ML15287A284

Fort Calhoun Unit 1, Response to NRC Request for Additional Information Re License Amendment Request to Adopt Emergency Action Level Scheme Per NEI 99-01, Rev. 6 (TAC No. MF5466)

ML15287A284
Person / Time
Site:	Fort Calhoun
Issue date:	09/11/2015
From:	Cortopassi L P Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-15-0102, TAC MF5466
Download: ML15287A284 (154)

Text

{{#Wiki_filter:OhaPubik Power 444 South 16Street MailOmaha, NE 68 102-2247LIC-1 5-010O2September 11, 2015U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001Fort Calhoun Station, Unit No. 1Renewed Facility Operating License No. DPR-40NRC Docket No. 50-285Fort Calhoun StationIndependent Spent Fuel Storage InstallationNRC Docket No. 72-054

Subject:

OPPD Response to NRC Request for Additional Information RE: LicenseAmendment Request to Adopt Emergency Action Level Scheme Pursuant to NE!99-01, Revision 6 (TAC No. MF5466)

References:

1. Letter from OPPD (L. P. Cortopassi) to NRC (Document Control Desk),"License Amendment Request 14-06 to Adopt Emergency Action LevelScheme Pursuant to NEI 99-01, Revision 6, Development of EmergencyAction Levels for Non-Passive Reactors,' dated December 28, 2Q14 (LI C-14-0098) (ML1 4365A1 23)2. Letter from NRC (C. F. Lyon) to OPPD (L. P. Cortopassi), "Fort CalhounStation, Unit No. 1 -Request for Additional Information Re: LicenseAmendment Request to Adopt Emergency Action Level Scheme Pursuant toNEl 99-01, Revision 6 (TAC No. MF5466)," dated July 14, 2015 (NRC-15--061) (ML15194A272)The Omaha Public Power District's (OPPD) response to the NRC request for additionalinformation (RAI) (Reference 2) regarding License Amendment Request (LAR) 14-06(Reference 1) is attached. LAR 14-06 proposes to revise the Emergency Plan for Fort CalhounStation to adopt the Nuclear Energy Institute's (NEI's) revised Emergency Action Level (EAL)scheme described in NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.OPPD also respectfully requests an implementation date of June 30, 2016 in order to coordinateimplementation of the proposed changes with the training cycles currently scheduled for theyear.Employment with Equal OpportunityCF~11) 7(Z9L)Fc5 Pr-j)q~sL U. S. Nuclear Regulatory CommissionLIC-1 5-0102Page 2This letter contains no regulatory commitments.If you should have any questions regarding this submittal or require additional information,please contact Mr. Bill R. Hansher, Principal Regulatory Engineer, at 402-533-6894.Respectfully, ,ousP*oroasSite Vice President and CNOLPC/EJ P/mole

Enclosure:

OPPD Response to NRC Request for Additional Information Regarding LicenseAmendment Request (LAR) 14-08Attachment 1.: Front Matter (Pages FC 3-1 through FC 3-10)Attachment 2: Procedure Matrix (Pages FC 3-11 through FC 3-32)Attachment 3: Radiological Analysis, Methodology for Development ofRadiological Effluent Emergency Action Levels RA 13-008 Rev. 1Attachment 4: Emergency Action Level Thresholds for Liquid Release AA1 (RA1)RP-AA-1010 FC-14-004 Rev, C LIC-15-01 02EnclosurePage 1OPPD Response to NRC Request for Additional informationRegarding License Amendment Request (LAR) 14-06:Adopt Emergency Action Level Scheme Pursuant to NEI 99-013Revision 6,Development of Emergency Action Levels for Non-Passive Reactors LIC-1 5-010O2EnclosurePage 2REQUEST FOR ADDITIONAL INFORMATIONLICENSE AMENDMENT REQUEST TO ADOPT EMERGENCY ACTION LEVELSCHEME PURSUANT TO NE1 99-01. REVISION 6OMAHA PUBLIC POWER DISTRICTFORT CALHOUN STATION, UNIT NO. 1DOCKET NO. 50-285By letter dated December 26, 2014, Omaha Public Power District (OPPD, the licensee)requested approval for an emergency action level (EAL) scheme change for the Fort CalhounStation, Unit 1 (FOS) (Agencywide Documents Access and Management System (ADAMS)*Accession No. ML1 4365A1 23). OPPD proposes to revise its current EAL scheme to one basedupon Revision 6 to Nuclear Energy Institute (NEI) document NEi 99-01 , "Development ofEmergency Action Levels for Non-Passive Reactors," November 2012 (ADAMS Accession No.ML 12326A805), instead of Revision 5.The requests for additional information (RAts) listed below, in regards to Attachment 2,Enclosure 2C, 'Emergency Action Level Basis Document," of the submittal, are needed tosupport U.S. Nuclear Regulatory Commission (NRC) staff's continued technical review of theproposed EAL scheme change.FC-RAI-01Section 4.3, "Instrumentation Used for EALs," to NE! 99-01, Revision 6, states, in part,that: "Scheme developers should ensure that specific values used as EAL setpoints arewithin the calibrated range of the referenced instrumentation ...." Please confirm that allsetpoints and indications used in the FCS EAL scheme are within the calibrated range(s)of the stated instrumentation and that the resolution of the instrumentation isappropriate for the selpoint/indication.FC-RAI-01 Resp~onseFort Calhoun Station (FCS) has confirmed, through review of design documents, calculationsand surveillance tests, that all setpoints and indications used in the FCS EAL scheme are withincalibrated ranges of stated instrumentation and that resolution of the instrumentation isappropriate for the setpointlindication.FC-RA!-02Please provide supporting calculations for all Abnormal Rad Levels I RadiologicalEffluent threshold values or provide a reference to the ADAMS accession number of thedocument that contains this information.FC-RAI-02 ResponseFCS radiological threshold calculations RP-AA-1 010 FC-1 5-003 (RAt 3-008) Rev. 1 and RP-AA-101O FC-14-004 Rev. 0 are provided in this response for review as Attachment 3 andAttachment 4. LI C-1 5-01 02EnclosurePage 3FC-RAI-03Section 4.6, "Basis Document," to NEt 99-01, Revision 6, states, in part, that: "Becausethe information in a basis document can affect emergency classification decision-making.."The NR~C staff expects that changes to the basis document will be evaluated inaccordance with the provisions of Title 10 of the Code of Federal Regulations (10 CFR)paragraph 50.54(q), "Emergency Please ensure that appropriate information isincorporated as related to how the technical basis doCUment will be maintained inaccordance with 10 CFR 50.54(q). :FC-RAI-03 ResponseEP-FC-120 Emergency Plan Administration states:4.1.3 Implementing Procedures, Administrative Procedures, and EP Documents1. EP document changes shall be revised and processed per Attachment 2, EPDocument Structure and Revision Process.2. All document changes will receive a §50.54(q) evaluation per EP-F~C-120-1001.Attachment 2 states:2.3 Emergency Plan revision process:1. Prior to implementation of Emergency Plan revisions PERFORM the following:A. A §50.54(q) evaluation per EP-FG-120-1001.FC-RAI-04Section 4.7, "EAL/Threshold References to AOP (Abnormal Operating Procedure) andEOP [Emergency Operating Procedure] Setpoints/Criteria," to NEI 99-01, Revision 6,states, in part, that: "As reflected in the generic guidance, the criteria/values used inseveral EALs and fission product barrier thresholds may be drawn from a plant's AOPsand EOPs," The NRC staff expects that changes to AOPs and EOPs will be evaluated inaccordance with the provisions of 10 CFR 50.54(q). Please ensure that verify thatappropriate information is incorporated that ensures changes to AOPs or EOPs arescreened to determine if an evaluation pursuant to 10 CFR 50.54(q) is required,FC-RAIo04 ResponseAll EOP/AOP changes are required to be verified by the EOPIAOP Coordinator using theVerification Review Checklist (SO-G-74, Attachment 1). The checklist asks the followingquestion: Is EOP/AOP change free of modifications, additions and deletions of any conditions inan emergency action level (EAL) indicator or basis? "No" response requires 50.54(q) evaluationby Emergency Preparedness. AOP-O1 Acts of Nature and AOP.07 Evacuation of Control Roomare required to have Emergency Preparedness review.FC-RAI-05Section 4.6, "Basis Document," to NEI 99-01, Revision 6, states, in part, that: "A basisdocument is an integral part of an emergency classification scheme. The material in thisdocument supports proper emergency classification decision-making by providinginforming background and development information in a readily accessible format. Itcan be referred to in training situations and when making an actual emergency LIC-1 5-0102Enclosure "Page 4classification, if necessary.' Emergency Planning implementing Procedure EPIP-OSC-1,"Emergency Classification," was provided for the NRC staff's review as part of theprevious NEI 99-01, Revision 5 conversion request dated August 15, 2008 (ADAMSAccession No. ML082320484). Please provide a similar document that includes theaddresses the following information:* A "Purpose" section that reflects the intent of the EAL Basis Document, asprovided in NEI 99-01, Revision 6;* A site-specific Definition/Acronyms section that provides information consistentwith NEI 99-01, Revision 6, Appendices A and B;* An Operating Mode Applicability section that provides information consistent withNEl 99-01 , Revision 6, Section 3.5;* An implementation guidance section that provides information consistent with NEt99-01, Revision 6, Section 5; and* A copy of the FCS classification aid used to facilitate event classifications, whichis typically referred to as a "Wallboard."FC-RAI-05 ResponseThe above is provided in this response for review as Attachment 1 =Front Matter'~ and asAttachment 2 "Procedure Matrix" job aide.FC-RAI-06For Initiating Condition (IC) RG1, radiation monitor (RM)-064 was removed from Table RI.RM-064 is included in the currently approved AG1 EAL (ADAMS Accession No.ML13358A327). A justification for the removal of RM-064 was not provided in Attachment2, Enclosure 2A, "EAL Comparison Matrix Document." Please provide justification forthe removal of RM-064 from the RGI.FC-RAI-06 ResponseUpon further review FOS has decided to maintain the RM-064 Post Accident Main Steam (Gas)monitor in the RG1 EAL Scheme.FC-RAI-07For IC RS1, Table R1 has monitors RM-063, RM-052, and RM-043 listed. IC AS1, inRevision 2a of TBD-EPIP-OSC-1A dated December 11, 2013 (ADAMS Accession No. ML13358A327), and the Revision 5 conversion request dated August 15, 2008, has RM-064listed in addition to RM-063, but does not include RM-052 and RM-043. These changesare not identified in the Attachment 2, Enclosure 2A, "EAL Comparison MatrixDocument." Please provide justification for the removal of monitor RM-064 and theaddition of RM-052 and RM-043 to the EAL.FC-RAI-07 ResponseUpon further review FCS has decided to maintain the RM-064 Post Accident Main Steam (Gas)monitor in the RS1 EAL Scheme. SLIC-15-0102EnclosurePage 5The following has been added to the RS1 Comparison Matrix justification column to justify theaddition of RM-052 and RM-043 rad monitors to the RSI threshold. *-*RM-052 and RM-043 were added as they are typical radiological effluent pathwaymonitors with ranges that c~an detect EAL thresholds at RS1 levels as calculated by sitecalculation RP-AA-1 010 PC-I15-003 (RA 13-008) Rev. I included in this response asAttachment 3,..FC-RAI-08For Its RAl and RUl, the RM-057 value for an Alert classification is 1 .79E+08 counts perminute (cpm), while the RM-057 value for an Unusual Event classification is a highervalue of 8.82E+08 cpm. Additionally, a note for IC RU1 Table fl3, "Effluent MonitorThresholds," provides that "1.45E+-08 [cpm] as the upper range of the instrument." Bothof these values are above the upper range of the instrument. Please verify that theprovided RM-057 values are within the calibrated range of the instrumentation or reviseaccordingly.PC-RAI-08 ResponseA review and recalculation of thresholds for RM-057 has resolved the issue with instrumentoverange, the upper indication of the instrument has been verified to be 1.45 E+08 cpm, therevised values are within this upper indication and have been used to update RAl and RU Ithresholds with respect to RM-057. The revised calculation is contained in RP-AA-l1010 FC-1 5-003 (RA 13-008) Rev. 1.FC-RAI-09For ICe RAl and RU1, Table Rl, "Effluent Monitor Thresholds for Alert Classification,"provides values for RM-043, RM-052, and RM-062 that are not significantly higher thanthe values provided by Table R3, "Effluent Monitor Thresholds for Unusual EventClassification." Please validate all RA1 and RUl threshold values and reviseaccordingly. This validation should include verification of appropriate separationbetween Unusual Event, Alert, Site Area Emergency, and General Emergencydeclarations.FC-RAI-09 ResponseA review and recalculation of thresholds for RUl and RA1 using the same isotopic mixture forboth initiating conditions has resolved the issue with classification escalation, the revised valuesprovide for proper progression between RU1 and RAI and have been used to update RIA1 andRUl. The revised calculation is contained in RP-AA-1010 FC-15-.003 (RA 13-008) Rev. 1.FC-RAJ-1 0For IC RUI, the proposed EAL 1 uses Table 2, "Effluent Monitor Thresholds," whichprovides "2X High Alarm set point" as threshold values. Additionally, the proposed EAL2 uses Table R3, "Effluent Monitor Thresholds," as threshold values. As provided, TableR2 is a subset of Table R3 with Iwo exceptions. T"he exceptions are the thresholds for LIC-1 5-0102EnclosurePage 6RM-052 and RM-062 on Table R3, which are significantly higher than the threshold valuesfor RM-052 and RM-062 on Table R2.a. Please justify using two tables that use different values to perform classificationsfor RU1 or revise accordingly.b. Please explain the significant difference in the Table R2 and Table R3 thresholdvalues for RM-052 and RM-062, or revise accordingly.FC-RAI-10 ResponseUpon review the following changes were made to Table R2 and R3.1. RUI EAL 1 contains effluent monitors that monitor non-continuous batch releasescovered by discharge permits at FOS, the applicable effluent monitors are containedwithin the provided revised Table R2.2. Radiation monitors RM-052 and 62, depending on which may be aligned to the building exhaust stack, are only contained in the revised Table R3. Although thesemonitors may be used as the Waste Gas Decay Tank Release monitor for batch gasreleases they are also the gaseous effluent monitors used for the continuous auxiliarybuilding exhaust stack release, as such the RUl EAL 2 threshold in the revised TableR3 bounds both conditions.3. RUl EAL 2 contains continuous release .path effluent monitors, the applicable effluentmonitors are contained within the provided revised Table R3.FC-RAI-,11For IC RUI, Table R3 is used to assess EAL #2, which includes both liquid and gaseousradioactivity radiation monitors. However, the RU1 basis discussion for EAL #2 onlydiscusses gaseous radioactivity releases. Please explain why EAL #2 Basis discussionexcludes liquid radioactivity releases.FC-RAI-1 1 ResponseThis has been corrected, RUt EAL #2 basis discussion now addresses both gaseous and liquidradioactivity releases.FC-RAI-1 2For IC RUl, Table R3 in Attachment 2, Enclosure 2C, "EAL Basis Document,' is differentthan Table R3 in the Attachment 2, Enclosure 2A, "EAL Comparison Matrix Document";specifically:* RM-043, RM-052, RM-062, and RM-057 have different values between the twotables; and*RM-063 is included in Table R3 in the Attachment 2, Enclosure 2A, "EALComparison Matrix Document," and Table R3 in Attachment 2, Enclosure 2B, "EALRed-Line Basis Document, but is not included in Table R3 of EAL RU1 ofAttachment 2,, Enclosure 2C, "EAL Basis Document." LIC-15-0 102EnclosurePage 7Please explain the apparent inconsistencies between Attachment 2, Enclosures 2A, 2B,and 2C, or revise accordingly.FC-RlAI-1 2 ResponseA review has been performed on all attached documents for agreement between RUl TablesR2 and R3 and they have been revised to agree between all of the documents.FC-RAI-1 3The deviation for the wording in IC RU1 EAL 3 was not justified in the submittal. Theaddition of "Confirmed" pertains to the timeliness of EAL classification. Please providejustification for this deviation, or revise accordingly consistent with NRC-endorsedguidance.FC-RAI-13 ResponseAgree, the word "Confirmed" has been removed from IC RU1 EAL 3.FC-RAI-1 4For lCs RA2, RS2, and RG2, the proposed EALs do not reflect enhanced spent fuel poollevel instrumentation. Please provide EALs reflecting the planned installation ofenhanced spent fuel pool level instrumentation for NRC pre-approval, or providejustification for not including at this time.FC-RAI-14 ResponseRevised the sites proposed EALs to contain the associated RG2, RS2 and additional RA2threshold related to the enhanced SFP level indicators being installed per NRC Order- EA-12-051. These EALs will be incorporated into the site's EAts when the enhanced spent fuel poollevel instrumentation is available for use, in accordance with the discussion in Section 1.4, NRCOrder EA-1 2-051.FC-RAI-1 5For IC RU2, the proposed EALs do not include site-specific refueling pathway levelindications per NEK 99-01, Revision 6. Please provide site-specific level indications forRU2 that could be used to support timely and accurate assessments, includingapplicable mode availability for level instrumentation.FC-RAI-15 ResponseAgree, the applicable refueling pathway instrumentation has been added to EAL RU2.FC-RAI-1 6For IC RA2, the proposed Basis discussion does not include the NEI 99-01, Revision 6,EAL AA2 guidance stating: "This IC applies to irradiated fuel that is licensed for drystorage up to the point that the loaded storage cask is sealed. Once sealed, damage to aloaded cask causing loss of the CONFINEMENT BOUNDARY is classified in accordance LIC-1 5-0102EnclosurePage 8with IC E-HUI." Please justify excluding theNEi 99-01, Revision 8, EAL AA2 guidancethat relates to RA2 applicability, or revise accordingly.FC-RAI-1 6 ResponseAgree, the paragraph has been irncluded in EAL RA2 basis discussion as follows:"This IC applies to irradiated fuel that is licensed for dry storage up to the pointthat the loaded storage cask is sealed. Once sealed, damage to a loaded caskcausing loss of the CONFINEMENT BOUNDARY is classified in accordance withIC E-HU1Y.FC-RAI-1 7Please provide verification that the areas identified for IC RA3 reflect only those areasrequired for normal plant operations, cooldown or shutdown, or revise as necessary tosupport accurate and timely assessment. In addition, the note for the RA3 EALreferences Table R4 versus Table R7. Please verify which table should be referenced,and revise accordingly.FC-RAI-1 7 ResponseA) Amended the sites mode dependent areas Table in RAS to ensure that the stated areas arelimited to those where access is required to operate equipment necessary for normaloperations, safe shutdown, and cooldown. Areas that do not contain equipment requiring localoperation are no longer reflected in these Tables.B) Added the following highlighted words to the RA3 basis section to ensure that the EAL Basisreflects that equipment for normal operation, safe shutdown, and cooldown is the concern of theEAL.uAssuming all plant equipment is operating as designed, normal operation iscapable from the Main Control Room (MCR). The plant is also able to transitionInto a hot shutdown condition from the MCR. therefore Table R6 is a list of plantrooms or areas with entry-related mode applicability that contain equipmentwhich require a manuaL/local action necessary to transition the plant from normalplant operation to cooldown and shutdown as specified in normal operatingprocedures (establish shutdown cooling), where if this action is not completed theplant would not be able to attain and maintain cold shutdown."C) The note for the RA3 EAL now references the correct Table number reference.FC-RAI-1 8For IC FRU3, please provide justification for including the statement:" ... as determined bylaboratory confirmation ... "in the plant-specific basis for declaration of an UnusualEvent with elevated coolant activity, or revise accordingly consistent with NRC-endorsedguidance, as this could impact the timeliness of the assessment. LIC-1 5-0102EnclosurePage 9FC-RAI-18 ResponseAgree, the following paragraph has been removed from RU3.*"An Unusual Event is only warranted when actual fuel clad damage is the causeof the elevated coolant sample activity (as determined by laboratorycornlirmatlon). Fuel clad damage should be assumed to be the cause of elevatedReactor Coolant activity unless another cause is known,"FC-RAl-i 9Address the following under IC RC1, Potential Loss:a. The proposed Fission Product Barrier (FPB) Threshold Potential Loss 2 does notreflect steam generator tube leakage, which could impact the ability to performaccurate and timely assessments. Please provide justification for this deviation,or revise accordingly consistent with NRC-endorsed guidance.b. The proposed FPB Threshold Potential Loss 2 deviates from NRC-endorsedguidance in that, "Operation of a standby charging (makeup) pump is required."The licensee proposes the following wording: "> the capacity of one chargingpump in the normal mode (greater than 40 gpm [gallons per minute])." Pleaseprovide justification for this change, or revise accordingly, as it could imply thatoperators must determine an actual leak rate of 40 gpm or greater rather thandetermine that a second charging pump is required due to either an unisolablereactor coolant system (RCS) leak or steam generator tube leakage.c. The proposed FPB Threshold Potential Loss 3 is related to a heat removalchallenge and not "UNISOLABLE RCS leakage." Please provide furtherjustification for this deviation, or revise consistent with NRC-endorsed guidance.FC-RAI-19 Responsea. Agree, S/G tube leakage is now reflected in RC! Potential Loss threshold #2.b. The following justification has been added to the Comparison Matrix:The words "> the capacity of one charging pump in the normal mode (greater than40 gpm)" is used since this would beathe earliest time that an additional chargingpump could be aligned and discriminates the use Of reduced letdown flow (non-normal mode) to allow for a net increased capacity of a single charging pump asallowing continued operation without EAL declaration.c. Agree, removed Potential Loss 3 from the RCS /S/G tube leakage sub category for RCSloss.FC-RAI-20For CT!, the proposed FPB Threshold Loss 1 deviates from NRC-endorsed guidancethat, "A leaking or RUPTURED SG [steam generator) is FAULTED outside ofcontainment." The licensee proposes the following wording: "> the capacity of onecharging pump in the normal mode (greater than 40 gpm)." Please provide justificationfor this deviation, or revise consistent with NRC-endorsed guidance, as it implies thatoperators must determine an actual leak rate of 40 gpm or greater rather than determinethat a second charging pump is required for a steam generator tube leak. L C_-1 15-0102EnclosurePage 10FC-RAI-20 ResponseAgree, revised the wording to UA leaking or RUPTURED SG is FAULTED outside ofcontainment" to be consistent with the endorsed guidance.FC-RAI-21For CT2, FPB Threshold Potential Loss la. threshold is provided as Tclad > 1550degrees. Please verify that Tclad can be determined by the operators in a timely manner,or revise accordingly.FC-RAl-21 ResponseReviewed and revised to Core Exit Thermocouples, not T clad.FC-RAI-22For CT4, FPB Threshold Potential Loss 3 includes "and rising." This deviation couldimpact the timeliness and accuracy of classification. Provide justification for thisdeviation, or revise accordingly consistent with NRC-endorsed guidance.FC-RAI-22 ResponseThe following justification was added to the comparison matrix:=Adde "and rising" to Potential Loss #3 to distinguish the transient conditionwhere Containment Pressure may have exceeded the design pressuremomentarily on a transient but due to containment safety equipment is now beingreduced to below the design pressure, this type of condition would not be apotential threat to containment. Whereas exceeding design pressure with anincreasing trend would pose a threat to containment."FC-RAI-23For CT4, FPB Threshold Potential Loss 5 does not include a 15 minute criteria for lessthan one train of containment spray. Provide additional justification for this deviation orrevise accordingly consistent with NRC-endorsed guidance.Fc-RAI-23 ResponseAgree, "per design for > 15 minutes" has been added to CT4 Potential Loss Threshold #5.FC-RAI-24For ICs MU3, MA3, and MS3, please justify why the words: "... as indicated by reactorpower > 2%," were added to the EALs, or revise accordingly. Relying solely on a reactorpower level of 2 percent is not consistent with EOP criteria as provided by NEt 99-01,Revision 6. LIC-1 5-0102EnclosurePage 11FC-RAI-24 ResponseRevised to add T=and SUR is negative" to the existing reactor power indication to be consistentwith guidance provided in EOPs.FC-RAI-25For IC MA3, please explain why "or manual" was not included in the third paragraph ofthe Basis discussion when the EAL includes both automatic and manual trips, or reviseaccordingly.FC-RAI-25 ResponseAgree, "or manual" has been included in the 3rd paragraph of the Basis discussion.FC-RAI-26For IC MA4, under Table M2, "Significant Transients," please explain the following orrevise accordingly:a. Why the proposed Table M2 includes "ECCS [Emergency Core Cooling System)Actuationer oscillations > 10%" versus "ECCS Actuation," as provided by NEi 99-01, Revision 6 and Attachment 2, Enclosure 2A, "EAL Comparison MatrixDocument"?b. Why the proposed Table M2 does not include a manual runback of greater than 25percent?FC-RAI-26 Responsea. Agree and proposed Table M2 corrected to stale "ECCS ActuationD on all enclosures.b. FCS is not equipped with automatic or manual runback capability.FC-RAI-27For IC CU4, please explain why EAL #2 Basis does not include a procedure number, orrevise accordingly.FC-RAI-27 ResponseAgree and procedure number FC-1 188, Event Notification Form, has been added to the basisfor CU4 EAL #2.FC-RAI-28For IC CU5, please explain how the addition of ".... due to the loss of decay heatremoval..." to EAL 1 would not result in potential misclassification for an event otherthan a loss of decay heat removal that leads to an unplanned RCS temperature and/orRCS/reactor pressure vessel (RPV) pressure to rise. Please provide justification, orrevise accordingly consistent with NRC-endorsed guidance. LIC-1 5-0102EnclosurePage 12FC-RAI-28 ResponseAgree, the following has been removed from GU5 EAL =. ..due to loss of decay heat removal"AndAdded the following Note to CU5 to allow for quick reference by the SM / EDO since it will showon the 1 1x17 Procedure Matrix EALs:S"A momentary UNPLANNED excursion above the Technical Specification coldshutdown temperature limit when heat removal function is available does notwarrant classification"FC-RAI-29For IC CA5, please explain how the addition of "... due to the loss of decay heatremoval ..." to EAL 1 and, "... as a result of temperature rise due to loss of heat removal..."to EAL 2, would not result in potential misclassification for an event other than a loss ofdecay heat removal that leads to an unplanned RCS temperature and/or RCS/RPVpressure to rise. Please provide justification, or revise accordingly consistent with NRC-endorsed guidance.FC-RAI-29 ResponseAgree, the following has been removed from CA5 EAL "...due to loss of decay heat removal".AndAdded the following Note to GA5 to allow for quick reference by the SM / EDO since it will showon the 1lx1 7 Procedure Matrix EALs:* 'A momentary UNPLANNED excursion above the Technical Specification coldshutdown temperature limit when heat removal function is available does notwarrant classification"FC-RAI-30For IC CG6, no justification is provided for the difference between the pr;oposed EAL andthe guidance of NEi 99-01 Revision 6. Specifically, the endorsed guidance has two EAI~s,whereas the licensee proposes three EALs. [Note: The major difference is the numberingscheme and not the actual content of the EALs.] This change introduces a potentiallydifferent logic methodology, which could impact timeliness and accuracy ofassessments. Please provide justification that the proposed changes will not impact thetimeliness or accuracy of assessment, or revise accordingly consistent with NRC-endorsed guidance.FC-RAI-3D ResponseAgree and this has been corrected. The EAL now contains EAL 1 and EAL 2 a., b. (with threebullets under it), and c. This coincides with the endorsed NEI 99-01 Rev. 6 CG1 IC. No contenthas changed. LIC-1 5-0102EnclosurePage 13FC-RAI-31For ICs CU6, CA6, CS6, and CG6, please provide further justification as to why the EALsfor Reactor Vessel/Reactor Pressure Vessel Level are not in accordance with theguidance in NEI 99-01, Revision 6, or revise accordingly. The RCS level criterion waschanged from "cannot be monitored" to "unknown". This change could impact the starttime from the moment when the indication is lost to a judgment as to when RCS levelbecomes "unknown," which could impact the timeliness of the assessment.FC-RAI-31 ResponseAgree, wording returned to "cannot be monitored."FC-RAI-32For IC CS6, please provide verification that FCS has both a Reactor Vessel LevelMeasurement System (RVLMS), as indicated in EAL #1, and a Reactor Vessel LevelIndicating System (RVLIS), as indicated in EAL #2, or revise accordingly.FC-RAI-32 ResponseAgree, corrected to reflect the FCS RVLMS only.FC-RAI-33For IC CA6, the Basis for EAL #1 provides "water level below 0 inches on DraindownLevel indicator" as an indication that operator actions have not been successful inrestoring and maintaining RCS level. Please explain why the basis for EAL #1 refers to aDraindown level indicator, when EAL #1 refers to an RVLMS level, or revise accordingly.FC-RAI-33 ResponseAgree, CA6 Basis for EAL #1 corrected to reflect 14% RVLMS and now agrees with EAL #1.FC-RAI-34For IC HG1, the NRC staff is not clear of the intent of the last sentence in the Basis whichstates: "contained in non-public documents such as the Security Plan." Please reviseaccordingly to clarify.FC-RAI-34 ResponseAgree, this sentence has been removed from HGt Basis.FC-RAI-35For IC HUJ3, the proposed EALs appear to cover a wider range than required by AppendixR. Please provide verification that the areas identified for this EAL are consistent withAppendix R guidance, or revise as necessary to support accurate and timelyassessment. LIC-15-0 102EnclosurePage 14FC-RAI-35 ResponseAgree, the table has been reviewed against the Appendix R guidance as well as the NFPA 805analysis and has been revised to agree with this guidance.FC-RAI-36For IC HU3, please provide justification for deviation in excluding a fire within theindependent spent fuel storage installation, or revise accordingly consistent with NRC-endorsed guidance.FC-RAI-36 ResponseThe Comparison matrix for HU3 now reflects the fact that the ISFSI is within the plantPROTECTED AREA and as such is not specifically contained within EAL #3 and #4.AndThe following sentence has been added to the basis section of HU3.*"ISFSI is not specifically addressed in EAL #3 and #4 since it is within the plantPROTECTED AREA."FC-RAI-37For IC H4U4, please verify that the "Strong Motion Seismic Event in Progress" alarm andthe event indicator (SMA Control Panel) of an Operating Basis Earthquake are indicatedin the Control Room.FC-RAI-37 ResponseVerified and stated the alarm and event indicator indicate in the Control Room, this informationis listed in the comparison matrix under the H-fU4 justifitation column.FC-RAI-38For IC HA5, please verify the areas identified for this EAL were developed in accordancewith the NRC-endorsed guidance and reflect only those areas required for normal plantoperations, cooldown or shutdown.FC-RAI-38 ResponseA) Amended the sites mode dependent areas Table in HA5 to ensure that the stated areas arelimited to those where access is required to operate equipment necessary for normaloperations, safe shutdown, and cooldown. Areas that do not contain equipment requiring localoperation are no longer reflected in these Tables.B) Added the following highlighted words to HA5 basis section to ensure that the EAL Basisreflects that equipment for normal operation, safe shutdown, and cooldown is the concern of theEAL. LIC-1 5-0102EnclosurePage 15"Assuming all plant equipment is operating as designed, normal operation iscapable from the Main Control Room (MCR). The plant is also able to transitioninto a hot shutdown condition from the MCR, therefore Table H3 is a list of plantrooms or areas with entry-related mode applicability that contain equipmentwhich require a manual/local action necessary to transition the plant from normalplant operation to cooldown and shu~tdown as specified in normal operatingprocedures (establish shutdown cooling), where if this action is not completed theplant would not be able to attain and maintain cold shutdown."FC-RAI-39For IC HU6, the EAL #2 Basis discussion on "Manual isolation of power to ..." appears tocontradict the information in EAL #2 and is not in accordance with NRC-endorsedguidance. Please provide clarification, or revise accordingly.FC-RAI-39 ResponseAgree, removed the following from HU6 EAL #2 basis information:* 1Manual isolation of power to a SAFETY SYSTEM component as a result ofleakage is an event of lesser impact and would be expected to cause small andlocalized damage. The consequence of this type of event is adequately assessedand addressed in accordance with Technical Specifications." LIC-1 5-01 02Enclosure, Attachment 1Front Matter(Pages FC 3-1 through FC 3-10O)

