attachment 1 consumers power company engineering … · these dampers were _also measured with the...

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ATTACHMENT 1

CONSUMERS POWER COMPANY PALISADES PLANT

DOCKET 50-255

ENGINEERING ANALYSIS - EA-TAM-95-05 REV 0 Rao1n•L.n~•cA• rnt..icEQ• 1ct..1rcc enc Tue DAI l~Anc~ I - .. - VUI ,...., .... UV111~ UL.I,.""'-"' I ""''' I .... I ,., ... ""r-'l.., .. '-"

MAXIMUM HYPOTHETICAL ACCIDENT AND LOSS OF COOLANT ACCIDENT

128 Pages

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9601290317 960124· PDR ADOCK 05000255 P PDR

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PALISADES NUCLEAR POWER PLANT ENGINEERING ANALYSIS COVER SHEET t§i

EA-TAM-95-05 ' NUCLEAR PLANT

Total Pages 128

Title: Radiological Conseguences for the Palisades Maximum HY2othetical Accident & Loss of Coolant Accident

Initiation & Review

Calculation Status Preliminary Pending Final Superseded D D !Bl D

Rev

I Description Initiated Init Review Method Technically Revr CPCo

Appel # Appd Reviewed Appd

By By

By Date Alt Detail Qual By Date Cale -- Teat

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PURPOSE

This analysis will demonstrate that the offsite dose limits of 10 CFR 100 and control room dose limits of 10 CFR 50 Appendix A will not be exceeded with the current plant configuration. Calculations are performed using a fission product source term based on Regulatory Guide 1.4 [Ref: 2.13]. In addition, since the analysis methodology is identical, calculations are also performed using the plant specific 10CFR50 Appendix K analysis which demonstrates no fuel failure will occur following a LBLOCA.

SUMMARY OF RESULTS

The following table summarizes the radiological dose consequences of an MHA and LOCA at Palisades:

Event

Limits

MHA

LB LO CA

Site Boundary (SB)

Thyroid WB [rem] [rem]

300 25

15.08 0.29

7.48 0.06

Low Population Zone Control Room (LPZ)

Thyroid WB Thyroid WB [rem] [rem] [rem] [rem]

300 25 30 5

8.68 0.05 23.31 2.70

4.33 0.01 11.29 2.66

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PALISADES NUCLEAR POWER PLANT ANALYSIS CONTINUATION SHEET

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TABLE OF CONTENTS

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1.0 Background .............................. · .................................................................................... 3

2.0 References .................................................................................................................... 5

3.0 Analysis Inputs ......................................................... ·.................................................... 9

4.0 Assumptions ................................................................................................................ 15

5.0 Method of Analysis ...................................................................................................... 20

6.0 Analysis Using Regulatory Guide 1.4 Source Terms .................................................... 20

6.1 Offsite Doses Using Regulatory Guide 1.4 Source Terms ................................ 20

6.2 Control Room Unfiltered Air Inleakage ............................................................. 26

6.3 Control Room Doses Using Regulatory Guide 1.4 Source Terms ..................... 27

7.0 Analysis Using 10 CFR 50 Append.ix K Analysis Source Terms ................................... 33

7 .1 Offsite Doses Using Append.ix K Source Terms ................................................ 33

7 .2 Control Room Doses Using Append.ix K Source Terms .................................... 35

8.0 Summary and Conclusio.ns .......................................................................................... 36

9.0 List of Attachments ...................................................................................................... 36

