Text

South Texas Project, Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Emergency Action Level Scheme Change
	ML15068A045
Person / Time
Site:	South Texas
Issue date:	02/26/2015
From:	Capristo A; South Texas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NOC-AE-15003226, STI: 34060108, TAC MD4195, TAC MD4196
	Download: ML15068A045 (464)
	v • d • e

Nuclear Operating CompanySouth Texas Prolect Electric Generating Station PO. lat 289 Wadsworth. Teas 77483 -vV/-- --February 26, 2015NOC-AE-1500322610 CFR 50.90File No. G25U. S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, DC 20555-0001South Texas ProjectUnits I and 2Docket Nos. STN 50-498, STN 50-499Response to Request for Additional Information -South Texas Project (STP), Units 1 and 2 License Amendment Request forEmergency Action Level Scheme Change (TACs MD4195 and MF4196)References:1. Letter; G. T. Powell to USNRC Document Control Desk; "License Amendment Requestfor Revision to Unit 1 and Unit 2 Emergency Action Levels;" NOC-AE-14003087; datedMay 15, 2014 (ML14164A341)2. E-mail; Balwant Singal to Lance Sterling; "Request for Additional Information (RAI) -Revised Emergency Action Levels for South Texas Project, Units 1 and 2 (TACsMD4195 and MF4196);" dated December 18, 2014 (ML14352A1 80)3. Letter; A. Capristo to USNRC Document Control Desk; "Response to Request forAdditional Information -South Texas Project (STP), Units 1 and 2 License AmendmentRequest for Emergency Action Level Scheme Change (TACs MD4195 and MF4196);"NOC-AE-15003214; dated February 11, 2015By Reference 1, STP Nuclear Operating Company (STPNOC) requested approval of a LicenseAmendment Request for revision to Unit 1 and 2 Emergency Action Levels. By Reference 2, theNRC staff requested additional information (RAI) to complete its review. STPNOC responded tothe RAI in Reference 3 with the exception of RAI-04. STPNOC's response to RAI-04 inReference 2 is provided in Attachment 1 to this letter. Based on a phone call with NRC stafffollowing transmittal of Reference 3, STPNOC is also including in Attachment 1 revisedresponses to RAI-01, RAI-06 and RAI-12.In Reference 3, STPNOC noted that several discrepancies were found in the calculation thatwas performed to determine EAL threshold values for Abnormal Rad Levels. In the process ofresolving the discrepancy, a review was conducted of calculations that were performed tosupport the proposed revised EALs. As a result, six calculations were revised; two of the revisedcalculations affect STPNOC's response to RAI-04 and RAI-10. The revised response to RAI-10is included in Attachment 1. Revision bars in Attachment 1 indicate changes to the RAIresponse provided in Reference 3 for RAI-01, RAI-04, RAI-06, RAI-10, and RAI-12.STI: 34060108AYqo NOC-AE-1 5003226Page 2 of 3A clean copy and a redline markup of the STPEGS Emergency Action Level Technical BasesDocument is included in Attachments 2 and 3, respectively. Attachment 4 provides revisions tothe STPEGS Emergency Action Level Deviation, Difference and Justification Matrix provided inReference 1. Attachment 5 contains revisions to two calculations that are being provided assupporting documents.The No Significant Hazards Consideration determination provided in Reference I is not alteredby the additional information provided in this correspondence.There are no commitments in this letter.If there are any questions, please contact Drew Richards at (361) 972-7666 or me at(361) 972-7697.I declare under penalty of perjury that the foregoing is true and correct.Executed on __ -_____- __________Date Aldo CapristoExecutive Vice PresidentChief Administrative Officeramr

Attachment:

1. Response to Request for Additional Information -South Texas Project (STP), Units 1 and 2License Amendment Request for Emergency Action Level Scheme Change2. STPEGS Emergency Action Level Technical Bases Document -clean copy3. STPEGS Emergency Action Level Technical Bases Document -redline markup4. STPEGS Emergency Action Level Deviation, Difference and Justification Matrix -revisionsonly5. Supporting documents NOC-AE-15003226Page 3 of 3cc:(paper copy)(electronic copy)Regional Administrator, Region IVU.S. Nuclear Regulatory Commission1600 East Lamar BoulevardArlington, TX 76011-4511Lisa M. RegnerSenior Project ManagerU.S. Nuclear Regulatory CommissionOne White Flint North (MS 8 G9A)11555 Rockville PikeRockville, MD 20852NRC Resident InspectorU. S. Nuclear Regulatory CommissionP. 0. Box 289, Mail Code: MN1 16Wadsworth, TX 77483Morgan, Lewis & Bockius LLPSteve FrantzU.S. Nuclear Regulatory CommissionLisa M. RegnerNRG South Texas LPJohn RaganChris O'HaraJim von SuskilCPS EnergqyKevin PolioCris EugsterL. D. BlaylockCrain Caton & James, P.C.Peter NemethCity of AustinCheryl MeleJohn WesterTexas Dept. of State Health ServicesRichard A. RatliffRobert Free Attachment IResponse to Request for Additional Information -South Texas Project(STP), Units 1 and 2 License Amendment Request for Emergency ActionLevel Scheme Change Attachment 1NOC-AE-15003226Page 1 of 5REQUEST FOR ADDITIONAL INFORMATIONSOUTH TEXAS PROJECT, UNITS 1 AND 2LICENSE AMENDMENT REQUEST FOREMERGENCY ACTION LEVEL SCHEME CHANGEDOCKET NUMBERS 50-498 AND 499The NRC staff requires the following additional information to complete its review of the request:RAI-01Because the information in the basis document can affect emergency classification decisionmaking, NEI 99-01, Revision 6, Section 4.6 contains an expectation that the basis document willbe evaluated in accordance with the provisions of Title 10 of the Code of Federal Regulations(10 CFR), Paragraph 50.54(q). Please explain how this expectation will be clearly identified toensure appropriate reviews are conducted for any potential changes to the basis document.Note: The NRC staff does understand that appropriate administrative controls are in place toensure that changes to Abnormal and Emergency Operating Procedures are screened todetermine if an evaluation pursuant to 10 CFR 50.54(q) is required. This RAI is intendedto ensure similar controls are in place for the STP EAL Basis Document.STPNOC RESPONSE TO RAI-01Administrative controls that address evaluating changes to the STP EAL Technical Bases inaccordance with 1OCFR50.54 (q) already exist in OPGP05-ZV-0010, Emergency Plan Change.A note has been added to the cover of the STP EAL Technical Bases stating the following:NOTE: Changes to this document require a review under 10CFR50.54 (q) asdirected by OPGP05-ZV-0010, Emergency Plan Chang Attachment 1NOC-AE-15003226Page 2 of 5RAI-04The proposed EALs RU1 appears to be a different base-value than the escalation values (RA1,etc.). Please justify further or revise accordingly. If the values are correct, please note thediscrepancy in the basis section.STPNOC RESPONSE TO RAI-04STPNOC maintains that the RU1 and RA1 values for the Unit Vent radiation monitor (RT-8010B) are consistent with the guidelines of NEI 99-01 Rev.6 and the current EAL scheme atSTP. STP does not have Main Steam Line radiation monitor (RT-8046 thru 8049) RU1 and RA1values in the current EAL scheme for comparison. The proposed STP RU1 thru RG1 EALswere compared to another US PWR (Comanche Peak) and were found to be similar. STPNOChas not identified any discrepancies.The STP Radiation Monitoring system is a distributed microprocessor based system consistingof radiation detectors, an associated microprocessor control panel (RM-80), radiation monitoringcomputers (RM-1 1), and digital display modules (RM-23) for the Process and EffluentsRadiation Monitoring System (PERMS) and the Area Radiation Monitoring System (ARMS).According to the STP UFSAR, the Unit Vent radiation monitor (RT-8010B) has a range from20 pci/sec to 2E+16 pci/sec and the Main Steam Line radiation monitors have a range from1.4E-02 pci/cc to 1.4E+06 pci/cc.The hand calculated and STAMPEDE (software) calculated values for the RU1, RA1, RS1 andRG1 are contained in Calculation No. STPNOC013-CALC-002 Revision 2, Table 2.1. Table 2.1appears in section 2.0, Summary of Results and also in Attachment 1 -Hand Calculations.Attachment 1, Summary of Results states the following: "Table 2.1 is displayed again belowshowing the results from all the calculations. The minor difference is due to STAMPEDE usingdecay factors over a one hour period after shutdown. This also accounts for the change in thelimiting dose being TEDE in the hand calculation and Thyroid CDE in the STAMPEDEcalculations. The accuracy of the hand calculation is considered sufficient and recommendedfor use in Emergency Action Levels."The Unit Vent (1.40E+05 [ici/sec) and the Main Steam Line (5.00E-02 pci/cc) RU1 values arethe unadjusted hand calculated values found in Calculation STPNOCO13-CALC-002 Rev. 2Table 2.1. The Unit Vent RA1 value (1.50E+06 pci/sec) was derived by conservatively roundingthe Table 2.1 hand calculated value of 1.57E+06 pci/sec. The Main Steam Line RA1 value(4.00E+00 pci/cc) was derived by conservatively rounding the hand calculated value of4.03E+00 pci/cc.The relationship of site boundary doses between the Alert and the Unusual Event isapproximately a factor of fifty. The gaps between the Unusual Event and the Alert are expectedto be different from the gaps between the Alert and higher classifications based on theunderlying assumptions in NEI 99-01.Radon response at STP is expected to be no more than 1% of the UE level based on operatingexperience and engineering judgmen Attachment 1NOC-AE-15003226Page 3 of 5RAI-06The proposed EAL RA3.2 includes a number of plant areas for all operating modes. Pleaseverify the plant areas identified for EAL RA3.2 reflect only those areas required for normal plantoperations, cooldown, or shutdown, and that access to these areas is required, i.e., cannot beoperated remotely. Please provide evidence of this verification, or revise as necessary tosupport accurate and timely assessment. In addition, consider adding operating modespecificity to the listed areas if applicable.STPNOC RESPONSE TO RAI-06STPNOC has revised EAL RA3.2 to include a listing of plant areas that require access fornormal plant operations, cooldown, or shutdown and components in these areas cannot beremotely operated. Additionally, modes of applicability have been included for each area asfollows:(2) An UNPLANNED event results in radiation levels that prohibit or impede access toANY of the areas listed in Table H3/R2.TABLEEH3/R2: "Pant Areas Requiring AccessRCB RHR Heat Exchanger Rooms0o MAB 51 ft Room 335EAB Roof, MCC 1G8, 4.16KV Switchgear Roomsu E00 "n EAB 4.16KV Switchgear RoomsEAL Selection BasisThe areas listed in EAL-2 apply to areas that contain equipment necessary for plant operations,cooldown, or shutdown. Assuming all plant equipment is operating as designed, Normaloperations and safe shutdown equipment operation is capable from the Main Control Room(MCR). The plant is able to transition into a hot shutdown from the MCR, therefore H3/R2 is alist of plant rooms or areas with entry-related mode applicability that contain equipment whichrequire a manual/local action necessary following entry into hot shutdown (establish ResidualHeat Removal shutdown cooling, disable operation of charging and ECCS equipment, and limitdilution pathways) and subsequent entry into cold shutdown (disable operation of ECCSequipment). After achieving cold shutdown it is assumed that the plant will be maintained in acold shutdown conditio Attachment 1NOC-AE-15003226Page 4 of 5RAI-10The proposed Loss of RCS Barrier due to Category 3, RCS Activity / Containment Radiation,Threshold A, contains a plant-specific basis discussion where temperature induced currents asthe result of an RCS leak would preclude the use of containment radiation monitors (RT-8050and RT-8051) for approximately 40 minutes, and a secondary system break would preclude theuse of the containment radiation monitors for 90 minutes.a. Please add this information to the table as the table is the decision-maker tool used forEAL determination, or justify how this information will consistently be used by EALdecision-makers.b. Please explain why these limitations were not included for Containment Barrier PotentialLoss threshold 3.A.1, or revise accordingly.c. Please explain why these limitations were not included for Fuel Clad Barrier Lossthreshold 3.A.1, or revise accordingly.STPNOC RESPONSE TO RAI-10STPNOC has removed containment radiation monitors (RT-8050 and RT-8051) from the RCSBarrier Category 3, RCS Activity/Containment Radiation table due to a reduction in the setpointvalue based on calculation STPNOC013-CALC-004, Revision 2. CalculationSTPNOC013-CALC-004 was revised in February 2015 and would have lowered the RT-8050and RT-8051 setpoint from 450 mR/hr to approximately 140 mR/hr above background.STPNOC believes that the proximity of the new setpoint to the background level and the effectof TIC precludes the use of these radiation monitors as reliable indications of an RCS breach.STPNOC does not have other Reg. Guide 1.97 radiation monitors in the containment that canfulfill the function of RT-8050 and RT-8051.STPNOC has revised the bases for the Containment Barrier Potential Loss threshold 3.A. 1 andthe Fuel Clad Barrier Loss threshold 3.A.1 to state that temperature induced current (TIC) is nota limitation for these events.Temperature induced current (TIC) limitations are not applicable to theContainment Barrier Potential Loss threshold 3.A.1 (Fuel Clad BarrierLoss threshold 3.A. 1) because the expected radiation dose for this eventoverwhelms the TIC effect. This is discussed in the 1OCFR50.59evaluation 04-8245-60 associated with DCP 04-8245-3 Attachment 1NOC-AE-15003226Page 5 of 5RAI-12The proposed EAL HA5 appears to cover a wide range of rooms or areas during all modes ofoperation.a. Please verify the plant areas identified for EAL RA3.2 reflect only those areas requiredfor normal plant operations, cooldown, or shutdown, and that access to these areas isrequired, i.e., cannot be operated remotely. Please provide evidence of this verification,or revise as necessary to support accurate and timely assessment. In addition, consideradding operating mode specificity to the listed areas if applicable.b. For EAL HA5, please provide justification for the omission of the control room as a plantarea where access is needed to support normal plant operations, cooldown, orshutdown.STPNOC RESPONSE TO RAI-12STPNOC has revised EAL HA5.1a to include the control room as a plant area where access isneeded to support normal plant operations, cooldown, or shutdown.1 a. Release of a toxic, corrosive, asphyxiant or flammable gas into the Control Room orany of the plant rooms or areas listed in Table H3/R2:ANDb. Entry into the room or area is prohibited or impeded._ TABLE H3/R2: Plant Areas Re6uiring AccessRCB RHR Heat Exchanger Rooms0o 0 MAB 51 ft Room 335EAB Roof, MCC 1G8, 4.16KV Switchgear RoomsLu0o Ln EAB 4.16KV Switchgear RoomsEAL Selection Basis:The areas listed in EAL-1 apply to areas that contain equipment necessary for plant operations,cooldown, or shutdown. Assuming all plant equipment is operating as designed, Normaloperations and safe shutdown equipment operation is capable from the Main Control Room(MCR). The plant is able to transition into a hot shutdown from the MCR, therefore H3/R2 is alist of plant rooms or areas with entry-related mode applicability that contain equipment whichrequire a manual/local action necessary following entry into hot shutdown (establish ResidualHeat Removal shutdown cooling, disable operation of charging and ECCS equipment, and limitdilution pathways) and subsequent entry into cold shutdown (disable operation of ECCSequipment). After achieving cold shutdown it is assumed that the plant will be maintained in acold shutdown conditio Attachment 2STPEGS Emergency Action Level Technical Bases Document -clean copy STPEGS Emergency Action LevelTechnical Bases Document Rev. 0NEI 99-01 Rev. 6 ImplementationFebruary 2015NOTE: Changes to this document require a review under 10CFR50.54 (q) as directed by OPGP05-ZV-O010,Emergency Plan Chang SUMMARY OF RESULTSThe results of the calculations for the radiation monitors specified in the STP EAL Basis Documentand are listed in Table 2.1, below.Table 2.1: Summary of Calculation ResultsEmergency ActionLevelRT-8010B, Unit Vent(pCi/sec)RT-8046 through 8049,Main Steam Lines(AtCi/cc)RU1 Unusual EventHand Calculation 1.40E+05 5.OOE-02STAMPEDE N/A* N/A*RA1 AlertHand Calculation 1.57E+06 4.03E+00STAMPEDE 2.50E+06 4.50E+00RS1 Site Area EmergencyHand Calculation 1.57E+07 4.03E+01STAMPEDE 2.50E+07 4.50E+O1RG1 General EmergencyHand Calculation 1.57E+08 4.03E+02STAMPEDE2.50E+084.50E+02*STAMPEDE was not used to determine the threshold for RU1. Reference 5.10 indicates that the ODCMmethodology should be used to determine the threshold value.This calculation will be used to establish the threshold values for abnormal radiation basedemergencies in the STP EAL Technical Basis documen I CALC. NO. STPNOC013-CALC-002E NERC0 N Radiological Release Thresholds REV. 2for Emergency Action LevelsExcelienre--Every ptoject Every doy f PAGE NO. 5 of473.0 METHOD OF ANALYSISPreviously, STAMPEDE was used to calculate the Emergency Action Level threshold values foreffluent releases. A hand calculation will verify the STAMPEDE calculations. The hand calculation isdescribed in Attachment 1 of this document STAMPEDE conforms to the requirements of STPProcedure OPGP07-ZA-0014, Software Quality Assurance Program. STAMPEDE was run at STP onan STP computer and under the supervision of an ENERCON employee with access to the STP site asa critical worker.4.0 INPUTS4.1 Per NEI 99-01, Revision 6, Initiating condition AUI, EAL 1, the Notice of Unusual Eventinitiating condition is a release of gaseous or liquid radioactivity greater than two times the ODCMlimit for sixty minutes or longer (Reference 5.10).4.2 The ODCM offsite dose limit is exceeded if the Xe-133 release concentration exceeds 7.41E-04[tCi/cc (Reference 5.6).4.3 The Unit Vent flow rate is 9.4E+07 cc/sec (Reference 5.1).4.4 The main steam line pressure and PORV choke flow rate are 1285 psig and 1.05E+06 lbm/hr,respectively (Reference 5.2).4.5 The specific volume of saturated steam at 1285 psig is 0.338 ft3/lbm (Reference 5.3).4.6 The release concentration is varied to find the release concentration which correlates to eachemergency action level. Emergency action levels are taken from NEI 99-01, Revision 6 (Reference5.10) for initiating conditions AAI, ASI and AGI. EAL I is the EAL of interest in each initiatingcondition. The doses at the Site Boundary that correlate to the threshold concentrations are listedin Table 4.1.Table 4.1 EAL Offsite Dose Initiating ConditionsAlert Site Area GeneralTEDErem 100 mrem 1000 mremThyroid CDE 50 mrem 500 mrem 5000 mrem5.0 REFERENCES5.1 Offsite Dose Calculation Manual, Revision 17, March 20115.2 Main Steam PORV Capacity Verification MC05591, Revision: 15.3 NIST Steam Tables, 20115.4 OERPO1-ZV-IN01, Emergency Classification Draft Revision 105.5 OERPOI-ZV-TPO1, Offsite Dose Calculations, Revision 215.6 STP Calculation NC-9012, CRMS Rad Monitor Setpoints, Revision 75.7 STP Calculation NC-901 1, Revision 25.8 STAMPEDE Computer Program, Revision 7.0.3.35.9 STAMPEDE Users Manual5.10 NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors5.11 OPGP07-ZA-0014 Quality Assurance Program5.12 ITWMS Call Number 1000010987 Design Document, Revision 0 CALC. NO. STPNOC013-CALC-002Radiological Release Thresholds CAV. Nfor Emergency Action Levels Eee- proe ey Y PAGE NO. 6 of 476.0 ASSUMPTIONS6.1 Unit Vent Noble Gas MonitorTo be consistent with the ODCM methodology, the unit vent release is assumed to be entirely Xe-133. The unit vent noble gas monitor is calibrated to Xe-133 (Reference 5.1) therefore; themonitor reading accurately reflects the Xe-133 release magnitude.To be consistent with ODCM methodology, the main steam line release is assumed to be entirelyXe-133. The noble gas monitor is calibrated to Xe-133 (Reference 5.6).6.2 Release DurationPer Reference 5.10, Sections IC AA1, ASI, and AGI developer notes, the release should beassumed to last one hour.6.3 Release following Reactor ShutdownThe release initiates one hour after reactor shutdown. While a release initiating at reactorshutdown is likely, significant decay of short lived nuclides occurs during the migration time. Arelease at reactor shutdown would have a significantly higher activity at the monitor location thanat the reception site. It is important for the threshold to not be calculated at shutdown as thiswould create a very high threshold which would not be appropriate for releases which occurshortly after shutdown. One hour after reactor shutdown is sufficient time to decay short livednuclides and create a conservative threshold.6.4 Source TermPer Reference 5.1, any unit vent release with increased RCS activity and no core melt should becalculated using the gap inventory. Therefore, the gap inventory is used for all unit vent releases.Per Reference 5.1, for a main steam line release following a steam generator tube rupture it isappropriate to use an inventory of noble gases plus 0.2% iodine. A steam generator tube rupture isthe only scenario which would create significant offsite doses through a main steam line release.6.5 Default STAMPEDE Input ValuesReference 5.10 developer notes for initiating conditions AA1, AS I and AGI suggest using theODCM or the site's emergency dose assessment methodology. STAMPEDE is used foremergency dose assessment. Per Reference 5.1, when actual meteorology is not available, thedefault STAMPEDE values should be used. Had the ODCM methodology been used, the 500hour peak x/Q value would be used which is less conservative than the X/Q value produced bySTAMPEDE using default meteorological conditions. Therefore, the use of STAMPEDE defaultvalues provides a more conservative estimate than that of the alternative method outlined inReference 5.10.6.6 Average Effluent Concentration (X/Q)The same X /Q is used for the unit vent and main steam line release. Reference 5. I applies thesame unit vent x/Q to Units 1 and 2 which would also be applicable to the main steam line. Allreleases are considered to be ground level release CA LC. NO. STPNOCOI3-CA LC-002ENER C N Radiological Release Thresholdsfor Emergency Action Levels REV. 2Excee very proec. ,ev doy PAGE NO. 7 of477.0 STAMPEDE CALCULATIONS7.1 Unusual Event -RU I.7.1.1 Unit Vent MonitorAU I recommends declaring an unusual event due to a release of gaseous or liquidradioactivity greater than 2 times the ODCM limits for 60 minutes or longer (Reference5.10).STP sets the ODCM limit at 7.41 E-04 giCi/cc (Reference 5.6, pg. 16). Two times the limitwould be 1.48E-03 ltCi/cc. The threshold is listed in giCi/sec so that variations in flow ratedo not change the threshold. The nonrmal flow rate from the unit vent is 9.4E+07 cc/sec(Reference 5.1).ICL\ cC \~C,Concentration ) *Flow Rate~- Release Rate ((1.48E -03) (&)*(9.4E + 07) (ec) (sec) 0Equation 7.1.1.17.1.2 Main Steam Line MonitorThe ODCM does not calculate a release corresponding to allowable limits for the mainsteam line monitors. Since the unit vent release calculated in the ODCM was assumed to beprimarily Xe-133, the assumption is made in the ODCM that other noble gases and iodinemay be ignored in the calculation. This assumption is equally justifiable for the main steamline and the same limiting release will be used.The magnitude of the release calculated for the unit vent Unusual Event applies to the mainsteam lines as well. The main steam line PORV's will create a dose exceeding two timesthe ODCM limit by releasing 1.4E+05 ptCi/sec of activity which is equivalent to the releasefrom the unit vent.The steam lines hold saturated steam at 1285 psig, per Reference 5.2, which has a specificvolume of 0.338ft3/Ibm (Reference 5.3). The PORVs will release the steam at 1.05E+06lbm/hr per Reference 5.2. This creates a set flow rate of steam from the main steam lines of2.79E+06 cc/sec as shown below.F

Density (lbm 28316.846 -ff + 3600 ( e schreC CCm)( th e1.05E" + 06 (-=--/* 0.338 (-- *28316.846 + 3600 2.79E +06-m)' f t3Y hr)secEquation 7.1. CALC. NO. STPNOCOI3-CALC-002NRadiological Release Thresholds 2for Emergency Action LevelsExcelence--Eve yproject. Ever day PAGE NO. 8 of47Since the flow rate is set, the concentration will determine the limit. Equation 7.1.2.2 solvesfor the limiting concentration of 5.00E-02 /aCi/cc as shown below.Lim iting Release (I --lCI L ( CiLimiting Concentration -Release Rate (-e-).1.40

105 (Ci)]1.4

o~ ~tC) -5.OOE -02 (IICi)2.79

106 c(.sec)Equation 7.1.2.27.2 Alert, Site Area and General Emergencies -RA1, RS 1, RG 17.2.1 Unit Vent MonitorInputThe Alert EAL is set to 10 mrem TEDE and 50 mrem Thyroid CDE per Reference 5.10.The emergency offsite dose calculation software STAMPEDE was used to calculate therelease which corresponds to this dose. A release concentration correlating to the EALthreshold value was calculated by varying the input. The following assumptions andinputs were used for the calculation as described in Sections 4.0 and 6.0.* Release begins one hour after reactor trip* Release lasts for one hour" Gap inventory source term" Default STAMPEDE input valueso Windspeed = 13.2 mpho Stability class DResultsGiven a monitored unit vent release of 2.50E+06 pCi/sec., the Thyroid CDE is 51mrem/hr at the closest portion of the site boundary and the EAL Initiating Condition isexceeded.Threshold values for the Site Area Emergency and General Emergencies are multiples of10 and 100 of the Alert. Since the Correlation between release concentration and dose islinear, threshold values for the steam line monitors are 2.50E+07 and 2.50E+08 ptCi/secfor the SAE and GE respectively. Both are also limited by Thyroid CDE. AdditionalSTAMPEDE iterations were performed to confirm this and are attached.The input and output files can be found at the end of this document in Attachment CA LC. NO. STPNOCO I3-CA LC-002E N E R C O N Radiological Release Thresholds REV. 2for Emergency Action Levels REV.Evefyay. t PAGE NO. 9 of 477.2.2 Main Steam Line MonitorInputA release concentration correlating to the EAL threshold value was calculated by varyingthe input. The following assumptions and inputs were used for this calculation asdescribed in Sections 4.0 and 6.0." Release begins at reactor trip* Release lasts for one hour* Noble gas + iodine with 0.2% iodine source tern* Default STAMPEDE input valueso Windspeed = 13.2 mpho Stability class DResultsGiven a monitored main steam line release of 4.5 [tCi/cc, the Thyroid CDE is 50 mrem/hrand the EAL Initiating Condition is exceeded.The input and output files can be found at the end of this document in Attachment 3.7.3 Threshold values for the Site Area Emergency and General Emergencies are multiples of 10 and100 of the Alert. Since the correlation between release concentration and dose is linear, thresholdvalues for the steam line monitors are 45 and 450 itCi/cc for the SAE and GE respectively. Bothare also limited by Thyroid CDE. Additional STAMPEDE iterations were performed to confirmthis and are attache Radiological Release Thresholds CALC. NO. STPNOC013-CALC-002ENERCO N for Emergency Action Levels REV. 2Excel!ence--Everyproject Every doy Attachment 1 PAGE NO. 10 of47Attachment 1 -Hand Calculations1.0 OBJECTIVE/SCOPEEach release calculated using STAMPEDE in the main document is calculated by hand in thisattachment and the results compared to STAMPEDE.2.0 SUMMARY OF RESULTSTable 2.1 is displayed again below showing the results from all the calculations. The minor differenceis due to STAMPEDE using decay factors over a one hour period after shutdown. This also accountsfor the change in the limiting dose being TEDE in the hand calculations and Thyroid CDE in theSTAMPEDE calculations. The accuracy of the hand calculation is considered sufficient andrecommended for use in Emergency Action Levels.Table 2.1 ResultsEmergency ActionLevelRT-8010b, Unit Vent(jiCi/sec)RT-8046 through 8049,Main Steam Line(RCi/cc)RU1 Unusual EventHand Calculation 1.40E+05 5.OOE-02STAMPEDE N/A N/ARAI AlertHand Calculation 1.57E+06 4.03E+00STAMPEDE 2.50E+06 4.50E+00RS1 Site Area EmergencyHand Calculation 1.57E+07 4.03E+O1STAMPEDE 2.50E+07 4.50E+O1RG1 General EmergencyHand Calculation 1.57E+08 4.03E+02STAMPEDE2.50E+084.50E+023.0 METHOD OF ANALYSISUsing the limiting dose at the site boundary, the release is back calculated using atmosphericdispersion models. The X/Q value used is calculated from Regulatory Guide 1.145, AtmosphericDispersion Modelsfor Potential Accident Consequence Assessments at Nuclear Power Plants. Ratherthan using the most conservative meteorology, average meteorological conditions are used as inputs Radiological Release Thresholds CALC. NO. STPNOC013-CALC-002EN ER CO N for Emergency Action Levels REV. 2verydy. Attachment 1 PAGE NO. II of 47to most closely agree with STP emergency dose assessment methodology per the ODCM andSTAMPEDE. Assumed nuclide inventories are taken from Reference 5.15. The dose conversionfactors are taken from Reference 5.2. A release concentration is used to find an initial projected doseat the Site Boundary. Using the projected dose at the Site Boundary, the release concentration isscaled to find the limiting dose for each EAL.4.0 INPUTS* The Unit Vent flow rate is taken from the Offsite Dose Calculation Manual; Revision 17, March2011 and is 9.44E+07 cc/sec." The main steam line pressure and PORV choke flow rate were taken from Reference 5.5 and are1285 psig and 1.05E+06 lbm/hr respectively.* The specific volume of saturated steam at this pressure is taken from the NIST steam tables and is0.338 ft3/lbm.* The release concentration is varied to find the release concentration which correlates to eachemergency action level dose. Emergency action level doses are taken from NEI 99-01 Revision 6for initiating conditions AAI, ASI and AG1. EAL I is the EAL of interest in each initiatingcondition. The limiting doses are listed in Table 4.1. NEI 99-01 Revision 6 states that thesevalues are based on fractions of the Environmental Protection Agencies Protective ActionGuidelines (EPA PAGs) and the General Emergency represents the protective action valuesrecommended by the EPA.Table 4.1 EAL ThresholdsAlert Site Area GeneralTEDE 10 mrem 100 mrem 1000 mremThyroid CDE 50 mrem 500 mrem 5000 mrem" A release lasting one hour is selected per NEI 99-01 Revision 6 developer notes.* Atmospheric dispersion factors are calculated per Regulatory Guide 1.145 (Reference 5.1). Thereactor building dimensions used as inputs for this calculation are taken from Reference 5.13.* Nuclide mixes are taken from Reference 5.15, which is the source document for the nuclidemixes used in STAMPEDE. The release mixes are a gap release and noble gases plus 0.2% iodinewhich are listed below. Each nuclide mix was normalized to one so it could be scaled to variousrelease activitie Radiological Release Thresholds CALC. NO. STPNOCO 1 3-CALC-002U EN ER CO N for Emergency Action Levels REV. 2Excellence--eyeproject. Everydoay Attachment I PAGE NO. 12 of47Table 4.2 Gap InventoryNuclide1-1311-1321-1331-1341-135Kr-83mKr-85mKr-85Kr-87Kr-88Kr-89Xe-131mXe-133mXe-133Xe-135mMix1.I1OE+051.50E+052.20E+052.40E+052.OOE+051.30E+062.90E+063.70E+055.50E+067.80E+069.50E+061.1OE+056.80E+052.20E+074.20E+06Normalized1. 1 2E-031.53E-032.25E-032.45E-032.05E-031.33E-022.97E-023.78E-035.62E-027.98E-029.72E-021.1 2E-036.95E-032.25E-0 14.30E-02I NuclideXe-135Xe-137Xe-138Cs-134Cs-137Te132Mo99RulO3Ru106Zr95Lai40Ce144Ce-141Sr89Sr9oMix Normalized5.50E+06 5.62E-021.90E+07 1.94E-0I1.80E+07 1.84E-013.70E+/-01 3.78E-072.90E+01 2.97E-074.80E+00 4.91E-081.22E+O1 1.25E-078.80E-03 9.OOE-1 12.90E-03 2.97E- I11.1OE-02 1.12E-101.90E-02 1.94E-107.40E-03 7.57E-1 I1.OOE-02 1.02E-106.40E-02 6.55E-103.20E-03 3.27E-1 1Table 4.3 Noble Gases+0.2% Iodine InventoryNuclide1-1311-1321-1331-1341-135Xe-131mXe-133Xe-133mXe-135Xe-135mXe-137Xe-138Kr-83mKr-85Kr-85mKr-87Kr-88Kr-89Mix6.1OE-028.61 E-021.OOE-011.86E-022.73 E-0 I2.80E+002.40E+024.20E+007.60E+004.OOE-0 11.60E-015.80E-0 I3.70E-017.60E+001.50E+009.80E-012.80E+008.40E-02Normalized2.26E-043.19E-043.72E-046.92E-051.0 1E-031.04E-028.90E-011.56E-022.82E-021.48E-035.93E-042.15E-031.37E-032.82E-025.56E-033.63E-031.04E-023.12E-04(Reference 5.2) are listed in Tables 4.4The dose conversion factors taken from EPA 400R92001and 4.5 belo Radiological Release Thresholds CALC. NO. STPNOCOI3-CALC-002SE ER C O N for Emergency Action Levels REV. 2Ex'ellence--Veryproject Fverydoy. Attachment I PAGE NO. 13 of47Table 4.4 TEDE Dose Conversion FactorsNuclide1-1311-1321-1331-1341-135Kr-83mKr-85mKr-85Kr-87Kr-88Kr-89Xe-131mXe-133mXe-133Xe-135mDose ConversionFactor(rem per uCi*hr/cc)5.30E+044.90E+031.50E+043.1OE+038.1OE+039.30E+011.30E+005.1OE+021.30E+031.20E+034.91.70E+O12.OOE+O 12.50E+02NuclideXe-135Xe-137Xe-138Cs-134Cs-137Tel32Mo99Ru103RulO6Zr95Lal40Ce144Ce-141Sr89Sr90DoseConversionFactor(rem peruCi*hr/cc)1.40E+021.1OE+027.20E+026.30E+044.1OE+041.20E+045.20E+031.30E+045.70E+053.20E+041.1OE+044.50E+051.1OE+045.OOE+041.60E+06Table 4.5 Thyroid CDE Dose Conversion FactorsNuclide1-1321-1331-1341-135Thyroid CDE DCF(rem per uCi*hr/cc)1.30E+067.70E+032.20E+051.30E+033.80E+04The unit vent noble gas monitor energy efficiency by nuclide is taken from Offsite DoseCalculation Manual (Reference 5.3). The values are relative to Xe-133 efficiency since themonitor is calibrated to Xe-133. Table 4.6 displays the energy efficiency by nuclide relative toXe-13 Radiological Release Thresholds CALC. NO. STPNOCOI3-CALC-002E N ER CO N for Emergency Action Levels REV. 2ExceP, p .cvFeyday Attachment I PAGE NO. 14 of47Table 4.6 Energy Efficiency Relative to Xe-133Efficiency Relativeto Xe-133Nuclide (U/Ceuian....................... ....... ..... ............ .(" C ~ s e ~ " eKr-83m *Kr-85m 1.9Kr-85 2.4Kr-87 2.8Kr-88 2.3Kr-89 2.8Xe-131m 0.015Xe-133m 0.14Xe-133 IXe-135m 0.042Xe-135 2.5Xe-137 2.8Xe-138 2.8*There is no relative efficiency available for Kr-83m.omission.t --Assumption 6.4 further justifies theTable 4.7 Nuclide Half LivesNuclide Half Life(hr)1-131 1.93E+021-132 2.38E+001-133 2.03E+011-134 8.77E-011-135 6.61E+00Kr-83m 1.83E+00Kr-85m 4.48E+00Kr-85 9.40E+04Kr-87 1.27E+00Kr-88 2.84E+00Kr-89 5.1OE-02Xe-131m 2.83E+02Xe-133m 5.42E+01Xe-133 1.27E+02Xe-135m 2.60E-01Nuclide Half Life(hr)".Xe-135Xe-137Xe-138Cs-134Cs-137Te132Mo99Ru103Rul06Zr95Lal40Ce144Ce-141Sr89Sr909.08E+006.38E-022.36E-011.80E+042.60E+057.79E+0 I6.62E+0 I9.44E+028.84E+031.55E+034.03E+016.82E+037.77E+021.21 E+032.50E+050 The half-lives are taken from Reference 5.15 which lists the input data used by STAMPED Radiological Release Thresholds CALC. NO. STPNOC013-CALC-002E N E R C O N for Emergency Action Levels RE\'.2Eaceferxp-Every ptojea. Every day Attachment I PAGE NO. 15 of 475.0 REFERENCES5.1 Regulatory Guide 1.145, Atmospheric Dispersion Models for Potential Accident ConsequenceAssessments at Nuclear Power Plants, Revision 1, November 1982.5.2 EPA 400R92001, Manual of Protective Action Guides and Protective actions for NuclearIncidents, Revision 1, May 1992:5.3 Offsite Dose Calculation Manual, Revision 17, March 2011.5.4 TGX/THX 3-1, Revision 5., Westinghouse Radiation Analysis Manual.5.5 MC05591, Main Steam PORV Capacity Verification, Revision 1.5.6 NIST Steam Tables, 2011.5.7 OERPO I-ZV-INO1. Emergency Classification, Revision 10.5.8 0ERP01-ZV-TPO1, Offsite Dose Calculations, Revision 21.5.9 STP Calculation NC-9012, Process and Effluent Radiation Monitor Set Points, Revision 75.10 STP Calculation NC-901 1, CRMS Rad Monitor Setpoints, Revision 2.5.11 STAMPEDE Computer Program, Revision 7.0.3.3.5.12 STAMPEDE Users Manual5.13 STP Drawing 6C189N5007, General Arrangement Reactor Containment Building, Revision 65.14 NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors5.15 ITWMS Call Number 1000010987 Design Document, Revision 06.0 ASSUMPTIONS6.1 Release lasts for one hourPer NEI 99-01 (Reference 5.14), IC AA1, AS], AGI developer notes,.the release should beassumed to last one hour.For this to be true for the main steam line, it is assumed that the PORV is open for one hour. Tocalculate the most limiting case, it is assumed that the maximum flow possible is being releasedfriom the PORV.6.2 Nuclide mixPer 0ERP0I-ZV-TPO1, Offsite Dose Calculations (Reference 5.8) any unit vent release withincreased RCS activity and no core melt should be calculated using a gap inventory. It isconservative to assume an increased RCS activity and not within the intended scope of therelevant initiating conditions to assume core melt. Therefore, a gap inventory is used for all unitvent releases.Per 0ERP0I-ZV-TPO1, Offsite Dose Calculations (Reference 5.8) for a main steam line releasefollowing a steam generator tube rupture it is appropriate to use an inventory of 100 percent noblegases plus 0.2 percent iodine. STAMPEDE's source mix for noble gases plus iodine is defined bythe noble gas levels from the coolant mix plus the iodine levels from the coolant mix scaled to apercentage of total noble gas (Reference 5.15). A definition of 0.2 percent iodine means thesummation of iodine levels is equivalent to 0.2 percent of the noble gas levels. Since a steamgenerator tube rupture releasing through the PORVs is the only steam generator tube rupture Radiological Release Thresholds CALC. NO. STPNOC013-CALC-002F4 E N E R C O N for Emergency Action Levels REV. 2Exceflence--Evetyptont. E'ety day Attachment 1 PAGE NO. 16 of47scenario which would create offsite doses large enough to meet or exceed the EALs, thisassumption is made.6.3 Atmospheric DispersionNEI 99-01 (Reference 5.14) developer notes for initiating conditions AA1, ASI and AGI suggestusing the ODCM or the site's emergency dose assessment methodology. Per OERPO 1 -ZV-TPO 1,Offsite Dose Calculations (Reference 5.8), when actual meteorology is not available, the defaultSTAMPEDE values should be used. The default STAMPEDE values assume a stability class Dfor atmospheric dispersion and a windspeed of 13.2 mph. These values were used as inputs forthe atmospheric dispersion calculation.It is clear that STAMPEDE uses the same method for calculating atmospheric dispersion factor(X/Q) outlined in section 7.1.1 of this Attachment. However, STAMPEDE does not follow thesame logic in selecting the appropriate result from the three calculations. The STAMIPEDE valueprinted in the results found in attachment 3 is consistent with the largest of the three handcalculated X/Q values. This suggests that STAMPEDE simply selects the largest of the three X/Qvalues resulting in a much more conservative estimate. This calculation will deviate from therecommendations of Regulatory Guide 1.145 and conform to the methodology STAMPEDE uses.The close proximity of all release points allows for a single atmospheric dispersion coefficient tobe used. This assumption is also made by STAMPEDE.6.4 Exposure PathwaysThe dose conversion factors used in Tables 4.4 and 4.5 represent a summation of dose conversionfactors for external plume exposure, inhalation from the plume and external exposure fromdeposition. Because the dose estimations are used for implementing early phase protectiveactions, conversion factors using limited pathways are appropriate.The EPA does not provide a dose conversion. factor for Kr-83m. Because the PAGs are based onEPA dose calculations, it is appropriate to only use the nuclides for which dose conversion factorsare provided. Additionally, Kr-83mn represents only 1.33% of the nuclide inventory activity andits exclusion would not significantly affect the final dose.6.5 DecayThe release initiates one hour after reactor shutdown. While a release initiating at reactorshutdown is likely, significant decay of short lived nuclides occurs during the migration time. Arelease at reactor shutdown would have a significantly higher activity at the monitor location thanat the reception site. It is important for the threshold to not be calculated at shutdown as thiswould create a very high threshold which would not be appropriate for releases which occurshortly after shutdown. One hour after reactor shutdown is sufficient time to decay short livednuclides and create a conservative threshold.Decay is incorporated for one hour friom reactor shutdown as well as migration time. Half-livesare taken from Reference 5.15. Migration time is assumed to be the reciprocal of the wind spee Radiological Release Thresholds CALC. NO. STPNOC013-CALC-002E N E R C O N for Emergency Action Levels REV. 2Exceieernce--veryproject. Fveryday Attachment 1 PAGE NO. 17 of 477.0 HAND CALCULATIONS7.1 Unit Vent Monitor7.1.1 X/QThe atmospheric dispersion factor, X/Q, determines the change in concentration betweenthe unit vent discharge and the dose reception site. This value is based on meteorologicalconditions and will vary with wind speed and stability class. The ODCM uses the highestannual average X/Q value at the site boundary which is 5.3 E-06 sec/r3.However, for anaccident related release STAMPEDE is used rather than the ODCM. STAMPEDE usesreal time, user entered., or default meteorological conditions to calculate the X/Q for aspecific accident. Default values will be used as inputs into the Regulatory Guide 1.145method for calculating X/Q as described below. Default values are identified in section6.0, Atmospheric Dispersion.For a neutral atmospheric stability class, which is the default in STAMPEDE. X/Qvalues can be determined through the following set of equations.X 1Equation 7.1.1.1X 1Q Ulb (3cruycrz)Equation 7.1.1.2X 1Q U10o YuzEquation 7.1.1.3WhereX/Q = relative concentration (sec/m^3)7C =3.14159U10 = windspeed at 10 meters above plant grade (m/s)ury = lateral plume spread (in), a function of atmospheric stability and distance,determined from Regulatory Guide 1.145 Figure 1UZ = vertical plume spread (m), a function of atmospheric stability and distance,determined from Regulatory Guide 1.145 Figure 2Vy = (M -1)aysoom + ay = lateral plume spread wvith meander and building wakeeffects (m), a function of atmospheric stability, windspeed U10, and distance; M isdetermined from Regulatory Guide 1.145 Figure 3A = the smallest vertical-plane cross-sectional area of the reactor building (mA2).taken firom Reference 5.13 and shown below Radiological Release Thresholds CALC. NO. STPNOCOI3-CALC-002NE CE 0 for Emergency Action Levels REV. 2Eveirerre-Eeyproyrrt ery day Attachment I PAGE NO. 18 of 47Figure 7.1.1.1: Reactor Building DimensionsEL 241"-0iAssuming the reactor building cross section to be a perfect rectangle and half sphere, thevariables are defined as follows;U10 = 13.2 mph = 5.9 m/suy = 1200 ina, = 4.2 mEy = (M -1)uy8o0m + -y ; M=I --y = 1200 l mA = (135'* 158')+ ( 2)= 31128.37The three equations become;xQ15.9 (7r1200

4.2 + 31128.37) 5.398

106 Radiological Release Thresholds CALC. NO. STPNOC013-CALC-002, E N E R C O N for Emergency Action Levels REV. 2Excelerce-Evety project. Every doy. Attachment 1 PAGE NO. 19 of 47= 1= 3.568*10-6Q 5.9(37r

1200

4.2)X 1x 1 -1.07

10-5Q 5.9

7r * [(1 -1)ay800oo + 1200]

4.2To select the appropriate X/Q value, the first two X/Q values should be compared and thehigher value selected. This value is then compared with the third X/Q value and the lowerof those two is the appropriate X/Q value. The appropriate X/Q is 5.3 9E-06 sec/m3 fordefault meteorological conditions by the methodology recommended in RegulatoryGuide 1.145.This calculated value is very similar to the ODCM highest average value of 5.3E-06sec/m3 which was not selected for use. Additionally, the value shown in the STAMPEDEoutput file at one mile is 1.032E-05 sec/m3.This suggests that STAMPEDE uses the samemethodology and simply selects the largest atmospheric dispersion value to remainconservative. This methodology will be replicated and 1.07E-05 will be used as the X/Q.7.1.2 Nuclide InventoryAs previously stated, a gap mix is appropriate for this problem. The gap mix is takenfrom Reference 5.15 which is used as the source term for STAMPEDE nuclide mixes.The mix was then normalized so they could be scaled to the varying emergencyclassifications. The values for the normalized inventory can be found in Table 4.2.7.1.3 Dose Conversion FactorsAs stated in NEI 99-01 (Reference 5.14) developer notes, the purpose of dose projectionsis to check if the Environmental Protection Agencies Protective Action Guidelines (EPAPAGs) have been exceeded. The dose conversion factors provided by the EPA in EPA400R92001 are used. These dose conversion factors account for external plume exposure,inhalation from the plume, and external exposure from deposition and are listed in Tables4.4 and 4.5, and taken from Tables 5-1 and 5-2 in EPA 400R92001 (Reference 5.2).The EPA does not provide a dose conversion factor for Kr-83m. This nuclide contributes1.33% of the inventory activity. The lack of this nuclide's contribution to the final dosewill not significantly affect the outcome.7.1.4 Decay TimeOne hour of decay is incorporated to the monitor response due to the release initiatingone hour after reactor shutdown. Decay is also incorporated for the duration of themigration time. The total decay time is one hour plus the reciprocal of wind speed, or1.07575 hours.7.1.5 Dose Calculations Radiological Release Thresholds CALC. NO. STPNOCOI3-CALC-002E N E R C O for Emergency Action Levels REV. EExce.ence--Evev, project. Fvery day. Attachment 1 PAGE NO. 20 of 47The dose rate at the site boundary is calculated using Equation 7.1.5.1.Sn 1.07575/ -F Ci*0.5 T1/2i *DCF1Equation 7.1.5.1WhereD = dose rate per hour at the site boundary-atmospheric dispersion coefficient as calculated in section 7.1.1QF = unit vent flow rateCi= concentration of nuclide i at the time of shutdown1.07575 = the total decay time of interest from section 7.1.4TI/2i = the half-life of nuclide iDCF1 = the dose conversion factor for nuclide i listed in tables 4.4 and4.5The total concentration of the nuiclides is varied to find the dose rate of interest.Beginning with an arbitrary release concentration of I [tCi/cc, the dose rate is calculated.Since the dose is linearly correlated to concentration, the release concentration may bescaled to find the dose rate of interest.The Alert EAL is 10 mrem TEDE or 50 mrem Thyroid CDE. Using the above method tocalculate TEDE with the appropriate conversion factors, a limiting release rate of2.33E+06 gCi/sec from the unit vent results in 5.7 mrem TEDE. Using the calculatedrelease rate to find Thyroid CDE with the appropriate conversion factors, the samerelease results in a 50 mrem Thyroid CDE at the site boundary. Thus, 2.33E+06 pCi/secis the limiting release rate based on the 50 mrem Thyroid CDE EAL initiating condition.The limiting release rate threshold values for the Site Area Emergency and GeneralEmergencies are multiples of 10 and 100 of the Alert release rate threshold value.These calculations can be found in Attachment 2.7.1.6 Monitor ResponseThe unit vent noble gas monitor is calibrated to Xe-133. Monitor efficiencies relative toXe-133 by nuclide are listed in ODCM Table B3-2. To find the monitor readingassociated with each limiting release, the noble gas concentrations must be multiplied bythe monitor response and summed. Table 4.6 shows the indicated response of the unitvent noble gas monitor by nuclide and Equation 7.1.5.2 shows how the monitor responsewas calculate Radiological Release Thresholds CALC. NO. STPNOC013-CALC-002E N E R C O N for Emergency Action Levels REV. 2Excel ence-Every project. very doy Attachment I PAGE NO. 21 of47Monitor Response =

RejEquation 7.1.5.2WhereC1 = concentration of nuclide i (pCi/cc)Re1 = monitor response to nuclide i (.tCi/cc)x_133 equivalentIn the case of an Alert, the 2.33E+06 ltCi/sec release rate will read as 1.57E+06pCi/sec on the monitor. Kr-83m does not have an indicated monitor responsecoefficient. Because Kr-83m is only 1.33% of the noble gases and does notcontribute to the dose calculation, its exclusion is acceptable.This again is a linear correlation and the SAE and GE scale by factors of 10 and100 respectively.These calculations can be found in Attachment 2.7.2 Main Steam Line Monitors7.2.1 X/QSince the atmospheric dispersion is independent of nuclide inventory or release rate andthe close proximity of thereleases, the X/Q value will be the same for a main steam linerelease as it is for a unit vent release. This assumption is also taken by STAMPEDE andoutline in Assumption 6.3.7.2.2 Nuclide InventoryPer OERPO1-ZV-TPO0, if the release path is the main steam line with a steam generatortube rupture, the nuclide inventory should be 100% noble gas from the reactor coolantand the reactor coolant iodine mix scaled to equal 0.2 percent of the total noble gas.The secondary steam concentration for noble gases and iodine after a steam generatortube rupture are taken from Reference 5.15. Values for the reactor coolant inventory arelisted in Table 4.3. All of the noble gases are used and the iodine concentration from thecoolant inventory is scaled to total 0.2% of the total noble gas mix. These inventories arethen normalized to one. These values are listed in Table 4.3.7.2.3 Dose Conversion FactorsThe dose conversion factors used are found in Tables 4.4 and 4.5, taken from Tables 5-1and 5-2 in EPA 400R9200 Radiological Release Thresholds CALC. NO. STPNOCO13-CALC-002E N E R CO N for Emergency Action Levels REV. 2ExceIence-Evetypfojev. Evetydoy Attachment I PAGE NO. 22 of477.2.4 Decay TimeOne hour of decay is incorporated to the monitor response due to the release initiatingone hour after reactor shutdown. Decay is also incorporated for the duration of themigration time. The total decay time is one hour plus the reciprocal of wind speed, or1.07575 hours.7.2.5 Dose CalculationsEquation 7.1.5.1 applies to the release from the main steam lines. The main steam lineflow rate is used instead of the unit vent flow rate for the value F. The main steam lineflow rate was calculated in Equation 7.1.2.2 of the STAMPEDE CALCULATIONSsection of this document as 2.79E+06 cc/sec.The Alert EAL threshold is 10 mrem TEDE or 50 mrem Thyroid CDE at the siteboundary (Table 4.2). Using the method in Equation 7.1.5.1 to calculate TEDE with theappropriate conversion factors, a concentration at time of shutdown of 4.10 i.tCi/cc wouldresult in 6.89 mrem TEDE at the site boundary if the steam line PORV was open for anhour. Using the same steam line concentration to calculate Thyroid CDE results in 50mrem Thyroid CDE at the, site boundary.The steam line concentrations at the time of shutdown for the Site Area Emergency andGeneral Emergencies are multiples of 10 and 100 of the Alert. Since the correlationbetween release concentration and dose is linear, values for the steam line concentrationat time of shutdown are 41.0 and 410 jiCi/cc for the SAE and GE respectively. Both arealso limited by Thyroid CDE.These calculations can be found in Attachment 2.7.2.6 Monitor ResponseBecause the main steam line monitor is adjacent to the main steam line, significantshielding takes place between the source and monitor. STP calculation NC-90 11 Revision2 calculates a conversion factor for the main steam lines for a noble gas inventory whichis incorporated into the monitor readout. No monitor response needs to be calculated.The concentration of the main steam line one hour after shutdown given a concentrationof 4.10 ltCi/cc at the time of shutdown is 4.03 ptCi/cc. This calculation is also found inAttachment 2. Additionally, the monitor readings for the SAE and GE one hour aftershutdown are 40.3 and 403 piCi/cc respectively. These values are the thresholds for themain steam line monito Radiological Release Thresholds CALC. NO. STPNOC013-CALC-0020 E NERCON for Emergency Action Levels REV.2Excelnce-EEvery pq Fery ody Attachment 2 PAGE NO. 23 of 47Table A2-1: Unusual Event Emergency Calculations1.40E+05 I 2.79E+06 I 5.OOE-02Table A2-2: Input Values for Calculations Radiological Release Thresholds CALC. NO. STPNOCOI3-CALC-002I EN ERCO N for Emergency Action Levels REV.2Excelence-Evenyproject Every day Attachment 2 PAGE NO. 24 of 47Table A2-3: Calculations for Boundary Concentrations and TEDE dose due to Unit Vent Release1-1311-1321-1331-1341-135Kr-83mKr-85mKr-85Kr-87Kr-88Kr-89Xe-131mXe-133mXe-133Xe-135mXe-135Xe-137Xe-1381.1OE+051.50E+052.20E+052.40E+052.OOE+051.30E+062.90E+063.70E+055.50E+067.80E+069.50E+061.1OE+056.80E+052.20E+074.20E+065.50E+061.90E+071.80E+071.12E-031.53E-032.25E-032.45E-032.05E-031.33E-022.97E-02..78E-035.62E-027.98E-029.72E-021.12E-036.95E-032.25 E-014.30E-025.62E-021.94E-0 I1.84E-012.76E-053.77E-055.55E-056.04E-055.06E-053..28E-047.33E-049.33)E-051.39E-031.97E-032.40E-032.76E-051.71 E-045.55E-031.06E-031.39E-034.79E-034.54E-031.0 1E-031.0 1E-031.0 1E-031.0IE-031.0 1E-031.0 1E-031.0 1E-031.0 1E-031.0 1E-031.01E-031.0 1E-031.0 1E-031.0 1E-031.0 1E-031.0 1E-031.0 1E-031.0 1E-031.01E-032.79E-08 1.93E+02 2.78E-08 5.30E+043.8 1 E-08 2.38E+00 2.79E-08 4.90E+035.61 E-08 2.03 E+0 I 5.40E-08 1.50E+046.11 E-08 8.77E-0 1 2.61 E-08 3.1 OE+035 11 E-08 6.61 E+00 4.56E-08 8.1 OE+033.3 1E-077.40E-079.42E-081.40E-061.99E-062.42E-062.79E-081.73E-075.61 E-061.07E-061.40E-064.83E-064.59E-061.83E+004.48E+009.40E+041.27E+002.84E+005.1OE-022.83E+025.42E+011.27E+022.60E-0 I9.08E+006.38E-022.36E-0 I2.21 E-076.27E-079.42E-087.79E-071.53E-061.08E-122.78E-081.71 E-075.57E-066.09E-081.29E-064.06E- I11.95E-079.30E+0 I1.30E+005.10E+021.30E+031.20E+032.50E+021.40E+021.1OE+027.20E+025.30E+044.90E+031.50E+041.47E-031.37E-048.11 E-048.09E-053.70E-040.OOE+005.83E-051.22E-073.97E-041.99E-031.30E-091.36E-072.90E-061.11 E-041.52E-051.81E-044.47E-091.40E-04 Radiological Release Thresholds CALC. NO. STPNOC013-CALC-002f ENERCoN for Emergency Action Levels REV. 2EC Nf_47Excellence-Everyproject Every day, Attachment 2 PAGE NO. 25 of 47Cs-134Cs-137Tel32Mo99Ru103Ru 106Zr95Lal40Ce 144Ce- 141Sr89Sr903.70E+Ol 3.78E-07 9.33E-09 1.01E-03 9.42E-12 1.80E+04 9.42E-12 6.30E+04 5.93E-072.90E+O1 2.97E-07 7.33E-09 1.01E-03 7.40E-12 2.60E+05 7.40E-12 4.1OE+04 3.03E-074.80E+00 4.91E-08 1.21E-09 1.01E-03 1.22E-12 7.79E+01 1.21E-12 1.20E+04 1.45E-081.22E+01 1.25E-07 3.08E-09 1.01E-03 3.11E-12 6.62E+01 3.08E-12 5.20E+03 1.60E-088.80E-03 9.OOE-11 2.22E-12 1.01E-03 2.24E-15 9.44E+02 2.24E-15 1.30E+04 2.91E-I 12.90E-031.1OE-021.90E-027.40E-031.00E-026.40E-023.20E-032.97E- II1.12E-101.94E-107.57E- II1.02E-106.55E- 103.27E- I17.33E-132.76E- 124.79E-121.87E-122.52E-121.62E-1 18.07E- 131.0 1E-031.0 1E-031.0 1E-031.0 1E-031.0 1E-031.0 1E-031.0 1E-037.40E-162.79E- 154.83E-151.89E-152.54E-151.63E-148.15E-168.84E+031.55E+034.03E+016.82E+037.77E+021.21 E+032.50E+057.40E-162.79E- 154.75E-151.89E-152.54E-151.63E-148.15E-165.70E+053.20E+041.t0E+044.50E+051.10E+045.OOE+041.60E+064.22E-108.93E-1 I5.22E- II8.49E-102.79E- II8.16E- 101.30E-09Total TEDEDose 5.77E-03 Radiological Release Thresholds CALC. NO. STPNOC013-CALC-00210 E -E RC ON for Emergency Action Levels REV. 2ECOf_47Excellence-E ery proec Ever ydoy Attachment 2 PAGE NO. 26 of 47Table A2-4: Thyroid Dose Calculation for Unit Vent Release1-131 2.78 E-08 1.30E+06 3.61 E-021-132 2.79E-08 7.70E+03 2.15E-041- 133 5.40E-08 2.20E+05 1.19E-021-134 2.61 E-08 1.30E+03 3.39E-051-135 4.56E-08 3 .80E+04 1.73E-03Table A2-5: Unit Vent Monitor Response to Nuclide InventoryKr-83mKr-85mKr-85Kr-87Kr-88Kr-89Xe-131mXe-133mXe-133Xe- 135mXe-135Xe-137Xe-1383.28E-047.33E-049.33E-051.39E-031.97E-032.40E-032.76E-051.71 E-045.55E-031.06E-031.39E-034.79E-034.54E-031.83 E+004.48E+009.40E+041.27E+002.84E+005.1OE-022.83E+025.42E+0 I1.27E+022.60E-0 I9.08E+006.38E-022.36E-012.25E6.28E9.33E8.03E1.54E3.00E2.76E1.69E5.52E7.38E1.28E9.15E2.41E-04-04 1.9-05 2.4-04 2.8-03 2.3-09 2.8-05 0.015-04 0.14-03 1-05 0.042-03 2.5-08 2.8-04 2.8Monitor Reading:0.00E+001.19E-032.24E-042.25E-033.55E-038.40E-094.13E-072.37E-055.52E-033.1OE-063.21 E-032.56E-076.74E-04(uCi/cc) (uCi/sec)

Radiological Release Thresholds CALC. NO. STPNOC013-CALC-00210 N ERCO N for Emergency Action Levels REV. 2Excellmen-Everyproject, EverydW Attachment 2 PAGE NO. 27 of 47Table A2-6: Input for Main Steam Line Release CalculationTable A2-7: Calculations for Boundary Concentrations1-1311-1321-1331-1341-135Xe-131mXe-133Xe-133mXe-135Xe-135mXe-137Xe-138Kr-83mKr-85Kr-85mKr-87Kr-88Kr-896.I01E-028.6 IE-021.00E-0 I1.86E-022.73 E-0 I2.80E+002.40E+024.20E+007.60E+004.OOE-0 I1.60E-015.80E-013.70E-0 17.60E+001.50E+009.80E-012.80E+008.40E-022.26E-043.19E-043.72E-046.92E-051.0 1E-031.04E-028.90E-011.56E-022.82E-021.48E-035.93E-042.15E-031.37E-032.82E-025.56E-033.63E-031.04E-023.12E-049.27E-041.3 1E-031.53E-032.84E-044.14E-034.26E-023.65E+006.40E-021.16E-016.07E-032.43E-038.82E-035.62E-031.16E-0I2.28E-021.49E-024.26E-021 .28E-032.9853E-052.9853E-052.9853E-052.9853E-052.9853E-052.9853E-052.9853E-052.9853E-052.9853E-052.9853E-052.9853E-052.9853E-052.9853E-052.9853E-052.9853E-052.9853E-052.9853E-052.9853E-052.77E-083.90E-084.55E-088.47E-091.24E-071.27E-061.09E-041.9 1E-063.45E-061.81E-077.26E-082.63 E-071.68E-073.45 E-066.81 E-074.44E-071.27E-063.82E-081.93E+022.38E+002.03E+O18.77E-016.61E+002.83E+021.27E+025.42E+019.08E+002.60E-016.38E-022.36E-0 I1.83E+009.40E+044.48E+001.27E+002.84E+005.1 OE-022.76E-082.85E-084.39E-083.62E-091.1OE-071.27E-061.08E-041.88E-063.18E-061.03E-086.10E-131.12E-081.12E-073.45E-065.76E-072.47E-079.79E-071.71E-145.30E+044.90E+031.50E+043.1OE+038.1 OE+034.92.OOE+011.70E+011.40E+022.50E+021.40E+027.20E+021.30E+009.30E+015.1OE+02L .30E+031.20E+031.46E-031.40E-046.58E-041.12E-058.95E-046.22E-062.17E-033.20E-054.45 E-042.57E-068.53E- II8.04E-060.OOE+004.49E-065.36E-051.26E-041.27E-032.05E-1 1Total Dose 7.28E-03*Release Constant = X/Q

duration

release rate Radiological Release Thresholds CALC. NO. STPNOCOI3-CALC-002EN E RCO N for Emergency Action Levels REV. 2Exctenl --Eer, project Eecry day Attachment 2 PAGE NO. 28 of 47Table A2-8: Main Steam Line Release Thyroid Dose Calculation1-131 2.76E-08 1.30E+06 3.58E-021-132 2.85E-08 7.70E+03 2.20E-041-133 4.39E-08 2.20E+05 9.66E-031-134 3.62E-09 1.30E+03 4.71 E-061-135 1.1OE-07 3.80E+04 4.20E-034.9E0 CALC. NO. STPNOCOI 3-CALC-002Radiological Release ThresholdsFE C O N for Emergency Action Levels REV. 2Excellence-Everyprojct, Every doy Attachment 3 PAGE NO. 29 of 47Table A2-9: Main Steam Line Reading at ReleaseI- I .) 11-1321-1331-1341-135Xe-131mXe-133Xe-133mXe-135Xe-135mXe-137Xe-138Kr-83mKr-85Kr-85mKr-87Kr-88V ,rQO,./ /12-Uq-1.3 1E-031.53E-032.84E-044.14E-034.26E-023.65E+006.40E-021.16E-016.07E-032.43E-038.82E-035.62E-031.16E-012.28E-021.49E-024.26E-021 1)Q 1 l7W22.38E+002.03E+018.77E-016.6 1E+002.83E+021.27E+025.42E+019.08E+002.60E-0 I6.38E-022.36E-011.83E+009.40E+044.48E+001.27E+002.84E+00Iz Inn Al)V./.LiL-U49.77E-041.47E-031.29E-043.73E-034.25E-023.63E+006.3 1E-021.07E-014.22E-044.65E-084.67E-043.85E-031.16E-011.95E-028.62E-033.34E-021.60E-09 CALC. NO. STPNOC013-CALC-002Radiological Release Thresholds REV. 2r E N E R C O N for Emergency Action Levelsknliece--Everyp,,fcFr. Every day. Attachment 3 PAGE NO. 30 of 47DRILL STAMPEDE User Supplied InformationDR LRvso7o.0. t DRELLDautm1ame: 12/1720U 1i524Uasr Nam: Un VeIt AlmT1huS r 11mfiermtAWwlgo Data lupffh:Graund bwd t mud ioty 13M mi~hrOruundLr Itudmdf ID degreesClass$hiy Class: "D -NeuFrnlUaiteedtnit Veal Rinse:kT Veat Release Rate atert 2044E+)6 uCitserReacts St DateTime: 12/1720131424Raluse Start 127172013 15:24EshiaatedRulgase Thonti LOD hmursNuock& 3&tre:.Gsph-teryCakuatedNOBLE GAS relese rate: LDE-0- MuCi/sec.NOmIEASMulisE auI/secNadci nuCtsecPAR37CiEATENMacfi RCisecKr-l3M:Kr-IS:IKr--L.I&Kr47:Kr-U:Xe--In1LMXe-133:Xe-I3M:Xe-135MXe-13TXe-1Im253E-+041.05E+0041.74E+0053.0ff0213.12Em+tIJ9IE+OW41.45E-'0&14E4-003953ECOXD266Ef4041-131:1-132:1-133:1-13:I-135:1112+02/3.IH+06-05B+0153.120+003S.12E+0-3Cs-.LM:Cs-137:Ce/Pr-3M4:Ce-!41:I.2l,40:lI'b-l99:Fm/Rh-lu&Rm-103:Sr/Y-w.Sr-3g:Te-132:zir-95.-1 DEa+l000.105EM10X.2.1024E102.SW4D45i3lE-COD1122E4)01352-WDI3.13Eql0112/1712013 3:24:46 PM CALC. NO. STPNOCOI3-CALC-002Radiological Release Thresholds REV. 2E N E R C O N for Emergency Action Levels vbxceflence-Eveyproject. po veryday, Attachment 3 PAGE NO. 31 of47DRILL ~STAA-REDE ResultsIfoatoDRILL R g DRILLlhf&Mr/IWs1172013 15:24 Uer Nan: Unit Vent AlertCnuraammznnflDistauca(miles)051.02.05.07-510.020oDistaxcv(Inits)0.51.02.05.07-510_0Distance(sniles)0-51.02.05.07-510-020.0Ptlmxe Trsrl Tisne( nuns:Msmntas)0:020.050:230-340:451.31CmLQ Va.ln(Sod=*)1.032E-003.755E-05:1.00'E-003.951E-007L541E-0Of7CM BinY243S0053.15EE-OD5737T4-0O?2-441E-0079.10912-00la tz Ikse Dow asIm rsion fl al Body171abrie Z,. 1C~amm0""0.0090.00330:0010:0(X)0.000Isa~rsicn fte Bodynaoil gus gmass (rein)0.0090..001O:0(X)external + anto:0.0160.0020.0010.0000.0w0Imfi a. CUErut (rusr"0.1370-0510-018WXM0.11120.0010.000'IMIE Idize CDEexernsl + internal Muraiu(rem) (rem)0.0160.0060.0M20.0010.0000.0000.0000.1370-0510.0180:0040.002-O.OO20.0010-M012317/2013 3 .2428 PM CALC. NO. STPNOC013-CALC-002for Emergency Action Levels REV. Radiological Release ThresholdsExcellence--Every proect. Every doy. Attachment 3 PAGE NO. 32 of 47STAM,,PEDE Results InformationDRILL R-iina 7.0.3.3 9%W82011 Page2of2 DRILL]CalcuLation ComphtedtRESULTSiMe&odofProjecdon: WindVelocity: 132nIr Release Rate: 119E+006 uCVsecSTAMPEDEWindDirection: ISOOffMie Dose Projection (rem):1 mile 2 mile.? S, miles' 10 milesTEDE 0.006 0.01)02 001 CDE 0.051 0).018 0.004 0.001Projected duration ofreleme: 1.0 hour0 days 0 hours 0 weeks 0 months sA General Emergency Requires a Protective Action RecommendationEVACUATE ZONE(S): ISHELTER LN PLACE ZONE(S): 2AFFECTED DOWeNWIND SECTORS: R. A, BAll Remainine Zones Go Indoors And Monitor EAS Radio StationBased on a Dose Rate Projection of> 3 mreminir (Immersion Ibole Body Noble Gas Gamma) at theSite Boundary (1 Mile) for 15 minutes or longer the Emergency Classification Initiating Condition RAIl(ALERT) has been met.PERFOR\IED I'Y:RIVX[IEWID BY:Kid Lanager.a~dioltgical Director12117!2013 3:24:44 PMDatT'TimeDareTime12117P-013 3:24-.2S PM CALC. NO. STPNOCOI3-CALC-002Radiological Release ThresholdsA E N E R C O N for Emergency Action Levels REV. 2Excei'lence--Every Everyday. Attachment 3 PAGE NO. 33 of47DRILL STAMPEDE User Supplied InformationDa4fr/Tn: 12'1&2-13 07:54Cammnts:9sr Name: Stesminti Site AltIUT SiDkwbrfata Input:hndleel ,Mnd'elofltr 132 mil/hrGroumd "ad dfrrn: 130 d&greestker-select-tedShlYl classStuImtyC is: "D- &bnitwed S)GTnube1pure RIdease:Stea= Adt t5E+000 uC1i/ccStezmT1hwlate: L050 MlhbrRadacr Shm DalteTme-:Rinms Start DatTimn:FklmatedRdeas Duration:12/1312f13 06:54n1mn21on1 07:5410D hearsNudi& Matrme: Mtle Gas +Icimelon. am mpm-atf of gz& 02%CakrlatedNOBLE GAS rn rate: 1gE+07 wCi/secNOELECAS IODIMEPAYCIITIIUEMaCB& uCi/secMucUSl umCI/secKr-UM:1r47:Xe-13&Xe-MmlXe-IM:xe-13atXe4137-Xe-lit:1.1,1E-t-(3.43E+00X55-7E40004255NE+0044.2E-00431.0lM-t0D73.IZENXIS123E40+M127E&101I3ffiXM1-131: 31)E+0031-132: 3.22E+0031-133: 42824GB1-134: 41229+0021-135: L23E+00tCs-li:Cs-137:ce/r-13'/:Ce-141:1.a-lAO:3&t-99:RaIRb-106:Sr/Y-90.Sr-":Te-412:Zr-95:GOJE4WO0.0aE24000GOIXJ-0000.00E+000O.OaE+COOO.XE+tX0O0.3m+10000311+030121M 13 7?55:19 AM CALC. NO. STPNOC013-CALC-002Radiological Release Thresholds REV.2E N E CO N for Emergency Action Levelscxceldence--e'y projwer. day. Attachment 3 PAGE NO. 34 of 47DRILL STAMPEDE Results InformationDP,07033 111 I g laf2 DR ILl "mrzEn 12/1, 20130754 lw Nam: StemI.,m Aatcammmmis051.02.05.0751D.02U.Duuance0.51.02.05.0731.02.05.07.510.020.0mam0:02&230-340:45131CW]/Q Vain.3.750-406T1.00_-00v"5.'D42-0011.5412407C D2 DMI2-43S0059.11aE-0067-373E-0972_441E-0W79.10-S-kkzs~uraie frost RufusIamerniaa Wfmlel Bmdynoble go gamma0.0110o0420.0020.000o.oooomoo0.000anoble em gamma (reim)0.0110.0040.002-0.0000.000IPAGDos RaisIodine CDEexternal +.iflerual MUyrei(--Ifb) (--11r)0.019 0.1350.003 0.0170001 0.0170.001 0.(040.000 0.000 0.0010.000 0.000IME Iodine CDE(lerui+ imainual '&Tria0.0190.0070.0010.0000.0000.1350.0500.0170.0040.0020.0010&012A &'2013 754:42 AM CALC. NO. STPNOCOI3-CA LC-002Radiological Release Thresholdst3 EN ER CO N for Emergency Action Levels REV.&~celence--Everyptoje.r, 'vetydoiy Attachmnent 3 PAGE NO. 35 of 47DRILL PaTA , Results IoraaionILLDR LLRE%'iion 7.0.3.3 9,29,72011 Page2of2DR LMethodof Projection:STA:MPEDEOffsde Dose Projection (rem):I mileTEDE 0.007CDE 0_050l C.acultiom CompletedRESULTSWind Vlocity: 13_2nihrWind Direction: 180Release Rate: l.19E+07uCiisec10 miles0-0012 mifles0.0030.017miles0.001OI0wProjected dsn-afion of'releae: 1.0 hour0 days 0 hours 0 weeks 0 months sA General Emergency Requires a Protective Action RecommendationEVACUATE ZONE(S): 1SHELTER IN PLACE ZONE(S): 2AFFECTED DOWNWIND SECTORS: R, A, BAll Remaminin Zones Go Indoors And Monitor EAS Radio StationBased on a Dose Rate Projection of > 3 mremnir (Immersion Whole Body Noble Gas Gamma) at theSite Botmdary (1 Mile) for 15 minutes or longer the Emergency Classification Initiating Condition RAI(ALERT) has been met.PERFORMED BY:'NameREKIIIMID BY:Rdls'd. nage r:Ramdolo gic al Director121&92013 7:55:14AMDasThne121212013 7:54:42, AM CALC. NO. STPNOCOI3-CALC-002Radiological Release ThresholdsREV. 2E N E R C O N for Emergency Action Levels _EV. 2Exce ence--ver eptoe. Every day. Attachment 3 PAGE NO. 36 of 47DRILL STAMPEDE User Supplied Information,71.033 9/O DRELLDthfrrie: 12/17/201315:25commmtsUser Nam*: UEit Mew Site AmaIar S- s, mnztk Ilh Impxf:Qomn1k-dfl tadikctf 132 nt&rQonmile~wi dfrsrr 1la &grfeeslker-siec-tedStzliiy ClassSthiy (Clas: "D -Neufr."niirmpedklf" Vat 1Rine:Ilit Veat Rlase Rate mteretd 2Z--1007 Reatdr Shutdm Dahtsrne:Rinse Start DatiTume:dRelnseflnraliowNni& Iftdure:12117fD13 14-:251217/2013 15:25100 hemsQzpbnnturyCakuatedNOBLE GAS rmnse rate: 1!91-7i7u -eNOBLEGASN Iadi Cv1sacNadide RCi/sA,MucS& mCilsec10"-80_K,,r-w9:Xe-.131Xe-13iXL-135MXe-137-2527E4051.fl7.06E+M]9.0AE.4X15I:73E+ODS3.14E-03DX3.121+0X14621+-W0191E'0051+J-NX149.74E+0X1-131:1-132:1-133:I-lM:--135:1-135:301SE--N-5.12E+004Cs-1i:Cs-137:Cemr-144:Ce-Idl:Rn/Rh-l06tSr/Y-w-Sr-":Te-132:Zr-0:1.05M+01924E+0002.GE-+O02.94M.3531rE-033.+43o000i24E,-OD425GE40031XIG-OO21.82Edl)135E+tOD3.LV3-M1247T2013 3"2533 PM CALC. NO. STPNOC013-CALC-002Radiological Release Thresholdsr E N E R C 0 N for Emergency Action Levels REV.2.-, y; day. Attachment 3 PAGE NO. 37 of47DRILL STAMPEDE Results InformationDRILL Rv=03%M11 Page In!2 DRILLiDak(Tz 12fl.,2D13 1525 w N'ame: Util Vnt Site AraIDihnaz(miles)0.2.05.07-510.020.0Diltauc,(Mmiks)1.02.007.5IDG2.0L5.07.5l.o20.0Pinm. "wel TMme CELDQ Valn.@ounmiamos)(soc/a')0012 2.&,.0050105 L0372E-000:09 375SE-00-23 1.01D-0060-34 5. 7E-0070:.45 131 1541E-0072-43dE-M09.11CE-003.151E-OW77338-007(3.2458-002441E-09.109E8-EImmursioa fob Bodyxale Zu gunoan(r.am~r)0.0820-0320-0120.0130.0020-aolImmersioaInoal BodyaRti. zgofmm. (rem)0.0120:0030.0020-0010ACO0IPAGDosoeHaloMTE Iodine CME(ron/ic~) (rom/ir)0.160 13640.060 05100.021 0.1760.005 01410.003 0.0210.,00 0.0140.0101 0.005Iodine CDEoxteroul + intern!j MUTSUi0.1600.06D0.0210.0050.0020.0(01136405100-1760.0410.0210.0140M0051217/2D_13 3:25:21 PS CALC. NO. STPNOCOI3-CAL-C-002Radiological Release Thresholds CALC. NO.2SPNOC13-CAC-00EN ER CO N for Emergency Action Levels 1EV.2Fx,, cP-11enrydojy. Evetyda. Attachment 3 PAGE NO. 38 of47DRILLResults information9)2ge2011 Page2of2Ca_.-intions- CompetedRESULTSDRILLleledodofProjectioa: WindVelocity: 132 mi/hr Relee Rate: l.19E-'07 uiQSTA-MPEDEWindflirerdon: 180Of0ste Dose Projection (rem):I mile 2 mile- Pmils 10 mile!TEDE 0.060 0.021 0.005 0.002CDE 0.510 0176 0.41 0.014Projected duration ofrelease: 1.0 houTsA General Emergency Requires a Protective Action RecommendationEVACUATE ZONE(S): 1SHELTER IN PLACE ZONE(S): 2AFFECTED DOWNWTIND SECTORS: R, A, BAll Remaining Zones Go Indoors And Monitor EAS Radio StationnecBased on a Site Boundary (1 Mile) Dose Projection > 0.1 rem TEDE andlor 0.5 rem Thyroid CDE theEmergency Classification Initiating Condition RS 1 (SITE AREA EMERGENCY) has been met. IPERFORMED BY-NameREVIEWED BY:Rod Mhnager:Xnadiological Director12/17/2013 3 25:28 PMDatv'TfieDat&eTime12'17fl013 3:25:21 PIM CALC. NO. STPNOC03-CALC-002Radiological Release ThresholdsREV. 2, E N E R C O N for Emergency Action LevelsExceilence-Everyptojecr. Everyday, Attachment 3 PAGE NO. 39 of 47STAMPEDE User Supplied InformatiOn DRILLDRILL DRism7.033 9M01IDhf/imm: 12f17M2._3 1513CeomatmSlr NamE: StEM LI AXeaIThaf SumuSed]Oeqmdlewi adiwlocity Ifl nil/hGrmmdie tmdsfdrkn 110 LgreesCsmStbbmT Ycl : "D -Neutarxmifsklmed SGTWIhRpInre ReiesSteam Arftif A45RE+001 uoCt/cStemmlhwRzte: LownlEbrRector Shut&=e m DateTime: 12/171913 1413Rase Start DatI/Tume: 12/17/201315:28hiuntedRleas Dwatori LOG homrsNndi& MAfhre: NuMo Gas +LItmeJ&O.. 2S p~rC4t oftmold gas: 01%CakuktINOBL'E GAS ralas rat.: 1102-001 m /secNOHILEGASNmUtb& aG/seCIODINENudkh o42i/sPARflCELIEMNumcis .0/secKr-83M:Kr47:Kr-97-X-13DIMXL-133MXL-lZM:XL-Un:Xe-137-XeL-U381.14E+003.4.5-+00S1IE+0052.55E+00591E7+005127E+0063.SE$XJO6121E-004114E40041]-131:1-132:I-lM21-133:1.-135:323E+0OG4-9aE400$1-24E4005Cs-134:Cs-UL7-Ce/Pr-lit:Ce-141:I.e-lO:lb-l(:RR-l03:Sr/Y9tSr-49:Te-OS:Zir-9:O.O+W00O.C(E+(O0O.OA+ODOO.O[E+O0000.3E+0000.0M+000O.XE+O000.O4IE-tO0O.DXI+OOD12J/7(/013 329:03 PM CALC. NO. STPNOC013-CALC-002Radiological Release Thresholds REV.2F ,.E E C Nfor Emergency Action LevelsEyctllence-Everypo]im. Evetyday Attachment 3 PAGE NO. 40 of 47DRILL STAMPEDE Results InformatoD-RILL Psgelaf2 DRILLIlairm 12117.,2013 15:28 Thu Na: StamLnM SkB ArmCUmmEts:mf15..usmiane=hJt I(miles)031.02.05b07-510-020-0Distance(mniles)0.52.05.07510-02O00DiSLfJe(Mniks)031.02.05.07520.0Plume T~rral Tuao0:050230-340-45[31Value21696-001.032E-003.45E_-0071.0.,'1.-0O63.9513-42US4IE-007CHVQ DflL(cecj')2-4360059.11C.-0067373E4-02-441E-1079-109E-.0I& M .Doe RwIsa~inn Whle Body0.1110-04230.0150.004O-O20.00101131Imaniaz Wfole Bodyoatblh Mgs gamm (rem)0.1110.0420.0150.0040.0020.0010.0017Mlorterusi +.aturnl0.1w90.0720.0250M60.0020.001LODose RatesIodine CD]13540.5060.1750.(04101Ml0.0130.0055 !E Iodize CDEextrnal + inieoal Tkyraid(cern) (Mm)0.189 13540.072 03500.025 0.1750.06 0.0410003B 0.0210.002 0-0130.001 01M0512117i2..013 23".53 PM CALC: NO. STPNOC013-CALC-002SRadiological Release ThresholdsjE N E R C 0 N for Emergency Action Levels REV. 2Excelle,,ce--Everyproect., ve.,day. Attachmnent 3 PAGE NO. 41 of 47STAMNIPEDE Results InformationDRILL id~onTO3 3 9!2&'2011 Page2of 2 DRILLCa-u'donCti ompletedRESULTSWind Velocit- Wind Dir eion: IgoRelease R-te: 1.20E+OOS uCilsecMlethod of Projec don:STAMPEDEOffsile Dose Projection (rem):ImileTEDE 0.072CDE 0.506-miles0.0250.175miles0.006OL04110miles0.0020,013Projected duration ofreleae: h.O thourA General Emergency Requires a Protective Action RecommendationEVACUATE ZONE(S): 1SHELTER IN PLACE ZONE(S): 2AFFECTED DOWNWIND SECTORS: R. A, BAll Remaining Zones Go Indoors And Monitor EAS Radio StationBased on a Site Boundary (1 Mile) Dose Projection > 0.1 rem TEDE and/or 0.5 rem Thyroid CDE theEmergency Classification Initiating ConditionRSl (SITE AREA EMERGENCY) has been met.PERFORMED BY:REVIIWED BY:RadiiiLd.tntger.,'.adiological DirectorI 17T2013 3:29:00 PMDaterime.Daterime12'17fl013 3-2&:53 PM CALC. NO. STPNOC013-CALC-002Radiological Release ThresholdsEN ER CO N for Emergency Action Levels REV. 2Excelence--Evey projec. Every doy. Attachment 3 PAGE NO. 42 of47DRILL STAMPEDE User Supplied InformationDRML PxW-47.0-33 9z2f01W1DRLDa mdt e : 12d17i2013 15:26C-nmisur fNam: Uni 'it (ekmwl=au SulitdmztILbmrtqwdeDatallhhopmt:Gr(mmudlk aMdwlo-ity 131 mit/hrQound IuL tdfranr 10 &O greeUer-e ttedStahly ClmSlaby clas: "D -NetufriItndtme~dUhl Vent Rinse:11oi Vent eRate terae 2.50E+CM nCi/sec1Reat Shuttun Dat/lutme: 12/1712113 14:26Rinse Start Datg/rTi: 12117/2013 15:26FltinmtedRolmsefDum-io- 1-00 hImrsNucdi Mhlnre:ClaphntnqyCauIcuedNOBLE GAS rne rate: LiB'O u -ilsecNOBLEGASNudkide m/sKIODMIENuduikb RUiSKPAR3fCL.AUfNucL& mCI/sacIr-tmKY-IS:1K,--45MKr M7:lKr-4S:K,,r-It.XTe-lW2M2E+0061.0-,M+0067.0Z2+0069.03E+_01.7313+0073.1(E+0013M22E+0X76=l+007191E+al61.45E+0X179.6fE-0061-131:1-132:1-133:VIM:1-L35:3.1914M3.0811+005.12E-405Cs-lid:Cs-137:celpr-lU:Ce-141:La-lID:11,1-99:Nm/Rh-l~dLSr/y-w:Sr-":Te-132:Zr-95:1.05E+aD26.25E-(X)I82.10022.1E--002531EOD3.43EWCC1.25FA-0B9.1CE-0031.321-0013.13M-0121q742013 3:2637 PM CALC. NO. STPNOCOI3-CALC-002~ E N E R ~ NRadiological Release Thresholds REV. 2C 0 N for Emergency Action LevelsY-pr. Attachment 3 PAGE NO. 43 of 47DRILL STAMPEDE Results InformationDRILL %Pagelaf 2 DRILLDaftznrm 12mfl2013 1526 UsNlk ne: CIEMMa,mflur I~aftgDixtnsa051.02.05-n7-510.020.0Distuca051.02.05.07510.?20.0Diunca(siles)0-51.0205.07.513.020.Plus. bad Min.(hecunsmiurths)01150-230-45131.C111V YangJL032E-0053.755-1"06LiME-GOW5.7DE-077I1-W1E-007CHUQ UM'2.43SE-09-11tH-GM31521E-0IM7372-0072-441E-009.109E-00&easunde DoseRtIsrieu flu! 5e4m0z79033220,117C.C290.0160.0100.00MImmr"ion Wfk.le B-dynabul gas gmma (rum)0.8790-3320.1170-M90.0160.0100-03MEm lodiza CD,exerrsl + itenlau "lyraid(remskr) (nsir)1.5_ 13.640.601 5090210 13,620.050 0.4110.027 02140.017 0.1350.006 OM05ME bidine C DEcuornu!l + jut.rual ¶Ikyri-d(,rum) (res)1.5980.60102100.0500.0270.0170.00613.6465(3M1-7620L41102140.1350.0501211..013 3 2 625 YM CALC. NO. STPNOCOI3-CALC-002Radiological Release Thresholds R EV__2J E NERC0 N for Emergency Action Levels REV. 2Fxcelence--Ever/project. Every day. Attachment 3 PAGE NO. 44 of47STA-MiPEDE Results InformationDRILL Rev-ion7Oit3 92Wi3011 Page 2of2 u DRILLC.cultaliorn CompltedRESULTSWindVelocity: 132ni/hrWindflirection: 120Release Rate: 1.19E+-0O uCisecAfethod of Projection:Offsite Doe Projection (rem):I mile 2 mile 5 miles 10 milesTEDE 0.601 0210 0.050 0.017CIDt 1-62 0.411 0.135Projected durta-on ofreleme: 1.0 hour0 days 0 hours 0 weeks 0 months sA General Emergency Requires a Protective Action RecommendationEVACUATE ZONE(S): 1, 2SHELTER IN PLACE ZONE(S); 6. 11AFFECTED DOWNWIND SECTORS: R, A, BAll Remaining Zones Go Indoors And Monitor EAS Radio StationBased on a Site Boundary (1 Mile) Dose Projection > 1 rem TEDE and,/or 5 rem Throid CDE theEmergency Classification Initiating Condition RG1 (GE NERAL EMERGENCY) has been metPERFORMIED BY:NameRfMIEW-ID BY:Kad .iinagerRadiological Director11q 7/2013 3:26:33 PFMDateflimeDaoe.Time121 7,2013 326:25 PM CALC. NO. STPNOC013-CALC-002r Radiological Release Thresholds REV. 2IAeO E for Emergency Action Levels 3EN.4F.xce.,flnce-E-Evpy profect. Every day. AttachmIlernt 3 PAGE N O. 45 of 47DRILL STAMPEDE User Supplied Informaion DRILLDRMDRILLm.-33 f&qIDhhilme: 12q7,2013 1530CUMMnRhe-r Namme: SteamLimeIf-rmo ndll ,tadwabc.ty 1-2 ni/krQacnlmkewdi dfrimn I0 yCIlassStibilty Chus: fl -Nmenr"3tnihorMdSJGTuhe Raipiur debasc:St 45-M+@02 uCiWcStem fl=wRate: LONO mllrOBactar Shut&= Datwflme: 12/17VIh13 14:30Rmnse Stat BatWklma: 12/17l2013 15:30BMtantedR1ease Duratiar 1. kournNmrh& 1skim:e NoM. Gas +Jmhtelotfm as pwc-rt ofnade gas: C26LNO.LECAS reeae rute: 12 009 nCi/secNudILEnC/SNudide IODMLENudide MiUMePARIICLAIENurfida aCilsecfl-ISMKr-IS:Kr4ffMKT497:KY-ItKr-StXe-l31n&xfL&.12-133k!XLe-IS:Xe-13SSXL-137-12u?-Mt1.14E+0063.45E-IXT12SM4U06925E+0064.13E-01127E4UJF73.LqE-041712M1+005124F-+00!135E'+005.-131:1-132:I--1]:1-L03:1-134:V1,.5:3.24E-054-QE40054214H+00tCsr-134:Cs-137:Ce)Pr-1dA:Ce-141:La-iS0:Mkb-99:MdMR-106:En-l~l:Sr/Y-gI:.Sr-ID:0.IX4OO.DEE+CX)o0.04E+C00OAXE4000O.D0E+000,O(E+OO00.UfE-NXO00.(XE+000O.4E+00Te-132: O.X+CCO0Zk---: 0.CCE+O012A1712013 3:3035 PM CALC. NO. STPNOC013-CALC-002Radiological Release ThresholdsF4ENERC 0N for Emergency Action Levels REV. 2Fxceflence--Everproject. Every day, Attachment 3 PAGE NO. 46 of47DRILL STAMPEDE Results InformationDRILL7.0dskm23&3 t2O11 Pge lo2 DRELLDN rnr 12172013 15:30 Us P&M: Stam.n CGEMMmts:(miles)051.02.05.0751031.02.05.07_5*(miles)0.51.02.05.0751.102CLOMnPlume Trarel S.m(iunrsrmihetes)0:020050:230-340:45131CULtI VYang(ser/m/)I.03MM003.75.-54-065.004-0063-ME-007154E-oCHUQ DI1PL2A43d-0059.11CE-,W3.151.E-.D7.373E-003.,845,-007i2441E-0079:109.E-I ra. Dose R Iioneniea lde Body7abl0 zs pummz(0DEm/k)1.1090L42360-1530.0400JO220.015Immersion Whlel Bodynoble jas p tmms (rne)1.109OL4240.1530.0400JO220.015-OM6LPAG Dos RatesMEh Iodinea CDEextersal+ intiruer. fyroi'(rem/kr) (remir)1.2950.71702540US0.03400220.008135375.1!581-7470.2110.1340.049MME ZIodine CDEextrnal + intnrnal Murvid(remn) (rem)18950.717D02540.0630.0340.0220.008135375.-1.74702110.1340.049 CALC. NO. STPNOC013-CALC-002Radiological Release Thresholds REV. 2EN E R C 0 N toraEmergeny ActionE Levels REV. 2Fxpene Eey pojet vefydoy Attachiiieiit 3 PAGE NO. 47 of47PEDE Results InformationDIRILL ,Rion 7.03.3 9-2&2011 Page2of2 DFRLLCalcultions CompletedRESULTSMedthodofProjection: WindVelocity: 132m.,ai Release Rate: 120E+009 uCi'secSTA-MPEDEWindDirection: 180Oite Dose Projection (rem):1 mile 2 miles Smiles 10 milesTEDE 0.717 0254 0.063 00o2CDE 1,747 0.407 0.134Projected duration ofrelease: 1. hoursA General Emergency Requires a Protective Action RecommendationEVACUATE ZONE(S): 1, 2SHELTER IN PLACE ZONE(S): 6, 11AFFECTED DOWNWINXD SECTORS: R., A, BAll Remaining Zones Go Indoors And Monitor EAS Radio StationBased on a Site Boundary (1 Mile) Dose Projection > 1 rem TEDE andfor 5 rem Thyroid CDE theEmergency Classification Initiating Condition RGI (GENERAL EMERGENCY) has been metPERFORMED BY:Rn=7D BI. :NameRNlEW1TD BYDBad ihanager.,Rmdlological Director12/1712013 3:30&.48 PMDate,/Tfie.DateMime1217/013 3:3039 NP CALC. NO. STPNOC0 I 3-CALC-004ID E N E R C O N CALCULATION COVER SHEET REV. 2.xcefl>n fe--ery ptoP G N Every" daPAGE NO. I of 17Title: Fission Product Barrier Failure for EAL Thresholds Client: South Texas ProjectProject: STPNOC013Item Cover Sheet Items1 Does this calculation contain any open assumptions that require confirmation? (If YES, Identifythe assumptions)2 Does this calculation serve as an "Alternate Calculation"? (If YES. Identify the design verifiedcalculation.) Design Verified Calculation No.3 Does this calculation Supersede -an existing Calculation? (If YES, identify the supersededcalculation.) Superseded Calculation No.Scope of Revision:Revision I incorporates the source term provided by STPEGS.Revision 2 removes an incorrect assumption of the RCS density and changes the Safety-Related designation to Non-Safety Related.Revision Impact on Results:For Revision 1, the monitor readings decreased using the updated source term.For Revision 2, the results decreased from 0.448, 137, and 547 R/hr for: the RCS, Fuel Clad, and Containment barriers to 0.134,40.2, and 383 R/hr respectively.Study Calculation 11 Final CalculationSafety-Related Non-Safety Related(Print Name and Sign)Originator: Caleb Trainor Date: 2/16/2015Design Reviewer: Chad Cramer Date: 2/17/2015Approver: Marvin Morris , Date: 2/17/2015 ENERCON CALC. NO. STPNOC013-CALC-004Eceienrp-Ev ey eery CALCULATIONREVISION STATUS SHEET REV. 2PAGE NO. 2 of 17CALCULATION REVISION STATUSREVISION DATE DESCRIPTION0 03/04/2014 Initial Issue1 03/21/2014 Updated the source term2 02/17/2015 Designate as Non-Safety RelatedPAGE REVISION STATUSPAGE NO. REVISION PAGE NO. REVISION1-8 2APPENDIX REVISION STATUSAPPENDIX NO. PAGE NO. REVISION NO. APPENDIX NO. PAGE NO. REVISION NO.A 9-17 I CALC. NO. STPNOC013-CALC-004E N E R C O N Fission Product BarrierFailures for EAL Thresholds REV. 2Excelen---vry project. Every oy F PAGE NO. 3 of 171. PURPOSE AND SCOPEThe purpose of this calculation is to determine whether a breach of Fission Product Barriers hasoccurred based on containment radiation levels. The calculated levels will be used as threshold valuesin the STP Emergency Action Level (EAL) Technical Basis Document which implements NEI 99-01,Revision 6, "Development of Emergency Action Levels for Non-Passive Reactors" (Reference 3.1).The failure of the fuel clad barrier, reactor coolant system barrier, and containment barrier will beanalyzed individually. Values will be derived for the containment high range radiation monitors RT-8050 and RT-8051 for the three barriers.2. SUMMARY OF RESULTS AND CONCLUSIONSThe results of this calculation are listed below.Table 2.1: RT-8050 & RT-8051 Response toFission Product Barrier FailureFailure Monitor Reading (R/hr)Reactor Coolant SystemFuel Clad 40.2Containment 383Readings on these monitors at or above the values listed indicate a failure of the associated fissionproduct barrier.3. REFERENCES3.1. NEI 99-01, Development of Emergency Action Levels for Non-Passive Reactors, Rev. 6.3.2. PSAT 3075CF.QA, Dose Calculation Database for Application of Alternate Source Term toLOCA and FHA for South Texas Project Electric Generating Station, Rev. 3.3.3. A41009-00458UB, Unit 1 RCS Volume and Temperature Assumptions for Evaluation ofRadiation Sources, Revision 63.4. Offsite Dose Calculation Manual, Rev. 17, March 2011.3.5. Regulatory Guide 1.183, Alternative Radiological Source Terms for Evaluating Design BasisAccidents at Nuclear Power Reactors, Revision 2.3.6. STPEGS Drawing 9C129A81105, Radiation Zones Reactor Containment Building Plan at El. 68'0", Revision 33.7. MicroShield 6.203.8. Federal Guidance Report No. 11.3.9. STP Procedure 0ERP001-ZV-1N01, Emergency Action Level Classification, Rev. 10, Draft.3.10. ENERCON Services, Inc., MicroShield 6.20 Computer Code Verification, STPNOCO13.3.11. STPEGS Technical Specifications, Unit I Amendment No. 170, Unit 2 Amendment No. 1583.12. NOC-AE-07002127, Request for License Amendment Related to Application of the AlternateSource Term Regulatory Guide 1.183 Standard Review Plan 15. CALC. NO. STPNOC013-CALC-00410 E N E R C0 N Fission Product BarrierFailures for EAL Thresholds REV.2Excellric-Fvery projc Fvry doy, F r oe l PAGE NO. 4 of 174. ASSUMPTIONS4.1. Monitor LocationThe Containment High-range Area Radiation Monitors (RE-8050 and RE-8051) are locatedinside the Reactor Containment Building (RCB) close to the outer structural wall. The monitorsare mounted approximately 5 feet above the 68'-0" elevation (Reference 3.6). Limitations of themodeling software used (Reference 3.7) requires that the geometry be configured with themonitors placed immediately outside the source volume rather than inside the source volume.This slight difference is assumed to be negligible.4.2. DispersionThe entire reactor coolant system (RCS) mass of noble gases are released into containment andevenly dispersed within the Reactor Building volume above the refueling floor (Reference 3.1).However, only ten percent of the iodine is volatilized and released from the RCS (Reference 3.5).It is assumed that all other fission and corrosion products are not released as specified inReference 3.1 developer notes.4.3. BuildupBuildup was ignored, as the detector is immersed in the atmosphere. This is conservative, as itproduces a lower dose, which provides a lower detector setpoint level.4.4. ActivityThe activity of the RCS corresponding to the failures of the RCS, fuel clad, and containmentbarriers are Technical Specification limit, 300 ýiCi/g DEI, and 20% fuel failure respectively asspecified in Reference 3. 1. The technical specification limit is I [tCi/g DEI per Reference 3.11,Section 3/4.4.8a. Reference 3.1 states that 300 piCi/g DEI is equivalent to 2-5% failed fuel whichresults in a conservative estimation of 1200 [tCi/g DEI for 20% failed fue OENERCONExcelence--very projct. F~vey Fission Product BarrierFailures for EAL ThresholdsCALC. NO. STPNOCO13-CALC-004REV. 2PAGE NO. 5 of 175. DESIGN INPUTSThe normal operating coolant inventory (for noble gases and iodine) is taken from Reference 3.12Table 4.2-20 and is listed in Table 5.1.Table 5.1: Reactor Coolant InventoryNuclide Activity (iCi/g)Kr831m 3.70E-01Kr85m 1.50E+00Kr85 7.60E+00Kr87 9.80E-01Kr88 2.80E+00Kr89 8.40E-02Xe131m 2.80E+00Xe133m 4.20E+00Xe133 2.40E+02Xe135m 4.OOE-0 IXe135 7.60E3+00Xe137 1.60E-01Xe138 5.80E-0 11131 4.25E+011132 6..00E+01133 7.OOE+011134 1.30E+011135 1.90E+02The dose conversion coefficients for iodine are taken from Reference 3.8, Table 2.2 and are listed inTable 5.2.Table 5.2: Dose Conversion FactorsDose Conversion Factors(Sv/Bq)1-131 8.89E-091-132 1.03E- 101-133 1.58F-091-134 3.55E-111-135 3.32 E- 10The containment free volume is taken from Reference 3.2 item 3.2 and is 3.8x106 ft3.The mass of the RCS is 2.658xl 08g per Reference 3.3.6. METHODOLOGYEquation 6.1 shows the calculation used to find the release concentration of each nuclid CALC. NO. STPNOCO03-CALC-004l E N E R C O N Fission Product BarrierFailures for EAL Thresholds REV. 2 of17Exce en e-F ery pm e Cve Ey doy PAGE NO. 6of1(XI-13,*DCFI-131]Euto .Release Activity =Ci

MRCS

Equation 6.1Si=13DCF1 /Where:Ci is the concentration of each nuclide in the reactor coolant inventory listed in Table 5.1 ([tCi/g),MRCS is the RCS mass taken from Reference 3.3 (g),The third figure in the equation scales the normal RCS inventory to each barriers specifiedactivity,X1-131 is the concentration of 1-131 specified for each fission product barriers DE1 (lCi/g),DCFi is the dose conversion factors from Reference 3.8 (Sv/Bq), andIi is the concentration of iodine found in the normal operation reactor coolant inventory (lCi/g).Because the releases are dictated as levels of DEI, dose conversion factors (DCF) must be used todetermine release activities. The STP ODCM dictates that the DCF which define DEI are to be takenfrom Reference 3.8. Using these conversion factors, the dose related to I ýtCi/g, 300 pCi/g, and 1200pCi/g is calculated.The dose rate from 1-131 is then compared to the dose rate from the full iodine spectrum in the reactorcoolant inventory found in Table 5.1. A ratio between the two dose rates is used to scale the coolantinventory to the dose equivalent specified. This is shown in Equation 6.1 and the tables in section 7.The containment building is modeled in MicroShield as a right circular cylinder with an equivalentvolume to the containment free volume. This is filled with the evenly distributed source activity with adetector placed at a location equivalent to actual placement.The MicroShield input and output information for each case can be found in Appendix A.MicroShield is appropriate for use in this calculation and has been approved and documented byENERCON Services, Inc., MicroShield 6.20 Computer Code Verification, STPNOCO13.7. CalculationsThe spreadsheet below contains the calculations described in the methodology sectio CALC. NO. STPNOC013-CALC-004O ENERCONExceflenc--Everynprojec. Eveiy doy,Fission Product BarrierFailures for EAL ThresholdsPAGE NO. 7 of 17Table 7.1: Release Inventory for Failed Fission Pr(NuclideKr83mKr85mKr85Kr87Kr88Kr89Xel31mXe133mXe133Xe135mXe135Xe137Xe13811311132113311341135ConcentrationpCi/gm3.70E-0 I1.50E+007.60E+009.80E-0 12.80E+008.40E-022.80E+004.20E+002.40E+024.OOE-017.60E+001.60E-015.80E-014.25E+016.OOE+017.OOE+011.30E+011.90E+02Gross ActivityptCi (concentration*mass)9.83E+073.99E+082.02E+092.60E+087.44E+082.23E+077.44E+081.12E+096.38E+101.06E+082.02E+094.25E+071.54E+081.13E+101.59E+101.86E+ 103.46E+095.05E+10Ci @ 1 I Ci/g DEI-131Ci total=activity* Scalingfactor/1061.57E+006.35E+003.22E+0 I4.15E+001. 19E+OI3.56E-O11.19E+011.78E+011.02E+031.69E+003.22E+016.77E-0 12.46E+001.80E+002.54E+002.96E+005.50E-018.04E+00oduct BarriersCi @ 300pCi/g DEI-131Ci total=activity*Scalingfactor/1064.70E+021.91 E+039.65E+031.24E+033.56E+031.07E+023.56E+035.33E+03_3.05E+055.08E+029.65E+032.03E+027.37E+025.40E+027.62E+028.89E+021.65E+022.41E+03Ci @ 120OOACi/g DEI-131Ci total=activity* Scalingfactor/1061.88E+037.62E+033.86E+044.98E+031.42E+044.27E+021.42E+042.13E+041.22E+062.03E+033 .86E+048.13E+022.95E+032.16E+043.05E+043.56E+046.60E+039.65E+04*The scaling factors used in this table are calculated in Tables 7.2 and 7.3**The values in bold have been multiplied by 0.10 to account for the 10% volatilization of iodine during the acciden O ENERCON 0Excelence-Every project Every doyY.CALC. NO. STPNOC013-CALC-004Fission Product BarrierFailures for EAL ThresholdsPAGE NO. 8 of 17Nuclide11311132113311341135Table 7.2:................................bI e............A ActivitygCi/g4.25E+0 I6.00E+0 17.00E+0 11 .30E+011.90E+02Full Iodine SpectrumDCFSv/Bq8.89E-091.03E-101.58E-093.55E-113.32E-10Total =...... ~ ~ ~ ~ ~ ~ ~ ~ ~ ... .......................tv t

CActivit y DC F(pCi/g)*(Sv/Bq)3.78E-076.18E-091.11 E-074.62E-106.3 1E-085.58E-07Table 7.3: Scaling FactorsDose Equivalent Activity(ýtCi/g DEI)3001200DCFDEA*DCF(Sv/Bq)8.89E-098.89E-098.89E-09(paCi/g)*(Sv/Bq)8.89E-092.67E-061.07E-05Scaling Factor(DEA*DCF) /(sum(Activity*DCF))1.59E-024.78E+001.91E+01 Fission Product Barrier CALC. NO. STPNOC013-CALCO004r EN ER CO0N Failures for EAL Thresholds REV. 2Exelene-I'vy polct Fvefyda Appendix A PAGE NO. 9of 17Case Siumainy of Fuel Clad Barier Page 1 of 3Micro!'hield 6.20 (05~-MSD-6.2O-1158)EnereronFe~M 1Re2f1DO Fil I,-,.Cftecked_Case Tile-- Fwel Ciad BafTi~rDescriptiont: ! P0CGzCGeometrin 8 -CyI djr vIulufi -End1 SIIeI1s14*1gMt ~ .e3 m (192Ft 11 5 n"Radius .&3c (7E ft)Dot-e P&ýntaA X YI 50ý.6 CM a 112,64 cmý I j c2 0it ;,,I 1i93 110 0 in1 j _7ftE _- __ýSN~ew N DimesloaI HAMatai Deni*tyS,"r; 156-s10 C1, Al .012Source Thput 91 Gu ngj S-a '_w: IcN of G~p 21ULAeer *Ile1'gv Ciulo : .015phoýtmw,3 < 0.015 I lnrudadT,132 2.4Q+09 0 .01 2 36-09732014 1-1233 2.65+Q 1.92 11 3 0t55e-X05 .33÷1_13A 5.5000me- 131 2.035 Ue + D1, 55ý,629 07, 21 795-00G1-135~~ CG e + 0400+0 2,9748a+0i *D I9s0 I6I 65n 00ýe+CZ00 2.349,75E +011 6.5765e-N_0S Aj4323e+0IKr-87 4.1 b(+ 1_!53 55a7+ i11 4 298G0e-005S 3C 359e3+ ,v,11 t-81. 17 2,?,+ 10 3. 6r,7 C -0C6 1.35642.2-0,71Xe-lImIIa 1. 1 KC la+ 0 4.45+ 11 .34-0 4.S9+0)(*3 3 I 1 2, I 3774?11LJ13 I 05944e-CX02 3.90564I+X002Xe- 333m 1.7890af_4+C01 65.5560f5+011 I .6435e-OC4 b8209e+1000Xs- 135 3,22F004+C'0 1.19 Sa+3!2 3 33111-004 .2339a4+001Xý- 13 5m ,P I.9 0e +CX0 62530s+010IC .7503es-005 F 6,76f*-o00Xe-137 6.77D0s-001 7.50C9eI01I7.0-15X-f, 2 .5942 e- 00u1X I I t2.4C -00+ý" ,0 Y. 1 02e4-" 1 2 54 7 *-Q X 9;42566-001BuldpTh atrllrdeeic s oucEbI- ~ N~ Fhaenom Rate Fluevee Rate Exposiare RAte Exposure RateHeY htot/ mevpvn3/c aC Pmev/cm.laec mR/hr mth#4 Eufu With Uufldap No sul~duP With 11Mu~dp40.015 2.437ie+12 4 1. 29 1!z F2 1 A 53e , (2 .1 07,E+O I 2461+01file -MCJProgran%2OFiles%/2 O(x86)/M cro ShieldlExamples%/Casefil es1thflA%1/20 gC L. 2117/2015 Fission Product Barrier CALC. NO. STPNOCO03-CALC-0040 E N E R C O N Failures for EAL Thresholds REV. 2Fxcellence-EFveyprojet EveFy yd'y Appendix A PAGE NO. 10 of 17Case Summary of Fuel Clad BarrierPage 2 of 30-430.60.11-00.520.30.4ATOWS1.880e+132.13 le + 11. 804e +112-370e+112.069e + I2.644e + 11J , SOe+1I2.605e ,105. 89B + 033.841e+23I.03?L+003.852~e-023.232e,033. 144 &-02I. G4 3.e-031. 419t -03L. 459e-032. 604e+032. 930e- 035.755e+0U31. 0 1 E+041. 1496+3&-C4.860e+04S. 1 45e032,3130e+041, 70 5- 005,761e+024.394e +033 .9686+021 261e+031 .66'e+(131.65r0e+032.911e+033.17.4e-036.156+e031.0716+041.198e+036.55'3e+046-.344e-015.964e-01,2-032&+r0O2-785e+C-D2,S817e6,0O4-9526+C05-309'e+001.sm.e+c014.334".28.072e+013.640ei-017.755e+007.52 7e-012.45ie -DG3.271e+005.548e+0,35.s551+001.041e+011 .857e+011.626e+004.483e.021.8816+02f~ie:///CJlProgram%2OFiles%20(x86)fMcaoShield'ExamplesICaseFiles/HTh1/1%20-)iCi.. 2/17/2015 Fission Product Barrier CALC. NO. STPNOC013-CALC-0040 E N E R C O N Failures for EAL Thresholds REV. 2Exc,,nre-E'project, ,vetydoy Appendix A PAGE NO. 11 of 17Case Summary of Fuel Clad BarrierPage 3 of 3to.,zfile..f//C:IProgramlc2OFiles%2o-O(x86)/MfiaoShieldf-xamples/CaseFiles/HTMEl/%2OgiCL.- 2/17,'201 5 Fission Product Barrier CALC. NO. STPNOCO13-CALC-0040 E ENE R C O N Failures for EAL Thresholds REV. 2nellec-Fry-roj- Evef day. Appendix A PAGE NO. 12 of 17Case Sunmmary of RCS BarrierMicroShield 6.20 (05-MSD-6.20-1158)EnerconPage 1 of 3pa'geDOS FileRun DateRuan TlmeDuration-t300 WC, DEI.mti6~Fcbruary 17, 012ýS3A45 PMM 0,:0:Do0File RerDatatByChe-ked(As TfflIei R.Cs BarrierDescriptiom 300 PCI/cc8 ffeo -Cy!i~ra8r Vdolume -End SýlIeldsSI~urce DlnterltonE$Height 5.9c+3 cmRadius 2.3e+3cmf 192 ft 11 .5 in)ý7sfrt)A*1x y z601.6 CmI 582.64 cm 1143 cm20 lt 4)[)in 11;3 FT00 In 37 It 60 ýShieldsShield N Ditmensimi materilasouice 9.66+10 CM3 AirAil Gap AXTSource Input -Groupinlg Kettbod -Standard LatticesNumber of GPMups 25Lower Ewgy Cutoff, 0.015pwunts < 0.015 " adaldedUllrary : rv0.001220.00122NucitdeI- 13t1-1321-1331-134Xe-137Xe- 1335.40001e-a-0247.600r8+0021.65008+003ý1. 91008+0 D 31,:40rt!-M33.508+01,07008a+0023. koc0e+QC`3.05008+e'005UC30e039 f-S008+0035 r08008+022 0300e+ý0027 370Ce-002buecuerel1.9980e+(0132,8194e+013ý332;938+0137 -0-57Ce+ G1335705se+016L1 72le+C1417261)2e,313-S.5926e-003i7,8918e-0039.2071e-c()]1 7088e-C032.496r08-0024 8676e-C0039'9942e-0021978 18-Q023 687rje-0023.6870e-0023 .1588 e+ý0005.5201e-00299942e-GO2S2612ii-0032.10248 0037 532;98-0032.0693e.0022.9200800923.4ý0668002c.3227e.+0010037,3-'19 18+ DO24 7518ý,+ 021-3612t+01)34,1002e+101.1.M42e8-0031.1687t-+1052,04248+003ý3.69788+00C31.9486"80027.77898+ý00112.8242e.002BLIldup : The maaittLV refaelele IS -SoUfceIneoM" ,rameteis20RadialCOecumnlerfIlliaI1t10Enetgy04eV0. .......015ACtivYty Flpulca RatePhorara/ac l~eV/O~n2/**7.436e-14 ~AI &* 8+9 4FteritsFluence RateNev/cmli/secWith Buildup4.34le-04Exposure RatemR/hrNo Buildup3.311e+03Exposure RatemR/hrWith Buildup3.726e.+03ffile:W/C /rogram%,2OFilesl20(x86)!NlicroShieldVExampkesiCaseFiles/HTMLJ3O00%2OpiC. 2117"2015 Fission Product Barrier CALC. NO. STPNOC013-CALC-0040 E N E R C O N Failures for EAL Thresholds REV. 2F vey da Appendix A PAGE NO. 13 of 17Case Summmry of RCS BamerPage 2 of 30.030.080-.15020L3o4.01.55.622e+ IS4. 142e -152.598e -116 .3 10e +133.8 7Be+ 142.448e. 135.954L 136. 399 e, 1-35.409e 137. 104e +136.200e 138.070e 131.ý047e+147.787e- 12-1,773e ,111.149e+16I .539e +063.ft96+063.0O886+,-G1. 158e,+C59.683e+059.437e+043. 123p, 0,4.2F 16+054. 375f,-,057,803e,+G58,6314+05ý_1. 724e- (,,3.027e+063. 434e4 0-51.053e+04IA55e+072,436,E-061.7 1 e+0D53 774e+055.004R4055.033-+058 742e,059.514e+051. S54,4ý0,53.206e -OF3.532-*051.689, +041.960e+07I 525.e+046.123e +G31-.907e+021.7G96+03I 790e+026.0854a+029 363e+028_54Ge+021.484e+031 .591e++32.901e+034,681e+034.65.9e+021_303e+014.020e+042,414e .04I .088e+047.8G3e-012.85 1e+022,323e+032.259,R +027,354e-029 B22e+029.834e+021,.663e +031.754,-03TI 196+034.958e+0134.660e+ 0'1,347-+015.68e8+04-file-./!C-/Pogr'am0/*2OFiles*/20(x86)MciroSbiield/ExamplesICase~iles/HdflJ 3O0%*20gC... 211712015 I Fission Product Barrier CALC. NO. STPNOC013-CALC-004E N E R C O N Failures for EAL Thresholds REV. 2E Everyday. Appendix A PAGE NO. 14 of 17Case Summary of RCS BarrierPage 3 of 3zffiecI//CilPrograml2OFilesl2O(xS6AicroShield/E-xamplesiCaseFile~fl1Tfl30OO%2OjiC. 2/1Ti201 5 Fission Product Barrier CALC. NO. STPNOC013-CALC-004E N E R C O N Failures for EAL Thresholds REV. 2Ecelnce-FEvrypret Evedy Appendix A PAGE NO. 15 of 17Case Summary of Contiamnent BarrierPage 1 of 3MicroShield 6.20 (05-MSD-6.20-1158)EnerconPageDOSFileRun Date,Run TimeDuration~1200 WCI DEL.ms6February 17, 20152,41 11 PMý.0 -0~0 0FI'le RA"CheckedCA"O Tltleý Coannment R5~fierDegcrlptjoe 1200 pci/cc6oojetiy. 8 CylInder Volumne -End hedsouroi, Dimenst~nsýRadius 2 3e+3 crrn J'7ft)voý,e PointsA X Y61019.6 cmi 5SI3264 cm, 1143 cm20 ft 0- In 193 TtO0.0In 37 R 6.0iWShield Nsou ceAC;ApslhfeldtDimension~9 66ce+ 10 cfrS"I'M Input. GroUF~ng Method -Standard radicesMumber of Groups 25Lower Eney Cu~toff~ 0.01sPhotýn S < 0.0 15 -Ind itJedLib~w,, ý GroveNucilde1-1311-1321-1331-1341-135Kr F83miKr- 3Kr-S 7Kr4S8Kr 89Xe-131wXe-133Xe-133muXe-135Xe-135mXe-1372. 1600e413043.rO5LK'e+0C,13.58E. +004-rQ,616000e+0031388(0C*0037.62OCý" 003lAaK0e+ 0G44.2700e+0021,4200,e-0041 .2200e. Out2.0130ce -+008. 1 300e+0022.950r~ep007.9923e+0141, 28q5e+0152.442DC-0143 'i705,4.0156.95(H05+013I 4282te+GIS2,519'4e.s014!.842t-e+C145S40+1L57995+,1135.25405+0144_5140ýe+015788310etf3!41.4282e+L157.51 1t0+0133.D0051a0131,0915e+-0143.2370ie-V016.8354e-01129,99421e-001.94 71e 0023,9977,ý-0017.869 1Se -CC2S. 1576.e-cl021 .47,_,e-0)14 4223.e-0031 .4706-ke-W2.20505t-003 .99'7e.-C'M2. 1024a-r0028.4.,2005e,-V,33.0552e-Cr02Material DensityAir 0.100 1221. 1679li-O02.520015+0031,9083e- 0035.44114e5+0034.F750.54.055.1621.5-031.4791e-QC47.77859e+0023. 11541w,0021. 13 04 C -00ý3Buildup ;The matefia reference Is -Sourcelnl,9 raitio~n Parameters,Radlat 20YCIrcutetisI 1Enearg yMev.....ACMKVit Flue"Ce Ratephafne/ve "v/CrI/eN2o Run-up29 1e+ 1ý S47e.+i05Flaence RtateMeNF/Cm./eerwnh 74 le+0Exposuere RateMR/fhrno But*1d9p1. 327e+-AExpojure Ratema/lwWith Buldup1 443e+04fiaei//lCirograml,2OFIks%2,?O(x8)MicroShielVExamples/CaseFiks/1TM1J1200%2OL..ý 1217/2015 Fission Product Barrier CALC. NO. STPNOC013-CALC-004SE N~ E R N Failures for EAL Thresholds REV. 2Excellence-Every prqect. Evy day. Appendix A PAGE NO. 16 of 17Case Summary of Contianment Barrier Page 2 of 30.03 2.254e16 6.172e,- 06 '9,767e-06 O.117e+04 9.679e-040.6 1 -6f$9e 16 ..1.5414e 075f+4 .5e00.1 1,03ý6q12 1.232--03 2. 34e÷03 1 4+ 00 3. 1 2e4000.15 2.647e -14 5 7.265+÷0D 8.00,e+02 1.196e+030...2 1.624e- 15 4.055, 06 ...13. .06 7-157e+03 9.730e+030.3 2.1)33eý14 1.131e-06 1.427e+0,6 2-145e+03 2.707e-03D04 1 0," e ,15 5 .4 7 9e"G6 6 b214+065 1.067e+04 I 24ce+040.5 1.20e+15 I 212e+07 1.423e-07 2 794-e040-6 1 ý679te+,15 1. 358e, 07 i34+7 2-651e+04 3.1)53e- D40.C8 1. 98 5e -I 2, 11e+07 2,443e +D7 4.14144-04 4.1,46e +041.0 2.769ea-07 3.053+07 5 105e+04 5.627e.0415 2.2768e+15 4.8684+07 5 235e+07 8.1544+04 .0e42.0 8.228e+14 2.377e+07 2.518e÷07 3.89et-04310 3.124e+13 1 .377e+06 1. 437e+06 1.869e+03 1 950e+034.0 7..75......... e+1 ..2e...4 4,34F..04 5 19a,-+01 5.3 +o01Totals S.Sg84+16 1,820e+08 2.156'e+08 3.531*4.05 4.721e+05file:/IIC~Ilrograml2OFilesl2Ox86)/MicroShiieldExamplesICaseFiles/HTML/1200%2Oiý.. 2/17/2015 Fission Product Barrier CALC. NO. STPNOC013-CALC-004E N E R C O N Failures for EAL Thresholds REV. 2,yroiect veryday Appendix A PAGE NO. 17 of 17Case Summary of Contianment BarrierPage 3 of 3K.file-./I/C:Program%/ý2OFiles*/20(x86),McroShield/Eamples!CaseFilesIHIMJ 1200%/204... 2117,2015

v t e Letter Sequence Response to RAI
TAC:MD4195, (Open) TAC:MD4196, (Open)
Initiation Request Acceptance... Supplement, Supplement Administration Questions 18 December 2014 Answers 11 February 2015 26 February 2015 11 February 2015 26 February 2015 Results Approval... Other: ML072120467
MONTHYEAR2007-08-07 [Table View]

ML15068A045

Text

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