Ft (P.Ilhm:n PHhl]r I LI I IIlillll8 l imflUbl IrkSection 3: Classification of Emergencies3.1 GeneralSection D of the Omaha Public Power District (OPPD) Radiological EmergencyResponse Plan divides the types of emergencies into four EMERGENCYCLASSIFICATION LEVELS (ECLs). The first four are the UNUSUAL EVENT(UE), ALERT, SITE AREA EMERGENCY (SAE), and GENERAL EMERGENCY(GE). These ECLs are entered by satisfying the Initiating .Condition (IC) throughmeeting an Emergency Action Level (EAL) of the IC provided in this section ofthe Annex. The ECLs are escalated from least severe to most severe accordingto relative threat to the health and safety of the public and emergency workers.UNUSUAL EVENT (UE): Events are in progress or have occurred which indicatea potential degradation of the level of safety of the plant or indicate a securitythreat to facility protection has been initiated. No releases of radioactive materialrequiring offsite response or monitoring are expected unless further degradationof safety systems occurs.ALERT: Events are in progress or have occurred which involve an actual orpotential substantial degradation of the level of safety of the plant or a securityevent that involves probable life threatening risk to site personnel or damage tosite equipment because of HOSTILE ACTION. Any releases are expected to belimited to small fractions of the EPA Protective Action Guideline exposure levels.SITE AREA EMERGENCY (SAE): Events are in progress or have occurredwhich involve an actual or likely major failures of plant functions needed forprotection of the public or HOSTILE ACTION that results in intentional damage ormalicious acts; 1) toward site personnel or equipment that could lead to the likelyfailure of or; 2) that prevent effective access to equipment needed for theprotection of the public. Any releases are not expected to result in exposurelevels which exceed EPA Protective Action Guideline exposure levels beyond thesite boundary.GENERAL EMERGENCY (GE): Events are in progress or have occurred whichinvolve actual or IMMINENT substantial core degradation or melting withpotential for, loss of containment integrity or HOSTILE ACTION that results in anactual loss of physical control of the facility. Releases can be reasonablyexpected to exceed EPA Protective Action Guideline exposure levels offsite formore than the immediate site area.Month 20xxFC 3-1Mont 2Ox FC3-1EP-XX-XXXX (Revision xx)

Ft_ Public Power F l C~lalhnru 5 flms hsi ......................r~EMERGENCY CLASSIFICATION LEVEL (ECL): One of a set of names or titlesestablished by the US Nuclear Regulatory Commission (NRC) for grouping off-normal events or conditions according to (1) potential or actual effects orconsequences, and (2) onsite and offsite response actions. Theemergency classification levels, in ascending order of severity, are:* UNUSUAL EVENT (UE)*] ALERT* SITE AREA EMERGENCY (SAE)*] GENERAL EMERGENCY (GE)INITIiATING CONDITION IC):An event or condition that aligns with the definitionof one of the four EMERGENCY CLASSIFICATION LEVELS by virtue of thepotential or actual effects or consequences.EMERGENCY ACTION LEVEL (EAL)I: A pre-determined, site-specific,observable threshold for an INITIATING CONDITION that, when met orexceeded, places the plant in a given EMERGENCY CLASSIFICATION LEVEL.An emergency is classified by assessing plant conditions .and comparingabnormal conditions to ICs and EALs, based on the designated OperationalCondition (MODE). Modes 1 through 5 are defined in the TechnicalSpecifications (T.S). "Defueled" Mode (D) was established for classificationpurposes to reflect conditions where all fuel has been removed from the ReactorPressure Vessel.FCS does not use Standard Technical Specifications for CE PWRs. FCS doesnot use an operating mode for plant conditions with the reactor subcritical, Tcoldgreater than or equal to 210 °F, and Tavg less than or equal to 515°F, the onlydifference between FCS Modes 4 and 5 is the reactor coolant boronconcentration, and FCS does not have a defueled mode. To ensure the intent ofthe NEI 99-01 scheme is met, the following stipulation is added that states:"Unless specific criteria are identified in the "Applicable Modes" section of anEAL, the plant shall always assume to be in the higher Operating Mode(numerically lower) during transitions between modes for the purposes ofEmergency Classification (i.e., if Tcold is 246°F, the plant is considered to be inOperating Mode 3 if no temperatures are specified)."Month 20xxFC 3-2Mont 20x FC3-2EP-XX-XXXX (Revision xx) Ft. Calhoun StationFt. alhon SttionOmaha Public Power DistrictEquivalent Plant Technical Specification Operating Mode Applicability to NEI 99 01NEI 99 01 PWR Operating Modes FCS Technical Specification Operating ModesPower Operation (1): Reactor Power >5%, Power Operation Condition (Operating Mode 1):Keff>- 0.99 The reactor is in the power operation condition when it iscritical and the neutron flux power range instrumentationindicates greater than 2% of rated power.Startup (2): Reactor Power s5%, Keff_> 0.99 Hot Standby Condition (Operating Mode 2):The reactor is considered to be in a hot standbycondition if the average temperature of the reactorcoolant (TIavg) is greater than 515 °F, the reactor iscritical, and the neutron flux power rangeinstrumentation indicates less than 2% of rated power.Hot Standby (3): RCS >_ 350 'F, Keff < 0.99 Hot Shutdown Condition (Operating Mode 3):The reactor is in a hot shutdown condition if the averagetemperature of the reactor coolant (Tay9) is greater than515 °F and the reactor is subcritical by at least theamount defined in Paragraph 2.10.2.Hot Shutdown (4): 200 'F <RCS <350 'F, .None :+~; ; ~'.I:....' ..iKeff < 0.99Cold Shutdown (5): RCS<200 'F, Keff<O.99 Cold Shutdown Condition (Operating Mode 4):The reactor coolant Toold is less than 210'F and thereactor coolant is >SHUTDOWN BORONCONCENTRATION but <REFUELING BORONCONCENTRATION.Refueling (6): One or more vessel head closure Refueling Shutdown Condition (Operating Mode 5):bolts less than fully tensioned The reactor coolant T,-ofd is less than 210 'F and thereactor coolant is REFUELING BORONCONCENTRATION.reactor pressur evessel. (Full c°oreooad during ! }:'i: lrefueling or extended outage) ..... ! !.: i. Hot Matrix -applies in FCS modes (1), (2), (3)Cold Matrix -applies in FCS modes (4), (5), and (D)Month FC 3-3Mont 2Ox FC3-3EP-XX-XXXX (Revision xx) Am ~ Dm.kIis. Dr~~Ae1a. fltalvii-t* S WL I *r. U i .&ahll 1*. CUllAlJ

• 1.I5.**lq. U U1 f1 I5./OLIl11.4Individuals responsible for the classification of events will refer to the InitiatingCondition and EALs on the matrix of this document. This matrix will contain l~s,EALs, Mode Applicability Designators, appropriate EAL numbering system, andadditional guidance necessary to classify events, it may be provided as a useraid.The matrix is set up in six Recognition Categories. The first is designated as "R"and relates to Abnormal Radiological Conditions / Abnormal Radiological EffluentReleases. The Second is designated as "F" and relates to Fission Product BarrierDegradation. The third is designated as "M" and relates to hot condition SystemMalfunctions. The fourth is designated as "CU and relates to Cold Shutdown /Refueling System Malfunctions. The fifth is designated as "H" and relates toHazards and Other Conditions Affecting Plant Safety. The sixth is designated "E-H" and relates to ISFSI Malfunctions.The matrix is designed to provide an evaluation of the Initiating Conditions fromthe worst conditions (General Emergencies) on the left to the relatively lesssevere conditions on the right (Unusual Events). Evaluating conditions from leftto right will reduce the possibility that an event will be under classified. AllRecognition Categories should be reviewed for applicability prior to classification.The Initiating Conditions are coded with a two letter and one number code. Thefirst letter is the Recognition Category designator, the second letter is theClassification Level, "Un for (NOTIFICATION OF) UNUSUAL EVENT, UA"~ forALERT, "S"I for SiTE AREA EMERGENCY and "G" for GENERAL EMERGENCY.The EAL number is a sequential number for that Recognition Category series. AllICs that are describing the severity of a common condition (series) will have thesame number.The EAL number may then be used to reference a corresponding page(s), whichprovides the basis information pertaining to the IC:EAL,, Mode ApplicabilityBasisClassification is not to be made without referencing, comparing and satisfying thespecified Emergency Action Levels.A list of definitions is provided as part of this document for terms having specificmeaning to the EALs.References are also included to documents that were used to develop the EALs.Month 20xxFC 3-4Mont 2Ox FC3-4EP-XX-XXXX (Revision xx)