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1.0 Background


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The concerns related to the Maximum Hypothetical Accident (MHA) originated in event report E-PAL-90-035 [Ref. 2.1]. This event report was generated after failing a test developed to determine the leak rate of the discharge isolation valves for the Safety Injection & Refueling Water Tank (SIRWT), CV-3031 & CV-3057. The basis for the test was the possibility ofpostLOCA containment pressure forcing sump water back to the SIRWT, which is vented to the atmosphere. The evaluation of this event report determined that the static head from the elevation of the SIRWT was greater than the peak post-recirculation containment pressure following a LOCA and that the leakage back to the SIRWT was not possible. The test had been performed with an acceptance criteria of 0.2 gpm, which is based on Technical Specification 4.5.3 [Ref. 2.2]. However, the evaluation identified that this Technical Specification was not applicable to t.11.is leak path since the specification is based on leakage from pump seals, valve stems, etc. as analyzed in previous MHA analyses of record. It was also identified that the testing performed was not valid for leakage back to the SIRWT since leak rates were measured for flow from the SIRWT as opposed to back flow to the SIRWT. (Back:flow would have to pass through the discharge check valves.) The root cause evaluation for the event report raised the concern of other possible leak paths. Further analysis concluded the existence of two potential paths for leakage to the SIRWT that are exposed to ESS pump discharge pressure. These potential leak paths were through the minimum recirculation flow path from the ESS pumps and through a shutdown cooling cross connect line. The minimum flow path for the ESS pumps is isolated by two control valves in series, CV-3027 & CV-3056, which close upon a recirculation actuation signal (RAS). The shutdown cooling cross connect line is isolated during normal operation by a locked closed manual isolation valve, MV-3225. The discovery of these leak paths resulted in NRC issuance of Information Notice 91-56 [Ref. 2.3].

Initially, qualitative arguments for justifying continued operation were submitted to the NRC in relation to the sump water leakage concern [Ref. 2.4]. Due to the small apparent margin in the MHA analysis, with respect to control room operator doses, work was begun evaluating the entire MHA analysis to identify conservatisms that could be removed. During this evaluation, deficiencies in post-LOCA containment sump pH control were discovered. In a parallel effort for revising the control room habitability calculations, inconsistencies were discovered in the previous control room habitability analyses of record. The NRC was informed of the additional issues that had been discovered and provided with a plan for a complete reanalysis effort and completion of required plant modifications to resolve the issues [Ref. 2.5]. This letter to the NRC again provided qualitative arguments for justifying continued operation in relation to all of the MHA concerns that had been discovered.

During the 1992 refueling outage, a modification was performed to add a spectacle flange, SF-0401, and an additional manual valve, MV-ES108, to the shutdown cooling cross connect line. The flange is blanked off during power operation to eliminate this leakage path to the SIRWT in the event of an accident. The control valves CV-3027 & CV-3056, in the ESS pump minimum flow recirculation path were also leak tested during the 1992 refueling outage [Ref. 2.6]. The test results for these valves showed approximately 0.0 and 0.01 gpm for each of the valves. These results were well below the established administrative limit of 0.1 gpm back to the SIRWT. Also during this time frame, engineering analyses documenting new computer codes written to perform the MHA analysis and control room habitability analyses were

• completed [Refs. 2.7 & 2.8].

Using the computer codes documented in References 2.7 & 2.8, an analysis was completed to update the justification for continued operation with quantitative information on predicted offsite and control room doses Ref. 2.9 . This JCO analysis used a fission product source


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term based on the plant specific 10 CFR 50 Appendix K analysis [Ref. 2.10], which justifies that no fuel melting would occur during a large break LOCA. The JCO analysis also demonstrated that up to 20 gpm of leakage back to the SIRWT could be tolerated with the source term assumed. Documentation of the magnitude of allowable leakage was provided due to the discovery of additional potential leak paths for sump water to the SIRWT. (These leak paths could occur through the SIRWT main discharge.line if one ESS train is inoperable and the operating spray pumps force sump water through the discharge check valve on the idle spray pump or through the HPSI suction check valves during HPSI subcooling [Ref. 2.11].) The results of the JCO analysis were then submitted to the NRC as an update to the justification for continued operation [Ref. 2.12]. Following receipt of this letter, the NRC requested additional information regarding the JCO analysis that was performed and requested that the offsite and control room doses for the fission product source term described in Regulatory Guide 1.4 [Ref. 2.13] be provided. This information was provided to the NRC in Reference 2.14.

During a forced outage in 1994, the MHA issues were brought into question following an event report [Ref. 2.15] when it was found that the discharge isolation valves from the SIRWT leak water out of the SIRWT excessively. If the approximate 20,000 gallons of water left in the SIRWT following recirculation leaks out to the operating train of safety injection, the results of the JCO analysis [Ref. 2.9] could change due to the dilution credited for water in the SIRWT. The excessive leakage out of the SIRWT heightened the concern over leakage into the SIRWT. Therefore, testing was completed to quantify the potential leakage rates for leakage back to the SIRWT through the main discharge lines [Ref. 2.16]. This testing demonstrated that a maximum leakage of less than 1.0 gpm through either of the two main discharge lines was possible. Completion of this testing produced the "as-found" results for all of the postulated sump water leak paths back to the SIRWT. Due to the additional information gained on potential leakage paths for sump water back to the SIRWT and the possibility of draining the water left in the SIRWT following recirculation, a new JCO analysis was warranted prior to the NRC responding to our justification continued operation in relation to the MHA issues. To remain consistent with the previous JCO submittal [Ref. 2.14], the analysis (EA-PAH-94-05 [Ref. 2.68]) calculated the offsite and control room doses using the fission product source term based on both Regulatory Guide 1.4 and the 10 CFR 50 Appendix K analysis. Sargent & Lundy provided a 3rd Party Review of this analysis [Ref. 2.67] and repeated the results without significant differences using an alternate calculation.

