8E+OO Y-93 8.8E-03 O.OE+OO Na-24 5.0E+02 5.0E+02 Mo-99 5.3E+Ol 0.0E+OO Mn-54 9.2E+02 O.OE+OO I-131 2.0E+02 l.1E+05 Mn-56 2.4E+Ol O.OE+OO I-132 1.4E+Ol 1.4E+03 Fe-59 l.2E+03 O.OE+OO I-133 5.6E+Ol 2.7E+04 Co-58 2.6E+02 O.OE+OO I-134 7.2E+OO 3.6E+02 Co-60 7.4E+02 O.OE+OO I-135 3.0E+Ol 5.6E+03 Cu-64 7.lE+OO O.OE+OO Cs-134 l.3E+05 O.OE+OO Zn-65 3.6E+04 O.OE+OO Cs-136 6.6E+04 0.0E+OO Zn-69m 2.3E+02 O.OE+OO Cs-137 7.3E+04 O.OE+OO Br-83 2.7E+02 O.OE+OO Cs-138 3.2E+02 O.OE+OO Sr-89* l.2E+03 O.OE+OO Ba-140 5.6E+Ol 0.0E+OO Sr-90* l.6E+04 O.OE+OO La-141 l.9E-03 O.OE+OO Sr-91 2.9E+Ol O.OE+OO Ce-141 2.7E-02 O.OE+OO Sr-92 l.2E+Ol O.OE+OO Ce-144 l.OE+OO 0.0E+OO Y-92 2.9E-03 O.OE+OO 4.3E-03 O.OE+OO Table B-8 Site Infant Ingestion Commitment Factor (Aij) (mrem/hr per µCi/ml) Nuclide Whole Body Thyroid 1: Nuclide Whole Body Thyroid H-3* l.7E+OO l.7E+OO Y-93 3.6E-03 O.OE+OO Na-24 5.4E+Ol 5.4E+Ol Mo-99 3.6E+Ol 0.0E+OO Mn-54 2.4E+Ol O.OE+OO I-131 l.OE+02 7.5E+04 Mn-56 7.6E-Ol O.OE+OO I-132 6.4E+OO 8.5E+02 Fe-59 l.1E+02 O.OE+OO I-133 2.9E+Ol l.8E+04 Co-58 4.8E+Ol 0.0E+OO .. I-134 3.4E+OO 2.2E+02 Co-60 l.4E+02 O.OE+OO I-135 l.4E+Ol 3.5E+03 Cu-64 l.5E+OO O.OE+OO Cs-134 3.8E+02 O.OE+OO Zn-65 l.6E+02 O.OE+OO Cs-136 2.7E+02 O.OE+OO Zn-69m 1.5E+OO O.OE+OO Cs-137 2.3E+02 0.0E+OO Br-83 2.0E+OO O.OE+OO *Cs-138 2.0E+OO O.OE+OO Sr-89* 3.9E+02 O.OE+OO Ba-140 4.7E+Ol O.OE+OO Sr-90* 3.1E+03 O.OE+OO La-141 7.8E-04 0.0E+OO ,' Sr-91 9.7E+OO O.OE+OO Ce-141 3.0E-02 O.OE+OO Sr-92 3.8E+OO O.OE+OO Ce-144 9.0E-01 O.OE+OO Y-92 1.2E-03 O.OE+OO Np-239 3.0E-03 O.OE+OO Analysis As no dilution was credited for a release via the service water discharge or the TBNWS, the dose resulting from a release concentration of 1 µCi/ml from either point is the same as that for the discharge canal. Thus, the concentration resulting in a dose at the Alert EAL level will be the same for all three detectors. j 02/28/2017 Calculation 04-199.001 Page 23 of 40 Using the parameters in Section 4.2.2.1, Table A-1 and Tables B-1 through B-4, the dose to the whole body and thyroid for four age groups were calculated. The results of the calculation are presented in Tables B-9 through B-12. Table B-9 Dose to an Adult Due to a Discharge Canal Release of 1 µCi/ml (mrem) :Nuclide ... \Yh9leBQdy Thyro_id .* ; Nuclide ',\I.hole Body Thyr9id . H-3* l.29E+OO l.29E+OO Y-93 l.46E-05 O.OOE+OO Na-24 3.03E+OO 3.03E+OO Mo-99 6.13E-02 O.OOE+OO Mn-54 9.18E-02 O.OOE+OO I-131 8.85E-01 5.06E+02 Mn"56 2.23E-01 O.OOE+OO I-132 4.93E-02 4.93E+OO Fe-59 3.32E-02 0.00E+OO I-133 . 6.0lE-01 2.90E+02 8.53E-02 O.OOE+OO I-134 l.32E-02 6.37E-01 Co-60 5.19E-01 O.OOE+OO 2.13E-01 3.82E+Ol Cu-64 1.16E-01 O.OOE+OO 2.01E+03 O.OOE+OO Zn-65 7.39E+OO O.OOE+OO I. Cs-136 9.64E+Ol 0.00E+OO Zn-69m 2.77E-01 O.OOE+OO Cs-D7 l.72E+03 O.OOE+OO Br-83 l.13E-01 O.OOE+OO Cs-138 l.62E+OO O.OOE+OO Sr-89* 8.65E-02 0.00E+OO Ba-140 l.31E-02 O.OOE+OO Sr-90* l.04E-01 O.OOE+OO La-141 2.77E-07 O.OOE+OO Sr-91 5.12E-02 O.OOE+OO Ce-141 3.64E-07 O.OOE+OO Src92 l.88E-02 O.OOE+OO Ce-144 8.28E-05 0.00E+OO Y-92 7.40E-06 O.OOE+OO Np-239 l.64E-05 O.OOE+OO Total 3.84E+03 8.44E+02 Table B-10 Dose to a Teen Due to a Discharge Canal Release of 1 µCi/ml (mrem) Nuclide Whole Body Thyroid Nuclide Whole Body Thyroid H-3* 9.24E-01 9.72E-01 Y-93 l.56E-05 O.OOE+OO .* Na-24 3.llE+OO 3.1 lE+OO 6.37E-02 O.OOE+OO Mn-54 9.37E-02 O.OOE+OO .. 8.52E-01 4.63E+02 Mn-56 2.34E-Ol O.OOE+OO I-132 5.07E-02 4.76E+OO Fe-59 3.41E-02 O.OOE+OO I-133 6.19E-Ol 2.83E+02 Co-58 8.65E-02 0.00E+OO l.32E-02 6.15E-Ol Co-'60 5.26E-Ol O.OOE+OO I-135 2.17E-Ol 3.76E+Ol Cl!-64 l.21E-01 O.OOE+OO Cs-134 1.16E+03 O.OOE+OO Znc65 7.55E+OO O.OOE+OO Cs-136 ..... 9.0lE+Ol O.OOE+OO Zn-69m 2.93E-01 O.OOE+OO Cs-137 9.51E+02 O.OOE+OO Br-83 l.23E-01 O.OOE+OO Cs-138 l.71E+OO O.OOE+OO Sr-89* 9.28E-02 0.00E+OO Ba-140 l.31E-02 O.OOE+OO 9.12E-02 O.OOE+OO La-141 2.96E-07 O.OOE+OO Sr-91 5.40E-02 O.OOE+OO Ce-141 3.67E-07 O.OOE+OO SrM92 l.98E-02 0.00E+OO Ce-144 8.38E-05 O.OOE+OO Y-92 7.88E-06 O.OOE+OO Np-239 l.74E-05 O.OOE+OO Total 2.22E+03 7.93E+02 02/28/2017 Calculation 04-199.001 Page 24 of 40 Table B-11 Dose to a Child Due to a Discharge Canal Release of 1 µCi/ml (mrem) Nuclide Whole Body Thyroid Nuclide Whole Body Thyroid H-3* l.60E+OO l.60E+OO Y-93 2.41E-05 O.OOE+OO Na-24 3.58E+OO 3.58E+OO Mo-99 l.1 lE-01 O.OOE+OO Mn-54 9.99E-02 O.OOE+OO I-131 l.07E+OO 6.24E+02 Mn-56 2.74E-01 O.OOE+OO I-132 7.38E-02 7.44E+OO Fe-59 3.91E-02 O.OOE+OO I-133 9.30E-OI 4.57E+02 Co-58 l.02E-01 O.OOE+OO I-134 l.92E-02 9.61E-01 Co-60 6.20E-01 O.OOE+OO I-135 3.13E-01 5.85E+Ol Cu-64 l.59E-01 O.OOE+OO Cs-134 4.44E+02 O.OOE+OO Zn-65 7.94E+OO O.OOE+OO Cs-136 7.17E+Ol 0.00E+OO Zn-69m 3.49E-OI O.OOE+OO Cs-137 3.66E+02 O.OOE+OO Br-83 l.58E-OI O.OOE+OO Cs-138 l.99E+OO 0.00E+OO Sr-89* l.41E-01 O.OOE+OO Ba-140 *. 2.55E-02 O.OOE+OO Sr-90* 1.17E-OI O.OOE+OO La-141 4.58E-07 O.OOE+OO Sr-91 7.72E-02 O.OOE+OO Ce-141 9.48E-07 O.OOE+OO Sr-92 2.80E-02 O.OOE+OO Ce-144 2.23E-04 O.OOE+OO Y-92 l.20E-05 O.OOE+OO No-239 3.04E-05 O.OOE+OO Total 9.01E+02 l.15E+03 Table B-12 Dose to an Infant Due to a Discharge Canal Release of 1 µCi/ml (mrem) Nuclide Whole Body Thyroid Nuclide Whole Body Thyroid H-3* l.45E+OO l.45E+OO Y-93 9.80E-06 0.00E+OO Na-24 3.85E-01 3.85E-01 Mo..:99 7.44E-02 O.OOE+OO -_Mn-54 2.63E-03 O.OOE+OO I-131 5.42E-01 4.05E+02 Mn-56 8.54E-03 O.OOE+OO I-132 3.50E-02 4.61E+OO Fe-59 3.85E-03 O.OOE+OO I-133 4.78E-01 2.97E+02 --Co-58 l.87E-02 O.OOE+OO I-134 9.09E-03 5.96E-01 Co-60 1.14E-01 O.OOE+OO I-135 1.48E-01 3.64E+OI Cu-64 3.42E-02 O.OOE+OO Cs-134 l.32E+OO O.OOE+OO Zn-65 3.46E-02 O.OOE+OO Cs-136 2.94E-OI O.OOE+OO Zn-69m 2.32E-03 O.OOE+OO Cs-137 l.17E+OO O.OOE+OO Br-83 l.14E-03 O.OOE+OO Cs-138 l.28E-02 O.OOE+OO Sr-89* 4.52E-02 O.OOE+OO Ba-140 2.17E-02 O.OOE+OO Sr-90* 2.19E-02 O.OOE+OO La-141 l.87E-07 0.00E+OO Sr-91 2.60E-02 O.OOE+OO Ce-141 l.08E-06 O.OOE+OO Sr-92 9.28E-03 O.OOE+OO Ce-144 l.99E-04 O.OOE+OO Y-92 4.82E-06 O.OOE+OO Np-239 2.14E-05 O.OOE+OO Total 6.26E+OO 7.46E+02 The adult receives the highest dose of 3 840 millirem, while the child receives the highest thyroid dose of 1150. As the adult whole body dose is more restrictive (380 times the Alert EAL value of 10 millirem, vs. 23 times the 50 millirem value for the thyroid) it is used to establish the set point. Using Equation 4, the concentration resulting in a whole body dose at the Alert EAL level of 10 millirem is 2.6E-03 (µCi/ml).

02/28/2017 Calculation 04-199.001 Page 25 of 40 TEDE vs. Whole Body Dose The ALERT set point of 10 mrem recommended by NEI, is based on a Total Effective Dose Equivalent (TEDE) rather than the Whole Body dose calculated using ODCM equations. The former is based on ICRP 26 dose conversion factors while the latter is based on Reg Guide 1.109 dose conversion factors. To convert the equations of the ODCM to calculate a TEDE rather than a Whole Body Dose, the factor Aij (the site related dose commitment factor) used in Equation 3 must be changed. If the dose conversion factor (DFij) in Equation B 1 is changed from the value listed in Reg Guide 1.109 to one based on the Annual Limit on Intake (ALI) of 1 OCFR20 Appendix B Table 2, then the new Aii will generate a dose calculated in TEDE and Thyroid CDE. The ALI based dose conversion factor can be obtained from: DCF = 5000/(ALI x 1000000) Where: EquationB2 DCF 5000 ALI 106 = Dose conversion factor (millirem/pCi) =Annual TEDE dose limit (millirem) = Stochastic Annual Limit oflntake from 1 OCFR20 Appendix B Table 1 (µCi). = Conversion factor (pCi per µCi) As the results using a TEDE based dose conversion factor are within a factor of 2 for TEDE vs Whole Body, the current ODCM methodology was employed.

' 02/28/2017 Calculation 04-199.001 Page 26 of 40 Appendix C Impact of SBGT Off The calculation assumes SBGT is in operation. However, because SBGT can be isolated, the impact such an isolation would have on the Alert, SAE and GE EAL set points was investigated. It is provided here for information only. The only difference between the LOCA scenario with SBGT on and that with SBGT off is the release rate entered into RASCAL. Whereas, specific values for SBGTRFi were used in Equation A3, this parameter is set to 1 when the SBGT is not in operation. The subsequent release rate entered into RASCAL is Provided in Table C-1. Table C-1 Release Rate for a LOCA with SBGT Off. , Relative Core Relative Core , .. Inventory@ Relative Normalized Inventory@ Relative Normalized . t=O Release Rate Release Rate , t=O Release Rate , Release Rate Nuclide (Ci) (Ci/sec) (Ci/sec) Naclide (Ci) (Ci/sec) (Ci/sec) Co*58 1.38E+02 3.45E-01 l.70E-04 Te-131m 3.84E+03 l.92E+02 9.46E-02 Co-60 l.33E+02 3.32E-01 l.64E-04 Te-132 3.82E+04 l.91E+03 9.40E-01 Kr-85 3.33E+02 3.33E+02 l.64E-01 I-131 2.68E+04 8.03E+03 3.96E+OO Kr-85m 7.38E+03 7.38E+03 3.64E+OO I-132 3.90E+04 1.17E+04 5.76E+OO Kr-87 l.42E+04 l.42E+04 7.0lE+OO I-133 5.51E+04 l.65E+04 8.15E+OO Kr-88 2.01E+04 2.01E+04 9.88E+OO 1*134 6.09E+04 1.83E+04 9.00E+OO Rb-86 6.35E+Ol l.59E+Ol 7.82E-03 I-135 5.17E+04 l.55E+04 7.65E+OO Sr-89 2.68E+04 5.37E+02 2.64E-01 Xe-133 5.48E+04 5.48E+04 2.70E+Ol Sr-90 2.64E+03 5.27E+Ol 2.60E-02 I' Xe-135 2.53E+04 2.53E+04 1.25E+Ol Sr-91 .... 3.37E+04 6.73E+02 3.32E-01 Cs-134 5.35E+03 l.34E+03 6.58E-Ol Sr-92 3.62E+04 7.24E+02 3.57E-01 ,Cs*136 l.86E+03 4.66E+02 2.29E-01 2.81E+03 5.61E-01 2.76E-04 Cs-137 3.47E+03 8.68E+02 4.27E-01 3.44E+04 6.88E+OO 3.39E-03 Ba-139 .. 4.97E+04 9.93E+02 4.89E-01 .** 3.64E+04 7.27E+OO 3.58E-03 Ba-140 4.77E+04 9.55E+02 4.70E-01 Y-93 4.18E+04 8.35E+OO 4.12E-03 La-140 4.92E+04 9.83E+OO 4.84E-03 Zr-95 4.85E+04 9.70E+OO 4.78E-03 Lac141 4.53E+04 9.06E+OO 4.46E-03 Zr*97 4.99E+04 9.99E+OO 4.92E-03 La-142 4.39E+04 8.78E+OO 4.32E-03 Nb-95 4.87E+04 9.74E+OO 4.80E-03 Ce-141 4.53E+04 2.27E+Ol 1.12E-02 Mo-99 5.12E+04 l.28E+02 6.3 lE-02 Ce-143 4.23E+04 2.llE+Ol l.04E-02 Tc-99m 4.54E+04 1.13E+02 5.59E-02 Ce-144 3.68E+04 l.84E+Ol 9.07E-03 Ru-103 4.05E+04 l.01E+02 4.99E-02 Pr-143 4.13E+04 8.27E+OO 4.07E-03 Ru-105 2.71E+04 6.77E+Ol 3.33E-02 Nd-147 l.81E+04 3.61E+OO l.78E-03 Ru-106 l.41E+04 3.52E+Ol l.74E-02 Np-239 5.22E+05 2.61E+02 l.29E-01 Rh-105_ 2.46E+04 6.15E+Ol 3.03E-02 ,Pu-238 9.04E+Ol 4.52E-02 2.23E-05 2.80E+03 l.40E+02 6.88E-02 Pu-239 l.09E+Ol 5.43E-03 2.67E-06 Sb*129 8.52E+03 4.26E+02 2.lOE-01 Pu-240 l.41E+Ol 7.04E-03 3.47E-06 Te-127 2.84E+03 l.42E+02 6.99E-02 Pu-241 4.09E+03 2.05E+OO l.OlE-03 Te-127m 3.70E+02 l.85E+Ol 9.12E-03 Am*241 4.61E+OO 9.22E-04 4.54E-07 Te-129 8.38E+03 4.19E+02 2.06E-Ol I Cmc242 l.09E+03 2.17E-Ol l.07E-04 Te-129m l.24E+03 6.22E+Ol 3.06E-02 Cm-244 5.24E+Ol l.05E-02 5.16E-06 Sum of Nobel Gases: 60.2 Sum oflodines: 34.5 Sum of Particulates: 5.4 As with the case of SBGT on, a RASCAL run was used to determine the dose for a 100 Ci/sec release rate. Equation 1 was then employed to determine the EAL set points. Table C-2 provides the pertinent infonnation from the RASCAL run, while Table C-3 provides the EAL set points.

02/28/2017 Calculation 04-199.001 Page 27 of 40 Table C-2 One Hour Dose from a LOCA with SBGT Off (rem) Distance (miles) 0.1 0.2 0.3 0.5 0.7 1: 1.5 2 ThyroidCDE 2.70E+OO l.90E+Ol 3.00E+Ol 2.40E+Ol l.50E+Ol 8.lOE+OO 4.90E+OO TEDE 6.60E-02 l.61E-01 6.97E-01 l.09E+OO 8.36E-01 5.48E-01 2.98E-Ol l.87E-01 Inhalation CEDE 8.60E-02 6.lOE-01 9.60E-01 7.60E-01 4.SOE-01 2.60E-01 l.60E-01

  • Cloudshine 6.60E-02 7.SOE-02 8.70E-02 l.30E-01 7.60E-02 6.SOE-02 3.SOE-02 2.70E-02 Table C-3 Plant Stack Monitor Set Points for a LOCA with SBGT Off Set Point Dose2 RR1 Dose2 (µCi/sec) (rem) (µCi/sec) (rem). ALERT 2.0E+05 0.05 SAE 2.0E+06 0.5 1.0 E+OS 30 GE 2.0E+07 5 02/28/2017 Attachment 1 Excerpt from EC 24037 ODCM-05.01 Table 1: Gaseous Source Terms (Ai, Ci/yr) Calculated in accordance with NUREG-0016 by using USNRC GALE Code. Calculation 04-199.001 Attachment 1 Calculation Steps Based on ODCM-05.01 Section 2.1.1.B. Stack Isolation Setpoint (X/Q per EC 24037 Reactor Mechanical Gaseous Drywell Si (Gland Seal) Vi Bi Radionuclide Building Vent Gland Sea11 Vacuum Pump Radwaste Purging No Kr-83 (Table 5) Si*Vi (Table 5) Li (Table 4) Kr-83m 0 0 0 0 0 0 2.61E-09 0 3.77E-07 0 Kr-85m 7.10E+01 4.lOE+Ol 0 0 3.00E+OO 1.68E-02 l.39E-04 2.34E-06 2.07E-04 1.46E+03 Kr-85 0 0 0 l.30E+02 0 0 2.lOE-06 0 3.lBE-06 l.34E+03 Kr-87 1.33E+02 1.40E+02 0 0 3.00E+OO 5.75E-02 6.33E-04 3.64E-05 9.52E-04 9.73E+03 Kr-88 2.33E+02 1.40E+02 0 0 3.00E+OO 5.75E-02 l.66E-03 9.54E-05 2.49E-03 2.37E+03 Kr-89 0 6.00E+02 0 0 0 2.46E-01 l.12E-03 2.76E-04 l.68E-03 l.01E+04 Kr-90 0 0 0 0 0 0 1.61E-04 0 2.42E-04 7.29E+03 Xe-131m 0 0 0 4.SOE+Ol 0 0 3.31E-05 0 5.21E-05 4.76E+02 Xe-133m 0 2.00E+OO 0 2.70E+Ol 0 8.21E-04 2.51E-05 2.06E-08 4.09E-05 9.94E+02 Xe-133 3.26E+02 5.60E+Ol 2.30E+03 8.90E+03 6.60E+Ol 2.30E-02* 2.61E-05 6.00E-07 4.0SE-05 3.06E+02 Xe-13Sm 6.96E+02 l.70E+Ol 0 0 4.60E+Ol 6.98E-03 3.34E-04 2.33E-06 5.06E-04 7.11E+02 Xe-135 7.09E+02 l.50E+02 3.50E+02 0 3.40E+Ol 6.16E-02 2.24E-04 l.38E-05 3.37E-04 l.86E+03 Xe-137 0 7.30E+02 0 0 0 3.00E-01 9.99E-05 2.99E-05 l.SlE-04 l.22E+04 Xe-138 l.41E+03 S.60E+02 0 0 7.00E+OO 2.30E-01 9.90E-04 2.28E-04 l.49E-03 4.13E+03 Xe-139 0 0 0 0 0 0 S.79E-05 0 8.69E-05 6.52E+04 Ar-41 0 0 0 0 0 0 1.20E-03 0 1.SOE-03 2.69E+03 Total 3.58E+03 2.44E+03 2.65E+03 9.10E+03 l.62E+02 1 6.84E-04 1Note that the setpoint calculations are based on the Gland Seal source terms, excluding Kr-83m (set to 0), which is the most limiting case Qt (body) 7.31E+05 Qt (skin) l.80E+06 HHSP 3.65E+05 µCi/sec Page 28 of40 Li*(X/Q)s+l.1
  • Si*(Li*(X/Q)s+ Bi 1.1 *Bi) 4.15E-07 0 3.27E-04 5.50E-06 9.46E-05 0 1.71E-03 9.82E-05 2.90E-03 l.67E-04 2.53E-03 6.24E-04 7.62E-04 0 8.97E-05 0 l.13E-04 9.24E-08 6.57E-OS 1.SlE-06 6.05E-04 4.22E-06 4.97E-04 3.06E-05 9.96E-04 2.98E-04 l.92E-03 4.41E-04 4.53E-03 0 2.16E-03 0 1.67E-03 02/28/2017 ODCM-05.01 Table 1: Gaseous Source Terms (Ai, Ci/yr) Calculated in accordance with NUREG-0016 by using USN RC GALE Code. Reactor Mechanical Gaseous Drywell Calculation 04-199.001 Attachment 1 Radionuclide Building Vent Gland Seal Vacuum Pump Radwaste Purging Si (RBV) Kr-83m 0 2.30E+Ol 0 0 0 Kr-85m 7.lOE+Ol 4.lOE+Ol 0 0 3.00E+OO Kr-85 0 0 0 1.30E+02 0 Kr-87 1.33E+02 1.40E+02 0 0 3.00E+OO Kr-88 2.33E+02 1.40E+02 0 0 3.00E+OO Kr-89 0 6.00E+02 0 0 0 Kr-90 0 0 0 0 0 Xe-131m 0 0 0 4.50E+Ol 0 Xe-133m 0 2.00E+OO 0 2.70E+Ol 0 Xe-133 3.26E+02 5.60E+Ol 2.30E+03 8.90E+03 6.60E+Ol Xe-135m 6.96E+02 1.70E+Ol 0 0 4.60E+Ol Xe-135 7.09E+02 1.50E+02 3.50E+02 0 3.40E+Ol Xe-137 0 7.30E+02 0 0 0 Xe-138 1.41E+03 5.60E+02 0 0 7.00E+OO Xe-139 0 0 0 0 0 Ar-41 0 0 0 0 0 Total 3.S8E+03 2.46E+03 2.65E+03 9.10E+03 1.62E+02 Qt (body) 2.S9E+04 Qt (skin) 9.55E+04 HHSP 1.30E+04 µCi/sec eeacim 811ildiog 0 1.98E-02 0 3.72E-02 6.SlE-02 0 0 0 0 9.llE-02 1.95E-01 1.98E-01 0 3.94E-01 0 0 1 Ki Calculation Steps Based on ODCM-05.01 Section 2.1.1.A. Reactor Building Vent Alarm Setpoint (X/Q per EC24037) (Table 4) Si*Ki Li (Table 4) Mi (Table 4) 7.56E-02 0 0 1.93E+Ol 1.17E+03 2.32E+Ol 1.46E+03 1.23E+03 1.61E+Ol 0 1.34E+03 1.72E+Ol 5.92E+03 2.20E+02 9.73E+03 6.17E+03 1.47E+04 9.57E+02 2.37E+03 1.52E+04 1.66E+04 0 1.01E+04 1.73E+04 1.56E+04 0 7.29E+03 1.63E+04 9.15E+Ol 0 4.76E+02 1.56E+02 2.S1E+02 0 9.94E+02 3.27E+02 2.94E+02 2.68E+Ol 3.06E+02 3.S3E+02 3.12E+03 6.07E+02 7.11E+02 3.36E+03 1.81E+03 3.59E+02 l.86E+03 1.92E+03 1.42E+03 0 1.22E+04 1.51E+03 8.83E+03 3.48E+03 4.13E+03 9.21E+03 5.02E+03 0 6.52E+04 5.28E+03 8.84E+03 0 2.69E+03 9.30E+03 5.67E+03 Page 29 of40 Si*(Li+l.l Li+l.1 *Mi *Mi) 2.12E+Ol 0 2.81E+03 6.E+Ol 1.36E+03 0 1.65E+04 6.E+02 l.91E+04 1.E+03 2.91E+04 0 2.52E+04 0 6.48E+02 0 1.35E+03 0 6.94E+02 6.E+Ol 4.41E+03 9.E+02 3.97E+03 8.E+02 1.39E+04 0 1.43E+04 6.E+03 7.10E+04 0 1.29E+04 0 9.24E+03 2/28/2017 Calculation 04-199.001 Attachment 2 Attachment 2 Excerpt from EC 26667 Source Term (From ODCM-04.01 Table 1) Ai Radioactivity MPC Source Term (Ci/yr) (µCi/ml) S; S;/MPC; H-3* 2.lE+Ol lE-02 8.77E-01 8.77E+Ol Na-24 1.7E-01 5E-04 7.lOE-03 1.42E+Ol Mn-54 2.6E-03 3E-04 1.09E-04 3.62E-01 Mn-56 2.7E-01 7E-04 1.13E-02 1.61E+Ol Fe-59 8.lE-04 lE-04 3.38E-05 3.38E-01 Co-58 9.3E-03 2E-04 3.88E-04 l.94E+OO Co-60 2.0E-02 3E-05 8.35E-04 2.78E+Ol Cu-64 5.4E-01 2E-03 2.25E-02 1.13E+Ol Zn-65 5.3E-03 5E-05 2.21E-04 4.42E+OO Zn-69m 3.7E-02 6E-04 1.54E-03 2.57E+OO Br-83 1.4E-02 9E-03 5.84E-04 6.49E-02 Sr-89* 2.8E-03 8E-05 1.17E-04 1.46E+OO Sr-90* 1.7E-04 5E-06 7.lOE-06 1.42E+OO Sr-91 6.4E-02 2E-04 2.67E-03 1.34E+Ol Sr-92 5.8E-02 4E-04 2.42E-03 6.0SE+OO Y-92 1.0E-01 4E-04 4.17E-03 l.04E+Ol Y-93 6.6E-02 2E-04 2.76E-03 1.38E+Ol Mo-99 5.0E-02 2E-04 2.09E-03 l.04E+Ol 1-131 1.3E-01 lE-05 5.43E-03 5.43E+02 1-132 1.3E-01 lE-03 5.43E-03 5.43E+OO 1-133 4.0E-01 7E-05 1.67E-02 2.39E+02 1-134 6.4E-02 4E-03 2.67E-03 6.68E-01 1-135 2.5E-01 3E-04 1.04E-02 3.48E+Ol Cs-134 8.3E-02 9E-06 3.46E-03 3.85E+02 Cs-136 2.6E-02 6E-05 1.09E-03 1.81E+Ol Cs-137 1.2E-01 lE-05 5.0lE-03 5.01E+02 Cs-138 1.5E-01 4E-03 6.26E-03 l.57E+OO Ba-140 1.lE-02 8E-05 4.59E-04 5.74E+OO La-141 5.7E-03 5E-04 2.38E-04 4.76E-01 Ce-141 8.5E-04 3E-04 3.55E-05 1.18E-01 Ce-144 5.3E-03 3E-05 2.21E-04 7.37E+OO Np-239 1.7E-01 2E-04 7.lOE-03 3.55E+Ol Total 2.40E+o1 100.00 2.00E+03 *Denotes Hard to Detect nuclide (fl-emitter only) Discharge Canal Rad Monitor Inputs L(S/MPC) sh E SF Background Calculations Cd(µCi/ml) Cm(µCi/ml) C.R. (cps) 2.00E+03 8. 77E-01 Fraction of total activity due to Hard to Detect Nuclides l .30E-07 Detector Efficiency 0.80 Setpoint Safety Factor Background C.R. 5.00E-04 Maximum Concentration 6.16E-05 Max Concentration of gamma emitters 3.79E+02 cps (Includes 0.8 Safety Factor) Page 30 of 40 _J 2/28/2017 Calculation 04-199.001 Attachment 2 Source Term (From ODCM-04.01 Table 1) Ai Radioactivity MPC Source Term (Ci/yr) (µCi/ml) S; S;/MPC1 H-3* 2.lE+Ol lE-02 S.77E-01 S.77E+Ol Na-24 1.7E-01 SE-04 7.lOE-03 1.42E+Ol Mn-S4 2.6E-03 3E-04 1.09E-04 3.62E-01 Mn-S6 2.7E-01 7E-04 1.13E-02 l.61E+01 Fe-S9 S.lE-04 lE-04 3.3SE-OS 3.38E-Ol Co-S8 9.3E-03 2E-04 3.88E-04 1.94E+OO Co-60 2.0E-02 3E-OS 8.3SE-04 2.78E+Ol Cu-64 S.4E-01 2E-03 2.2SE-02 1.13E+Ol Zn-6S S.3E-03 SE-OS 2.21E-04 4.42E+OO Zn-69m 3.7E-02 6E-04 1.S4E-03 2.S7E+OO Br-83 l.4E-02 9E-03 S.84E-04 6.49E-02 Sr-89* 2.SE-03 SE-OS 1.17E-04 1.46E+OO Sr-90* 1.7E-04 SE-06 7.lOE-06 1.42E+OO Sr-91 6.4E-02 2E-04 2.67E-03 1.34E+Ol Sr-92 S.8E-02 4E-04 2.42E-03 6.0SE+OO V-92 1.0E-01 4E-04 4.17E-03 1.04E+01 V-93 6.6E-02 2E-04 2.76E-03 l.38E+Ol Mo-99 S.OE-02 2E-04 2.09E-03 1.04E+01 1-131 1.3E-01 lE-OS S.43E-03 S.43E+02 1-132 1.3E-01 lE-03 S.43E-03 S.43E+OO 1-133 4.0E-01 7E-OS 1.67E-02 2.39E+02 1-134 6.4E-02 4E-03 2.67E-03 6.68E-01 l-13S 2.SE-01 3E-04 1.04E-02 3.48E+Ol Cs-134 8.3E-02 9E-06 3.46E-03 3.8SE+02 Cs-136 2.6E-02 6E-OS 1.09E-03 1.81E+Ol Cs-137 1.2E-01 lE-OS S.OlE-03 S.01E+02 Cs-138 1.SE-01 4E-03 6.26.E-03 l.S7E+OO Ba-140 1.lE-02 SE-OS 4.S9E-04 S.74E+OO La-141 S.7E-03 SE-04 2.3SE-04 4.76E-Ol Ce-141 8.SE-04 3E-04 3.SSE-OS l.18E-01 Ce-144 S.3E-03 3E-OS 2.21E-04 7.37E+OO Np-239 1.7E-01 2E-04 7.lOE-03 3.SSE+Ol Total 2.40E+Ol 100.00 2.00E+03 Page 31of40
  • Denotes Hard to Detect nuclide (fl-emitter only) Service Water Rad Monitor Inputs L(SJMPq sh E SF Background Calculations Ci(µCi/ml) Cm(µCi/ml) C.R. (cps) 2.00E+03 0.877 Fraction of total activity due to Hard to Detect Nuclides 4.30E-07 Detector Efficiency 0.80 Setpoint Safety Factor Background C.R.
  • 5.00E-04 Maximum Concentration 6.16E-05 Max Concentration of gamma emitters 1.15E+02 cps (Includes 0.8 Safety Factor) 2/28/2017 Calculation 04-199.001 Attachment 2 Source Term (From ODCM-04.01Table1) Ai Radioactivity MPC Source Term (Ci/yr) (µCi/ml) S; S;/MPC; H-3* 2.lE+Ol lE-02 8.77E-01 8.77E+Ol Na-24 1.7E-01 5E-04 7.lOE-03 1.42E+Ol Mn-54 2.6E-03 3E-04 l.09E-04 3.62E-01 Mn-56 2.7E-01 7E-04 l.13E-02 1.61E+Ol Fe-59 8.lE-04 lE-04 3.38E-05 3.38E-01 Co-58 9.3E-03 2E-04 3.88E-04 1.94E+OO Co-60 2.0E-02 3E-05 8.35E-04 2.78E+Ol Cu-64 5.4E-01 2E-03 2.25E-02 1.13E+Ol Zn-65 5.3E-03 5E-05 2.21E-04 4.42E+OO Zn-69m 3.7E-02 6E-04 1.54E-03 2.57E+OO Br-83 1.4E-02 9E-03 5.84E-04 6.49E-02 Sr-89* 2.8E-03 8E-05 1.17E-04 1.46E+OO Sr-90* 1.7E-04 5E-06 7.lOE-06 1.42E+OO Sr-91 6.4E-02 2E-04 2.67E-03 l.34E+Ol Sr-92 5.8E-02 4E-04 2.42E-03 6.05E+OO Y-92 1.0E-01 4E-04 4.17E-03 1.04E+Ol Y-93 6.6E-02 2E-04 2.76E-03 1.38E+Ol Mo-99 5.0E-02 2E-04 2.09E-03 1.04E+Ol 1-131 1.3E-01 lE-05 5.43E-03 5.43E+02 1-132 l.3E-01 lE-03 5.43E-03 5.43E+OO 1-133 4.0E-01 7E-05 1.67E-02 2.39E+02 1-134 6.4E-02 4E-03 2.67E-03 6.68E-01 1-135 2.SE-01 3E-04 1.04E-02 3.48E+Ol Cs-134 8.3E-02 9E-06 3.46E-03 3.85E+02 Cs-136 2.6E-02 6E-05 1.09E-03 1.81E+Ol Cs-137 1.2E-01 lE-05 5.0lE-03 5.01E+02 Cs-138 l.5E-01 4E-03 6.26E-03 1.57E+OO Ba-140 1.lE-02 8E-05 4.59E-04 5.74E+OO La-141 5.7E-03 5E-04 2.38E-04 4.76E-01 Ce-141 8.5E-04 3E-04 3.55E-05 l.18E-01 Ce-144 5.3E-03 3E-05 2.21E-04 7.37E+OO Np-239 1.7E-01 2E-04 7.lOE-03 3.55E+Ol Total 2.40E+ol 100.00% 2.00E+03
  • Denotes Hard to Detect nuclide (B-emitter only) ITBNWS Inputs Calculations Ct Cm (µCi/ml) 2.00E+03 0.877 Fraction of total activity due to Hard to Detect Nuclides 3.SOE-09 Detector Efficiency (µCi/ml per cpm) 0.80 Setpoint Safety Factor 5.00E-04 Maximum Concentration 6.16E-05 Max Concentration of gamma emitters l.41E+04 cpm(Includes 0.8 Safety Factor) Page 32 of 40 2/28/2017 Calculation 04-199.001 Attachment 3 Attachment 3 RASCAL Run Reactor Building Vent St1mmary Report Case title: CA-04-199-REV 1 FHA Run date/time: 2017/02/01 0828 Maximum Dose Values (rem) -Close-In Dist from release miles 0.1 0.2 0.3 0.5 0.7 (kilometers) (0.16) (0.32) (0.48) (0.8) (1.13) Total EDE 2.3E+OO 6.6E-01 3.2E-01 1.3E-01 7.1E-02 Thyroid COE 5.8E+01 1.6E+01 7.7E+OO 3.0E+OO 1.7E+OO Inhalation CEDE 1.8E+OO 5.0E-01 2.4E-01 9.2E-02 5.1E-02 Cloudshine 6.5E-02 3.5E-02 2.2E-02 1.1 E-02 7.2E-03 4-day Groundshine 4.6E-01 1.3E-01 6.1E-02 2.4E-02 1.3E-02 Inter Phase 1st Yr 1.5E+OO 4.1 E-01 2.0E-01 7.6E-02 4.2E-02 Inter Phase 2nd Yr *** *** *** *** *** Notes:
  • Doses exceeding EPA PAGs are underlined.
  • Inhalation dose factors used: ICRP 26/30 * *'** indicates values less than 1 mrem *To view all values -use Detailed Results I Numeric Table *Total EDE= CEDE Inhalation + Cloudshine + 4-Day Grouridshine Case Summary Event Type Nuclear Power Plant Case description 1. (1.61) 3.7E-02 8.6E-01 2.6E-02 4.1E-03 6.8E-03 2.2E-02 *** 1.5 (2.41) 1.8E-02 4.2E-01 1.3E-02 2.1E-03 3.3E-03 1.1E-02 *** Defined case to determine Reactor Building vent set points for EAL declarations. Location Name: Monticello City, county, state: Lat I Long I Elev: Time zone: Population (2010): Reactor Parameters Reactor power: Peak rod burn-up: Containment type: Containment volume: Design pressure: Design leak rate: Coolant mass: Assemblies in core: Source Term Type: Measurement desc.: Sample rate units: Sample rate units: Sample period: Start: Monticello, Wright, MN 45.3333° N, 93.8483° W, 283 m Central 2,009 / 23,242156,655 (2 / 5 / 10 mi) 1775 MWt 30000 MWd I MTU BWR Mark I 2.42E+05 ft3 6 lb/in2 0.50 Id 8.35E+04 kg 484 Effluent Release Rates -by Nuclide USAR Table 14.7-24 T=24 µCi/s µCits 2017/01/19 Page 33 of 40 2. (3.22) 1.1 E-02 2.4E-01 7.4E-03 1.2E-03 1.9E-03 6.1E-03 ***

2/28/2017 Summary Report Stop: Nuclide Xe-133 Xe-135 Kr-85 Kr-85m Kr-87 Kr-88 1-131 1-132 1-133 1-134 1-135 Release Pathway Type: Release height Release timings To atmosphere start: 00:00 2017/01/19 01:00 µCi/s 8.99E+07 7.62E+06 1.25E+06 3.38E+05 5.48E+01 1.07E+05 3.68E+05 4.22E+02 3.71E+04 5.07E-03 6.22E+04 Calculation 04-199.001 Attachment 3 Direct to Atmosphere 10. m To atmosphere duration: 2017/01/19 00:00 O days, and 01 :00 Meteorology Type: Dataset name: Dataset desc: Summary of data at release point Actual Observations CA-04-199-R1 RB Vent Obs/fcsts for Monticello Type Dir deg Speed Stab mph class Temp Precip °F 2017/01/19 00:00 Obs 338 14.0 D None Dataset options: Case title: End of calculations: Distance of calculation: Close-in distances: Analyst name: Inhalation dose factors: Est. missing stability using: Wind speed, time of day, etc. Modify winds for topography: Yes CA-04-199 R1 REV 1 FHA 2017/01/19 04:00 Start of release to atmosphere + 4 h Close-in +to 10 miles 0.1, 0.2, 0.3, 0.5, 0.7, 1.0, 1.5, 2.0 miles Dose Analyst ICRP 26/30 Page 34 of 40 2/28/2017 Calculation 04-199.001 Attachment 4 Attachment 4 RASCAL Run for Plant Stack SBGT Off Summary Report Case title: RASCAL Run for Plant Stack SBGT Off Run date/time: 2017/02/02 13:55 Maximum Dose Values (rem) -Close-In Dist from release miles 0.1 0.2 0.3 0.5 0.7 (kilometers) (0.16) (0.32) (0.48) (0.8) (1.13) Total EDE 6.6E-02 2.3E-01 1.2E+OO 1.9E+OO 1.5E+OO Thyroid COE *** 2.7E+OO 1.9E+01 3.0E+01 2.4E+01 Inhalation CEDE *** 8.6E-02 6.1 E-01 9.6E-01 7.6E-01 Cloudshine 6.6E-02 7.5E-02 8.7E-02 1.3E-01 7.6E-02 4-day Groundshine *** 6.9E-02 4.9E-01 7.7E-01 6.1 E-01 Inter Phase 1st Yr *** 1.1E-01 8.0E-01 1.3E+OO 1.0E+OO Inter Phase 2nd Yr *** 9.1E-03 1.0E-01 8.1E-02 Notes:

  • Doses exceeding EPA PAGs are underlined.
  • Inhalation dose factors used: ICRP 26/30 * *** indicates values less than 1 mrem *To view all values -use Detailed Results I Numeric Table
  • Total EDE = CEDE Inhalation + Cloudshine + 4-Day Groundshine Case Summary Event Type Nuclear Power Plant Case description This is a RASCAL run to Determine EAL set point. CA-04-199 R1 Location City, county, state: Lat I Long I Elev: Time zone: Population (2010): Reactor Parameters Reactor power: Peak rod burn-up: Containment type: Containment volume: Design pressure: Design leak rate: Coolant mass: Assemblies in core: Source Term Type: Shutdown: Sample taken: Release rates Noble gases: Total Iodines: Name: Monticello Monticello, Wright, MN 45.3333° N, 93.8483° W, 283 m Central 2,009 / 23,242156,655 (2 / 5 / 10 mi) 1775 MWt 30000 MWd I MTU BWR Mark I 2.42E+05 ft' 6 lb/in2 0.50 Id 8.35E+04 kg 484 Effluent Release Rates -by Mixtures No 2017/02/02 00:00 6.02E+01 Cits 3.45E+01 Cits 1. (1.61) 9.4E+OO 1.5E+01 4.8E-01 6.8E-02 3.9E-01 6.4E-01 5.2E-02 Page35 of 40 1.5 2. (2.41) (3.22) 5.0E-01 3.1 E-01 8.1 E+OO 4.9E+OO 2.6E-01 1.6E-01 3.8E-02 2.7E-02 2.1 E-01 1.2E-01 3.4E-01 2.1 E-01 2.7E-02 1.7E-02 2/28/2017 Summary Report Particulates Release Pathway Type: Release height: Release timings To atmosphere start: 5.30E+OO Ci/s Calculation 04-199.001 Attaclnnent 4 Direct to Atmosphere 100. m To atmosphere duration: 2017/02/02 00:00 0 days, and 01 :OO Meteorology Type: Dataset name: Dataset desc: Summary of data at release point: Actual Observations MONT 2017-02-02 1226 Obs/fcsts for Monticello Type Dir deg Speed Stab mph class Temp Precip °F 2017/01/19 00:00 Obs 338 14.0 D None Dataset options: Case title: End of calculations: Distance of calculation: Close-in distances: Analyst name: Inhalation dose factors: Est. missing stability using: Wind speed, time of day, etc. Modify winds for topography: Yes RASCAL Run for Plant Stack SBGT Off 2017/02/02 04:00 Start of release to atmosphere + 4 h Close-in+ to 10 miles 0.1, 0.2, 0.3, 0.5, 0.7, 1.0, 1.5, 2.0miles Dose Analyst ICRP 26/30 Page 36 of 40 2/28/2017 Calculation 04-199.001 Attachment 5 Attachment 5 RASCAL Run for Plant Stack SBGT On Summary Report Cc:1se title: RASCAL Run for Plant Stack SBGT On Run date/time: 2017/02/0214:17 Maximum Dose Values (rem) -Close-In Dist from release miles 0.1 0.2 0.3 0.5 (kilometers) (0.16) (0.32) (0.48) (0.8) Total EDE 8.3E-02 2.8E-01 4.4E-01 Thyroid CDE *** 5.5E-01 3.9E+OO 6.2E+OO Inhalation CEDE 1. 7E-02 1.2E-01 2.0E-01 Cloudshine 4.5E-02 5.2E-02 6.0E-02 8.7E-02 4-day Groundshine *** 1.4E-02 9.9E-02 1.6E-01 Inter Phase 1st Yr *** 2.1 E-02 1.5E-01 2.3E-01 Inter Phase 2nd Yr *** *** 2.4E-03 3.9E-03 Notes:
  • Doses exceeding EPA PAGs are underlined. 0.7 (1.13) 3.3E-01 4.9E+OO 1.6E-01 5.2E-02 1.2E-01 1.8E-01 3.1E-03
  • dose factors used: ICRP 26/30 * **** indicates values less than 1 mrem
  • To view all values -use Detailed Results I Numeric Table
  • Total EDE = CEDE Inhalation + Cloudshine + 4-Day Groundshine Case Summary Event Type Nuclear Power Plant description This is a RASCAL run to Determine EAL set point. CA-04-199 R1 Location City, county, state: Lat I Long I Elev: Time zone: Population (2010): Reactor Parameters Reactor power: Peak rod burn-up: Containment type: Containment volume: Design pressure: Design leak rate: Coolant mass: Assemblies in core: Source Term Type: Shutdown: Sample taken: Release rates Noble gases: Total Iodines: Name: Monticello Monticello, Wright, MN 45.3333° N, 93.8483° W, 283 m Central 2,009 I 23,242 I 56,655 (2 I 5 I 10 mi) 1775 MWt 30000 MWd I MTU BWR Mark I 2.42E+05 ft3 6 lb/in2 0.50 Id 8.35E+04 kg 484 Effluent Release Rates -by Mixtures No 2017 /02/02 00: 00 9.19E+01 Ci/s 7.90E+01 Ci/s 1. (1.61) 2.2E-01 3.1E+OO 9.9E-02 4.6E-02 7.9E-02 1.2E-01 2.0E-03 Page 37 of 40 1.5 2. (2.41) (3.22) 1.2E-01 7.7E-02 1.6E+OO 1.0E+OO 5.2E-02 3.2E-02 2.6E-02 1.9E-02 4.2E-02 2.6E-02 6.2E-02 3.8E-02 1.0E-03 ***

2/28/2017 Summary Report Particulates Release Pathway Type: Release height: Release timings To atmosphere start: 5.30E+OO Ci/s Calculation 04-199.001 Attachment 5 Direct to Atmosphere 100. m To atmosphere duration: 2017/02/02 00:00 O days, and 01 :00 Meteorology Type: Dataset name: Dataset desc: Summary of data at release point: Actual Observations MONT 2017-02-02 1226 Obs/fcsts for Monticello Type Dir deg Speed Stab mph class Temp Precip °F 2017/02/02 00:00 Obs 338 14.0 D None Dataset options: Calculations Case title: End of calculations: Distance of calculation: Close-in distances: Analyst name: Inhalation dose factors: Est. missing stability using: Wind speed, time of day, etc. Modify winds for topography: Yes RASCAL Run for Plant Stack SBGT On 2017/02/02 04:00 Start of release to atmosphere + 4 h Close-in + to 10 miles 0.1, 0.2, 0.3, 0.5, 0.7, 1.0, 1.5, 2.0 miles Dose Analyst ICRP 26/30 Page 38 of 40 2/28/2017 Calculation 04-199.001 Attachment 6 Page 39 of 40 Attachment 6 Relationship of Reactor Building Exhaust Plenum Monitor Trip Point to Effluent Monitor Release Rate for FHA Ar-41 Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-137 Xe-138 Xe-139 Plenum room Volume (61'0"x 32'0" x 15'8"} Response Factor (Ki Total Body Ki converted to (mrem/yr per mrem/hr per µCi/m3} uCi/cc} 8.84E+03 1.01E+06 7.56E-02 8.62E+OO 1.61E+01 1.84E+03 1.17E+03 1.33E+05 5.92E+03 6.75E+05 1.47E+04 1.68E+06 1.66E+04 1.89E+06 1.56E+04 1.78E+06 9.15E+01 1.04E+04 2.94E+02 3.35E+04 2.51E+02 2.86E+04 1.81E+03 2.06E+05 3.12E+03 3.56E+05 1.42E+03 1.62E+05 8.83E+03 1.01E+06 5.02E+03 5.73E+05 3.06E+04 cubic feet Overall Dose Rate/ Response Factor Source Term (From USAR-14.07, Relative Source (mrem/hr per Ci/MWth} Term µCi/cc} 0.0% 0.00E+OO 0.0% O.OOE+OO 3.330E+02 0.6% 1.16E+01 1.800E+02 0.3% 4.56E+02 2.920E-02 0.0% 3.75E-01 5.740E+01 0.1% 1.83E+03 0.0% 0.00E+OO 0.0% O.OOE+OO 0.0% O.OOE+OO 4.800E+04 91.2% 3.06E+04 0.0% 0.00E+OO 4.070E+03 7.7% 1.60E+04 0.0% O.OOE+OO 0.0% O.OOE+OO 0.0% O.OOE+OO 0.0% 0.00E+OO 52640.4292 100.0% 4.88E+04 (Dimensions based on Drawing NF-36308 and estimated height based on building elevations}

2/28/2017 Geometry Factor Concentration to reach trip point 26 mR/hr. Release Rate (µCi/sec@ Nominal Flow} Ratio of dose to 35.8 infinite plume dose 1.90E-02 µCi/cc Calculation 04-199.001 Attachment 6 Page 40 of 40 Based on Equation 9 in Nuclear Power Plant Control Room Ventilation System Design for Meeting General Criterion 19 (K. G. Murphy and Dr. K. M. Campe}, as referenced by Cale CA-94-009. Note that this is based on 0.733 MeV average gamma energy and may not apply to all noble gas source terms. 1.08E+06 µCi/sec @120,000 cfm

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