Ft. Calhoun StationOmaha Public Power DistrictReferences to the Emergency Director means the person in Command andControl as defined in the Emergency Plan. Classification of emergencies is anon-delegable responsibility of Command and Control with responsibilityassigned to the Shift Manager (Main Control Room), the Control RoomCoordinator (Main Control Room), the TSC Site Director (Technical SupportCenter), or the EOF Emergency Director (Emergency Operations Facility).Although the majority of the EALs provide very specific thresholds, theEmergency Director must remain alert to events or conditions that lead to theconclusion that exceeding the EAL is IMMINENT. If, in the judgment of theEmergency Director, an IMMINENT situation is at hand, the classification shouldbe made as if the EAL has been exceeded. While this is particularly prudent atthe higher ECL (as the early classification may provide for more effectiveimplementation of protective measures), it is nonetheless applicable to all ECLs.3.2 Classification, Instrumentation and Transient EventsAll classifications are to be based upon valid indications, reports or conditions.Indications, reports or conditions are considered valid when they are verified by(1) an instrument channel check, or (2) indications on related or redundantindications, or (3) by direct observation by plant personnel, such that doubtrelated to the indication's operability, the condition's existence, or the report'saccuracy is removed. Implicit in this is the need for timely assessment.Indications used for monitoring and evaluation of plant conditions include thenormally used instrumentation, backup or redundant instrumentation, and the useof other parameters that provide information that supports determination if anEAL has been reached. When an EAL refers to a specific instrument or indicationthat is determined to be inaccurate or unavailable, then alternate indications shallbe used to monitor the specified condition.During an event that results in changing parameters trending towards an EALclassification, and instrumentation that was available to monitor this parameterbecomes unavailable or the parameter goes off scale, the parameter should beassumed to have been exceeded consistent with the trend and the classificationmade if there are no other direct or indirect means available to determine if theEAL has not been exceeded.The assessment of some EALs is based on the results of analyses that arenecessary to ascertain whether a specific EAL has been exceeded (e.g., doseassessments, chemistry sampling, ROS leak rate calculation, etc.); the EALandlor the associated basis discussion will identify the necessary analysis. Inthese cases, the 15-minute declaration period starts with the availability of theanalysis results that show the EAL to be exceeded (i.e., this is the time that theEAL information is first available).Month 20xxFC 3-5Mont 2Ox FC3-5EP-XX-XXXX (Revision xx) Ft. Calhoun StationFt. alhon SttionOmaha Public Power DistrictPlanned evolutions involve preplanning to address the limitations imposed by thecondition, the performance of required surveillance testing, and theimplementation of specific controls prior to knowingly entering the condition inaccordance with the specific requirements of the site's Technical Specifications.Activities which cause the site to operate beyond that allowed by the site'sTechnical Specifications, planned or unplanned, may result in an EAL being metor exceeded. Planned evolutions to test, manipulate, repair, performmaintenance or modifications to systems and equipment that result in an EALbeing met or exceeded are not subject to classification and activationrequirements as long as the evolution proceeds as planned and is within theoperational limitations imposed by the specific operating ticense. However, theseconditions may be subject to the reporting requirements of 10 CFR 50.72.When two or more EAts are determined, declaration will be made on the highestclassification level.Concerning ECL Downgrading, OPPD Nuclear policy is that ECts shall no_.t bedowngraded to a lower classification. Once declared, the event shall remain ineffect until no Classification is warranted.There may be cases in which a plant condition that exceeded an EAL was notrecognized at the time of occurrence but is identified well after the condition hasoccurred (e.g., as a result of routine log or record review), and the condition nolonger exists. tn these cases, an emergency Should not be declared. Reportingrequirements of 10 CFR 50.72 are applicable, the guidance of NUREG-1022,Event Reporting Guidelines 10 CFR 50.72 and 50.73 and the ReportabilityReference Manual, should be applied.3.3 Mode ApplicabilityThe plant-operating mode that existed at the time that the event occurred, prior toany protective system or operator action initiated in response to the condition, iscompared to the mode applicability of the EALs. If an event occurs, and a loweror higher plant-operating mode is reached before the emergency classificationcan be made, the declaration shall be based on the mode that existed at the timethe event occurred.For events that occur in Cold Shutdown or Refueling, escalation is via EALs thathave Cold Shutdown or Refueling for mode applicability, even if Hot Shutdown(or a higher mode) is entered during any subsequent heat-up. In particular, theFission Product Barrier Matrix EALs are applicable only to events that initiate inHot Shutdown or higher.If there is a change in Mode following an event declaration, any subsequentevents involving EAts outside of the current declaration escalation path will beevaluated on the Mode of the plant at the time the subsequent events occur.Month 20xxFC 3-6Month2Oxx C 3-6EP-XX-X)(XX (Revision xx) Ft. Calhoun StationFt. aihon SttionOmaha Public Power District3.4 Emergency Director JudgmentEmergency Director (ED) Judgment EALs are provided in the Hazards and OtherCondition Affecting Plant Safety section and on the Fission Product Barrier (FPB)Matrix. Both of the ED Judgment EALs have specific criteria for when theyshould be applied.The Hazards Section ED Judgment EALs are intended to address unanticipatedconditions which are not addressed explicitly by other EALs but warrantdeclaration of an emergency because conditions exist which are believed by theED to fall under specific emergency classifications (UE, Alert, SAE or GE).The FPB Matrix ED Judgment EALs are intended to include unanticipatedconditions, which are not addressed explicitly by any of the other FPB thresholdvalues, but warrant determination because conditions exist that fall under thebroader definition for a significant Loss or Potential Loss of the barrier (equal toor greater than the defined FPB threshold values).3.5 Fission Product Barrier (FPB) ThresholdA fission product barrier threshold is a pre-determined, site-specific, observablethreshold indicating the loss or potential loss of a fission product barrier.FPB thresholds represent th'reats to the defense in depth design concept thatprecludes the release of radioactive fission products to the environment. Thisconcept relies on multiple physical barriers, any one of which, if maintainedintact, precludes the release of significant amounts of radioactive fission productsto the environment, The primary FPBs are:EU Fuel Clad (FC)* Reactor Coolant System (RCS)[] Containment (CT)Upon determination that one or more FPB thresholds have been exceeded, thecombination of barrier loss and/or potential loss thresholds is compared to theFPB IC/EAL criteria to 'determine the appropriate ECL.In some accident sequences, the ICs and EALs presented in the AbnormalRadiation Levels/ Radiological Effluent (R) Recognition Category will beexceeded at the same time, or shortly after, the loss of one or more fissionproduct barriers. This redundancy is intentional as the former ICs addressradioactivity releases that result in certain offsite doses from Whatever cause,including events that might not be fully encompassed by fission product barriers(e.g., spent fuel pool accidents, design containment leakage following a LOCA,etc.).Month 20xxFC 3-7Mont 2Ox FC3-7EP-XX-XXXX (Revision xx) Ft. Calhoun StationOmaha Public Power District3.6 Fission Product Barrier RestorationFission Product Barriers are not treated the same as EAL threshold values.Conditions warranting declaration of the loss or potential loss of a FPB mayoccur resulting in a specific classifcation. The condition that caused the loss orpotential loss declaration could be rectified as the result of Operator action,automatic actions, or designed plant response. Barriers will be considered re-established when there are direct verifiable indications (containment penetrationor open valve has been isolated, coolant sample results, etc) that the barrier hasbeen restored and is capable of mitigating future events.The reestablishment of a FPB does not alter or lower the existing classification.However the reestablishment of the barrier should be considered in determiningfuture classifcations should plant conditions or events change.3.7 DefinitionsCONTAINMENT CLOSURE: The procedurally defined actions taken to securecontainment and its associated structures, systems, and components as afunctional barrier to fission product release under existing plant conditions.EXPLOSION: A rapid, violent and catastrophic failure of a piece of equipmentdue to combustion, chemical reaction or overpressurization. A release of steam(from high energy lines or components) or an electrical component failure(caused by short circuits, grounding, arcing, etc.) should not automatically beconsidered an explosion. Such events may require a post-event inspection todetermine if the attributes of an explosion are present.FIRE: Combustion characterized by heat and light. Sources of smoke such asslipping drive belts or overheated electrical equipment do not constitute fire.Observation of flame is preferred but is NOT required if large quantities of smokeand heat are observed.FISSION PRODUCT BARRIER (FPB) THRESHOLD: A preo-determined, site-specific, observable threshold indicating the loss or potential loss of a fissionproduct barrier.HOSTAGE: A person(s) held as leverage against the station to ensure thatdemands will be met by the station.Month 20xxFC 3-8Mont 2Ox FO3-8EP-XX-XXXX (Revision xx) Ft. Calhoun StationFt Clhou StaionOmaha Public Power DistrictHOSTILE ACTION: An act toward a Nuclear Power Plant (NPP) or its personnelthat includes the use of violent force to destroy equipment, take HOSTAGES,and/or intimidate the licensee to achieve an end. This includes attack by air, land,or water using guns,' explosives, PROJECTILEs, vehicles, or other devices usedto deliver destructive force. Other acts that satisfy the overall intent may beincluded. HOSTILE ACTION should not be construed to include acts of civildisobedience or felonious acts that are not part of a concerted attack on theNPP. Non-terrorism-based EALs should be used to address such activities (i.e.,this may include violent acts between individuals in the owner controlled area).HOSTILE FORCE: Any individuals who are engaged in a determined assault,overtly or by stealth and deception, equipped with suitable weapons capable ofkilling, maiming, or causing destruction.IMMINENT: The trajectory of events or conditions is such that an EAL will be metwithin a relatively short period of time regardless of mitigation or correctiveactions.NORMAL LEVELS: As applied to radiological IC/EALs, the highest reading in thepast twenty-four hours excluding the current peak value.OWNER CONTROLLED AREA (OCA): The property associated with the stationand owned by the company. Access is normally limited to persons entering forofficial business.PROJECTILE: An object directed toward a Nuclear Power Plant (NPP) that couldcause concern for its continued operability, reliability, or personnel safety.PROTECTED AREA: An area that normally encompasses all controlled areaswithin the security protected area fence.REFUELING PATHWAY: All the cavities, tubes, canals and pools through whichirradiated fuel may be moved or stored, but not including the reactor vesselbelow the flange.RUPTURED: The condition of a steam generator in which primary-to-secondaryleakage is of sufficient magnitude to require a safety injection.SAFETY SYSTEM: A system required for safe plant operation, cooling down theplant and/or placing it in the cold shutdown condition, including the ECCS.These are typically systems classified as safety-related.SECURITY CONDITION: Any Security Event as listed in the approved securitycontingency plan that constitutes a threat/compromise to site security, threat/riskto site personnel, or a potential degradation to the level of safety of the plant. ASECURITY CONDITION does not involve a HOSTILE ACTION.Month 20xxFC 3-9Mont 2Ox FO3-9EP-.XX-XXXX (Revision xx) Ft. Calhoun StationFt Clhou StaionOmaha Public Power DistrictUNISOLABLE: An open or breached system line that cannot be isolated,remotely or locally.UNPLANNED: A parameter change or an event that is not 1) the result of anintended evolution or 2) an expected plant response to a transient. The cause ofthe parameter change or event may be known or unknown.VISIBLE DAMAGE: Damage to a component or structure that is readilyobservable without measurements, testing, or analysis. The visual impact of thedamage is sufficient to cause concern regarding the operability or reliability of theaffected component or structure.Month 20xxFC 3-10Mont 2Ox FO -10EP-XX-XXXX (Revision xx) LIC-1 5-010O2Enclosure, Attachment 2Procedure Matrix(Pages FC 3-11 through FC 3-32) k-r' (':nlhmm HOT HOT MATRIX Omaha Public Power District6T l~alhnun Rtetlnn NOT MATRI~d HOT MATRIX Omaha Public Power DistrictIAbnormal Rad Levels I Radiological EffluentsA.l Roeleus of gaseous radiocativit [] rresulting In oflsite dose greater hean 1,000 mRem TEDEor 5,000 mRera thyrold CDE.Emreo cion Levels EALNotes:* The Emergency D rector should declare the event promptlyS upon dalermlnirng that the applicable tiwe has been exceeded,S or wilt likely be exceeded.f tan ongoing release is detected and the release utedi time Isunkncwn, assume thrat tire release duration has exceeded 15minateax.* Clasuification based en effluent reonitor readings sasumesthai a ref ease path to the environment Is established, lIftheeffiuent flow past xn effluent monitor is known to have stoppeddue to actions to isolate the releasue path, then the effluenti menitor reading in no longer valid for classiticatlon purposes.* The pmo-calculated effluent monitor values presented in EALff1 should be used for emergency classificahion assessmentsuntil dose assessment resnits are available.1. Readings on ANY Table Rl Effluent Monitor,> Table R1 valuetor> I5 minutes.2. Dose assessmeat Using actual meteorology indicates doses ator beyond the site boundary of EITHER: -a. > 1000 wRem TEDEORb. > 5000 mRem COE Thyroidft.RS1 Release of gaseous radioactivity, :resulting in off uite dose greater than 100 wRem TEDEor 50t mRene thyroid CDE.Emergence Aetlon Levels tEALl::Notes:* The Emergency Director should declare the event promptlyupon determining that the applicable time has been exceeded,or wilt likely be exceeded.* if an ongoing release ia detected and the releuxe etari time inunkrrown, assume that fire release duration thes erroeeded 15rein utes.* Classification based on ettluent manrlter readirtgs essumes thata releaxe path to the environment Ia estebtished. If the etlluerrtflow past an effluent monitor Is known to have slopped cue toactions to Isolate the release path, then the effluent monitorreading ls-rrotonger valld torclassificatton purposes.o The pre-calcatated effluent monitor values presented in EAL#1 should be used for emergency etassifi cation assessmentsuntil dose assessment results are available;1. Readings on ANY Table R1t Effluent Monitor> Table Rlvaluetorn. 15 minutes.ORt2. Dose assessment using actual meteorology indicates doses ator beyond thle site boundary of EITHER;-x, >,100mwRem TEDEOR.b, >;500 atRem CDEThyroidOR ,",3. Ffeld survey resufts at or beyond the site boundary indicateEITHER:* ia. Gamma (cosoed window) dose rules >100 mRem areexpected to continue lor>s 60 minautes.ORb. Analyses of hield survey samples indicate > 500 m~amCOE Thyroid for 60 mrinutee of Inhastation.HA1 Roeuso o..f guceous or liquid radoesotivity resrrltrrg In otfsute dose greater than 10 mrerm TEDEor 50 wrew thyroid ODE.Emerr-enov Action Levels IEALI :Notes:* The Emergency Direct or should declare the event pmomptlyupoa determining that the applicable time baa been exceeded,or will likely be exceeded.I* It an ongoing release is detected and the release start time isi unknown, assume thut the release duration has exceeded 15i. minutes.* Classilicstlon based on effluent monitor readings assumes thata release path to the environment is established, it the effluentI tiOW paut an effluent monitor ia known to have stepped due toactions to isolate thu release path, than the effluent monitorreading is no longer vatid for classifIcation purposes.* The pre-calcutated effluent rnonitor~vataee presented In EAL f#1should be used for emergency classification aesse-surents untildose assessment results are available.1:Readelgs an ANY TSJSe Rt hiffuest Mosilorn. Table Rt value for_> 15:mthnutes..*OR :,2." Oweuuse aresetauslng actual muteomlogy.indicates dosessator* beyond the esit beundury of ErTIT ER;* ..l.>Orur~mTEnlCOR" .."O5b. >50mm COD Thyroid3. Analyeis al a mlud em auent, samefe indicates ascmncenrtrtion or releaserate that eroald result in rtang reeler than EITHER el the tulounetg atbeyonrd the xlte baundura 10 wRem TEDE tar 55 artnutas ofieuposureORb. 50 mRem CDE ThyroId far a6 rminutsa at auposure4. Feld aumey reuolta at ur beyond the nile besedaG indioute EITHER;a .G~amme ctaleed wlndarw) dose raransv 10 areexpecrted In cantinue for aff60 minutes.ORh. of huie~ Survey searples indicate>s 50 Rew ClE hylrnirt for S0 ernuteus 01 inhalatiou.RUl Any release of gaseous or liquid [radioactivity lottie environment greater than2 tinres thu 0DCM for 60 minutes or longer.EmeroRenoy Action Leanls tEALt}:Notes:* Toe Emergency Director should declare the event promptlyupon determining that the applicable time has been exceeded,or will likely be exceeded.* If an ongoing riexeae is detected and the release start time lsunknown, assume that the release duraffion has exceeded 60mlnutes.Classification based on effiluest monitor readiongs assumes thata release puth to the environment Is established, If thte effluentflow past an effluent monitor is known to have stopped due toactions to isolate the release path, then the effluent monitorreadirrg is no longer valid for classification purposes.1. Reading on ANY Table R2 effluent meonltors >2 times alarmsenpolnt established by a current radioactive release dischargepen'tif for is 60 minutes.OR2. Readings on ANY Table R3 Effluent Monitors> Table R3 valuefor 60 minutes:OR3:- Samrple analyses for gaseous or liquid releases indicateconsentrstloes or releuse rates,> 2 times 00CM Limit with arelease duration of is60munuteas.OR3. ReId survey results at or beyond the sit a bundary indicateEITHER:a. Gamma (closed window) dose rates >1000 wRemame expected to continue for > 60 minrates.ORb. Analyses of field survey eareplas indicate ">5000wRem CDE Thyroid for 60 minutes of inhalation.Mode:1 -Power Operations2 -Slartup3 -Not Standby 4 -HcI iSnutdown 5 -JOad Shitutoowa U -IUehseiedMonlter General Ewergenoy [- Site Area Emergency AlertRM-063 AB Stack 3.71 E+0O uCuico 3.71 E-0t uCi/co 3.71 E-02 oCt/coTal 1 RM-064 (If affected SI'G is not isolated) 5.68 E+01 orm [ 2.28 E+01 cpmN/RM-062 AB Stack ft'A N/A 5.25 E+05 cpmEffluent _____________ _____________Monitor RM-052 AS Stack N/A 6.23 E+06 cpm 8.23 E+05 opmoThreshtolds RM-04.3 LRWPB Stack N/A 5.44 E+06 cpm 5.44 E+05 cpmRM-057 Condenser Ott-Gas N/A N/bA 1.34 E+08 cpmMonth 20XX HOT MATRIXFC 3-11Mot OX O ARX i -1HOT MATRfX EP-XX-XXXX (Rlevision XX) ~r ~Ih,iB ATDIYIA ATOIY n;.*.=^,Thhla RO FffhInt MonninThrahnldaEffluent Monitor Description J2X High AlarmRM-055 (if discharge not Liquid 28E0 pisolated) Mirimum 1 OW 28E0 pPump Discharge HeaderRM-055 (it discharge notisolated) Minimum 2 RW Liquid &O4O pPump Discharge Header 80EO pTablte R3 Effluent Monitor ThresholdtsEffluent Monitor Description NOUERM.082, AB Stack (Gas). 3.25 E+04 cpmRM-052 AD Stack (Gas) .. 3.55 E+04 cpmRM-043 LAW PB Stack (Gsa) 3.37 E*04 cpin... M-057 ' Condenser Ott-Gas "* 8.83 Si-06 cparRM-.054A (it:SG "*blowdown isnot SG blowdown " 9.86E+04 cprnisotated) ____________"__________RM-0545 (if SOblowdown is not ObwonSG blowdownisolated) S.88E+04 cpmMonth 20XX HOT MATRIXFC 3-12Mot OX HTMARXF -2HOT MATRIX EP-XX-XXXX (Revision XX) It'tT Ms ATmEV CE,.ah D O.hil.. Dnwunr flkrl^5FT. Calhoun Station HUT WIMAT I I nv ' i~ ......,uJ 5'. ,Abnornmal Rad Levels/IRadiologicat Effluentsr FRG2 Spent fuel pool level cannot be 1[]]restored to at least (site-specific Level 3description) for 60 minutes or longer.Emergency Action Levels lEAL):Note: The Emergency Director should declare theGeneral Emergency prmmpty upon determining thaithe applicable time has been exceeded, or will llkelybe exceeded.Spent fuel pool level cannot be restored to at least (site-specific Level 3 value) Ior 60 minutes or longer.I RS2 Spent fuel pool level at-(site-specific Level 3 description).Emergencv Action Level fEA.&L):Lowering of spent fuel pool level to (site-specific Level 3value).RA2 Significant lowering of water E]level above, or damage to, irradiated fuel.Emergencv Action Levels (EAL) :1. Uncovery of irradiated feel in the REFUELINGPATHWAY.OR2. Damage to irradiated fuel resulting in a release ofradioactivity from the fuel as indicated by ANY Table R4Radiation Monitor reading >1000 mRernihrOR3. Lowering of spent fuel pool level to (site-specific Level 2value). RU2 Unplanned loss of water levelabove irradiated fuel.Emergency Action Levels tEAL):f~ll~1. a. UNPLANNED waler level drop in the REFUELINGPATHWAY as indicated on ANY of the following:,* LI-06 (Cold Shutdown PZR Level)"* L1-197 (Cold Shtdn RC Level)-L1-199 (sight glees)* LI-2a46 (Spent Fuel Pool Level)ANDb. UNPLANNED Area Radiation Monitor reading rieson ANY radiation monitor in Table R4., .:,Table R5- S iAreee Requiring Continuous OccupancyIa,a,"wMain Control Room~i" :': ~!JCentral Alarm Stati6n Radiation levels th~at impede i rc RU3 Reactor coolant activity ]][,access to equipment necessary for normal plant operations.cooldow or shton greater than Technica l Specification allowable limits.Table R4RadIation MonitorsRMS Area MonitoredRM-. j Containment Rad Monitor085M8 Auxiliary fituilding Red MonitorPortable Containment and auxiliary Building nearMonto fuel handling areasi ::'Table R6: ,Aress with Entry Related Mode Aoo~li~abilltv"A.rea " Entry Related ModeContainment Modes 4, S and 0Room 6 Modes 4, 5and DRoom 13 Modes 4, S and DRoom iSA Modes 4, 5 and DRoom 21 Modes 4, 5 and DRoom 22 Modes 4, 5Sand DRoom S6 Modes 4, 5and DRoomS57 Modes 4,S5 nd ORoom 89 Modes 4, 5Sand DEmergency Action Levels tEAL) :Note: ilf te equJipment in the room or area listed in Table.RE was already inoperable, or out of aervice, beforethe event occurred, then no emergency classificationis warranted.1. Dose rate greater than 15 mR/hr in ANY of the areascontained In Table RS.OR2. An UNPLANNED event results in radiation levels thatprevent or significantly impede access to any of theplant rooms in Table RE,EmergencY Action Levels (EAL) :I. Dose rate on Contact" on the primary sample pipingimmediately adjacent to the Sample Hood (SL-1) is> 4R/htr.OR............. ......... ....2.Sample analysis indicates that:a. Dose Equivalent 1-131 specific coolantactivity >1.0 uClI/gn for more than 100hours during one continuous timeinterval OR > 60 uClfgm.-.,OR ....b. Activity > 100IE-bar uCl/gm,___________________________________ I _________________________________ +/- _________________________________ aS -rizanup 6-net orariuuy -nut Orutuvwri -uuu OiIUWUW~~ U -Mose:1 -l-ower (dpemtionsS--- }'10[ -t O -- O;lutuuwn U -- Month 20XX HOT MATRIXFC 3-13Mth2X HOMTRXF3-3HOT MATRIX EP-XX-XXXX (Revision XX) FG1 Loss of ANY" two barriers AND Loss or Potential Loss of third barrier.(il2l[I~ FIFS Less or Potentlal Loss ot ANY tw(a barrders.I PAl ANY Loss or ANY Potential Loss of either Fuel Clad or RCS[i]21II{.... i p .... --FC -ueal Clad PC -Reactor Coolant System CT -ConeraenmsreSub-CalegoryLess Petenetilt Less LOSS Potenltiel Loss Loss J Potential Lessa. UNISOLABLE RC5 ot 5/0 rube Iseakage511 thepepolly of snea chargitrg pernp1. Astormatie er easeo ECC$S (SrI) eatntion inlr are ed gelrteis reqeired by EITHER of rhe lellenoxng: 4Op .1.RSe 1 asRVLMS indicates 0.0%. 5. UNItSOiA5LO PCS leakage OR A leaking or R UPTUR ED SG isLeakae1Re rSG ue None OR 0. 0. A transient has osesed 5 raoid RC5 FAULTED outside of containment. I None5. Stnerm Generator tuba RUPTURE. ANDb. PrBesuers ned Temprnarulrs Is shoneAttachrnent PC-tb PressureOTepeatrole Curve.* AND0. Care Eair Thennaeosyl~e readiNgs 5. Reslc-ratian pracodurea not etfeotive is> 7g5lF , a 15 elanutas.'.Cr s snnoal naiaaO * -eng.lp"O-oHdi OR2. lnadequrate Heat f" >Cotea-pEl Throoperaig ~. * " aNoie " : ff .OnaTruhC°n'O-OH4i None 2. a. Core sen therraoeouples *700 0FRerseost s. Onnc-Througr-Ccolino;EOP-2O HR4 irr

• ANDel-nnr.. ..1 b. RVLMS Ilnics.teO 0.0%,' :"" :, :.AND* """ I. " a. Rasesbo=ase procedures Ist effeotine in* .. .." 15 rrinlbtes.RP-0.01 A/E reuing > 5500 RMwl. : ',3. Containmeel 2. Coolant acrivity >300 ruCulga Cane : Colanrairanna radinean Oron~er.RM-09t AltoPsisrirres I RCS Eqelo~enet r-rr Noane riS.dr > 40 Rlhnr. None .Noese Conrainrment radiation maniro, Rtr-051 r./EA55tivJl a er/h ncnata 3r~e/o reading
• 25,000 PRfhr.30 crane prier/ry" asapre piping edsti~an t othe irod SL-t per CH-SlP-PA.0O07 ________F t. Coalaismenl isolatlon Is required andEIThER oi the lOllowisyj a3 cent.inranal Pressure > so pasi onda. UNPLANNED dmwe0n5 in rislng.aaesraiureenr pressure or rise is Orairriotna moniror readingsetO~tide at onainrsilenet Is rrre. 4. Hydrogen Consentrearloa in Coermorn'ent] [ Emergency' DireCtors iudgreent > Sindioare a eosS at cairainraenl OR4. Cnerainnnerrre Hn Non ne Nonea None thtegriry. 5. a. Contuiarent nreosure
• 5 poigIntegrit or bypass OR AN5 .UNISOI.AEL5 pathwasy from to. ess tosnan raiful train ciCenrlornat I rh nearoeoonl Cantalnmest Cooing ORerdsts. Containarent Spray anlulpre~ntiOR operating per design fre > 152. Ingleation or POS leakage outside of aringtee..ontenllnraent.5 mnergnc 1. Asy Corsdnion in the npiniaa oI rue 2. Asp Condition in Ire opinean ot rale 1. Any Condi~tion in lthe opliion at rho 2. Any Condtone in the opinion athre 1. Any Condition in 1he opinion or the 2. Any Condition in toe cpinioa at theEnrergensy Directar thar incastea LOSS Emergency Direcror that indicares Emergency Director lhar mndicates Lnss Emergency Dirnoer rce tha etleeke Emeergency Cirestor thut indlo.ales Loss Pomeroncla Diester thae iotandiereDirector Judgenn at rho Fueal Cla.d Osrner. Poreatlal Less at lhe Pear Crud Sorrier. nf thn RCS Barrier. Potentilr Loan of tene RCS Boarier. 01 nsa Conrainmenr Earrner.PoetaLenn aCnirnt____________ __________________________________________________ ________________________ ________________________ _______________________rt-iarrerMonth 20XX HOT MATRIXv -in- riot 4- -Hot oniutcoewn a -uc[ic biaUroOWnFC 3-14-UelUeledHOT MATRIX EP-XX-XXXX (Revision XX)

FT. Calhoun Station HOT MATIRIX ...N OT MATRIX Omaha Public Power DisticSystem MalfunctionMG1 Prolonged loss of all otfflte T[]and all onsite AC power to emergency buses.Emeroqency Action Levels (EAL) :Note: The Emergency Director should declare the avant-promptly upon determining that the applicable-timehas been exceeded, or will likely be exceededMS1 Loss of all Off-site and On-Site ,AC power to emergency busses for 15 minutes or longer.!Emeraency Action Levels (EAt.) :I Note: The Emergency Director should declare the eventS promptly upon determining that the applicable timei has been exceeded, or wilt likely be exceededo31. Loss of ALL off site AC power to vital 4160 volt buses t A3 1. Loss of ALL offsite AC Power to vital 4160 volt busesand 1A4. I A iaand1A4."MA1 Loss of all but one AC power F[source to emergency buSes fof 15 minutes or longer.Emergency Action Levels (EAt.) :Note: The Emergency Director should declare the eventpromnpty upon determining that the applicable limehss been exceeded, or mill likely be exceededt. AC power capability to vital 4160 volt buses 1A3 and1A4 reduced to only one of the following power sourcesfor> 15 minutes.* 1 61- Kv.Circuit ..*.. .EDGOalm i2. Any additional single power source ilailure mill result in atoes of ALL AC power to SAFETY SYSTEMS.MU1 Loss of eli oft site AC pomer capability to emergency buses for 15 minutes or longer.Emerctencv Action Levels (EAt) :Note: The Emergency Director shOUld declare the eventpromptly upon determining that the applicable limehas been exceeded, or will likely be exceededLoss of ALL offsite AC power capability to vital 4160 voltbuses 1A3 and 1A4 for > 15 minutes.AND2. Failure of EDG's DGI and 0G2 to supply power to vital4160 v0lt buses 1A3 and 1A4.AND3. EITHER O1 the following:a. Restoration oi at least one vital 4160 volt bus in< 4 hours is not likely.OR'b. Core exit thermocouples > 1 550°F.AND2. Failure ofE.DGas 051 and DG2 to. supply power to vital4160 V0lt busesl1A3 and 1A4'.. :AND:.* i3. Failure toe restore power to at least one 60 volt bus ..in < 15 lminutes froma the lime of loss of both offsite and*onsife AC power. -? ,": MG2 Loss of all AC and Vital DC power sources for 15 minutes or longer.Emeroencv Action Levels ('EAL.):;Note: The Emergency Director should declare the eventpromptly upon determining that the applicable timehas been exceeded, or will likely be exceededMS2 "Loss of all Vital DC power-for15 minute~s or longer. j':;Ifr~rIEmeroency Action Levels (EAL} :Note: The Emergency Director shoutd declare the eventpromptly upon determining that the applicable timehas been exceeded, or will likely be exceeded00-U0,1. Loss of ALL oftsita AC power to vital 4160 volt buses I A3and 1A4, Voltage is < 105 VDG on 125 VOC Dual and Bus 2 for> 15 minutes.AND2. Failure of EDG'a DC 1 and DC-2 to supply power to vital4160 volt buses 1A3 and 1A4.AND3. Voltage is < 105 VDC on 125 VDC Bus I end Bue 2.AND4. ALL AC and Vital DC power sources have been lost for>_ 15 minutes.Mode:t- Power Operations2 -Stanup3- Hot Standby 4 -Hot Shutdown 5 -Cold Sul~udown 0 -DefueledMonth 2OXX HOT MATRIXFC 3-15Mot OX HTMARXF -5HOT MATRIX EP-XX-XXXX (Revision XX) IT" HOT HOT MATRIX Dmaha Public Power DistrictFT l~lhn~n Rtatinn IdOT MATRIX HOT MATRIX Omaha Public Power DistrictSystem MalfunctionMSS inability to shutdown the reactor causing achaflenge to core cooling or RCS heat removal.wMA3 Automatic or manual trip fails to shutdown jf]j, MU3 Automatic or manual trip fails to shutdownthe reactor, and subsequent manual actions taken at the the reactor.reactor control consoles are not successful in shutting down itho ,carqntTXD!_)0.SEmeroency Action Levels rEAL) :tAutomatic or Manual Trip did no._t shutdown the reactoras indicated by Reactor Power > 2% and SUM is, negative.S AND2. All manual actions to shutdown the reactor have beenunsuccessful as indicated by Reactor Power >2% andSUR is negative.AND3. EITHER of the following conditions exist:a. Core exit thermocouples > 1550°F.OR'b. RVLMS indicates 0.0%ORo. Once-Through-Cooling, EOP-20 HR4 in :affect.Emerqencv Action Levels rEAL) : i Emerge'ncy Action Levels (EAL) :Note: A manual action is any operator action, or set of Note- A manual action is any operator action, or set ofactions, which causes the control rods to be rapidly actions, which causes the control rods to be rapidlyinserted into the core, and does not include manually I inserted into the core, and does not include manuallydriving in control rods or implementation o1 boron drivying in control rods or implementation of boroninjection strategies. injection strategies.1. Automatic or manual Trip did not shutdown the reactor ]. a. Automatic Trip did not shutdown the reactor asas indicated by Reactor Power > 2% and SUR is i Indicated by Reactor Power > 2% and SUR isnegative, negative,AND .AND2. Manual actions taken at the Console Center are no.tsuccessful in" shutting down the reactor as indicated byReactor Power > 2% and SUR is negative.Center is successful in shutting down the reactor.OR2. a. Manual Trip did not shutdown the reactor asindicated by ReactOr Power > 2% and SUR Ianegative.ANDb. EITHER of the following:1. Subsequent manual action taken at theConsole Center is auccesaful in shuttingdown the reactor.OR2. Subsequent automatic Trip is successful inshutting down the reactor.tMA4 UNPLANNED loss of Control Room MU4 UNPLANNED lose of Control Room Tabla li1 Controt Room Parameters Table M2 Signitlcant Transients indications for I15 minutes or longer with a significant indications for 15 minutes or longer.to________________________ transient in progress.0O

• Reactor Power Emergency Action Levels rEALt Emergefncy Action Levels (EALhI* Z ee Electricsl Lead Rejection >25% lull electrical learl* O rsue*Reactor Trip jNote: The Emergency Director should declare the event Note: The Emergency Director should declare the event__ *RSPesreEC cuto promptly upon determining that the applicable time promptly upon determining that the applicable timeSIn CorelCore Eait Temperature
• CSAtainhas been excaeded, or will likely be exceeded has been esceeded, or will likely be esceededoo ° Level in at least one OTSG. 1. a An UN PLANNED event results In the Inability to An UNPLANNED event results in the inability to monitor*[O *Auxiliary Peed Water Flow monitor ANY Table M1 parameters from within the ANY Table M1 parameters from within the Control Room forIControl Room for> I5 minutaes. > 15 minutea.r- ANDfO b; ANY Table M2 transient in progress.-Power Operations2 -Startup3- Hot Standiby 4 -Hot Shutdown 5 -Celdl Shtrdown D) -DerueledMonth 20XX HOT MATRIXFC 3-16Mot OX itT ARXF -6HOT MATRIX EP-XX-XXXX (Revision XX)

HOT MATRIX Omaha Public Power DistrictFT. Calhoun Station HOT MATRIX HTMTI mh ulcPwrDsrcLSystem Malfunctioni ~~MA5 Hazardous event affecting a SAFETY SYSTEM required for the current operating mode.Emerqency Action Levels ("EAL) :1, The occurrence of ANY of the following hazardousevents:* Seismic event (earthquake)*EI*Ifra or external floodingevn* High winds or tornado strike(0

• FIRE>"
• EXPLOSION*Other events with similar hazard characterist~ce asCO determined by the Shift Manager* i: : " ~2. E'ITHERof, thea following: .::'/: ::; :: ... .:"" :'i~ a. Evernt damage has ceased indications ol degraded::; performance in at least one train of a SAFETY., :: : " .:,:: SYSTEM required by Technical Specifications for= , , : .: Current ...operating m'ode...:;:. ,:.':, i::::b. The event has caused VISIBLE DAMAGE to a:: ... .. 'i: :: :::,:::- SAFETY SYSTEM component or structure./.. .:,.-. .,:,, ': : ;' :,:, required by Technical Spapifications for the curret~* :"S .:i '...;: : ... operating mode ,.:..* MU6 RCS leakage for 15 minutes or" longer. E]]-_merqencv Action Levels (EAL) :Note: The Emergency Director should declare the eventpromptly upon determining that the applicable timehas been esceeded. or will likely be exceeded.-J 1. RCS unidentified or pressure boundary leakagetoI> 10gpm for > 15 minuteso I OR2. ROS identified leakage >25 gpm for > 15 minutes.OR1 3. Leakage from the ROS to a location outsidecontainment >25 gpm for_> 15 minutesi_ .-. _________________ ________________Made: 1 -Power Operations 2 -Startup a -i-rt vtanoby 4 -i-Ot Snuteown 5- Cold Shartdown I) -DatuetedMonth 20XX HOT MATRIXFC 3-17Mot OX HTMARXF -7HOT MATRIX EP-XX-XXXX (Revision XX)

FT ahu tto O ARXHTMTI O-haPuli Poe Ditrj!System MalfunctionTable M3 Communications Capablltfv(50(5C.)CE0C)System Onaite Offaite NRC I800 MHz Radio System XGai-tronics System XSecurity Building PABX X X XTraining Building PABX X X [ XCommercial X XTelephones .Conference Operations !Network (COP) -_____FTS-ENS ... X IXHPNX XSatellite phones X "MUJ7 Loss of all On-site or Off-site communication capabilities.Emergency Action Levels (EAL) :1.Loss of ALL Table M30Onsite communicationscapability affecting the ability to perform routineoperations.OR2. Loss of ALL Table M30Offaite communication capabilityaffecting the ability to perform olfa'ite notifications.OR3. Loss of ALL Table M3 NRC communication capabilityaffecting the ability to perform NRC notifications.Blair Phone Lineux IMU8 Failure to isolate containment or lost ofcontainment* pressure control.'~JI~1I~00Mode: t -Power OperationsEmergency Action Levels tEAL) :1. a. Failure of containment to isolate when requiredby an actuation signal.AND .b. ANY required penetration remains open > 15minutes of the actuation signal.OR2. a. Containment pressure>* 5 paigANDb. Less than one full traIn of Containment CoolingOR Containment Spray equipment operatingfor > 15 minutes.2 -Startup3 -Hot Standby 4 -Hut Shutdown 5 -Cotrd Sheuttown 0 -DefueatedMonth 20XX HOT MATRIXFC 3-18Mnh2X HOMARXC3.8HOT MATRIX EP-XX-XXXX (Revision XX) T.ahonStation NOT MATRIX OTMATRIX Omh ulcPerDtrcHazads nd Oherconditions Affecting Plant SafetyHG1 HOSTILE ACTION resulting in loss of physical control of the facilityEmerqency Action Levels (EALlI:1. A notification from the Security Force that a 1-OSITLEACTION is occurrng or has occurred within theS PROTECTED AREA.2. a. ANY Table IHl safety function cannt be= controlled or maintained.S ORb. Damage to spent fuel has occurred or isIMMINENTHS1 HOSTILE ACTION within fhePROTECTED AREAEmerqency Action Levels tEAL) :A notification from the Security Force that a HOSITLEACTION is occurring or has occurred within the.PROTECTED AREA. -HA1 HOSTILE ACTION within the OWNER CONTROLLED AREA or airborne attack threatwithin 30 minutes.Emergency Action Levels (EAL):1. A validated notification from NRC of an aircraft altackrthreat < 30 minutes from the site.OR2. Notification by the Security Force that a HOSTILEACTION is occurring or has occurred within the OWNERCONTROLED AREA.HUI Confirmed SECURITY CONDITIONor threat.~I~II~1E~EmeqecyAction Levels EAL)1, Notification ol a credible security threat directed at thesite as determined per SY-AA-10f -132, SecurityAssessment and Response to Unusual Activities.OR2. A validated notification from the NRC providinginformation of an aircraft threat.OR3. Notification by the Security Force of' a SECURITYCONDITION that does no~t involve a HOSTILE ACTION.I .1 +Table H1 Safety Functions[.Reactivity Control(ability to shut down the reactor and keep it shutdown)Core Cooling (ability to cool the core)RC$ Heat Removal (ability to maintain heat sink)NS2 Inability to control~a key safety function twi outside the Control Room :; !'i:!Emergency Action Levels (EAIL)' i:/;;..Note: Th~e Emergency Director should declare the eventprornpty upon determining th~at the applicable time has been exceeded, or will likely be exceeded. i,1. ( A Control Room evacuation h~as' reulteriri plant controlbeing trannsferred from the Con~trol Room to altematelocation ..% .. :* AOP-07 Evacuat ion cit Control RoomOR* AOP-O6 Fire EmergencyAND2. Control of ANY Table HI key safety function is noreestablished in <c 15 minutes.' A2 Control Room evacuation renulting in transfer of plant control to alternate locationsEmergency Action Levels (EAL): ."A Control Room evacuation has resulted in pf ant contirolbeing.transferred from the Control Room to alternate.locaions per:": i1-*:' Evacuation of Control ;Room.OR :"" °"AOP-C6 Fire Emergency ..-50,a.Mode:I- Power Operations2 -Startup3 -Nor Standby 4 -Hot Shutdown S -Cold Shurdown 0 -DatfsaladMonth 20XX HOT MATRIXFC 3-19Mot OX HTMARXF -SHOT MATRIX EP'-XX-XXXX (Revision XX) PT. FT. C~slh~n Ch~finn LIAT MATOIYHazards and Other conditions Affecting Plant SafetyHU3 FIRE potentially degrading the level of satety of the plant.Emergency Action Levels (EAL):Note: The Emergency Director should declare the eventpromptly upon determining that the applicable timehas been exceeded, or will likely be exceeded.1. A FIRE in ANY Table H-2 area is no extinguishod in< 15 minutes ot ANY of the following FIRE detectionindications:Table H2 Vital Areas

• Report from the hield (i.e., visual observation)*Containment Building
• Receipt of multiple (more than f ) tire alarms or, .oAuxiliary Building *. .,::;' " *Intake ~trocture *Field verification of aeingle fire alarm...
• Turbitne Building (SSE only) OR*: ". ": Main and Auxiliary Tranrslorrner Yard 2. a. Receipt of a single fire alarm in ANY Table H2.Condensate Storage Tank Area area (i.e., no other indications of a FIRE).i", " " ;. , "AND-!.,.. -.b. The existence of aFIRE isnottverified in <30: " :. " ,minutes of alarm receipt.* -OR" _,..../i~i .'..,,;ii~ ..3. A FIRE within the plant PROTECTED AREA not" .i:.. 'i....: -extinguished in < 60-minutes of the initial report, alarm: ,:. '. :i :.; '"or indication.* '" " A FiRE within the plant PROTECTED AREA that" requires tirefighting support by en offaite tire responseagency to extijnguish.-HU4 Seismic event greater than OBE levelsEmerqency Action Levels tEAL) :a Seismic event
• Operating Basis Earthquake (OBE) 5s~indicated byoSTRONG MOTION SEISMIC EVENT INtPROGRESS alarm~OREvent indicator (SMA-3 Control Panel) haschanged trom Black to WhiteMode: 1 -Power Operations 2 -SIarIUp 3 -Hol Standby 4 -Hot Shutdown Col Shutdown 0- DetueledMonth 20XX HO'r MATRIXFC 3-20Mot OX HTMARXF -0HOT MATRIX EP-XX-XXXX (Revision XX) nr ~Ihn,,n a*nyinn wrvr MATLnIYHazards and Other conditions Affecting Plant SafetyTable H3Areas with Entry Related Mode Applicabilitya0Area Entry Related Mode________________ ApplicabilityContainment Modes 4, 5Sand 0Room 6 Modes 4, S and 0Room 13 Modes 4, 5 and 0Room 15A Modes 4, 5 and 0Room 21 Modes 4, 5 and DRoom 22 Modes 4, 5 and DRoom 56 Modes 4,,5 and DRoom 57 Modest5 Sand 0Room 69 "- Modes 4, S and 0HAS Gaseous release impeding access to equipment necessary for nsornmal plant operations,cooldown or shutdown.Emerqenoy Action Levels (EAL) :Note: It the equipment in the listed room or area wasalready inoperable, or out of service, before the eventoccurred, then no emergency classification Iswarranted.1. Release of a toxic, corrosive, asphysiant or flammablegas in ANY Table H-3 ares.AND2. Entry into the room or ares Is prohibited or impededaw0*0a=HUB Hazardous Event r [ Emeruenov Action Levels (,E, tL) :Note:. EAL #4 does not apply to routine traffic impedimentssuch as tog, snow, ice, or vehicle breakdowns oraccidents.1. Tornado strike within the PROTECTED AREA.OR2. Instemeal room or area flooding of a magnitude sufficientto require manual or automatic electrical isolation of aSAFETY SYSTEM component required by TechnicalSpecifioations for the current operating mode.OR3. Movement of personnel within the PROTECTED AREAis impeded due to an offsite event involving hazardousmaterials (e.g., an offsite chemical spilt or toxic gasrelease).OR4. A hazardous event that results in on-site conditionssufficient to prohibit the plant staff from accessing site via personal vehicles.ORi5.Abnormal River level, an indicated by EITHER:a. > 1004 feet MSL elevation (high level)OR0. < 976 feet, 9 Inches MSL elevation (tow level)Mea 5 'wrUeainMOde:1- PowerOpemtions2 -Startup3 -HOt Standby 4- HOt Shutdown 5 -Cald Shsutdown D0- DeluetedMonth 20XX HOT MATRIXFC 3-21Mnh2X HOMARX- F3-1HOT MATRIX EP-XX-XX.XX (Revision XX)

FT. Calhoun Station HOT MATRIX HOT MATRIX Omaha Public Power Di'strietHazards and Other conditions Affecting Plant SafetyHG7 Other conditions exist which in the I-s7 Other conditions exist which in the HA7 Other conditions exist which in the HU7 Other conditions exist which in the judgment ot the Emergency Director wsrrant declaration of a judgment of the Emergency Director warrant declaration of a Ijudgment of the Emergency Director warrant declaration of judgment of the Emergency Director warrant declaration ofGENERAL EMERGENCY. SITE AREA EMERGENCY., an ALERT.anUU ALE NTEmerge~ncyAction Levels EAL}:Other condilions exist which in the judgment of theEmergency Director indicate that events are in progress orhave occurred which Involve actual or IMMINENTtiubstantiel core degradation or melting with potential forloss of containment integrity or HOSTILE ACTION thatresults in an actual loss of physical control of the facility.Releases can be reasonably expected to exceed EPAProtective Action Guideline exposure levels offeile for morethan the immediate site area.Emerqency Action Levela (EAL):Other conditions exist which in the judgment of theEmergency Director indicate that events are in progress orhave occurred which involve actual or likely major failures ofplant functions needed for protection of the piublic orHOSTILE ACTION that results in intentional damage ormaticlous acts, (1) toward site personnel or equipment thatcould lead to the likely failure of or. (2) that prevent effectiveaccess to equipment needed for tho protection of the public.Any releases are not expected to result in exposure levelswhich exceed EPA Protective Action Guideline exposuretevets byenotd he site boundary,; .Emerglency Action Levels tEAL) :Other conditions exist which, in the judgment of theEmergency Director, indicate that events are in progress orhave occurred which involve as actual or potentialsubstantial degradation of the level of safety of the plant or asecurity event that invoices probable life threatening risk tosite personnel or damage to site equipment because ofHOSTILE ACTION. Any releases are expected to be limitedto smoall fractions of the EPA Protective Action Guidelineexposure levels.Emerqency Action Levels (EAL):Other conditions esist which in the judgment theEmergency Director indicate that events are in progress orhave occurred which indicate a potential degradation of thelevel of safety of the plant or indicate a security threat tofacility protection has been initiated. No releases ofradioactive material requiring otisite response or monitoringare expected unless further degradation of safety systemsoccurs.CE0-s055.0Caa.Iii* , J ....... .. .. ..... ... ...... ... ... L ... .....Mose:1 -rower uperasonsS- w5arrupC-10 HOt Cn~y 4 --1 H~ tUneownb -GOcrd ahetdown D -DeuetsdeMonth 20XX HOT MATRIXFC 3-22Mot OX HTMARXF -2HOT MATRIX EP-XX-XXXX (Revision XX) tHOT HOT MATRIX Omaha Public Power HOT MATRIX HOT MATRIX Omaha Public Power District--IISFSI MalfunctionsE-HU1 Damage to a loaded cask i11111lCONFINEMENT BOUNDARYEmeruency Action Levels (EAL)Damage to a loaded cask CONFINEMENT BOUNDARY asindicated by an on-contact radiation reading:* > 60mrihr (gamma + neutron) on the top of thespent fuel caskOR* > e00mrlhr (gamma + neutron) on the side of thespent fuel cask, excluding inlet and outlet ducts-I ________________________________________________________Mode:1- Power Operations2 -Startup3 -Hot Standby 4 -Hot Shutdown5 -eld ShatdownD -IletueledMonth 20XX NOT MATRIXFC 3-23Mot OX HTMARXF -3HOT MATRIX EP-XX-XXXX (Revision XX) rl IE:I ILR A'rnlVr'[. I..t]l[]Ql.l[I OluLIgrl U I hi^ gnu i ll,^l nl^ r , It..I.Abnormal Rad Levels I Radiological Effiuentsresulting in olfsite dose greater than 1.000 mRem TEDE resufltg in offistie dose greater than 100 ruRem TEDEor SOG00 mRam thyroid COE. or 500 mflem thyroid COE.i Emergency Action Levels tEALt : Emergency Action Levels tEALINotes: Notes:!* Tme Emergency Director should declare the event promptly

• The Emergency Director should declare the event promptlyupon deterrinlnng thet the applicable time hen been exceeded, upon dotermrining that the applicable time has bean exceeded.i owillikely be exceeded. or will likely be exceeded, anthreassatliesi unknown, assume that the release duration has exceeded 15 unknown, assume that the release duration has exceeded t15S minutes. minutes.* Classiticetlon based us etifluevt rmonitor readings aS.umes Ciaausitio.atlen based on effluent monitor readings assumes thatI- that a release petit to the eunironment is established. It the a release path to hthe environrrvent iv established. if the ettluentS ettluent flow past an ettluent monitor in known to have stopped flew past an effluent monitor is known to have stopped due lvS due to actions to isolate the releuse path, then the effluent acthons to isolate the release path, then the effluent monitorS mnonitor reading Is no longer vaild for elaus,.iticatlue purp.oses. readursg is no longer vaild for Olasxilicatlon purposes,=t° The pre-csslculuted etiluent meaitor values presented In EAL
• The pre-calculated ettiuent monitor values presented in EALAt# shousid be used tot enmergerroy ciassitication assessments .I1 sihosid be used ior emergency classitication assessments: " until dose assessment results are available.* until done asess..ment mooults are aveiabteb.18 1. Readings on ANY Table R1 Eifflueni Monitor > Table R1 value 1. Readings on ANY Tubte RI Effluent Monitor > Table Rlvalue2 for > 15 minutes., Icr_> 16 minutes.-OR OR' ~2. Dose assessment Using actual meteorology indica~tes doses at 2. Dose assessment using actual meteorology indicates doses at/ or beyoed the site boundary ot EITHER: or beyond the site boundary of EITHER:a. >l000mRemTSDE a. >100mRemTEDEOR ORS b. > 5000mRem COEThyroid b. ,Seo0mRem COE ThyrtoldOR OR3. Field survey renults at or beyond Ihe site boundary indicate 3. Field survey reaulls al or beyond the site boundary indicuteEITHER:. EITHER:a .Gam,'ma (closed window) dose retes >1000 wRertm a. Gamma (closed window) dose rates >100 mRem ameare expected to continue tar > 60 minut en. expected to continue tot > 60 mInutes.OR ORt. Analyses at Saied survey esampies indicate > 5000 b. Analyses of field eurvey sempies Indicate > 500 mRem, mRerm COE Thgnold tar 60 minutes ci Inhalation. CDE Thyroid for 60 minutes ot inhalation.1RA Relase at. fgaseo..s orliquid radioecstvity resulhing In otisite dose greeter than tO rerem TEDEor 50 wrem thyroid DDE.Emergqency Action Levels Notes:* The Emergency Director should declare the event promptiyupon determining that the applicable time bus been exceeried,or wiii likety be excoeeded.* it an ongoing release is detected and lbs release start time isunknown, assume that the release duraeion has exceeded 15minutes.* Classificetion baeed on etiluent monitor readings assumes thata releave path to the environment is established. lifthe effluent11OW pant as elflsent monitor lu known to have stopped due tsactions to isolate the release path, then the effluent meonitorreading is no lunger valid lor classitlcation purposes.* Thes pmo-catculated etflueni monitor` values presented in E.AL e1should be used for emorgenoy classitication assessments untildose assessment results are available.I .ReaOineson ANYsTable RI eldoeni Monitors Table R1 selue tora1mlrnutes.DR2. Dose es-seosrent usnttg acteri watesrelugy iniccates dasas at erbeyond thes boundary ot ErTHER:a. >l10mttoteTsEEORb. > 50 ia sraC0E ThyreidOR3. Analysis oeta leis~ etlusent sempte indicates a coricantrarite or releaserule thet would tenoJf n ivdunes greater than 611THER Ol tha fl~lowng atat" beyond the site boundaryu. 10 m~em TEDE tsrtO 60 mnates at exposureOR5 .50mrRam COCThywid lor60 einutesoe at axpere4. Field sumevy results at atr beyond the site boundaryInlcadie EITHER:a. Gamnmn (boned nilndowl dane tales a 10 wRthr oreaugeated ro ac~ns~ne let a. 65 minutes.DR5. Anedynes O1 bald survey osepiss indicate>. 50 mffet Deo Thyroid tar 611 minutes 01 lnhmstion.RUI Any release el gaseous or liquid ltadioactivlty tO the environment greater than2 times tha DOCM for eo minutes or longer.EmergencY Action Levets tEALI :Notes:* The Emergency Director shonid declare the event promptlyupon determining ithot the applicable tima hax been exceeded,or will likely be exceeded.*f lin ongoing release is detected and Ihe releuue salrt tIme ivunknown, assume that the release duration has esceeded 6Ominutes.* Classiticeice based on effluenl moenlIto readingo assumes thata release past to the environment is established. It the effluentflow paul as effluent monitor is known lv have stopped due toustiono to solate the release path, than the effiosnt monitorreadlng Is no longer vulid tor clussificatlon purposes.1. Reading on ANY Table R2 eftiuent monitoms a 2 times alarmsetpoint estabtebhed by a current radioactive releaseOlscharge permit for > 60 minutes.OR2. Readings on ANY Table R3 t-fftuent Monitor a Table R3 valuefor > 60 minutes:OR3. Sample analyses for gaseous at liquid releases indicateconcentrutivos or release rates > 2 times 0DCM Ltmtt with arelease duration ot > 60 minates.Mode: ! -Power Op ratlss Sturtup 3 -Hot Standiby 4 -Hot Shutdown5 -Cold Shutdown D -Detueled1MolitorGeneral EmergencyS Site Area EmergencyAlertTable R1EffluentMonitorThresholdsRM-053 AS Stack 3.71 E+.O0 uCi/co T 3,71 E-Ot u~i/oc 3.71 E-02 uC~i/cRM-064 (If affected S/0 is not Isolated) 5.68 E+Olcprn i 2.28 E+01 cpms N/ARM-062 AS Stack N/A TN/A 5.25 2405 cpmRM-052 AB Stack N/A 6.23 E+06 cpm 6.23 E+05 opelRM-043 LRWPB Stack N/A 5.44 0+06 cpms 8.44 E+OS cpmRM-057 Condenser Off-GasN/AN/A1.34 E+08 cpmeMonth 20XX COLD SHUTDOWN/REFUELING MATRIXFC 3-22Mot 2X CL SUDONREULIGMARX O3-2COLD SHUTDOWN/REFUELING MATRIX EP-XX-XXXX (Revision XX) n ILq Cf fl.~Ih..,.. C*a~tnn flAl fl CUIlrnnWM~flCCIICI I~Ifl LA ATDAVTable R2 Effluent Monitor ThresholdsEffluent Monitor Description 2X High AlarmRtM-055 (if discharge not Liquid 2SE0 pisolated) Minimum 1 CW 28E0 pPump Discharge HeaderOM-O55 (if disoharge not Lqiisolated) Mnimum 2 W Liquid cpPump Discharge HeaderTable R3 Effluent Mornitor ThresholdsEffluent Monitor Description NOUERM-062 AS Stack (Gas) 3.25 E+04 cpesRM-052 AS Stacis (Gas) 3.55 E+04 cpmRM-043 LRWPB Stack (Gas) 3.37 E+04 cpmRM-057 Condenser Off-G~s 8.83 E-+-5 cpmRM-054A (if SGblowdown is not SC blowdown 9.56 E+04 cpmsisolated)RM-054B (if SGbiowdown is not SG biowdown 9.88E+04 cpmi,,olated)- ________IMonth 20XX COLD SHUTDOWN/REFUELING MATRIXFC 3-23Moth2XXCLDSUTONIIEULIGMARX C3-3COLD SHUTDOWNJREFUELING MATRIX EP-XX-XXXX (Revision XX)

COLD SHUTDOWN/REFUELING MATRIX Omaha Public Power DistrictCIN fl RHl1TflflWt4tlD~FtlFl INA SAATRIY COLD SNUTDOWNIREFUELING MATRIX Omaha Public Power DiatrintAbnormal Rad Levels IRadiological EffluentsRG2 Spent fuel pool level cannot be RS2 Spent fuel pool level at restored to at least lsite-specific Level 3 (site-specific Level 3 description).description) for 60 minutes or longer.Emergency Action Levels tEAt.:. Emergency Action Level IEALI,,Note: The Emergency Director should declare the iLowering of spent fuel pool level to (site-specific Level 3General Emergency promptly upon determining that value).the applicable time has been exceeded, or will likelybe exceeded.Spent fuel pool level cannot be restored to at leant (sifte-specific. Level 3 value) for 60 minlutes or longsr.RA2 Significanftolweling of water D [II][level above, or damage to, irradiated fuel.Emerqency Action Levels (EALI :1. Uncovery of irradiated fuel in the REFUELINGPATHWAY.OR2. Damage to irradiated fuel resulting in a release ofradioactivity from the fuel as indicated by ANY Table R4Radiation Monitor reading >1000 mRers~hrOR3. Lowering of spent fuel pool level to (site-specitoc Level 2value).RU2 Unplanned loss of water levelabove irradiated fuel.Emerqency Actiton Levels (EAL) :WE~JWE~JL~1. a,. UNPLANNED water level drop in the REFUELINGPATHWAY as indicated on ANY of thte following;* L1-I0e (Cold Shutdown PZR Level)oL1-197 (Cold Shtdn RC Level)*, L1-199 (sight glass)* LI-2846 (Spent Fuel Pool Level)ANDb. UNPLANNED Area Radiation Monitor reading riseon ANY radiation'monitor In Table R4.(a0n-Table R4Radiation MonitorsRMS J Area MonitoredRM- otaimn a oio73 Cntinen4RdontoRM- AuiirT ulin e oioAuiiay5ulinedMnioPortable TContainment and ausiliary Building nearMonto f uel handling areasTable R5Areas Requiring Continuous OccupancyMain Control RoomCentral Alarm Station (CAS)Tabte RBAreas with Entry Retated Mode ApplicabilityArea Entry Related ModeArea ApplicabilityContainment Modes 4,.5 and DRoom 6 Modes 4, 5 and DRoom 1.3 Modes 4, 5 and DRoom 3.5A Modes 4, S and DRoom 21 Modes 4,5S and DRoom 22 Modes 4,S5and CRoom 56 Modes 4, 5 and DRoom 57 Modes 4,S5and DRoom 69 Modes 4, 5 and DRA3 Radiation levels that impede [[[access to equipment necessary for normal plant operations,cooldown or shutdown.Emergency ActIon Levels (EAL) +/-Note: If the equipment in the room or area listed in TableR6 was already in~operable, or out of service, beforethe event occurred, then no emergencyctassification is warranted.1. Dose rate greater than 15 mR/hr in ANY of the areascontained in Table R5.OR2. An UNPLANNED event results in radiation levels thatprevent or signitlisally ilapede access to any of theplant rooms in Table R6.Mode:1 -Power Opemlonss2 -Startup3 -Hot Standby 4 -Hot Shutdewn 5 -Cold Shutdown 0 -betfueledMonth 20XX COLD SHUTDOWN/REFUEUNG MATRIXFC 3-24Moth2XXCODSIUTONIEUENGMTRX O3-4COLD SHUTDOWN/REFUJELING MATRIX EP-XX-XXXX (Revision XX) Ft n ING MATRIXCOLD SHUTDOWN/REFUELING MATRIX Omaha Public Power DistrictFt 4~nIho~n ~frtinn CflLfl 5HtITflAWNIREFItFLINE~ MATRIX COLD SHUTDOWN/REFUELING MATRIX Omaha Public Power DistrictCold Shutdown/IRefueling System MalfunctionsCA1 Loss of all oftsile and onsite AC powerto emergency busses tor i5 minutes or longer.Emerqency Action Leveis (EALi!:5)S00~C)"C0-aNote: The Emergency Director should declare the eventpromptly upon determining that the applicable timehas been exceeded, or will likely be exceeded1. Loss ot all otitsite AC power to vital 4160 volt buseslA3 and 1A4.AND2.Failure of EIJG's DG1 and DG2 to supply power tovital 4160 volt buses 1A3 and 1A4.AND3.Failure to restore power to at least one vital 4160volt bus in <i15 minutes tram the lime of loss atboth offeite and onsite AC power.CUI Loss at all but one AC power source []"to emergency buses for 15 minutes or longer.Emergency Action Levels tEAL) :Note: The Emergency Director should declare the eventprompty upon determining that the applicable time has beenexceeded, or will likely be exceeded1. AC power capability to vital 4160 volt buses 1A3 and1A4 reduced to only one of the following powersources tar > 15 minutes.* 161 Kr, Circuit* 345 Ky Circuit* EDG DGI* EDG DG2AND2. ANY additional single power source failure will resultin a loss of ALL AC power to SAFETY SYSTEMS.Eeaa.CA2. l-azardoua event affecting -1SAFETY SYSTEM required for the current operating mode.Emerglency Action Levels (EAL'):1. The occurrence of ANY at the following hazardous _events:* Seismic event

• Internal or external tlooding event* High winds or tornado stdke"*FIRE* EXPLOSION* Other events with similar hazard characteristics a~sdetermined by the Shift ManagerAND2. EITHER at the following;a. Event damage has caused indications otdegraded performance in at leas! one train at aSAFETY SYSTEM required by TechnicalSpecifications tar the current operating mode.ORb. The event has caused VISIBLE DAMAGE to aSAFETY SYSTEM component or structurerequired by Technical Specifications for the currentoperating made.__________________________________________________________ +/- .i~ aMode:1 -Power Opewtions2 -Startup3-- Hot Standby 4 -Hot Shutdown 5 -Cold Shutdown D0- DefueiedMonth 20XX COLD SHUTDOWN/REFUELING MA'I'FUXFC 3-25Mot 2X CL SUDONREUUG ARI C .5COLD SHUTDOWN/REFUELING MATRIX EP-XX-XXXX (Revision XX)

C'I"II I'1 Pt"tl lIMP- Coid Shutdown I Refueling System MalfunctionsCU3 Loss of Vital DC power for 15 minutes or longer.Emergency Action Levels ~Note: The Emergency Director should declare the eventm° promptly upon determining that the applicable time haso bean exceeded, or will likely be exceededVoltage is <1O5 VOC on required 125 VDC Bus I and Bus 2for >15 minutes.CU4 Loss of all onsite or otfsite communication I@]lr-di-"Table Cl Communicationls Capability -capabilities.System Onsite Offalte NRC -Emergency Action Levels (EAL'L:SystemzRdi X 1. Loss of ALL Table C10Onsife communications capabilityGai-trenics System X affecting thle ability to perform routine operations.Security Building X X X ORPA8X _____- 2. Loss of ALL Table C10Offsite communication capabilityTraining Building X X affecting the ability to perform off site notifications.0PABX OCommercial OTelephones X X X 3. Loss 01 ALL Table Cl NRC communlcat~on capabilityEofeece affecting the ability to perform NRC notifications.0oOperations Network i X(COP)FTS-ENS __ X XHPN J XSatellite phones x X XBlair Phone Line i X ;Table C2 ROS Heat-up Duration Thresholds -CA5 Inability to maintain plant in cold shutdown CU5 UNPLANNED rise in RCS temperature.

• C otanetCosr e- -p Emergency Action Levels (BALl : Emerg[ency Action Levels rEAL) :Status Status Duration Note:Noeintact Not Applicable 60 minutes' The Emergency Director should declare the event promptiy *The Emergency Director should declare the event promptlyNot Intact ' upon determining that the applicable time has been upon determining that the applicable time has beenEstablished I20 minutes" exceeded, or will likely be exceeded. exceeded, or will likely ha exceeded..I *A momentary UNPLANNED excursion above the Technical * -A momentary UNPLANNED excursion above the Technical__________________I Specification cold shutdown temperature limit when heat Specification cold shutdown temperature limit when heatII removal function is available doss not warrant removal function is available does not warrantaclassification, classification.Reduced Not Established 0 minutes i. UNPLANNED r'ise in ACS temperature > 21 00F.Inventory j .UNPLANNED rise in RCS temperatures>210°F for OR"It an ROS heat removal system as in operation within TalO 2drto.R oso tefloigfr 5mntsOR a. ALL ROS temperature indications--this time frame and lRCS temperature is being reduced, 2. UNPLANNED RCS pressure rise > 10 psig as a result of ANDthn..LThehod..tis.t.p.icbl.temperature rise. (This EAL threshold does not apply b. ALL RPV level indicationsduring water- solid plant conditions.) ________________ ______________________________________________________Macre:Month 20XX1 -r'ower uperarranS 2 -Star'tup 3COLD SHUTDOWNIREFUELING MATRIX-HOt Staneey 4 -Hot Shutdown 5 -uOld Sauldcwn D -OefueledFC 3-26COLD SHUTDOWNIREFUELING MATRIX EP-XX-XXXX (Revision XX)

Ft. Calhoun Station COLD SHUTDOWN/REFUELING MATRIX *COLD SHUTDOWN/REFUELING MATRIX Omaha Public Power DistrictCold Shutdown I Refueling System MalfunctionsCOG LOSS of reactor vessel / ROS inventoryaffecting fuel clad integrity with containment challenged.Emereency Action Levels (EALt:Note: The Emergency Director should declare the eventpromptly upon determining that the applicable lime hasbeen exceeded, or will likely be exceeded1. RVLMS indicates 0.0% for >30 minutes.OR2. a. Reactor Vessel / RCS level cannot be monitored for>__30 minutes.ANDb. Core uncovery is indticated by ANY of the following:* Table C3 indicalions of a sufficient magnitudeto indicate core uncovery.OR,, Erratic Source Range Neutron Monitorindication.OR* Containment Area Radiation Monitors reudlng> 20 H/hr.ANDc. ANY Containment Challenge Indication (Table C4)Table C3 Indications of RCS Leakagle* UNPLANNED Containment Sump level rise** UNPLANNED Auxiliary ffIdg. Sump level rise'-Reactor Coolant Drain Tank level rise'* UNPLANNED Quench Tank level rise'o UNPLANNED Spent Regenerate Tank level rise"* UNPLANNED rise in RCS makeup* Observation of leakage or inventory loss*Riee in level is attributed losa loss of reactor nesseL'RCS inventoly.CS6 Loss of reactor vessel I RCS inventoryaffecting core decay heat removal capabilities.Emergency Action Levels IEALl;Note: The Emergency Director should declare thepromptly upon determining that the applicablehas been exceeded, or will likely be exceeder1. Wilh CONTAINMENT CLOSURE established RVLindicates 0.0%OR2. With CONTAINMENT CLOSURE no._t establishedRVLMS _<&80%OR3. a. Reactor Vessel!/ RCS level cannot be monitorsfor>30 minutes.ANDb. Core uncovery is indicated by ANY of the follow° Table C3 indicat ions olea sufficient magnitude toindicate core uncovery.OR* Erratic Source Range Neutron Monitor indicationOR* Containment Area Radiation Monitors weading* 20 R/hr.CA6 Loss of reacfor vessel / RCS inventoryCU6 UNPLANNED loss of reactor vessel / RCSinventory for 15 minutes or longer.~If~Ernerqency Action Levels tEAL)Note: The Emergency Director should declare the eventpromptly upon determining that the applicable timehas been exceeded, or will likely be exceeded1. Loss of Reactor Vessel / PCS inventory as indicated byRVLMS < 14%OP2.a. Reactor Vessel/IRCS level cannot be monitored for> 15 minutes.ANDb. Loss of Reactor Vessel / RCS inventory per Table C3indicationsEmerqency Action Levels /EAL) :Note: The Emergency Director should declare the eventpromptly upon determining that the applicable timehas been exceeded, or will likely be exceeded1. UNPLANNED loss of reactor coolant results in the inabilityto restore and maintain Peactor Vessel I R0S level to> procedurally established lower limit for > 15 minutes.OP2. a. Reactor Vessel / RCS level cannot be monitored.ANDb. Loss of Reactor Vessel / ACS inventory per Table C3indications.0SreTable C4 Containment Challenge Indications* Hydrogen Cencentration in Coataewemen > 3%* UNPLANNED rise in constaimnenl pressure* CONTAINMENT CLOSURE not eslablinhed"*If CONTAINMENT CLOSURE is re-established peer to esceedingthe 30-minute core uncovery/time limit, then esoolalien to aGeneral Emergency Is otrequired.+/- _____________________________________________________ :4 I _______________________________________________________1 -Poser Operations2 -St artup3 -Hot Standby 4 -Hot Shutdown 5 -Cald Shutdown 0 -DeluetedMonth 20XX COLD SHUTDOWN/REFUELING MATRIXFC 3-27Mot 2X OL HUDW/RFEIN ATI C -7COLD SHUTDOWN/REFUELING MATRIX EP-XX-XXXX (Revision XX) Ft. Calhoun Station COLD SHUTDOWN/REFUELING MATRIXmFt. Calhoun Station COLD SHUTDOWNIREFUELING MATRIX COLD SHUTDOWNIREFUEUNG MATRIX Omaha Public Power tilsirtet-A -A- A A ISHazards amnd Other conditions Affecting Plant SafetyHIGI HOSTILE ACTION resulting in loss Jr HSI HOSTILE ACTION within the HA1 HOSTILE ACTION within the HU1 Confirmed SECURITY' CONDITION of physical control of the facility PROTECTED AREA OWNER CONTROLLED AREA or airborne attack threat or threat.within 30 minutes.Emergency Action Levels (EALl:;1. A notification from the Secudty Foice that a HOSITLE Emergency Action Levels tEAL) : ,Emerqency Action Levels tEAL) : Emerqency Action Levels IE.AL):ACTION is occurring or has occurred within the A notification from the Security Force that s HOSITLE 1. A validated notification from NRC of an aircraft attack 1. Notification of a credible security threat directed at thePROTECTED AREA. ACTION is occurring or has occurred within the tra 3 iue rmteStst sdlrie e YA 3,ScrtoPROTECTED AREA.thet<3mitefomteitstasdtriepr -A-012.SuiyAND OR Assessment and Response to Unusual Activities.2. a. ANY Table Hi safety function cannot be ORS controlled or maintained. 2. Notificetion by the Security Force that a HOSTILE 2. A validated notilication from the NRC providing.... ... ..... ....ACTION is occurring or has occurred within the OWNER information of an aircraft threat.,,rOR .CONTROLED AREA. ORIDmMgeIN sent fulh oure r s. ...... .3. Notification by the Security Force of a SECURITYIMMINENT CONDITION that does no..t involve a HOSTILE ACTION.HS2 Inability to control a key safety HA,2 Control Room evacuation resulting Table Hi Safety Functions functfiont from outside the Control Room in transfer of plant controt to alternate locations*= Reactivity Control EmerQenicv Action Levels tEAL) : Emergency Action Levels (EAt):(ability to shut down the reactor and keep it shutdown) Note.* The Emergency Director should declare tre'event A Control Room evacuation has resulted in. plant control* Core Cooling (ability to coocithe Core) promptly upon determining that the applicable time being transferred from the Control Room to alternate --* RCS Heat Removal (ability to maintain heat sink) has been exceeded, or mill likely be exceeded, locations per.1. A Control Room evacuation has resulted in plant control *AOP-07 Evacuation of Control Roomnbeing transferred from the Control Room to altemnate OR " ......Slocations per: .* AOP-O6 Firs Emergency-AOP-07 Evacuation of Control Room *C) .OR,, AOP-06 Fire Emergencyi ~ ~~AND... .2. Control of ANY Table N1 key safety function Is no~~reestablished in < 15 minutes."-ruw, utiaiuii z .ttu ..m ..a .a ii ivuwr ~ Lll atow uaeWlOOe:L -- t'df lupO -- nul ordrwuoy -not o -LO]Q U -Month 20XX COLD SHUTDOWN/REFUELING MATRIXFC 3*28Mot 2X CL SUDONREULIGMARX C3-8COLD SHUTDOWN(REFUELING MATRIX EP-XX-XXXX (Revision XX) 13 MATRIX Omaha Public Power ~* t~k,,,.n QMZn ~AI fl euii~nnw~mneiim I~Jf~ MATOIY (~flI fl ~I4tffflflWNIRFFlIFLING MATRIX Omaha Public Power fll~fri~,tHazards and Other conditions Affecting Plant SafetyHU: FIRE potentially degrading the level -T _________ofsafety _____t__eplant*il ~Emerqency Action Levels lEALi~Note: The Emergency Director should declare the eventpromptly 'upon determining that the applicable tfmehas been exceeded, or will likely be exceeded.t. A FIRE in ANY Table H2 area is no extinguished in._ ..-. * <15 minu~tes of ANY of th~efollowing FIR E-detection:-indications:Table H2 Vital Areas

• Report from the field (i.e., visual 'observation)* Containment Building *Reoei'pt of multiple (more than 1) fire alarms or* Auxiliary Building indications*Intake Structure *, Field verification of a single tire alarrr*Turbine Building (SSE only) OR* Main and Auxiliary Transformer Yard 2. a. Receipt of a single fire alarm in ANY Table H2* Condensate Storage Tank Area area (i.e., no other indications of a FIRE).ANDb. The existence of a FIRE is no verified In .5 30minutes of alarm receipt.OR3. A FIRE within the plant PROTECTED AREA notextinguished in < 60-minutes of the initial report, alarmor indication.OR4. A FIRE within the plant PROTECTED AREA thatrequires tirefighting Support by an offaile fire responseagency to extinguish.levelsEmerqency Action Levels (EALISeismic event > Operating Basis Earthquake (OBE) asa- -.*iae bSTRONG MOTION SEISMIC EVENT INPROGRESS alarm*Event indicator (SMA-3 Control Panel) haschanged from Black to White1 -Power operations 2 -8tartup 3 -Hot 4 -HOt b -L;Old L) -UelueleclMonth 20XX COLD SHUTDOWN/REFUELING MATRIXFC 3-29Mot 2X CL SUDONREULIGMARX C3-gCOLD SHUTDOWN/REFUEUNG MATRIX BP-XX-XXXX (Revision XX)

I::l' P(*ll il l1:1 IMP. COLD MATRIX Omaha Public Power tAI h ITfl~nItnI LM(5 5AATDIV COLO RHIJTDOWN/REFll~LtNG MATRIX Omaha Public Power flienrt,,tI -., -IHazards and Other conditions Affecting Plant Safety0001-Table H3Areas with Entry Related Mode ApplicabilityArea Entry Related ModeArea ApplicabilityContainment Modes 4, 5 and 0Room 6 Modes 4,S5and PRoom 1.3 Modes 4,5S and D--Room i5A Modes 4, S.and 0Room 2"1" Modes 4, 5 and DRoom 22 Modes 4, 5 and DRoom 56 .Modes 4, 5 and 0Room 57 Modes 4, 5 and DRoom 69 Modes 4.5 and DHAS Gaseous release impeding access to equipment necessary tor aormal plant operations,cooldown or shutdown.Eeenov Ation Levels EAL :Note: If the equipment in the listed room or area wasalready inoperable, or out ot service, betore the eventoccurred, then no emergency classification iswarranted.1. Release oa a toxic, corrosive, asph yriant or flam~mable.gas in ANY Table H3 area.AND2. Entry into the room or area is prohibited or impeded-J +I-- --IHUe Hazardous Event~I~1I~II~Ca.,Emergency Action Levels tEAL) :Note: EAL #*4 does not apply to routine traffic impedimentasuch as fog, snow, ice, or vehicle breakdowns-oraccidents.1. -Tornado strike within the PROTECTED AREA. --*OR2. Internal room or area Ilooding oi a rnagntitude sufficientto require manual or automatic electrical isolation of a* SAFETY SYSTEM component required by TechnicalSpecifications for the current operating mode.OR.3. Movement of personnel within the PROTECTED AREAis impeded due to an offithe event involving hazardous-.-materials (e.g., an offaite chemical spilt or toxic gasrelease).-OR -4. A hazardous event that results in on-site conditionssufficient to prohibit the plant staff from accessing thesite vie personal vehicles.OR5, Abnormal River level, as indicated by EITHER:a. > 1004 feet MSL elevation (high tevel).ORb. < 976 feet, 9 inches MSL elevation (low level)Mode:Month 20XX1- Power Operations 2 -Startup 3 -Hot Stand'byCOLD SHUTDOWN/REFUELING MATRIX4 -Ilot Shutdown 5 -Cold Shutdo'wnFC 3-30D0- OetuetedCOLD SHUTDOWN/REFUELING MATRIX EP-XX-XXXX (Revision XX) It, Calhoun Station COLD SHUTDOWN/REFUELING MATRIXCOLD SHUTDOWN/REFUELING MATRIX Omaha Public Power DistrictFt. Calhoun Station COLD SHUTOOWN/REFUELING MATRIX COLD SHUTOOWNIREFUELING MATRIX Omaha Public Power DistractHazards and Other conditions Affecting Plant SafetyHG7 Other conditions exist which in the judgment of the Emergency Director warrant declaration of aIGENERAL EMERGENCY.EmrinyAction Levels (EALI :Other conditions exist which in the judgment of theEmergency Director indicate that events are in progress orhave occurred which involve actual or IMMINENT -substantial core degradation or meltiag with potential forloss of containment integrity or HOSTILE ACTION thatresults in an actual loss of physical control of the facility.Releases can be reesonebly expected to exceed EPAProtective Action Guideline exposure levets offsite for morethan the immediate site area;HS7 Other conditions exist which in the HA7 Other conditions exist which in the judgnmenf of the Emergency Director warrant declaration o! a judgment of the Emergency Director warrant declaration oitSITE AREA EMERGENCY. an ALERT.Emersiency Acitton Levels (EALlOther conditions exist which in lie judgment of theEmergency Director indicate that events are in progress orhave occurred which involve actual or likely major failures ofplant functions needed for protection of the public orHOSTILE ACTION that results in intenfional damage ormalidious acts, (1) toward site personnel or equipment thatcoutd lead to the tikely failure of or, (2) that prevent effectiveaccess to equipment needed for the protection of the public.Any releases are not expected to result in exposure levelswhich exceed EPA Protective Action Guideline exposurelevels beyond the site boundary.Emerqtency,,Action.Levels (EAL) :Other conditions exist which, in the judgment of theEmergency Director, indicate that events are in progress orhave occurred which involve an actual or potentialsubstantial degradation of the level of safety of the plant or asecurity event that involves probable life threatening risk tosilo personnel or damage to site equipment because ofHOSTILE ACTION. Any releases are expected to be limitedto small fractions of the EPA Protective Action Guidelineexposure levels.HUT Other conditions exist which in the 1 j111['1[judgment o[ Ihe Emergency Director warrant declaration ofan UNUSUAL EVENT.Emerrtencv Action Levels tEAL'):Other conditions exist which in the judgment of theEmergency Director indicate that events are in progress orhave occurred whnich indicate a potential degradation of thelevel of safety of the plant or indicate a security threat tofacility protection has been initiated. No releases ofradioactive material requiring oftisite response or monitoringare expected unless further degradation of safety systemsoccurs.0Eor0ororEuJMode:I- Power Operariors2- Startupa -Hot Standby 4 -Hot Shutdown 5 -Cole Shutdown D0- DetuestedMonth 20XX COLD SHUTDOWN/REFUELING MATRIXFC Moth2XXCLDSUTON/EFEIN ATI F -.tCOLD SHUTDOWN/REFUELING MATRIX EP-XX-XXXX (Revision XX) Pt COLD SHUTDOWN/REFUELING MATRIX Omaha Public Power DistrictFt ~ Ctsllnn roLfl ~HIITflflWtifflFPIIFI ItM~ MATRIX COLD SHUTDOWN/REFUELING MATRIX Omaha Public Power DistrictISS afucinE-HU1 Damage to a loaded caskCONFINEMENT BOUNDARYErnerctency Action Levels (EALt :Damage to a loaded cask CONFINEMENT BOUNDARY asindicated by an on-contact radiation reading:* > 60mrlbr (gamma + neutron) on tie top of thespent fuel caskOR* > OO0mrIhr (gamma + neutron) on the side of thespent fuel cask, excluding inlet and outdet ducts(aU-Made: I -Power OperatiensMOde:1 -Power Operations2 -Starlup3- Hot Standby 4 -Not Shutdown 5 -Gold Shtdacown 0 -DatuetecdMonth 20XX COLD SHUTDOWN/REFUELING MATRIXFC 3-32Mot 2X OL HUDWIRFEIN ATI C -2COLD SHUTDOWNIREFUJELING MATRIX EP-XX-XXXX (Revision XX) LIC-1 5-01 02Enclosure, Attachment 3Radiological AnalysisMethodology for Development of Radiological Effluent*Emergency Action ,LevelsRA 1 3-008 Rev. 1 RP-AA1O1OFC-15.-003 (RA 13-008)S PAGE 1 OF 74________REV.1By: (date)repared by: (dat*) -By: ~dato)IZN~AA.EZ~TMj-~20Meth l~ogy for Development of RadiologicalEfl uent Emergency Action Levels RP-AA-1O010 FC-15-003 (IRA 13-008)PAGE 2 OF 74REV. 1This anatysis documnents the methodology for development of effluent emergency actionlevels (EAL) from the guidance found in NEI 99-01 Rev 6. The process monitor thresholdsare to be used to supplement dose assessment during the early phases of a radiologicalaccident. This analysis supersedes all previous versions of RA-03-004. Radkg~jialAnalysis RA 13-008 revision 1 is now documented in RP-AA-10a 0 FC-1,5-XXX revision 1A revised analysis is required, because th .site is implementing a more recent version ofNEI 99-01 and therefore the actin levels are being updated to:rmeet the new revision.Revision 1 of this analysis calculates the CEDE from iodine for the thresholds readingsindicatng a notificatio of unusual event conditton, These thresholds are now based on aTotal Effecve Dose Equivalent for these conditions rather than whole body doseRadiation Monitor readings are also corrected for inst"ument uncertainty and differencesfor the range of isotopes that could be detected in the effluent (Ref. 4). The th~resholds forRM-0S4 were revised to asstume a release through a lo-pesure steam safety ratherthan the condenser and change is consistent wit the dose assessment program UnriedRASCAL Interface (UJRI).1) The source termn used in this calculation is based on the predominate radlonuclidesthat effect offite dose. These radlonuclides are and Ir1l and are consistent withthe Offsite Dose Calculation Manual (ODCM), The primary calibration of the effluentrad~aton montors uses '=Xe to develop monitor efficencies.2) The initatng conditions for each EAL is basedion doses at the sit boundary of 0.1,10, 100, and 1,000 mrern Total Effctv Dose Equivalent ('TEDE-) in one hour fortetime periods found in reference (1), or 50. 50d, 5,000-mrern for the thyroid dose_ Inaccordance with reference (1), NOUE is based on a multtle of the high alarm effluentset point (,4<), wh~idh are approximately equal tn 0.1 mremlyr see Methods section. Inthe case of action levels for Alert, Site Area and General Emergency a comparison ofTotal Effective Dos Equ~valent (TEDE) and Committa Dose Equivalent (CDE") to thethyroid are calculte~d (Ref. 1).3) This analysis use annual average meteorology to calcuJte monitor thresholds asdefined the ODOM and normal oper'atonal alignments Norm-l alinments are usedbecause EALs are based on the most probable accident scenano Use of averagemeteorology is cwisnlset wit the guidance in reference (1).4) The mronito indcto is based on a single release pathway. A correction forinstrumenet unctinty (15%) an~d a 10% tolerance to account for the differences indetector sensitiviy for the range of isotopes detected. This this correction is con'sistenwihthe O0CM meth~odology.

RP-AA-1 010 FC-15-4003 (RA 13-008)* PAGE 3OF 74REV. 15) The Condenser is assumed operatioal durig a Steam

Generator Tube Rupture(SGTR) arnd: t effluent is meonitored by RM-057 or if arigned to Auxiliary Buildingstad< monitored by RM-063. However, if 1the site loses off-site power, the steamsefetles and atmospheric dump valves Will opens and this; reease path is monitoredby RM-064;I otherwise, the evacuation pumps will remain operabional to rnaintainCondenser Vacuum. These EAts should be based on the most probably accidentevent, however dose assessment pertormed using actual conditions is always themost approp:riate method of classifying (reference 1).5) The radieinde~s used inthe varous process monitrsare assumed to have arelatively fiatI energy response. The only exception is RM-064 because RM-a64 usesa GM-Detector. However, GM-detectors exhibit a flat energy response above 0.1-MeV and over respond to energies below 0.1-MeV. A Nal detector is in RM-057 and these detectors are very seositive and responses accurately to very lowgamma energies. All the other detectors are beta scdintlators, which exhibit flat energyresponse reference (9). The lowest energy typically measured at a nudlear powerplant is approximately .03-MeV, the effective energy of '=Xe. Since tbese processmonitors are calibrated using t~Xe, so their response will sllghtky overestimate to theacial count: rate. resultng in a conservative A 10% tolerance is applied toaccount from these potential difference and is consistent with the ODCM.1) NE! 99-01 Rev. 6. _De~veloomnent of Ermeraencv Action Level for Non.PassiveR_.Q[ November 2012.2) FCS Memo' CHP-2003-01. Radiation Monitor ParamTePtrs for EAGLE. January 6,2003.3) EPA-.400-R-92-001. Manual of Protetv Adion Guides and Prot~ectiv Actions forNuclear Incidns May 1992.4) CH-ODCM-O001 Rev. 24,.Off-Site Dose Calcuiation Manual. January 15, 20155) Technical Data Book ('TDB-lV-7). Pw0cess Monitor Settn,,s. Revisico 223. Juiy 17,2015. i6) Engineering Analysis EA13-021. Dete~rmination of romenrstailve samolina orUeoost-acClent main steam-lne nionitor RM-06,. Rev. 0.7) NCRP Report No. 112. Calibration of Survey Insruments used in Radiation Protectionfor the.Assessetn'u of Ilonzina Radialion Fields Radioactie Surface Conlanination.December 31, 1991. !8) Technical Specifications Seto 5.16(g) Raedioloak/zal Effluent arnd EnvkornmentalProgam,u Page 5,0- Page 14. Amendment N~o, 237.9) Glenn F. Knoll. Radlatbon Dete ctkn and Measurement, Second Edition 1988.10) Engineering Analysi EA-FC-02-019. EAGL.E &.0.. Secondary Side Source TermRev. 0. November 11, 2003.

RP-AA-101O FC-185-003 (RA 13-008)PAGE 4OF 7'4REV. 111) Engineering Analysis FA-FC-02-20. 6.0.0. Source Te~rn Undamaod Core.Rev. 0 November 12, 2003. :12) Calcuistion FC8073. USAR 11.2 Update -Design Basis Curie Content of theRawate Building. 9(112013.13) STM-PM Volume 33,/?adlatxio Manffoiiio Rev I9a. February 28, 2013.14) 10 CFR 20. Standards for, .Proectbn. Aaalnist Radia~tion. ht./1 ovf.- w:15) EC 37873. Subsut Reice t for Radia~tkn Monitr tM-05. Local RatemetarRM-057-1. and Monif or Elements RE-O57. Rev. 2_ October 17, 2007.1) Annual aver'age abnosphe~c disperslon factor (x'O) used in this analysis is smas defed in Table 4of theODCM reference (4).2)- Sensitivy for RM-043 (LRWPB Stc Gas) used in this analysis is 2,33x1073 wWh a b0ackground count rate of 38 cpm, reference (5).3) Sensi~vtr~ for RM-052 (Auxilary Building Stack Gas) used in this analysis is 2,24x107with a backgrwid count r'ate of 70 cpm. reference (5).4) Sensitivity for RM-062 (Auxiliary Building Stack Gas) used in this analysis is ! .89x1073 with a background count rat of 50 cpm, reference (5).5) Sensitlvity for RM-0$4 (Post Accident Main Stea Gas) used in this analysis i3 04x10' 3 with a background count rate of 19 cpm, reference (5).6) Sensitivity for RM-057 (Condenser Off-Gas) used in this analysis is 5.94x10hcpm/p.C/crn3 with a background count rate of 820 cpm, reference (5).7)The DDE dose conversion factors were tak~en from Table 5-3 =~ose Conve,,sionFactors (DCF) and Deri'ved Response Levels (VAL) for Extemal Exiposure Due toImmeso in Contaminated Al, fromt~ reference (3).8) The specific volume used in this analysis is for saturae steam at 222 0F, (22.568f/tabrn) fro stan~dard steam ta~bls, per MR-FC.79-I SOC9) A Main Steam rate of 1.28x10S-4bmr~h is used in this analysis and is equal toth~e design Ilo rate of the 1,00&-PSLA Main Steam Saet and the Steam DrivenAuxiliary Feed water Pump (5,328-cfrn), from reference (8).1O} Condenser off-gas stack flow rate dwng nonmal operations (100% power) measuredat 320-ftrnin (DFCR 94-0014, MR-FC,-84-155D-T3), Maximum condenser evacuationflwrate is rated at 4.500- tE/min.11) Aux~liary Building stack flo rate of 24,157, reference (4). RP-AA-1O1O FC-15-003 (RA 13-008):PAGE 5OF 74REV. 112) iodine to Noble Gas ratio for a non-degraded core 0.007 for non-steam releases and*0.085 for ste~am releases, reference (2), rfeferenc (10), and reference (1 1),13) Radwaste Building stack flow rate of reference (4).14) The thyrokd-weighting factor is 0.03 found in 10 CFR 20.1003 "Weigh~ng Factor W9',reference (14).15) The calcuations were performed using commelialty .available software.Spreadsheets vere calculated using EXCEL 2013 and hand calculatins wereperformed using Mathcad Priso, 3.0.Fort Calhoun must have a formal set of theshold conditions that require plant personnel totake specific actions concerning notifying local governments when olf-orrnai indicators inthe effluent monitors are recognized. The level of response and the codtin leading tothese responses were evakuaedl and documnentxed NEI 99-01 Rev. 8. These guidelineswere developed by NE! and endorsed by the NRC to provide a systematic approach forthe basis of tihe revised EALs.In revision 8, it was recognized that the condition described by the radiological initiatingconditions (IC) might result In radiological effluenlt values beyond the operating or displayrange of the insteled effluent monitor. in those cases, revision B provides guidance=...that the EAL values should be determilned with a margin sufficent to ensure that anaccurate monitor reading is available. For example, an EAL monitor reading might be setat 90% to 95% of the highest accurate monitor feading. This prov~s~ii notwithstanding, ilfih eastimatd/calculated monitor reading Is greater than approximately 110% of thehighest-accurate monitor reading, then develope, may choose not to include the monitoras an indi'cation and identify an afternate EAL threshoid" (referencel1).The dose consequences from these events start at a small fraction of the EPA PAG e.g.,tess th~an 10-millirer to 100-inlilirern TEDE, escalatng to those of the EPA PAG for aGeneral Emergency. The calculatin of these ad~ion levels uses a simprlife approach toTEDE and CDE, which assumes the main radlonudkies are 1=Xe and Site boundarydoses are calculated using a Gaussian plume distnbutlon to determine the gross countrate or radioactive concentrations. By using, an action level 'based on a site boundarydose for a given period of time (1 hour) a monitr set point (threshold) is calculated. TEDEis th sum of Intral and external radiation exposure and those isotopes noted abovebest estimate the major external and internal dose:,.TEDE =EDE.,+ w.CDE,4: (5.1)The TEDE ( I ) rriem In one hour and can be rerte as folows: RP-AA-1O10 FC-15-003 (RA 13-008),; ' PAGE 6 OF 74: REV. 1Whomer Q is the gross release rate fromn nobe gas (1and Iodine X/Q is theannual average dispersion ractor. DC;F is the external' and internal dose converson factor(DCF) and w is the thyroid weighting factor reference (14). is the externl doseeonvj5ion facto forj 1~3)e, DCF, is the external dose (EDE) conversion factor for 131 andis tile Ithyroid dose facto (CDE) for The todine release rate can be calculate by using the bdlne to noble gas ratio 0.007or 0.065 for secondary reeases) and mulptying it by tii noble gas release rate(Qrj.Substituting k0.Q,= for Q~and Into the TEDE equation, the following formula can beQ the gross release rate (noble gas) corresponding to the action level dlose rate (H) atthe site boundary. The process radiation monitors are calibrated using '3wXe. Solvng forQ, the equation is rewritten:> Q(D: ~ oD~WC~] (5 4)The monitor set points for as NOUE is based on 2X the ODOM limit and is based onTechnical Specification section 5.16 (g), at 5 times the Imit (0.1-rem/yr for Noble Gases)as set for in 10 CFR 20 for members of the public (note reference (14): 10 CER 20Appendix B ). Therefore, the dose equivalent equals 500-rn rm/yr (TEDE). The folowingcalculation shows the dose in any one hour for a NOUE at2 traes the limit (reference 1) :H 2 x500-rmy 14mrem/(5): yrRounding this dose per hour to one slgndiant dlgit the EAL for a NOUE is D.1-mrernihrCalculation of the gross release rate based on the oommitted dose equivalent is done by,settng the external dose conversion factors to zero (0), the werg.hb0ng factor to 1. andusing the CDE thyroid dose EAL for H .Since the FALs for an NOUE are based on 2Xthe TEDE annual Ilmits (500-mremn/yr) and is Wrchluded in the TEDE calculation of CEDE aspecifi thyroid dose is not calculatead (refernce 1).,Q: ,, (5.6)X/Q(k,, The gross count rate on the process monitors-are caclae by the following formula(referece 4)R cck~+ A(7 RP-AA-1 010 FC-1 8-003 (RA 13-008): .PAGE 70F 74~REV IWhere R is the monitor threshold count rate (EAL), F is the stack flow rate, ki corrects formonitor uncertainty (0.75), 8 is the monitor efficiency, end Rb is the background count rate.The comredion k2 is only applicable to the accident range monitor RM-.0:64. and corrects forchanges in steam density, however because the dose assessment computer programalready correct for this parameters k2 is setel ..., * ,The accident range monitor RM-063 measures the gross ionncenfralian in the effluent of:the Atndliary Building stack, and the threshold is calculated by dMdlng the l~imitg releaserate by the stc flow rate.Q(5.8)Monitor thresholds eae calculated for each of the emergency ciassiflcations fthatcorresponds to the limitng dose for an exposure perxIo of one-hour.The thresholds for'TEDE an CDE are compared and the tower of the two readings areassigned as th EAL threshiolds.Table 1: Parameter List for Radiation MonitorsIodine to Noble Background Efficiencygas ratio (cain) RM--043 0.007 28,750 38 2.33E+07RM-052 0.007 24,167 70 2.24E+07RM-067 ,0.085 320 ,820 5.94E+08RM020.007 24,167 ...50 1.895+07RM-063 0 .0,07 24,187RM-064 0.065 320 19 3.04E+01Table 2: Radiation Monitor Range and Detector Type'Channel .Rarge : DetecterRM-043 101 -10t cpm Beta, Plastic ScantRM-052 I0 -107cpm Beta, Piastic ScintRM-057 10' -1.48x108cpm2 Gamma. Nal' takeni *rom ST-RU Volume 33. RaIm Mwmtaobig Syusen (vu~ien 13)2jppr ra~ga 1lt k~sbIrmmet Lr (15 b l~s uzpperw c if't equ.rnef b RP-AA-01O FC-t15-003 (RA 13--008), PAGE 8 OF 74____ ___ ____ ___ ___ ____ ___ ____ ___ ___REV. 1RM-062: 10 -107cpm Beta, Plastic Scint.RM-063. 10O pCt/cm3 Ion ChamberRM-064 i0' -107 cpm GM TubeCalculations for each process effluent and accident range mnonitors are In Appendix IThne results of this calculation are used to establish EAL thresholds to alert plant personnelof abnormal conditons.Table 2: Action Level thresholds based on site boundary dose FALs in onehourEmeraencv Action Level (corn or uCl/cc for RM-0631Monitor NOUSE ALERT SITE AREA GENERALRM-043 3.37E+04 5.44E+'05 5.44 E+06 off scaleRM-052 3.85E+04 6.23E+05 6.23E+06 off scaleRM-057' 8,83E+06 1.34E÷08 off scale off scaleRM-062 3.25E.04 5.25E+05 Shift to RM-063 Shift to RM-063RM-003 -3.71E-02 3.71E-01 3.71E+00RM-064 -2,28E+0135,&68E+01Note: The thresholds for RM-063 are in units of pCi/cc. Auother monitor action levels are in units of cpm. Process andaccident range monitor action levels are based iodine aridCDE because the thyroid dose Is more limiting.The process effluent monitors are capable of measuring Instantaneous releases ofroa~ctiit that correspond to a Notification of and Unusual Event (NOUE) and in somecases a SiTE AREA emergency. When condibons the process effluent monitorswill over range, and th high range accident moitors0 wif provide indicatio. The onlyexception is RM-043 the Radwaste Processilng Building. However, the actual source termIn this building is not sfcin to cause a release would require a General emergencyreterenre (12).Radiati0n monitor RM-064 is an off-line acoident irange monitor used to monitor the mainsteam lines and has a low efficec (30.4-cpmn/iCi/cc). Therefore, small changes in countrats will result in Larger measured cocnrain of radioactiiy. For normal levels ofreactor coolant this radiation monlor is not good indict~or for cdassifiation and otheropeaioa method:s should be cosdee.For Auwilriy Building releases monitor RM.062 is th~e normally aligned monitor and willprov:de indicatio of a stack rees until the monitor exceeds 5x108-cpm, when valvesflow. ;., ! RP-A-1 010 F'C-15-003(A130)i PAGE 9 OF 74I REVL 1My-I, MV-2, MV-3 and MV-.4 ,,ill douse off normal samaple flow and redirect flow to theaccident range monitor RM-063. This shif can also be caused if RM-063 exceeds 5x1 OajiCi/cm3.When the radiation level detects decreases to )es the 5x10'3 pCi/crm3 RM-062w~il automaticaly return to normal sample flow (reference 13).The monitor count rates or stack concentrations were! calculated using the guidelinesfoundl in reference (I). For example, a sustained count rote of 3.37x104-cpm on RM-043would correspond to a TEDE dose of 2x500-mrem (i,000-rrem) in one year underaverage mete~ological conditions,.A Notiiation of Unusual Event (NOUE) addresses a potential or actual decrease inthlevel of safetyof the plant asinditd by aradlo/lcalreleases thatexceeds regutatorycommitments for an extended period. Foat Calhoun has 'incorporated features intenh'ded toconlrol the release of radioactive effluents to the e'nvironment. Further, these areadministrative controls established to prevent unintentional releases, or control andmonitor intentional releases. These controls are loae In the Offshe Dose CalculatinManual. The ocourrence of ext~ended, uncontrolled mrad'oective releases to theenvimrnment is Indictive of degradation in these features and/or controls.In accordance with reference (1) readitngs that exceed two limes the TechnicalSpeiicto limit and not terminated within 60 mwiutes; th a NOUE shall be declared.This high alarm set point may be associated with a batch release, or a continuousrelease path. n esler csetpontsetpiti stabll~shed bytie ODCMto wamnof areleasethat is not [n compl~ance with RETIS. Indexing the EAL threshold to the 00CM set points inthis manoer insures that the E.AL threshold will never be less than the set point esteblishedby a specifi discharge permit. Settig the EAL threshold to two times the hIgh alarm setpoint for a NOUE Is cornse~vatie with respect to an) instantaneous release of O.1-mrerm inany one hour TEDFE .For an ALERT emergency' classfifcation EAL, there exists a potential or actual decrease inthe level of safety of the plant as Indicated by ,a releae that exceedsregulatory commitments for an extended period. Therefore, tn accordance with reference(1) a reading on any effluent monitor that exceeds 1Q-norero TEDE or 50-mrem CDEthyroid in one hour for 15 minutes or longer an ALERT s!ait be dclared.The Site Area emergency EA is based on radioactivity releases that result in doses at orbeyond the sit boundary that exceed 10% (100-mrernihr TEDE or 500-mrem in one hourCDE) of the EPA .Protective Action Guides (PAGS) for 15-minue. Releases of thismagritude are associated with the faiture of plant systems needed for th protection of thepublic. .. .IThe GENERAL' emergency EA is based on releases that result in doses at or beyond thesite boundary that meet or exceed the EPA Protective Acio Guides (PAGe). Publiprotective actions will be necessary within Releases of this magnitude areassociated wih the failure of plant systems needed for the prtcin of the public andrikely invotve fuiel damage.on acual me , wheras te monitor ,u~ EA~s me h resuls rowiheeassessments mosy Indicate that the clasiicto Is not wananted, or mayindicate tha a higher classlflaailon Is wa .nte For thi ue~son,euiecImplementing procedwres sh~ould. call for the ftrmely perlonnance of doseactual nmetomlogy and releae informatin. If the results of RP-A-1 010 FC-1 6-003 (RA 13-008); PAGE 10OF74: ~REV7 1doe re available whe,. tte n l, made (e.g.,The gross mornior set points are ccnservahely based on TEDE or CDE ca~cuaonsr-aher than body, and takes into account the thyroid dose and effect on the bodyas a The NOUE process monitor EALs are x2 the efiluentTechnical Specificaion set points found in reference (8) anid ALERT, SITE AREA andGENERAL EALs are based on percantages of the EPA PAGs reference (3)Recalculation of these monitoraction levels should be performed when calibrations and/oratmosn eic dispesin factors differ by more than 20%..An accur'acy of + 20% isconsistent .witI Industry practices for radletln mon, toilrng equipment and follows theguidance found in relerenos (7), which states. .=for projected doses significantly above thedose Ilmis, accuracies of + 20% are recommen~ded." RP-AA-101 0 FCo1 5-003 (RA 13-008)PAGE 11 0F74RE-V. 1AppendixI EAL Setpoint (NOUE) for RM-043 process monitorEP-AA-1010 F-C-15-003 (RA-13-008)Rev. 1Page Constants:Ci:=37.7- l~°BqI0 Bq0.01

• T m~=0.OOl-rerrk0:=0.007 Iodine to Noble Gas RatioF:=28750., afto Xovuei-Q .-- .3. lO0-fi01O i-pCi3BKG z-"36 -mrin-limit =500. mrevnyrDose Conversion factors for 133-Xe and 13 1-IaDC .,=2.0 -OI0
• merr mCi *hTr3DCTF1:=2.2.1O,
• eow=O.03k1:=0.75Thyroid weighting factorMonitor error correction factor.Calculated 2x the Technical Specification Umit (500-mrem/hr):/'r/10.11LhrHz= Round (H,0.1-~T Calculation PagePag~e ! of 2 EAL Setpolnt (NOUE) for RM-043 process monitor EP-AA-1010 FC-15-003 (RA-13-008)Rev. 1Page -! Calculate the setpolnt based on a site boundary dose in any one hourGross release rate:xovr. 0o. ()XP, +w=.fXEF,))Monitor SetpoInt:R= (3.367. lO') Calculate appropriate setpoint as the EAL threshold.m-'[IIeII [else -EAL (3.367.1&o) Calculate the Site Boundary Concentration:x = Q. XoverQCalculation PagePage 2 of 2 EAL Setloint (Aje-t) for IRM-043 process monitorEP-AA-1O1O FC-15-.003 (RA-13-008)Rev. 1Page -:: of Con..ants:C l'.LBq /_Ci:= 3.7-10" oIq iom;= 0.O1 .Sv wnr crx==.00.1 .rcrnk6=0.007 Iodine to Nobie Gas Ratio F=2875O'.c/m -3e+/---2.33.°1O7 o BKG=36 TEDE = 10. mrm neDose Conversion factor for 133-Xe and 131-I.!DCFp, z.2.0.10 .eor. DCF1.:=2.2 .10 e )CFth,==.3° 10 .C i, r C .hrCi, hrw-= 0.03 Thyroid weighting factr~=0.75 Monitor error correction factor.Calculate the setpolnt based on a site boundary dose in any onehourGross release rate base on TEDE:TEDExoverQ. (F, + w. 7F,))Q=2.612 .Calculation PagePage 1 of 3 EAL Setpolit (Alert) for RM-043 process monitor EP-AM-101O FC-1S-003 (RA-13-008),Rev. 1_o~Monitor Setpoint (TEDE):R= (3.364. 1o5) mm-'Gross Release Rate based on (CDE):QCDEXo,,TQ CiQuhv= 0,2S --MOnit" Setpoint (CDE):.)c 1 + BKG(5.444. io:') m-irJ'Calculate lower setpolnt as the EAL thresholdII=IIIfRRu,,'ele.s-(&54.1.&o) mir-'II JjEBAL4-O95spActua! l EALCalculation PagePage 2 of 3 EAL Setpoint (Alert) for RM-043 process monitorEP-AA-I0I0 F-C-15-003 (RA-13-008)Rev. iPage jka'f '"If the EAL is 0 the EAL threshold Is off-scale hlgh and alternate measures are needed.EAL='1 if EA> 107 .rrn-'liii A4s-- cta2(5.4.44 -( .1-&) Calculate the Site Boundary Concentration:x.-Q .Xovr Gross TEDE Gross CDEx=(3.395'10-') X,=(5.495 .i0- j _Calculation PagePage 3 of 3 EAL Setpoint (Site Area) for RM-O43 process monitorEP-MA-1010 FC2-15-003 (RA-13-008)Rev, 1Page Constants:G:-=3.7,10O oq rem:=O.O1I.3v mr~m =0,001 ,Ter/so=0.007 Iodine to Noble Gas Ratio F,=28750. ofin XoverQ.= 1.3.10-.O---~ BKG:=36-min- CD'0 -~~TEDE:=1O............. :DE -O--7,C hr hrDose Conversion factors for 133-Xe and 131-Il~ 'no DCF,:=2.2.102.* r~ DCF~,&= 1.3-10 .Cefori hr Ci
• w.=0.03 Thyroid weighting factor/k -=0,75 Monitor error correction factor.Calculate the setpoint based on a site boundary dose In any one hourGross release rate base on~ TEDE:Q TEDECalculation PagePage 1 of 3 EAL Setpoint (Site Area) for RM-043 process monitor EP-AA-101O FC-15-003 (RA-13-008)Rev. I.Monitor Setpoirit (-TEDE):R= (3.364. 1o) mi-1Gr'os Release Rate based on ((DE):CDEQ,-XoverQ. (k0Monitor Setpoint (CDE):Calculate lower setlpoint as the EAL thresholdII elsII KretrIIIIII o9-II elseActua- EALCalculation PagePage 2 of 3 E.AL Setpoint (Site Area) for RM-043 process monitorEP-AA-1O1O FC-15-003 (RA-13-008)Rev, 1Page .J~L of _-w-:.tIf the EAL is 0 the EAL threshold is off-scale high anid alternate measures are needed.EAL-- I if EAL> II[return EALCalculate the Site Boundary Concentration:xt=Q.Xcn'e~rQ Gross TEDE uXwr Gross CDEX= (3.395~ -Ci..Calculation PagePage 3 of .3 EA.Stolnt (General) for RM~-043 process monitorEP-AA-1010 F-C-15-003 (RA-13-008)Rev. 1Constants:Ci:= 3.7d010m. q u0i~=3.7.10t or := .01 .S.v k0,zO.O07 Iodine to Noble Gas Ratio F=28750.cfm 1.3. 10-s--e;=2,33,107.. -BKG=36.mtn-1 TEDE=1O0O. mr~ CD=50 .__LJ2Dose Converslon factors for 133-Xe and 131-Iemr. -eo LC:=L.& D w =0.0,3 Thyroid weighting factor/.--0.75 Monitor enror correction factor.Calculate the setpoint based on a site boundary dose in anty one hourGross release rate base on TEDE}EQ TEDECalculation PagePage 1 of 3 EAL Setpnt (General) for FM-043 process monitor EP-AA-101O FC-15-003 (RA-13--008)Rev. 1Page MonitJor Stpoint (TEDE):R~=(-9R= (3.3a4. 108) m-in-Gross iRlease Rate based on (CDE):Q CDExovr. (ko. DC'F,=)Quy= 4.?.265 CiMonitor Setpolnt (CDL=):FTh1= io7) m.Th-kCalculate lower setpoint as the F.AL thresholdrI[ IreALI0u 5Ii elsAcua Calculation PagePage 2 of 3 EAL Setpoint (General) for RN-043 process monitor EP-MA-1OiO FC-15-003 (RAk-13-OOS)Rev. 1If the EAL is 0 the EAL threshold is off-scale high and alternate measures are needed.EAL.-- I if EAL> I0 -min-41]IIEAL+-Omin-'EAL=O min-1 Actu --=(5A7.1f711) mniln-Calculate the Site Boundary Concentration:x:=Q.XoverQ Gross TEDE Qa1 .Xove'rQ GrossC(DE=- 003o-- x = (5.49)s.'10-) 3;rf a~Calculation PagePage 3 cof 3 EAL Setpolnt (NOUE) for RM-052 process monitor EP-MA-1010 FC-1S-003 (RA-13-008)Rev. 1Page Z _74Constants:Ci:=3,7.1O0 .13 .13q /%=0,007 lodinieto Noble Gas Ratio F~=24167ocfrn 6=- 2.24.107. -_ BKG:--70.mnr -l Limit=5Q0,O-3Dose Conversion factors for 133-Xe and 131-I)XTF,, 2o_ I, DFp2.2.102 .-ei l__ C /% :=0,75 Monitor error correction factorCalculated 2x the Technical Specificatdon Uimit (500-mremlhr):day jr JH= 0.114 hrH =Ro0,1(H 0.1.FCalcuiation PagePage 1 of 2 EAL Setpoint (NOUE) for RM-052 process monitor EP-AA-1010 FC-15-003 (RA-13-(008)Rev.,1Page o, __Caiculate the setpoint based on a site boundary dose in any one hourGross release rate:HXoe. + k0 (DOTF, + =. TF,))Q--o.026 Monitor Setpaint:R = (3.854 .O 1)+ran-Calculate appropriate set~point as the EALtlhreshold"1 IEAL4-o-95"RII elseIIJIEAL,,-RCalculate the Site Boundary Concentration:X=(3.395'107-) 131Calculation PagePage 2 of 2 EAL Setpdnt (Adert) for RM-052 process monitorEP-AA-1O10 FC-15-003 (RA-13-008)Page & of "I"iConstant~s:Ci=3.7,101°.Bq 3.7-10' .Eq =0.01o Sv ~ka = {.007 Iodlre to Noble Gas Ratio F:=24167.r caa XoverQ=--1.3, e~22.o7 BKG =-70() o =I0. :rr~e CD .... flLeCrh,uCi h,r hi',1Dose Conversion factors for 133-Xe and 131-IDCF, 9 = 2.0o 101o~e( ° DCF:= .2'&* DC~: .34 00 ,.*rem ~Ch DF :2-10 Ci, ]r Ji ohi'w~=O.03 Thyroid weighting factork 0.75 Monitor error correction factor.Calculate the setpoint based on a site boundary dose in any one hourGross release rate base on TEDE:Q TEDE"Q =2.612 Calculation PagePage 1. of 3 EAL Setpoint (Alert) for RM-052 process monitor EP-AA-1010 FC-15-003 (RA-13-008)Rev. 1 .,Page ___/! of1:.Monitor Setpoint (TEDE):R= ( 9 "."ki)+ BKG£R= (3.847-10&) rmin-Gross Release Rate based on (CDE):Q CDECi0.423 --8Monitor Setpoint (CDE):--- .s. k,+ BKGCalculate lower setpolnt as the EAL. thresholdsp=I[ if R>ThyIIsp~a/= ( E2.is mnCac Eatio PagePagep 2Oo*m3 EAL Setpoint (Alert) for RM-052 process monitorEP-AA-1010 F'C-15-003 (RA-13-008)Rev.i : ,If the EAL is 0 the EAL thresholdl is off-scale high and alternmate measures are needed.EA-if EAL,> 10 .mm-jj I rtr .,.T-u= (6.226.1&o) n,, Acua= (&.26. 1o6) Calaulate the Site Boundary Concenlmton:x :=Q .Xove'rQ Gross TEDE Xo1,eTQ Gross CDEx=(3.3§5.' +=54.1-),CalcuIation PagePage 3 of 3 EAL Setpoint (Site Area) for RM-052 process monitorEP-AA-101O FC-15-003 (RA-13-008)Page 2 of __Constants:,q Ci.--3.714O -. rcm:=0.01oSiv koz=O.007 Iodine to Noble Gas Ratio F:=24167,cfr ,,-1z'-2.24,10' .in BKG-=70,.r7n- TEDE.--OO0. :toer CDE,--50O.-rn.Dose Converson factors for 133-Xe and 131-I3 I: 3DCF,~ z_2.0.10'o ~ DCFp ==2.2.10 ye're, or DCFt,:=1,3,10U *____,o_Cicohr Ci ohr Ci o hrw'-0.03 Thyroid weighting factor/ic 2=0.75 Monitor error corraecton factor.Calculate the setpoint based on a site boundary dlose in any one hourGross release rate base on TEDE:XoeQ .-- +~.(DF+~DF)Calaulation PagePage 1 of 3 1A1 ~ah~ninI" ('~itA Arn~i~ fnr ~M4~) nrvv~ce nin,~iMrS-,-, .... *' .. ......v. ..... EP-AA-1010 FC-1S-003 (RA-13-008)Rev. 1Page .2. ofMonitor Setpoint (TEDE):R=(9 ..-k)+BKCR= (3.&47- 1o) mrin-Gross Release Rate based on (CDE):Q CDEc-Monitor Setpoint (CDE):F(6.226.1I06) mi&-'Calculate lower setpolnt as the EAL thresholdsp = (6.226. I06) main-lIiII ILO9~EA/.Calculation PagePage 2 of 3 EAL Setpoint (Site Area) for process monitor EP-AM-i0i0 FC-15-003 (RA-13-008)Rev. 1If the EAL is 0 th EAL threshold is otf-scale high and alternate measures are needed.EAL,-IIif EAL> 101 .mn~n-'elseV[Ireturn3 AEAL= (6,226 106) wiz-' Achtua = (6.226.10&) mmn-calculate the Site Boutndary Concentration:x= Q .XoverQ Gross TEDE! XoveTQ Gross CDE3=33~*i~ IL__Calculation Pagepage 3 of 3 EAL Setpoint (General) for RM-OS'2 process monitorEP-AA-1010 FC-15-003 (RA-13-O08)Rev. IConlstanlts:Qj:=3.7-.10l Bq /Ci 3.7.- I0 ,ti re'n .O.O1 *Sv mrem0.-=O.1
• remk0:=1.007 Iodine to Noble Gas Ratio F--24167.cf'n XoverQ=L3.10--"-RKAGr=70-.mn-' TEDE= IO00 Dose Conversion factors for 133-Xe and 131-I3 3 3rCF =2,-10 m TT F=22.0
• Ta... rew .mw- 0.03 Thyroid weighting factork1=0.75 Monitor error crorrect~on factor.Calculate the setpoint based on a site boundary dose in any one hourGross release rate base on TEDE:TEDEXovei. ko. (DcF, +weWFC) )Q=261.183 ..iCalculation PagePage 1 of 3 EAL Setpolnt (General) for RM-052 process monitor EP-MA-10I0 FC-15-O03 (RA-13-008)Rev. 1Monitor Set~polnt (TEDE):R= (s.847- 1o3) mam-Gross Release Rate based on (CDE):Q CiQmu= 42,.265-SMonitor Setpont (CI)E):R .=-u .t+ KF(6.26.1lo7) Calculate lower setpolnt as the EMt threshold5~Dif R>R~vUIelseII -sp=(6.226.107) maml]IIE~ ..Actsai EAtCalculation Pagepage 2 of 3 EAL Setpoint (General) for RH-052 process monitorFC-15-003 (RA-13-O08)Rev. 1Page ofIf the EAL is 0 the EAL threshold is off-scale high and alternate measures are needed.EALJ---.' if EAL >101 .min'-[]II E _ -0. d -"elseEAL = 0ari'-1 Ada= (5.914-107) -Calculate the Site Boundary Conce~ntration:X:=Q.Xo~e'rQ Gross TEDE x~;= Gross (CDEn=.0 er_ CCalculation PagePage 3 Cl 3 EAL Setpoint (NOUE) for RM-057 process monitor EP-MA-1OI0 FC-15-003 (RA-13-008)Rev. 1Constants:Ci :=3.7 *10O°.Bq 'C 3..i B m=.1.v 'n'r d.O eIodine to Noble Gas Ratio PF=32O. fin X-overQ=_1.3.104. se._=5.94,1~ i0 Ez KG~=820..~m Li- .... .. zr:Dose Conversion factors for 133-Xe and 131-I!DcFI:=2.O.1IO DGF¢z=2.2.lO2 reor DG:Fth:=1.3.10. emrCi. hr Ci ohr, Ci ohrw=O0.03 Thyroid weighting factork1 ~=0.75 Monitor error correctdon factor,Calculated 2)( the Technical Specification Umit (500-mrem/hr):H=0.114 -H:=P~td HO I h )H=0l.1.nv'rhrCalculation PagePage 1 of 2 EAL Setpoint (NOUE) for RM-057 process monitor EP-AA-1010 FC-15-003 (RA-13-008)Calculate the setlpoint baseg on a site boundary dose in any one hourGross release rate:Q :HQ=O.00Monitor Setpont:R =(8.833. lob) Calculate appropriate setpint as the EAL thresholdIIII else-- (a.s3s.ilo') 1Calculate the Site Boundary Concentration:y :==Qo XoerQCalculation PagePage 2 of 2 EAL Setpoint (Alert) for RM-057 process monitorFC-15-0003 (RA-13-008)Rev. 1Page &Li~tof Constnts:Ci-'=3.7.10O -Bq CO{3.7-10O °Bq rm;z= 0,01.S, mrTrn:=IO.OD1.* Trnk0;=0.065 Iodine to Noble Gas Ratio F= 320., elfm XoverQ:= 1.3-10- a*:.41
• BKG :=820- TEDE--O 0* rnrrn O _u oDose Conversion f'actrs for 133-Xe and 131-Iw:=O0.3 Thyroid weighting factor/ =0.75 Monitor error correctin factor.Calculate the setpoint based, on a site boundary dose In any one hourGross release rate base on TEDE:TEDECalculaion PagePage I of 3 EAL Setpoint (Alert) for RM-057 process monitor EP-AA-010 FC-15-0003 (RA-13-008)Rev. 1Monitor Setpoint (TEDE):R= (8.832. ion) mi-(Gross Release Rate based on (CDLE):Q CDEFCalculate lower setpolnt as the EAL thresholdsp~sp i-- R>R,V1 else11II ,-.sp= 1&) mi-1IISreturn EA.LA~tUIA stEALCalculation PagePage 2 of 3 EAt_ Setpoint (Alert) for RH-057 process monitorEP-AA-101O FC-15-0003 (RA-/3-008)Pav1If the EAL Is 0) the EAL threshold is off-scale high and alternate measures are needed.EA.-,'- if EAL>L4S4&,0 .ral-I11 I E.kL'- -1Ieisere[urn --LEA.L-(1.343-10&) m;4sn- Actuta1= (1.343.10 ~) Calculate the Site Boundary Concentration:x=Q.Xover Gross TEDE Gross CDE"y Calaculation PagePage 3 of 3 EAL_ Setpoint (Site Area) for RM-057 process monitorEP-AA-1010 F'C-15-003 (RA-i3-008)Rev. 1Conslants:ko=O.065 Iodine to Noble Gas Ratio XoverQ =1.3.10-' ",-1g==5.94.1Qu -~ ma BKG:=820.ra~in- TEDE=IO00. CDE,=500. axi r hrDose Conversion factors for 133-Xe and 131-IDCF320 0 ____ Tern rn em I /F1 .=2.2 .102 e~ *-.______Ci ° hr Ci, .hr i°hw -=0.03 Thyroid weighting factor:=0.75 Monitor error correction factor.Calculate the setpolnt based on a site boundary dose in any one hourGross release rate base on 1TEDE:Q TEDEXvQ.(DCF +k~ (DLF,+wI F~)Calculatio PagePage 1 of 3 EAL Setpoint (Site Area) for RM-057 process monitor EP-AA-101O F=C 003 (RA-13-O08)Rev. 1Monitor _Setpint (TEDE):R:=(9....kI)+BKGR = (8.832. I0°) rr, n-Gross Release Rate based on (CIX):Q ODEQu,,= .455 c.-_Monitor Setpoint (CDE-):Rum= Q* +BKGFCalculate lower setpoint as the EAL. thresholdsp+/-(i.a4. 1o9) ,min-EAL-isl48O rrmn-II l EAl*- 95"e'II elseI return EALActual. EALCalculation Page*Page 2 of 3 FA! fnr mnnitnr-----I--,F ....wir f'1- ...... f' ........ nw" c .. ......... FC-15-L-O03 R.Page_44 of_..$If the EAL Is C) the EAL threshold is off-scale high and alternate measures are needed.iAL='EAL> 1.48-10O -mird~t-liiiEAL4---0rapEA.,=O 0 mn .Actui= (1.276.1lOD) Calculate the Site Boundary Concentration:X~=Q .Xove-Q Gross TEDE Gross COECalculation PagePage 3 of 3 EAL Setpoint (General) for RM-057 process monitorEP-AA-1010 FC-15-003 (RA-13-008)Rev. 1Ci ::_3.7-10 1 o~q jC 437 ,0 .q ~ r~0Oi.S =.OIodine to Noble Gas Ratio F,--32O. -jm. Xoer~.31*-- .TED., 1O.~ --~ D350.L2Dose Conversion facto~rs for 133-Xe and 131-IDC( 20.0 Gi °hr Ci htr Ci ,:. hr==0.03 Thyroid weighting factor.--0.75 Monitor error correction factor.Calculate the setpoint based on a site boundary dose in any one hourGrass release rate base on TEDE:Q TEDEXoeQ W,9+ ko. QX, 'DCF, ) )Q=29.939Calcuiation PagePage 1 of 3 EAL Setpolnt (General) for RM-057 process monitor EPA-11 FC-15-003 (RA-13-008)Rev.,1Page 4 of ~Monitor Setpoint (TEDE):R-"(&8.32.10"') rain-Gross Release Rate based on (CDE):CDEc-_SMonitor Setpolnt (CDE):t=- 1 +BKGF~=(.4.z o i-Calculate Jower setpoint as the EAt thresholdsp =(1.3434o1'o) mm1--A u 873rp>1.48-10= mrI[ JEAL i-- .95. spII elseAci-L=EALCalcuflation PagePage 2 of 3 EAL Setpoint (General) for RM-057 process monitor ~1I C1-0 R-3O8Rev:LPage._.<.o -If the EAL is 0 the EAL threshold is off-scale high and alternate measures are needed.EA-Tff AL>L148.10& .mi-1E-4L =0 m in- Actua- (1.276. IO0') Calculate the Site Boundary Concentration:x'=Q.XotverQ Gross TE'D Gross CDEX= (3.&92 o !0) 11 fh =(.1. 0 U:; 3Caiailation PagePage 3 of 3 EAL Setpolnt (NOUE) for RM-062 process monitor EP-AA-010 FC-15-O03 (RA-13-008)Rev.1I...ZPage _ of Constants:tO'1e .L~ 7C==3.7.104 dBq mrn ,,=O.OOl,.r rnk~:OO7Iodine to Noble Gas Ratio P=24167. XoierQ r= e1810' BKG r=-50*.a,&. Limri.--O- ,'u rn.Dose Conversion factors for 133-)(e and 131-IDC ~~.O 1... DGF,:= .2,1O °- 1)CFo'-"1.3.1 I -~~w= D.03 Thyroid weighting factork1 =0.75 Monitor error correction factor.CailcaGted 2x the Technical Specification LUmr (500-mrern/hr):l 24 6525 -tday yr )H= 0.114 rve~nmH=P~und )Fl=0.1 Calculation PagePage 1 of 2 EAL Setpoint (NOUE) for RM-062 process monitor EP-AA-1O10 FC-15-003 (RA-13-008)Calculate the setpint based on a site boundary dose in any one hourGross release rate:H~xove. (DCTF, ++/-k°. (WF, + Q=O.026 Monitor Setpolnt:R =(3.251.* rw. -'Calculate appropriate setpoint as the EAL thresoldII elseCalculate the Site Boun~dary Concentration:x z=Q "XomerQx =(3.395. io-) !+/-%Calculation PagePage 2 of 2 EALd Setpoint (Alert) for RM-062 process monitorEP-AM-1O1O FC-15-003 (RA-13-O08)Rev. 1Pae41of LConstants:C: = 3.7.*1O0.w q -- .7.lO *L rg Sv rrmw .01.rcrnk+/-OO7 Iodine to Noble Gas Ratio F--24167°cfim Xover:= 1.3-10%-.---(~L9.17.KG~=5O~niW' TED=1O--m'hr hrDose Conversio)n fctors for 133-Xe and 131-i"5 ohr Cy° r n rw=0.03 Thyroid weighting fact~orks 1=0.75 Monitor error correction factor.Calculate the setpolnt based on a site boundary dose in any one hourGross release rate base on TED:Xo'vr- ko. (ECF, C~alculatio PagePage 1 of 3 EAL Setpolnt (Alert) for RM-062 Ipracss monitor EPA-M010 FC-15-003 (RA-13-008)Rev. 1,Monitor Setpolnt ("EDE):Rt=(9.e "kl) +BKGR= (3.24g.1o6) rain-'G;ross Re~ease Rate based on (CDE):CDEMonitor Setpoint (CDE):-(.25. los) min1Calculate lower setpolnt as the EAL threshoadsp=II II elses-- I5.253.lo8) II *95a,-II elseAcua =EALCalculation PagePage 2 of 3 EAL Setpolnt (Alert) for RM-062 proces monitorEP-AM-1010 FC-15-003 (RA-13-008)Rev. 1 .-Page __u of.25If the EAL is 0 the EAL threshold Is off-scale high and altrnate measures are needed.EA~"if RAL> 10T* n.m~n-else_-=(5.253.1O5) Acta=(5.25.Io&) Calculate the Site Boundary Concentration:x;=Q.XoverQ Gross TEDE Gross CD)E3r, rCalculation PagePage :3 of 3 EA. Setpoint (Site Area) for RM-062 process monitorEP-A-1010 FC-1S-O0 (RA-13008)e.Page of iConstants:C =3.7.. 0 .Lq p C{=3.7- I04 oFq .Sv me --t0.001,.rerk0:=0.007 Iodne to Noble Gas Ratio F.--24167, XoverQ.-- 13. mr621891
• BK:= 5O,. mvm -t TED"= 1O.--L CDE .--500.-Dose Conversion factors for 133-Xe and 131-I3', 3." ..0 i 2.0.1
• i0 1Xr, 1:= 2.21O. D02 -=1"3.10 Ci .Its C{. hrCi oArw = 0.03 Thyroid weighting factork1=0.75 Monitor error correcton factor.CalcuLate the setpolnt based on a site boundary dose in any one hourGross release rate base on TEDE:TEDEXoter. (DCF, + )Calculation PagePage 1 of 3 EAL Set~point Area) for RM-062 process monitor EP-AA-1Ol0 FC-15-003 (RA-13-0O8)Rev, 1f/Page Monitor Setpoint (TEDE):-[.(Q k)+ aR= (3.246.1O7) rmin-Gross Release Rate bae on (C:DE):4.227 --SMonitor ,etpoint (C:DE):~ =(5.253.1o8)mnCalculate lower setpoint as the EAL threshoddIIelIl=EAL.pCalculation PagePage 2 of 3 EAL ,Setpoint (Sfte Area) for RN-062 process monitorEP-AA-1010 FC-15-003 (RA-13-008)Rev. 1Ifthe EAL is 0 the EAL threshold is off-scale high and alternate measures are neededh,,3 3LEA=(.23.08Atui=(.531O),~~Calculation PagePage 3 of 3 EAL Setio~nt (General) for RM-062 process monitorEP-MA-1010 F-C-15-003 (RA-13.-008)Rev, 1Constants:k0,=O.007 Iodine to Noble Gas Ratio F---24167.<f. XoverQ= 1.3.1(-f' e,=1.89.10. *z BKG:50°o i CDE:=z5000. mr'mDose Conversion factors for 133-Xe and 131-ICi o hr ~Ci oAthirhw =0.03 Thyroid weighting factork 0.75 Monitor error aorrection factor.Calculate the setpolnt based on a site boundary dose In anty one hourGross release rate base on TEDE:TEDEQ=26 6Calculation PagePage 1 of 3 EAL Setpoint (Genieral) for RM-062 pmoces monitor EP-AA-101O FC-15-003 (RA-13-008)M~onito~r (Th-):R= +BKGR= min'-Gross Release Rate bae on (CDE):Q CDEMonitor Se-tpolnt (O)E):Calaulate lower as the EAL thresholdII elseEAL-z=llif>sp .o7-*II elseAc-'L =EAL,Calculaton PagePage 2 of 3 EAL Setpoint (General) for RM-062 proces monitorEP-AA-tOlO FC-i5-003 (RA-13-008)Rev.Pane of 7SLIf the EAt. Is 0 the EAL threshold is off--s~le high and alternate measures are nede.E~Z=II AfEA.L> 10 mi' n -r 'III ret -O- -A.BA,=O w'= n.Calculate the Site Boundary Concentr"ton:X r=-Q. X(Au'Q Gross TEDEx=O.O03 3mScriGross CDECalculation PagePage 3 of 3 EAL Setpoint (NOUE) for RM-063 process monitorEP-M-1O10 FC-15-003 (RA-13-008)Rev.1Page .~ of i~-Constants:CL "=3.7 -1010 ,Drem -'-=O. 01 -Svmrem.' 0.001 .rem/c%,=0.007 Iodine to Noble Gas lRaUoF'= 24167. L3.310~ *-.--mDose Conversion factors for 133-Xe and 131-IDCF~'= 20. i i. r0 h*DC I=,. 2rem, o~'fl6 Tm.Czo hr iotk1:=0.75Thyroid weighting factorMonitor error oxrectlon factor.Calculated 2)( the Technical Specdfication Umit (500-mrernlhr):___Limrt H="24.2HZ" °385.25.H=0.1U4 m"*'"zH=O.1Calculaton PagePage 1. of 2 EAL Setpoirt (NOULE) for RM~-063 process monitorEP-AA-1010 FC:-15-003 (RA-I.3-008)Rev. 1 "Calculate monitor concentration and off site con centration:Gross re~ease rate;Q Hxo,,e-Q. ko. w.WFc-,.))Monitor- Concentration:Fo = 0.002 i5LiaRM-062 would not have shifted to thismointor becuse the couJnt rate Is < 5E+O06-cpmCalculate the S~te Boundary Concentration:x Q: x= (3.395.io-')3Calculation PagePage 2 of 2 EAL. Setpaint (Alert) for RM-063 process monitorCostnts:k/%=O.007 Iodine to Noble Gas RatioTEDF --10 DE -5 o ratEP-AM-1O10 FC-1S-003 (RA-13-008)Rev. 1w =0.01. *v 001.~F = 24167.c~fa XoVeTQ:= 1.3.10.5Dose Conversin factors for 133-Xe and 131-IS 3rem~ ... .... rerIe emre.w =0.03 Thyroid weighting factork1'=0.75 Monitor error correction f-ctor.Calculate the monitor concentration and oraste concentraton:Gross release rate base on TEDE:Q TEDEXo, veaQ .k. (WPY,++/-w WFte,) )Q=2.612 Calculation PagePage 1 of 2 ied Uo i[ OdJmuouJIUOW, Siq pe~jqs pjfnoM e~go-Il si U aQUo~ a~ sne :3JOj 1< o'=7Y~UI =...f..I,* ' rruoj~u~

EAL Setpolnt (SAE) for RAM-063 process monitorConstants:Ci:= 3.7- Ol o~ 104 -Bqk0-=O.aO7 Iodine to Noble Gas RatioTEDE~= I00o -GDI=SOO-- ,hr hrEP-AA-1O1O FC-15-003 (RA-13-OO8)Rev. 1-Sv nrm := 0.001. * ;maF= 24167. XoverQ:---1.3.1O *.0~aDose Conversion factors for 133-Xe and 131-IDCF. :=2.0. I0' ."rio____J DYF7p= 2.2102 .L2:-_!L DCF =I.3.1o6.-----tn=0.03 Thyroid weighting factork% ~=0.75 Monitor error correction factOr.Calculate the monitor concentration and offsit concentration:Gross release rate base on TEDE:Q TEDExovr. + k. Calculation PagePage 1 2 EAL Setpoint (SAE) for RfM-063 process monitorFC-4S-003 (RA-13-008)Page. oL51Monit.r Concet:aion CfEDL=):FGross R elea.e Rate based on (CDt):C'DEMonitor Concentration (CDE):,FO.37.1 SIIELCEAL= 0.371 RN,02 wCaleculate the Site Boundary Concentration:x=Q.Xovr TEDEx (a.96 a o')muse the concentration is >5E-3Sfhave shifted to this monitoro cGross CDECalailation PagePage 2 of 2 EA~L Setpolnt (General) for RM-063 process monitorConstat:=..10 ko~=O.O07 Iodine to Noble Gas RatioTEDEi= 1O00. m CDE'.=5002o n~reEP-MA-1010 FC-15-003 (RA-13-O08)Rev. Page k,/'of = .OISv e:= 0.001

• F= 24167, wm XoverQ := 1.3.O rnDose Conversion factors for 133-Xe and 131-I1X7F,9=2.0. 101 *_DFF22 102 ' TF 3 ;~w+/-=0.03 Thyroid weighting factork1 =0.75 Monator error commdon factor.Calculate the monitor concentration and offslt concentration:Gross release rat base an TEDE:Q TEDEXoq,eQ. (WXF, + ko.(D rw1YF)Calculation PagePage 1. of 2 EAL Setpoirnt (General) for RM-063 process mnonitor EP-AA-1O1O FC-15-003 (RA-i3-008)Monitor Concentration (-EDLE):FC--22-898 ,u, L3Gross Release Rate based on (CDE):Q CDEQ -Xo,,erQ. (ko Monitor Cnncantmtfion (C]DE):FCO=v=3.706 iCjEAL,= II if IL elseEAL=3.706-"C KOTh: Because the concetato is >5E-03 /3CRM-062 would have shifted to this monitorCalculate the Site Boundary Concentmatlon:x-= Q.XoverQ GrOss TEDE Gross CDECalcuaton PagePage 2 of 2 EAL Setpoint (NOUE) for RM- ,t process monitor EP-AA-1O1O Frc-15-003 (RA-13-008)Rev. 1 .Page Constants:Gi = 3.7.1 -0°.
• Bq r~m ---O.01 o~v /%=0.065 Iodine to Noble Gas Ratio F=5823.c!pm 1.3- 10 .*=.410.' -BKG= 19° 1 Ii=50u0. ,-r-UCL 3cmfDose Conversion factors for 133-Xe and 131-IDCF .L2J1on__ DCF:f= 2.2.102*____ .fF,=.3 10 fl1?919 hrCio h* 1XiF o h.uw =0.03 Thyroid weighting factor, =0.75 Monltor error cor-ection factor.*=1.0 steam density correctonCalculated 2x the Technical Spedfi"catlon umit (500-rnrem/hr):L d ay yr ).HzO .114 mahrc~mcrPage 1 of 2 EAL Setpoint (NOUE) for RM-064 process monitorCalculate the setporn based on a site boundary dose in any one hourGross release rate:Q HQ= o.o03 Monitor Setplnt:R= 19.025 Calculate approprate setpoint as the EAt. thresholdEAL:"l f R>10 *msi-iIIEP-AA-1010 F-C-15-003 (RA-13-008)Rev.1 ,1Page k of 1.4= 19.025 rnr'1NOTE: The reading is slightly, over backgroundand would not provide an adequate value for anEAL thresholdCalculate the Site Boundary Concentration:Calouatiaon PagePage 2 of 2 EAL Setpoint (Alert) for RM-064 process monitorEP-AA-1O10 FC-I5-003 (RA-13-008)Rev. 1Page _.Li_Constants:Xouer,= 13-10 ko =0.065 Iodine to Noble Gas Ratio F~=5823.~r Xove,-=L3.1Ot~.4.0 d.z KG:=lgo.min TEDE=IO. "L CDE;=&O. e'hrh'r-1q%Dose Conversion factors for 133-Xe and 131-ILUF, := 2,04 10
• DCF1._ 2.2. i02 .r~mo. JgF : 1.3 I0 eom,w =0.03 Thyroid we.ighting factor, =0.75 Monitor error correction fadnr.1: Steam density correctionCalculate the setpolnt based on a site boundary dose in any one hourGross release rate base on TEDE:Q TEDECalculation PagePage 1 of 3 EAL Setpoint (Alert) for RM4-O64 process monitorMonitor Setpolnt (TEDE):-( .k1 .B-*R= 21.484 mmn-Gross Release Rate based on (C.DE):Q CDEMonitor Setpolnt (Q)E'):R,= 19.37S main'Calcul~ate lower setpoirnt as the EML threshold8p= iif R>Rvqsp =19.378 mmn-EP-AA-iO1O FC-lS-O03 (RA-13-008)Rev 1 ;EAL=ffsp1O7 ri-elsere~turn ALActual ---EALPagePage 2 of 3 EAL Setpoint (Alert) for R1406 process monitorEP-M-1O1O FC-15-003 (RA-13-008)Rev. 1.~ge4~ofi~If the EAt- is 0 the EAt. threshold is off-scale high and alternate measures are needed.EA='If EAL >107 -iiEAL= 19.378 nActul= 19.378 -1NOTE: The reading is ~0.4-c:pm over backgroundand would not provide an adequate value for anEAL thresholdCalcutate the Site BoJndaiy Corncenfration:x'-Q .XovuerQGross TEDEXth Qt, ,. Xove1Q.7Gross C..Ecalculatlon PagePage 3 of 3 FEAL Setpoint (Site Area) for RM-064 process monitorE.P-AA-1010 FC-15-003 (RA-13-008)Rev. 1Constants:/%.--0.065 Iodine to Noble Gas Ratio F=5823.cfmn XoverQ= 1.3'10~ -.----Dose Conversion fadxors for 133-Xe and 131-43 3 3wv =0.3 Thyroid weighting factork2%=O.75 Monitor error correction factor.k,= 1 Steam density correctionCalculate the based on site boundary dose in any one hourGross release rate base on TEDE:TEDEQ =2.994 --Calculation PagePage 1 of 3 EAL Setpolnt (Site Area) for RMI-064 process monitor EP-/M-1O1O FC-15-003 (RA-13-008)Re'.l.Monito Setpoint CrEDE):R =43.839 mmi-Gross Rl~ease Rate based on (CDE):Q CDE-_Monitr Setpolnt (CDE):R,,+-" 22.776 mmi1-Calculate lower setpoint as the EAL thresholdII , ,II Ie l .-.sp =22..776 mm'+-E...111fCalculation PagePage 2 of 3 EAL Setpoint (Site Area) for RI'-064 process monitor EP-AA-1010 F-C-15-003 (RA-13-008)Rev. 1*If the EAL Is 0 the EAL threshold is off-scale high and aiternate measures are needed.1]Ii HEAL4-omM'-U enLEAL =22.776 mittir Aet~ua= 22.776 min-iCalculate the Site Boundary ConcentraUon:x:= Q XoverQ Gross TEDE Qu-XemerQ Grass CDEer ?e'Z raCalculaton PagePage 3 of 3 EAL Setpoint (General) for RM-064 process monitorEP-AA-1010 FC-15-003 (RA-13-O08)Rev, :Page _¶Constants:C3/4 ==3.7.*10° o~3q 1iCi ' 3.7.*104 0.01 -Sv. .:0.001
• re'j,,rko-=O.0O5 Iodine to Noble Gas Raijo F7=5823oacf XovoerQ= -.1O *s..-' mv-- BG= TEDE=1000. mC, DE1,hrDose Conversion factors for 133-Xe and 131-I3 3 ,3DOF,? .=2.0.10* o )JF = 2.2 .102 .remo.m DCF 1=3.10a ...Ci rCiohr C{ w = .03 Thyroid weIghting factork 0.75 Monitor error corecio factor.==1 Steam denit correctonCalculate the sepoint based on a site boundary dose in any one hourGross release rate base on TEDE:Q= ThDE(DCF,+ Q=29.9 3 !.CaluaIon-agPage 1 of 3 EAt. Sel~oint (General) for RlM-064 process monitor EP-AA-1010 FC-15-003 (RA-13-008)Rev. 1Monitor Sfetpolnt (TEDE):R=267.391 main-1Gross Release Rate based on (C:DE):Xo,--exQ. (ko .iXFo)Q0.=4.652 c.9Monitor Setpont (CDE):R,.:=56.763 mm'-Calculate lower setpofnt as the EALt. bresholdsp,: II if R.,II else8p 56.7O3 mim-Aculj HreturLCalculatio PagePage 2 of 3 EAL Setpoint (General) for RM-O64 process monitor EP-AA-i010 FC-15-003 (RA-13-008)Rev. 1If the EAL is 0 the EAL thresho~d is off-scale high arnd alternate measures are needed.EL if EAL,> 107 .min-II ~EAL +- 0 orni-Ii elseIII return EAEAL=--56.763 Aeo= 56.763 -Calculate the Sit Boundary Concenraltion:X = Q.X°Oe' Gross TEDE =QO..XoverQ Gross CDECakulaUon, PagePage 31 of3 LIC-1 5-0102Enclosure, Attachment 4Emergency Action Level Thresholds for Liquid, Release AA1 (RAl)RP-AA-1 010 FC-1 4-004 Rev. 0(Calculation with Attachment 1 -Pages 1-11)i(Attachment 2: EAL Threshold Calculations based on TEDE -Pages 1-7)(Attachment 3: EAL Threshold Calculations based on Thyroid CDE -Pages 1-7)

!F -AA-1 010 FC-1t4-004, Revision 0I of 11Emergency Action Level Thresholds for Liquid Release AAI (RAI)Prepared b: (date) Reviewed By date) Apred By {date)1 Problem or Issue StatementThis calculation documents the methodology used to determine the Emergency Action Level(EAL) thresholds for the initiating condition (IC) AA 1 as defined in NE] 99-01 Rev. 6 forliquid effluent discharges; a release of liquid radioactivity resulting in offsite dose greaterthan JO mrem TEDE or SO mi-em thyroid CDE.2 Background or IntroductionNE] 99-01 Rev. 6 initiating condition AA I addresses, a release of liquid radioactivity thatresults in a projected dose greater than and equal to :1% of the Environmental ProtectionAgency (EPA) Protective Action Guides (PAG). Releases of this magnitude represent anactual or potential substantiai degradation of the level of safety of the plant and exceedsregulatory limits.NEI 99-01 Rev. 6 provides the following generic guidance for selection of thresholds:* Select the appropriate installed liquid monitorr*The effluent monitor reads should correspond to a dose of 1 0-torero TEDE or 50-* mrem CDE thyroid at the site specific receptor point for one-hour of exposure.* The monitor readings will be calculated using a set of assumed data. Acceptablesources of this data include, but not limited to the RET/ODCM and values used foremergency dose assessment methodology.*The calculation of readings will also require use of an assumed releaseisotopic mix: the selected mix should be the same that is employed to calculatemonitor readings for IC AS I and AG].*NE! guidance recognized that the conditions described in IC AA I may result in aradiological effluent value beyond the operating display range of the installedeffluent monitor. In those cases, EALs should be determined with a sufficient marginsufficient to ensure that an accurate monitor reading is available. RP-AA-1O1t0 FC-'14-004Revision 0Page 2 of 113 DiscussionsThe ODCM identifies three pathways for human exposure to liquid releases from FortCalhoun Station (FCS) to the Missouri Rivern 1) fish, 2) drinking water, and 3) Shorelinedeposition. Fish are considered to be taken from the vicinity of the plant discharge. Thedrinking water for Omaha is located 19 miles downstream from FCS. For this calculationthe drinking water pathway is considered because accident releases are acute releases andthe emergency action thresholds are based on an acute exposure of one hour as describedin the NEI 99-01 Rev.6 (Ref. 8.11),Figyre / Liquid Radioactie /Jischarge Poihwoy.ss/aAu0s8] WAlERThe concentration of radioactive material in the liquid effluents are normally diluted by thecirculating water system.4 Methodology .4.1 This analysis develops the model used to estimate of the radion~uclide concentration andradiation monitor count rate from an ac~cidental release into the Missouri river exceeding I 0-mrem TEDE or 50-mirem CDE to the thyroid. This calculation provides a link between theeffluent releases and the direct pathway to man from an acute intake of radioactive materialfrom potable water, -A.A;110t FC-14-004.: : Revision 0iPage 3 of 11This calculation is based on the use of simple models and is a conservative approach. Theeffluent is considered small with respect to the receiving water body (Missuri River) arndrapid mixing will reduce the discharge concentration.The initial dilution process is based on turbulent mixing produced as the effluent isintroduced in the stream. This process is assumed to be relatively rapid. Large dilution onthe order of 10 to 100 can be achieved (Ref. 8.2). This calculation uses a mixing coefficientof 30.8 for the Metropolitan Utility District (MUD) intake (Ref. 8.1) and is the specificreceptor identified in the ODCM, The radionucl ides will undergo radioactive decay as theliquid is transported downstream. ,The following equation from Reference 8.1 is used to calculate the TEDE and CDE from anoral intake of rid onuclides (assuming annual water intake of standard man) for a one-hourexposure:H. U Q,.DF&'o (1)Where He, is the effective dose equivalent for radionuclide i in units ofmtrero. U is the adultannual intake of water (730,000 mL), M is the mixing ratio of 30.8 at the point of intake forMUD (unit-less), F is the river flow at the time of discharge in mL/s, Q, is radionucliderelease rate in Ci/s, DF, is the ingestion dose factor for the dose equivalent (TEDE) in unitsof mrem/Ci, L, is the radioactive decay constant in inverse seconds (hri'), and tp is the transittime in hours from the discharge at MUD (Ref. 8.1) intake (site specific receptor point).The transit time tp is calculated by dividing the distance from the discharge to the point ofintake (i.e.4 19 miles) (Ref. 8.1) by the river velocity v (mph) (Ref. 8.7):19 miiest,- v(mph) (2)To calculate the release rate at the site discharge for a 10-torero TEDE or" 50-torero CDEthyroid exposure equation I is solved for Qi the isotopic release rate for an one hourexposure. The isotopic release rate is based on the fraction of the assumed radionuclide mixin the source term (0):Q' uAMvDy,-' (3)The isotopic fraction is calculated by dividing the assumed Ci/MWth for each isotope bythe sum of the inventory: ,AXA'.,I (4)iThe assumed inventory is the accident source term employed by the Universal RASCALInterface (URI) program; the site dose assessment program. RP-AA-1010 FC-t4-004Revision 0Page 4 of 11Tale I UR?! Accident Source Termn (NUREG-1228)Dose Etiulv Dose Equlv1-1311-1321-1331-1341-135Cs-23C-137Sb- 127Sb-1!9Te-I2~gmTe -132Ba-140Sr-B9Sr-90Sr-91Mo-93Ru- 10Ru-106La- 140Y-91C~e-144N.P-29SumFGRft11FEDEsv/Bq1.44E-0a1.S2E-102.aOE-096.66E-116.08E -101.98£-O83.04E-091.3E-OB1.81E-094. 45E-L?.1.57E-10246E-095.95E-OB25I6E-O93. 51E-074.49E-101.07£-0942A2-091.2.9E-071.31E-091.32.E-085.84E-086,78E-1O6.90E-07F6 R 11Thyroid4.76E-073K87E-099.10E-086.21E-10l1.79E-08".76E-032.7460/.26E-(383. 16E-114.61E-102.a9E-094,2.9E-082.54E-09S.2SE-114.1GE-102,64E-O94.08E-111.74E-095.97E-1O1.69E-081L22E-lOI.IOE-101.88E-097,62E-126.96E-07CEDECs-1_37_Factor_1.OTE+001.35E-022.07E-014.93E-034. 50E-021.47E+002.25E-011,00E+O01.346-a13. 30E-041.166-024.41E-+001.90E-018.3OE-012.60E+0I3.33E-027.93E-.021.79E-O19.56E4009.70E-029.78E-014.33E+005.11E+O1CDE ThyroidFactor...1.'OOE+OO8.13E-031.91E-01tL30E-033.76E--023.70E-025.76E-032,65E-029.68E-046.07E-035.34E-021..10E-04a74E.-04S.SSE-038,57E-053.666-03* l25E-033. 55E-022,56E-042.31E-043.95E-031.606-051.46E+0OSCltMWt2.67E+04.3.BSE*04S. 9,8E-404.70E-031.49E+033.25E-+032.39E+038.68E+O,31,68E4.035.41E+033.816+044.76E+042,411:+042,39E+03,3.01E+045.306*044,34E+041.55E*044.91E+043.17E+043...4E+045,69E4-051.206+06ratio2,23E-023.246-024S52E-024.99E-024. 32E-023.92E-031.24E-032.7J.E-03"1.99E-037,24E.-031.406-034.51.E-033. 1,8E-023.97E-022,026-021,99E-0.32516-024,42E-023.62E-021.29E-024.10E-022.G5E-022956-024.75E-011.00E-400The gross release rate is calculated by summing the isotopic release rates Q,:Qi :ZQ(5)The gross undiluted concentration is calculated by dividing the total flow rate into the grossrelease rate:.QI(6)The design pump flows for the overboard wastes (wp) is S0-gprnand 1 35-gpm for theRiowdown pumps (270-gpm total) (Ref. 8.1). These .pump flow rates have no effect, i Revision 0i "Page 8 of 11because .the circulat~ing water pumps (we) have significantly imore di~lution flow (120,000-gpm).The threshold count rate is calculated by multiplying the radiationl monitor efficiency(cpmn/itCi/mL) by the undiluted concentration Cr and adding the background.R = e*C, + Rb (7)Instrument uncertainties and allocation factors are ignored because this eventis an acuteaccidental release and the EAL thresholds are not designed to provide! automatic action toprevent a release greater than a regulatory limit.5 Assumptions5.1 Any noble gases resulting from a radiological accident are assumed released to theatmosphere.Basis: Noble gases are non-reactive gases and the effluent stream is open to theatmosphere at ambient temperatures; so an insignificant fraction of noble gases areassumed entrained in the effluent. In addition, as the effluent is' transporteddownstream entrained noble gases in the stream would be released via theturbulently river flow.5.2 A river current of 7-mph is assumed in this analysis.Basis: 'Reference 8.7 provides a range of river velocities between 4 to 7 miles per hour.-The river speed is used :to calculate decay time as the effluent isi transporteddownstream. A higher transport velocity will result in less decay and aconservative estimate of decay.5.3 The annual oral intake of water is based on the use factor in the 00CM (Ref. 8.1) of 730 L.Basis: The annual intake usage factor for an adult in referencei 8.1 is 730 L which istaken from NRC Regulatory Guide 1.109 (Ref. 8.4). This intake factor isconsistent with reference man's intake of~l I L given in ICRP 23 (Ref. 8.8).5.4 Liquid releases through the plants discharge pathways have alarm set paint ealculated basedon known isotopic mixtures as measured by isotopic analysis of the liquid. This calculationassumes that the effluent isotopic mixture is unknown and uses the default mix ofradionuclides used by the URI dose assessment program.Basis: By definition the EAL threshold values for this IC are for unexpected andunauthorized releases, so the isotopic mix is unknown. In accordance With NE!99-0 1 Rev. 6 developer notes state that the source term should be based the0DCM or emergency dose methodology. The ODCM is not an emergency releaseprogram and therefore the accident source used by the dose assessment program RP-AA-1 010 FC-1 4.004.' ! .Revision 0Page 6 of 11provides a reasonable inventory for an acute unknown The inventory used* in the URI dose assessment code in based on NUREG-1228 (Ref. 8.1i2).6Results or ConclusionsThe results of the calculation show the maximum range of the liquid efflueint radiationmonitors are exceeded (>1 107epta). In accordance with NEI 99-01] Rev. 6 alternate methodsof assessment or reduction in count rates that provide a reasonable threshold should beemployed. With three circula~ting water pumps running the: TEDE threshold isapproximately 128% of full range operation (Table 2) and large differences for less dilutionflow would occur (Attachment 2).Table 2. Caliculated EAL£ l77rar/dds ([E.DI').CaletulatedEffluent Monitor Deseription____ ___ ___ ___ ___ ___ _ __ ___ ___ ___ ___ ___ __ AL. Threshold (cpm)RM-054A (I CW puamp) Steam Generator Slowdown l.LE-0SRM-054 B (I CW pump) Steam Generator Slowdown 1-. 2E+08RM-054 A (2 CW pump) Steam Generator Slowdown 5.4E+07RM-054 B (2 CW pump) Steam Generator Blowdown 5 .4E -07RM-054 A (3 CW pump) Steam Generator Biowdown 3.6 E+07RM-054 B (3 CW pump) Steam Generator Slowdownt 3.6 E-07RM-05S (I CW pump) Liquid Discharge Header RM-055 (1 CW pump) L L~uid Discharge Header 6.1 E-07RM-055 ( I CW pump) _Lquid Discharge Header 4.0E+07The CDE thyroid calculations in Attachment 3 are greater than 107-cpm, which alsosupporting alternate methods of indication.In accordance with guidance in NEI 99-01 Rov. 6 (page 35) alternate methods will applysince the expected radiation monitor readings for the EAL thresholds are greater than 1 10%of full scale. These alternate methods may include grab samples from the effluent or fieldmonitoring samples at the MUD intake.A grab sample of from an unauthorized rele~ase of 0.4-l.Ci/cc (e.g.. run off from anuncontrolled release or tank breach) in the effluent stream is an indicator of meeting theALERT threshold for IC AA 1 (Attachment 2). 7 of 117 Calculations7.1 Inputs7.1.1 Process monitor sensitivity for R.M-(J54A '9.84x 101 cpmdiCi/mL, and background 96cpm (Ref. 8.5)'.7.1!.2 Process monitor sensitivity for R.M-054B 9.84x I07 cpm~xCi/mL, and background 220cpm (Ref. 8.5).7.1.3 Process monitor sensitivity for RM-055 1.1 lxi cprnlkCi/mL, and background 160 epmo(Ref. 8.5).7.1.4 The mixing ratio (reciprocal of the dilution factor) at the withdrawal point for theMetropolitan Utilities District (MUD), intake is 30.8 (Ref. 8.1),7.1.5 River current is a range of 4 to 7 miles per hour (Ref. 8.7). Seven (7) mph is used in thisanalysis.7.1!.6 The dose conversion factors used in this analysis are the effective dose equivalent (l-1)from oral ingestion published in USEPA Federal Guidance Report 11! (Ref., 8,3).7.1 .7 The source term used in the analysis is based on the generic source term used by theURI/RASCA L dose assessment computer code. As noted in the assumptions the noblegases are assumed released to the atmosphere prior to any liquid intake.7.1.8 The distance from Fort Calhoun to the MUD intake is 19-miles (Ref. 8.1).7.1.9 The annual intake for an adult is 730 L(Ref. 8.1).7.I. 10 FCS has three Circulating water pump and each as a design capacity of I120,000-gpm(Ref. 8.1.)7.1],11 Average river flow rate is based on the 16-years of data measured by the USGS atDecatur, Nebraska, just upstream of Fort Calhoun Station (Attachment 1).7.2 See Mathcad calculation in Attachment 2 and Attachment 3.8 References8. [ CH-ODCM-O0001. Offsite Dose Calculation ManuaL. Rev. 22. 1/8/2013.8.2 NUREG/CR.-3332 ORNL-5968. Radiological Assessment A Textbook on EnvironmentalDose Analysis. September 1983,:NOTE: The background for the Blowdown manitors RM-054 A/S is averaged and the average background is usedin the calculation (158-cprm). This averaging is consistent with the approach used In the URI dose assessmentprogrm. Revision 08 of 118.3 USEPA Federal Guidance Report I1I. Limiting Values of Radionuclide Intake andAirConcentration and Dose Con'ersion Factors for Inhalation. Submersion, and Ingestion.1 988.8.4 Regulatory Guide I. 109. Calculation of Annual Doses to Man from RoUtine Releases ofReactor Effi uents for (he Purpose of Evaluating Compliance with JO CFR 50 Appendix I.October 1977.8.5 TDB-IV.7. Technical Data Book Process Monitor SetPoints. Rev. 222. 6/04/13.8.6 Regulatory Guide , .183, Alternate Radiological Source Terms for Evaluating DesignBasis Accidents at Nuclear Power Reactors. July 2000.8.7 U S Army Corps of Engineers Omaha District. Aerial Photography and Maps of theMissouri River Ponca State Park. Nebraska to Rule, Nebraska. September 2004.8.8 Nucleon Lectern Associates. The Health Physics and Radiological Health Handbook,1984.8.9 US EPA 400-R-92-001. Manual of Protective Action Guides and Protec'tive Action forNuclear Incidents. May 1 992.8.1I0 USEPA. Protective Action Guides And Planning Guidance For Radiological Incidents(Draft). March 2013.8.1 NI El 99-01 Revision 6. Development of Emergency Action Levels Jar Non-PassiveReactors. November 2012.8.12 USNRC NUREG- 1228. Source Term Estimation Incident Response to Severe NuclearPower Plant Accidents. October 1988.9 Attachments9.1 USGS Average River Flows9.2 EAL Threshold Calculations based on TEDE9.3 EAL Threshold Calculations based on Thyroid CDE m A :RP-AA-1 01:0 FC-14-004Revision 0Page 9ofi11Attachment 1: usGS Average River FlowsUSGS Surface-Water Annual Statistics for Iowa1) USGS 06601200 Missouri River at Decatur, NEBurr County, Nebraska:Hydrologic Unit Code 10230001Latitude 42=00'26, Longitude 96014'291, NAD27Drainage area 316,200 square milesGage datum 1,010.00 feet above NGVD292}r d *. 7WaterYear19931994199519961997199819992000200120022003200400060,Discharge,cubic feet persecond1988198919901991199225,94030,39036,49046,00057,44039,35039,14033,32027,69024,68024,67024,73029,03025,47021,82021,45022,240 ,,;i .....RP-AA-1 010 FG-14-0040Page 10 of I100060,Discharge,cubic feet persecondWater 1988 29,030Year 1989 25,470.... .1990 .. ...21,820 ,1991 21,4501992 22,2402005 21,2202006 22,4002007 21,0002008 19,6502009 23,9702010 39,0202011 80,2902012 35,1702013 25,850~* No Incomplete data have been used for statistical calculation

i, 010 FC-'I 4-004.... ..0

Page 1:1 of 11A~'emg Mi~cwi River Flowe RiverFlowYear cfs1988 290301989 25470]1990 218201991 214501992 222402001 276902002 246802003 246702004 247302005 212202006 224002007 21O002008 196502009 239702010 390202011 802902012 354702013 25850Average 28369 RP-AA-1O1O FC-14-004Revision 0Page 1 of 7Attachment 2: E.AL Threshold Calculations based on TEDEOi'=:3.7.10m.Bq pO{.'= 3.7- I0= ;<:= 0.01 * ~m :0.00IIsotope-= R~AkDEXCEL (".\ELR.D Spread Sheet. xlsc", '=Liquid Source Term!A5;A28")haiflife:=READEXCEL (".\ELRID Spread Sheet.xlsx" ,"Calculation SheetlE21I :E44") .dayActivity =R.EADEXCEL (".\ELR:D Spread Sheet.xlsx" , "Liquid Source Termn!F5;F28") .0DF REAOEXCEL (",\ELRD Spread Sheet.xlsx", "Liquid Source TermlB5:B28")-S.Calculate the Isotopic Fraction based on the Ci/MWt from UP.I Source Termf=Activity2. ActivityIsotope ="I-1311I"I--132""1--133""1-135""Cs--134""Cs-l36"'"Sb- 127""Sb-129""'Te- 1 29m""Te--1 31m""re-1 32,'"Ba-140""Sr-89"'"Sr-90""Sr-91""Mo-99""1*u-103"R~u-106""La- "Y-91"",Ce--144,'"Np--239"!2.2282 .10-2]13.2379"10 j!S4.5231.10 I[4.9904- 10 4.3228'10 213,9223,0..102I2,7122- i0"i17.2437.10 -111.4o2-1o -l-'S3.9723. o-022.0112.1o0-L9945. 10 I2.5119.10--4.423*

• 1 -3.6218.10-211.2935- 10 "I4.95.021!2.6454.10 21[4.7484.10holZflfe=18029.7. 10-28.7.10-'S3.6.1 0 211.3 .10J1,1"I0'13.851.28-1032.714.8.105 .05 '10"1.102.79dayl

~dpRP-AA-I 010 FC-1 4-004'= Revision 0Page 2 of 7TEDE 1= 0 -rn'i'eLUr-730.-F~=283869 ft'M:=3fO.8v :=7-mvht =2.7143 hri;=O04..22Threshold for AMt liquid EAL.Annual intake of water (ODCIV & Regulatory Guide 1.109)Average river flow rateMixing factor (ODCM)Distance from Fort Calhoun Discharge to MUD (ODCM)Average liyer flow is 4 -7 mphCalculate decay time distance to Intake and current speedExposure ltimeNumber of Isotopes in UPI Source TermSln(2)Calculate the decay constant for each Isotope(f.-E.E Calculate the release rate for each IsotopeU. At.M.DF .e[ Q Calculate total release rateQ2=8.3079 -_. llIIil RP-AA-1 010 FC-14-004Revision 0Page 3 of?7j,= I0,5000.. 12O000tu' = 120000. gp-Calculate a range of release flow paeRow rate of 1 Circulating Water Pumpw =U )~3QTCalculate the range of concentrations the equal the TDEDEAL base on a range of undiluted disch.arge flow rates1' (j iw,(gm RP-AA-1O10 FC-14-004Revision 0Page 4 of 7RM-05SBKC1t :=160 .mran-RMN-054 A/B (Blowdawn)= 9.84.*107 BKC2 ==158. Calculate a range of Threshold count rates based on dischargeflow rate (RNI-055)R1(wvi(pn a ~ /~t-A1RP-AA-1 010 FC-14-004: Revision 0Page 5 of 7/R~2:= (CT.-e2)+ BKG,2Calculate a range of Threshold count rates based on dischargeflow rate (RM-054 A/B)di-I'ft2 (rnin.'~)to (gpm)As can be seen by the charts above the pump flows have little no effect on the thresholdbased on the design range of the pumps 50 -270-gpm. RP-AA-1010 FC-14.004Revision 0Page 6 of 7During norami operations 3 dirculating wat~er pumps are running, each at 120,000 gpm.During power reductions or startup one circulator may be running. During outage periods oneRaw Water pump may provide dilution flow.EAL thresholds for a 1 circulating water pumps provideingdilutionEAL,=(L81.21O10) mmn.EAL2:= * --2+/-+BKG2EA_,A_ = (1.0798.10'~) mmn'DF ="5.328 6.734" 0:1.036

• 2.4642-1022.2496 "107.326.10'I1. 1248.1I0'4.995.106.69r-1031.6485.1 05.809<*10:9.102.*10:2.2015 9.472,10&4.144- i01.2987.*10 1.6813 *I08.954, 4.847- I0 4.884<-10'=2.1608.10"2.5086 *10EAL thresholds for a 2 circulatIng water pumps providelngdilutionEAL'=2-(2w26+ BKG,refa~CiEAL2=(5.399* 0') %,.g EAL thresholds for a 3 circulating water pumps provideing dilutionEAL1I=(- L BKG1EA,=~(4.o6o3. 1o7) =(Q.-T.,e+ BKG.,EAL2= (3.5904-10') rr"imiting concentration based on 3 circu[ation waite pump3 .wr,co=(a.6579. 1&") RP-AA-1O1O FC-1 4-004Revision 0Page 7 of 7 RP-AA-l10 FC-14-004:Revision 0Attachment 3: EAL Threshold Calculations based Thyroid CDECi,'3.7.1O10.-Bq jiCi::3.7.10'.Bq mrre~rn:-.0,001-rn,Isotope:= READEXCEL (".\ELR.D Spread "Liquid Source TernalAS:A28"1)halfli~fe "=READEXCEL (".\ELRLD Spread Sheet .xlsx", Sheet!E2I:E44'") =da~yActivity :=READEXCEL (".\ELRD Spread Sheet.,lsx"', Liquid Source Termn!FS'~F28"})GCDF R,-IEADEXCEL Spread Sheet~xlsx?", Liquid Source TermiOS :C28")*Calculate the Isotopic Fraction based on the Ci/MWt from UR.I Source Term._ActivityZActivity [8.029.7.10lf "1-431" ro[.02231 8,7.10-'1 "I-132" I 0.03241 3,-1 I1 "-133" 10.0452I 361 II 1-134" I 0.0499 28.8 -I0.["1-135" 0.0432175-0S"Cs-I34" 0.00Q39I 1.3" 10["Os-136" 0.0012' 1.1,10'I "Cs-137' (0.0027 l3.85'["b-2"0.002 I1,83,10-"Te-129mj 10.00141 halflife=I 1.25 day"Te--131m"I .0.0045 I 3.2Isotope=1 "Te-132"I 1=0.0318 1 (1.28-10.I"Ba-140" 10,03971 ]5.05.-10uSr-89)" 0,0201 1I"Sr-90"1 I0 002 I Ii o 10 .Is -59J1 o 0o251~ 4. o-aMo-99" ~ 0.0442.11,79"R~u-103" 3.0625 .1& -"Rtu-106" 0,01 ] .6 I 0'"La-10" 0,41 I1.68"aY-91" ( 0.0461 15.8'.10 I"Ce--144" I 0.02951]29-0"Np--23 9" L [0.4748 1 2.33

/f10 FC-14-004Revision 0Page 2 of 7CDE := 5O-mremLU:==730.*y rF:= 28369~ M:30.8d :=Wt.rnilev :=7,rnpht 2.714,3 hrAt := 1.hri :=0,1..22Threshold for AA1 liquid EALAnnual Intake of water (ODCM & Regulatory Guide 1,109)Average river flow rateMixing fadtor (ODCM4)Distance from Fort Calhoun Disdharge to MUD (ODL--M)Average river flow is 4 7 mphCalculate decay time distance to Intake and current speedExposure TimeNumber of Isotopes in URI Source TermA-- ln(2) Calculate the decay constant for each Isotope----i=- Calculate the release rate for eacdh IsotopeU.-At-M.DF .eCalculate total release rateQ.-(1.30T7. I) c- ~mw~2RP-AA-1 010 FC-14-004Revision 0Page 3 of 7w = 120000.

• pmj =1Q,5O000,. 120000Flow rate of 1 Circulating Water PumpCalculate a range of rejlease flow ratesin .'=J.gpmCTCalculate the range of concentrations the equal the CDE EALbase on a range of discharge flow ratesI-\I,.,,)

aRP-AA-l0iO FC-14-804Revision 0Page 4 of 7R, "= (Cr .e,) + BKG,RM-D54 A/B (Blowdown)£2=98 o17 *rmm6L,BKG2 :=l158 rn~in-'a range of Threshold count rates based on dischargeflow rates (R.N-O55)R1,(,,.)wL~ (gyir), RP-AA-1O1O FC-14-004Revision 0Page 5 of 7B =(Cr .E2) + BKG.,Calculate a range of Threshold count rates based on dischargeflow rates (RM-054 A/B)&,u, (g-m).1As czn be seen by the charts above the pump flows have little no effect on the thresholdbased on the design range of the pumps 50 -270-gpm. j-,RP-AA-1O10 FC-14-004Revision 0Page 6 of 7During norami operations 3 circulating water pumps are running, each at 120,000 gpm.During power reductions or startup one circulator may be running. During outage periods oneRaw Water pump may provide dilution flow.EAL thresholds for 1 circulating pump provideing dilutionEA1(Qr. +BGEAL = (1.9175.10&) mmnEAL2 ~.= .2+BKG2FAL2= vmn,I)F=I1.4319 3.367-10s2.2977,1036.623.

• 06.5'12 -1041.0138-10&4.662.1041.1692.1021.0693
• 1011.5873.10a1.9425.1021.5392 .1029.768.1031.5096 *.1026.438.*1022.2089'* 10a6.253.* I04.514.1024.07.1026.956 -2.8194-10remCiEAL thresholds for 2 drculating pump provideing dilutionEAL " L +/- 1EAL1= (9.5874.107) ranmEAL,::::: "

RP-AA-1 010 FC-1 4-004-Revision 0Page 7 of 7EAL thresholds for 3 dmulating pump provideing dilutionEA =(QT ).c, +BKG1EAL = (6.3916.107) EAL2= (5.6661-107) Limiting concentration based on 3 circulation water pumpC0=O0.5758 }}