However, EA-PAH-94-05 was never sent to the NRC since a Safety Evaluation Report (SER) by the NRC, dated January 9, 1995 [Ref. 2.69], justified continued operation at Palisades based on the arguments in EA-A-NL-92-012-02 Rev. 1 [Ref. 2.9]. The SER concluded that this JCO analysis was sound and that Palisades be allowed continued operation until completion and submittal of the final MHA analysis during Cycle 12, but no later than January 1996.

Since receipt of the SER, Palisades underwent a refueling outage prior to cycle 12. During this outage TSP baskets were installed in containment to provide passive pH control (7 < pH < 8) prior to RAS. This ensures that iodine will'not re-evolve from the containment sump. In addition, the Control Room smoke purge and normal isolation dampers were visually inspected to determine the amount (if any existed) of gap width present. The Ap's across these dampers were _also measured with the CRHVAC in the Emergency Mode [Ref. 2.3]. Using this data, and a calculation done by Sargent & Lundy to determine the damper leak rate per gap length at various operating pressures (see EA-DBD-1.06-02 Rev. 0 [Ref. 2.70]), a bounding amount of unfiltered inleakage into the control room was determined in Reference 2.75 to be 67.06 cfm. This is much greater than the SRP 6.4 and RG. 1.95 limit of 0.06

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volume changes per hour (- 36 cfm.) for which periodic testing would be required. However, as stated in Reference 2.74, we will test these dampers once per 5 years to show that the bounding value of unfiltered inleakage is still valid.

Finally, the tests to determine the amount of unfiltered inleakage into the SIRWT (R0-119 and RT-71L) were performed using revised procedures [Refs. 2.70 and 2.71 respectively] to account for instrument uncertainties and co:rnbine the results of the two tests for an acceptance determination. The results of the 1995 R0-119 test are 0 gpm and for RT-71L are 1.15 gpm with 0.116 gpm measurement uncertainty for a total of 1.266 gpm. This is less than the maxim.um permissible combined leak rate of the two tests= 2.116 gpm (see Ref 2.71 and Ref. 2.72) based on the following analysis which uses 2.2 gpm.

It is apparent that several modifications to the plant have resulted since the discovery of the previously discussed MHA issues. These modifications were implemented in order to prove that Palisades can protect the safety of the public from an event as unlikely as the MHA. The following analysis provides the details which support such a conclusion.

2.0 References

2.1 E-PAL-90-035, "RT-88A Test Failure," September 1990.

2.2 Palisades Technical Specifications.

2.3 NRC Information Notice 91-56, "Potential Radioactive Leakage to Tank Vented to Atmosphere," September 19, 1991.

2.4 Letter from GBSlade to the NRC dated June 14, 1991. Subject: "Unreviewed Safety Question - Potential for Leakage of Containment Sump Water to the SIRW Tank During anMHA."

2.5 Letter from GBSlade to the NRC dated January 10, 1992. Subject; "Unreviewed Safety Question-Potential for Leakage of Containment Sump Water to the SIRW Tank During an MHA - Rev I."

2.6 R0-119 Rev 0, Technical Specification Surveillance Procedure, "Inservice Testing of Engineered Safegiiards Valves CV-3027 and CV-3056," February 1992.

2.7 EA-PAH-91-05 Rev 0, "Benchmarking of the MHACALC Code," March 1992. Cart/Frame: F059/1453.

2.8 EA-A-NL-92-012-01 Rev 0, "Benchmarking of the CONDOSE Code for Control Room Babitability Calculations," March 1992. Cart/Frame: F059/1625.

2.9 EA-A-NL-92-012-02 Rev 1, "Offsite Doses and Control Room Habitability Following a Large Break LOCA to Justify Continued Operation Until Cycle 12," March 1992. Cart/Frame: F080/0831.

2.10 EMF-91-177, "Palisades Large Break LOCA/ECCS Analysis with Increased Radial Peaking and Reduced ECCS Flow," Siemens Nuclear Power Corporation, October 1991.

EMF-91-177, "Palisades Large Break LOCA ECCS Analysis with Increased Radial

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Peaking and Reduced ECCS Flow Supplement 1 -Alternate Enrichment Scheme," Siemens Nuclear Power Corporation, June 1994.

2.11 Internal Correspondence from PAHarden to GESchrader, dated July 13, 1992. Subject: "Clarification of Leak Path to the SIRW Tank Described in A-PAL-92-029," PAH92-008.

2.12 Letter from GBSlade to the NRC dated April 21, 1992. Subject: "Unreviewed Safety Question - Potential for Leakage of Containment Sump Water to the SIRW Tank During an MHA- Additional Information and Update of Justification for Continued Operation.

2.13 Regulatory Guide 1.4 Rev 2, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors," June 1974.

2.14 Letter from GBSlade to the NRC dated July 28, 1992. Subject: "Unreviewed Safety Question - Potential for Leakage of Containment Sump Water to the SIRW Tank During an MHA- Regulatory Guide 1.4 Source Terms Used as Interim Calculation Inputs."

2.15 E-PAL-94-011, "SIRW Tank Outlet Valves Leakage," March 1994.

2.16 RT-71L Rev 1, Technical Specification Surveillance Procedure, ''Technical Specification 4.5.3 Pressure Test ofESS Pump Suction Piping," March 1994.

2.17 Palisades Plant Final Safety Analysis Report.

2.18 EA-GCP-91-04 Rev. 1, "Maxim.um and Minimum Containment Sump Volume and Boron Concentration Following a Large Break LOCA," August 1994.

2.19 Letter from A. Schwencer (NRC) to D. Bixel (CPCo) dated November 1, 1977. Subject: Transmittal of Amendment No. 31 with Safety Evaluation. Cart/Frame: 2511/1751.

2.20 Drawing C-38 Rev 5, "Field Erected Tanks Sheet 2," January 1989.

2.21 Vendor File C-18 Sheet 51 Rev 3, "Nozzle Details With 125# Slip on Flange Flat Face."

2.22 EA-PAH-91-06 Rev 0, "Iodine Removal Coefficients for Containment Sprays Based on Standard Review Plan 6.5.2, Revision 2,"' December 1991. Cart/Frame: F005/2454.

2.23 NUREG/CR-4679 ORNL/NUREG-1135, "Chemistry and Transport of Iodine in Containment," Oak Ridge National Laboratory, October 1986.

2.24 NUREG-0800, USNRC Standard Review Plan, Section 6.5.2 Rev 2, "Containment Spray as a Fission Product Cleanup System," December 1988.

2.25 EA-A-NL-92-012-03 Rev 0, "O:ffsite Doses and Control Room Habitability From the MHA Accounting For Plant Modifications to Occur By Cycle 12," April 1992; Cart/Frame: F096/0244.

2.26 NED0-24782, "BWR Owner's Group NUREG-0578 Implementation: Analysis and Positions for Plant Unique Submittals," General Electric, August 1980.

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2.27 NUREG/CR-1413 ORNL/NUREG-70, "A Radionuclide Decay Data Base - Index and Summary Table," Oak Ridge National Laboratory, May 1980.

2.28 ICRP Publication 30, "L~ts for Intakes of Radionuclides by Workers," July 1978.

2.29 DBD-1.06 Rev 2, Palisades Design Basis Document, "Control Room HVAC System," December 1994.

2.30 NUREG-0800, USNRC Standard Review Plan 6.4 Rev 2, "Control Room Habitability System," July 1981.

2.31 EA-PAH-94-04 Rev 0, "Documentation of Appropriate Atmospheric Dispersion Factors for Control Room Habitability Assessments Based on Wind Tunnei Tests."

2.32 "Consumers Power, Company Palisades Plant NUREG-0578 Design Review Study of Plant Shielding for Post-Accident Operations," Commonwealth Associates Inc. January 15, 1982. Cart/Frame: 2687/1277.

2.33 Commonwealth Associates Calculation 0350-1-270-63-23-1-04 Rev 0, "Control Room Doses," December 1980. Cart/Frame: 2687/1819.

2.34 Drawing C-539 Rev 0, "Cellular Slab Repair Plan of Control Room Roof El 643'-0"," February 1986.

2.35 NUREG-0800, USNRC Standard Review Plan Section 15.6.5, Appendix A Rev 1, "Radiological Consequences of a Design Basis Loss-of-Coolant Accident Including Containment Leakage Contribution," July 1981 and Appendix B Rev 1, "Radiological Consequences of a Design Basis Loss-of-Coolant Accident: Leakage From Engineered Safety Feature Components Outside Containment," July i981.

2.36 Letter from E. C. Beahm (Martin Marietta Energy Systems Inc. at ORNL) to Jay Y. Lee (NRC) dated February 5, 1992. Subject: ''Technique for Calculating Iodine Partitioning in a Safety Injection Refueling Water Tank."

2.37 Pal. Spray Notebook, November 1989.

2.38 EA-D-PAL-93-272E-03 Rev 0, "LOCA Containment Response Analysis With Degraded Heat Removal Systems Using the CONTEMPT EI-28A Computer Code," May 1994.

' 2.39 Internal Correspondence WLR*004 from WLRoberts to PMDonnelly dated February 5, 1992. Subject: "Palisades Plant - Continuation of Conversations with the NRC on CRHAB and MHA Issues."

2.40 "MICROSHIELD Version 3 User's Manual," Grove Engineering, Inc. October 1987.

2.41 ASME Steam.Tables, Fourth Edition, 1979 .

2.42 NUREG/CR-5732 ORNL/TM-11861, "Iodine Chemical Forms in LWR Severe Accidents," Oak Ridge National Laboratory, April 1992.

2.43 ''The Engineers' Manual," Second Edition, Ralph G. Hudson, John Wiley & Sons, Inc.

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2.44 R0-28 Rev 14, Technical Specification Surveillance Procedure, "Control Room/TSC Ventilation," April, 1995.

2.45 Drawing C-78 Rev 5, "Control Room Details," December 1990.

2.46 1989 ASHRAE Handbook, "Fundamentals", I-P Edition.

2.47 Vendor File M-140 Sheet 40 Rev 0.

2.48 Vendor File M-140 Sheet 27 Rev 0.

2.49 Instrument Calibration Sheet for FT-1711 Rev 1.

2.50 Instrument Calibration Sheet for FT-1 712 Rev 2.

2.51 Instrument Calibration Sheet for FI C-1 711 Rev 1.

2.52 Instrument Calibration Sheet for FIC-1712 Rev 1.

2.53 Instrument Calibration Sheet for Fl-174 7 Rev 2.

2.54 Instrument Calibration Sheet for FI-17 48 Rev 3.



2.57 Work Order# 24100371completed6/19/93. Cart/Frame: F463/1120.

2.58 Work Order# 24202640 completed 12/9/92. Cart/Frame: F292/0057.

2.59 Work Order# 24100393 completed 9/23/91. Cart/Frame: C759/1720.

2.60 Work Order# 24100394 completed 9/23/91. Cart/Frame: C759/1749.

2.61 Instrument Calibration Sheet for M&TE Manometer 8428-00936 Rev 1.

2.62 Work Order# 2410292.completed 2/5/92. Cart/Frame: F098/0959.

2.63 EA-DBD-1.06-01 Rev 0, "Control Room HVAC Isolation Damper Leakage During Emergency Mode," August 1990. Cart/Frame: D267 /0513.

2.64 Vendor File M-244(Q) Sheet 30 Rev C, "Zero-Leak Louver."

2.65 FDM-911(Q) Rev 10, "Heating, Ventilation & Air Conditioning Control Room Analysis Palisades Plant.''

2.66 Deleted

2.67 SLP-94-355, Letter from Sargent & Lundy to TCDuffy dated November 30, 1994. Subject: "3rd Party Review of the Control Room Maximum Hypothetical Analysis MHA,"

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2.68 EA-PAH-94-05 Rev. 0, "Updated Justification for Continued Operation for the MHA and Related Issues," October 1994; Cart/Frame G113/ 1002

2.69 Letter from Marsha Gamberoni (NRC) to KMHaas (CPCo) dated January 9, 1995, Subject: "Palisades Plant - Justification for Continued Operation - