Text

NE-02-09-12 - CGS Emergency Action Levels (Eals) Technical Bases - Enclosure 2
	ML16210A530
Person / Time
Site:	Columbia
Issue date:	07/28/2016
From:	Hettel W G; Energy Northwest
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML16211A338	List: GO2-16-104, LAR to Change EAL Scheme; ML16210A528; ML16210A529; ML16210A530; ML16214A372;
References
	GO2-16-104
	Download: ML16210A530 (269)
	v • d • e

GO2-16-Enclosure 2 EALs Calculation Revision Status RU1.1 RA1.1RS1.1RG1.1 NE-02-09 CGS Emergency Action Levels (EALs) Technical Bases Rev. 3 Dated 3/30/15 ENERGY NORTHWESTCALCULATION COVER SHEETECPage Equipment Piece No

.FW-SOFT-TECH-RASCAL; FW-SOFT-COTS-URIPage 1.000Cont'd on Page1.001 PRM-RE-1A; PRM-RE-1B; PRM-RE-1C;PRM-RR-3 DisciplineCalculation No.NE-02-09-12TEA-RE-13; TEA-RIS-13NUCLEARQuality Class II+WEA-RE-14; WEA-RIS-14SW-RIS-604; SW-RIS-605; SW-RE-4; SW-RE-5 FDR-RIS-606; FDR-RE-6 TSW-RIS-5; TSW-RIT-5; TSW-RE-5 Remarks TITLE/SUBJECT/PURPOSETitle/SubjectCGS EMERGENCY ACTION LEVELS (EALs) TECHNICAL BASESPurposePPM 13.1.1A provides the technical bases for emergency classificaiton per PPM 13.1.1 and the Emergency Plan. Thiscalculation derives selection of EAL values using the design database, QAR records and regulatory correspondence and is intended to be the source reference in PPM 13.1.1A for these EALs.CALCULATION REVISION RECORDREV NO.STATUS/F,P, OR SREVISION DESCRIPTIONINITIATINGDOCUMENTS 0 FINITIAL ISSUANCEAR 00184268-06 1 FDocument basis for NRC approved NUMARC/NESP-007 EALs and u pdate to current confi guration per CR 244578; void rev 0 license withdrCR 00244578, CR 00247379-01, CR 00246173-2 FCMR 0000010715, CMR 0000011948, CMR 0000012565CR00257071, CR00251948,CR00260848, AR00268160, 3 FIncorporate CMR 13192. Software updateURI replaces QEDPSAR 319446-04PERFORMANCE/VERIFICATION RECORDREV NO.PERFORMED BY/DATEVERIFIED BY/DATEOWNER'S REVIEW BY/DATEAPPROVED BY/DATE 0 SJ Rejniak 12/28/09LS Woosley 12/29/09N/AMA Armenta 12/30/09 1 LS Woosley 8/9/11JD Fisher 9/9/11N/AJL Tansy 11/08/11 2 JD Fisher2/4/14LS Woosley 2/4/14N/AMJ Kennedy 2/5/14 3 LS Woosley 3/29/15JD Fisher3/30/15N/AMJ Kennedy *Study Calculations shall be used only for the purpose of evaluating alternate design options orassisting the engineer in performing assessments.18645 R7 ENERGY NORTHWEST 0 BCALCULATION REVISION

SUMMARY

PageCont'd On Page1.0011.100Calculation No.NE-02-09-12Prepared By/DateVerified by/DateRevision No.LS Woosley2/2/15JD Fisher2/12/15 3REVISION NO.REVISION

SUMMARY

0PPM 13.1.1A provides the technical bases for emergency classification per PPM 13.1.1 and the Emergency Plan. The revision 0 of this calculation contained a vendor calculation, and documented assumptions, calculations and results for the gaseous monitor parameter values used to establish the CGS site specific Radiological Effluent Emergency Action Level values implementing the guidance of NEI 99-01 Revision 5.1Revision 1 voids the vendor calculation because adoption of NEI 99-01 Revision 5 was withdrawn from NRC review. Correct PRM-RE-1A calibration factor in QEDPS per CR 246173.2Resolution of CRs CR00257071, CR00251948, CR00260848, AR00268160, CR00281061, CR00301589and incorporation of CMRs 10715, 11948, and 12565.3Update Table 3 values using new URI-RASCAL software, replacing QEDPS/EDPS. IncorporateCMR 13192.Update calculation forms; since every single page of the calculation has the forms updated, software cases rerunand the content manipulated, there are no revision bars.27059R0 ENERGY NORTHWESTCALCULATION INDEX Page1.100Cont'd on Page1.200Calculation No.NE-02-09-12Revision No.

3ITEMPAGE NO. SEQUENCECalculation Cover Sheet1.000 -&1.001Calculation Index1.100 -Verification Checklist for Calculations and CMR's1.200 -1.208Calculation Reference List1.300 -1.303Calculation Output Interface Documents Revision Index1.400 -Calculation Output Summary2.000 -2.001Calculation Method3.000 -3.002Sketches4.000 -Manual Calculation5.000 -5.016APPENDICES:Computer runsURI Rascal dose assessment runsAppendixA150PagesAppendixBPagesAppendixCPagesSupport CalculationsAppendixD112PagesAppendixPagesAppendixPagesHistorical informationAppendixH156PagesAppendixPagesAppendixPages 25278 R7 ENERGY NORTHWESTVERIFICATION CHECKLIST FORCALCULATIONS AND CMRsPage 1.200Cont'd On Page1.201Calculation/CMRNE-02-09-12Revision003was verified using the following methods:Checklist BelowAlternate Calculation(s)Checklist ItemVerifier InitialsClear statement of purpose of analysisMethodology is clearly stated, sufficiently detailed, and appropriate for the proposed application.Is raw data (PDIS) being used as a calculation/CMR input?Yes NoIf yes, ensure the data was adequately validated (ref. DES-4-1 step 2.3).Does the analysis/calculation result require revising any existing output interface document as identified in DES 4-1, Attachment 7.3? Yes NoIf yes, ensure that the appropriate actions are taken to revise the output interface document per DES-4-1, Section 3.1.8. (i.e., document change is initiated in accordance with applicable procedures.)Does the Calculation's Summary of Results (or CMR's Predicted Results) include a discussion of available margin? Yes No Not ApplicableLogical consistency of analysisCompleteness of documenting referencesCompleteness of inputAccuracy of input dataConsistency of input data with approved criteriaCompleteness in stating assumptionsValidity of assumptionsCalculation sufficiently detailedArithmetical accuracyPhysical units specified and correctly usedReasonableness of output conclusionSupervisor independency check (if acting as Verifier)N/A-Did not specify analysis approach

- Did not rule out specific analysis options

-Did not establish analysis inputsN/AIf a computer program was used:

-Is the program appropriate for the proposed application?Yes No-Have the program error notices been reviewed to determine if theypose any limitations for this application?Yes No-Is the program name, revision number, and date of run inscribedon the output?Yes No-Is the program identified on the Calculation Method Form?Yes NoIf so, is it listed in the Software Catalog or if the software is used for calculations completed by vendors is it done under an approved (10 CFR Appendix B) software program?Yes No25280 R13Page 1 of 2 ENERGY NORTHWESTVERIFICATION CHECKLIST FORCALCULATIONS AND CMRsPage 1.201Cont'd On Page1.202Calculation/CMRNE-02-09-12Revision003Checklist ItemVerifier InitialsIf a CMR or calculation revision was prepared against calculation E/I-02-90-01:- Verify that manual calculations agree with automatic calculations on rows with modified input data.N/A-Verify that changes in loading are reflected at the upstream load centers.

N/A-Verify that other calculation cells have been checked as deemed appropriate by the verifier using manual calculations to assure accuracy has been maintained.N/A-Discussion of Results/Conclusions are still valid after calculation update. (i.e., bus & transformer rating not exceeded, etc.)N/AIf the calculation involves an instrument, verify that the calculated values are within the instrument display range............................................................................{AR-244578}Other elements considered:Verifier InitialsBased on the above, the Calculation/CMR is adequate for the purpose intended.Verifier(s)Print Name/Signature/DateVerifier InitialsJD Fisher25280 R13Page 2 of 2 VERIFIER COMMENTSPage 1.202 Cont'd On Page

Calculation No.

NE-02-93-30 Revision No. 3 # Verifier Comment Preparer Response 1. p. 2.0, refers to supporting information contained in a previous revision. That information needs to be retained in the current revision to be used in the calculation output. "and variations in the dose output with the variation allowed in input range was evaluated in the previous revision." We started this rev by saying how we should reduce the math to one page and reduce the rest to historical stuff available in passport. Will readjust which components are part of this revision and are rerun with URI. 2. p. 3.001 Cont'd On Page is 4.000. It should be 3.002 ok 3. p. 4.0 refers to QEDPS. The figure should be updated to URI or annotated. I can't edit it, so it was deleted. 4. p. 2.0 refers to Appendices A, B and C which do not exist in this revision and cannot, therefore, be calculation output. Recommend removing the discussion of previous revision content or retaining that content and justifying its applicability to a URI based Table 3. Appendix A is attached. Appendices B & C are not needed. 5. p.2.0 The QEDPS sensitivity study in Appendix D that forms the basis for the PPM limits on background variation needs to be updated for URI and spreadsheet tabs cal range and PPM INPUT updated. I updated the table on page D.1 and pages D.70-D.71. 6. p. 1.4 PPM 5.4.1 and SAG2 Table 26 need to be listed the output revision index Table 2 changed and the GE column is used per p. 2.001. Ok 7. p. 2.001 Error! Bookmark not defined. Appears twice. FDR results need to be re-linked to footnote 1. It is your form. Will delete the link. 8. p. 2.001 references pp. 5.008 and 5.023 as the sources for Tables 1 and 2. These are not correct. p. 5.012 contains tab FINAL but incorrectly reports the results for Table 2; it should have Table 1 results. Table 1 does not appear to be documented in the spreadsheet since tab EP EALs was not updated to provide Table 2 values. I can't follow so you will have to show me. Perhaps my editing up to this point has moved enough things to prevent following the issue. 9. p. 3.0 Unverified Program box needs to be checked. Software is classified as "commercial off the shelf" which does not need to be verified beyond functionality check. 10. p. 3.0 The method discusses benchmarking the current model against the 1994 results, but tab 1994 was not included in this revision. Discussion of the benchmark of URI needs to be added and Will think about it consistent with #1 response. I have edited the method section so see if it is sufficient.

VERIFIER COMMENTSPage 1.203 Cont'd On Page

Calculation No.

NE-02-93-30 Revision No. 3 # Verifier Comment Preparer Response the benchmarking against 1994 updated. "The calculation in the body of this document is validated by reproducing the results from the 1994 certification package [reference 12] and then updating the input parameters for the current plant configuration:" 11. Reconstruction of the basis is no longer present in the calculation and does not appear to be needed since Appendix H contains the 1994 method. Recommend deleting: "The details of the method used to reconstruct the basis, with spreadsheet names and considerations, are presented on pages 5.000-5.001." consistent with #1 response, discussion does explain the steps in how the calculation was derived, but there is more text saying when the spreadsheet pages are no longer needed. 12. p. 3.0 FW-SOFT-COTS-URI v2.0.0 is not listed in the software catalog, which lists v1.1. What EP wants is what was used. Sid Bauman's version number disagrees with Gary Ash's EPN number but neither are within my control. 13. p. 3.001 the change in method to URI is noted but the basis for the methodology change is not provided. Please document or reference the technical basis for URI and provide justification for the change in method, e.g. it's within a small factor of QEDPS results. SVVR added to the references. 14. Please annotate URI printouts per DES-4-1. You might want to move these to Appendix A, since your can't have a cover page easily in Part 5 and marking each "run" separately is tedious. INCLUDE the software name, revision number, and date of run on the first page of the computer output or computer output cover page. See Appendix A

Software output labeled appropriately. 15. p. 3.002 Pathway O discussion does not explain why QEDPS and URI are different. MAN-QEDPS-01 does not indicate that suppression pool scrubbing is modeled. Containment reduction factors for QEDPS are much larger for the first 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months in QEDPS ~1.75 times larger. The stack monitor response factors are different in URI. SGT filtration is less efficient than QEDPS. Recommend deleting the Path O discussion. Path J appears consistent with QEDPS based on the user manual. ok 16. p. 3.002 Software notes does not mention WEA or TEA monitored paths selected. Please add. Will do that with pathway selection and flow rate for each

EAL.

VERIFIER COMMENTSPage 1.204 Cont'd On Page

Calculation No.

NE-02-93-30 Revision No. 3 # Verifier Comment Preparer Response 17. p. 5.00, Item 2 use of the QEDPS default flow rates becomes problematic when QEDPS is retired. Rev 2 page 5.0 provides an approach. Added input selection table 18. Please justify or correct the default flow rates in URI for SGT, WEA and TEA. They are not specified in NE-02-10-05. I don't have the power to do either. I can declare what I used in the input/output section 5, and fill in the table intended for that purpose, with source references. 19. p. 5.0 Error! Bookmark not defined. Appears under Item 5. Assumptions and References are missing as a result. Will delete link. 20. p. 5.0 Item 5.d, discusses QEDPS usage; it should discuss URI usage since the monitor scaling is completely different. Edited 21. p. 5.0 footnote 1 discusses QEDPS output. Update to URI output. Ref 83 should be Rev 2 and the output interface discussion in the footnote deleted. Footnote was supposed to be on page 3.000 or so and migrated when the form was changed. Has been deleted. 22. p. 5.001 Output interfaces are not numbered and Ref # is not filled in.

Edited. 23. p. 5.001 Emergency Plan Table 1 (updated Table 3) does not exist. Table 3 is present in 13.1.1 and 1A but not EP-01. Output not needed. Deleted. 24. pp. 5.0 - 5.001 What is meant by LBD in LBD data source. In the Outputs, most items in that column are not licensing basis documents.

Edited. 25. p. 5.002 Emergency Plan Table 3 should be PPM 13.1.1A Table 3 since EP-01 no longer contains a copy of Table 3. Deleted per comment 23. 26. P. 5.3 Assumption 2 should be applicable since NE-02-10-05 references NE-02-09-12 as the source for background in URI.

Edited. 27. Assumption 3 supports BKGD shading of the URI derived EAL draft column. The greyed out text needs to be updated to reflect URI. It would be easier to annotate BKGD instead of having an assumption. Ok 28. Assumption 9 is not consistent with the results reported on p. 2.001 in Tables 1 and 2.

Assumption 9 defines a factor of 10 as the acceptance criteria for EAL selection and applies 50% of that or a factor of 5 as the analytical limit. We are using assumption 9A. Will use a goal of factor of 10 and factor of 2 or 3 satisfies 50.54(q) screening criteria.

VERIFIER COMMENTSPage 1.205 Cont'd On Page

Calculation No.

NE-02-93-30 Revision No. 3 # Verifier Comment Preparer Response The analytical limit should be reduced to a factor of 2 or 3, based upon the design limit in NE-02-10-05 for QEDPS v. URI. Determine whether the Alternate Assumption 9 can be eliminated if the factor of 2 or 3 satisfies 50.54(q) screening criteria. The results reported in p. 2.001 appear to be already applying this logic-i.e., the exact 1000 mrem results are reported in Table 1 and the rounded, within some dose factor are reported in Table 2. This is the opposite of the current Assumption 9, which would report the exact results in Table 2. 29. p. 5.5 Assumption 9 needs to be updated for URI; it still refers to QEDPS. LDCN-EP-023 should be LDCN-EP-11-023 in the Justification. Ok 30. p. 5.6 needs to be updated for URI. QEDPS is referenced. Steps 1 and 2 were not included in Rev 3. In order to use URI, without maintaining QEDPS as the basis code, the calculations in Step 1 need to be repeated with URI and compared to the 1994 EALs. Recommend not retaining the 1SGT case and going directly to NEW since we don't need to reverse engineer the 1994 results, having them in Appendix H now. Steps 2 and 3 could be combined. Yes, because that was how it was developed.

Is this direction to change history? You are correct, did not include those steps in this version. Sufficient explanation exists for the pages that are included to follow what was done.

Agree- didn't keep that 1SGT page (says "historical - do not use"), and did start with the NEW page. 31. p. 5.6 Step 4 should be incorporated into Input Item 5 (p5.0). The stack monitor calibration factors used in URI need to be explained as well as tied back to CR 244578. p. 5.11 should be updated to use the monitor detection efficiency used in URI, not the IMDS value. Used in cal range page.

ok 32. p. 5.7 background discussion needs to be included under Input 3 p. 5.0. The 1A gain discussion under Input 5. Understand this is direction to remove the contents of assumption 33. p. 5.7 Step 5 is not relevant to URI. Step 6 refers to lower limit of detection. MDL is the Ok VERIFIER COMMENTSPage 1.206 Cont'd On Page

Calculation No.

NE-02-93-30 Revision No. 3 # Verifier Comment Preparer Response term used on p. 5.11. 34. Step 7 should be replaced with p 5.3 from CMR 12865. Photos are not good design references. There is no 5.3, only -4,5,6,7, then 5.23, 5.24... 35. Steps 8 and 9 do not exist in Rev 3. Do we need them? no 36. p. 5.9 recommend using hidden text rather than gray for 1C UE. It looks like poor printing rather than info not used. Deleting the cells would also work. ok 37. p. 5.9 URI page numbers need to be added for 1C and WEA/TEA results reported. done 38. p. 2.1 The 1B UE in both tables does not match p. 5.12. The UE should not be affected by URI. Agree. Calculated then picked the bounding, but I can just remove it. 39. p. 5.12 does not report dose results consistent with the EAL 1.77 mrem should be divided by 3 for comparison to the UE dose rate from 13.1.1A Table 4. 5.12 is page FINAL; I did not change that case from previous rev. see sheet NEW for comparison to values that were altered. Method same, just ran with same input. 40. pp. 5.9 and 5.12 the results are not reported in a manner consistent with the EAL limits in Assumption 9. The units should be mrem/hr, not mrem or mrem/3hr. The URI results need to be divided by the release duration. ok 41. p. 5.009 reports dose results but the URI cases are not documented in the calculation. Please add the missing cases. You just complained about one of those in comment #39. 42. Selection of the Rx Bldg HUT needs to be discussed under INPUT or Assumptions and justification for the selection provided. This feature was not available in QEDPS and it is not clear why the HUT is 2 - 24 Hours instead of <2 Hours; there was no PRF for Rx Bldg. Drywell spray and Precipitation inputs need to be identified in Assumptions even though this feature was not available in QEDPS. Selection of Reactor Core Accident - Clad needs to be discussed in Assumptions since QEDPS was based on a melt accident Agree, will be in the table inserted for input values. See page 3.002 for methodology parameter inputs decided by EP, and see page 5.001 for URI Run parameter values with references. 43. p. 3.2 RCS should be included in the pathway description. Ok 44. pp. 5.12 and 5.17 1C GE does not appear to be Math performed in the spreadsheet FINAL page 5.012 VERIFIER COMMENTSPage 1.207 Cont'd On Page

Calculation No.

NE-02-93-30 Revision No. 3 # Verifier Comment Preparer Response correct. 7000 cps results in 1.07E3 mrem over 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , not 1070 mrem/hr as reported. The correct value appears to be 1.9E4 cps for 3.01E3 mrem. Similarly the SAE should be 2.14E3.

WEA and TEA results are essentially a factor of three low as well. EP says they do not want to change from the 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months base. Their procedure says round up plus 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for an ongoing release of unknown duration, so they have selected 3 hrs.

Beaver Valley just got a violation from the NRC for using 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months base for the estimate. Took the runs you cited to EP and current value was selected, so table will remain unchanged. 45. Page 1.200, on this page the "Does the Calculation Summary of results-" is not checked-, probably is N/A. ok 46. Page 1.303, on this page Sequence 89-should read "Unified RASCAL Interface" Ok, spell check got me on the "uniform" versus "unified" rascal interface 47. Page 2.001, Table 1 EP EAL Limits, Heading for Site Area Emergency should read "SAE" Fixed typo. 48. Should provide justification for the UE thresholds using pathway <RCS><Drywell><Rx Bldg><SBGT><Stack><Env> with clad failure similar to the justification for ALERT and higher emergencies using the Reactor Building monitors.

There is not enough information from a cold read to conclude that this is the appropriate pathway. For example <RCS><Rx Bldg><Stack><Env> might be appropriate, using normal coolant similar to the pathways used for the Turbine or Radwaste Buildings. I attached an example. Note in this example the thyroid dose drives the threshold.

Would gaseous effluents at 2x ODCM start SBGT and realign ventilation? At the low end, EP has decided for us that we are to use the LOCA pathway to keep it the same as QEDPS used even though now we are using different software. We use the UE thresholds based on 2x ODCM settings for each instrument. See page 5.013.

On the pathways question and the issue of whether SGT would start, the Z-signal is at 13 mrem heading up the stack. During our AST submittal we checked to see if it would start SGT and found that the release concentrations during the DBA LOCA would easily do it in the first few minutes.

49. All the dose assessments in Appendix A are based on a 3-hour duration of release. However, all the EALs are based on a dose in any one hour for a specific time period (e.g., for UE 60-minutes and ALERT 15-minutes). The duration of release should be based on 1-hour for development of the radiation monitor thresholds. We understand your concern and appreciate that you are making sure CGS understands what we are doing. The NESP says "-for the duration of the release" and our SER says the EALs are set based on dose projection software; our dose projection procedure PPM 13.8.1 says releases of unknown duration consist of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months plus the 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to confirm the end of the release by the field team for a total of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . So initial dose projections are performed for a minimum of 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months entered in the software, and the alert limits are based on that dose projection divided by 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to get the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months rate. Independent confirmation of this approach is noted by the fact that Beaver Valley got a violation for using a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and not using a 3-hour release duration.50. pp. A.1, 4, 16 and 20, URI runs for the UE's and PRM-RE-1B Alert did not add background to the UE/Alert value from spreadsheet NEW. URI None requested VERIFIER COMMENTSPage 1.208 Cont'd On Page

Calculation No.

NE-02-93-30 Revision No. 3 # Verifier Comment Preparer Response subtracts background. However, the dose results are not used to establish an EAL. Also, given the large margin to background, the calculated doses should not be affected. Therefore, these URI cases do not need to be re-run.

ENERGY NORTHWESTCALCULATION REFERENCE LISTPage 1.300Cont'd On PageCalculation No.NE-02-09-12Revision No.

3 SEQUENCE NO.AUTHORISSUE DATE,EDITION OR REVISIONTITLEDOCUMENT NO. 1Nuclear Management and Resources Council, Inc. (NUMARC)Rev 2January 1992Methodology for Development of Emergency Action LevelsNUMARC/

NESP-007 2EPA 1991Manual of Protective Action Guides and Protective Actions for Nuclear IncidentsEPA 400-R 001 3Kocher, David C.

1981Radioactive Decay Data TablesDOE/TIC-11026 4Energy NorthwestAmend. 60DEC 2009Gaseous Waste Management SystemsFSAR 11.3 5Energy NorthwestAmend. 60DEC 2009Process and Effluent Radiological Monitoring and Sampling SystemsFSAR 11.5 6Energy NorthwestAmend. 60DEC 2009Radioactive Gas Waste System Leak or FailureFSAR 15.7.1 7Energy NorthwestAmend 44May 2005Gaseous Effluent Radiation Monitoring SystemODCM 3.2 8Energy NorthwestRevision 0CC/RC -WEA Intermediate Range Noble Gas MonitorISP-WEA/PRM-X301 9Energy NorthwestRevision 2CC/RC -TEA Intermediate Range Noble Gas MonitorISP-TEA/PRM-X301 10Energy NorthwestAmend 47Aug 2008Offsite Dose Calculation Manual ODCM 11Energy Northwest7EOP/SAG Technical DocumentTM-212012Energy Northwest10/13/94Response to NRC Request for Additional Information Regarding WNP-2 Emergency Action LevelsGO2-94-235 13Energy Northwest0EDPS/QEDPS Input filesNE-02-10-01 14Energy Northwest29EMERGENCY DOSE PROJECTION SYSTEM OPERATIONSPPM 13.8.1 15Energy Northwest30AED IMDSSW-RIS-604 16Energy Northwest33AED IMDSSW-RIS-605 17Energy Northwest0AED IMDSFDR-RE-6 18Energy Northwest33AED IMDSTSW-RIS-5 19Energy Northwest1AED IMDSTSW-RIT-5 20Energy Northwest1AED IMDSPRM-RE-1B 21Energy Northwest1AED IMDSPRM-RA-1B 22Energy Northwest2AED IMDSPRM-RE-1C 23Energy Northwest1AED IMDSPRM-RA-1C 24Energy Northwest1AED IMDSPRM-RA-2 25Energy Northwest2AED IMDSPRM-XAY-1B 26Energy Northwest2AED IMDSPRM-XAY-1C 27 Deleted 28Energy Northwest24AED IMDSPRM-RR-3 29Energy Northwest34AED IMDSTEA-RIS-13 30Energy Northwest 22AED IMDS TEA-RIS-13A 31Energy Northwest32AED IMDSWEA-RIS-14 32Energy Northwest 16AED IMDS WEA-RIS-14A25281 R3 ENERGY NORTHWESTCALCULATION REFERENCE LISTPage 1.301Cont'd On PageCalculation No.NE-02-09-12Revision No.

3 SEQUENCE NO.AUTHORISSUE DATE,EDITION OR REVISIONTITLEDOCUMENT NO. 33Energy Northwest9AED IMDSPRM-LCRM-1B 34Energy Northwest5AED IMDSPRM-LCRM-1C 35Energy NorthwestAmend 37Jan 2003Radioactive Liquid Effluent Monitoring InstrumentationODCM Table 6.1.1-1 36Energy NorthwestPDC 4788Setpoint Calculation for RadWaste Building Exhaust Air Noble Gas Effluent MonitorNE-02-08-08 37Energy NorthwestPDC 4789Setpoint Calculation for Turbine Building Exhaust Air Noble Gas Effluent MonitorNE-02-08-09 38 Deleted 39Energy Northwest1MAXIMUM SETPOINT DETERMINATION FORINSTRUMENT LOOP PLANT SERVICE WATER RIS-5E/I-02-02-03 40Energy Northwest1MAXIMUM SETPOINT DETERMINATION FOR INSTRUMENT LOOP SW RADIATION INDICATING SWITCH 604E/I-02-91-1050 41Energy Northwest1MAXIMUMSETPOINT DETERMINATION FOR INSTRUMENT LOOP SW RADIATION INDICATING SWITCH 605E/I-02-91-1051 42Energy Northwest7/14/05Liquid Monitoring Setpoint Calculations SW-RIS-604 calibration QAR 09282007 0070116.14.2 43Energy Northwest11/12/07Liquid Monitoring Setpoint Calculations SW-RIS-605 calibration QAR 10082010 0150816.14.2 44Energy Northwest5/19/05Gaseous Monitoring Setpoint Calculations PRM-RE-1A calibration (also for -1B)QAR 09272007 0070116.14.1 45NRC11/30/2010Appendix B to Part 20-Annual Limits on Intake (ALIs) and Derived Air Concentrations (DACs) of Radionuclides for Occupational Exposure; Effluent Concentrations; Concentrations for Release to Sewerage10CFR 20 Appendix B, Table 2 46NRC12/9/94Safety Evaluation by Office of NRR for NUMARC /NESP-007 Based Emergency Action Levels at the WNP-2GI2-94-349, 7Energy Northwest1UNCERTAINTY DETERMINATION FORINSTRUMENT LOOP PRM RADIATION RECORDER 3, RECORDER POINT 1E/I-02-94-1306 48Energy Northwest4AED IMDSSW-RR-1 49Energy Northwest8AED IMDSSW-RR-2 50Energy Northwest 2 12/11/1983Radwaste Effluent Monitor12.13.11 51Energy Northwest5/19/05Gaseous Monitoring Setpoint Calculations TEA-RIS-13 calibrationQAR 09272007 00701PPM 16.14.125281 R3 ENERGY NORTHWESTCALCULATION REFERENCE LISTPage 1.302Cont'd On PageCalculation No.NE-02-09-12Revision No.

3 SEQUENCE NO.AUTHORISSUE DATE,EDITION OR REVISIONTITLEDOCUMENT NO. 52Energy Northwest5/19/05Gaseous Monitoring Setpoint Calculations WEA-RIS-14 calibrationQAR 09272007 00701 PPM 16.14.1 53Energy Northwest4/1/84NMC Midrange noble gas calibrationPPM 12.13.14 54Energy Northwest3/25/09Rx BldgEffluent Monitor Intermediate Range W/O 01160310-01CSP-PRMRE-X301 55Energy Northwest6/29/09Rx Bldg Effluent Monitor High Range W/O 0116705203-03CSP-PRMRE-X302 56Energy Northwest6/29/84Effluent Radiation MonitorsGO2-84-413 57Energy Northwest10/10/03Rx Bldg Effluent Monitor High RangeW/O 01062336-06CSP-STACK-M201 58Energy Northwest12/12/83RADWASTE EFFLUENT MONITOR FDR-RIS-606PPM 12.13.11 59Energy Northwest6AED IMDSPRM-LCRM-1A 60Energy Northwest3/19/1996Stack Monitor Gross Efficiency CalculationChemistry Calculation DIC 1441.696-001 61Energy Northwest6/1/84QAR CHM -WEA RADIATION CALIBRATION NUC MEASUREMENTS MIDRANGE NOBLE GAS MONITOR PPM 12.13.24 62Energy Northwest5/18/84QAR CHM -TEA RADIATION CALIBRATION NUC MEASUREMENTS MIDRANGE NOBLE GAS MONITOR PPM 12.13.24 63Energy Northwest7AED IMDSPRM-RE-1A 64Energy NorthwestWEA-RIS-14 instrument setpoint change request (Appendix H)ISCR-1341 65Energy NorthwestnewComparison of Gaseous Effluent Grab Sample with ODCM and EAL Thresholds - Quick TestCI-11.6 66Energy Northwest1UNCERTAINTY DETERMINATION FORINSTRUMENT LOOP PRM RADIATION RECORDER 3 RECORDERPOINT NUMBER 4E/I-02-94-1323 67Energy Northwest1UNCERTAINTY DETERMINATION FOR THELOOP WHICH IDENTIFIES THE REACTOR BUILDING ELEVATED RELEASE DUCT ACTIVITYE/I-02-93-01 68Energy Northwest1PRM RADIATION RECORDER 3 AND POINTS 2 AND 3E/I-02-94-1312 69Energy Northwest7LIQUID RADWASTE EFFLUENT RADIATION MONITOR -CCPPM 16.7.1 70Energy Northwest6RADIOACTIVE LIQUID WASTE DISCHARGE TO THE RIVERPPM 16.10.1 71Energy Northwest5RADIOLOGICAL EFFLUENT MONITORING-LIQUIDPPM 12.11.1B 72Energy Northwest16CHEMISTRY MONTHLY SOURCE AND CHANNEL CHECKSCSP-INST-M201 73Energy Northwest39CLASSIFYING THE EMERGENCY13.1.125281 R3 ENERGY NORTHWESTCALCULATION REFERENCE LISTPage 1.303Cont'd On PageCalculation No.NE-02-09-12Revision No.

3 SEQUENCE NO.AUTHORISSUE DATE,EDITION OR REVISIONTITLEDOCUMENT NO. 74Energy Northwest23CLASSIFYING THE EMERGENCY -TECHNICAL BASES13.1.1A 75Energy Northwest19PRIMARY CONTAINMENT CONTROL5.2.1 76Energy Northwest 14RADIOACTIVITY RELEASE CONTROL

5.4.1 77Energy

Northwest3CONTAINMENT AND RADIOACTIVITY RELEASE CONTROLSAG2 78Energy Northwest1QUICK EMERGENCY DOSE PROJECTION SYSTEMMAN-QEDPS79Energy Northwest0Setpoint Calculation for Radwaste Building Exhaust Air Noble Gas EffluentMonitorNE-02-08-08 80Energy Northwest0Setpoint Calculation for Turbine Building Exhaust Air Noble Gas Effluent MonitorNE-02-08-0981General Atomics Electronic Systems 0ANSI N42.18 Performance Report for TEA (04391601)Gas Monitor04391199CVI 1057-00,10082General Atomics Electronic Systems 00E 0ANSI N42.18 Performance Report for WEA (04391701)Gas Monitor04391197CVI 1057-00,95 83Energy Northwest1Plant Data Information System Software Design DescriptionSDD-PDIS-01 84Energy Northwest4PRM INSTRUMENTATIONEWD-36E-027 85Energy NorthwestPDC 4788PDC 4789GASEOUS MONITOR SETPOINT DETERMINATIONS16.14.1 86Energy Northwest0Determination of Low Range Stack Monitor Xe-133 Equivalent EfficiencyNE-02-13-10 87Energy Northwest0RASCALDOSE PROJECTION SOFTWARENE-02-10-05 88Energy Northwest3EMERGENCY PROCEDURE GUIDELINES SECONDARY CONTAINMENT CONTROLNE-02-84-33 89Energy Northwest0Software Validation and Verification Report for UnifiedRascal Interface (URI)FW-SOFT-COTS-

URI 90Energy Northwest0ELECTRICAL WIRING DIAGRAMPROCESS RADIATION MONITORING SYSTEMTEA-RIS-13EWD-36E-035 91Energy Northwest1ELECTRICAL WIRING DIAGRAMPROCESS RADIATION MONITORING SYSTEMWEA-RIT-14EWD-36E-037 92Energy Northwest10Reactor BuildingAED SPC 318A 93Energy Northwest1EDPS/QEDPSNE-02-10-0125281 R3 ENERGY NORTHWESTCALCULATION OUTPUT INTERFACEDOCUMENTS REVISION INDEXPage1.400Cont'd On Page2.000Calculation No.NE-02-09-12Prepared By/DateLS Woosley3/8/15Verified by/DateJD Fisher3/30/15Revision No.

003The below listed output interface calculations and/or documents are impacted by the current revision of the subject calculation. The listed output interfaces require revision as a result of this calculation. The documents have been revised, or the revision deferred with Manager approval, as indicated below.AFFECTED DOCUMENT NO.CHANGED BY(e.g., PDC,LDCN, CMR, Rev.)CHANGED DEFERRED(e.g., AR, LETTER NO.)

DEPT.MANAGER *PPM 13.1.1 PPM 13.1.1A Emergency PlanNE-02-10-01FW-SOFT-COTS-URILDCN-EP-15-001LDCN-EP-15-001 LDCN-EP-15-001LDCN-EP-15-001AR 283069-09LDCN-EP-15-001 AR 319446-14*Required for deferred changes only.Design Engineering Manager approval required for deferred design calculations.25285R4 ENERGY NORTHWESTCALCULATION OUTPUT

SUMMARY

Page Cont'd On Page2.0002.001Calculation No.NE-02-09-12Pre p ared B y/DateVerified b y/DateRevision No.LS Woosley2/2/15JD Fisher3/30/15 3Results and ConclusionsREV.BARThiscalculation provides the basis for the PPM 13.1.1A Table 3 values as committedin Reference 12, and uses current flow rates and alarm analytical limits to calculate new EAL values. The instruments with limits based on alarm values use the ODCM setpoint calculation proceduresas the reference for the analytical limit for the alarm. The draft EAL is computed from the requisite multiplier on the alarm analytical limit.The instrument limits based on dose used the target dose values from reference 12to iterate until the dose rate target is reached. The draft EAL is the input value to the software URI, and the output is the dose rate at the dose target selected.Background radiation values are incorporated into the limits and EAL's selected to minimize sensitivity to variations in background.Consideration is given to the minimum detectablelevel for the instrument so that all limits can be detected.Minimum and maximum instrument range is considered so that selected EAL's are on-scale.Final values are based on all these considerations and rounded to the nearest readable increment on the log chart recorder. This includes variation in calibration factors and tolerance for background changes.Doses at the rounded EALs are within a factor of 3 of the dose target, since an acceptable result is within a factor of 10per reference 1.------------------------------------------------------------------------------------------------------------------------------------------------------The analytical limit for each instrument was calculated on spreadsheet tab BKGD (page 5.010) using the formula on page 3.002. Range checking of the final values was performed on sheet RANGE CHK (page 5.011) and all EALs still meet the constraints from page 5.011. The limits that were close based on background variation were evaluated using URI runsand variations in the dose output with the variation allowed in input range was evaluated on page 5.011.The exception to this approach is for selecting the reactor building intermediate range alarm value, using ODCM limits. The UE value for PRM-RE-1B was derived for use in sheet NEW using the Chemistry department spreadsheet for that purpose, located in Appendix D..See page 5.009for the ODCM limits.The Appendix A cases that werethe first try at developing dose values consistent with the historical commitments are pages A.1-A.13.The process description starting on page 5.006 describesthe historical path to development.Final EAL values are shown on page 5.015 and the computer runs are in Appendix A.All of the Unusual Event values were selected based on the ODCM limits and UE/2 calculated on page 5.014 for EOP and TM-2120 Table PC-1.18652 R4 ENERGY NORTHWESTCALCULATION OUTPUT

SUMMARY

Page Cont'd On Page2.0013.000Calculation No.NE-02-09-12Pre p ared B y/DateVerified b y/DateRevision No.LS Woosley 3/29/15JD Fisher3/30/15 3Results and ConclusionsREV.BAR ConclusionTable of ANALYTICAL results for use for Emergency Response EAL limits (page 5.015):Table 1EP EALsEmergency Action LimitsInstrumentUE A~SAEGE PRM-RE-1B 6.0E3 cps -- -- -- PRM-RE-1C -- 400 cps 2000 cps 20000 cps TEA-RIS-13 1.02E-04 Ci/cc 8.35E-04 Ci/cc 8.35E-03 Ci/cc 8.35E-02 Ci/cc WEA-RIS-14 1.98E-03 Ci/cc 3.45E-03 Ci/cc 3.45E-02 Ci/cc 3.45E-01 Ci/cc SW-RIS-604 1E2 cps 1E4 cps -- -- SW-RIS-605 1E2 cps 1E4 cps -- -- FDR-RIS-606 70 cps 1 7E3 cps 1 -- -- TSW-RIS-5 3E-5 Ci/cc 3E-3 Ci/cc -- --

1Value based on HIGH-HIGH alarm setpoint with no discharge in progress. PPM 13.1.1A Table 3 should use 2 and 200 times the HIGH-HIGH alarm for UE and A, respectively since the alarm setpoint is adjusted prior to discharge for the isotopic mixture determined by laboratory analysis.The background rangesfor PRM-RE-1C, TEA-RIS-13 and WEA-RIS-14 are specified on page 5.016 for use in surveillance procedures.PPM 5.2.1 and SAG2 Table 27values for the effluent radiation monitors are specified below:INSTRUMENTTABLE 27 LIMITBASISPRM-RE-1B3.0E+03CPSUE / 2TEA-RIS-135.1E-05Ci/ccUE / 2WEA-RIS-149.9E-04Ci/ccUE / 2 ConclusionThe Emergency Action Levels (EALs) comply with regulatory requirements and commitments.The EALs were developed to provide margin to accommodate slight variations in inputs, with upper and lower background values evaluated and the EALs centered in their ranges.

18652 R4 ENERGY NORTHWESTCALCULATION METHOD Page Cont'd On Page3.0003.001Calculation No.NE-02-09-12Pre p ared B y/DateVerified b y/DateRevision No.LS Woosley2/3/15JD Fisher3/30/15 3Analysis Method (Check appropriate boxes)Manual (As required, document source of equations in Reference List)Computer Verified Program: Software/RevisionFW-SOFT-COTS-URI v2.0.0Unified RASCAL InterfaceUnverified Program: Document in Appendix BGaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001.xlsxApproach/MethodologyREV.BARNUMARC/NESP-007 methodology for determining Emergency Action Levels (EALs) was adopted with NRC approval in 1994 (GI2-94-349). The approved methodology was initially submitted in GO2-93-302 and largely revised as part of an NRC request for information (RAI) response (GO2-94-235). The underlying calculations were documented in the licensing certification package for GO2-94-235 and are included here as Appendix H. The approved 1994 methodology is described below followed by the changes in methods required to update the EALs to the current CGS configuration.Paragraph numbers are based on the current PPM 13.1.1A format. The NUMARC/NESP-007 Initiating Conditions (IC) related to the EALs are included as the underlying requirement that the values in PPM 13.1.1A Table 3 support. Page numbers are from the enclosure to GO2-94-235 found in Appendix H. The details of the method, with spreadsheet names and considerations, are presented on pages 5.006-5.007.5.1.U.1 Unusual EventNUMARC IC:AU1 -Any unplanned release of gaseous or liquid radioactivity to the environment that exceeds two times ODCM limits for 60 minutes or longer.From Appendix H [reference 12]:Threshold values for Emergency Action Levels under Initiating Condition AU1 were established at two times the applicable ODCM limit. For gaseous effluents, the threshold takes into account the partitioning of total allowable release between the release points. The high alarm is used for the elevated release intermediate range monitorand the high-high alarm is used for the radwaste and turbine building low range monitors. Liquid effluent thresholds for SW and TSW are based on high alarms and take into account the 80% of allowable setting of the alarm. The FDR threshold is based on 100% of the high-high alarm.5.1.A.1AlertNUMARC IC:AA1 -Any unplanned release of gaseous or liquid radioactivity to the environment that exceeds 200 times the radiological specifications for 15 minutes or longer.

25290 R4 ENERGY NORTHWESTCALCULATION METHOD Page Cont'd On Page3.0013.002Calculation No.NE-02-10-05Pre p ared B y/DateVerified b y/DateRevision No.LS Woosley1/23/2015JD Fisher 3/30/15 3From Appendix H [reference 12] pages 4 -5:With effluent monitor readings that approximate 200 times normal operating limits, it is reasonable to assume the presence of an isotopic mixture that is more representative of an accident source term mixture than a normal operating source term. The CGS evaluation in 1994 showed that a minimal containment bypass event with fuel gap release, as evaluated by the RASCAL emergency dose projection code, closely approximates the Alert level threshold. CGS therefore revised this EAL to use effluent monitor threshold values equivalent to 10 mrem/hr TEDE or 50 mrem/hr thyroid CDE based on emergency dose calculation methods and parameters as opposed to ODCM methodology. Where Standby Gas Treatment is applicable, it was assumed to be operating as this provides the more conservative level for beginning assessment of the release.The effect is to more realistically maintain the gradient from Unusual Event to Alert to Site Area emergency through consideration of the change in source term isotopic mixture that is expected to occur between two and two hundred times ODCM limits. It also reduces the threshold for beginning assessment of a release without impacting the level at which declaration of an alert will occur. Assuming an accident source term allows assessment to be performed using monitor readings and an emergency dose projection code in accordance with PPM 13.8.1, Emergency Dose Projection System Operation.Columbia ODCMRFO 6.2.2.1limits restrict Site Boundary dose rate to 500 mrem/yrwhole bodyand 1500 mrem/yr toany organ. Two hundred (200x) times the thyroid dose rate equates to approximately 34 mrem/hr. Fifty (50) mrem/hr is used in the EAL for IC AA1where thyroid CDE is found to be most limiting, to maintain the desired gradient between Alert and Site Area EALs.5.1.S.1 Site Area EmergencyNUMARC IC:AS1 -Offsite dose resulting from an actual or imminent release of gaseous radioactivity that exceeds 100 mrem TEDE or 500 mrem thyroid CDE for the actual or projected duration of the release.From Appendix H [reference 12] pages 5 -7:The EAL has been revised using 5 mph wind speed and stability class E, conditions that are representative of annual average meteorology at Columbia. Other assumptions used in the calculations are release duration of one hour, one train of standby gas treatment where SGTS is in use, and design building effluent flow rates where SGTS is not applicable.Gaseous effluent monitor thresholds for entry into the revised Alert EAL were developed using the same methodology and source termisotopic mixture as was used to establish the threshold values for the Site Area EALs. The desired gradient of one order of magnitude is maintained by basing the Alert threshold on 10 mrem/hr TEDE and 50 mrem/hr CDE to the thyroid while the Site Area threshold is based on 100 mrem/hr TEDE and 500 mrem/hr thyroid CDE. Columbia originally adopted an Emergency Dose Projection code QEDPSand is now replacing by URI-Rascal with this revision.For consistency between values used in the EALs and the code which will be used by the Control Room staff in assessing the EAL indicators, EALs under Initiating Conditions AA1, AS1 and AG1 have been recalculated using URI.5.1.G.1 General EmergencyNUMARC IC:AG1 -Offsite dose resulting from an actual or imminent release of gaseous radioactivity that exceeds 1000 mrem TEDE or 5000 mrem thyroid CDE for the actual or projected duration of the release using actual meteorology.

25290 R4 ENERGY NORTHWESTCALCULATION METHOD Page Cont'd On Page3.0025.000Calculation No.NE-02-10-05Pre p ared B y/DateVerified b y/DateRevision No.LS Woosley3/29/15JD Fisher 3/30/15 3FORMULAS (page 5.006)Minimum Detectable Level [MDL] = 4.66

SQRT(background) or 4.66

STDEV.S(background)(1)[Ref. 10, Definition Lower Limit of Detectability (LLD), Reference 56 (page 87)and Reference 50, LLD]Decade rounding [x] = truncate ( LOG10(AL', 0 decimal digits))(2)Draft Analytical Limit [AL'] = MAX( (MDL + background), ( draft EAL + background))(3)SOFTWAREMETHODOLOGY NOTESThe use of URI RASCAL instead of QEDPS/EDPSprovides flexibility in selection of the release path that did not exist in QEDPS. The RAPID assessment capability of URI has 6 pathways to pick from instead ofassuming LOCA; theLOCA pathway is the 5 thone in the list RCS -DW -RB -SGT -RB effluent (stack) -ENVThe DETAILED assessment of URI, pathway J was selected, which is the same drywell LOCA pathway RCS -DW -RB -SGT -RB effluent (stack) -ENVThe input run parametersfor the Detailed assessment are as follows:Meteorological data 33 ft CGS Met tower 5 mph, 330 W/D, Stab class = E Selected pathway option(1) Path J LOCA Hold up time 2-24 hours (Reactor Bldg/2 hr (DW)) Monitored release point Stack (Hi) Release Point Flow Rate 4500 cfm Selected pathway option (2) Path C Turbine building Monitored release point TEA (Hi) Turbine Generator Bldg < 2 hr holdup Release Point Flow Rate 360,000 cfm Selected pathway option (3) Path V Radwaste building Monitored release point WEA (Hi) RadWaste Bldg <2 hr holdup Release Point Flow Rate 84,000 cfm 25290 R4 ENERGY NORTHWESTMANUAL CALCULATION Page5.000Cont'd On Page 5.00 1Calculation No.NE-02-09-12Prepared By/DateLS Woosley 3/8/15Verified by/DateJD Fisher3/10/15Revision No.

3REV.BARINPUTSAND OUTPUT INTERFACESMany of the references were used for general understanding of the parameters selected for input. Only the values cited in these tables have been used as a specific source of data values, the rest were generic references.INPUTSITEMData of interest data sourceRef #1Certification package is used as the baseline for the basis of the emergency plan Table 3 values. The submittal certification package contains the technical basis for each limit, the dose projections from QEDPS rev. 1 substantiating the limits, and the IMDS sheets for the instrument settings. Attached in Appendix H. G02-94-235 Appendix H

-2DELETED -3Background and detection efficiency values are from the calibration references for the specific instruments

-13, 38, 39, 42, 43, 44, 54, 55, 58, 60, 79, 80, 86 41.Liquid Calibration Factors (detector efficiencies equivalent Cs-137):a.FDR-RIS-606 liquid calibration factor is 3.151E6 cps/Ci/cc (Reference 50). PPM 16.7.1, Rev 6, reports 3.301E6 cps/Ci/cc, which is incorrect based on CR 00223352, which corrected PPM 16.7.2. CR 00248950 initiated to correct PPM 16.7.1. GO2-84-413 reported 2.92E6 based upon the uncorrected version of QAR 12.13.11 (Reference 50).

-5 0 52.Gaseous Calibration Factors (detector efficiencies equivalent Xe-133)a.PRM-RE-1A is 3.69E8 cps/Ci/cc (References63and 86). References 59 and 44 contain erroneous values per CR 00202259, CR 00246173 and CR 00248448.Reference 86 added per CR 00281061.b.PRM-RE-1B is 5.51E5 cps/Ci/cc (References 60 and 33). Reference 54 contained an incorrect value, which has been removed in Rev 6.c.PRM-RE-1C is 12.8 cps/Ci/cc (Reference 60 and 34). Reference 55 contained an incorrect value, which has been corrected in Rev 8.d.URIstack monitor gains are 1/0.367 (Reference 3)times the calibration factors. URI does not normalize to gamma-abundance,equivalent Xe-133; the ODCM spreadsheet does.e.TEA-RIS-13 is 2.15E7 cpm/Ci/cc (Reference37p. 5.002). f.WEA-RIS-14 is 1.81E7 cpm/Ci/cc (Reference36p. 5.002). NE-02-13-10Chemistry Calc 96-00163, 8659, 4460, 3360, 34 54 55 80 79 86 6SDD-PDIS-01 defines the radiation monitor displays in the emergency centers. 1.PRM-RE-1A "Stack Lo" 10 -10 6cps format integer "nnn,nnn"2.PRM-RE-1B "Stack Int" 10 -10 6cps format integer "nnn,nnn"3.PRM-RE-1C "Stack Hi" 10 -10 6cps format integer "nnn,nnn"4.TEA-RIS-13 "TG Exh COMP" 10 10 3Ci/cc format exponential 83 18694 R4 ENERGY NORTHWESTMANUAL CALCULATION Page5.001Cont'd On Page 5.00 2Calculation No.NE-02-09-12Prepared By/DateLS Woosley 3/8/15Verified by/DateJD Fisher3/10/15Revision No.

3REV.BAR"n.nnEnnn" 15.WEA-RIS-14 "RW Exh COMP" 10 10 3Ci/cc format exponential "n.nn E nnn" 17 The maximum allowed background for TEA-RIS-13 Channel 1 is 388 cpm (1.80E-5 Ci/cc). This is larger than the Alert Alarm setpoint. NE-02-08-09 [reference 80] page 5.005, TEA-RIS-13 Channel 1 and Channel 3 Alert Alarm setpoint is 9.97E-6 Ci/cc. The setpoint was established at 4.66

background as a value reasonably above expected background to indicate that an actual release may be in progress. FSAR 11.5.2.2.1.6 states that normal activity is expected to be below detectable levels. In the absence of an actual release, the Alert Alarm setpoint represents an upper bound on background variation because a spurious alarm would alert the operators to a potentially degraded condition. A spurious alarm would result in a functionality evaluation, so there is no need for a separate procedural limit on background for Channel 1. The same conclusion applies to WEA-RIS-14.

NE-02-08-09 NE-02-08-08 80 79 URI Run Parameter Inputs

Data of interestData sourceRef #

1 Reactor building HVAC flow rates:

SGT flow rate =4500 cfm (historical practice) NE-02-10-01 MAN-QEDPS-01 13 78 2 Turbine Generator building HVAC flow rate:

TEA flow rate = 360,000 cfm (historical practice) NE-02-10-01 MAN-QEDPS-01 13 78 3 Radwaste building HVAC flow rate:

WEA flow rate = 84,000 cfm (historical practice) NE-02-10-01 MAN-QEDPS-01 13 78 4 Meteorology conditions = site nominal selections of 5mph wind speed, 330 direction, condition E, no precipitation page 3.001 - 5 Rx Bldg. hold up time (HUT) = instead of <2 hrs, use 2-24 hours This feature not available in QEDPS; there's no process reduction factor (PRF) for Rx Bldg. AED-SPC-318A 92 6 Selection of Reactor Core Accident = Clad. NUMARC/NESP-007 1 7 NUMARC/NESP-007 Table 3 EAL bases are 2-20% clad failure. Time since reactor shutdown = 0 min 0 sec selected consistent with reference 12 application. Appendix H - 8 Projected release duration = 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months selected consistent with historical practice Originally developed due to limitation in QEDPS model. MAN-QEDPS-01 78 18694 R4 ENERGY NORTHWESTMANUAL CALCULATION Page5.002Cont'd On Page 5.00 3Calculation No.NE-02-09-12Prepared By/DateLS Woosley 3/8/15Verified by/DateJD Fisher3/10/15Revision No.

3REV.BAROUTPUT INTERFACES

Data of interestOutput reference Appendix C for analytical limit, lower limit of detection and allowed range for background from sheet BKGD page 5.010: E/I-02-02-03 (TSW-RIS-5)E/I-02-91-1050 (SW-RIS-604)E/I-02-91-1051 (SW-RIS-605)E/I-02-94-1306 (PRM-RE-1B)E/I-02-94-1323 (PRM-RE-1C)E/I-02-93-01 (PRM-RE-1A)E/I-02-94-1312, NE-02-08-08 & NE-02-08-09 (TEA-RIS-13, WEA-RIS-14)FDR-RIS-606 does not have instrument loop or setpoint calculations.

E/I-02-02-03 E/I-02-91-1050 E/I-02-91-1051 E/I-02-94-1306 E/I-02-94-1323 E/I-02-93-01 E/I-02-94-1312 NE-02-08-08 NE-02-08-09 Analytical Limit and background range: PPM 16.14.1 (PRM-RE-1A, TEA-RIS-13, WEA-RIS-14)PPM 16.14.2 (SW, TSW)CSP-PRMRE-X301 (PRM-RE-1B)CSP-PRMRE-X302 (PRM-RE-1C)ISP-TEA/PRM-X301 (TEA-RIS-13)ISP-WEA/PRM-X301 (WEA-RIS-14)PPM 16.7.1 (FDR)PPM 16.10.1 (FDR)PPM 12.11.1B (FDR)CSP-STACK-M201 (PRM-RE-1B, PRM-RE-1C)CSP-INST-M201 (TEA,WEA,SW,TSW,FDR)

PPM 13.1.1 and the bases PPM 13.1.1A PPM 13.1.1 PPM 13.1.1A EOP/SAG Technical Document EOPs and SAGs: PPM 5.2.1 Table 27PPM 5.4.1 Table 26SAG2 Table 26 andTable 27Table 26 contained the Emergency Plan Table 3 General Emergency Offsite Radioactivity Release Limits but has been removed from EOPs. Table 27 contains the Table 3 UE limits divided by 2 to produce the ODCM RFO Offsite Radioactivity Release Limits. NE-02-84-33 for TM-2120 PPM 5.2.1 PPM 5.4.1 SAG2 URI RASCAL CGS ANNEX NE-02-10-05 18694 R4 ENERGY NORTHWESTMANUAL CALCULATION Page5.003Cont'd On Page 5.00 4Calculation No.NE-02-09-12Prepared By/DateLS Woosley3/8/15Verified by/DateJD Fisher3/10/15Revision No.

3REV.BARASSUMPTIONS

Data of interestdata sourceRef #

1The equation for the minimum detectable activity concentration for each instrument is characterized by Minimum Detectable Level [MDL] = 4.66

SQRT(background) , equation (1) above. Justification: submission to the NRC described the equation and demonstrated this formula as more conservative than ANSI 13.10. It is used to characterize the impact of the background radiation field on the instrument analytical limit of the instrument that is operating in the field, and conservative estimation of impact allows for variations in plant conditions. GO2-84-413 56 2Background radiation values are from the calibration references for the specific instruments. An attempt was made to use the most recent documented value that represents shutdown or low power operation. Justification: Plant surveillance data is reliable and retrievable for the purpose of this calculation. The principal use of the emergency plan will be in the shutdown or low power configurations, so basing the anticipated radiation field strength on that condition, and not requiring the software user (dose assessor) to manually make the adjustment, will improve accuracy of results.

-44, 54, 55, 79, 80 3Draft analytical limits consist of the preliminary EAL value plus applicable background. Justification: Draft analytical limits are developed using equation (3), either by actually adding the terms together or by using software that performs that addition during use. The math in the spreadsheet cell (shaded blocks on page 5.010) is derived from the URI runs already including background, so it does not need to be added.

-Page 5.010 4 The EAL thresholds for SW and TSW are rounded to the nearest discernable

meter graduation. Justification: GO2-94-235 submitted this for approval (RAI #4b, page 5). GI2-94-349 approved the associated EAL's for SW and TSW.

GO2-94-235 GI2-94-349 - 5The formula for the tolerance on the EAL threshold is the largest value of the MDL or the draft analytical limit with background. Justification: Useful limits should at least be on scale, above the minimum value detected by the instrument. If any of the values do not meet that criterion, either dose-derived or setpoint-derived, then the final analytical limit is adjusted to account for it.

Page 5.010 18694 R4 ENERGY NORTHWESTMANUAL CALCULATION Page5.004Cont'd On Page 5.00 5Calculation No.NE-02-09-12Prepared By/DateLS Woosley3/8/15Verified by/DateJD Fisher3/10/15Revision No.

3REV.BAR 6Rounding on final analytical limit is expected and practical for use in the Emergency Plan. Justification: Readings on the graphical output on a log scale are not readable by Operations to more than one significant digit. Operators are not experienced at interpolation, even on linear scales, having a training expectation if not a procedural requirement to use the next higher value. The next higher value rounded off to one significant digit is the expectation for log scale instruments, and the appropriate readings have been calculated for the final analytical limit.

Page 5.012 7Gaseous and liquid calibration factors are accurate to within 20% of the primary calibration results. Justification: EAL values do not need to account for variations due to calibration accuracy. This is the level of variation allowed in surveillance procedures before re-scaling with the transfer source or a new gaseous/liquid calibration is performed. - 42, 43, 44 8DELETED 9NUMARC/NESP-007 EAL Thresholds are evaluated within a factor of 10 for dose resulting in the following acceptable range for each dose threshold General = 1000 mrem TEDE Site Area = 100 mrem TEDE Alert = 10 mrem TEDE OR General = 5000 mrem CDE Site Area = 500 mrem CDE Alert = 50 mrem CDE Operator ability to read the exact values specified in Table 3 on the log chart recorders is not required.Alternate indications such as TDAS/eDNAor manually selected digital displays on the chart recorders may be used where available.Table 3 values must be on-scale and above minimum detectable values for the instruments.Existing calibration tolerance (20%) is allowed without change to Table 3 values. This is based on the existing functionality,acceptance criteria in current procedures. Larger variations require a recalculation of Table 3.Background variations are restricted such that dose varies by no more than the amount allowed by existing calibration variation-i.e the dose impact of a 20% change in calibration factor.Changes to background or calibration variations in excess of the above criteria require recalculation of Table 3.

Justification: Provided by LDCN-EP-11-023 output interface. Calibration tolerances in plant procedures have been in place since initial approval of the NUMARC/NESP-007 EAL scheme. NUMARC/NESP-007 Appendix H SER

- 10DELETED 18694 R4 ENERGY NORTHWESTMANUAL CALCULATION Page5.005Cont'd On Page 5.00 6Calculation No.NE-02-09-12Prepared By/DateLS Woosley3/8/15Verified by/DateJD Fisher3/10/15Revision No.

3REV.BAR 11EOP/SAG Table 27 ODCM RFO Limit is 1/2 of the UE for PRM-RE-1B, TEA-RIS-13 and WEA-RIS-14 Justification: TM-2120 Table PC-1, documents that Table 27 is based on PPM 13.1.1 Table 3. Table 27 was established in Rev 2 of TM-2120 and was based on 1/2 of the UE value in PPM 13.1.1, Rev 33. The methodology for 5.1.U.1 defines the UE as 2 x the ODCM limit. The converse should also be true. This assumption is validated by comparison to the instrument readings corresponding to the ODCM limit, using ODCM methodology (see Chemistry department spreadsheet documented in Appendix D). Page 5.016 references the specific results in Appendix D, all of which are higher than the proposed Table 27 values. Final Calculation of these values on page 5.014. TM-2120NE-02-03-05NE-02-03-06PPM 13.1.1 18694 R4 ENERGY NORTHWESTMANUAL CALCULATION Page5.006Cont'd On Page 5.00 7Calculation No.NE-02-09-12Prepared By/DateLS Woosley3/8/15Verified by/DateJD Fisher3/10/15Revision No.

3REV.BARConstructing the basis for the EAL table for the Emergency Plan 1.Start with the approved bases of the Emergency Action Levels (EALs) from 1994 [NRC SER letter [reference 46] and the certification package [12] in Appendix H] 2.Fix the parameter values determined to be in error during the AR 244578244578root cause.a.Gain for the high range stack monitor PRM-RE-1C was changed from 12.8 to 34.9. [CR 244578, reference 60]b.Gain for the intermediate range stack monitor PRM-RE-1B was changed from 5.5e5 to 1.5e6. [reference 54, 60]c.Background for the low range stack monitor PRM-RE-1A was changed from 15000 cps (100% power background value) to 3300 cps (shutdown background value) since most of the events that dose projection would be used for begin with direction to shut down the reactor. Alarm setpoints are based on shutdown too [Ref. 44].Gain for the low range stack monitor PRM-RE-1A was changed from 3.0e8 to 1.01e9. [CR 246173]3.Spreadsheet "NEW" [page 5.009]a.Use the chemistry department ODCM spreadsheet to determine a useful, valid setpoint for the intermediate range stack monitor. This validation study is found in Appendix D.b.Perform dose analysis for the dose-based setpoints using URIand the dose targets shown on sheet NEW.c.Liquid monitors are based on multiples of the alarm ODCM setpoints. Nocalculations are performed.d.QEDPS is replaced by URI RASCAL in this revision 34.Spreadsheet "BKGD" calculatesacceptable variation in background for each instrument that would invalidate Table 3 and/or URI. [page 5.010]a.Fill in the reference for each background value, usually the calibration, or average historical data.b.Provide the analytical limit from the monitor detection efficiency and the minimum detectable level, using the same methodology for all gaseous detectors and the ODCM methodology for the liquid detectors. c.TEA and WEA monitor background have been updated to use engineering units of uCi/cc.5.Determine if the EALs fall within the ranges of the instruments, making adjustments if needed. The results are onsheet RANGE CHK page 5.011.6.Perform a sensitivity study of calibration range consistent with assumption 9 and +/-20%. The results are on sheet "CAL RANGE" pages 5.012-5.013.

18694 R4 ENERGY NORTHWESTMANUAL CALCULATION Page5.007Cont'd On Page 5.00 8Calculation No.NE-02-09-12Prepared By/DateLS Woosley3/8/15Verified by/DateJD Fisher3/10/15Revision No.

3REV.BAR[/][data]/[Dose]/[NE-02-09-12]

/[NE-02-09-12.003]

/NameSize Date/Time ModifiedCRCPermOwnerNE-02-09-12 003.xlsx199451 Mar 31 2015 09:34:44 09071 -rw-dcjfishe 18694 R4 ENERGY NORTHWESTMANUAL CALCULATION Page5.008Cont'd On Page5.009Calculation No.NE-02-09-12Prepared By/DateLS Woosley2/5/15Verified by/DateJD Fisher3/30/15Revision No.

3REV.

BARCalculation assembly directionsInsert files as follows:filenamePagesDescriptionNE-02-09-12 003 p1000 cover.docx 1.000Cover NE-02-09-12 003 p1005 summary.docx 1.001Summary NE-02-09-12 003 p1100 index.docx 1.100 Index NE-02-09-12 003 p1200 ver.docx 1.200-1.201Verification checklist NE-02-09-12 003 p1200 verifier comments.docx 1.202-1.207 Verification issue resolution NE-02-09-12 003 p1300 refs.docx 1.300-1.303References list NE-02-09-12 003 p1400 output.docx 1.400Output cross reference NE-02-09-12 003 p2000 results.docx 2.000-2.002Output summary / results NE-02-09-12 003 p3000 method.docx 3.000-3.001 Methodology NE-02-09-12 003 p5000 IO.docx5.000-5.002Calculation inputs and outputsNE-02-09-12 003 p5000 assumpt.docx5.003-5.007Calculation assumptions and method of calc constructionNE-02-09-12 003 p5000 calclist.docx5.008FILE LIST (this sheet)NE-02-09-12 003.xlsxsheet NEW5.009New input values from softwareNE-02-09-12 003.xlsxsheet BKGD5.010Calculated min level of detection with decade rounding to develop final analytical limitsNE-02-09-12 003.xlsxsheet RANGE CHK 5.011 Background range check NE-02-09-12 003.xlsxsheet CAL RANGE 5.012-5.013 Allowed +/-20% impact NE-02-09-12 003.xlsxsheet Table PC-15.014Final ODCM limits from UE/2NE-02-09-12 003.xlsxsheet FINAL 5.015 Final EALs with dose results using URI software NE-02-09-12 003.xlsxsheet PPM INPUTS 5.016 Calibration background ranges NE-02-09-12 003 AppA.pdf A Computer runs NE-02-09-12 003 AppC.pdf C Meteorology Sensitivity Study NE-02-09-12 003 AppD.pdfDChemistry Dept support calcs NE-02-09-12 003 AppH.pdfHHistorical licensing information NE-02-09-12 003 p1000 DMS.docxlastDMS reference document list 18694 R4 LS Woosley 3/25/15JD Fisher 3/26/15NE-02-09-12 003page 5.009NE-02-09-12 003.xlsx NEWNEW EALsCR MONITORINSTRUMENT EALINPUTBASISALARM TARGETREFERENCESdose goalin 3 hrsPRM-RR-3PRM-RE-1BUE5,000CPS2XODCM = 5 X HI ALARM , Hi =1000CPSD.2-5. page A.1mremALERT500,000CPS200XODCM = 500X HI ALARMpage A.4PRM-RR-3PRM-RE-1CALERT 404CPS10 MR/HR TEDE OR 50 MR/HR THY CDE10mrem/hr TEDEpage A.730 SAE 2100CPS100 MR/HR TEDE OR 500 MR/HR THY CDE100mrem/hr TEDEpage A.10300 GE1.95E+04CPS1000 MR/HR TEDE OR 5000 MR/HR THY CDE1000mrem/hr TEDEpage A.133000PRM-RR-3TEA-RIS-13UE1.00E-04Ci/cc2XODCM = 5X HI ALARM H=2.00E-05Ci/ccpage A.16; ref 37 p5.5 ALERT8.35E-04Ci/cc10 MR/HR TEDE OR 50 MR/HR THY CDE50mrem/hr THYpage A.19150 SAE8.35E-03Ci/cc100 MR/HR TEDE OR 500 MR/HR THY CDE500mrem/hr THYpage A.221500 GE8.35E-02Ci/cc1000 MR/HR TEDE OR 5000 MR/HR THY CDE5000mrem/hr THYpage A.2515000PRM-RR-3WEA-RIS-14UE1.98E-03Ci/cc2XODCM = 10X HI ALARM , H =1.98E-04Ci/ccpage A.28; ref 36 p 5.5 ALERT3.450E-03Ci/cc10 MR/HR TEDE OR 50 MR/HR THY CDE50mrem/hr THYpage A.31150 SAE3.450E-02Ci/cc100 MR/HR TEDE OR 500 MR/HR THY CDE500mrem/hr THYpage A.341500 GE3.450E-01Ci/cc1000 MR/HR TEDE OR 5000 MR/HR THY CDE5000mrem/hr THYpage A.3715000SW-RR-1SW-RIS-604UE92CPS2XODCM = 2X HI ALARM , Hi =alarm/0.837CPSref 42 ALERT9,240CPS200xODCM = 200x HI alarm/0.8SW-RR-2SW-RIS-605UE90CPS2XODCM = 2X HI ALARM , Hi = alarm/0.836CPSref 43 ALERT8,980CPS200xODCM = 200*hi alarm/0.8SW-RR-1FDR-RIS-606UE53CPS2XODCM = 2X HI-HI ALARM, Hi-HI =26CPSref 50 ALERT5,280CPS200xODCM = 200*HI-HI alarmPRM-RR-3TSW-RIS-5UE2.00E-05Ci/cc2XODCM = 2X Alert ALARM/0.8 , Alert =8.00E-06Ci/ccref 18, 19, 39ALERT2.00E-03Ci/cc200xODCM = 200*hi alarm/0.8 LS Woosley 3/25/15JD Fisher 3/26/15 NE-02-09-12 003page 5.010NE-02-09-12 003.xlsxBKGDANALYTICAL LIMIT DEVELOPMENTBACKGROUND DATA (1)draft (2) (3)

A.L.monitorminimumanalyticalALanalyticalLIQdetectiondetectionlimitdecadelimitMONITORNEW EAL draftbkgdREFfactorREFefficiencyMDL+bkgdw/ bkgdroundingFINALPRM-RE-1AshutdownCPS3300cps44581.01E+09CPS/uCi/cc3.57E+03cpsnormal opsCPS15000cps44581.01E+09CPS/uCi/cc1.56E+04cpsPRM-RE-1BUE5,000 CPS550cps54601.50E+06CPS/uCi/cc6.59E+02cps5.6E+03355506E+03ALERT500,000CPS550cps545.0E+0555005505E+05PRM-RE-1CALERT404CPS210cps55603.49E+01CPS/uCi/cc2.78E+02cps4.0E+0224044E+02SAE2100CPS210cps552.1E+03321002E+03GE19500CPS210cps552.0E+044195002E+04TEA-RIS-13UE1.00E-04Ci/cc46cpm 80802.15E+07cpm/uCi/cc2.40E-07Ci/cc1.02E-041.02E-04ALERT8.35E-04Ci/cc46cpm 808.35E-048.35E-04SAE8.35E-03Ci/cc46cpm 808.35E-038.35E-03GE8.35E-02Ci/cc46cpm80817.85E+03cpm/uCi/cc6.52E-04Ci/cc8.35E-028.35E-02WEA-RIS-14UE1.98E-03Ci/cc46cpm 79791.81E+07cpm/uCi/cc4.68E-07Ci/cc1.98E-031.98E-03ALERT3.45E-03Ci/cc46cpm 793.45E-033.45E-03SAE3.45E-02Ci/cc46cpm 793.45E-023.45E-02GE3.45E-01Ci/cc46cpm79828.58E+03cpm/uCi/cc6.19E-04Ci/cc3.45E-013.45E-01SW-RIS-604UE 92 CPS4.5cps422424.62E+06cps/uCi/cc1.44E+01cps971971E+02ALERT9,240 CPS4.5cps42200429245392451E+04SW-RIS-605UE 90 CPS5.5cps432434.49E+06cps/uCi/cc1.64E+01cps951951E+02ALERT8,980 CPS5.5cps43200438986389861E+04FDR-RIS-60 6 UE 53 CPS9cpm502583.15E+06cpm/uCi/cc2.30E+01cpm621627E+01ALERT5,280 CPS9cpm502005289352897E+03TSW-RIS-5UE2.00E-05Ci/cc300cpm392381.28E+08cpm/uCi/cc2.97E-06Ci/cc2.23E-05-52.2E-053E-05ALERT2.00E-03Ci/cc300cpm39200382.00E-03-22.0E-033E-03Effluent Concentration per 10CFR 20 [reference 51]formula changed from patternEC for Cs-1371.00E-06uCi/mlTEA-RIS-13 & WEA-RIS-14 AL selected to match display units of QEDPS output.

LS Woosley 3/27/15JD Fisher 3/30/15NE-02-09-12 003 page 5.011S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.003\NE-02-09-12 003.xlsxRANGE CHKNE-02-09-12range checking for analytical limit (1)Range decade per CR panelsCR MONITO RINSTRUMENTEAL from BKGDmin detect level (MDL)lowhighRefMDL met?within range?PRM-RR-3PRM-RE-1BUE60006.59E+02cps1.00E+011.00E+0628, 33YesOKALERT500000YesOKPRM-RR-3PRM-RE-1CALERT4002.78E+02cps1.00E+011.00E+0628, 34YesOKSAE2000 OKGE20000 OKPRM-RR-3TEA-RIS-13UE1.02E-042.40E-07Ci/cc1.00E-071.00E-0181, 90 (CH1)YesOKLow RangeALERT8.35E-04 OKLow RangeSAE8.35E-03 OKLow RangeGE8.35E-02 OKHigh RangeGE8.35E-026.52E-04Ci/cc1.00E-031.00E+0381, 90 (CH2)YesOKPRM-RR-3WEA-RIS-14UE1.98E-034.68E-07Ci/cc1.00E-061.00E-0182, 91 (CH1)YesOKLow RangeALERT3.45E-03 OKLow RangeSAE3.45E-02 OKLow RangeGE3.45E-01 BADHigh RangeGE3.45E-016.19E-04Ci/cc1.00E-031.00E+0382, 91 (CH2)YesOKSW-RR-1SW-RIS-604UE1E+021.44E+01cps1.00E-011.00E+06YesOKALERT1E+04 OKSW-RR-2SW-RIS-605UE1E+021.64E+01cps1.00E-011.00E+06YesOKALERT1E+04 OKSW-RR-1FDR-RIS-606UE7E+01 2.30E+01cpm1.00E-011.00E+06YesOKALERT7E+03 OKPRM-RR-3TSW-RIS-5UE3E-052.97E-06Ci/cc1.00E-081.00E-02YesOKALERT3E-03 OK LS Woosley 3/29/15 JD Fisher 3/30/15 NE-02-09-12 003 page 5.12S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.003\NE-02-09-12 003.xlsx cal rangeNE-02-09-12SENSITIVITY STUDY --explore range of calibration factors that can be toleratedALERT10 MR/HR TEDE OR 50 MR/HR THY CDECAL RANGEAlternate solution investigation using Assumption 9SAE100 MR/HR TEDE OR 500 MR/HR THY CDEThis is the method that EP prefers, but there are issues (see last column)GE1000 MR/HR TEDE OR 5000 MR/HR THY CDEDose-based EALs onlyHIDE?MONITOREAL input rangeinput value w/calCHECK variationsLLD @ bkgdUnitsreferencegoal mrem/hrUri dose result per 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months sURI inputdose-based background checkCheckURI runISSUESPRM-RE-1Cfrom AL on BKGD sheet =400ALERT EAL400CPSLLD =67.5from BKGD sheet >BKGD210CPSLLD @ bkgd277.5CPS 80%12.035.935.94.38E+02cpsmin bkgd >172233okA.9710.029.929.9mrem TEDE/3hr4.00E+02cpsnorm bkgd >210278okA.49 120%8.023.924.03.62E+02cpsmax bkgd >248321okA.100PRM-RE-1Cfrom AL on BKGD sheet =2000SAE EAL2000CPSLLD =67.5from BKGD sheet >BKGD210CPSLLD @ bkgd277.5CPS 80%112.8338338.02.36E+03cpsmin bkgd >-1480not okA.1030 min bkgd94.0282282.0mrem TEDE/3hr2.00E+03cpsnorm bkgd >210278okA.52 120%75.2226225.01.64E+03cpsmax bkgd >568679okA.106PRM-RE-1Cfrom AL on BKGD sheet =

20000GE EAL20000CPSLLD =67.5from BKGD sheet >BKGD210CPSLLD @ bkgd277.5CPS 80%1248374437502.40E+04cpsmin bkgd >-37480not okA.1090 min bkgd 104031203120mrem TEDE/3hr2.00E+04cpsnorm bkgd >210278okA.55 120%832249624901.60E+04cpsmax bkgd >41684469okA.112TEA-RIS-13from AL on BKGD sheet =8.35E-04ALERT EAL8.35.E-04Ci/ccLLD =32cpmLow Range Detectorfrom BKGD sheet >BKGD46cpmLLD @ bkgd78cpmCi/cc 80%60.01801801.00E-03Ci/ccmin bkgd >-35350.00E+00not okA.1150 min bkgd50.0150150mrem/hr CDE/3h r8.35E-04Ci/ccnorm bkgd >463.61E-06okA.61 120%40.01201206.68E-04Ci/ccmax bkgd >36271.82E-04okA.118TEA-RIS-13from AL on BKGD sheet =8.35E-03SAE EAL8.35.E-03Ci/ccLLD =32cpmLow Range Detectorfrom BKGD sheet >BKGD46cpmLLD @ bkgd78cpmCi/cc 80%600180018001.00E-02Ci/ccmin bkgd >-358500.00E+00not okA.1210 min bkgd 50015001500mrem/hr CDE/3h r8.35E-03Ci/ccnorm bkgd >463.61E-06okA.64 120%400120012106.68E-03Ci/ccmax bkgd >359421.71E-03okA.124 LS Woosley 3/29/15 JD Fisher 3/30/15 NE-02-09-12 003 page 5.13S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.003\NE-02-09-12 003.xlsx cal rangeTEA-RIS-13from AL on BKGD sheet =8.35E-02GE EAL8.35E-02Ci/ccLLD =32cpmLow Range Detectorfrom BKGD sheet >BKGD46cpmLLD @ bkgd78cpmCi/cc 80%600018000180001.00E-01Ci/ccmin bkgd >-3589950.00E+00not okA.1270 min bkgd 50001500015000mrem/hr CDE/3h r8.35E-02Ci/ccnorm bkgd >463.61E-06okA.67 120%400012000121006.68E-02Ci/ccmax bkgd >3590871.68E-02okA.130from AL on BKGD sheet =8.94E-02GE EAL8.94E-02Ci/ccLLD =32cpmHigh Range Detectorfrom BKGD sheet >BKGD46cpmLLD @ bkgd78cpmCi/cc 80%1.06E-01Ci/ccmin bkgd >-850.00E+00not okEstimatedmrem/hr CDE/3h r8.94E-02Ci/ccnorm bkgd >469.89E-03okcan't 120%7.27E-02Ci/ccmax bkgd >1773.05E-02oktestWEA-RIS-14from AL on BKGD sheet =3.45E-03ALERT EAL3.45E-03Ci/ccLLD =32cpmLow Range Detectorfrom BKGD sheet >BKGD46cpmLLD @ bkgd78cpmCi/cc 80%60.01801804.14E-03Ci/ccmin bkgd >-124340.00E+00not okA.1330 min bkgd50.0150150mrem/hr CDE/3h r3.45E-03Ci/ccnorm bkgd >464.29E-06okA.73 120%40.01201202.76E-03Ci/ccmax bkgd >125267.21E-04okA.136WEA-RIS-14from AL on BKGD sheet =3.45E-02SAE EAL3.45E-02Ci/ccLLD =32Low Range Detectorfrom BKGD sheet >BKGD46cpmLLD @ bkgd78Ci/cc 80%600180018004.14E-02Ci/ccmin bkgd >-1248350.00E+00not okA.1390 min bkgd 50015001500mrem/hr CDE/3h r3.45E-02Ci/ccnorm bkgd >464.29E-06okA.76 120%400120012002.76E-02Ci/ccmax bkgd >1249276.99E-03okA.142WEA-RIS-14from AL on BKGD sheet =3.45E-01GE EAL3.45E-01Ci/ccLLD =32Low Range Detectorfrom BKGD sheet >BKGD46cpmLLD @ bkgd78Ci/cc 80%600018000180004.14E-01Ci/ccmin bkgd >-12488450.00E+00not okA.1450 min bkgd 50001500015000mrem/hr CDE/3h r3.45E-01Ci/ccnorm bkgd >464.29E-06okA.79 120%400012000120002.76E-01Ci/ccmax bkgd >12489376.93E-02okA.148from AL on BKGD sheet =3.50E-01GE EAL3.50E-01Ci/ccLLD =

32High Range Detectorfrom BKGD sheet >BKGD46cpmLLD @ bkgd78Ci/cc 80%4.19E-01Ci/ccmin bkgd >-5460.00E+00not okEstimatedmrem/hr CDE/3h r3.50E-01Ci/ccnorm bkgd >469.04E-03okA.79can't 120%2.81E-01Ci/ccmax bkgd >6388.81E-02oktestmethod:1. Use the reference URI run from sheet FINAL to establish the dose goal.

2. change URI input by 80% and record the dose value for the target input from step 1.

3. change URI input by 120% and record the dose value for the target input from step 1.

4. Find the input values that result in those dose values from steps 2 and 3. Record input in center column.

5. check EAL values found in step 4 for LLD and drift to see if there is a margin problem with that instrument. Check sum = -1*(value from step 4)+EAL+BKGD If check sum <= LLD@ BKGD then not ok else okrepresents margin for drift/ cal errors beyond LLD6. establish EAL value as target dose value in the middle row.

LS Woosley 3/29/15JD Fisher 3/30/15NE-02-09-12 revision 003page 5.014S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.003\NE-02-09-12 003.xlsxNE-02-09-12 003.xlsx Table PC-1ODCM RFO Offsite Radioactivity Release LimitsUE valueURI caseUE/2 valueURI casePRM-RE-1B6.00E+03cpsA.823.0E+03cpsA.88TEA-RIS-131.02E-04uCi/ccA.585.1E-05uCi/ccA.91WEA-RIS-141.98E-03uCi/ccA.709.9E-04uCi/ccA.94TM-2120 Table PC-1 LS Woosley 3/29/15JD Fisher 3/30/15 NE-02-09-12 003 page 5.015NE-02-09-12 003.xlsx FINAL NE-02-09-12EMERGENCY PLAN Table 3 for PPM 13.1.1 URI runCR MONITORINSTRUMENT EAL BASISactual hourly dose rate at EALREFERENCEPRM-RR-3PRM-RE-1BUE 6,000 CPS2XODCM = 5 X HI ALARM 0.0mrem TEDEA.82N/A500,000 CPS200XODCM = 500X HI ALARM0.6mrem/hr TEDEA.85PRM-RR-3PRM-RE-1CALERT400 CPS10 MR/HR TEDE OR 50 MR/HR THY CDE10mrem/hr TEDEA.49SAE2,000 CPS100 MR/HR TEDE OR 500 MR/HR THY CDE94mrem/hr TEDEA.52GE20,000 CPS1000 MR/HR TEDE OR 5000 MR/HR THY CDE1040mrem/hr TEDEA.55PRM-RR-3TEA-RIS-13UE1.02E-04Ci/cc2XODCM = 5X HI ALARM6mrem/hr THYA.58ALERT8.35E-04Ci/cc10 MR/HR TEDE OR 50 MR/HR THY CDE50mrem/hr THYA.61SAE8.35E-03Ci/cc100 MR/HR TEDE OR 500 MR/HR THY CDE500mrem/hr THYA.64GE8.35E-02Ci/cc1000 MR/HR TEDE OR 5000 MR/HR THY CDE5000mrem/hr THYA.67PRM-RR-3WEA-RIS-14UE1.98E-03Ci/cc2XODCM = 10X HI ALARM 29mrem/hr THYA.70ALERT3.45E-03Ci/cc10 MR/HR TEDE OR 50 MR/HR THY CDE50mrem/hr THY A.73SAE3.45E-02Ci/cc100 MR/HR TEDE OR 500 MR/HR THY CDE500mrem/hr THY A.76GE3.45E-01Ci/cc1000 MR/HR TEDE OR 5000 MR/HR THY CDE5000mrem/hr THY A.79SW-RR-1SW-RIS-604UE1E+02CPS2XODCM = 2X HI ALARM , Hi =alarm/0.8ALERT1E+04CPS200xODCM = 200x HI alarm/0.8SW-RR-2SW-RIS-605UE1E+02CPS2XODCM = 2X HI ALARM , Hi = alarm/0.8ALERT1E+04CPS200xODCM = 200*hi alarm/0.8SW-RR-1FDR-RIS-606UE7E+01CPS2XODCM = 2X HI-HI ALARMALERT7E+03CPS200xODCM = 200*HI-HI alarmPRM-RR-3TSW-RIS-5UE3.E-05Ci/cc2XODCM = 2X Alert ALARM/0.8ALERT3.E-03Ci/cc200xODCM = 200*hi alarm/0.8change from patternchanged in this revision LS Woosley 3/29/15JD Fisher 3/30/15NE-02-09-12 003 Page 5.016S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.003\NE-02-09-12 003.xlsxNE-02-09-12 003.xlsx PPM INPUTNE-02-09-12PPM INPUTS

SUMMARY

OF RESULTSfrom sheet CAL RANGEALLOWED BACKGROUND RANGECR MONITORINSTRUMENTMINNORMALMAXPRM-RR-3PRM-RE-1BUE CPS ALERTCPSPRM-RR-3PRM-RE-1CALERTCPS172210248 SAE CPS GECPSPRM-RR-3TEA-RIS-13 CPM0.046150Channel1 UECi/ccChannel2 GECi/cc 0.05.86E-031.91E-02Channel3Ci/ccBkg okPRM-RR-3WEA-RIS-14 CPM 0465 3 3Channel1 UECi/ccChannel2 GECi/cc0.00E+005.36E-036.21E-02Channel3Ci/ccNo value cited means there is no limitation on background for that instrumentBackground is more constrained than value presented on sheet CAL RANGE.NE-02-09-12PPM INPUTS

SUMMARY

OF RESULTSfrom sheet FINALINSTRUMENT BASIS2xODCM +Bkg1xODCM +Bkg REFERENCEPRM-RE-1B3.0E+03CPSUE / 265503550cpsD.90, D.103TEA-RIS-135.1E-05Ci/ccUE / 21.02E-045.22E-05Ci/ccD.94, D.107WEA-RIS-149.9E-04Ci/ccUE / 21.98E-039.92E-04Ci/ccD.98, D.111PPM 5.2.1 & SAG2 Table 27 InputTABLE 27 LIMITODCM RFO Offsite Radioactivity Release Limits ENERGY NORTHWESTMANUAL CALCULATION Page A.0Cont'd On Page A.1Calculation No.NE-02-09-12Prepared By/DateLS Woosley3/29/15Verified by/DateJD Fisher3/30/15Revision No.

3REV.

BARAppendix ACOMPUTER RUNS WITH URIDescription Pages Notes Cases from spreadsheet page NEW A.1 - A.39 Initial values Not referenced A.40 - A.48 skip Cases from spreadsheet page FINAL A.49 - A.87 Final values Cases from spreadsheet page PC-1 A.88 - A.96 Procedure values Cases from spreadsheet page cal range A.97 - A.150 Calibration range checking 18694 R4 Dose AssessmentColumbia Generating StationMonday, March 09, 2015 13:43Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (INT)Readings: 5.00E+03 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+001.50.00E+000.00E+000.00E+000.00E+000.00E+000.00E+002.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 3.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 4.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 5.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 7.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+0010.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03092015 134354.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate6.26E-08 (0.0%)Iodine1.53E-06 (0.0%)Noble Gas6.30E-03 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.1___________________________________________ByJohnD.Fisherat12:53pm,Mar30,2015 Isotopic Release RatesColumbia Generating StationMonday, March 09, 2015 13:43Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.15E-05Kr-85m2.56E-04Kr-875.10E-04Kr-887.05E-04Xe-131m1.51E-05Xe-1332.25E-03Xe-133m7.13E-05Xe-1355.89E-04Xe-1381.89E-03Iodines in Ci/secI-1311.77E-07I-1322.57E-07I-1333.60E-07I-1343.96E-07I-1353.44E-07Particulates in Ci/secCs-1343.11E-08Cs-1369.89E-09Cs-1372.16E-08Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.2 Additional Meteorological InputsColumbia Generating StationMonday, March 09, 2015 13:43CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (INT) reads in units of CPS- Conversion Factor: 1.5000E+12- Background Subtract: 5.5000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - MilesUnable To Calculate1.005 - MilesUnable To Calculate1.0010 - MilesUnable To Calculate1.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.3 Dose AssessmentColumbia Generating StationMonday, March 09, 2015 13:50Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (INT)Readings: 5.00E+05 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.8.37E-011.66E+000.00E+001.13E-011.77E+003.87E-011.56.96E-011.34E+000.00E+001.21E-011.47E+003.10E-012.05.36E-011.00E+000.00E+001.32E-011.14E+002.41E-01 3.03.45E-016.27E-010.00E+000.00E+006.27E-011.60E-01 4.03.34E-015.96E-010.00E+000.00E+005.96E-011.33E-01 5.02.68E-014.71E-010.00E+000.00E+004.71E-011.10E-01 7.01.57E-012.84E-010.00E+000.00E+002.84E-010.00E+0010.01.42E-012.60E-010.00E+000.00E+002.60E-010.00E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03092015 135028.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate7.02E-06 (0.0%)Iodine1.72E-04 (0.0%)Noble Gas7.07E-01 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.4____________________________________________ByJohnD.Fisherat12:53pm,Mar30,2015 Isotopic Release RatesColumbia Generating StationMonday, March 09, 2015 13:50Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.29E-03Kr-85m2.87E-02Kr-875.72E-02Kr-887.91E-02Xe-131m1.70E-03Xe-1332.53E-01Xe-133m8.01E-03Xe-1356.61E-02Xe-1382.12E-01Iodines in Ci/secI-1311.99E-05I-1322.89E-05I-1334.04E-05I-1344.45E-05I-1353.86E-05Particulates in Ci/secCs-1343.49E-06Cs-1361.11E-06Cs-1372.42E-06Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.5 Additional Meteorological InputsColumbia Generating StationMonday, March 09, 2015 13:50CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (INT) reads in units of CPS- Conversion Factor: 1.5000E+12- Background Subtract: 5.5000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles1.001.005 - Miles1.001.0010 - Miles1.001.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.6 Dose AssessmentColumbia Generating StationMonday, March 09, 2015 09:33Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (HI)Readings: 4.04E+02 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.1.40E+012.76E+011.05E+001.89E+003.05E+016.47E+001.51.16E+012.24E+011.08E+002.03E+002.56E+015.17E+002.08.96E+001.68E+011.17E+002.20E+002.02E+014.03E+00 3.05.76E+001.05E+017.02E-011.28E+001.25E+012.66E+00 4.05.56E+009.95E+006.79E-011.20E+001.18E+012.23E+00 5.04.48E+007.87E+005.93E-011.01E+009.47E+001.83E+00 7.02.63E+004.73E+003.84E-016.15E-015.73E+001.16E+0010.02.38E+004.35E+003.61E-014.72E-015.18E+001.17E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03092015 093303.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate1.17E-04 (0.0%)Iodine2.87E-03 (0.0%)Noble Gas1.18E+01 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.7___________________________________________PByJohnD.Fisherat12:52pm,Mar30,2015 Isotopic Release RatesColumbia Generating StationMonday, March 09, 2015 09:33Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-852.16E-02Kr-85m4.79E-01Kr-879.56E-01Kr-881.32E+00Xe-131m2.84E-02Xe-1334.22E+00Xe-133m1.34E-01Xe-1351.10E+00Xe-1383.54E+00Iodines in Ci/secI-1313.32E-04I-1324.82E-04I-1336.74E-04I-1347.42E-04I-1356.44E-04Particulates in Ci/secCs-1345.83E-05Cs-1361.85E-05Cs-1374.04E-05Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.8 Additional Meteorological InputsColumbia Generating StationMonday, March 09, 2015 09:33CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (HI) reads in units of CPS- Conversion Factor: 3.4900E+07- Background Subtract: 2.1000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.930.945 - Miles0.930.9410 - Miles0.920.93Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.9 Dose AssessmentColumbia Generating StationWednesday, March 25, 2015 11:47Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (HI)Readings: 2.10E+03 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.1.36E+022.69E+021.03E+011.84E+012.98E+026.29E+011.51.13E+022.18E+021.06E+011.98E+012.49E+025.03E+012.08.76E+011.63E+021.15E+012.15E+011.96E+023.92E+01 3.05.60E+011.02E+026.85E+001.24E+011.21E+022.59E+01 4.05.44E+019.71E+016.63E+001.17E+011.15E+022.17E+01 5.04.36E+017.68E+015.78E+009.86E+009.24E+011.78E+01 7.02.56E+014.62E+013.75E+006.00E+005.60E+011.13E+0110.02.32E+014.24E+013.52E+004.61E+005.05E+011.14E+01Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03252015 114708.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Site Area Emergency * * *Release Rates (Ci / sec)Particulate1.14E-03 (0.0%)Iodine2.80E-02 (0.0%)Noble Gas1.15E+02 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.10___________________________________________Pa gByJohnD.Fisherat12:52pm,Mar30,2015 Isotopic Release RatesColumbia Generating StationWednesday, March 25, 2015 11:47Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-852.10E-01Kr-85m4.67E+00Kr-879.31E+00Kr-881.29E+01Xe-131m2.76E-01Xe-1334.11E+01Xe-133m1.30E+00Xe-1351.07E+01Xe-1383.45E+01Iodines in Ci/secI-1313.23E-03I-1324.70E-03I-1336.56E-03I-1347.23E-03I-1356.27E-03Particulates in Ci/secCs-1345.68E-04Cs-1361.80E-04Cs-1373.94E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.11 Additional Meteorological InputsColumbia Generating StationWednesday, March 25, 2015 11:47CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (HI) reads in units of CPS- Conversion Factor: 3.4900E+07- Background Subtract: 2.1000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.930.945 - Miles0.930.9410 - Miles0.920.93Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.12 Dose AssessmentColumbia Generating StationWednesday, March 25, 2015 11:57Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:01Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (HI)Readings: 1.95E+04 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.1.38E+032.71E+031.04E+021.83E+023.00E+036.52E+021.51.14E+032.21E+031.07E+021.97E+022.51E+035.21E+022.08.84E+021.66E+031.16E+022.14E+021.99E+034.06E+023.05.68E+021.03E+036.92E+011.24E+021.23E+032.69E+024.05.48E+029.84E+026.70E+011.16E+021.17E+032.25E+024.035.48E+029.84E+026.70E+011.16E+021.17E+032.25E+025.04.40E+027.79E+025.85E+019.81E+019.36E+021.84E+027.02.60E+024.69E+023.80E+015.98E+015.67E+021.17E+0210.02.36E+024.32E+023.58E+014.60E+015.14E+021.18E+02Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03252015 115750.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miPAGs Exceeded in Designated Areas* *

Classification: General Emergency * * *Release Rates (Ci / sec)Particulate1.18E-02 (0.0%)Iodine2.89E-01 (0.0%)Noble Gas1.17E+03 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.13___________________________________________PByJohnD.Fisherat12:58pm,Mar30,2015 Isotopic Release RatesColumbia Generating StationWednesday, March 25, 2015 11:57Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-852.18E+00Kr-85m4.83E+01Kr-879.57E+01Kr-881.33E+02Xe-131m2.87E+00Xe-1334.26E+02Xe-133m1.35E+01Xe-1351.11E+02Xe-1383.41E+02Iodines in Ci/secI-1313.35E-02I-1324.85E-02I-1336.80E-02I-1347.40E-02I-1356.49E-02Particulates in Ci/secCs-1345.89E-03Cs-1361.87E-03Cs-1374.08E-03Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.14 Additional Meteorological InputsColumbia Generating StationWednesday, March 25, 2015 11:57CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (HI) reads in units of CPS- Conversion Factor: 3.4900E+07- Background Subtract: 2.1000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.930.945 - Miles0.930.9410 - Miles0.920.93Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.15 Dose AssessmentColumbia Generating StationMonday, March 09, 2015 09:36Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Turb Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = < 2 HoursRW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Turb BldgReadings: 1.00E-04 uCi/ccFlowrate: 360000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.0.00E+000.00E+006.96E-012.87E-019.83E-011.76E+011.50.00E+000.00E+005.51E-012.26E-017.77E-011.39E+012.00.00E+000.00E+004.15E-011.69E-015.84E-011.05E+01 3.00.00E+000.00E+002.75E-011.06E-013.81E-016.96E+00 4.00.00E+000.00E+002.14E-010.00E+002.14E-015.41E+00 5.00.00E+000.00E+001.77E-010.00E+001.77E-014.47E+00 7.00.00E+000.00E+001.11E-010.00E+001.11E-012.83E+0010.00.00E+000.00E+000.00E+000.00E+000.00E+002.36E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03092015 093601.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate2.62E-04 (1.5%)Iodine6.41E-03 (37.3%)Noble Gas1.05E-02 (61.1%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.16___________________________________________PByJohnD.Fisherat12:58pm,Mar30,2015 NE-02-09-12 Rev 3, pa g e A.17 NE-02-09-12 Rev 3, pa g e A.18 Dose AssessmentColumbia Generating StationThursday, March 26, 2015 18:06Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Turb Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = < 2 HoursRW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Turb BldgReadings: 8.35E-04 uCi/ccFlowrate: 360000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.4.72E-015.88E-015.93E+002.44E+008.96E+001.50E+021.53.68E-014.57E-014.69E+001.92E+007.07E+001.19E+022.02.58E-013.18E-013.54E+001.43E+005.29E+008.94E+01 3.01.78E-012.25E-012.34E+009.02E-013.47E+005.93E+01 4.01.36E-011.82E-011.82E+006.85E-012.69E+004.61E+01 5.01.14E-011.48E-011.50E+005.59E-012.21E+003.81E+01 7.00.00E+000.00E+009.49E-013.46E-011.30E+002.41E+0110.00.00E+000.00E+007.92E-012.58E-011.05E+002.01E+01Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03262015 180603.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate2.23E-03 (1.5%)Iodine5.46E-02 (37.3%)Noble Gas8.97E-02 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.19______________________________________________PByJohnD.Fisherat12:59pm,Mar30,2015 Isotopic Release RatesColumbia Generating StationThursday, March 26, 2015 18:06Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.64E-04Kr-85m3.64E-03Kr-877.26E-03Kr-881.00E-02Xe-131m2.15E-04Xe-1333.20E-02Xe-133m1.01E-03Xe-1358.38E-03Xe-1382.69E-02Iodines in Ci/secI-1316.30E-03I-1329.16E-03I-1331.28E-02I-1341.41E-02I-1351.22E-02Particulates in Ci/secCs-1341.11E-03Cs-1363.52E-04Cs-1377.67E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.20 Additional Meteorological InputsColumbia Generating StationThursday, March 26, 2015 18:06CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 36 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Turb Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.1400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.000.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.21 Dose AssessmentColumbia Generating StationThursday, March 26, 2015 18:06Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Turb Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = < 2 HoursRW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Turb BldgReadings: 8.35E-03 uCi/ccFlowrate: 360000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.4.72E+005.90E+005.94E+012.45E+018.98E+011.50E+031.53.69E+004.60E+004.70E+011.93E+017.10E+011.19E+032.02.60E+003.19E+003.55E+011.43E+015.30E+018.96E+02 3.01.79E+002.26E+002.35E+019.04E+003.48E+015.94E+02 4.01.37E+001.82E+001.83E+016.87E+002.69E+014.62E+02 5.01.14E+001.48E+001.51E+015.60E+002.22E+013.82E+02 7.06.76E-019.06E-019.51E+003.47E+001.39E+012.41E+0210.05.08E-017.12E-017.93E+002.58E+001.12E+012.02E+02Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03262015 180640.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Site Area Emergency * * *Release Rates (Ci / sec)Particulate2.23E-02 (1.5%)Iodine5.47E-01 (37.3%)Noble Gas8.99E-01 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.22___________________________________________Pa geByJohnD.Fisherat12:59pm,Mar30,2015 Isotopic Release RatesColumbia Generating StationThursday, March 26, 2015 18:06Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.64E-03Kr-85m3.65E-02Kr-877.27E-02Kr-881.01E-01Xe-131m2.16E-03Xe-1333.21E-01Xe-133m1.02E-02Xe-1358.40E-02Xe-1382.70E-01Iodines in Ci/secI-1316.32E-02I-1329.18E-02I-1331.28E-01I-1341.41E-01I-1351.23E-01Particulates in Ci/secCs-1341.11E-02Cs-1363.52E-03Cs-1377.69E-03Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.23 Additional Meteorological InputsColumbia Generating StationThursday, March 26, 2015 18:06CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 36 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Turb Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.1400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.080.27Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.24 Dose AssessmentColumbia Generating StationThursday, March 26, 2015 18:07Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Turb Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = < 2 HoursRW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Turb BldgReadings: 8.35E-02 uCi/ccFlowrate: 360000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.4.72E+015.90E+015.94E+022.45E+028.99E+021.50E+041.53.69E+014.60E+014.70E+021.93E+027.10E+021.19E+042.02.60E+013.19E+013.55E+021.43E+025.30E+028.96E+033.01.79E+012.26E+012.35E+029.04E+013.48E+025.94E+033.351.61E+012.05E+012.04E+027.79E+013.03E+025.17E+034.01.37E+011.82E+011.83E+026.87E+012.70E+024.62E+035.01.14E+011.48E+011.51E+025.60E+012.22E+023.82E+03 7.06.76E+009.06E+009.51E+013.47E+011.39E+022.41E+0310.05.08E+007.12E+007.93E+012.58E+011.12E+022.02E+03Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03262015 180709.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miPAGs Exceeded in Designated Areas* *

Classification: General Emergency * * *Release Rates (Ci / sec)Particulate2.23E-01 (1.5%)Iodine5.47E+00 (37.3%)Noble Gas8.99E+00 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.25___________________________________________PaByJohnD.Fisherat12:59pm,Mar30,2015 Isotopic Release RatesColumbia Generating StationThursday, March 26, 2015 18:07Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.64E-02Kr-85m3.65E-01Kr-877.28E-01Kr-881.01E+00Xe-131m2.16E-02Xe-1333.21E+00Xe-133m1.02E-01Xe-1358.40E-01Xe-1382.70E+00Iodines in Ci/secI-1316.32E-01I-1329.18E-01I-1331.28E+00I-1341.41E+00I-1351.23E+00Particulates in Ci/secCs-1341.11E-01Cs-1363.53E-02Cs-1377.69E-02Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.26 Additional Meteorological InputsColumbia Generating StationThursday, March 26, 2015 18:07CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 36 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Turb Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.1400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.080.27Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.27 Dose AssessmentColumbia Generating StationMonday, March 09, 2015 09:38Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 1.98E-03 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.2.70E-013.37E-013.40E+001.40E+005.13E+008.59E+011.52.10E-012.60E-012.70E+001.11E+004.07E+006.82E+012.01.47E-011.80E-012.02E+008.16E-013.01E+005.10E+01 3.01.01E-011.30E-011.30E+004.91E-011.93E+003.30E+01 4.00.00E+001.03E-011.05E+003.83E-011.53E+002.65E+01 5.00.00E+000.00E+008.18E-012.94E-011.11E+002.07E+01 7.00.00E+000.00E+005.16E-011.81E-016.97E-011.31E+0110.00.00E+000.00E+003.85E-011.21E-015.06E-019.80E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03092015 093830.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate1.23E-03 (1.5%)Iodine3.01E-02 (37.2%)Noble Gas4.95E-02 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.28____________________________________________PByJohnD.Fisherat1:00pm,Mar30,2015 Isotopic Release RatesColumbia Generating StationMonday, March 09, 2015 09:38Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-859.06E-05Kr-85m2.01E-03Kr-874.01E-03Kr-885.54E-03Xe-131m1.19E-04Xe-1331.77E-02Xe-133m5.60E-04Xe-1354.63E-03Xe-1381.49E-02Iodines in Ci/secI-1313.48E-03I-1325.06E-03I-1337.06E-03I-1347.78E-03I-1356.75E-03Particulates in Ci/secCs-1346.11E-04Cs-1361.94E-04Cs-1374.24E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.29 Additional Meteorological InputsColumbia Generating StationMonday, March 09, 2015 09:38CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.000.0010 - Miles0.000.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.30 Dose AssessmentColumbia Generating StationWednesday, March 25, 2015 13:04Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 3.45E-03 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.4.71E-015.87E-015.93E+002.44E+008.96E+001.50E+021.53.66E-014.55E-014.70E+001.93E+007.09E+001.19E+022.02.56E-013.13E-013.52E+001.42E+005.25E+008.89E+01 3.01.77E-012.27E-012.28E+008.58E-013.36E+005.76E+01 4.01.40E-011.80E-011.83E+006.69E-012.68E+004.62E+01 5.01.04E-011.38E-011.43E+005.13E-012.08E+003.61E+01 7.00.00E+000.00E+009.00E-013.16E-011.22E+002.28E+0110.00.00E+000.00E+006.72E-012.09E-018.82E-011.71E+01Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03252015 130405.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate2.14E-03 (1.5%)Iodine5.25E-02 (37.2%)Noble Gas8.63E-02 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.31____________________________________________PaByJohnD.Fisherat1:00pm,Mar30,2015 Isotopic Release RatesColumbia Generating StationWednesday, March 25, 2015 13:04Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.58E-04Kr-85m3.50E-03Kr-876.99E-03Kr-889.65E-03Xe-131m2.07E-04Xe-1333.08E-02Xe-133m9.77E-04Xe-1358.06E-03Xe-1382.59E-02Iodines in Ci/secI-1316.07E-03I-1328.81E-03I-1331.23E-02I-1341.36E-02I-1351.18E-02Particulates in Ci/secCs-1341.07E-03Cs-1363.38E-04Cs-1377.38E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.32 Additional Meteorological InputsColumbia Generating StationWednesday, March 25, 2015 13:04CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.000.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.33 Dose AssessmentColumbia Generating StationWednesday, March 25, 2015 13:04Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 3.45E-02 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.4.71E+005.88E+005.93E+012.45E+018.96E+011.50E+031.53.67E+004.55E+004.70E+011.93E+017.09E+011.19E+032.02.56E+003.13E+003.52E+011.42E+015.25E+018.89E+02 3.01.77E+002.27E+002.28E+018.58E+003.36E+015.76E+02 4.01.40E+001.81E+001.83E+016.69E+002.68E+014.62E+02 5.01.04E+001.38E+001.43E+015.14E+002.08E+013.61E+02 7.06.32E-018.40E-019.00E+003.17E+001.30E+012.28E+0210.04.24E-015.89E-016.72E+002.09E+009.41E+001.71E+02Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03252015 130426.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Site Area Emergency * * *Release Rates (Ci / sec)Particulate2.14E-02 (1.5%)Iodine5.26E-01 (37.3%)Noble Gas8.63E-01 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.34___________________________________________PByJohnD.Fisherat1:00pm,Mar30,2015 Isotopic Release RatesColumbia Generating StationWednesday, March 25, 2015 13:04Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.58E-03Kr-85m3.51E-02Kr-876.99E-02Kr-889.66E-02Xe-131m2.07E-03Xe-1333.09E-01Xe-133m9.78E-03Xe-1358.07E-02Xe-1382.59E-01Iodines in Ci/secI-1316.07E-02I-1328.82E-02I-1331.23E-01I-1341.36E-01I-1351.18E-01Particulates in Ci/secCs-1341.07E-02Cs-1363.39E-03Cs-1377.39E-03Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.35 Additional Meteorological InputsColumbia Generating StationWednesday, March 25, 2015 13:04CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.080.27Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.36 Dose AssessmentColumbia Generating StationWednesday, March 25, 2015 13:04Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 3.45E-01 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.4.71E+015.88E+015.93E+022.45E+028.96E+021.50E+041.53.67E+014.55E+014.70E+021.93E+027.09E+021.19E+042.02.56E+013.13E+013.52E+021.42E+025.25E+028.89E+033.01.77E+012.27E+012.28E+028.58E+013.36E+025.76E+033.351.54E+012.02E+012.03E+027.57E+012.99E+025.14E+034.01.40E+011.81E+011.83E+026.69E+012.68E+024.62E+035.01.04E+011.38E+011.43E+025.14E+012.08E+023.61E+03 7.06.32E+008.40E+009.00E+013.17E+011.30E+022.28E+0310.04.24E+005.89E+006.72E+012.09E+019.41E+011.71E+03Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03252015 130448.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miPAGs Exceeded in Designated Areas* *

Classification: General Emergency * * *Release Rates (Ci / sec)Particulate2.14E-01 (1.5%)Iodine5.26E+00 (37.3%)Noble Gas8.64E+00 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.37____________________________________________PByJohnD.Fisherat1:01pm,Mar30,2015 Isotopic Release RatesColumbia Generating StationWednesday, March 25, 2015 13:04Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.58E-02Kr-85m3.51E-01Kr-876.99E-01Kr-889.66E-01Xe-131m2.07E-02Xe-1333.09E+00Xe-133m9.78E-02Xe-1358.07E-01Xe-1382.59E+00Iodines in Ci/secI-1316.07E-01I-1328.82E-01I-1331.23E+00I-1341.36E+00I-1351.18E+00Particulates in Ci/secCs-1341.07E-01Cs-1363.39E-02Cs-1377.39E-02Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.38 Additional Meteorological InputsColumbia Generating StationWednesday, March 25, 2015 13:04CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.080.27Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.39 Dose AssessmentColumbia Generating StationMonday, March 09, 2015 14:54Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (INT)Readings: 3.00E+03 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+001.50.00E+000.00E+000.00E+000.00E+000.00E+000.00E+002.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 3.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 4.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 5.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 7.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+0010.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03092015 145400.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate3.44E-08 (0.0%)Iodine8.45E-07 (0.0%)Noble Gas3.47E-03 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.40 0 0.0 0E++0 0 E++0 0 0 0 0.0 0 E+0+0 0+0 00 0.0 00 E+00 0 E+0 0 0 0.0.0 0E+0 0 0 E++0 0 0 Isotopic Release RatesColumbia Generating StationMonday, March 09, 2015 14:54Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-856.35E-06Kr-85m1.41E-04Kr-872.81E-04Kr-883.88E-04Xe-131m8.33E-06Xe-1331.24E-03Xe-133m3.93E-05Xe-1353.24E-04Xe-1381.04E-03Iodines in Ci/secI-1319.75E-08I-1321.42E-07I-1331.98E-07I-1342.18E-07I-1351.89E-07Particulates in Ci/secCs-1341.71E-08Cs-1365.44E-09Cs-1371.19E-08Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.41 1.4 4 2E E-0 7 Additional Meteorological InputsColumbia Generating StationMonday, March 09, 2015 14:54CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (INT) reads in units of CPS- Conversion Factor: 1.5000E+12- Background Subtract: 5.5000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - MilesUnable To Calculate1.005 - MilesUnable To Calculate1.0010 - MilesUnable To Calculate1.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.42 ul at at e u l a at e e ul ul at t e e Dose AssessmentColumbia Generating StationMonday, March 09, 2015 14:52Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Turb Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = < 2 HoursRW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Turb BldgReadings: 5.10E-05 uCi/ccFlowrate: 360000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.0.00E+000.00E+003.47E-011.43E-014.91E-018.79E+001.50.00E+000.00E+002.75E-011.13E-013.88E-016.96E+002.00.00E+000.00E+002.08E-010.00E+002.08E-015.26E+00 3.00.00E+000.00E+001.38E-010.00E+001.38E-013.48E+00 4.00.00E+000.00E+001.07E-010.00E+001.07E-012.71E+00 5.00.00E+000.00E+000.00E+000.00E+000.00E+002.24E+00 7.00.00E+000.00E+000.00E+000.00E+000.00E+001.41E+0010.00.00E+000.00E+000.00E+000.00E+000.00E+001.18E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03092015 145215.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate1.31E-04 (1.5%)Iodine3.20E-03 (37.2%)Noble Gas5.26E-03 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.43 1 1 0.0 0E E+0 0 1 0 0.0 0E E++0 0 1.1 3E-0 0 1 0 0.0 0E++0 0 2 Isotopic Release RatesColumbia Generating StationMonday, March 09, 2015 14:52Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-859.62E-06Kr-85m2.14E-04Kr-874.26E-04Kr-885.88E-04Xe-131m1.26E-05Xe-1331.88E-03Xe-133m5.95E-05Xe-1354.92E-04Xe-1381.58E-03Iodines in Ci/secI-1313.70E-04I-1325.37E-04I-1337.50E-04I-1348.27E-04I-1357.17E-04Particulates in Ci/secCs-1346.49E-05Cs-1362.06E-05Cs-1374.50E-05Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.44 E++0 00 0 C Ce Additional Meteorological InputsColumbia Generating StationMonday, March 09, 2015 14:52CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 36 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Turb Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.1400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.000.005 - MilesUnable To Calculate1.0010 - MilesUnable To Calculate1.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.45 Dose AssessmentColumbia Generating StationMonday, March 09, 2015 14:53Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 9.90E-04 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.1.35E-011.68E-011.70E+006.99E-012.56E+004.29E+011.51.05E-011.30E-011.34E+005.53E-012.03E+003.41E+012.00.00E+000.00E+001.01E+004.08E-011.41E+002.54E+01 3.00.00E+000.00E+006.51E-012.45E-018.97E-011.65E+01 4.00.00E+000.00E+005.23E-011.91E-017.14E-011.32E+01 5.00.00E+000.00E+004.09E-011.46E-015.55E-011.04E+01 7.00.00E+000.00E+002.58E-010.00E+002.58E-016.54E+0010.00.00E+000.00E+001.93E-010.00E+001.93E-014.90E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03092015 145313.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate6.14E-04 (1.5%)Iodine1.50E-02 (37.2%)Noble Gas2.47E-02 (61.3%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.46 1 9 1E 0 0 1 0 0 0 5.5 3 3E-0 1 0 0 0 4.0 0 8E-0 1 0 0 1 2.4.4 5E-0 1 1 0 1 Isotopic Release RatesColumbia Generating StationMonday, March 09, 2015 14:53Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-854.52E-05Kr-85m1.00E-03Kr-872.00E-03Kr-882.77E-03Xe-131m5.94E-05Xe-1338.83E-03Xe-133m2.80E-04Xe-1352.31E-03Xe-1387.42E-03Iodines in Ci/secI-1311.74E-03I-1322.52E-03I-1333.53E-03I-1343.88E-03I-1353.37E-03Particulates in Ci/secCs-1343.05E-04Cs-1369.70E-05Cs-1372.11E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.47 0 M o-9 9 9 0 C e--1 44 Additional Meteorological InputsColumbia Generating StationMonday, March 09, 2015 14:53CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.000.005 - Miles0.000.0010 - Miles0.000.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.48 Dose AssessmentColumbia Generating StationThursday, March 26, 2015 18:42Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (HI)Readings: 4.00E+02 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.1.37E+012.70E+011.03E+001.85E+002.99E+016.33E+001.51.14E+012.20E+011.06E+001.99E+002.50E+015.06E+002.08.80E+001.64E+011.15E+002.16E+001.98E+013.95E+00 3.05.64E+001.03E+016.88E-011.25E+001.22E+012.61E+00 4.05.44E+009.74E+006.65E-011.17E+001.16E+012.18E+00 5.04.36E+007.70E+005.80E-019.91E-019.27E+001.79E+00 7.02.57E+004.63E+003.76E-016.03E-015.61E+001.14E+0010.02.32E+004.25E+003.53E-014.63E-015.07E+001.15E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03262015 184231.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate1.15E-04 (0.0%)Iodine2.81E-03 (0.0%)Noble Gas1.16E+01 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.49___________________________________________ByJohnD.Fisherat2:38pm,Mar30,2015 Isotopic Release RatesColumbia Generating StationThursday, March 26, 2015 18:42Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-852.12E-02Kr-85m4.70E-01Kr-879.36E-01Kr-881.29E+00Xe-131m2.78E-02Xe-1334.13E+00Xe-133m1.31E-01Xe-1351.08E+00Xe-1383.47E+00Iodines in Ci/secI-1313.25E-04I-1324.72E-04I-1336.60E-04I-1347.27E-04I-1356.31E-04Particulates in Ci/secCs-1345.71E-05Cs-1361.81E-05Cs-1373.96E-05Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.50 Additional Meteorological InputsColumbia Generating StationThursday, March 26, 2015 18:42CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (HI) reads in units of CPS- Conversion Factor: 3.4900E+07- Background Subtract: 2.1000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.930.945 - Miles0.930.9410 - Miles0.920.93Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.51 Dose AssessmentColumbia Generating StationThursday, March 26, 2015 18:42Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (HI)Readings: 2.00E+03 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.1.29E+022.55E+029.74E+001.75E+012.82E+025.96E+011.51.07E+022.08E+021.00E+011.87E+012.36E+024.76E+012.08.28E+011.55E+021.09E+012.04E+011.86E+023.71E+01 3.05.32E+019.67E+016.49E+001.18E+011.15E+022.46E+01 4.05.16E+019.20E+016.28E+001.11E+011.09E+022.05E+01 5.04.12E+017.27E+015.48E+009.34E+008.75E+011.68E+01 7.02.43E+014.38E+013.55E+005.68E+005.30E+011.07E+0110.02.20E+014.01E+013.33E+004.36E+004.78E+011.08E+01Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03262015 184256.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Site Area Emergency * * *Release Rates (Ci / sec)Particulate1.08E-03 (0.0%)Iodine2.65E-02 (0.0%)Noble Gas1.09E+02 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.52____________________________________________Pa gByJohnD.Fisherat8:47am,Mar31,2015 Isotopic Release RatesColumbia Generating StationThursday, March 26, 2015 18:42Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.99E-01Kr-85m4.42E+00Kr-878.82E+00Kr-881.22E+01Xe-131m2.62E-01Xe-1333.89E+01Xe-133m1.23E+00Xe-1351.02E+01Xe-1383.27E+01Iodines in Ci/secI-1313.06E-03I-1324.45E-03I-1336.22E-03I-1346.85E-03I-1355.94E-03Particulates in Ci/secCs-1345.38E-04Cs-1361.71E-04Cs-1373.73E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.53 Additional Meteorological InputsColumbia Generating StationThursday, March 26, 2015 18:42CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (HI) reads in units of CPS- Conversion Factor: 3.4900E+07- Background Subtract: 2.1000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.930.945 - Miles0.930.9410 - Miles0.920.93Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.54 Dose AssessmentColumbia Generating StationThursday, March 26, 2015 18:43Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (HI)Readings: 2.00E+04 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.1.43E+032.82E+031.08E+021.93E+023.12E+036.60E+021.51.18E+032.29E+031.11E+022.07E+022.61E+035.28E+022.09.16E+021.70E+031.20E+022.25E+022.05E+034.12E+023.05.88E+021.07E+037.17E+011.30E+021.27E+032.72E+024.05.68E+021.02E+036.94E+011.22E+021.21E+032.27E+024.035.68E+021.02E+036.94E+011.22E+021.21E+032.27E+025.04.56E+028.04E+026.05E+011.03E+029.67E+021.86E+027.02.68E+024.84E+023.93E+016.28E+015.86E+021.18E+0210.02.43E+024.44E+023.68E+014.82E+015.29E+021.20E+02Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03262015 184353.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miPAGs Exceeded in Designated Areas* *

Classification: General Emergency * * *Release Rates (Ci / sec)Particulate1.20E-02 (0.0%)Iodine2.93E-01 (0.0%)Noble Gas1.20E+03 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.55____________________________________________Pa gByJohnD.Fisherat8:48am,Mar31,2015 Isotopic Release RatesColumbia Generating StationThursday, March 26, 2015 18:43Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-852.20E+00Kr-85m4.89E+01Kr-879.75E+01Kr-881.35E+02Xe-131m2.89E+00Xe-1334.30E+02Xe-133m1.36E+01Xe-1351.13E+02Xe-1383.61E+02Iodines in Ci/secI-1313.39E-02I-1324.92E-02I-1336.87E-02I-1347.57E-02I-1356.57E-02Particulates in Ci/secCs-1345.95E-03Cs-1361.89E-03Cs-1374.12E-03Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.56 Additional Meteorological InputsColumbia Generating StationThursday, March 26, 2015 18:43CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (HI) reads in units of CPS- Conversion Factor: 3.4900E+07- Background Subtract: 2.1000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.930.945 - Miles0.930.9410 - Miles0.920.93Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.57 Dose AssessmentColumbia Generating StationThursday, February 05, 2015 15:22Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Turb Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = < 2 HoursRW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Turb BldgReadings: 1.02E-04 uCi/ccFlowrate: 360000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.0.00E+000.00E+007.11E-012.93E-011.00E+001.80E+011.50.00E+000.00E+005.63E-012.31E-017.94E-011.42E+012.00.00E+000.00E+004.25E-011.72E-015.97E-011.07E+01 3.00.00E+000.00E+002.81E-011.08E-013.89E-017.11E+00 4.00.00E+000.00E+002.18E-010.00E+002.18E-015.52E+00 5.00.00E+000.00E+001.80E-010.00E+001.80E-014.57E+00 7.00.00E+000.00E+001.14E-010.00E+001.14E-012.88E+0010.00.00E+000.00E+000.00E+000.00E+000.00E+002.41E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 02052015 152229.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate2.67E-04 (1.5%)Iodine6.54E-03 (37.4%)Noble Gas1.07E-02 (61.1%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.58____________________________________________PByJohnD.Fisherat8:48am,Mar31,2015 Isotopic Release RatesColumbia Generating StationThursday, February 05, 2015 15:22Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.97E-05Kr-85m4.37E-04Kr-878.70E-04Kr-881.20E-03Xe-131m2.58E-05Xe-1333.84E-03Xe-133m1.22E-04Xe-1351.00E-03Xe-1383.23E-03Iodines in Ci/secI-1317.56E-04I-1321.10E-03I-1331.53E-03I-1341.69E-03I-1351.47E-03Particulates in Ci/secCs-1341.33E-04Cs-1364.22E-05Cs-1379.20E-05Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.59 Additional Meteorological InputsColumbia Generating StationThursday, February 05, 2015 15:22CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 36 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Turb Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.1400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.000.005 - Miles0.000.0010 - MilesUnable To Calculate1.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.60 This is a DrillThis is a DrillDose AssessmentColumbia Generating StationThursday, February 05, 2015 14:32Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Turb Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = < 2 HoursRW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Turb BldgReadings: 8.35E-04 uCi/ccFlowrate: 360000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.4.72E-015.88E-015.93E+002.44E+008.96E+001.50E+021.53.68E-014.57E-014.69E+001.92E+007.07E+001.19E+022.02.58E-013.18E-013.54E+001.43E+005.29E+008.94E+01 3.01.78E-012.25E-012.34E+009.02E-013.47E+005.93E+01 4.01.36E-011.82E-011.82E+006.85E-012.69E+004.61E+01 5.01.14E-011.48E-011.50E+005.59E-012.21E+003.81E+01 7.00.00E+000.00E+009.49E-013.46E-011.30E+002.41E+0110.00.00E+000.00E+007.92E-012.58E-011.05E+002.01E+01Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 02052015 143218.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate2.23E-03 (1.5%)Iodine5.46E-02 (37.3%)Noble Gas8.97E-02 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.61__________________________________________ByJohnD.Fisherat8:48am,Mar31,2015 This is a DrillThis is a DrillIsotopic Release RatesColumbia Generating StationThursday, February 05, 2015 14:32Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.64E-04Kr-85m3.64E-03Kr-877.26E-03Kr-881.00E-02Xe-131m2.15E-04Xe-1333.20E-02Xe-133m1.01E-03Xe-1358.38E-03Xe-1382.69E-02Iodines in Ci/secI-1316.30E-03I-1329.16E-03I-1331.28E-02I-1341.41E-02I-1351.22E-02Particulates in Ci/secCs-1341.11E-03Cs-1363.52E-04Cs-1377.67E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.62 This is a DrillThis is a DrillAdditional Meteorological InputsColumbia Generating StationThursday, February 05, 2015 14:32CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneThis is a DrillThis is a DrillMiscellaneous Inputs and DataRelease Point Elevation: 36 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Turb Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.1400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)This is a DrillThis is a Drill EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.000.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.63 Dose AssessmentColumbia Generating StationThursday, March 26, 2015 17:36Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Turb Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = < 2 HoursRW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Turb BldgReadings: 8.35E-03 uCi/ccFlowrate: 360000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.4.72E+005.90E+005.94E+012.45E+018.98E+011.50E+031.53.69E+004.60E+004.70E+011.93E+017.10E+011.19E+032.02.60E+003.19E+003.55E+011.43E+015.30E+018.96E+02 3.01.79E+002.26E+002.35E+019.04E+003.48E+015.94E+02 4.01.37E+001.82E+001.83E+016.87E+002.69E+014.62E+02 5.01.14E+001.48E+001.51E+015.60E+002.22E+013.82E+02 7.06.76E-019.06E-019.51E+003.47E+001.39E+012.41E+0210.05.08E-017.12E-017.93E+002.58E+001.12E+012.02E+02Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03262015 173625.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Site Area Emergency * * *Release Rates (Ci / sec)Particulate2.23E-02 (1.5%)Iodine5.47E-01 (37.3%)Noble Gas8.99E-01 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.64____________________________________________PByJohnD.Fisherat8:48am,Mar31,2015 Isotopic Release RatesColumbia Generating StationThursday, March 26, 2015 17:36Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.64E-03Kr-85m3.65E-02Kr-877.27E-02Kr-881.01E-01Xe-131m2.16E-03Xe-1333.21E-01Xe-133m1.02E-02Xe-1358.40E-02Xe-1382.70E-01Iodines in Ci/secI-1316.32E-02I-1329.18E-02I-1331.28E-01I-1341.41E-01I-1351.23E-01Particulates in Ci/secCs-1341.11E-02Cs-1363.52E-03Cs-1377.69E-03Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.65 Additional Meteorological InputsColumbia Generating StationThursday, March 26, 2015 17:36CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 36 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Turb Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.1400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.080.27Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.66 NE-02-09-12 Rev 3, pa g e A.67ByJohnD.Fisherat8:48am,Mar31,2015 NE-02-09-12 Rev 3, pa g e A.68 NE-02-09-12 Rev 3, pa g e A.69 Dose AssessmentColumbia Generating StationThursday, March 26, 2015 19:22Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 1.98E-03 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.2.70E-013.37E-013.40E+001.40E+005.13E+008.59E+011.52.10E-012.60E-012.70E+001.11E+004.07E+006.82E+012.01.47E-011.80E-012.02E+008.16E-013.01E+005.10E+01 3.01.01E-011.30E-011.30E+004.91E-011.93E+003.30E+01 4.00.00E+001.03E-011.05E+003.83E-011.53E+002.65E+01 5.00.00E+000.00E+008.18E-012.94E-011.11E+002.07E+01 7.00.00E+000.00E+005.16E-011.81E-016.97E-011.31E+0110.00.00E+000.00E+003.85E-011.21E-015.06E-019.80E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03262015 192219.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate1.23E-03 (1.5%)Iodine3.01E-02 (37.2%)Noble Gas4.95E-02 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.70__________________________________________ByJohnD.Fisherat8:49am,Mar31,2015 Isotopic Release RatesColumbia Generating StationThursday, March 26, 2015 19:22Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-859.06E-05Kr-85m2.01E-03Kr-874.01E-03Kr-885.54E-03Xe-131m1.19E-04Xe-1331.77E-02Xe-133m5.60E-04Xe-1354.63E-03Xe-1381.49E-02Iodines in Ci/secI-1313.48E-03I-1325.06E-03I-1337.06E-03I-1347.78E-03I-1356.75E-03Particulates in Ci/secCs-1346.11E-04Cs-1361.94E-04Cs-1374.24E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.71 Additional Meteorological InputsColumbia Generating StationThursday, March 26, 2015 19:22CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.000.0010 - Miles0.000.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.72 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 11:22Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 3.45E-03 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.4.71E-015.87E-015.93E+002.44E+008.96E+001.50E+021.53.66E-014.55E-014.70E+001.93E+007.09E+001.19E+022.02.56E-013.13E-013.52E+001.42E+005.25E+008.89E+01 3.01.77E-012.27E-012.28E+008.58E-013.36E+005.76E+01 4.01.40E-011.80E-011.83E+006.69E-012.68E+004.62E+01 5.01.04E-011.38E-011.43E+005.13E-012.08E+003.61E+01 7.00.00E+000.00E+009.00E-013.16E-011.22E+002.28E+0110.00.00E+000.00E+006.72E-012.09E-018.82E-011.71E+01Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 112246.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate2.14E-03 (1.5%)Iodine5.25E-02 (37.2%)Noble Gas8.63E-02 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.73___________________________________________ByJohnD.Fisherat8:49am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 11:22Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.58E-04Kr-85m3.50E-03Kr-876.99E-03Kr-889.65E-03Xe-131m2.07E-04Xe-1333.08E-02Xe-133m9.77E-04Xe-1358.06E-03Xe-1382.59E-02Iodines in Ci/secI-1316.07E-03I-1328.81E-03I-1331.23E-02I-1341.36E-02I-1351.18E-02Particulates in Ci/secCs-1341.07E-03Cs-1363.38E-04Cs-1377.38E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.74 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 11:22CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.000.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.75 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 11:23Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 3.45E-02 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.4.71E+005.88E+005.93E+012.45E+018.96E+011.50E+031.53.67E+004.55E+004.70E+011.93E+017.09E+011.19E+032.02.56E+003.13E+003.52E+011.42E+015.25E+018.89E+02 3.01.77E+002.27E+002.28E+018.58E+003.36E+015.76E+02 4.01.40E+001.81E+001.83E+016.69E+002.68E+014.62E+02 5.01.04E+001.38E+001.43E+015.14E+002.08E+013.61E+02 7.06.32E-018.40E-019.00E+003.17E+001.30E+012.28E+0210.04.24E-015.89E-016.72E+002.09E+009.41E+001.71E+02Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 112318.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Site Area Emergency * * *Release Rates (Ci / sec)Particulate2.14E-02 (1.5%)Iodine5.26E-01 (37.3%)Noble Gas8.63E-01 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.76___________________________________________PaByJohnD.Fisherat8:49am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 11:23Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.58E-03Kr-85m3.51E-02Kr-876.99E-02Kr-889.66E-02Xe-131m2.07E-03Xe-1333.09E-01Xe-133m9.78E-03Xe-1358.07E-02Xe-1382.59E-01Iodines in Ci/secI-1316.07E-02I-1328.82E-02I-1331.23E-01I-1341.36E-01I-1351.18E-01Particulates in Ci/secCs-1341.07E-02Cs-1363.39E-03Cs-1377.39E-03Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.77 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 11:23CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.080.27Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.78 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 11:25Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 3.45E-01 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.4.71E+015.88E+015.93E+022.45E+028.96E+021.50E+041.53.67E+014.55E+014.70E+021.93E+027.09E+021.19E+042.02.56E+013.13E+013.52E+021.42E+025.25E+028.89E+033.01.77E+012.27E+012.28E+028.58E+013.36E+025.76E+033.351.54E+012.02E+012.03E+027.57E+012.99E+025.14E+034.01.40E+011.81E+011.83E+026.69E+012.68E+024.62E+035.01.04E+011.38E+011.43E+025.14E+012.08E+023.61E+03 7.06.32E+008.40E+009.00E+013.17E+011.30E+022.28E+0310.04.24E+005.89E+006.72E+012.09E+019.41E+011.71E+03Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 112523.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miPAGs Exceeded in Designated Areas* *

Classification: General Emergency * * *Release Rates (Ci / sec)Particulate2.14E-01 (1.5%)Iodine5.26E+00 (37.3%)Noble Gas8.64E+00 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.79____________________________________________PaByJohnD.Fisherat8:50am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 11:25Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.58E-02Kr-85m3.51E-01Kr-876.99E-01Kr-889.66E-01Xe-131m2.07E-02Xe-1333.09E+00Xe-133m9.78E-02Xe-1358.07E-01Xe-1382.59E+00Iodines in Ci/secI-1316.07E-01I-1328.82E-01I-1331.23E+00I-1341.36E+00I-1351.18E+00Particulates in Ci/secCs-1341.07E-01Cs-1363.39E-02Cs-1377.39E-02Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.80 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 11:25CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.080.27Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.81 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 11:31Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (INT)Readings: 6.00E+03 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+001.50.00E+000.00E+000.00E+000.00E+000.00E+000.00E+002.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 3.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 4.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 5.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 7.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+0010.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 113103.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate7.66E-08 (0.0%)Iodine1.88E-06 (0.0%)Noble Gas7.72E-03 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.82___________________________________________PByJohnD.Fisherat8:50am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 11:31Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.41E-05Kr-85m3.13E-04Kr-876.25E-04Kr-888.63E-04Xe-131m1.85E-05Xe-1332.76E-03Xe-133m8.74E-05Xe-1357.21E-04Xe-1382.32E-03Iodines in Ci/secI-1312.17E-07I-1323.15E-07I-1334.40E-07I-1344.85E-07I-1354.21E-07Particulates in Ci/secCs-1343.81E-08Cs-1361.21E-08Cs-1372.64E-08Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.83 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 11:31CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (INT) reads in units of CPS- Conversion Factor: 1.5000E+12- Background Subtract: 5.5000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - MilesUnable To Calculate1.005 - MilesUnable To Calculate1.0010 - MilesUnable To Calculate1.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.84 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 11:39Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (INT)Readings: 5.00E+05 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.8.37E-011.66E+000.00E+001.13E-011.77E+003.87E-011.56.96E-011.34E+000.00E+001.21E-011.47E+003.10E-012.05.36E-011.00E+000.00E+001.32E-011.14E+002.41E-01 3.03.45E-016.27E-010.00E+000.00E+006.27E-011.60E-01 4.03.34E-015.96E-010.00E+000.00E+005.96E-011.33E-01 5.02.68E-014.71E-010.00E+000.00E+004.71E-011.10E-01 7.01.57E-012.84E-010.00E+000.00E+002.84E-010.00E+0010.01.42E-012.60E-010.00E+000.00E+002.60E-010.00E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 113901.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate7.02E-06 (0.0%)Iodine1.72E-04 (0.0%)Noble Gas7.07E-01 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.85___________________________________________PaByJohnD.Fisherat8:50am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 11:39Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.29E-03Kr-85m2.87E-02Kr-875.72E-02Kr-887.91E-02Xe-131m1.70E-03Xe-1332.53E-01Xe-133m8.01E-03Xe-1356.61E-02Xe-1382.12E-01Iodines in Ci/secI-1311.99E-05I-1322.89E-05I-1334.04E-05I-1344.45E-05I-1353.86E-05Particulates in Ci/secCs-1343.49E-06Cs-1361.11E-06Cs-1372.42E-06Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.86 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 11:39CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (INT) reads in units of CPS- Conversion Factor: 1.5000E+12- Background Subtract: 5.5000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles1.001.005 - Miles1.001.0010 - Miles1.001.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.87 Dose AssessmentColumbia Generating StationMonday, March 30, 2015 15:28Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (INT)Readings: 3.00E+03 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+001.50.00E+000.00E+000.00E+000.00E+000.00E+000.00E+002.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 3.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 4.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 5.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00 7.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+0010.00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03302015 152845.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate3.44E-08 (0.0%)Iodine8.45E-07 (0.0%)Noble Gas3.47E-03 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.88____________________________________________ByJohnD.Fisherat8:51am,Mar31,2015 Isotopic Release RatesColumbia Generating StationMonday, March 30, 2015 15:28Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-856.35E-06Kr-85m1.41E-04Kr-872.81E-04Kr-883.88E-04Xe-131m8.33E-06Xe-1331.24E-03Xe-133m3.93E-05Xe-1353.24E-04Xe-1381.04E-03Iodines in Ci/secI-1319.75E-08I-1321.42E-07I-1331.98E-07I-1342.18E-07I-1351.89E-07Particulates in Ci/secCs-1341.71E-08Cs-1365.44E-09Cs-1371.19E-08Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.89 Additional Meteorological InputsColumbia Generating StationMonday, March 30, 2015 15:28CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (INT) reads in units of CPS- Conversion Factor: 1.5000E+12- Background Subtract: 5.5000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - MilesUnable To Calculate1.005 - MilesUnable To Calculate1.0010 - MilesUnable To Calculate1.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.90 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 11:34Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Turb Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = < 2 HoursRW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Turb BldgReadings: 5.10E-05 uCi/ccFlowrate: 360000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.0.00E+000.00E+003.47E-011.43E-014.91E-018.79E+001.50.00E+000.00E+002.75E-011.13E-013.88E-016.96E+002.00.00E+000.00E+002.08E-010.00E+002.08E-015.26E+00 3.00.00E+000.00E+001.38E-010.00E+001.38E-013.48E+00 4.00.00E+000.00E+001.07E-010.00E+001.07E-012.71E+00 5.00.00E+000.00E+000.00E+000.00E+000.00E+002.24E+00 7.00.00E+000.00E+000.00E+000.00E+000.00E+001.41E+0010.00.00E+000.00E+000.00E+000.00E+000.00E+001.18E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 113436.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate1.31E-04 (1.5%)Iodine3.20E-03 (37.2%)Noble Gas5.26E-03 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.91___________________________________________ByJohnD.Fisherat8:51am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 11:34Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-859.62E-06Kr-85m2.14E-04Kr-874.26E-04Kr-885.88E-04Xe-131m1.26E-05Xe-1331.88E-03Xe-133m5.95E-05Xe-1354.92E-04Xe-1381.58E-03Iodines in Ci/secI-1313.70E-04I-1325.37E-04I-1337.50E-04I-1348.27E-04I-1357.17E-04Particulates in Ci/secCs-1346.49E-05Cs-1362.06E-05Cs-1374.50E-05Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.92 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 11:34CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 36 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Turb Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.1400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.000.005 - MilesUnable To Calculate1.0010 - MilesUnable To Calculate1.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.93 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 11:35Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 9.90E-04 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.1.35E-011.68E-011.70E+006.99E-012.56E+004.29E+011.51.05E-011.30E-011.34E+005.53E-012.03E+003.41E+012.00.00E+000.00E+001.01E+004.08E-011.41E+002.54E+01 3.00.00E+000.00E+006.51E-012.45E-018.97E-011.65E+01 4.00.00E+000.00E+005.23E-011.91E-017.14E-011.32E+01 5.00.00E+000.00E+004.09E-011.46E-015.55E-011.04E+01 7.00.00E+000.00E+002.58E-010.00E+002.58E-016.54E+0010.00.00E+000.00E+001.93E-010.00E+001.93E-014.90E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 113522.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate6.14E-04 (1.5%)Iodine1.50E-02 (37.2%)Noble Gas2.47E-02 (61.3%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.94___________________________________________ByJohnD.Fisherat8:51am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 11:35Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-854.52E-05Kr-85m1.00E-03Kr-872.00E-03Kr-882.77E-03Xe-131m5.94E-05Xe-1338.83E-03Xe-133m2.80E-04Xe-1352.31E-03Xe-1387.42E-03Iodines in Ci/secI-1311.74E-03I-1322.52E-03I-1333.53E-03I-1343.88E-03I-1353.37E-03Particulates in Ci/secCs-1343.05E-04Cs-1369.70E-05Cs-1372.11E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.95 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 11:35CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.000.005 - Miles0.000.0010 - Miles0.000.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.96 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 10:11Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (HI)Readings: 4.38E+02 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.1.64E+013.24E+011.24E+002.22E+003.59E+017.59E+001.51.36E+012.64E+011.27E+002.38E+003.01E+016.07E+002.01.06E+011.97E+011.38E+002.59E+002.37E+014.73E+00 3.06.76E+001.23E+018.25E-011.50E+001.46E+013.13E+00 4.06.56E+001.17E+017.99E-011.41E+001.39E+012.62E+00 5.05.24E+009.24E+006.96E-011.19E+001.11E+012.15E+00 7.03.08E+005.56E+004.52E-017.23E-016.74E+001.37E+0010.02.79E+005.10E+004.24E-015.55E-016.08E+001.38E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 101152.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate1.38E-04 (0.0%)Iodine3.38E-03 (0.0%)Noble Gas1.39E+01 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.97___________________________________________PByJohnD.Fisherat8:52am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 10:11Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-852.54E-02Kr-85m5.63E-01Kr-871.12E+00Kr-881.55E+00Xe-131m3.33E-02Xe-1334.96E+00Xe-133m1.57E-01Xe-1351.30E+00Xe-1384.16E+00Iodines in Ci/secI-1313.90E-04I-1325.67E-04I-1337.92E-04I-1348.72E-04I-1357.57E-04Particulates in Ci/secCs-1346.85E-05Cs-1362.18E-05Cs-1374.75E-05Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.98 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 10:11CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (HI) reads in units of CPS- Conversion Factor: 3.4900E+07- Background Subtract: 2.1000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.930.945 - Miles0.930.9410 - Miles0.920.93Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.99 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 10:10Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (HI)Readings: 3.62E+02 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.1.09E+012.17E+018.26E-011.48E+002.40E+015.06E+001.59.08E+001.76E+018.50E-011.59E+002.01E+014.04E+002.07.04E+001.31E+019.20E-011.73E+001.57E+013.16E+00 3.04.52E+008.20E+005.50E-011.00E+009.76E+002.09E+00 4.04.36E+007.79E+005.32E-019.41E-019.27E+001.74E+00 5.03.50E+006.16E+004.64E-017.93E-017.42E+001.43E+00 7.02.06E+003.71E+003.01E-014.83E-014.49E+009.10E-0110.01.86E+003.40E+002.82E-013.70E-014.05E+009.18E-01Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 101049.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate9.19E-05 (0.0%)Iodine2.25E-03 (0.0%)Noble Gas9.25E+00 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.100___________________________________________PByJohnD.Fisherat8:52am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 10:10Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.69E-02Kr-85m3.76E-01Kr-877.49E-01Kr-881.03E+00Xe-131m2.22E-02Xe-1333.31E+00Xe-133m1.05E-01Xe-1358.64E-01Xe-1382.78E+00Iodines in Ci/secI-1312.60E-04I-1323.78E-04I-1335.28E-04I-1345.82E-04I-1355.05E-04Particulates in Ci/secCs-1344.57E-05Cs-1361.45E-05Cs-1373.17E-05Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.101 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 10:10CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (HI) reads in units of CPS- Conversion Factor: 3.4900E+07- Background Subtract: 2.1000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.930.945 - Miles0.930.9410 - Miles0.920.93Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.102 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 10:11Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (HI)Readings: 2.36E+03 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.1.55E+023.06E+021.17E+012.10E+013.38E+027.16E+011.51.29E+022.48E+021.20E+012.25E+012.83E+025.72E+012.09.96E+011.86E+021.31E+012.45E+012.24E+024.46E+01 3.06.40E+011.16E+027.79E+001.42E+011.38E+022.95E+01 4.06.16E+011.10E+027.53E+001.33E+011.31E+022.47E+01 5.04.96E+018.72E+016.57E+001.12E+011.05E+022.03E+01 7.02.91E+015.25E+014.26E+006.82E+006.36E+011.29E+0110.02.63E+014.81E+014.00E+005.24E+005.74E+011.30E+01Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 101128.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Site Area Emergency * * *Release Rates (Ci / sec)Particulate1.30E-03 (0.0%)Iodine3.19E-02 (0.0%)Noble Gas1.31E+02 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.103____________________________________________PByJohnD.Fisherat8:52am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 10:11Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-852.39E-01Kr-85m5.31E+00Kr-871.06E+01Kr-881.46E+01Xe-131m3.14E-01Xe-1334.68E+01Xe-133m1.48E+00Xe-1351.22E+01Xe-1383.93E+01Iodines in Ci/secI-1313.68E-03I-1325.35E-03I-1337.47E-03I-1348.23E-03I-1357.14E-03Particulates in Ci/secCs-1346.46E-04Cs-1362.05E-04Cs-1374.48E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.104 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 10:11CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (HI) reads in units of CPS- Conversion Factor: 3.4900E+07- Background Subtract: 2.1000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.930.945 - Miles0.930.9410 - Miles0.920.93Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.105 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 10:13Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (HI)Readings: 1.64E+03 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.1.03E+022.04E+027.77E+001.39E+012.25E+024.77E+011.58.56E+011.66E+027.99E+001.49E+011.89E+023.82E+012.06.64E+011.24E+028.66E+001.63E+011.49E+022.98E+01 3.04.24E+017.72E+015.18E+009.42E+009.18E+011.97E+01 4.04.12E+017.34E+015.01E+008.84E+008.73E+011.64E+01 5.03.30E+015.81E+014.37E+007.46E+006.99E+011.35E+01 7.01.94E+013.49E+012.83E+004.54E+004.23E+018.57E+0010.01.75E+013.20E+012.66E+003.48E+003.82E+018.65E+00Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 101356.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Site Area Emergency * * *Release Rates (Ci / sec)Particulate8.64E-04 (0.0%)Iodine2.12E-02 (0.0%)Noble Gas8.70E+01 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.106___________________________________________ByJohnD.Fisherat8:52am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 10:13Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.59E-01Kr-85m3.53E+00Kr-877.04E+00Kr-889.74E+00Xe-131m2.09E-01Xe-1333.11E+01Xe-133m9.85E-01Xe-1358.13E+00Xe-1382.61E+01Iodines in Ci/secI-1312.45E-03I-1323.56E-03I-1334.97E-03I-1345.47E-03I-1354.75E-03Particulates in Ci/secCs-1344.30E-04Cs-1361.37E-04Cs-1372.98E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.107 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 10:13CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (HI) reads in units of CPS- Conversion Factor: 3.4900E+07- Background Subtract: 2.1000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.930.945 - Miles0.930.9410 - Miles0.920.93Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.108 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 10:15Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (HI)Readings: 2.40E+04 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.1.71E+033.38E+031.29E+022.32E+023.75E+037.93E+021.51.42E+032.75E+031.33E+022.49E+023.13E+036.34E+022.01.10E+032.05E+031.44E+022.70E+022.47E+034.93E+023.07.08E+021.28E+038.62E+011.57E+021.53E+033.27E+024.06.84E+021.22E+038.34E+011.47E+021.45E+032.73E+025.05.48E+029.65E+027.27E+011.24E+021.16E+032.24E+025.594.68E+028.33E+026.44E+011.08E+021.01E+031.96E+027.03.22E+025.81E+024.71E+017.54E+017.03E+021.43E+0210.02.92E+025.33E+024.42E+015.79E+016.35E+021.44E+02Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 101515.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miPAGs Exceeded in Designated Areas* *

Classification: General Emergency * * *Release Rates (Ci / sec)Particulate1.44E-02 (0.0%)Iodine3.52E-01 (0.0%)Noble Gas1.45E+03 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.109____________________________________________PByJohnD.Fisherat8:52am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 10:15Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-852.65E+00Kr-85m5.88E+01Kr-871.17E+02Kr-881.62E+02Xe-131m3.48E+00Xe-1335.17E+02Xe-133m1.64E+01Xe-1351.35E+02Xe-1384.34E+02Iodines in Ci/secI-1314.07E-02I-1325.92E-02I-1338.26E-02I-1349.10E-02I-1357.90E-02Particulates in Ci/secCs-1347.15E-03Cs-1362.27E-03Cs-1374.95E-03Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.110 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 10:15CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (HI) reads in units of CPS- Conversion Factor: 3.4900E+07- Background Subtract: 2.1000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.930.945 - Miles0.930.9410 - Miles0.920.93Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.111 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 10:55Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Drywell> <Rx Bldg> <SBGT> <Stack> <Env>PRF: 1.60E-04Drywell HUT: = < 2 HoursDrywell Sprays: = OFFSupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = 2 - 24 HoursSBGT Filters: = WorkingTurb Bldg HUT: = N/ARW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Stack (HI)Readings: 1.60E+04 CPSFlowrate: 4500 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.1.14E+032.25E+038.59E+011.54E+022.49E+035.26E+021.59.48E+021.84E+038.84E+011.65E+022.09E+034.20E+022.07.32E+021.37E+039.58E+011.79E+021.64E+033.28E+022.924.68E+028.54E+025.73E+011.04E+021.01E+032.17E+023.04.68E+028.54E+025.73E+011.04E+021.01E+032.17E+024.04.56E+028.12E+025.54E+019.76E+019.65E+021.81E+025.03.65E+026.42E+024.83E+018.23E+017.73E+021.48E+02 7.02.14E+023.86E+023.14E+015.01E+014.68E+029.45E+0110.01.94E+023.55E+022.94E+013.85E+014.23E+029.53E+01Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 105515.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miPAGs Exceeded in Designated Areas* *

Classification: General Emergency * * *Release Rates (Ci / sec)Particulate9.54E-03 (0.0%)Iodine2.34E-01 (0.0%)Noble Gas9.61E+02 (100.0%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.112___________________________________________PByJohnD.Fisherat8:53am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 10:55Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.76E+00Kr-85m3.90E+01Kr-877.78E+01Kr-881.08E+02Xe-131m2.31E+00Xe-1333.43E+02Xe-133m1.09E+01Xe-1358.98E+01Xe-1382.88E+02Iodines in Ci/secI-1312.70E-02I-1323.93E-02I-1335.48E-02I-1346.04E-02I-1355.24E-02Particulates in Ci/secCs-1344.75E-03Cs-1361.51E-03Cs-1373.29E-03Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.113 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 10:55CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 70 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Stack (HI) reads in units of CPS- Conversion Factor: 3.4900E+07- Background Subtract: 2.1000E+02 EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.930.945 - Miles0.930.9410 - Miles0.920.93Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.114 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 09:53Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Turb Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = < 2 HoursRW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Turb BldgReadings: 1.00E-03 uCi/ccFlowrate: 360000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.5.65E-017.05E-017.10E+002.92E+001.07E+011.80E+021.54.40E-015.48E-015.63E+002.30E+008.48E+001.42E+022.03.10E-013.80E-014.24E+001.71E+006.33E+001.07E+02 3.02.14E-012.69E-012.81E+001.08E+004.16E+007.10E+01 4.01.63E-012.18E-012.18E+008.20E-013.22E+005.52E+01 5.01.36E-011.77E-011.80E+006.69E-012.65E+004.56E+01 7.00.00E+001.08E-011.14E+004.15E-011.66E+002.88E+0110.00.00E+000.00E+009.48E-013.08E-011.26E+002.41E+01Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 095354.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate2.67E-03 (1.5%)Iodine6.54E-02 (37.4%)Noble Gas1.07E-01 (61.1%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.115_____________________________________________ByJohnD.Fisherat8:53am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 09:53Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.97E-04Kr-85m4.36E-03Kr-878.70E-03Kr-881.20E-02Xe-131m2.58E-04Xe-1333.84E-02Xe-133m1.22E-03Xe-1351.00E-02Xe-1383.22E-02Iodines in Ci/secI-1317.55E-03I-1321.10E-02I-1331.53E-02I-1341.69E-02I-1351.46E-02Particulates in Ci/secCs-1341.33E-03Cs-1364.21E-04Cs-1379.19E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.116 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 09:53CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 36 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Turb Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.1400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.000.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.117 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 09:55Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Turb Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = < 2 HoursRW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Turb BldgReadings: 6.68E-04 uCi/ccFlowrate: 360000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.3.78E-014.70E-014.74E+001.95E+007.16E+001.20E+021.52.94E-013.66E-013.76E+001.54E+005.66E+009.48E+012.02.07E-012.54E-012.83E+001.15E+004.23E+007.15E+01 3.01.43E-011.80E-011.87E+007.20E-012.77E+004.74E+01 4.01.09E-011.45E-011.46E+005.47E-012.15E+003.68E+01 5.00.00E+001.18E-011.20E+004.46E-011.77E+003.04E+01 7.00.00E+000.00E+007.59E-012.77E-011.04E+001.92E+0110.00.00E+000.00E+006.33E-012.06E-018.39E-011.61E+01Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 095520.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate1.78E-03 (1.5%)Iodine4.36E-02 (37.2%)Noble Gas7.17E-02 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.118___________________________________________ByJohnD.Fisherat8:56am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 09:55Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.31E-04Kr-85m2.91E-03Kr-875.80E-03Kr-888.02E-03Xe-131m1.72E-04Xe-1332.56E-02Xe-133m8.11E-04Xe-1356.70E-03Xe-1382.15E-02Iodines in Ci/secI-1315.04E-03I-1327.32E-03I-1331.02E-02I-1341.13E-02I-1359.77E-03Particulates in Ci/secCs-1348.85E-04Cs-1362.81E-04Cs-1376.13E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.119 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 09:55CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 36 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Turb Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.1400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.000.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.120 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 10:52Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Turb Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = < 2 HoursRW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Turb BldgReadings: 1.00E-02 uCi/ccFlowrate: 360000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.5.65E+007.06E+007.12E+012.93E+011.08E+021.80E+031.54.40E+005.50E+005.64E+012.31E+018.50E+011.43E+032.03.10E+003.82E+004.25E+011.72E+016.35E+011.07E+03 3.02.14E+002.70E+002.81E+011.08E+014.17E+017.12E+02 4.01.64E+002.18E+002.19E+018.23E+003.23E+015.53E+02 5.01.36E+001.78E+001.80E+016.71E+002.65E+014.57E+02 7.08.08E-011.08E+001.14E+014.16E+001.66E+012.89E+0210.06.08E-018.52E-019.50E+003.09E+001.35E+012.41E+02Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 105242.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Site Area Emergency * * *Release Rates (Ci / sec)Particulate2.67E-02 (1.5%)Iodine6.55E-01 (37.2%)Noble Gas1.08E+00 (61.3%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.121____________________________________________PaByJohnD.Fisherat8:56am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 10:52Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.97E-03Kr-85m4.37E-02Kr-878.71E-02Kr-881.20E-01Xe-131m2.59E-03Xe-1333.85E-01Xe-133m1.22E-02Xe-1351.01E-01Xe-1383.23E-01Iodines in Ci/secI-1317.56E-02I-1321.10E-01I-1331.54E-01I-1341.69E-01I-1351.47E-01Particulates in Ci/secCs-1341.33E-02Cs-1364.22E-03Cs-1379.21E-03Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.122 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 10:52CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 36 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Turb Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.1400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.080.27Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.123 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 10:21Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Turb Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = < 2 HoursRW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Turb BldgReadings: 6.68E-03 uCi/ccFlowrate: 360000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.3.79E+004.72E+004.76E+011.96E+017.19E+011.21E+031.52.95E+003.67E+003.77E+011.54E+015.68E+019.52E+022.02.08E+002.54E+002.84E+011.15E+014.25E+017.18E+02 3.01.43E+001.80E+001.88E+017.24E+002.78E+014.76E+02 4.01.09E+001.46E+001.46E+015.50E+002.16E+013.70E+02 5.09.12E-011.19E+001.21E+014.48E+001.77E+013.05E+02 7.05.40E-017.24E-017.61E+002.78E+001.11E+011.93E+0210.04.08E-015.69E-016.35E+002.06E+008.98E+001.61E+02Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 102118.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Site Area Emergency * * *Release Rates (Ci / sec)Particulate1.78E-02 (1.5%)Iodine4.38E-01 (37.3%)Noble Gas7.19E-01 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.124___________________________________________PaByJohnD.Fisherat9:09am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 10:21Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.32E-03Kr-85m2.92E-02Kr-875.82E-02Kr-888.04E-02Xe-131m1.73E-03Xe-1332.57E-01Xe-133m8.14E-03Xe-1356.72E-02Xe-1382.16E-01Iodines in Ci/secI-1315.05E-02I-1327.34E-02I-1331.03E-01I-1341.13E-01I-1359.80E-02Particulates in Ci/secCs-1348.88E-03Cs-1362.82E-03Cs-1376.15E-03Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.125 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 10:21CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 36 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Turb Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.1400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.080.27Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.126 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 10:53Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Turb Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = < 2 HoursRW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Turb BldgReadings: 1.00E-01 uCi/ccFlowrate: 360000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.5.67E+017.06E+017.13E+022.93E+021.08E+031.80E+041.54.40E+015.50E+015.64E+022.31E+028.50E+021.43E+042.03.10E+013.82E+014.25E+021.72E+026.35E+021.08E+043.02.14E+012.70E+012.82E+021.08E+024.17E+027.12E+034.01.64E+012.18E+012.19E+028.23E+013.23E+025.54E+034.031.64E+012.18E+012.19E+028.23E+013.23E+025.54E+035.01.36E+011.78E+011.81E+026.71E+012.65E+024.58E+037.08.08E+001.08E+011.14E+024.17E+011.67E+022.89E+0310.06.08E+008.52E+009.51E+013.09E+011.35E+022.42E+03Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 105347.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miPAGs Exceeded in Designated Areas* *

Classification: General Emergency * * *Release Rates (Ci / sec)Particulate2.67E-01 (1.5%)Iodine6.55E+00 (37.2%)Noble Gas1.08E+01 (61.3%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.127___________________________________________PaByJohnD.Fisherat9:10am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 10:53Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.97E-02Kr-85m4.37E-01Kr-878.71E-01Kr-881.20E+00Xe-131m2.59E-02Xe-1333.85E+00Xe-133m1.22E-01Xe-1351.01E+00Xe-1383.23E+00Iodines in Ci/secI-1317.57E-01I-1321.10E+00I-1331.54E+00I-1341.69E+00I-1351.47E+00Particulates in Ci/secCs-1341.33E-01Cs-1364.22E-02Cs-1379.21E-02Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.128 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 10:53CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 36 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Turb Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.1400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.080.27Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.129 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 09:57Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <Turb Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = < 2 HoursRW Bldg HUT: = N/ASource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: Turb BldgReadings: 6.68E-02 uCi/ccFlowrate: 360000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.3.79E+014.72E+014.76E+021.96E+027.19E+021.21E+041.52.95E+013.67E+013.77E+021.54E+025.68E+029.52E+032.02.08E+012.54E+012.84E+021.15E+024.25E+027.18E+032.241.53E+011.77E+012.26E+028.86E+013.33E+025.73E+033.01.43E+011.81E+011.88E+027.24E+012.78E+024.76E+034.01.10E+011.46E+011.46E+025.50E+012.16E+023.70E+03 5.09.12E+001.19E+011.21E+024.48E+011.77E+023.05E+03 7.05.40E+007.25E+007.61E+012.78E+011.11E+021.93E+0310.04.08E+005.69E+006.35E+012.06E+018.98E+011.61E+03Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 095713.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miPAGs Exceeded in Designated Areas* *

Classification: General Emergency * * *Release Rates (Ci / sec)Particulate1.79E-01 (1.5%)Iodine4.38E+00 (37.3%)Noble Gas7.19E+00 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.130___________________________________________PaByJohnD.Fisherat9:10am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 09:57Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.32E-02Kr-85m2.92E-01Kr-875.82E-01Kr-888.05E-01Xe-131m1.73E-02Xe-1332.57E+00Xe-133m8.14E-02Xe-1356.72E-01Xe-1382.16E+00Iodines in Ci/secI-1315.05E-01I-1327.34E-01I-1331.03E+00I-1341.13E+00I-1359.81E-01Particulates in Ci/secCs-1348.88E-02Cs-1362.82E-02Cs-1376.15E-02Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.131 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 09:57CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 36 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:Turb Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.1400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.080.27Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.132 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 09:58Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 4.14E-03 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.5.65E-017.05E-017.11E+002.93E+001.07E+011.80E+021.54.40E-015.45E-015.65E+002.31E+008.51E+001.43E+022.03.07E-013.76E-014.22E+001.71E+006.31E+001.07E+02 3.02.12E-012.73E-012.73E+001.03E+004.03E+006.91E+01 4.01.68E-012.16E-012.19E+008.02E-013.21E+005.55E+01 5.01.25E-011.66E-011.71E+006.16E-012.49E+004.34E+01 7.00.00E+001.01E-011.08E+003.80E-011.56E+002.74E+0110.00.00E+000.00E+008.07E-012.51E-011.06E+002.05E+01Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 095834.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate2.57E-03 (1.5%)Iodine6.30E-02 (37.2%)Noble Gas1.04E-01 (61.3%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.133______________________________________________PByJohnD.Fisherat9:10am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 09:58Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.89E-04Kr-85m4.21E-03Kr-878.38E-03Kr-881.16E-02Xe-131m2.49E-04Xe-1333.70E-02Xe-133m1.17E-03Xe-1359.68E-03Xe-1383.11E-02Iodines in Ci/secI-1317.28E-03I-1321.06E-02I-1331.48E-02I-1341.63E-02I-1351.41E-02Particulates in Ci/secCs-1341.28E-03Cs-1364.06E-04Cs-1378.86E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.134 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 09:58CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.000.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.135 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 09:59Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 2.76E-03 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.3.75E-014.68E-014.73E+001.95E+007.15E+001.20E+021.52.93E-013.62E-013.76E+001.54E+005.66E+009.50E+012.02.04E-012.50E-012.81E+001.14E+004.20E+007.10E+01 3.01.41E-011.81E-011.82E+006.85E-012.69E+004.60E+01 4.01.12E-011.44E-011.46E+005.34E-012.14E+003.69E+01 5.00.00E+001.10E-011.14E+004.10E-011.66E+002.89E+01 7.00.00E+000.00E+007.19E-012.53E-019.73E-011.83E+0110.00.00E+000.00E+005.37E-011.67E-017.04E-011.36E+01Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 095912.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Validate against Emergency Action Levels * * *Release Rates (Ci / sec)Particulate1.71E-03 (1.5%)Iodine4.20E-02 (37.3%)Noble Gas6.90E-02 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.136___________________________________________PByJohnD.Fisherat9:11am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 09:59Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.26E-04Kr-85m2.80E-03Kr-875.59E-03Kr-887.72E-03Xe-131m1.66E-04Xe-1332.47E-02Xe-133m7.81E-04Xe-1356.45E-03Xe-1382.07E-02Iodines in Ci/secI-1314.85E-03I-1327.05E-03I-1339.85E-03I-1341.08E-02I-1359.41E-03Particulates in Ci/secCs-1348.52E-04Cs-1362.71E-04Cs-1375.91E-04Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.137 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 09:59CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.000.00Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.138 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 09:59Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 4.14E-02 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.5.65E+007.05E+007.11E+012.93E+011.07E+021.80E+031.54.40E+005.45E+005.65E+012.31E+018.51E+011.43E+032.03.07E+003.76E+004.22E+011.71E+016.31E+011.07E+03 3.02.12E+002.73E+002.73E+011.03E+014.03E+016.91E+02 4.01.68E+002.16E+002.19E+018.02E+003.21E+015.55E+02 5.01.25E+001.66E+001.71E+016.16E+002.49E+014.34E+02 7.07.56E-011.01E+001.08E+013.80E+001.56E+012.74E+0210.05.08E-017.07E-018.07E+002.51E+001.13E+012.05E+02Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 095949.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Site Area Emergency * * *Release Rates (Ci / sec)Particulate2.57E-02 (1.5%)Iodine6.31E-01 (37.2%)Noble Gas1.04E+00 (61.3%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.139___________________________________________PByJohnD.Fisherat9:11am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 09:59Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.90E-03Kr-85m4.21E-02Kr-878.39E-02Kr-881.16E-01Xe-131m2.49E-03Xe-1333.70E-01Xe-133m1.17E-02Xe-1359.68E-02Xe-1383.11E-01Iodines in Ci/secI-1317.28E-02I-1321.06E-01I-1331.48E-01I-1341.63E-01I-1351.41E-01Particulates in Ci/secCs-1341.28E-02Cs-1364.06E-03Cs-1378.87E-03Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.140 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 09:59CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.080.27Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.141 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 10:00Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 2.76E-02 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.3.78E+004.70E+004.74E+011.96E+017.17E+011.20E+031.52.94E+003.64E+003.77E+011.54E+015.67E+019.52E+022.02.05E+002.51E+002.82E+011.14E+014.21E+017.12E+02 3.01.42E+001.82E+001.82E+016.86E+002.69E+014.61E+02 4.01.12E+001.44E+001.46E+015.35E+002.14E+013.70E+02 5.08.32E-011.10E+001.14E+014.11E+001.66E+012.89E+02 7.05.04E-016.72E-017.20E+002.53E+001.04E+011.83E+0210.03.38E-014.71E-015.38E+001.68E+007.53E+001.37E+02Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 100026.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miNo PAGs Exceeded* *

Classification: Site Area Emergency * * *Release Rates (Ci / sec)Particulate1.71E-02 (1.5%)Iodine4.20E-01 (37.2%)Noble Gas6.91E-01 (61.3%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.142_____________________________________________PByJohnD.Fisherat9:11am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 10:00Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.26E-03Kr-85m2.81E-02Kr-875.59E-02Kr-887.73E-02Xe-131m1.66E-03Xe-1332.47E-01Xe-133m7.82E-03Xe-1356.46E-02Xe-1382.07E-01Iodines in Ci/secI-1314.86E-02I-1327.06E-02I-1339.86E-02I-1341.09E-01I-1359.42E-02Particulates in Ci/secCs-1348.53E-03Cs-1362.71E-03Cs-1375.91E-03Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.143 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 10:00CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.080.27Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.144 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 10:23Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 4.14E-01 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.5.65E+017.05E+017.11E+022.93E+021.07E+031.80E+041.54.40E+015.45E+015.65E+022.31E+028.51E+021.43E+042.03.07E+013.76E+014.22E+021.71E+026.31E+021.07E+043.02.12E+012.73E+012.73E+021.03E+024.03E+026.91E+034.01.68E+012.16E+012.19E+028.02E+013.21E+025.55E+034.031.68E+012.16E+012.19E+028.02E+013.21E+025.55E+035.01.25E+011.66E+011.71E+026.16E+012.49E+024.34E+037.07.56E+001.01E+011.08E+023.80E+011.56E+022.74E+0310.05.08E+007.07E+008.07E+012.51E+011.13E+022.05E+03Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 102304.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miPAGs Exceeded in Designated Areas* *

Classification: General Emergency * * *Release Rates (Ci / sec)Particulate2.57E-01 (1.5%)Iodine6.31E+00 (37.2%)Noble Gas1.04E+01 (61.3%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.145___________________________________________PByJohnD.Fisherat9:12am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 10:23Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.90E-02Kr-85m4.21E-01Kr-878.39E-01Kr-881.16E+00Xe-131m2.49E-02Xe-1333.70E+00Xe-133m1.17E-01Xe-1359.68E-01Xe-1383.11E+00Iodines in Ci/secI-1317.28E-01I-1321.06E+00I-1331.48E+00I-1341.63E+00I-1351.41E+00Particulates in Ci/secCs-1341.28E-01Cs-1364.06E-02Cs-1378.87E-02Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.146 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 10:23CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.080.27Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.147 Dose AssessmentColumbia Generating StationSunday, March 29, 2015 10:01Method: Detailed Assessment - Monitored ReleaseRelease Pathway: <RCS> <RW Bldg> <Exhaust> <Env>PRF: 4.00E-01Drywell HUT: = N/ADrywell Sprays: = N/ASupp Pool HUT: = N/ASupp Pool Status: = N/ARx Bldg HUT: = N/ASBGT Filters: = N/ATurb Bldg HUT: = N/ARW Bldg HUT: = < 2 HoursSource Term: Reactor Core Accident - CladCGS 33ft TowerTime After S/D (hh:mm): 0:00Wind: From 330° @ 5 mphRelease Duration (hh:mm): 3:00ETE (hh:mm): [N/A ]Stability Class: EPrecipitation: NoneMonitor: RW BldgReadings: 2.76E-01 uCi/ccFlowrate: 84000 CFMDistance(Miles)ExposureRate(mR/hr)ExternalPlume DDE(mRem)InhalationCEDE(mRem)DepositionGround DDE(mRem)TEDE(mRem)CDEThyroid(mRem)S.B.3.78E+014.70E+014.74E+021.96E+027.17E+021.20E+041.52.94E+013.64E+013.77E+021.54E+025.67E+029.52E+032.02.05E+012.51E+012.82E+021.14E+024.21E+027.12E+032.241.68E+012.09E+012.31E+028.88E+013.41E+025.85E+033.01.42E+011.82E+011.82E+026.86E+012.69E+024.61E+034.01.12E+011.44E+011.46E+025.35E+012.14E+023.70E+03 5.08.32E+001.10E+011.14E+024.11E+011.66E+022.89E+03 7.05.04E+006.72E+007.20E+012.53E+011.04E+021.83E+0310.03.38E+004.71E+005.38E+011.68E+017.53E+011.37E+03Assessment Data Results Saved to File:Columbia Generating Station 10Miles Monitored Release 03292015 100106.URI7Evacuation Areas From 0 to 10 Miles 1 2 3 4 2miPAGs Exceeded in Designated Areas* *

Classification: General Emergency * * *Release Rates (Ci / sec)Particulate1.72E-01 (1.5%)Iodine4.20E+00 (37.2%)Noble Gas6.91E+00 (61.2%)Reviewed By: ________________________________________Page 1 of 3Columbia Generating Station / 2.0.1.0NE-02-09-12 Rev 3, pa g e A.148_____________________________________________PaByJohnD.Fisherat9:13am,Mar31,2015 Isotopic Release RatesColumbia Generating StationSunday, March 29, 2015 10:01Method: Detailed Assessment - Monitored Release \ Source Term: Reactor Core Accident - CladNoble Gasses in Ci/secKr-851.26E-02Kr-85m2.81E-01Kr-875.59E-01Kr-887.73E-01Xe-131m1.66E-02Xe-1332.47E+00Xe-133m7.82E-02Xe-1356.46E-01Xe-1382.07E+00Iodines in Ci/secI-1314.86E-01I-1327.06E-01I-1339.86E-01I-1341.09E+00I-1359.42E-01Particulates in Ci/secCs-1348.53E-02Cs-1362.71E-02Cs-1375.91E-02Sb-1270.00E+00Sb-1290.00E+00Te-129m0.00E+00Te-131m0.00E+00Te-1320.00E+00Ba-1400.00E+00Sr-890.00E+00Sr-900.00E+00Sr-910.00E+00Mo-990.00E+00Ru-1030.00E+00Ru-1060.00E+00La-1400.00E+00Y-910.00E+00Ce-1440.00E+00Np-2390.00E+00Page 2 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.149 Additional Meteorological InputsColumbia Generating StationSunday, March 29, 2015 10:01CGS 33ft TowerWind Speed: 5.0 mphWind Direction From: 330°Delta T:Stab Class: EPrecip: NoneMiscellaneous Inputs and DataRelease Point Elevation: 20 metersPlume Exposure Duration (Release duration + Plume travel time): 5.00 hour0 days 0 hours 0 weeks 0 months sAdditional Monitor Information:RW Bldg reads in units of uCi/cc- Conversion Factor: 1.0000E+06- Background Subtract: 2.5400E-06

- Isotopic Conversion Factors are in place for this monitor and were used in the calculation.)

EDE to TEDE RatiosDistanceEDE / TEDE Ratio with IodineEDE / TEDE Ratio without Iodine2 - Miles0.080.275 - Miles0.090.2910 - Miles0.080.27Page 3 of 3Columbia Generating Station / 2.0.1.0 NE-02-09-12 Rev 3, pa g e A.150 ENERGY NORTHWESTMANUAL CALCULATION Page D.0Cont'd On Page D.1Calculation No.NE-02-09-12Prepared By/DateLS Woosley3/29/15Verified by/DateJD Fisher3/30/15Revision No.

3REV.BARAppendix DSupport Spreadsheets from Chemistry Dept.Description #Pages Page label ranges DELETED 1 Derivation of intermediate range ODCM alarm, and PPM 16.14.1 36 D.2 - D.37 DELETED 33 PPM 5.2.1 & SAG2 Table PC-1 input and ODCM spreadsheet cases that support it 40 D.72 - D.112 18694 R4 ENERGY NORTHWEST MANUAL CALCULATION PageD.0 Cont'd On Page D.1 Calculation No. NE-02-09-12 Prepared By/Date LS Woosley 3/29/15 Verified by/Date JD Fisher 3/30/15 Revision No.

3 REV.BAR18694 R4 Appendix D Support Spreadsheets from Chemistry Dept.

Description#PagesPagelabelrangesDELETED1 DerivationofintermediaterangeODCMalarm,andPPM16.14.136D.2-D.37DELETED33 PPM5.2.1&SAG2TablePC 1inputandODCMspreadsheetcasesthatsupportit40D.72-D.112 NE-02-09-12 003 page D.1 of 76 Reactor Building Low Range Monitor Setpoint Calculation This spreadsheet was derived from PPM 16.14.1 Rev 2 (ODCM dispersion value changes) and l/E 2-94-1312 loop uncertainties/instrument drift Reactor Building Low Range Monitor PRM*RE-1 A Gas Mixture See ODCM Table 3-15 and FSAR Table 11.3-1 X/Qj 8.20E-07 sec/m3 X/Qj for the Reactor Building release pathway from ODCM Table 3-3. Fj 0.4 Forty percent (40%} of the site boundary dose rate limit Is allocated to the Reactor building, Fj is 0.4 Rj 4.48E+07 cc/sec The maximum exhaust flow rate (Rj) is 4.48E+07 cc/sec (95,000 cfm). E(Xe-133) 5.51E+05 ccps/uCi/cc Xenon-133 efficiency (Gas Calibration factor from PPM 16.1.2 Rev 7) Bkg 5.50E+02 cps Background step 4.13 value., Based on instrument range, accuracy, and the ability to accurately read instrument values, select an Upper level that is less than or Upper Level 1 1.00E+03 1550 equal to the maximum allowable setpoint value determined in Step 4.13 Turbine Building Low Range Monitor (TEA*RE-13)

Gas Mixture See FSARTable 11.3-7 X/Qj 1.50E-05 sec/m3 X/Qj for the Turbine Building release pathway from ODCM Table 3-3. Fj 0.4 Forty percent { 40%) of the site boundary dose rate limit is allocated to the Turbine building.

Fj is 0.4. Rj 1.79E+08 cc/sec The maximum exhaust flow rate (Rj) is 1.79E+OB cc/sec (380,000 cfm). E(Xe-133) 4.83E+07 cpm/uCi/cc Xenon-133 efficiency cpm/uCi/cc From PPM 16.2.1 Rev 6 Bkg 40 cpm Background step 4.13 value= Based on instrument range, accuracy, and the ability to accurately read instrument values, select an Upper Level that is less than or Upoerlevel 4.80E+03 4850 equal to the maximum allowable setpoint value determined in Step 4.13. Radwaste Bulldlng Low Range Monitor (WEA-RE-14)

Gas Mixture See FSAA Table 11.3-7 X/Qj 1.50E-05 sec/m3 X/Qj for the Aadwaste Building release pathway from ODCM Table 3-3. Fj 0.2 Twenty percent (20%) of the site boundary dose rate limit is allocated to the Radwaste building.

Fj is 0.2. Ai 3.91E+07 cc/sec The maximum exhaust flow rate (Ai) Is 3.91 E+07 cc/sec (83,000 elm) E(Xe-133) 4.83E+07 cpm/uCi/cc Xenon-133 effic i ency cpm/uCi/cc from PPM 16.3.1 Rev 7 Bkg 36 cpm Background step 4.13 value= Based on instrument range, accuracy, and the ability to accurately read instrument values, select an Upper Level that is less than or Upper level 2.67E+04 26718 equal to the maximum allowable setpoint value determined in Step 4.13. Mechanical Vacuum Pump (AR-RIS-21)

Gas Mixture Setpoint Calculation 98-01 of 3/3198 & B&R Calculation 5.03.01 of 3/80 by E Stergokes X/Qj 8.20E-07 sec/m3 X/Oj for the Reactor Building release pathway from ODCM Table 3-3. Fj 0.4 Forty percent (40%) of the site boundary dose rate limit is allocated to the Reactor building, Fj is 0.4 Rj 1.13E+06 cc/sec The maximum exhaust flow rate (Rj) is 1.13E+06 cc/sec (2400 cfm) Xenon-133 efficiency mR/hr/uCi/cc from Setpoint Calculation 98-01. tsoshield calculation of initial mixture=0.34 mr/hr. (0.34/4.56E-E(Xe-133) 7.14E+01 mR/hr/uCi/cc 3)=71.3686 mR/hr/uCi/cc

0.1 Background

--'7 (,), ::...-Bkg cpm Step 4.13 value= Based on instrument range, accuracy, and the ability to accurately read instrument values, select an Upper level that Is less than or equal to the maximum allowable setpoint value determined in Step 4.13. Upper Level 7.5 7.6 F1<<rn -N,'E -, -*' J), z._ GaseousEffluentMonitorSetpointCalculationsRev7.xls, Inputs Page 1of1 9/29/2011 NE-02-09-12 003 page D.2 of 76 Reactor Building Setpoint Calculation Table4.3a Nuclide Mii MTi lTii K r83m 6.47E-05 2.25E-03 2.88E-02 K r85m 1.25E-04 2.25E-03 5.57E-02 Kr87 3.35E-07 2.25E-03 1.49E-04 K r88 3.35E-04 2.25E-03 1.49E-01 K r89 4.02E-04 2.25E-03 1.79E-01 Xe131m 3.35E-07 2.25E-03 1.49E-04 Xe133m 6.25E-06 2.25E-03 2.78E-03 Xe133 1.83E-04 2.25E-03 8.15E-02 Xe135m 1.54E-04 225E-03 6.86E-02 Xe135 4.91E-04 2.25E-03 2.19E-01 Xe137 1.SOE-05 2.25E-03 6.66E-03 Xe138 4.69E-04 2.25E-03 2.09E-01 Sum 2.25E-03 1.00E+OO Table 4.4a Maximum Release Rate Nuclide rrii Ki (rrii)(Ki)

Kr83m 2.88E-02 0.0756 2.18E-03 Kr85m 5.57E-02 1170 6.51E+01 Kr87 1.49E-04 5920 8.83E-01 Kr88 1.49E-01 14700 2.19E+03 Kr89 1.79E-01 16600 2.97E+03 Xe131m 1.49E-04 91.5 1.36E-02 Xe133m 2.78E-03 251 6.99E-01 Xe133 8.15E-02 294 2.40E+01 Xe135m 6.86E-02 3120 2.14E+02 Xe135 2.19E-01 1810 3.96E+02 Xe137 6.66E-03 1420 9.46E+OO Xe138 2.09E-01 8830 1.84E+03 Sum of rrij*Ki= 7.72E+03 Reactor Building Low Range Monitor Setpoint Calculation Mij Measured or estimated concentration o f nuclide i in release path j (µCi/cc) MTJ Measured o r estimated t otal concentration of all gases in release path j (µCi/cc) rrij Fraction o f each nuclide released (unitless)

Whole Body Dose Rate QTj Maximum Release Rate based on Whole Body Dose (uCi/sec)

Fj Fraction of total dose allocated to this release pathway (Dimensionless) 500 Whole body dose rate limit (mrern/yr)

X/Qi Maximum nonnalized diffusion coefficient for this pathway at and beyond the site boundary (sec/m3) QTj= QTj= Ki Total whole body dose factor due to gamma emission from nuclide i, as listed in the ODCM or Reg Gulde 1.109, revision 1 (mrern/year per µCilm3) rrij I s the fraction o f t he total activity for nuclide i (Dimensionless) m Total number of nuclides in the gaseous effluent Release pathway = I 3:16E+04 luCi/sec hYm

.. 1 13' v.;* , ... ,

i1 *;.-* v ,.._: ... , GaseousEffluentMonitorSetpointCalcu l ationsAev7.x l s , REACalculations Page 1of3 9/29/2011 NE-02-09-12 003 page D.3 of 76 Reactor Building Low Range Monitor Setpoin t C alculation Table 4.5a Maximum Release Rate Nuclide rrii Li+ 1.1Mi (rrii)(Li+

1.1 Mil Kr83m 2.BBE-02 0 0.00E+OO Kr85m 5.57E-02 2.81E+03 1.56E+02 Kr87 1.49E-04 1.65E+04 2.46E+OO Sk i n Dose Calculation Kr88 1.49E-01 1.91E+04 2.85E+03 3000 Dose Rate Limit Kr89 1.79E-01 2.91E+04 5.21E+03 Xe131m 1.49E-04 6.48E+02 9.66E-02 Q Tj= 4.00E-01 3.00E+03 = I --1:2oE+o5 I uCi/sec Xe133m 2.78E-03 1.35E+03 3.76E+OO 8.20E-07 1.22E+04 Xe133 8.15E-02 6.94E+02 5.66E+01 Xe135m 6.86E-02 4.41E+03 3.03E+02 Xe135 2.19E-01 2.30E+03 5.03E+02 Xe137 6.66E-03 1.39E+04 9.26E+01 Lowest Dose Rate Value Xe138 2.09E-01 1.43E+04 2.99E+03 QTj = I 3.16E+04 luCi/sec Sum(rrii (Li+ 1.1Mi) = 1.22E+04 Step 4.7 Table 4.Ba Maximum Allowable Value Maximum Nuclide Concentration CTj = (OT1/Rj) Nuclide rrii CTi Cii R j = Release Rate Kr83m 2.88E*02 7.06E-04 2.03E*OS Kr85m 5.57E-02 7.06E*04 3.93E-OS Kr87 1.49E*04 7.06E*04 1.05E-07 CTj = maximum allowed concentra,...tio_n

____ _ C TJ = I 3.16E+04 I = I 7.06E-04 luCi/cc 4.48E+07 Kr88 1.49E-01 7.06E-04 1.05E-04 Kr89 1.79E-01 7.06E-04 1.26E-04 Xe131m 1.49E*04 7.06E-04 1.05E-07 Xe133m 2.78E-03 7.06E-04 1.96E-06 Xe133 8.15E-02 7.06E-04 5.75E-05 Xe135m 6.86E-02 7.06E-04 4.84E-05 Xe135 2.19E-01 7.06E-04 1.54E-04 Xe137 6.66E-03 7.06E-04 4.70E-06 Xe138 2.09E-01 7.06E-o4 1.47E-04 GaseousEffluentMoni1orSetpointCalculationsRev7.xls, REACalculations Page 2 of 3 '/'. .u. v. I D <t , I 9/29/201 1 NE-02-09-12 003 page D.4 of 76 Table4.9a Relative Efficiency Gamma Relative Nuclide Abundance Abundance E(Xe-133}

Kr83m 0.09 0.245 5.51E+05 Kr135m 0.74 2.016 5.51E+05 Kr137 0.837 2.281 5.51E+05 Kr138 1.372 3.738 5.51E+05 Kr139 1.6 4.36 5.51E+05 Xa131m 0.0196 0.053 5.51E+05 Xe133m 0.14 0.381 5.51E+05 Xe133 0.367 1 5.51E+05 Xe135m 0.81 2.207 5.51E+05 Xe135 0.939 2.559 5.51E+05 Xe137 0.33 0.899 5.51E+05 Xe138 1.222 3.33 5.51E+05 Table 4.11a Counts above Background Nuclide Cil Eil C.Rii Kr83m 2.03E*05 1.35E+05 2.75E+OO KrBSm 3.93E-05 1.11E+06 4.36E+01 Kr87 1.05E-07 1.26E+06 1.32E-01 Kr88 1.0SE-04 2.06E+06 2.17E+02 Kr89 1.26E-04 2.40E+06 3.03E+02 Xe131m 1.05E-07 2.92E+04 3.07E-03 Xe133m 1.96E-06 2.10E+05 4.12E-01 Xe133 5.75E-05 5.51E+05 3.17E+01 Xa135m 4.84E-05 1.22E+06 5.89E+01 Xe135 1.54E-04 1.41E+06 2.18E+02 Xe137 4.70E-06 4.95E+05 2.33E+OO Xe138 1.47E-04 1.B3E+06 2.70E+02 C.Rj= 1.00E+03 Reactor Building Low Range Monitor Setpoint Calculation Eii 1.35E+05 1.11E+06 1.26E+06 2.06E+06 2.40E+06 2.92E+04 2.10E+05 5.51E+05 1.22E+06 1.41E+06 4.95E+05 1.B3E+06 lJ.S d i n the following table. Eij= Effluent monitor detection efficiency f or nuclide i (ccps/µCi/cc)

C.Rj= Cij= Eij = C oun t rate above background (cps) Maximum acceptable concentration o f noble gas i (µCi/cc) Effluent monitor detection efficiency for nuclide i (ccps/µCi/cc)

Reactor Building Step 4.13 Maximum Allowable Setpoint Bkg+C.Rj = I 1,550 I Step 4.14 Upper Level (UL) = I I "'.-_. I -( ._:. / "/ .'

' (" " {a -**------s:-...-v'_.i:;, ... , ***""'""f

,! (1 Note, there is only one alarm on this system Step 4.16.2 Alarm UL Nominal Lower Level 1,000 I 910 191% of UL 82082% of UL GaseousEffluentMonitorSetpoinlCalculationsRev7.xls, REACalculatlons Page 3 of 3 9/29/20 11 NE-02-09-12 003 page D.5 of 76 NE-02-09-12, Rev 1 A ppendix D R evision Notes Revision 4 contains a first cut at including loop uncertainties and instrument drift into the setpoint calculations Revision 5 takes out the loop uncertainty and instrument drift calculation as engineering detennined it unnecessary.

Revision 6 corrects the relative beta efficiencies and matches PPM 16.14.1Rev2 Revision 7 adds a sheet that determines the efficiency of the RD-52 to betas. GaseousEffluentMonitorSetpointCalculationsRev? .xis PAGE 1of6 Page D.6 9 9/1/2011 NE-02-09-12 003 page D.6 of 76 NE-02-09-12, Rev 1 Appendix D Page D.7 INPUT VALUES This spreadsheet was derived from PPM 16.14.1 Rev 2 (ODCM dispersion value changes) and l/E 2-94-1312 l oop uncertainties/instrument drift Reactor Gas MixU1re X/Qj Fj Rj E(Xe-1 Bkg Uooer Level itor PRM-RE-1A See ODCM Table 3-15 and FSAR Table 11.3-1 X/Qj for the Reactor Building release pathway from OOCM Table 3-3. Forty percent (40%) of the site boundary dose rate limit is allocated to the Reactor building, Fj is 0.4 The maximum exhaust flow rate (Rj) is 4.48E+07 cctsec (95,000 cfm). Xenon-133 efficiency (Gas Calibration factor from PPM 16.1.2 Rev 7) Background ue = Based on instrument range, accuracy, and the abi li ty to accurately read instrument values, select an Upper Level that is less than or equal to the maximum allowable setpoint value determined in Step 4.13 Turbine Building Low Range Monitor (TEA-RE-13)

Gas Mixture See FSAR Table 11.3-7 X/Qj 1.50E-05 sedm3 X/Qj for the Turbine Building release pathway from ODCM Table 3-3. Fj 0.4 Forty percent (40%) of the site boundary dose rate limit is allocated to the Turbine building Fj is 0.4. RJ 1.79E+08 cclsec The maximum exhaust flow rate (RJ) is 1.79E+08 c c/sec (380,000 cfm) E{Xe-133) 4.83E+07 cpm/uCi/cc Xenon-133 efficiency cpm/uCilcc From PPM 16.2 1 Rev 6 Bkg 40 cpm Background Step 4.13 value= Based on instrument range , accuracy, and the ab ili ty to accurately read instrument values, select an Upper Level that 1s less than or Uooer Level 4.80E+03 4850 equal to the maximum allowable setpoint value determined in Step 4.13. Radwaste Building Low Range Monitor (WEA-RE-14)

Gas Mixture See FSAR Table 11.3-7 X/Qj 1.50E-05 sec/m3 X/Qj for the Radwaste Building release pathway from ODCM Table 3-3. FJ 0.2 Twenty percent (20%) of the site boundary dose rate limit is allocated to the Radwaste building. FJ 1s 0.2. Rj 3.91E+07 cc/sec The maximum exhaust flow rate (Rj) is 3.91E+07 ce/sec (83,000 cfm) E(Xe-133) 4.83E+07 cpm/uCi/cc Xenon-133 efficiency cpm/uCi/cc from PPM 16.3.1 Rev 7 Bkg 36 cpm Background Step 4.13 value= Based on instrument range, accuracy, and the ab ili ty to accurately read i n strume n t v a lues, select an Upper Level that is less than or Upper Level 2.67E+04 26718 equal to the maximum allowable s e tpoint v a l ue d ete rmined in St e p 4.13. GaseousEffluentMonitorSetpo i ntGalculationsRev7

.xJs. Inputs PAGE20F6 9/1/20 1 1 '1 NE-02-09-12 003 page D.7 of 76 NE-02-09-12, Rev 1 Appendix D Page 0.8 INPUT VALUES Mechanical Vacuum Pump (AR-RIS-21)

Gas Mixture Selpoint Calculation 98-01 of 3/3/98 & B&R Calculation 5.03.01 of 3/80 by E Stergokes X/Qj 8.20E-07 sec/m3 X/Qj for the Reactor Building release pathway from ODCM Table 3-3. Fj 0.4 Forty percent (40%} of the site boundary dose rate limit is allocated to the Reactor building, Fj is 0.4 Rj 1.1 3E+06 cc/sec The maximum exhaust now rate (RJ) is 1.13E+06 cc/sec (2400 cfm) Xenon-133 efficiency mR/hr/uCi/cc from Selpoint Calculation 98-01. lsosh1eld calculation of initial mixture=0.34 mr/hr. (0.34/4.56E-E(Xe-133) 7.1 4E+01 rnRJhr/uCi/cc 3)=71.3686 mR/hr/uCi/cc Bkg 0.1 cpm Background step 4 13 value= Based on instrument range, accuracy, and the ability to accurately read instrument values, select an Upper Level that is less than or Upper Level 7.5 7.6 equal to the maximum allowable setpoint value determined in Step 4.13. GaseousEffluentMonitorSetpointCalculationsRev 7 .xis, Inputs PAGE 3 0F6 9/1/2011 v NE-02-09-12 003 page D.8 of 76 NE-02-09-12, Rev 1 Reactor Building Setpoint C alculation Table4.3a Nuclide Mii MTi nii Kr83m 6.47E-05 2.25E-03 2.88E-02 Kr85m 1.25E-04 2.25E-03 5.57E-02 Kr87 3.35E-07 2.25E-03 1.49E-04 Kr88 3.35E-04 2.25E-03 1.49E-01 Kr89 4.02E-04 2.25E-03 1.79E-01 Xe131m 3.35E-07 2.25E-03 1.49E-04 Xe133m 6.25E-06 2.25E-03 2.78E-03 Xe133 1.83E-04 2.25E-03 8.15E-02 Xe135m 1.54E-04 2.25E-03 6.86E-02 Xe135 4.91E-04 2.25E-03 2.19E-01 Xe137 1.SOE-05 2.25E-03 6.66E-03 Xe138 4.69E-04 2.25E-03 2.09E.01 Sum 2.25E-03 1.00E+OO Table 4.4a Maximum Release Rate Nuclide rrii Ki f rriillKi\

Kr83m 2.88E-02 0.0756 2.18E-03 Kr85m 5.57E-02 1170 6.51E+01 Kr87 1.49E-04 5920 8.83E-01 Kr88 1.49E-01 14700 2.19E+03 Kr89 1.79E-01 16600 2.97E+03 Xe131m 1.49E-04 91.5 1.36E-02 Xe133m 2.78E-03 251 6.99E-01 Xe133 8.15E-02 294 2.40E+01 Xe135m 6.86E-02 3120 2.14E-t-02 Xe135 2.19E-01 1810 3.96E-t-02 Xe137 6.66E-03 1420 9.46E+OO Xe138 2.09E-01 8830 1.84E+03 Sum of rrij*Ki* 7.72E+03 Appendix D Page D.9 Reactor Building Low Range Monitor Setpoint Calculation Mij Measured or estimated concentration of nuclide i in release path j (µCi/cc) MTj Measured or estimated total concentration o f all gases in release path j (µCi/cc) rrij Fraction of each nuclide released (unitless) Whole Body Dose Rate QTj Maximum Release Rate based on Whole Body Dose (uCi/sec)

Fj Fraction of total dose allocated to this release pathway (Dimensionless) 500 Whole body dose rate limit (mrem/yr)

X/Qi Maximum normalized diffusion coefficient for this pathway at and beyond the site boundary (sec/m3) QTj= QTj = Ki Total whole body dose factor due to gamma emission from nuclide i, as listed in the ODCM or Reg Guide 1.109,.revision 1 (mrerntyear per µCi/m3) rrij Is the fraction of the t otal activity for nuclide i (Dimensionless) m Total number of nuclides in the gaseous effluen t j Release pathway = I 3.16E+04 nluCi/sec GaseousEffiuentMonilorSetpointCalculationsRev7.xls, REACalculations Page 4 of 6 9/1/2011 0 ..'....s>

NE-02-09-12 003 page D.9 of 76 NE-02-09-12, R ev 1 Appendix D Page D.10 Reactor Building Low Range Monitor Setpoint Calculation Table 4.5a Maximum Release Rate Nuclide mi Li+1.1Mi 11Tiil(Li+1.1 Mi) Kr83m 2.88E-02 0 O.OOE+OO Kr85m 5.57E-02 2.81E+03 1.56E+02 Kr87 1.49E*04 1.65E+04 2.46E+OO Skin Dose Calculation Kr88 1.49E-01 1.91E+04 2.85E+03 3000 Dose Rate Limit Kr89 1.79E-01 2.91E+04 5.21E+03 Xe131m 1.49E-04 6.48E+02 9.66E-02 OTJ= 4.00E-0 1 3.00E+03 = C 1.20E+05 luCiJsec Xe133m 2.78E-03 1.35E+03 3.76E+OO . 8.20E-07 1.22E+04 Xe133 8.15E-02 6.94E+02 5.66E+01 Xe135m 6.86E-02 4.41E+03 3.03E+02 Xe135 2.19E-01 2.30E+03 5.03E+02 Xe137 6.66E-03 1.39E+04 9.26E+01 Lowest Dose Rate Value Xe138 2.09E-01 1.43E+04 2.99E+03 QTj = I 3.16E+04 fuCiJsec Sum(nii)(Li+1

.1 Mi)= 1.22E+04 Step4.7 Table 4.8a Maximum Allowable Value Maximum Nuclide Concentration CTj = (QTj/Rj) Nuclide nii CTi Cii Rj = Release Rate Kr83m 2.88E-02 7.06E-04 2.03E-05 Kr85m 5.57E-02 7.06E-04 3.93E-05 Kr87 1.49E-04 7.06E.Q4 1.0SE-07 CTJ = maximum allowed concentra,..;..ti...;.,on""-----

CTJ = I 3.16E+04 I = I 7.06E-04 luCi/cc 4.48E+07 Kr88 1.49E-01 7.06E-04 1.0SE-04 Kr89 1.79E-01 7.06E.Q4 1.26E-04 Xe131m 1.49E-04 7.06E-04 1.0SE-07 Xe133m 2.78E-03 7.06E-04 1.96E-06 Xe133 8.15E-02 7.06E-04 5.75E-05 Xe135m 6.86E-02 7.06E-04 4.84E-05 Xe135 2.19E-01 7.06E-04 1.54E-04 Xe137 6.66E*03 7.06E-04 4.70E-06 Xe138 2.09E-01 7.06E.Q4 1.47E-04 ..... -0 GaseousEffluentMonitorSetpointCalculationsRe117.xls, REACalculations Page 5 of 6 9/1/2011 NE-02-09-12 003 page D.10 of 76 NE-02-09-12, Rev 1 Appendix D Reactor Building Low Range Monitor Setpoint Calculation For Gamma Detectors (REA) the relative efficiencies is calculated in the following table. Table4.9a Relative Efficiencv Gamma Relative Nuclide Abundance Abundance E(Xe-133)

Kr83m 0.09 0.245 3.72E+08 Kr85m 0.74 2.016 3.72E+08 Kr87 0.837 2.281 3.72E+08 Kr88 1.372 3.738 3.72E+08 Kr89 1.6 4.36 3.72E+08 Xe131m 0.0196 0.053 3.72E+08 Xe133m 0.14 0.381 3.72E+08 Xe133 0.367 1 3.72E+OB Xe135m 0.81 2.207 3.72E+08 Xe135 0.939 2.559 3.72E+08 Xe137 0.33 0.899 3.72E+OB Xe138 1.222 3.33 3.72E+08 Table 4.11a Courrts above Background Nuclide Cii Eii C.Rii Kr83m 2.03E-05 9.11E+07 1.85E+03 Kr85m 3.93E-05 7.50E+08 2.95E+04 Kr87 1.0SE-07 8.49E+08 8.93E+01 Kr88 1.0SE-04 1.39E+09 1.46E+05 Kr89 1.26E-04 1.62E+09 2.05E+05 Xe131m 1.05E*07 1.97E+-07 2.07E+OO Xe133m 1.96E-06 1.42E+08 '2.78E+02 Xe133 5.75E-05 3.72E+OB 2.14E+04 Xe135m 4.84E-05 8.21E+08 3.97E+04 Xe135 1.54E-04 9 52E+08 1.47E+05 Xe137 4.70E-06 334E+08 1.57E+03 Xe138 1.47E-04 1.24E+09 1.82E+05 C.R1= 7.75E+05 Eii 9.11E+07 7.SOE+OB 8.49E+08 1.39E+09 1.62E+09 1.97E+07 1.42E+08 3.72E+OB 8.21E+08 9.52E+08 3.34E+08 1.24E+09 Eij = C.Rj= Cij= Eij = Step 4.13 Effluent monitor detection efficiency for nuclide i (ccps/µCi/cc)

Count rate above background (cps) Maximum acceptable concentration o f noble gas i (µCi/cc) Effluent monitor detection efficiency for nuclide i (ccps/µCi/cc)

Reactor Building Maximum Allowable Setpoint .... =----. Bkg+C.Rj = I 776,300 I Step 4.14 Upper Level (UL) = I 71s-.-ooo I Note, there is only one alarm on this system Step 4.16.2 Alarm UL Nominal Lower Level 775,000 705,250 91 % of UL 635,500 82% of UL GaseousEffluentMonitorSetpointCalculationsRev7.xls, REACalculations Page 6 of 6 Page D.1 1 0 9/1/2011 NE-02-09-12 003 page D.11 of 76 NE-02-09-12, Rev 1 Appendix D Page 0.12 NUMBl!R 16.14.1 VOLUME NAME P e op l e* V i s i on* Solution s C O LUM B IA G E N E R ATING S TA TION PLANT PR OC ED U RES MA N UAL APPR OV E D B Y C MK -Rev isi on 2 ODCM IMPLEMENTlNG PROCEDURES SECTION SETPOINT CALCULATIONS TITLE GASEOUS MONITOR SETPOJNT DETERMINATIONS Setpoint Calcu l ation for (EPN): 'f"?M* CZ.C-\A J I \ ,r?f?/as Calculation Performed By:

Comments:

DATE 05111105 I To,,Complotod D"' .:c;b;bs Assigned Revi e wer: _ ......

___________

Date $:-Z6-D.S-RECEIVED MAY 2 6 2005 RECORDS STORAGE NUMBER REVISI ON PAGE 16.14.1 V a u t t iJ S i 7 2 8 8 7 8 G 7 i) i I of 18 / 1 NE-02-09-12 003 page D.12 of 76 NE-02-09-12, Rev 1 Append ix D Page D.13 .* TABLE OF CONTENTS 1.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 PREREQUISITES

.................................

.............

3 3.0 PRECAUTIONS AND LIMITATIONS

.................................

3 4.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 5.0 DOCUMENTATION

..............................

..............

18

6.0 REFERENCES

................................................

18 7.0 ATTACHMENTS

...............................................

18 16.1 4. l REVISION P AG E \i a u l t 20 9 2 7 2 0 8 8 0 7 0 1 2 of 18 I NUMBER 2 NE-02-09-12 003 page D.13 of 76 NE-02-09-12 , Rev 1 Append ix D Page 0.14 ,* 1.0 PURPOSE To provide instructions for determining the setpoint(s) for radiation monitors as required by ODCM RFO 6. 1.2. l. {R-5560} 2.0 PR E REQUISITES No n e 3.0 PRECAUTIONS ANP LIMITATIONS None 16.14. I REVISION PA GE \i a u t t iJ *;; 2 7 2 8 0 D 8 7 G l.3 o f 18 I NIA O H!R 3 NE-02-09-12 003 page D.14 of 76 NE-02-09-12, Rev 1 Append ix D Page 0.15 4.0 PROCEDURE 4.1 Due to the repetitious nature of these calculations, use of a spreadsheet is recommended.

If one is used, the data may be transferred to the corresponding tables in this procedure, or a hard copy of the spreadsheet may be printed and attached.

If a hardcopy is attached, mark the corresponding tables NIA, and reference the appropriate hardcopy.

It is recommended that any spreadsheet tables used be numbered to match the corresponding procedure table number. 4. 2 Based on rhe following, detennine the appropriate gas mixture to be used for this radiation monitor: {R-5559}, {R-5561},* {R-5562} 4.2.1 For the Reactor Bu il d in g: 1 6.14. l a. The values f ro m ODC M Table 3-15 are recommended, but a d iff erent m i x tu re may be selected based on operational conditions or expected e fflu e nt acti v i ty. Any mixture selected should be representative o f an e fflu e n t condition that could actually reach the setpoim. N.Q'.I:E:

The ODCM Table 3-15 values are for a design base mixture at 30 m i nutes decay, and produce a setpoint which is appropriate for operation o f the o ff gas system in the charcoal bypass mode. The setpo i nt result i ng f rom the use of these values is lower than the value obtained by us ing a gas m i xture appropriate for offgas system operation with the charco beds in service. b. If a gas mixrure other than ODCM Table 3-15 is used, it may be necessary to limit the operation of the off gas system to require the use of the charcoal beds. c. If a mixture other than ODCM Table 3-15 is used, document this fact and the reasoning for its use along with any operational limitations on the offgas treatment system, and attach to this procedure.

d. The setpoint for the Reactor Building effluent is on the Low Range o i o PRM-RE-lA.

e. X/QJ for the Reactor Building release pathway is 8.2E-07 sec/m 3 , from ODCM Table 3-3. f. Forty percent (40%) of the site boundary dose rate limit is allocated to the Reactor building, FJ is 0.4. g. The m3"imum exhaust flow rate (J9 is 4.48E+07 cc/sec (95,000 cfrn). RJ!VISION PAGE! Va u t '-i 3 *:; 2 l 2 8 8 / 8 8 7 8 14 o f18 4 NE-02-09-12 003 page D.15 of 76 NE-02-09-12, Rev 1 Appendix D Page 0.16 4.2.2 For the Turbine Building:

a. The values from FSAR Table 11.3-7 are recommended, but a different mixrure may be selected based on operational conditions or expected effluent activity.

b. If a mixrure other than FSAR Table 11.3-7 is used, document this fact, and the reasoning for its use, and attach to this procedure.

c. The setpoint for the Turbine Building effluent is on the Low Range Monitor, TEA-RJS-13.

d. XJQJ for the Turbine Building release pathway is l.5E-05 scclm', from ODCM Table 3-3. e. Forty percent (40%) of the site boundary dose rate limit is allocated to the Turbine building.

Fi is 0.4. f. The maximum exhaust flow rate is I. 79E+08 cc/f1ee (380,000 cfm). 4.2.3 For the Radwaste Building:

16.1 4.) a. The values from FSAR Table 11.3-7 are recommended, but a different mixture may be selected based on operational conditions or expected effluent activity.

b. If a mixture other than FSAR Table 11.3-7 is used, document this fact, and the reasoning for its use, and attach to this procedure.

c. The setpoint for the Radwaste Building effluent is on the Low Range Monitor, WEA-RJS-14.

d. X/QJ for the Radwaste Building release pathway is l.SE-05 f,e;C/m 3 , from ODCM Table 3-3. e. Twenty percent (20%) of the site boundary dose rate limit is allocated to the Radwaste building.

F; is 0.2. f. The maximum exhaust flow rate 09 is 3.91E+07 cc/sec (83,000 cfm). REVISION PAO! V a u L t 213 :3 2 7 L 8 fJ 1 8 0 7 8 1 5 of 18 5 NE-02-09-12 003 page D.16 of 76 NE-02-09-12, Rev 1 Append i x D Page D.17 NUMBER 4. 3 Detennine the fraction for each nuclide of total activity released by completing Table 4.3a as follows: {R-5564} Fraction=

where: M11 -Mii 7t .. --,, M Tj Measured or estimated concentration of nuclide i in re l ease path j. Measured or estimated total concentration of all gases in release path j. 4.3.1 Enter the se l ected nuc li de concentration or activity for each nuclide i n the Mg co l umn. Mark nuc li des no t present in the mixture NIA. 4.3.2 Enter the selec t ed total conc e n tr a ti on or activity for each nuclide in the M 11 column. 4.3.3 Calculate the fract i on for each app l icab l e nu cl i de and record i n the rt , 1 co lumn. Table 4.3a Nuclide Kr83m Kr85m Kr87 Kr88 Kr89 Xe l 3lm Xel33m Xe 1 33 Xe l 35m Xel35 Xe l 37 Xe 1 38 16.1 4.l 8 t:J 7 8 ":ti of 18 I llE VJSION 'v'OUtt 2 0 S27288 I PAGE 6 NE-02-09-12 003 page D.17 of 76 NE-02-09-12, Rev 1 Appendix D Page D.18 4.4 Oetennine the maximum release rate based on whole body dose by co m p l et i ng Table 4.4a as follows: Max release rate = where: 500 = = = m Fraction of total dose allocated to this release pathway (Dimensionless).

Whole body dose rate limit. Maximum normaJ i zed d i f fu sion coefficient for this pathway at and beyond the si te boundary (sec/m 1). Total who l e body dose factor due to gamma emission from nuc li de i , as li s t ed i n the ODCM or Reg Guide 1.109, revision l (mrem/year per µC i/m 3). I s lhe frac ti on o f th e to tal activity for nuclide i (Dimens i on l ess). To tal n u mber of nuc li d e s i n the gaseous effluent.

Release pathway. 4 4.1 E nt er lhe 7t 9 values f rom Ta bl e 4.3a. Mark nuclides not present in the m i xt u re NIA. 4.4.2 Multiply the value by its corresponding K;, and record the result in the Ki1tij column. 16.14.1 I RE VISIO N V a u l t 2 8 *3 2 7 2 G G 7 0 0 7 0 ii of 18 PAO£ 7 NE-02-09-12 003 page D.18 of 76 NE-02-09-12 , Rev 1 AppendixD Page D.19 4.4.3 Sum the values in the (1tij}{K,)

column. Table 4.4a Muimum Release Rate Nuclide 1tn K. (1tn)CIO Kr83m 2..<ose-'2..

0.0756 z. \'2h=* -3. Kr85m S S'1*-'2. 1170 l..S\S +\ Kr87 l.4<:te.-4 5920 8.9 3.E.-\ Kr88 1. t.:-\ 14700 2-\G Kr89 \ .1qe-1 16600 2 .<<11 E. Xe131m 1.49*-4 91.5 \.

-2 Xel33m 2.l'B F. _, 251

-' Xe133 ,c;:;..;::

-'L 294 Xel35m {,,.. 8foE. ... 2. 3120 2. I 4: f!. -tZ X e 135 1810 .3 ;.z Xel37 l, j.L r.:-1420 Xe138 2-0°J ,;; -\ 8830 1.84*.+3 *.t'"": <J L 1t;;*K.= 7.72.E..-+3

... ,.,..., ... '\ ... " . :*_,,.._ . . 4.4.4 Determ i ne QTJ by entering the approp ri ate values for the applicable effluent pathway i n the spaces provided below and completing the indicated calculat i on; {R-5565} QT.= ( 0.l\-)500 :: 3..\feE.+:\cµCi/sec) J ( 8.'2E-1 16.14.l \/autt ltEVISI ON I PAO E 28 9 2 7 2 8 8 8 7 8 1 8 of 1 8 8 NE-02-09-12 003 page D.19 of 76 NE-02-09-12, Re v 1 Append ix D Page D.20 4.5 Detennine the maximum release rate based on skin dose by completing Table 4.5a as NUMBER follows: {R-5567} F.3000 Max release rate = Q 1. = J (µCi/sec) l m where: FJ = 3000 = X/Qi = Li Mi 'ltij m = = ..!. I; (Li + 1.1Mi)(1t;)

Qj i*l Fraction of total dose allocated to this re l e ase pathw ay (Dimensionless)

Skin dose limit Maximum normalized diffusion coefficient for this pathway at and beyond the site boundary (sec/m 3) Skin dose factor due to beta emission from nuclide i, as listed in the ODCM or Reg Guide 1.109, revision 1 (mrem/year per µ.Ci/m 3) Air dose factor due to gamma emission from*nuclide i, as listed in the ODCM or Reg Guide 1.109, revision I (mrem/year per l'Ci/m 3) Is the fraction of the wtal activity for nuclide i (Dimensionless)

Total number of nuc li des i n the gase-0us effluent Release pathway 4.5.1 Enter the tt ij values from Tab l e 4.3a. Mark nuclides not present in the mil'tture NI A. 4.5.2 Multiply the Tt 1 J value by i ts corresponding L 1 + LIM 1 , and record the result in the (Li+ 1.1 MJ7t iJ column. 4.5.3 Sum the va l ues in the + l.lMJ column. 16.1 4. l I R EVISION 'v' a u t t 2 1.:; *3 2 7 2 8 13 Pit.O E G 8 7 8 19of18 I 9 NE-02-09-12 003 page D.20 of 76 NE-02-09-12, Rev 1 Appendix D Page D.21 Table4.5a Maximum Release Rate Nuclide 'It;; L.+ l.lM (1t,.)(L,+

1. IM,) Kr83m z..eai:::-2 0 D Kr85m 'S.'5.1 £-2. 2.81E+03 \ .c::;:;(o + '2. Kr87 1.4<\ E..-4 I.65E+04 Kr88 I.91E+04 Kr89 1.1qs-l 2.91E+04 Xel3lm \ .

-4 6.48E+02 i:. -'2. Xcl33m l.35E+03 s.1(pe. *O X e l33 6.946+02 \ Xel35m 4.41E+03 ,3.038-\-'2.

Xel35 2.30E+03 s .()3e-T2..

Xe137 l.s>.bls, 1.39E+04 Xel38 e;--1 1.43E+04 2_<i9 .... ._,..,,,.,,.!,, ....

L(1t,J(L.+

1.lM;) = '-2.2 e-T4 NUMBER 4.5.4 by entering the appropriate values for the applicable efflue n t pathway in the spaces provided below, and completing the ind i cated calculation:

c o.4 )3000 Q 1) = ( g

)(\ ) \ .2*. :S (µCi/sec)

REV ISION PAGE 16.1 4.1 V a u l t 2.3 *:; 7 :-n:.i 8 8 G 7 G JI o of 1 8 I 10 NE-02-09-12 003 page D.21 of 76 NE-02-09-12, Rev 1 Append ix D Page D.22 4.6 Compare the whole body and skin QTJ values calculated above and select the lower of the two values. Record the selected value below: {R-5563} QTj = .:s . \ t.e 1:;: -'I 4-4. 7 Determine the maximum allowable concentration as follows: {R-5566} Max concentration

= CTj = Qr;(µCi/cc)

R; M . c O rj ax concentr au on = T l = -= =

w h e r e: J-.blot.--.\-cµ.Cilcc)

= Total all owed co n c e ntrat i on of all noble gases (JiCi/cc)

Q 1) Maxi mum acceptab le release rate for all noble gases (µC i/sec) = E ffl uent re l ease rate (cc/sec) 4.8 Determ i ne the maximu m a ll owab l e co n ce nt ration for each nuclide by complet i n g Table 4.8a as fo ll ows: NUMBER Max concentr a tio11i = C;; = x 1;Cr i (µC i/cc) where: = As defined i n Sect i on 5.3 = As defined above 4.8.l Enter the 7tu values from Tab l e 4.3a. Mark nuclides not present NIA. 4.8.2 Enter the Cq value from Step 4.8. 4.8.3 Multiply the app li cab l e '!t i v alu es by th e Cq value, and record the result in the cij column. Rl!VJSIOl'I PAO£ 1 6.14.1 ' a u t t 2 *:; ,., -7 1 G 8 7 tie 7 em of 18 11 NE-02-09-12 003 page D.22 of 76 NE-02-09-12, Rev 1 App e n d ix D Page D.23 Table 4.8a Maximum Nuclide Concentration Nuclide n. c.. c .. Kr83m 2.sBc.-z..

-'S Kr85m S.'S7r -'Z... -cs Kr87 I

,-:; -4 \.oS\:.. -1 Kr88 1.4-'h;:-\

\ *05*.-4-Kr89 1.1q e -\ \

-4 Xe l 31m l-49i== -4 I. oSf::.-1 Xe 13 3m '2.

-l Xe l3 3 fJ.\'SC: -z. s.rsr-s Xe l 35m ... t:=.-2 4.84-G-S Xe 13 5 ?. \<1 ,.::: -\ t.s ..t. i.= -.:\-Xe l 37 4-70 !=-In Xe l3 8 2.oq e-\ 'I 1-41E"-+ PAGE Rl!.V I SION V a u t t 28 S 2 7 .2 G G 8 G 7 13 i2of18 16.14. l I 12 NE-02-09-12 003 page D.23 of 76 NE-02-09-12, Rev 1 Append i x D Page D 24 4.9 For gamma radiation detectors, (REA), determine the efficiency for the applicable nuclides by completing Table 4. 9a as follows: 4.9. l Enter the Xem efficiency in column for Ex .. 133* 4.9.2 Multiply the Relative Abundance for nuclides present in lhe mixture times the Ex.,.m, and record the result in the Eg column. Mark nuclides not present in the mixture NIA. Table 4.9a Relative Efficiency Gamma Relative I ' , ' " Nuclide Abundance Abundance Ev ..... \ E.. ..

Kr83m 0.09 0.245 .12 \-=--t9-. ' l Kr85m 0.74 2.016 Kr87 0.837 2.281 'iJ.+'lE.+8 Kr88 1.372 3.738 Kr89 1.6 4.360 J,IPZ.t:: Xel31m 0.0196 0.053 L't76-+1 Xe133m 0.14 0.381 1.+z..e;+8 Xel33 0.367 1.000 3.72G-t8 Xel35m 0.81 2.207 .B.2\*. .. 2 Xel35 0.939 2.559 q SZ£.-t8 Xel37 0.33 0.899 ,

Xel38 1.222 3.330 16.14. l R E VISIO/'I \l autt 2 8 S2728 8 7 8 0 7 t il!3 of l 8 PAG E I 13 NE-02-09-12 003 page D.24 of 76 NE-02-09-12, Rev 1 Appendix D Page 0.25 4.10 For beta radiation derectors, (TEA, WEA), determine the efficiency for the applicable nuclides by completing Table 4. lOa as follows: 4. 10.1 Enter the Xe 133 efficiency in column for Ex ... m* 4.10.2 Multiply the Relative Efficiency for nuclides present in the mixrure times the E,c.,.133 , and record the result in the column. Mark nuclides not present in the mixture N/A. Table 4.lOa Relative Efficiency Relative Nuclide Efficiency<

1> &,_,,, E.1 Kr83m 0.07 J Kr85m 4.63 / Kr87 13.66 I ' Kr88 7.15 Kr89 13.66 \\f' Xel3lm 0.99 \' Xe133m 1.63 I Xe133 l.00 I Xe135m 0.36 I Xel35 5.85 I Xel37 13.66 I Xe138 13.01 I {l) CVI-02-92B-OOOO,l34,I ltSVJSION PAOS <

16.14. l Rf!VISION' PAOE Va u t t 20 ::; 2 7 2 0 8 . 8 8 7 1 6 of 18 I 16 NE-02-09-12 003 page D.27 of 76 NE-0 2-09-1 2, R ev 1 Append ix D Page D.28 4.1 5 If t h e U p per Level is l ess than 8 0% of the calculated value, document the rational for th is se l ect i on, and attach t o th i s procedu r e. 4.16 As si gn the Upper Leve l t o a spec ifi c al ann as follows: 4.16. l F or TEA-RIS-13 and WEA-RIS-14:

16.14.1 a. Ass i gn the U ppe r Level to the High-Hig h alarm. b. Determ ine t h e nom i nal and l o we r l evel values for alarm as fo ll ows: NOTE: Since the High-High alarm setp

t i s based on a regulatory limit, the upper level value must be L e selected setpoinL Upper level (UL) = ---@. (f m Step 4.15) Nominal value ::::: (Up w r.vel)
0.91 = Lower Level (LL) = Level)
0.82 = ----c. Determine the no background value of the monitor based o d. e. instrument opera
g history. = ---Round the Hi g h A l arm YR to die nearest interger value that can be clearly read on the i nstrument.
High A l arm = ----Assign this value to the H i gh alarm setpoint, or i f i s desirable to assign a d i fferent value, document the justification for the d i fferent High alarm setpoint and attach to this procedure.
g. Detennine the nom i nal, upper level and lower l e v el values for the High as foll ows: REVISIOI' P AOS Va u t t 28 *::; 2 7 2 8 8 *' 0 0 7 ti 17 of 18 17 NE-02-09-12 003 page D.28 of 76 NE-02-09-1 2, Rev 1 Append i x D Page D.29 NQJ£: The High alarm is not based on a regula 1mit, therefore it is acceptable to have values gre , r less than the selected value. Upper level (U =High Alann
1.2 =High Alarm = High Alarm* 0.80 = ----4.16.2 For PRM-RE-lB (REA): a. There is only one alarm on this system. b. Detennine the nominal and lower level values as follows: NOTE: Since this alarm setpoint is based on a regulatory limit, the upper level value must be LE the selected setpoint.
Upper level (UL) TI5 1 CJ:O (from Step 4.15) Nominal value = (Upper Level)* 0.91 = 70 2,SQ Lower Level (LL) = (Upper Level)
0.82 = {p3S, '500 5.0 DOCUMENTATION Maintain the completed procedure in the permanent plant file in accordance with the appropriate record procedure(s).
6.0 REFERENCES
6.1 Of(site Dose Calculation Manual, Section 3.4 {R-5560}, {R-5561 }, {R-5562}, {R-5563}, {R-5564}, {R-5565}, {R-5566}, {R-5567} 6.2 CVl-02-928
-00,134,l 7.0 ATTACHMENTS None NUMB Ell R I M S ION PAOF. 16.14.1 '*J a u l. t 2.!J *3 2 7 l 8 G 8 7 8 11 8 o f 18 18 NE-02-09-12 003 page D.29 of 76 NE-02-09-12, Rev 1 <'. Q! c: .-. ,z. fJ) ,._.. "*' C::* IZ* "*I c::* C::* __ , C::* ... Reactor Building Setpoint Calculation Appendix D Reactor Low Range Monhor SetpOinl Calculation Mij Measured or estimated CX1ncentration of nucWde I in release path j (llCVc:c:) MTj Measured or estimated total concentration of ail gases in release path j (µCi/c:c:)
nij Fradion of each nuclide released (unilless)
'Mlole Bady Ooso Rate QTj Maiamum Release Rate bllS8d on Whole Body Dose (uCllsec)
Fj Fraction of total dose allocated to this release pathway {Dimensionless) 500 Whole body dose rale Wrril {rmunlyr)
X/Qi Maximum normalized diffusion coefficient for lhts pathway at and beyond !tie site boundary {sec/m3) Qlj = Qlj* Kl Total wholo body dose fadDr duo to gamma emission from nuc:tlde i, as listed in the OOCM or Reg Guide 1.109, revision 1 (mrem/year per µCilm3) nij Is lhe fraction oflhe tolal activily for nudide I (Olmenslonleas) m Total number of nuclides in the gaseous eflluent j Release pathway IMll:si;m@'luCilaec GaseousElfluentMonitorSetpolntCalc:ulationsRe\16.xls, REACalculations Paga 1of3 5/19/2005
..a. <D Page D.30 c NE-02-09-12 003 page D.30 of 76 NE-02-09-12, Rev 1 Niickle Kfii3iii Ki8sm Kr8 7 Kr8B Kt8ii Xe131m 'Xe133m xe:i33' Xemm X9ffi' Xe'i38 i= I>> c: .... r* (!;* U:* I\.' "'-' G:* G:O ... c;:. C::* ... C::* ...... Appendix D RC!3cior Building Low Range Monitor Solpoinl Calculation Skin Dose Calculation QTj" 3000 Dose Rel& Limit Lowest Dose Rate Volue QTj = lilWlifi'i.U!uCilsec Step4 7 Maximum Allowable Value CTj a (QTj/Rj) RJ ., Release Rate r*.-lit@llluCilsec CT1 = maximum allowlld C1i" IW.dlll " liHi@l*luevc.:
GeseousElfluenlMonilorSetpointCalculalionaReY6
.xls. REACalculalions Page 2of3 9\) 0 Page D.31 5119/2005 I """
NE-02-09-12 003 page D.31 of 76 NE-02-09-12, Rev 1 Appendix D N c::: Q) c: r* ,.,. <::* U:* ,.._. "'-l "-' a;. G;r "'J C::* C::* "'J C* ... Reactor Buading Low Range Monitor Setpoiot CalculatioJ\
For Gamma Celeclors (REA) lhe relative efficiendes l$ calculated in the followiJ\g tabla. Callie 4.9a I Gamma Nud l d e Abu ndanc Kr83m 0.09 Kt85m 0.7 4 Kr8 7 0.83 7 rS8 1.372 Kr89 1.6 Xe1 31m 0.0196 Xa133m 0.1 4 Xe13 3 0.367 Xe135m 0.8 1 Xe13 5 0.93 9 Xe137 0.33 1 Xe138 1.222 I Nucl id e Kr83m l<t85m Kt8 7 Ki1l8 Kt89 Xe 1 3 1m Xe 1 33m Xe13 3 Xe 1 35m l<.e135 Xe13 7 Xe138 R e l ative Effid 2.0 1 6 2.28 1 3.738 4.3 0 0.05 3 0.38 1 Eij= c Rj = Cij= Eija Slap4.13 Effluent monitor detection efficiency for nudlda i (a:psl11Cilcc) Count rate above background (cps) Maximum scceptable com:entration of noble gos i (µCi/cc) Effluent monitor detection efficiency for nuclide i (a:p&111Ci/ccl Reactor Building Maximwn Allowable Bkg*C.RJ = l lt7@illl'lfjl Slep4.14 Upper Level (UL} " Nole. there is only ooe alarm on this syslem Step 4.162 Alarm UL Nominal -91% ot UL Lower Level 82% ot UL GasoousEHluentMooitorSelpoontCalculationsRev6.xts, REACalculations Page 3of 3 Page D.32 5/19/2005 \
NE-02-09-12 003 page D.32 of 76 NE-02-09-12, Rev 1 Appendix D ...., ...., Rx LR Rad M 2Q0Q0 -I I 1 I I I I I 1 5000 I I 11"\iol-.o f-I I D I 11-1--G :: I fl) u u;. 10000 I
I I I .._.. w I Ill 1 11 1 I 5000 -I I I I 1 a:* a:* C:'.< .....
3/20/0 6/28/0 10/6/0 1/14/0 4/23/0 8/1/04 11/9/0 2/17/0 5/28/0 9/5/05 3 3 3 4 4 4 5 5 Page D.33 rj -\,/'lo NE-02-09-12 003 page D.33 of 76
., NE-02-09-12, Rev 1 Appendix D Page 0.34 NOTE: T h e H i gh al arm i s n o t based on a regu l atory li m it , th er efore it is acceptable to h ave va lue s tha t are g re ate r, or Jes s than the selected value. Upper l evel (UL) = Hi g h Alann
1.2 = __ _ Nominal value = Hi g h Alarm Lower Level (LL) = High Alano
0.80 = ----4.16.2 For ntv\-\2.C.,.-\f\ a. There is only one alarm on this system.
b. Determin e the n om inal and lower level values follows: ;, S i nce this alarm setpo in t is b ased oo a regu l a t ory lim it , the upper eve! value must be LE th e selec t ed s etpoint. Upper l eve l (UL) (fr om Nom i nal va l ue = (Upper Leve l)
0.91 = ___ _ Lower Leve l (LL) = (Upper Leve])
0.82 = ___ _ 5.0 DOCUM E NTATION Maintain the completed procedure in lh e permane n t plant file i n accordance w i th th e appropriate record procedure(s).
6.0 REFERENCES
6.1 Offsite
Dose Calculation Manual, Section 3.4 {R-5565}, 6.2 CVl-02-928-00, 134, l 7.0 ATTACHMENTS None {R-5560}, {R-5561}, {R-5562}, {R-5563}, {R-5564}, {R-5566}, {R-5567} lll!M 8 ER REVISION PAGE 16.14.1 .-.. -. .,. .-.* 18 of 1 8 23 NE-02-09-12 003 page D.34 of 76
.. NE-02-09-12, Rev 1 Append ix D Page 0.35 4.15 If the Upper Level is less than 80% of the caJculated value, document the rational for this selection, and attach to this procedure. 4.16 Assign the Upper Level to a specific alarm as follows: NUM BER 4.16.1 For TEA-RIS-13 and WEA-RIS-14:
16.14. l a. Assign the Upper Level to the High-Hi gh alarm. b. Determine the nominal and lower leve l va l ues f or th e High-H i gh alann as follows: NOTE: S i nce che H i gh-Hig h alarm setpOint i s based on a re gula tory lim i t, the upper l ev el va lue must be LE the selected setpo i nt. Upper l eve l (UL) = ___ (from ptZJ""l-" Nominal value =(Upper Level)* 0.9 1 = i::;o' Lower Leve l (LL) = (Upper Level)
0.82 = ___ 1'1 {af c. Determ i ne the normal background value of the mo ni tor b ased on instrument operating history. Background=---------
d. Multiply the bac k grou nd v al ue by 4.66. High Alarm = (Background)(4.66)'
=
= __ _ e. Round the High Alann YI! t o the nearest interger value thal can be clear l y read on the instrument.
High Alarm=----
f. Assign th i s value to the High alann setpOint, or if is desirable 10 assign a d i fferent v a ue, document the justification for the different H i gh alarm setpoint and attach to this procedure.
g. Determine the nominal, upper level and lower level values for the Hi gh as fo ll ow s: ) : -... ,.. I PAGE *j 2 7 0 0 7 ... -.... -. .* .* 17 of 18 0 iJ, 0 .... Rl!VISION o o a c c 24 NE-02-09-12 003 page D.35 of 76 NE-02-09-12, Rev 1 Appendix D ..., <.n <: Cl c: ,. <ZI U:* "' C::* C::* ..... , <:: C::*
C::* .... INPUT VALUES This spreadsheet was derived from PPM 16.14.1Rev2 (ODCM dispersion value changes) and llE 2-94-1312 loop uncertalntieslinsb'ument drift Ke11Ctor811111U11g L.ow Range MonltorPRM-RE*1A Gas Mixture See ODCM Table 3-15and FSAR Table 11.3-1 X/Oj 8 20E..07 sec/m3 X/Qj lorthe Reactor Building 1'1111111&11 pathway is aBE-07 sec:/m3, from OOCM Tabla 3-3. Fj 04 Fortv percent (40%) of the site boundary dose rate is allocated to the Reactor buadlng, Fj is 0.4 Rj 4.48E+07 oc:isec The maximum exhaust Row rate (Rj) is 4.48E+07 celsec (96,000 dm). E(Xe-133) 3.72E+08 Xenon-133 efficiency (Gas Calibration factor from PPM 16.1.2 Rev 7) Bkg 3.30E+-03 cps Background Sl<P <.13 ..iue A Based on instrument range, accura(¥, and the ability to accurately read instrument vai..es. select an Upper Level that Is less than or Unrwl.ellel 7.75E+05 nl300 equal to the maximum allowable setpoint value determined in Step 4. 1 J Twtiine BuUdlng Low Range Monitor (TEA-RE-13)
Gas Mixture See FSAR Table 11.3-7 X/Qj 1 SOE-05 seo'm3 X/Qj for the Twtine Building release p81hway is 1.SE-05 seetm3, tiom OOCM Table 3-3 Fj 0.4 Forty percent (40%) of tile site boundary dose rate Hmll ls alocated to the Turbin& building Fj is 0.4. RJ 1.79E+08 cc/sec The maximum exhaust now rate (Rjl ls 1. 79E +08 cc/sec (380 , 000 elm). E(Xe-133) 4 83E*07 cpm/uCi/CC Xenon-133 efficiency cpm/uCilcc From PPM 16.2..1 Re116 Bkg 40 Cj)ll1 Bad\grOUlld Upper Level 4.80E.03 si.p, 1, ..... Based on kistrument range, accuracy and the abilily to accurately read Ul$lrument values, select an Upper Leve! that IS less than °' 4854 equal to the maximum allowable setpolnt value determined in Step 4 13. Radwaste BuUdlng Lew Range Monitor (We:A*RE-14)
Gas Mlxlvre See FSAR Table 11 3-7 X/Oj 1 SOE-05 sec/m3 X/OJ for the Radwaste Building release palllway is 1.SE-05 sac/m3, from OOCM Table 3-3. Fl 02 Twenly percent (20%) of the site bOundary dose rate is aUocatad to the Radwaste building Fj is 0.2.. Rj 3.91E+07 oc/&e<; The maximum exhaust now rete (Rj) is 3.91E +07 cc/sec (83.000 cfm) E(Xe-133) 483E*07 cpmluCl/cc Xenon-133 etllciency cpm/uC:Ucc from PPM 16.3.1 Rev 7 BJtg 36 cpm Background sa.p*.13 .,...,. = Bssod on instrument range, accuracy, and the abDl!y to accurotol1 road lnSlnlment values, seled an Uppor Level that is less than ot U1>br!rlevel 2.67E+-O<t 267ta equal to the maximum allowable selpDlnt vakle deleimined in Step 4.13. GaseousElftuenlMonito<SelpointCala.laliotlsRev6.xJs, Input& PAGE 1 OF2 511912005 Page D.36 0 " 1f NE-02-09-12 003 page D.36 of 76 NE-02-09-12, Rev 1 Appendix D N c:: DI c: r* IZ* u:* "-' ..... 1 G:* G:O .... G;t C:.:* ,.., INPUT VALUES Mechanical Vacuum Pump {AR*RIS*:Z1 1 Gas Mixture Setpoint Calc:ulation 98-01 of 313198 & B&R Calculallon 5.03.01 of 3180 by E Stergotea X/Qj B.20E-07 sectm3 X/Qj for the Reactor Bulding release palllway Is B.2E-07 seclm3 , from OOCM Table 3-3. Fj 0.4 Forty percent (40%) or lhll site bo1.11dery dose rale is ellocsted to IN Reactor building, Fi is 0.4 RJ 1.13E*06 cc/sec The maximum exhauSI ftow rate (Rj) is 1.13E+06 cc'aec (2400 cfm) E(Xe-133) 7.14E+0 1 X anon-133 efficiency mRn)rluCwcc from Selpolnt Calculation 98-01. lsoshield calculation of inlllal mixture=0.34 mrlhr. (0.34/4.56E-mR/hr/uCi/cc 3)=71 3686 mR/hr/uCVcc Bkg 0.1 cpm Background
Based on instrument range, accuracy, end the ablily to accurately read lnsltunenl values, sel!lct an Upper Level that Is less than or UnMrlewl 7.5 7.G equal to the maximum alowable setpoint value determined'" Step 4 13 GaseouaEffluenlMonitorSelpointCaiculationsRev&
xis, Inputs PAGE 20F 2 511912005 Page D.37 "'=:) ..
NE-02-09-12 003 page D.37 of 76 NE-02-09-12 Rev2 Appendix D Revision Notes Revision 4 cont ai ns a first cut at including loop uncerta in ties and instrument drift into the setpoint calculations Re visi on 5 takes out the loop uncerta in ty and inst r ument d ri ft calculation as engineering determined it unnecessary. R e vi si on 6 co rr ects the r e l a t iv e beta e ffi c i encies and matches PPM 16.14.1 Rev 2 Rev ision 7 adds a sheet th at d e te rmin es the eff i ciency of the RD-52 to betas. N E-02-09-12.001 PR M-RE-1A i npu ts c ha ng e d to PRM-RE-18 C M R0000011948-001 T E A Cal cula t i ons & WE ACalculations updated to NE-02-08-09 and NE-02-08-08 Setpoint Calculations S :\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE 09-12.001 \CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7
-NE-02-09-12 R1 -CMR0000011948-001
.xlsx Revision Notes PAGE 1 OF 14 Page 0.72 2/4/2014 NE-02-09-12 003 page D.38 of 76 NE-02-09-1 2 Rev 2 Appendix D INP UT V A LU E S Page D.7 3 This spreadsheet was derived from PPM 16.14.1 Rev 2 (ODCM dispersion value changes) and E/1-02-94-1312 loop uncertainties/instrument drift Re acto r B uilding I nterme diat e Rang e Monito r P RM-R E-18 Gas Mixture See ODC M Ta bl e 3-15 a n d FS A R T a bl e 11.3-1 XJQ) 8.20E-07 seclm 3 XJQj for t h e Rea c t or B uilding r e lease pa thwa y f rom ODCM T a ble 3-3. F j 0.4 Fo rty pe r cent (40%) of th e site bo unda ry do s e r a te l imi t is a llo c ate d to t h e React o r b uildin g , FJ i s 0.4 R j 4.48E+07 cclsec The maximum e xhaus t flow ra te (RJ) is 4.4 8E+07 cc/s e c (9 5 , 0 0 0 c f m). E(Xe-1 33) 5.51E+05 ccps/u C i/c c Xeno n-1 33 e fficienc y (Gas Ca libratio n facto r f ro m C hemis try Cal culatio n 96-00 1 , A ttachmen t 3 P age 5) Bkg 5.50E+02 cps Ba ckgroun d (NE-02-10-0 1 C MR 0 0 000 1 0 3 57) step 413 vaiue = Ba se d on instrumen t range, acc uracy, a n d th e abil ity to a c c urately r e ad i n s t rumen t val u es , s elec t a n U pper Le v el that is l ess t han or Uppe r L eve l 1.00E+03 15 50 equa l to t h e maximum allowabl e s etpo i n t valu e d etermine d i n Ste p 4.1 3 Tur bi n e Buil di n g L o w R an ge Mo n ito r (TEA-R E-13) Gas Mixtur e S ee F S AR T able 1 1.3-7 XJQ j 1.50E-05 seclm 3 XJQj f or t he T urbine B uildin g r elea se pathway f rom O D C M T abl e 3-3. F j 0.4 Fo rty percent (40%) of th e site boundary d os e ra te l imi t is a llocated to th e T urbin e b uildin g. Fj i s 0.4. R j 1.79E+08 cclse c T he maximum exhaust flow ra te (R j) i s 1.79E+08 c c/sec (380 , 000 c fm). E(X e-133) 2.15E+07 cprn/uCi/cc Xenon-133 e fficienc y cprn/uCi/c c from NE-02-0 8-0 9 Bkg 46 cpm Background (NE-0 2-1 0-01 C M R 0 0000 11 6 47} Step 41 J vatue = B ased on instrumen t range , accuracy , a nd t h e ability to accurately r ea d i nstrument val u es , selec t an U pper Le v el t h at i s less than or Upper Le vel 3.81E+02 477 equal t o 80% of the maximum allowable setpoi n t value determine d i n S te p 4. 13. Ra d was te B u il din g Lo w Ra ng e Monit or (W EA-RE-1 4) Gas Mixture S e e F S AR Table 11 3-7 XlQ j 1.SOE-05 sec/m3 XJQj for the R adwaste Building release pathway from O DCM Table 3-3. F j 0.2 Twenty percent (20%} of the site boundary dose rate limit is a llocated to the R adwa s te buildin g. FJ 1s 0 2 Rj 3.91E+07 cclsec The maximum exhaust flow rate (RJ} is 3.91 E+07 c c/sec (8 3 , 000 cf m} E(Xe-133) 1 81E+07 cprn/uCi/cc Xenon-1 33 efficiency cprn/uC1/cc from PPM 1 6 3 1 Rev 7 Bkg 46 cpm Background (NE-02-10-0 1 C MR 00000 1 1647) step 4 1 3 value= Based on instrument range , accu r acy , and the ab il ity to accurately r ead i nstrumen t va l u es. select a n Uppe r Le v e l t h at 1 s le s s than or Upper Le ve l 2.90E+03 3626 equal to 80% o f the maximum allowable setpoi n t value determ in e d in S te p 4. 1 3 S \Engineenng\Rx Fuels Eng\Fuels\EPG S AG\CR002 4 4578\calc\NE-0 2-09-1 2.001\CMR-WEA_
TEA\ G aseousEffiuentMonitorSetpointCalculationsRev7-NE-0 2-0 9-1 2 R 1-C MR000 0011 9 48-001 x l s x Inputs PAGE 2 OF 1 4 214/2 014 NE-02-09-12 003 page D.39 of 76 NE-02-09-12 Rev 2 Mechanical Vacuum Pump (AR-RIS-21)
Gas Mixture X/Qj 8.20E-07 sec/m3 Fj 0.4 Rj 1.13E+06 cc/sec Appendix D INPUT VALUES Setpoint Calculation 98-01 of 3/3/98 & B&R Calculation 5 03 01 of 3/80 by E Stergokes X/Qj for the Reactor Building release pathway from ODCM Table 3-3. Forty percent (40%) of the site boundary dose rate limit is allocated to the Reactor building, Fj is 0.4 The maximum exhaust flow rate (Rj) is 1.13E+06 cc/sec (2400 cfm) Page D 74 Xenon-133 efficiency mR/hr/uCi/cc from Setpoint Calculation 98-01. lsoshield calculation of initial mixture=0.34 mr/hr. (0.34/4.56E-E(Xe-133) 7.14E+01 mR/hr/uCi/cc 3)=71.3686 mR/hr/uCi/cc Bkg 0.1 cpm Background step 4.13 value= Based on instrument range, accuracy, and the ability to accurately read instrument values. select an Upper Level that is less than or Upper Level 75 76 equal to the maximum allowable setpoint value determined in Step 4.13 S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001 ICMR-WEA_
TEA\ GaseousEffiuentMonitorSetpointCalculationsRev?-NE-02-09-12 R 1-CMR0000011948-001.xlsx Inputs PAGE 3 OF 14 2/4/2014 NE-02-09-12 003 page D.40 of 76 NE-02-09-12 Rev 2 Appendix D Page D 75 Reactor Building Intermediate Range Monitor Setpoint Calculation Reactor Building Setpoint Calculation Table 4.3a Nuclide Mii MTj Kr83m 6.47E-05 2.25E-03 Kr85m 1.25E-04 2.25E-03 Kr87 3.35E-07 2.25E-03 Kr88 3.35E-04 2.25E-03 Kr89 4.02E-04 2.25E-03 Xe131m 3.35E-07 2.25E-03 Xe133m 6.25E-06 2.25E-03 Xe133 1.83E-04 2.25E-03 Xe135m 1.54E-04 2.25E-03 Xe135 4.91E-04 2.25E-03 Xe137 1.SOE-05 2.25E-03 Xe138 4.69E-04 2.25E-03 Sum 2.25E-03 Table 4 4a Maximum Release Rate Nuclide rrij Ki Kr83m 2.88E-02 0.0756 Kr85m 5.57E-02 1170 Kr87 1.49E-04 5920 Kr88 1.49E-01 14700 Kr89 1.79E-01 16600 Xe131m 1.49E-04 91.5 Xe133m 2.78E-03 251 Xe133 8.15E-02 294 Xe135m 6.86E-02 3120 Xe135 2.19E-01 1810 Xe137 6.66E-03 1420 Xe138 2 09E-01 8830 Sum of rrij*Ki= rrii 2.88E-02 5.57E-02 1.49E-04 1.49E-01 1.79E-01 1.49E-04 2.78E-03 8.15E-02 6.86E-02 2.19E-01 6.66E-03 2.09E-01 1.00E+OO (rrii)(Ki) 2.18E-03 6.51E+01 8.83E-01 2.19E+03 2.97E+03 1.36E-02 6.99E-01 2.40E+01 2.14E+02 3.96E+02 9.46E+OO 1.84E+03 7.72E+03 Mij Measured o r es t imated concentration of nuclide i in release path j (µCi/cc) MTj Measured or estimated total concentration of all gases in release path j (µCi/cc) rrij Fraction of each nuclide released (unitless)
Whole Body Dose Rate QTj Maximum Release Rate based on Whole Body Dose (uCi/sec)
Fj Fraction of total dose allocated to this release pathway (Dimensionless) 500 Whole body dose rate limit (mrem/yr)
X/Qi Maximum normalized diffusion coefficient for this pathway at and beyond the site boundary (sec/m3) QTj= QTj= Ki Total whole body dose factor due to gamma emission from nuclide i, as listed in the ODCM or Reg Guide 1 109 , revision 1 (mrem/year per µCi/m3) rrij Is the fraction of the total activity for nuclide i (Dimensionless) m Total number of nuclides in the gaseous effluent Release pathway = I 3.16E+04=1uCi/sec S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR002445 78\calc\NE-02-09-12.001
\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev?-NE-02-09-12 R1-CMR0000011948-001
.xlsx REACalculations Page 4 of 14 2/4/201 4 NE-02-09-12 003 page D.41 of 76 NE-02-09-1 2 Rev 2 Appendix D Reactor Building Intermediate Range Monitor Setpoint Calculation Table 4.5a Maximum Release Rate Nuclide nij Li+1.1Mi 'nii)(Li+1.1 Mi) Kr83m 2.BBE-02 0 O.OOE+OO Kr85m 5 57E-02 2 81 E+03 1.56E+02 Kr87 1 49E-04 1.65E+04 2.46E+OO Skin Dose Calculation Kr88 1 49E-01 1.91E+04 2.85E+03 3000 Dose Rate Limit Kr89 1 79E-01 2 91 E+04 5 21E+03 Xe131m 1.49E-04 6.48E+02 9 66E-02 QTj= 4.00E-01 3.00E+03 = I 1.20E+05 JuCi/sec Xe133m 2.78E-03 1.35E+03 3.76E+OO 8.20E-07 1.22E+04 Xe133 8.15E-02 6.94E+02 5.66E+01 Xe135m 6.86E-02 4.41E+03 3.03E+02 Xe135 2.19E-01 2.30E+03 5.03E+02 Xe137 6.66E-03 1.39E+04 9.26E+01 Lowest Dose Rate Value Xe138 2.09E-01 1 43E+04 2.99E+03 QTj = I 3.16E+04 luC1/sec Sum(lTli 1(Li+ 1.1 Mil = 1 22E+04 Step 4 7 Table 4 Ba Maximum Allowable Value Maximum Nuclide Concentration CTJ = (QTj/RJ) Nuclide nii CTi CiJ Rj = Release Rate Kr83m 2 88E-02 7.06E-04 2.03E-05 CTj = maximum allowed concentra..._tio_n
____ _,__.., CTj = I 3.16E+04 I = I 7.06E--04 luCi/cc Kr85m 5.57E-02 7.06E-04 3.93E-05 Kr87 1 49E-04 7.06E-04 1.05E-07 4.48E+07 Kr88 1 49E-01 7.06E-04 1.0SE-04 Kr89 1 79E-01 7.06E-04 1.26E-04 Xe131m 1.49E-04 7.06E-04 1.05E-07 Xe133m 2.78E-03 7.06E-04 1.96E-06 Xe133 8.15E-02 7.06E-04 5.75E-05 Xe135m 6.86E-02 7.06E-04 4.84E-05 Xe135 2.19E-01 7.06E-04 1.54E-04 Xe137 6.66E-03 7.06E-04 4.?0E-06 Xe138 2 09E-01 7 06E-04 1.47E-04 S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev?-NE--02-09-12 R 1-CMR0000011948-001.xlsx REACalculations Page 5of14 Page D 76 2/4/20 14 NE-02-09-12 003 page D.42 of 76 NE-02-09-12 Rev 2 Appendix D Reactor Building Intermediate Range Monitor S etpoint C alculation
.. in the following table . T a ble 4.9a R elat iv e E ff i cie n c y G amm a R elati v e Nuc li d e A bunda n ce Abundan c e Kr83m 0.0 9 0.24 5 K r85m 0.7 4 2.016 Kr8 7 0.837 2.28 1 K r 8 8 1.3 7 2 3.73 8 Kr8 9 1.6 4.36 X e 131 m 0.019 6 0.0 5 3 X e 13 3 m 0.14 0.381 Xe133 0.3 67 1 Xe 1 35m 0.81 2.2 07 Xe1 3 5 0.9 3 9 2.5 5 9 Xe 13 7 0.3 3 0.8 99 X e1 3 8 1.222 3.33 Table 4.11a Counts above Background Nuclide Cij Eij Kr83m 2.03E-05 1.35E+05 Kr85m 3.93E-05 1.11E+06 Kr87 1.0SE-07 1.26E+06 Kr88 1.0SE-04 2.06E+06 Kr89 1.26E-04 2.40E+06 Xe131m 1.05E-07 2.92E+04 Xe133m 1.96E-06 2.10E+05 Xe133 5.75E-05 5.51E+05 Xe135m 4.84E-05 1.21E+06 Xe135 1 54E-04 1.41E+06 Xe137 4 70E.06 4.95E+05 Xe138 1 47E-04 1.83E+06 C.Rj= E(Xe-133)
E i i 5.51E+05 1.35E+05 5.51E+05 1.11E+06 5.51E+05 1.26E+06 5.51 E+05 2.06E+06 5.51E+05 2.40E+06 5.51 E+05 2.92E+04 5.51 E+05 2.10E+05 5.51 E+05 5.51 E+05 5.51E+05 1.2 1E+06 5.51E+05 1.41E+06 5.51E+05 4.95E+05 5.51 E+05 1.83E+06 C.Rij 2.74E+OO 4.36E+01 1.32E.01 2.17E+02 3.03E+02 3.07E.03 4.12E.01 3.17E+01 5.88E+01 2.17E+02 2.33E+OO 2.70E+02 1.00E+03 E1j= C.Rj= Cij = E11= Step 4.13 Effluent monitor detection efficiency for nuclide i (ccps/µCi/cc)
Count rate above background (cps) Maximum acceptable concentration of noble gas i (µCi/cc) Effluent monitor detection efficiency for nuclide i (ccps/µCi/cc)
Reactor Building Maximum Allowable Setpoint Bkg+C. Rj = I 1,550 I Step 4.14 Upper Level (UL) = 0000*-1 Note, there is only one alarm on this system Step 4.16.2 Alarm UL Nominal Lower Level 1,000 I 910 191% of UL 820 82% of UL S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE.02-09-12
.001 \CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001
.xlsx REACalculations Page 6 of 14 Page 0.77 2/4/20 1 4 NE-02-09-12 003 page D.43 of 76 NE-02-09-12 Rev 2 Turbine Building Setpoint Calculation T able 4.3 a N u c lid e M ii M Ti rrij K r 83m O.OOE+OO 1.15E+02 0.00 Kr8 5 m 2.25E+OO 1.15E+02 0.02 Kr87 6.34E+OO 1.15E+02 0.05 Kr88 7.61E+OO 1.15E+02 0.07 Kr89 O.OOE+OO 1.15E+02 0.00 Xe131m O.OOE+OO 1.15E+02 0.00 Xe 13 3m O.OOE+OO 1.15E+02 0.00 Xe 133 9.19E+OO 1.15E+02 0.08 Xe1 35m 2.15E+01 1.15E+02 0.19 Xe135 2.09E+01 1.15E+02 0.18 Xe13 7 O.OOE+OO 1.15E+02 0.00 X e138 4.75E+01 1.15E+02 0 41 S um 1.15E+02 1.0 0 T able 4.4a M aximum R eleas e Rate Nuclid e rri i Ki <rriilC KD Kr8 3m 0.00 0.0 756 0.00E+OO Kr85m 0.02 11 7 0 2.28E+01 Kr8 7 0.05 592 0 3.25E+02 Kr8 8 0.07 14 7 00 9.69E+02 T urbin e B u 0.00 1 6600 O.OOE+OO Xe13 1m 0.00 9 1.5 O.OOE+OO Xe 1 3 3m 0.00 2 5 1 O.OOE+OO Xe133 0.08 29 4 2.34E+01 X e13 5m 0.19 31 2 0 5.83E+02 X e 135 018 1810 3.28E+02 Xe137 000 1 42 0 0.00E+OO Xe 138 0.41 8 83 0 3.64E+03 S um of rrij*K i= 5.89E+03 Appendix D Turbine Building Monitor S etpoin t Calculation Mij Measured or estimated concentration of nuclide i in release path j (µCi/cc) MTj Measured or estimated total concentration of all gases in release path j (µCi/cc) rrij Fraction of each nuclide released Whole Body Dose Rate = (Fj*500)/(X/Qi*Sum(rrij*Ki)
QTj Maximum Release Rate based on Whole Body Dose Fj Fraction of total dose allocated to this release pathway (Dimensionless) 500 Whole body dose rate limit X/Qi Maximum normalized diffusion coefficient for this pathway at and beyond the site boundary (sec/m3) Ki Total whole body dose factor due to gamma emission from nuclide i, as listed in the OOCM or Reg Guide 1.109, revision 1 (mrem/year per µCi/m3) rrij Is the fraction of the total activity for nuclide i (Dimensionless) m Total number of nuclides in the gaseous effluent Release pathway QTj= 4.00E.01 5.00E+02 = 1.SOE.05 5.89E+03 I 2.26E+03 JuCi/sec S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE.02-09-12.001
\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev?-NE-02-09-12 R1-CMR0000011948-001.xlsx TEACalculations Page 7 of 14 Page D 78 2/4/2014 NE-02-09-12 003 page D.44 of 76 NE-0 2-09-1 2 R ev 2 Ta ble 4.5 a M ax i mum R eleas e R ate Nuclide lT i i Li+1.1 M i (1T iil(Li+1.1 M i l Kr8 3m 0.00 0 O.OOE+OO Kr85m 0.02 2.81E+0 3 5.48E+01 Kr8 7 0.05 1.6 5E+0 4 9.06E+02 Kr8 8 0.07 1.9 1E+0 4 1.26E+03 Kr89 0.00 2.91E+0 4 O.OOE+OO Xe 1 31m 0.00 6.4 8 E+02 O.OOE+OO Xe 1 33m 0.00 1.3 5E+03 O.OOE+OO X e 133 0.08 6.94E+0 2 5.53E+01 Xe1 3 5m 0.19 4.4 1E+0 3 8.24E+02 Xe135 0.18 2.3 0E+0 3 4.17E+02 Xe 13 7 000 1.3 9E+04 O.OOE+OO Xe 13 8 0.41 1.4 3 E+04 5.89E+03 S um(1Tii)(Li+1.1 Mil = 9 41E+03 T able 4.B a M a x im u m N uclide C oncentratio n Nuclid e lTi i CT i C i i Kr8 3m 0.00 1 26E-05 0.00E+OO Kr85m 002 1.26E-05 2.47E-07 Kr87 0 05 1.26E-05 6.95E-07 Kr88 0.07 1 26E-05 8.34E-07 Kr8 9 0.00 1 26E-05 O.OOE+OO Xe1 31 m 0.00 1 26E-05 O.OOE+OO Xe 133m 0.00 1.26E-05 O.OOE+OO Xe 1 3 3 0.08 1 26E-05 1.01 E-06 Xe 13 5m 0.19 1 26E-05 2.36E-06 Xe13 5 0.18 1.26E-05 2 29E-06 X e137 0.00 1.26E-05 O.OOE+OO Xe1 3 8 0.41 1.26E-05 5.21 E-06 Appendix D T urbin e Buildin g Monitor S etpoint C a lcula t ion S k in Dose Rate = (Fj"3000)/(X/Q 1*S um (m)*Ki) 3000 D o se R a te Li mit QT)= 4 OOE-01 3.00E+03 [ 1.50E-05 9.41E+03 R ele a s e rate f o r l o w es t d ose rate value (Whole bo d y o r S kin) Q T J =I 2.26E+03 IuCi/s e c S t e p 4.7 Maxi m um Allowabl e C on centr a ti on (CT J) CT j = (Q T J/Rj) Q Tj=max i mum a cc eptable releas e ra t e f o r all noble g ases (u C 1/sec) Rj = R eleas e R ate c cfsec) C T j = 2.2 6 E+0 3 = I 126E-05 lu CJ/cc 1 79E+08 S \Engineerin g\Rx Fu els E ng\Fuels\EP G S A G\C R00 244578\calc\NE-0 2-0 9-12 001\CMR-WE A_ T EA\ G aseousEffluentMonitor S etpointCalculationsPev
?-NE-02-09-12 R 1-C MROOOOO 11 94 8-00 1.x lsx TEACalculations P ag e 8 o f 14 Page D.79 2/4/2 01 4 NE-02-09-12 003 page D.45 of 76 NE-02-09-12 Rev 2 Appendix D T urbine Building Monitor S etpoin t C alculation For the TEA Beta detector the relative efficiency is calculated in the following table. T abl e 4.1 0a Relativ e Efficiency R elative Efficiency (1 N uclide ) E!Xe-133) Kr8 3 m 0.0 5 0 2.15E+07 Kr85m 1.6 22 2.15E+07 Kr8 7 2.205 2.15E+07 Kr8 8 1.5 44 2.15E+07 Kr8 9 2.2 5 5 2.15E+07 Xe1 31 m 1.119 2.15E+07 Xe 1 33 m 1.44 4 2.15E+07 X e 133 1.0 0 0 2.15E+07 Xe 1 3 5m 0.387 2.15E+07 Xe 1 35 1.949 2.15E+07 Xe 137 2.315 2.15E+07 Xe 1 3 8 1.999 2.15E+07 (1) NE-02-08-09 T abl e 4.1 1 a Co un t R ate C ontribution s Nuclid e C ii Eii Kr8 3m O.OOE+OO nla Kr85m 2.47E-07 3 49E+07 K r87 6.95E-07 4.74E+07 K r8 8 8.34E-07 3.32E+07 K r89 O.OOE+OO n/a Xe 131m 0.00E+OO nla Xe 13 3m O.OOE+OO nla Xe13 3 1.01 E-06 2.15E+07 X e1 3 5 m 2.36E-06 8.32E+06 Xe135 2.29E-06 4.19E+07 Xe13 7 0 OOE+OO n/a Xe13 8 5.21E-06 4.30E+07 C.R j= Eii n/a 3.49E+07 4.74E+07 3.32E+07 n/a n/a n/a 2.15E+07 8.32E+06 4.19E+07 n/a 4.30E+07 C.Ri i O.OOE+OO 8 60E+OO 3.29E+01 2.77E+01 O.OOE+OO O.OOE+OO O.OOE+OO 2 17E+01 1.96E+01 9.61E+01 O.OOE+OO 2.24E+02 4 31 E+02 I Eij=Effluent monitor detection efficiency for nuclide i (cpm/µC i/c c) C.Rj Cij E1J = = = Count rate above background (cpm) Maximum acceptable concentration of noble gas i (µCi/cc) Effluent monitor detection efficiency for nuclide i (cpm/µCi/cc) cpm 2.00E-05 !'Ci/cc I S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001.xlsx TEACalculations Page 9 of 14 Page D.80 2/4/2014 NE-02-09-12 003 page D.46 of 76 NE-02-09-12 Rev 2 Appendix D Turbine Building Monitor Setpoint Calculation Turbine Building 3.97E+03 !JCils Step 4.13 Maximum Allowable Setpoint=Bkg+C
.Rj= 1-46+43[]
I 477 lcpm Step 4. 14 Upper Level = 2.22E-05 !JCilcc I 381 !Based on instrument range, accuracy, and the ability to accurately read instrument values select an Upper Level that is less than or equal to 80% of the maximum allowable setpoint value detennined in Step 4.13. Activity Si gnal s Ch 1 & Ch 3 i n !JC ilcc Effluent Activity Signal Ch 4 !JCi/s High Alarm High Alarm UL 1 77E-05 UL 3.17E+03 Nominal 1.61E-05 91% of UL Nominal 2.89E+03 91%ofUL Lower Leve 1.45E-05 82% of UL Lower Level 2.60E+03 82% of UL Bkg 2.14E-06 Bkg 3.83E+02 Alert Alarm 9.97E-06 Bkg*4.66 Alert Alarm 1.78E+03 Bkg*4.66 Alert Alann 9.98E-06 Rounded up Alert Alarm 1.79E+03 Rounded up UL 1.20E-05 120% of Nominal UL 2.15E+03 120% of Nominal Nominal 9.98E-06 Alarm Nominal 1.79E+03 Alarm LL 7.98E-06 80% of Nominal LL 1.43E+03 80% of Nominal S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001
\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001.xlsx TEACalculations Page 10 of 14 Page D.81 2/4/2014 NE-02-09-12 003 page D.47 of 76 NE-02-09-12 Rev 2 Appendix D Radioactive Waste Building Monitor Setpoint Calculation Radwaste Building Setpoint Calculation Table 4.3a Nuclide Mij MTj Kr83m O.OOE+OO 1.74E+OO Kr85m O.OOE+OO 1.74E+OO Kr87 0.00E+OO 1.74E+OO Kr88 O.OOE+OO 1.74E+OO Kr89 0.00E+OO 1.74E+OO Xe131m O.OOE+OO 1.74E+OO Xe133m O.OOE+OO 1.74E+OO Xe133 3.17E-01 1.74E+OO Xe135m 0.00E+OO 1.74E+OO Xe135 1.43E+OO 1.74E+OO Xe137 O.OOE+OO 1 74E+OO Xe138 O.OOE+OO 1 74E+OO Sum 1.74E+OO Table 4.4a Maximum Release Rate Nuclide TTij Ki Kr83m O.OOE+OO 0.0756 Kr85m 0.00E+OO 1170 Kr87 O.OOE+OO 5920 Kr88 O.OOE+OO 14700 Kr89 O.OOE+OO 16600 Xe131 m O.OOE+OO 91.5 Xe133m 0.00E+OO 251 Xe133 1.82E-01 294 Xe135m O.OOE+OO 3120 Xe135 8.18E-01 1810 Xe137 0 OOE+OO 1420 Xe138 0.00E+OO 8830 Sum of TTij*Ki= TTij O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.82E-01 O.OOE+OO 8.18E-01 O.OOE+OO O.OOE+OO (TTij)(Ki)
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.35E+01 O.OOE+OO 1 48E+03 0 OOE+OO O.OOE+OO 1.53E+03 Mij Measured or estimated concentration of nuclide i in release path j (µCi/cc) MTj Measured or estimated total concentration of all gases in release path j (µCi/cc) TTij Fraction of each nuclide released Whole Body Dose Rate = (Fj"500)/(X/Qi*Sum(rrij°Ki)
OTJ Maximum Release Rate based on Whole Body Dose FJ Fraction of total dose allocated to this release pathway (Dimensionless) 500 Whole body dose rate limit X/Qi Maximum normalized diffusion coefficient for this pathway at and beyond the site boundary (sec/m3) Ki Total whole body dose factor due to gamma emission from nuclide i , as listed in the ODCM or Reg Guide 1.109, revision 1 (mrem/year per µCi/m3) TTij Is the fraction of the total act ivi ty for nuclide i (Dimensionless) m Total number of nuclides in the gaseous effluent Release pathway QTj= 2 OOE-01 5 OOE+02 = 1 50E-05 1.53E+03 r 4.34803 ]uCi/sec S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12
.001 \CMR-WEA_ TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09
-12 R1-CMR0000011948-001
.xlsx WEACalculations Page 11 of 14 Page D 82 2/4/201 4 NE-02-09-12 003 page D.48 of 76 NE-02-09-12 Rev 2 Table 4.5a Maximum Release Rate Nuclide rrii li+1.1Mi 'rrii)(Li+
1. 1 Mi) Kr83m 0.00E+OO 0 O.OOE+OO Kr85m 0.00E+OO 2.81E+03 O.OOE+OO Kr87 0.00E+OO 1.65E+04 O.OOE+OO Kr88 0.00E+OO 1.91 E+04 O.OOE+OO Kr89 0.00E+OO 2.91 E+04 O.OOE+OO Xe131m 0 OOE+OO 6.48E+02 O.OOE+OO Xe133m 0.00E+OO 1.35E+03 O.OOE+OO Xe133 1.82E-01 6.94E+02 1.26E+02 Xe135m 0.00E+OO 4.41 E+03 O.OOE+OO Xe135 8.18E-01 2.30E+03 1.88E+03 Xe137 0 OOE+OO 1.39E+04 O.OOE+OO Xe138 O.OOE+OO 1.43E+04 O.OOE+OO Sum(rrii)(Li+1.1Mi)
= 2.01E+03 Table 4.8a Maximum Nuclide Concentration Nuclide TTll CTi Cii Kr83m 0.00E+OO 1.11 E-04 0.00E+OO Appendix D Radioactive Waste Building Monitor Setpoint Calculation Skin Dose Rate = (Fj"3000)/(XJQ1*Sum(rrij'K1) 3000 Dose Rate Limit Q Tj= 2.00E-01 1.50E-05 Lowest Dose Rate Value I 4.34E+03 luCi/sec Step 4.7 Maximum Allowable Value CTj = (QTj/Rj) Rj = Release Rate 3.00E+03 2.01 E+03 CTj ::: maximum allowed concentration
= [U9E+o4]uCi/sec Kr85m O.OOE+OO 1.11 E-04 O.OOE+OO CTj = I 4.34E+03 I = I 1.11 E-04 I Kr87 O.OOE+OO 1.11 E-04 O.OOE+OO 3.91 E+07 Kr88 0.00E+OO 1.11 E-04 0 O.OE+OO Kr89 O.OOE+OO 1.11 E-04 O.OOE+OO Xe131m O.OOE+OO 1.11 E-04 O.OOE+OO Xe133m 0.00E+OO 1.11 E-04 O.OOE+OO Xe133 1 82E-01 1 11 E-04 2.02E-05 Xe135m O.OOE+OO 1.11 E-04 0 OOE+OO Xe135 8.18E-01 1 11 E-04 9 09E-05 Xe137 0.00E+OO 1 11 E-04 0 OOE+OO Xe138 O.OOE+OO 1.11 E-04 O.OOE+OO S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001
\CMR-WEA_
TEA\ GaseousEffluentMon itorSetpointCalculationsRev7 -NE-02-09-12 R 1-CM ROOOOO 11948-001 .xlsx Page D 83 WEACalculations Page 12of14 2/4/2014 NE-02-09-12 003 page D.49 of 76 NE-02-09-12 Rev 2 Appendix D Radioactive Waste Building Monitor Setpoint Calculation For Beta detectors 0NEA) the relative efficiency is calculated in the following table. Table 4.10a Relative Efficiency Relative Nuclide Efficiency( 1) E(Xe-133)
Kr83m 0.050 1.81E+07 Kr85m 1.626 1.81E+07 Kr87 2.208 1.81E+07 Kr88 1.549 1.81E+07 Kr89 2.259 1.81E+07 Xe131m 1.122 1.81E+07 Xe133m 1.449 1.81E+07 Xe133 1.000 1.81E+07 Xe135m 0.387 1.81E+07 Xe135 1.953 1.81E+07 Xe137 2.318 1 81E+07 Xe138 2.005 1 81E+07 (1) NE-02-08-08 Table4.11a Counts above Background Nuclide Cii E11 Kr83m 0.00E+OO n/a Kr85m O.OOE+OO n/a Kr87 O.OOE+OO nla Kr88 0.00E+OO n/a Kr89 O.OOE+OO nla Xe131m O.OOE+OO n/a Xe133m O.OOE+OO n/a Xe133 2.02E-05 1 81E+07 Xe135m 0.00E+OO nla Xe135 9.09E-05 3 54E+07 Xe137 O.OOE+OO n/a Xe138 O.OOE+OO n/a CRj= Eii nla nla n/a nla n/a n/a n/a 1.81E+07 n/a 3.54E+07 n/a nta CRii O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0 OOE+OO O.OOE+OO 3 66E+02 0 OOE+OO 3 21E+03 0 OOE+OO O.OOE+OO 3 58E+03 I I I C.Rj Cij Eij :: = = Count rate above background (cpm) Maximum acceptable concentration of noble gas i (µCi/cc) Effluent monitor detection efficiency for nuclide i (cpm/µCi/cc) cpm 1.98E-04 µCi/cc ' S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001
\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev?-NE-02-09-12 R1-CMR0000011948-001.xlsx WEACalculations Page 13 of 14 Page D 84 2/4/201 4 NE-02-09-12 003 page D.50 of 76 NE-02-09-12 Rev 2 Appendix D Radioactive Waste Building Monitor Setpoint Calculation Radwaste Building 7.83E+03 11Ci/s Step 4.13 Maximum Allowable Setpoint = I 46+3580 I= I 3626 lcpm 2.00E-04 11Ci/cc Step 4.14 Upper Level = I 2901 I Based on instrument range, accuracy, and the ability to accurately read instrument values, select an Upper Level that is less than or equal to 80% of the maximum allowable setpoint value determined in Step 4.13. Activity S ignal s C h 1 & Ch 3 i n 11 Cilcc Effluent Activity Signal Ch 4 11Ci/s High Alarm High Alarm UL 1.60E-04 80% of Max UL 6.27E+03 Nominal 1.46Ec04 91% of UL Nominal 5.70E+03 91% of UL Lower Level 1.31E-04 82% of UL Lower Level 5.14E+03 82% of UL Bkg 2.54E-06 Bkg 9.94E+01 Alert Alarm 1.18E-05 Bkg*4.66 High Alarm 4.63E+02 Bkg*4 66 Alert Alarm 1.19E-05 Rounded up High Alarm 4.64E+02 Rounded up UL 1.43E-05 120% of Nominal UL 5.57E+02 120% of Nominal Nominal 1.19E-05 Alarm Nominal 4.64E+02 Alarm LL 9.52E-06 80% of Nominal LL 3.71E+02 80% of Nominal S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE--02--09-12
.001 \CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE--02-09-12 R1-CMR0000011948-001 xls x WEACalculat i ons Page 14 of 14 Page D.85 21412014 NE-02-09-12 003 page D.51 of 76 E-02-09-12 Rev 2 Appendix 0 INPUT VALUE S page 0.86 This spreadsheet was derived from PPM 16.14.1 Rev 2 (ODCM dispersion value changes) and E/1-02-94-1312 loop uncertainties/instrument drift Reacto r Building I ntermediat e R an g e Mo n it o r PRM-RE-1B Ga s Mixture S ee ODC M T abl e 3-15 a n d FS ARTable 11.3-1 X/Q j 8.20E-07 sec/m 3 X/Q j f or t he R eacto r B uildin g r elease pathway f rom OOCM Table 3-3. F J 1 F orty percen t (40%) of th e site boundary dose rate limit is allocated to the Reactor building, FJ i s 0.4 R J 4.48E+07 cc/sec T h e maximum exhaust flow rate (Rj) i s 4.48E+07 cc/sec (9 5 , 000 cfm) E(X e-1 33) 5 51E+05 ccps/uCl/cc Xenon-133 e fficiency (G a s Calibration factor from C hemistry Calculation 96-001, Attachment 3 Page 5) Bkg 5.50E+02 cps Background (NE-02-10-01 C MR 0000010357) step 4.1 3 value= Based o n i nstrument range , a ccuracy, and the ability t o accurately read instrument values, s elect an Upper Level that is less than or Upper Level 1 OOE+03 355 0 equal to th e maximum allowable setpoint value determined in Step 4.13 Turbin e Building Lo w R ang e Monitor (T EA-R E-1 3) Gas Mixture S ee F S AR Table 11 3-7 X/Q j 1.SOE-05 sec/m3 X/Qj for t he T urbine Build i n g r elease pathway from ODCM Table 3-3. F j 1 Forty percent (40%) of the s ite boundary dose rate limit i s allocated t o the Turbin e building FJ IS 0 4 Rj 1.79E+08 cc/sec The maximum exhaus t flow rate (Rj) is 1.79E+08 cc/sec (380,000 cfm). E(Xe-133) 2.15E+07 cpm/uCi/c c Xenon-133 efficiency c pm/uCi/cc from NE-02-08-09 Bkg 46 cpm Background (NE-0 2-10-01 CMR 0000011647)
Step 4.13va1ue = Based on instrument range, accuracy , and the ability to accurately read instrument values, select an Upper Leve l that is less than or Upper Level 3.81E+02 1122 equal to 80% of the maximum allowable setpoint value determined in S te p 4. 13 Radwaste Building L o w Ra nge Monito r (WEA-RE-1 4) Gas Mixture See FSAR T able 1 1 3-7 X/Qj 1.SOE-05 sec/m3 X/Qj f or the Radwaste Building release pathway from ODCM Table 3-3. F J 1 Twenty percent (20%) of the site boundary dose rate limit is allocated to the Radwaste building.
FJ 1s 0 ::!. Rj 3.91E+07 cc/sec The maximum exhaust flow rate (Rj) is 3.91E+07 cc/sec (83,000 cfm) E (Xe-133) 1 81E+07 cpm/uCi/cc X enon-1 33 efficiency cpm/uCi/cc from PPM 16 3.1 Rev 7 46 cpm B ackground (NE-02-10-01 CMR 0000011647)
Bkg Step 4 13 value= Based on instrumen t range, accuracy , and the ability to accurately read instrumen t values. select an Upper Level that is less than or U pper Level 2.90E+03 17948 equal to 80% of the maximum allowable setpoint value d etermined in Step 4. 13 S \Engineering\Rx Fuels Eng\Fuels\EPG S A G\CR00244578\calc\NE-0 2-0 9-1 2 001\CMR-WEA_
TEA\ G aseousEffiuentMonitorSetpointCalculationsRev?
-NE-02-09-12 R 1 *C MR0000011948-001 xlsx Inputs PAGE 1 OF 1 3 2/4/20 14 NE-02-09-12 003 page D.52 of 76 NE-02-09-12 Rev 2 Mechanical Vacuum Pump (AR-RIS-21)
Gas Mixture X/Qj 8.20E-07 sec/m3 Fj 0.4 Rj 1.13E+06 cc/sec Appendix D INPUT VALUES Setpoint Calculation 98-01 of 3/3/98 & B&R Gal c ulat i on 5 03.01 of 3/80 by E Stergokes X/Qj for the Reactor Building release pathway from ODCM Table 3-3. Forty percent (40%) of the site boundary dose rate l i m i t is allocated to the Reactor building, Fj is 0.4 The maximum exhaust flow rate (RJ) is 1.13E+06 cc/sec (2400 cfm) page D.87 Xenon-133 efficiency mR/hr/uCi l cc f r om Setpoint Calculation 98-01. lsoshield calculation of initial mixture=0.34 mr/hr. (0 34/4.56E-E(Xe-133) 7.14E+01 mR/hr/uCilcc 3)=71.3686 mR/hr/uCi/cc Bkg 0.1 cpm Background step 4.13 value= Based on instrument range, accuracy, and the ability to accurately read instrument values, select an Upper Level that 1s less than or Upper Level 75 7.6 equal to the maximum allowable setpoint value determined in Step 4 13 S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001
\CMR-WEA_
TEAi GaseousEffiuentMonitorSetpointGalculationsRev7-NE 09-12 R1 -CMR0000011948-001
.xlsx Inputs PAGE 2 OF 13 2/412014 NE-02-09-12 003 page D.53 of 76 NE-02-09-12 Rev 2 Appen d ix D page D 88 Reactor Building Intermediate Range Monitor Setpoint Calculation Reactor Building Setpoint Calculation Table 4.3a Nuclide Mii MTi 1 6.47E-05 2.25E-03 Kr85m 1.25E-04 2.25E-03 Kr87 3.35E-07 2.25E-03 Kr88 3.35E-04 2.25E-03 Kr89 4.02E-04 2.25E-03 Xe131m 3.35E-07 2.25E-03 Xe133m 6.25E-06 2.25E-03 Xe133 1.83E-04 2.25E-03 Xe135m 1.54E-04 2.25E-03 1 4.91E-04 2.25E-03 Xe137 1.50E-05 2 25E-03 Xe138 4.69E-04 2.25E-03 Sum 2.25E-03 Table 4.4a Maximum Release Rate Nuclide lTii Ki Kr83m 2.88E-02 0.0756 1 5.57E-02 1170 Kr87 1.49E-04 5920 Kr88 1.49E-01 14700 Kr89 1.79E-01 16600 Xe131m 1.49E-04 91.5 Xe133m 2.78E-03 251 Xe133 8.15E-02 294 Xe135m 6.86E-02 3120 Xe135 2 19E-01 1810 Xe137 6.66E-03 1420 Xe138 2.09E-01 8830 Sum of Tiij"Ki= lTii 2.88E-02 5.57E-02 1.49E-04 1.49E-01 1.79E-01 1.49E-04 2.78E-03 8.15E-02 6.86E-02 2.19E-01 6.66E-03 2.09E-01 1.00E+OO (lTiil(Ki) 2.18E-03 6.51E+01 8.83E-01 2.19E+03 2.97E+03 1.36E-02 6.99E-01 2.40E+01 2.14E+02 3 96E+02 9 46E+OO 1.84E+03 7.72E+03 MiJ Measured or estimated concentration of nuclide i rn release path j (µCi/cc) MTJ Measured or estimated total concentration of all gases in release path j (µCi/cc) lTij Fraction of each nuclide released (unitless)
Whole Body Dose Rate QTj Maximum Release Rate based on Whole Body Dose (uCi/sec)
FJ Fraction of total dose allocated to this release pathway (Dimensionless) 500 Whole body dose rate limit (mrem/yr)
X/Qi Maximum normalized diffusion coefficient for this pathway at and beyond the site boundary (sec/m3) QTJ= QTJ= Ki Total whole body dose factor due to gamma emission from nuclide i, as listed in the ODCM or Reg Guide 1.109, revision 1 (mrem/year per µCi/m3) mj Is the fraction of the total activity for nuclide i (Dimensionless) m Total number of nuclides in the gaseous effluent Release pathway F *soo t xtQ1*Sum m *K1 1.00E+OO 5.00E+02 = OJOE+04--)uCi/sec 8.20E-07 7.72E+03 S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09
-12.001 \CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001
.xlsx REACalculations Page 3 of 13 2/4/20 1 4 NE-02-09-12 003 page D.54 of 76 NE-02-09-12 Rev 2 Appendix D Reactor Building Intermediate Range Monitor Setpoint Calculation Table 4.5a Maximum Release Rate Nuclide 1Tii Li+1.1Mi 11Tii)(Li+1.1 Mi) Kr83m 2.88E-02 0 O.OOE+OO Kr85m 5.57E-02 2.81E+03 1.56E+02 Kr87 1.49E-04 1.65E+04 2.46E+OO Skin Dose Calculation Kr88 1.49E-01 1.91 E+04 2.85E+03 3000 Dose Rate Limit Kr89 1.79E-01 2.91E+04 5.21 E+03 Xe131m 1.49E-04 6.48E+02 9.66E-02 QTj= 1 OOE+OO 3 OOE+03 = [ 3.01E+Cl5-]uCi/sec Xe133m 2.78E-03 1.35E+03 3 76E+OO 8.20E-07 1.22E+04 Xe133 8.15E-02 6.94E+02 5.66E+01 Xe135m 6.86E-02 4.41E+03 3.03E+02 Xe135 2.19E-01 2 30E+03 5.03E+02 Xe137 6.66E-03 1.39E+04 9 26E+01 Lowest Dose Rate Value Xe138 2.09E-01 1.43E+04 2 99E+03 QTj = I 7 90E+04 luCi/sec Sum(mi\(Li+
1 1 Mil = 1.22E+04 Step 4.7 Table 4.8a Maximum Allowable Value Maximum Nuclide Concentration CTj = (QTj/Rj) Nuclide 1Tii CTi Cii RJ = Release Rate Kr83m 2.88E-02 1.76E-03 5.09E-05 Kr85m 5.57E-02 1.76E-03 9.82E-05 CTJ = maximum allowed CT j = I 7.90E+04 I = I 1.76E-03 luCi/cc Kr87 1.49E-04 1.76E-03 2.63E-07 4.48E+07 Kr88 1.49E-01 1.76E-03 2.63E-04 Kr89 1.79E-01 1.76E-03 3.16E-04 Xe131m 1.49E-04 1.76E-03 2.63E-07 Xe133m 2.78E-03 1.76E-03 4.91E-06 Xe133 8.15E-02 1.76E-03 1.44E-04 Xe135m 6.86E-02 1.76E-03 1.21E-04 Xe135 2.19E-01 1.76E-03 3.86E-04 Xe137 6.66E-03 1.76E-03 1.17E-05 Xe138 2 09E-01 1.76E-03 3.68E-04 S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001
\CMR-WEA_
TEAi GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R 1-CMROOOOO 11948-001.xlsx REACalculations Page 4 of 13 page D 89 2/4/2014 NE-02-09-12 003 page D.55 of 76 NE-02-09-12 Rev 2 Appendix D Reactor Building Intermediate Range Monitor Setpoint Calculation For Gamma Detectors (REA) !he relative efficiencies is calculated in the following table. T able 4.9a R e l ativ e Efficienc y Ga mma R elative Nuclide Ab undance Abundance E(Xe-13 3) Kr83m 0.0 9 0.245 5.51E+05 Kr85m 0.7 4 2.016 5.51 E+05 Kr87 0.83 7 2.2 8 1 5.51E+05 Kr88 1.37 2 3.738 5.51E+05 Kr89 1.6 4.36 5.51E+05 Xe 131m 0.01 9 6 0.053 5.51E+05 Xe1 3 3m 0.1 4 0.38 1 5.51 E+05 Xe 133 0.367 1 5.51 E+05 Xe 1 3 5 m 0.81 2.20 7 5.51E+05 Xe 135 0.93 9 2.559 5.51E+05 Xe 13 7 0.33 0.899 5.51 E+05 Xe 13 8 1.222 3.33 5.51E+05 Table 4.11a Counts above Background Nuclide Cij Eii C.Ri1 Kr83m 5.09E-05 1.35E+05 6.86E+OO Kr85m 9.82E-05 1.11E+06 1.09E+02 Kr87 2.63E-07 1.26E+06 3.30E-01 Kr88 2.63E-04 2.06E+06 5.41E+02 Kr89 3.16E-04 2.40E+06 7.58E+02 Xe131m 2.63E-07 2.92E+04 7.67E-03 Xe133m 4.91E-06 2.10E+05 1.03E+OO Xe133 1.44E-04 5.51E+05 7.92E+01 Xe135m 1.21 E-04 1.21E+06 1.47E+02 Xe135 3.86E-04 1.41E+06 5.43E+02 Xe137 1 17E-05 4.95E+05 5.81E+OO Xe138 3.68E-04 1.83E+06 6.75E+02 C.Rj:: 3.00E+03 E i i 1.35E+05 1.11E+06 1.26E+06 2.06E+06 2.40E+06 2.92E+04 2.10E+05 5.51 E+05 1.21E+06 1.41E+06 4.95E+05 1.83E+06 Eij:: C.Rj:: Cij= Eij:: Step 4.13 Effluent monitor detection efficiency for nuclide i (ccps/µCi/cc)
Count rate above background (cps) Maximum acceptable concentration of noble gas i (µCi/cc) Effluent monitor detection efficiency for nuclide i (ccps/µCi/cc)
Reactor Building Maximum Allowable Setpoint Bkg+C.Rj = I 3,550 I Step 4 14 Upper Level (UL) = C!faoo*J Note, there is only one alarm on this system Step 4.16 2 Alarm UL Nominal Lower Level 1,000 I 910 191%ofUL 820 82% of UL S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001.xlsx REACalculations Page 5 of 13 page D.90 2/4/2014 NE-02-09-12 003 page D.56 of 76 NE-02-09-12 Rev 2 Turbine Building Setpoint Calculation T able 4.3a N u cl i d e M i j MT i lT i i 1 O.OOE+OO 1.15E+02 0.00 K r85m 2.25E+OO 1.15E+02 0.02 K r87 6.34E+OO 1.15E+02 0.05 K r88 7.61E+OO 1.15E+02 0.07 K r89 0.00E+OO 1.15E+02 0.00 Xe131m O.OOE+OO 1.15E+02 0.00 Xe 1 3 3m O.OOE+OO 1.15E+02 0.00 Xe 133 9.19E+OO 1.15E+02 0.08 Xe135 m 2.15E+01 1.15E+02 0.19 1 2.09E+01 1.15E+02 0. 18 Xe13 7 0.00E+OO 1.15E+02 0.00 Xe 1 38 4.75E+01 1.15E+02 0.41 S um 1.15E+02 1.00 T able 4.4 a Max i mum Release R at e Nuclide lTi i Ki (TT i il(Ki) Kr83m 0.00 0.0 7 5 6 O.OOE+OO 1 0.02 1170 2.28E+01 Kr87 0.05 5 92 0 3.25E+02 Kr8 8 0.07 1 4700 9.69E+02 T urbin e BL 0.00 1 6600 O.OOE+OO Xe 131m 0.00 9 1.5 O.OOE+OO Xe 13 3 m 0.00 25 1 O.OOE+OO Xe133 0.08 294 2.34E+01 Xe 135 m 0.19 31 2 0 5.83E+02 Xe135 0.18 1810 3 2BE+02 Xe137 0.00 14 2 0 0 OOE+OO Xe13 8 0 41 88 3 0 3 64E+03 S u m of Tiij*Ki= 5.89E+03 Appendix D Turbine Building Monitor S etpoint Calculation Mij Measured or estimated concentration of nuclide i in release path j (µCi/cc) MTj Measured or estimated total concentration of all gases in release path j (µCi/cc) Tiij Fraction of each nuclide released Whole Body Dose Rate = (Fj*500)/(X/Qi*Sum(rrij*Ki)
QTj Maximum Release Rate based on Whole Body Dose Fj Fraction of total dose allocated to this release pathway (Dimensionless) 500 Whole body dose rate limit X/Qi Maximum normalized diffusion coefficient for this pathway at and beyond the site boundary (sec/m3) Ki Total whole body dose factor due to gamma emission from nuclide i. as listed in the ODCM or Reg Guide 1.109 , revision 1 (mrem/year per µCi/m3) lT i J Is the fraction of the total activity for nuclide i (Dimensionless) m Total number of nuclides in the gaseous effluent Release pathway QTJ= 1 OOE+OO 5 OOE+02 = 1 50E-05 5.89E+03 [5Jl6E+b[l uCi/sec S: \Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12
.001 \CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001
.xlsx TEACalculations Page 6 of 13 page 091 2/4/2014 NE-02-09-12 003 page D.57 of 76 NE-02-09-1 2 Rev 2 T ab le 4.5 a M aximum R e l ea se Rate N uclid e rri j Li+1.1 Mi 'rr ij)(Li+ 1 .1 M i) Kr83m 0.00 0 O.OOE+OO K r8 5 m 0.02 2.8 1 E+03 5.48E+01 Kr87 0.05 1.6 5E+0 4 9.06E+02 Kr88 0.07 1.9 1 E+0 4 1.26E+03 Kr89 0.00 2.91 E+04 O.OOE+OO Xe13 1 m 0.00 6.4 8 E+0 2 O.OOE+OO X e1 33m 0.00 1.35E+0 3 O.OOE+OO Xe1 33 0.08 6.94 E+02 5.53E+01 Xe 1 3 5 m 0.19 4.4 1 E+0 3 8.24E+02 Xe 1 35 0 18 2.30E+0 3 4.17E+02 Xe 1 37 000 1.39E+04 O.OOE+OO Xe 1 3 8 0.41 1.4 3 E+04 589E+03 S um f rri' 1(li+1.1 Mi)= 9.41E+03 T abl e 4.8a M aximu m N uclide Co n c e n trat io n N uclid e rrii CT i C i i Kr83m 0.00 3.16E-05 O.OOE+OO K r8 5m 002 3. 16E-05 6.17E-07 K r87 0.05 3 16E-05 1 74E-06 Kr8 8 0.07 3.16E-05 2 08E-06 Kr8 9 0.00 3 16E-05 O.OOE+OO Xe 1 3 1 m 0.00 316E-05 O.OOE+OO Xe13 3 m 0.00 3.16E-05 O.OOE+OO Xe 133 0.08 3.16E-05 2.52E-06 X e 1 3 5m 0.19 3.16E-05 5 91E-06 X e 1 35 0.18 3.16E-05 5 73E-06 X e1 37 000 3.16E-05 0.00E+OO Xe 1 3 8 0.41 3.16E-05 1 30E-05 Appendix D T urbine Buildin g M o nito r S etpoin t C alculation
S ki n Do se R ate = (Ft3000)/(X/
Q 1*Sum(mj*Ki) 300 0 D os e Rate li mi t QTj= 1.00E+OO 3 OOE+03 =
1 50E-05 9 41 E+03 R ele a s e r a te f or l o west d os e rate valu e (Whol e body o r S kin) QTj =I 5.66E+03 luCi/se c S te p 4.7 Max imum Allowable C oncen t ration (CTJ) C Tj = (OTJ/R j) Q T i=maximum acceptable release rat e for all nobl e ga ses (u C i/sec) Rj = Re lease R ate c c/sec) C T J = 5.66E+03 = I 3.16E-05 luCi/cc 1.79E+08 S.\Engineering\Rx F uels E ng\F u els\E PGS A G\C R0024 4578\ca l c\NE-0 2-0 9-12 0 01 \C MR-WE A_ T EA\ G aseousEffluentMonitor S etpoin tC a l cu l a t ionsPev7-NE-02 1 2 R 1-C MR00000 1 1948-001.xlsx TEACalculations Page 7 of 13 p age D 92 2/4/201 4 NE-02-09-12 003 page D.58 of 76 NE-02-09-1 2 Rev 2 Appendix D T urbine Building Monitor Setpoint Calculation For the TEA Beta detector the relative efficiency is calculated in the following table. T able 4.10a Relativ e Efficienc y R elat i ve Eff i ciency ( 1 Nuc li d e ) E(Xe-133) Kr83m 0.0 5 0 2.15E+07 Kr85m 1.6 2 2 2.15E+07 Kr87 2.2 0 5 2.15E+07 Kr88 1.544 2.15E+07 K r8 9 2.25 5 2.15E+07 Xe13 1 m 1.119 2.15E+07 X e133 m 1.444 2.15E+07 X e 13 3 1.000 2.15E+07 X e13 5m 0.3 87 2.15E+07 Xe135 1.9 4 9 2.15E+07 Xe13 7 2.3 1 5 2.15E+07 Xe1 3 8 1.99 9 2.15E+07 (1) NE-02-08-09 T able 4.11a C ount Rat e Co ntribution s Nuclid e C i j Ei i Kr8 3 m O.OOE+OO nla Kr85m 6.17E-07 3 49E+07 K r8 7 1.74E-06 4.74E+07 Kr8 8 2.08E-06 3.32E+07 Kr89 O.OOE+OO n/a Xe 131 m O.OOE+OO nla Xe13 3m O.OOE+OO n/a Xe13 3 2.52E-06 2.15E+07 Xe1 3 5m 5.91E-06 8.32E+06 Xe 1 35 5.73E-06 4.19E+07 X e13 7 0 OOE+OO nla X e 13 8 1 30E-05 4.30E+07 C.R j= E ii n/a 3.49E+07 4.74E+07 3.32E+07 n/a n/a n/a 2.15E+07 8.32E+06 4.19E+07 nla 4.30E+07 C.R ii O.OOE+OO 2 15E+01 8.23E+01 6.92E+01 O.OOE+OO O.OOE+OO O.OOE+OO 5.42E+01 4.91E+01 2.40E+02 O.OOE+OO 5 60E+02 1 08E+03 I Eij=Effluent monitor detection efficiency f or nuclide i (cpm/µCi/cc)
CRj Cij Eij = = = C ount rate above b ac k ground (cpm) Maximum acceptable concentration of noble gas i (µCi/cc) Effluent monitor detection efficiency for nuclide i (cpm/µCi/cc) cpm 5.01 E-05 !'C i/cc ' S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02..09-12.001
\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001 xlsx TEACalculations Page 8 of 13 page D.93 2/4/2014 NE-02-09-12 003 page D.59 of 76 NE-02-09-1 2 Rev 2 Appendix D T urbine Building Monitor Setpoint Calculation Turbine Building 9.35E+03 pCi/s Step 4.13 Maximum Allowable Setpoint=Bkg+C.Rj=
Q6+1016 I = I 1122 lcpm Step 4.14 Upper Level= 5.22E-05 pCi/cc I 381 !Based on instrument range, accuracy, and the ability to accurately read instrument values, selec t an U pper Level that is less than or equal to 80% of the maximum allowable setpoint value determined in Step 4.13. Activity S ignal s Ch 1 & Ch 3 i n pC i/c c Effluent Activity Signal Ch 4 pCi/s High Alar m High Alarm UL 1.77E-05 UL 3.17E+03 Nominal 1.61 E-05 91% of UL Nominal 2.89E+03 91% of UL Lower Leve 1.45E-05 82% of UL Lower Level 2.60E+03 82% of UL Bkg 2.14E-06 Bkg 3.83E+02 Alert Alarm 9.97E-06 Bkg*4.66 Alert Alarm 1.78E+03 Bkg*4.66 Alert Alarm 9.98E-06 Rounded up Alert Alarm 1.79E+03 Rounded up UL 1.20E-05 120% of Nominal UL 2.15E+03 120% of Nominal Nominal 9.98E-06 Alarm Nominal 1.79E+03 Alarm LL 7.98E-06 80% of Nominal LL 1.43E+03 80% of Nominal S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12
.001 \CMR-WEA_ TEA\ GaseousEffluentMonitorSetpointCalculationsRev7
-NE-02-09-12 R1-CMROOOOO 11948-001.xlsx TEACalculations Page 9 of 13 page D 94 2/4/2014 NE-02-09-12 003 page D.60 of 76 NE-02-09-12 Rev 2 Appendix D R adioactive Waste Building Monitor Setpoint Calculation Radwaste Buildin g Setpo i n t Calc ul a ti o n Table 4.3a Nuclide Mij MTj 1 O.OOE+OO 1.74E+OO Kr85m O.OOE+OO 1.74E+OO Kr87 0.00E+OO 1.74E+OO Kr88 O.OOE+OO 1.74E+OO Kr89 O.OOE+OO 1.74E+OO Xe131m O.OOE+OO 1.74E+OO Xe133m O.OOE+OO 1.74E+OO Xe133 3.17E-01 1.74E+OO Xe135m 0.00E+OO 1.74E+OO 1 1.43E+OO 1.74E+OO Xe137 O.OOE+OO 1.74E+OO Xe138 0.00E+OO 1.74E+OO Sum 1.74E+OO Table 4.4a Maximum Release Rate Nuclide TT ii Ki Kr83m O.OOE+OO 0.0756 1 O.OOE+OO 1170 Kr87 0.00E+OO 5920 Kr88 O.OOE+OO 14700 Kr89 0.00E+OO 16600 Xe131m O.OOE+OO 91.5 Xe133m 0.00E+OO 251 Xe133 1.82E-01 294 Xe135m O.OOE+OO 3120 Xe135 8 18E-01 1810 Xe137 0 OOE+OO 1420 Xe138 0.00E+OO 8830 Sum of rrij*Ki= TTij O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 1.82E-01 O.OOE+OO 8.1 SE-01 0.00E+OO O.OOE+OO (TTii)(Ki)
O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.35E+01 O.OOE+OO 1.48E+03 O.OOE+OO O.OOE+OO 1.53E+03 Mij Measured or estimated concentration of nuclide i in release path j (µCi/cc) MTj Measured or estimated total concentration of all gases in release path j (µCi/cc) TTij Fraction of each nuclide released Whole Body Dose Rate = (Fj*500)/(X/Qi*Sum(TTij*Ki)
QTj Maximum Release Rate based on Whole Body Dose Fj Fraction of total dose allocated to this release pathway (Dimensionless) 500 Whole body dose rate limit X/Qi Maximum normalized diffusion coefficient for this pathway at and beyond the site boundary (sec/m3) Ki Total whole body dose factor due to gamma emission from nuclide i, as listed in the ODCM or Reg Guide 1.109, revision 1 (mrern/year per µCi/m3) TTij Is the fraction of the total activity for nuclide i (Dimensionless) m Total number of nuclides in the gaseous effluent Pelease pathway OTJ= 1 OOE+OO 5.00E+02 = 1.50E-05 1 53E+03 [ 2.17E+04 JuCi/sec S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001
\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001.xlsx WEACalculations Page 10 of 13 page D 95 2/4/20 14 NE-02-09-12 003 page D.61 of 76 NE-02-09-12 Rev 2 Table 4.5a Maximum Release Rate Nuclide TTij Li+1.1Mi (rrij)(Li+
1.1 Mi) Kr83m O.OOE+OO 0 O.OOE+OO Kr85m O.OOE+OO 2.81 E+03 O.OOE+OO Kr87 0.00E+OO 1.65E+04 O.OOE+OO Kr88 O.OOE+OO 1.91E+04 O.OOE+OO Kr89 O.OOE+OO 2.91 E+04 O.OOE+OO Xe131m 0 OOE+OO 6.48E+02 O.OOE+OO Xe133m O.OOE+OO 1.35E+03 O.OOE+OO Xe133 1.82E-01 6.94E+02 1.26E+02 Xe135m 0.00E+OO 4.41 E+03 O.OOE+OO Xe135 8.18E-01 2.30E+03 1.88E+03 Xe137 O.OOE+OO 1.39E+04 O.OOE+OO Xe138 0.00E+OO 1.43E+04 O.OOE+OO Sum(rrij l(Li+1.1Mi)
= 2.01E+03 Table 4.8a Maximum Nuclide Concentration Nuclide TTij CTi Cii Kr83m O.OOE+OO 5.56E-04 O.OOE+OO Appendix D Radioactive Waste Building Monitor Setpoint Calculation
Skin Dose Rate = (Fj*3000)/(X/Qi*Sum(rrij'Ki) 3000 Dose Rate Limit QTj= 1.00E+OO 3.00E+03 1.50E-05 2.01 E+03 Lowest Dose Rate Value I 2.17E+04 luCi/sec Step 4.7 Maximum Allowable Value CTJ = (OTJ/RJ) RJ = Release Rate CTj = maximum allowed concentration
= I 9.96E+04]uCi/sec Kr85m O.OOE+OO 5.56E-04 O.OOE+OO CTj = I 2.17E+04 I = I 5.56E-04 I 3.91E+07 Kr87 0 OOE+OO 5.56E-04 O.OOE+OO Kr88 0 OOE+OO 5.56E-0.4 0.00E+OO Kr89 O.OOE+OO 5.56E-04 O.OOE+OO Xe131m O.OOE+OO 5.56E-04 O.OOE+OO Xe133m O.OOE+OO 5.56E-04 O.OOE+OO Xe133 1.82E-01 5.56E-04 1.01 E-04 Xe135m O.OOE+OO 5.56E-04 0.00E+OO Xe135 8.18E-01 5.56E-04 4.55E-04 Xe137 O.OOE+OO 5.56E-04 O.OOE+OO Xe138 O.OOE+OO 5.56E-04 O.OOE+OO S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001
.xlsx page 0.96 WEACalculations Page 11 of 13 2/4/2014 NE-02-09-12 003 page D.62 of 76 NE-02-09-12 Rev 2 Appendix D Radioactive Waste Building Monitor Setpoint Calculation For Beta detectors (WEA) the relative efficiency is calculated in the following table. Table4.10a Relative Efficiency Relative Nuclide Efficiencv(1)
E(Xe-133)
Kr83m 0 050 1.81E+07 Kr85m 1.626 1.81 E+07 Kr87 2.208 1.81E+07 Kr88 1.549 1.81E+07 Kr89 2.259 1.81E+07 Xe131m 1.122 1.81E+07 Xe133m 1.449 1.81E+07 Xe133 1.000 1.81E+07 Xe135m 0.387 1.81E+07 Xe135 1.953 1 81E+07 Xe137 2.318 1.81E+07 Xe138 2.005 1 81E+07 (1) NE-02-08-08 Table 4.11a Counts above Background Nuclide Cii Eii Kr83m O.OOE+OO nla Kr85m O.OOE+OO n/a Kr87 O.OOE+OO nla Kr88 O.OOE+OO n/a Kr89 O.OOE+OO nla Xe131m O.OOE+OO nla Xe133m O.OOE+OO nla Xe133 1.01E-04 1.81E+07 Xe135m O.OOE+OO nla Xe135 4.55E-04 3.54E+07 Xe137 0 OOE+OO n/a Xe138 0 OOE+OO n/a C.Rj = Eii n/a nla nla nta n/a nla nta 1.81E+07 nla 3.54E+07 nla nla C.Rii O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.83E+03 O.OOE+OO 1.61E+04 O.OOE+OO O.OOE+OO 1.79E+04 ' ' C.Rj Cij Eij = = = Count rate above background (cpm) Maximum acceptable concentration of noble gas i (µCi/cc) Effluent monitor detection efficiency for nuclide i (cpm/µCi/cc) cpm 9.89E-04 .. CiJcc I S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001
.xlsx WEACalculations Page 12 of 13 page D.97 2/4/2014 NE-02-09-12 003 page D.63 of 76 NE-02-09-12 Rev 2 Appendix D Ra dioactive Waste Building Monitor Setpoint Calculation Radwaste Building 3.88E+04 11Ci/s Step 4.13 Maximum Allowable S etpoint = I 46+17902 I= I 17948 lcpm 9.92E-04 11Ci/cc Step 4 14 Upper Level= I 2901 !Based on instrument range, accuracy, and the abihty to accurately read instrument values, select an Upper Level that is less than or equal to 80% of the maximum allowable setpoint value determined in Step 4 13. Activity Signal s Ch 1 & Ch 3 in 11 Ci/cc Effluent Activity Signal Ch 4 11Ci/s High Alarm High Alarm UL 1.60E-04 80% of Max UL 6.27E+03 Nominal 1.46E-04 91% of UL Nominal 5.70E+03 91% of UL Lower Level 1.31E-04 82% of UL Lower Level 5.14E+03 82% of UL Bkg 2.54E-06 Bkg 9.94E+01 Alert Alarm 1.18E-05 Bkg*4.66 High Alarm 4.63E+02 Bkg*4 66 Alert Alarm 1.19E-05 Rounded up High Alarm 4.64E+02 Rounded up UL 1.43E-05 120% of Nominal UL 5.57E+02 120% of Nominal Nominal 1.19E-05 Alarm Nominal 4.64E+02 Alarm LL 9.52E-06 80% of Nominal LL 3 71E+02 80% of Nominal S: \Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02--09-12.001
\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE--02-09-12 R1-CMR0000011948-001.xlsx WEACalculations Page 13 of 13 page D 98 2/4/2014 NE-02-09-12 003 page D.64 of 76 NE-02..0S.12 Rev::? Appendix O page O 99 I NP U T V A LU E S This spreadsheet was derived from PPM 16.14.1 Rev 2 (OOCM dispersion value changes) and E/1-02-94-1312 loop uncertainties/instrument drift Reacto r Building I nterme di ate R ang e Mo n itor P RM-RE-18 Gas M ixtur e S e e O DCM T able 3-15 a n d FS AR Ta bl e 11.3-1 X/Qj 8.20E-07 sec/m 3 X/Qj fo r th e R eacto r B uilding relea se pa thwa y f rom O OCM T able 3-3. Fj 2 Fo rty percent (40%) of the site bounda ry d o se ra te l imit is a llocate d to the R e a ctor buildin g , FJ 1 s 0 4 R j 4.48E+07 cc/sec Th e maximum e xhaus t fl ow rat e (R j) is 4.4 8E+07 cc/s ec (9 5,000 cf m) E (Xe-133) 5.51E+05 ccps/uC1/c c X enon-133 e fficienc y (G a s calibratio n f act o r f ro m C h emistry ca lculatio n 96-00 1 , Attachmen t 3 Pa ge 5) Bk g 5.50E+02 cps Background (NE-0 2-10-01 C MR 00 00010357) step 4 1 3 valu e = Bas e d on ins t rumen t range , ac curacy, a nd t h e ability to acc uratel y r ead instrumen t values , s elec t an U pper Le ve l that is l es s t han o r U pper Le ve l 1.00E+03 65 50 equal to t h e m aximum a ll owa ble s etpoin t valu e determined in S tep 4.1 3 Turbine Building Low R ange Mo n itor (TEA-RE-13) Gas M ixtur e See FS A R Ta ble 11 3-7 X/Qj 1.SOE-05 sec/m 3 X/Qj for th e T urbin e B uilding r e l ea se pathway f rom O OCM T able 3-3. Fi 2 Fo rty pe rcent (4 0%) of t he s ite bo undary d os e rat e limit i s a llocate d to t h e T urbine b uildin g. FJ 1s 0.4 R j 1.79E+08 cc/se c The maximum e xhau st flow rate (R j) is 1.7 9E+08 c c/se c (38 0 ,000 cfm) E (Xe-133) 215E+07 cpmtu C ilc c X enon-133 e fficienc y c pmtu C1/cc from NE-02-08-0 9 Bk g 46 cpm B ackgroun d (NE-02-10-01 C M R 00000 116 47) step 4.1 3 value= B ased on instrumen t rang e , a ccuracy , a nd t he abilfty t o accurately read instrumen t value s , s elect an U pper L evel that is less t han o r U ppe r Le ve l 3.81E+02 2199 e qua l to 80% of the maximum a llowable setpoint value de t ermined in S te p 4.13. Radwaste Building Low Ra n ge Mo n itor (WEA-RE-1 4) Gas M ixtur e See F S A R T abl e 11 3-7 X/Qj 1 50E-05 sec/m 3 X/Qj for th e R adwast e B uildin g r elease pathwa y f rom OOC M T able 3-3. FJ 2 T wenty percen t (2 0%) of the s ite boundary dose rate limit i s allocated to the Radwast e b uilding F J is 0 2 RJ 3.9 1 E+07 cc/sec Th e maximum exhau st fl ow rat e (R j) is 3.91 E+0 7 c c/sec (8 3 ,000 cfm) E(X e-1 33) 1.81E+07 cpmtuCilc c Xe non-1 33 efficien c y c pmtu C i/cc from PPM 16 3.1 R ev 7 B kg 46 cpm Background (NE-02-1 0-0 1 C MR 00000 11 647) St ep 4.13 value= Based on i nstrument range, accuracy, and t he ability t o accurately read ins t rumen t values. s elect an U pper Level that is less t han or Upper Lev e l 2.90E+0 3 35 850 equal to 8 0% of the maximum allowable s etpoint value determined in S te p 4. 13. S. \Engineering\Rx F uels E ng\Fuels\EP GS A G\C R002 4 4578\calc\NE-02-0 9-1 2.001 \C MR-WEA_ TEA\ G aseousEffluentMonitorSetpointCalculationsRev 7 -NE-0 2-09-1 2 R 1-C MR0000 0 1194 8-001 xlsx Inputs PA G E 1 O F 1 3 214/2 014 NE-02-09-12 003 page D.65 of 76 Rev:! Appendix D pageD.100 INPUT VALUE S Mechanical Vacuum Pump (AR-RIS-21)
Gas Mixture Setpoint Calculation 98-01 of 3/3/98 & B&R Calculation 5.03.01 of 3/80 by E Stergokes X/Qj 8.20E-07 sec/m3 X/Qj for the Reactor Building release pathway from ODCM Table 3-3. Fj 0.4 Forty percent (40%) of the site boundary dose rate limit is allocated to the Reactor building, FJ 1s 0.4 Rj 1.13E+06 cc/sec The maximum exhaust flow rate (Rj) is 1.13E+06 cc/sec (2400 cfm) Xenon-133 efficiency mR/hr/uCi/cc from Setpoint Calculation 98-01. lsoshield calculation of i nitial m 1 xture=O 34 mr/hr. (0 34/4.56E-E(Xe-133) 7.14E+01 mR/hr/uCi/cc 3)=71.3686 mR/hr/uCi/cc Bkg 0.1 cpm Background step 4.1 3 value= Based on instrument range , accuracy, and the ability to accurately read instrument values, select an Upper Le v el that is less than or Upper Level 7.5 76 equal to the maximum allo'Nable setpoint value determined in Step 4.13. S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09
-12.001\CMR-WEA_ TEA\ GaseousEffluentMonitorSetpointCalculat i onsRev7-NE-02-09-12 R 1-CMR0000011948-001
.xlsx Inputs PAGE 2 OF 13 214/201 4 NE-02-09-12 003 page D.66 of 76 NE-02-09-12 Rev 2 Appendix D page D.101 Reactor Building Intermediate Range Monitor Setpoint Calculation Reactor Building Setpoint Calculation Table 4.3a Nuclide Mii MTi nij MiJ Measured or estimated concentration of nuclide 1 in release path j (µCi/cc) 2 6.47E-05 2.25E-03 2.88E-02 MTj Measured or estimated total concentration of all gases in release path j (µC1/cc) Kr85m 1.25E-04 2.25E-03 Kr87 3.35E-07 2.25E-03 Kr88 3.35E-04 2.25E-03 Kr89 4.02E-04 2.25E-03 Xe131m 3.35E-07 2.25E-03 Xe133m 6.25E-06 2.25E-03 Xe133 1.83E-04 2.25E-03 Xe135m 1.54E-04 2.25E-03 2 4.91E-04 2.25E-03 Xe137 1.50E-05 2.25E-03 Xe138 4.69E-04 2.25E-03 Sum 2.25E-03 Table 4.4a Maximum Release Rate Nuclide nij Ki Kr83m 2.88E-02 0.0756 2 5.57E-02 1170 Kr87 1.49E-04 5920 Kr88 1.49E-01 14700 Kr89 1 79E-01 16600 Xe131m 1.49E-04 91.5 Xe133m 2.78E-03 251 Xe133 8.15E-02 294 Xe135m 6.86E-02 3120 Xe135 2.19E-01 1810 Xe137 6.66E-03 1420 Xe138 2.09E-01 8830 Sum of mj*Ki= 5.57E-02 1.49E-04 1.49E-01 1.79E-01 1.49E-04 2.78E-03 8.15E-02 6.86E-02 2.19E-01 6.66E-03 2.09E-01 1.00E+OO (nij)(Ki) 2.18E-03 6.51E+01 8.83E-01 2.19E+03 2.97E+03 1.36E-02 6.99E-01 2.40E+01 2.14E+02 3.96E+02 9.46E+OO 1.84E+03 7.72E+03 nij Fraction of each nuclide released {unitless)
Whole Body Dose Rate QTj Maximum Release Rate based on Whole Body Dose (uCi/sec)
FJ Fraction of total dose allocated to this release pathway (Dimensionless) 500 Whole body dose rate limit (mrem/yr)
X/Qi Maximum normalized diffusion coefficient for this pathway at and beyond the site boundary (sec/m3) QTj= QT1= Ki Total whole body dose factor due to gamma emission from nuclide i, as listed in the ODCM or Reg Guide 1.109 revision 1 (mrem/year per µCi/m3) nij Is the fraction of the total activity for nuclide i (Dimensionless) m Total number of nuclides in the gaseous effluent Release pathway
F *500 I X/Q1*Sum m *Ki 2 OOE+OO 5 OOE+02 = I 1.58E+05=1uCi/sec 8 20E-07 7.72E+03 S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12
.001 \CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R 1-CMR0000011948-001.xlsx REACalculations Page 3 of 13 2/4/20 14 NE-02-09-12 003 page D.67 of 76 NE-02-09-12 Rev 2 Appendix D Reactor Building Intermediate Range Monitor Setpoint Calculation Table 4.5a Maximum Release Rate Nuclide TT ii Li+1.1Mi 1 TTij)(Li+
1.1 Mi) Kr83m 2.88E-02 0 O.OOE+OO Kr85m 5.57E-02 2.81 E+03 1.56E+02 Kr87 1.49E-04 1.65E+04 2.46E+OO Skin Dose Calculation Kr88 1.49E-01 1.91 E+04 2.85E+03 3000 Dose Rate Limit Kr89 1.79E-01 2.91 E+04 5.21E+03 Xe131m 1.49E-04 6.48E+02 9.66E-02 QTj= 2 OOE+OO 3.00E+03 = [ 6.02E+0-5
]uCi/sec Xe133m 2.78E-03 1.35E+03 3.76E+OO 8.20E-07 1.22E+04 Xe133 8.15E-02 6.94E+02 5.66E+01 Xe135m 6.86E-02 4.41E+03 3.03E+02 Xe135 2.19E-01 2.30E+03 5.03E+02 Xe137 6.66E-03 1.39E+04 9.26E+01 Lowest Dose Rate Value Xe138 2.09E-01 1.43E+04 2.99E+03 QTj = I 1.58E+05 luCi/sec Sum(m* 1(Li+ 1 1 Mi) = 1.22E+04 Step 4 7 Table 4.8a Maximum Allowable Value Maximum Nuclide Concentration CTJ = (QTJIRJ) Nuclide TTii CTi Cij Rj = Release Rate Kr83m 2.88E-02 3.53E-03 1.02E-04 CTJ = maximum allowed concentra_tio_n'------
CTj = I 1.58E+05 I = I 3.53E-03 luCi/cc Kr85m 5.57E-02 3.53E-03 1.96E-04 Kr87 1.49E-04 3.53E-03 5.26E-07 4.48E+07 Kr88 1.49E-01 3.53E-03 5.26E-04 Kr89 1.79E-01 3.53E-03 6.31E-04 Xe131m 1.49E-04 3.53E-03 5.26E-07 Xe133m 2.78E-03 3.53E-03 9.82E-06 Xe133 8.15E-02 3.53E-03 2.88E-04 Xe135m 6.86E-02 3.53E-03 2.42E-04 Xe135 2.19E-01 3.53E-03 7.72E-04 Xe137 6.66E-03 3.53E-03 2.35E-05 Xe138 2 09E-01 3.53E-03 7.37E-04 S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001.xlsx REACalculations Page 4 of 13 age 0.102 2/4/2014 NE-02-09-12 003 page D.68 of 76 NE-02-09-12 Rev 2 Nuclid e Kr83m Kr85m Kr 87 Kr88 Kr89 Xe1 31m X e 13 3m Xe133 Xe 13 5m Xe 1 35 X e 13 7 Xe138 Nuclide Kr83m Kr85m Kr87 Kr88 Kr89 Xe131m Xe133m Xe133 Xe135m Xe135 Xe137 Xe138 Appendix D Reactor Building Intermediate Range Monitor Setpoint Calculation in the following table T abl e 4.9 a Relat iv e E fficien cy G am m a R e lat iv e Abu ndance Abundanc e 0.0 9 0.24 5 0.7 4 2.01 6 0.837 2.28 1 1.372 3.73 8 1.6 4.36 0.01 96 0 053 0.14 0.38 1 0.367 1 0.81 2.2 0 7 0.93 9 2.55 9 0.33 0.899 1.222 3.33 Table 4.11a Counts above Background Cii Eii 1.02E-04 1.35E+05 1.96E-04 1.11E+06 5.26E-07 1.26E+06 5.26E-04 2.06E+06 6.31E-04 2.40E+06 5.26E-07 2.92E+04 9.82E-06 2.10E+05 2.88E-04 5.51E+05 2.42E-04 1.21E+06 7.72E-04 1.41E+06 2.35E-05 4.95E+05 7.37E-04 1.83E+06 C.Rj = E (X e-133) Eii 5.51E+05 1.35E+05 5.51E+05 1.11 E+06 5.51E+05 1.26E+06 5.51E+05 2.06E+06 5.51E+05 2.40E+06 5.51 E+05 2.92E+04 5.51E+05 2.10E+05 5.51 E+05 5.51 E+05 5.51E+05 1.21E+06 5.51E+05 1.41E+06 5.51E+05 4.95E+05 5.51E+05 1.83E+06 C.Rii 1.37E+01 2.18E+02 6.61E-01 1.08E+03 1.52E+03 1.53E-02 2.06E+OO 1.58E+02 2.94E+02 1.09E+03 1.16E+01 1.35E+03 6.00E+03 Erj= C.Rj= Cij= Eij= Step 4.13 Effluent monitor detection efficiency for nuclide i {ccps/µCi/cc)
Count rate above background (cps) Maximum acceptable concentration of noble gas i (µCi/cc) Effluent monitor detection efficiency for nuclide i (ccps/µCi/cc)
Reactor Building Maximum Allowable Setpoint Bkg+C.Rj = I 6,550 I Step 4 14 Upper Level (UL) = Qooo-1 Note, there rs only one alarm on this system Step 4.16 2 Alarm UL Nominal Lower Level 1,000 I 910 191% of UL 820 82% of UL S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001
\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001.xlsx REACalculations Page 5 of 13 page D.103 2/4/2014 NE-02-09-12 003 page D.69 of 76 NE-02-09-12 Rev 2 Turbine Building Setpoint Calcu l ation T able 4.3 a N u cl id e Mii MT j rr i i 2 O.OOE+OO 1.15E+02 0.00 K r 8 5m 2.25E+OO 1.15E+02 0.02 K r 87 6.34E+OO 1.15E+02 0.05 Kr 8 8 7.61E+OO 1.15E+02 0.07 Kr89 0.00E+OO 1.15E+02 0.00 Xe131 m 0.00E+OO 1.15E+02 0.00 Xe 133 m O.OOE+OO 1.15E+02 0.00 X e 1 33 9.19E+OO 1.15E+02 0.08 X e 1 35m 2.15E+01 1.15E+02 0.19 2 2.09E+01 1.15E+02 0.18 Xe 13 7 O.OOE+OO 1.15E+02 0.00 Xe138 4.75E+01 1.15E+02 0.41 S um 1 15E+02 1.00 T able 4.4 a Ma ximum Release R at e Nuclid e rri i Ki (rrij)(Ki) Kr8 3 m 000 0.0 75 6 O.OOE+OO 2 0 02 1 1 7 0 2.28E+01 Kr8 7 005 5920 3.25E+02 Kr8 8 0.07 14 7 00 9.69E+02 Turbin e B L 0.00 16 60 0 O.OOE+OO X e 131 m 0.00 91.5 O.OOE+OO Xe133m 0.00 25 1 O.OOE+OO Xe 133 0 08 294 2.34E+01 Xe 13 5m 0.19 31 2 0 5.83E+02 Xe 1 35 0.18 1 8 10 3.28E+02 Xe 137 000 1 4 2 0 O.OOE+OO Xe 1 3 8 0 41 8830 3.64E+03 S um of rri j*Ki= 5.89E+03 Appendix D Turbine Building Monitor Setpoint Calculation Mij Measured or estimated concentration of nuclide i in release path j (µCi/cc) MTj Measured or estimated total concentration of all gases in release path j (µCi/cc) rrij Fraction of each nuclide released Whole Body Dose Rate= (Fj*500)/(X/Qi*Sum(rrij*Ki)
QTj Maximum Release Rate based on Whole Body Dose Fj Fraction of total dose allocated to this release pathway (Dimensionless) 500 Whole body dose rate limit X/Qi Maximum nonnalized diffusion coefficient for this pathway at and beyond the site boundary (sec/m3) Ki Total whole body dose factor due to gamma emission from nuclide i, as listed in the ODCM or Reg Guide 1.109, revision 1 (mremtyear per µCi/m3) rrij Is the fraction of the total activity for nuclide i (Dimensionless) m Total number of nuclides in the gaseous effluent Release pathway QTj= 2.00E+OO 5 OOE+02 = 1.50E-05 5 89E+03 I -1.13E+04 luCi/sec S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001.xlsx TEACalculations Page 6 of 13 page D.104 2/4/2014 NE-02-09-12 003 page D.70 of 76 NE-02-09-1:? Rw::: T a ble 4.5 a Ma ximu m R e l eas e R at e N uc l i d e rr i i Li+1.1 Mi 'rriil (Li+ 1.1 M i l Kr83m 0.00 0 O.OOE+OO Kr85m 0.02 2.81E+03 5.48E+01 Kr8 7 0.05 1.65E+04 9.06E+02 Kr8 8 0.07 1.9 1 E+04 1.26E+03 Kr89 0.00 2.9 1E+0 4 O.OOE+OO Xe 131 m 0.00 6.48E+02 O.OOE+OO X e 1 33m 0.00 1.3 5 E+03 O.OOE+OO X e13 3 0.08 6.94E+02 5.53 E+01 Xe 1 35m 0.19 4.41 E+0 3 8 24E+02 X e 1 35 0.18 2.30E+03 4 17E+02 Xe 13 7 0.00 1.39E+04 O.OOE+OO Xe138 0.41 1.43E+04 5.89E+03 S um(rri' 1(li+1.1 M i)= 9 41 E+03 T abl e 4.8a M aximu m N uc l ide C o n ce n t ra t io n N u c li de rr i i CT i Ci i Kr83m 0 00 6.32E-05 O.OOE+OO Kr8 5 m 0.02 6.32E-05 1.23E-0 6 Kr8 7 0.05 6.32E-05 3.47E-06 Kr8 8 0.07 6.32E-05 4.17E-06 Kr8 9 0.00 6.32E-05 O.OOE+OO Xe 13 1 m 0.00 6.32E-05 0.00E+OO Xe133m 000 6.32E-05 O.OOE+OO Xe 1 3 3 0.08 6.32E-05 5.04E-06 Xe 1 3 5m 019 6.32E-05 1.18E-05 Xe135 0.18 6.32E-05 1 15E-05 Xe 1 37 000 6.32E-05 O.OOE+OO Xe138 0.41 6 32E-05 2.61E-05 Appendix D T urbine B uildin g M onitor S etpomt C alculatio n : S ki n D o s e R a te = (Fj*3 00 0)/(X/Ql*S um(mj*Ki) 3000 D os e R a te Li mi t Q T J= 2.00E+OO 3.00E+03 = I 4 25E+04 lu C 1/s ec 1.50E-05 9.41E+03 R e lease r at e for l owes t d o se ra te valu e (Whol e body o r S kin) Q T j =I 1.13E+04 luC1/s ec S te p 4.7 Maximum Allowable C oncentration (CTJ} CTJ = (Q T j/R j) Q T j=maximum acceptable releas e rate fo r all nobl e gase s (uC1/sec) Rj = R el ease R ate cc/se c) C T J = 1 .13E+04 = I 6.32E-05 I uC1/cc 1.79E+08 S \Engineering\R x F uels Eng\Fuels\EP GS AG\C R 0 0 244578\calc
\NE-0 2-0 9-1 2 001\C M R-WEA_ TEA\ G ase o usEffluentMonitor S etpointCalculationsR e v 7-NE-02-0 9-12 R 1-C MR00 0 00 11 948-001 xlsx TEACalculations Page 7 o f 13 page 0.1 05 2/4/2 01 4 NE-02-09-12 003 page D.71 of 76 NE-02-09-12 Rev 2 Appendix D Turbine Building Monitor Setpoint C alculation For the TEA Beta detector the relative efficiency is calculated in the following table. T able 4.1 0a R e l ativ e Efficienc1 R elativ e Efficiency ( 1 Nuclid e ) ElXe-133) Kr8 3 m 0.0 5 0 2.15E+07 K r8 5m 1.6 2 2 2.15E+07 K r8 7 2.2 05 2.15E+07 Kr8 8 1.5 4 4 2.15E+07 K r8 9 2.25 5 2.15E+07 X e 131 m 1.119 2.15E+07 Xe1 3 3m 1.444 2.15E+07 Xe 133 1.0 0 0 2.15E+07 Xe 1 35m 0.38 7 2.15E+07 X e1 3 5 1.949 2.15E+07 Xe137 2.315 2.15E+07 X e1 3 8 1.99 9 2.15E+07 (1) NE-02-08-09 T able 4.11a C o un t Rat e C ontribution s Nuclid e C ii E ii Kr8 3 m O.OOE+OO n/a K r8 5 m 1.23E-06 3.49E+07 Kr8 7 3.47E-06 4.74E+07 K r8 8 4.17E-06 3.32E+07 K r8 9 O.OOE+OO n/a X e 131m O.OOE+OO n/a X e 13 3 m O.OOE+OO n/a Xe 1 3 3 5.04E-06 2.15E+07 X e1 35 m 1.18E-05 8.32E+06 X e 13 5 1 15E-05 4.19E+07 X e13 7 0 OOE+OO nla Xe 13 8 2.61E-05 4.30E+07 C.Rj= Eii n/a 3.49E+07 4.74E+07 3.32E+07 n/a n/a n/a 2.15E+07 8.32E+06 4.19E+07 n/a 4.30E+07 C.Ri i 0.00E+OO 4.30E+01 1.65E+02 1.38E+02 O.OOE+OO O.OOE+OO O.OOE+OO 1.08E+02 9.82E+01 4.80E+02 O.OOE+OO 1.12E+03 2 15E+03 ErJ=Effluent monitor detection efficiency for nuclide i (cpm/µCi/cc)
CRj Cij Eij = = = C oun t rate above background (cpm) Maximum acceptable concentration of noble gas i (µCi/cc) Effluent monitor detection efficiency for nuclide i (cpm/µCi/cc) cpm 1.00E-04 11Ci/c c ' S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001
\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001.xlsx TEACalculations Page 8 of 13 page D.106 21 4/201 4 NE-02-09-12 003 page D.72 of 76 NE-02-09-12 Rev 2 Appendix D Turbine Building Monitor Setpoint Calculation Turbine Building 1.83E+04 1:1Cils Step 4.13 Maximum Allowable Setpoint=Bkg+C
.Rj= I 46+2153] = I 2199 lcpm Step 4. 14 Upper Level = 1.02E-04 1:1Ci/cc I 381 !Based on instrument range, accuracy, and the ability to accurately read instrument values, select an Upper Level that is less than or equal to 80% of the maximum allowable setpoint value determined in Step 4 .13 Activity S ignals Ch 1 & C h 3 i n 1:1 C i/cc Effluent Activity S i gnal Ch 4 1:1Ci/s High Alarm High Alarm UL 1 77E-05 UL 3.17E+03 Nominal 1.61 E-05 91% of UL Nominal 2.89E+03 91% of UL Lower Leve 1.45E-05 82% of UL Lower Level 2.60E+03 82% of UL Bkg 2.14E-06 Bkg 3.83E+02 Alert Alarm 9.97E-06 Bkg*4.66 Alert Alarm 1 78E+03 Bkg*4.66 Alert Alarm 9.98E-06 Rounded up Alert Alarm 1 79E+03 Rounded up UL 1.20E-05 120% of Nominal UL 2 15E+03 120% of Nominal Nominal 9.98E-06 Alarm N omi nal 1 79E+03 Alarm LL 7.98E-06 80% of Nominal LL 1.43E+03 80% of Nominal S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001
\CMR-WEA_ TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001
.xlsx TEACalculat i ons Page 9 of 13 page D.107 2/4/2014 NE-02-09-12 003 page D.73 of 76 NE-02-09-12 Rev 2 Appendix D Radioactive Waste Building Monitor Setpoint Calcu l ation Radwaste Building Setpoint Calculation Table 4.3a Nuclide Mij MTj 2 0.00E+OO 1.74E+OO Kr85m O.OOE+OO 1.74E+OO Kr87 O.OOE+OO 1.74E+OO Kr88 O.OOE+OO 1.74E+OO Kr89 0.00E+OO 1.74E+OO Xe131m O.OOE+OO 1.74E+OO Xe133m 0.00E+OO 1.74E+OO Xe133 3.17E-01 1.74E+OO Xe135m 0.00E+OO 1.74E+OO 2 1.43E+OO 1.74E+OO Xe137 O.OOE+OO 1.74E+OO Xe138 0.00E+OO 1 74E+OO Sum 1.74E+OO Table 4.4a Maximum Release Rate Nuclide rrii Ki Kr83m O.OOE+OO 0.0756 2 O.OOE+OO 1170 Kr87 O.OOE+OO 5920 Kr88 O.OOE+OO 14700 Kr89 O.OOE+OO 16600 Xe131m 0.00E+OO 91.5 Xe133m 0.00E+OO 251 Xe133 1.82E-01 294 Xe135m 0.00E+OO 3120 Xe135 8 18E-01 1810 Xe137 0 OOE+OO 1420 Xe138 O.OOE+OO 8830 Sum of rrij*Ki= rrij O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 1.82E-01 O.OOE+OO 8.18E-01 0 OOE+OO 0 OOE+OO (TTii)(Ki)
O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 5.35E+01 O.OOE+OO 1.48E+03 O.OOE+OO O.OOE+OO 1.53E+03 Mij Measured or estimated concentration of nuclide i in release path j (µCi/cc) MTj Measured or estimated total concentration of all gases in release path j (µCi/cc) rrij Fraction of each nuclide released ' Whole Body Dose Rate= (Fj*500)/(X/Qi*Sum(rrij*Ki)
QTj Maximum Release Rate based on Whole Body Dose Fj Fraction of total dose allocated to this release pathway (Dimensionless) 500 Whole body dose rate limit X/Qi Maximum normalized diffusion coefficient for this pathway at and beyond the site boundary (sec/m3) Ki Total whole body dose factor due to gamma emission from nuclide i as listed in the ODCM or Reg Guide 1.109, revision 1 (mrem/year per µCi/m3) rrij Is the fraction of the total acti vi ty for nuclide i (Dimensionless) m Total number of nuc li d e s in the gaseous effluent Release pathway OTJ= 2 OOE+OO 5 OOE+02 = 1 50E-05 1.53E+03 [4.34E+04-]
uCi/sec S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12 001 \CMR-WEA_
TEA\ GaseousEffluentMon itorSetpointCalcu lationsRev?-NE-02-09-12 R 1-CMROOOOO 11948-001
.xlsx WEACalculations Page 10of13 p a ge D.108 2/4/2014 NE-02-09-12 003 page D.74 of 76 NE-02-09-12 Rev 2 Table 4.5a Maximum Release Rate Nuclide TTij Li+1.1Mi rrii)(Li+
1.1 Mi) Kr83m O.OOE+OO 0 O.OOE+OO Kr85m 0.00E+OO 2.81 E+03 O.OOE+OO Kr87 O.OOE+OO 1.65E+04 O.OOE+OO Kr88 O.OOE+OO 1.91E+04 O.OOE+OO Kr89 O.OOE+OO 2.91 E+04 O.OOE+OO Xe131m 0 OOE+OO 6.48E+02 O.OOE+OO Xe133m O.OOE+OO 1.35E+03 O.OOE+OO Xe133 1.82E-01 6.94E+02 1.26E+02 Xe135m O.OOE+OO 4.41E+03 O.OOE+OO Xe135 8.18E-01 2.30E+03 1.88E+03 Xe137 O.OOE+OO 1.39E+04 O.OOE+OO Xe138 O.OOE+OO 1.43E+04 O.OOE+OO Sum(rrii)(Li+1.1 Mi)= 2.01E+03 Table 4.8a Maximum Nuclide Concentration Nuclide TT ii CTi Cii Kr83m O.OOE+OO 1.11 E-03 O.OOE+OO Appendix D Radioactive Waste Building Monitor S etpoint Calculation Skin Dose Rate = (Fj*3000)/(X/Qi*Sum(rrij*Ki) 3000 Dose Rate Limit QTj= 2.00E+OO 3.00E+03 1.50E-05 2.01 E+03 Lowest Dose Rate Value I 4.34E+04 luCi/sec Step 4.7 Maximum Allowable Value CTJ = (QTJIRJ) Rj = Release Rate = I 1.99E+05]uCi/sec Kr85m O.OOE+OO 1.11E-03 O.OOE+OO CTJ = maximum allowed concentration CTJ = I 4.34E+04 I = I 1 11 E-03 I Kr87 O.OOE+OO 1.11 E-03 O.OOE+OO 3.91E+07 Kr88 O.OOE+OO 1.11 E-03 O.OOE+OO Kr89 0.00E+OO 1.11 E-03 O.OOE+OO Xe131m O.OOE+OO 1.11 E-03 O.OOE+OO Xe133m 0.00E+OO 1.11 E-03 O.OOE+OO Xe133 1.82E-01 1 11 E-03 2 02E-04 Xe135m O.OOE+OO 1 11 E-03 0 OOE+OO Xe135 8.18E-01 1 11 E-03 9 09E-04 Xe137 O.OOE+OO 1.11 E-03 O.OOE+OO Xe138 0 OOE+OO 1.11 E-03 O.OOE+OO S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001
\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev?-NE-02-09-12 R1-CMR0000011948-001 xlsx page D 109 WEACalculations Page 11 of 13 2/4/201 4 NE-02-09-12 003 page D.75 of 76 NE-02-09-12 Rev 2 Appendix D Radioactive Waste Building Monitor Setpoint Calculation For Beta detectors (WEA) the relative efficiency is calculated in the following table. Table 4 10a Relative Efficiencv Relative Nuclide Efficiency( 1 l E(Xe-133)
Kr83rn 0.050 1.81E+07 Kr85rn 1.626 1.81E+07 Kr87 2.208 1.81E+07 Kr88 1.549 1.81E+07 Kr89 2.259 1.81E+07 Xe131 rn 1.122 1.81E+07 Xe133rn 1.449 1.81E+07 Xe133 1.000 1.81E+07 Xe135rn 0.387 1.81E+07 Xe135 1.953 1.81E+07 Xe137 2.318 1.81E+07 Xe138 2.005 1.81E+07 (1) NE-02-08-08 Table 4.11a Counts above Background Nuclide Cii Eii Kr83rn O.OOE+OO nta Kr85rn O.OOE+OO nta Kr87 O.OOE+OO nla Kr88 O.OOE+OO nla Kr89 O.OOE+OO n/a Xe131 rn O.OOE+OO n/a Xe133rn O.OOE+OO nla Xe133 2.02E-04 1.81E+07 Xe135rn O.OOE+OO nla Xe135 9.09E-04 3 54E+07 Xe137 O.OOE+OO n/a Xe138 O.OOE+OO nla CRj= E11 nla nla nta nta nla nla nla 1.81E+07 nta 3.54E+07 nla nla C.R11 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 3.66E+03 O.OOE+OO 3.21E+04 0 OOE+OO 0 OOE+OO 3 58E+04 I I I GRj Cij EiJ = = = C oun t rate above background (cpm) Maximum acceptable concentration o f noble gas i (µCi/cc) . Effluent monitor detection efficiency for nuclide i (cpm/µCi/cc) cprn 1.98E-03 .. Ci/cc S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE-02-09-12.001
\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE-02-09-12 R1-CMR0000011948-001.xlsx WEACalculations Page 12 of 13 page 0.110 2/412014 NE-02-09-12 003 page D.76 of 76 NE-02-09-12 Rev 2 Appendix 0 Radioactive Waste Building Monitor Setpoint Calculation Radwaste Building 7.7 4E+04 !'Cits Step 4.13 Maximum Allowable Setpoint = I 46+35804 I= I 35850 lcpm 1 .98E-03 .,cuc c Step 4.14 Upper Level= I 2901 !Based o n instrument range, accuracy.
and the ability to accurately read instrument values, select an Upper Level that is less than or equal to 80% of the maximum allowable setpoint value determined in Step 4.13. Activity Signals Ch 1 & Ch 3 in l'Ci/cc Effluent Activity Signal Ch 4 l'Ci/s High Alarm High Alarm UL 1.60E-04 80% of Max UL 6.27E+03 Nominal 1.46E-04 91% of UL Nominal 5.70E+03 91% of UL Lower Level 1.31 E-04 82% of UL Lower Level 5.14E+03 82% of UL Bkg 2.54E-06 Bkg 9.94E+01 Alert Alarm 1.18E-05 Bkg*4.66 High Alarm 4.63E+02 Bkg*4.66 Alert Alarm 1.19E-05 Rounded up High Alarm 4.64E+02 Rounded up UL 1.43E-05 120% of Nominal UL 5.57E+02 120% of Nomina I Nominal 1.19E-05 Alarm Nominal 4.64E+02 Alarm LL 9.52E-06 80% of Nominal LL 3.71E+02 80% of Nominal S:\Engineering\Rx Fuels Eng\Fuels\EPGSAG\CR00244578\calc\NE--02--09-12.001
\CMR-WEA_
TEA\ GaseousEffluentMonitorSetpointCalculationsRev7-NE--02-09-12 R1-CMR0000011948-001.xlsx WEACalculations Page 13of13 page 0.111 2/4/2014

v t e Letter Sequence Request
CAC:MF8219, (Approved, Closed)
Initiation Request, Request Acceptance Supplement Administration Questions Answers 23 February 2017 Results Approval Other:
MONTHYEAR2017-02-23 [Table View]

ML16210A530

Text

SUMMARY

SUMMARY

5.4.1 77Energy

SUMMARY

SUMMARY

SUMMARY

SUMMARY

0.1 Background

6.0 REFERENCES

6.0 REFERENCES

6.0 REFERENCES

6.1 Offsite

Navigation menu

Search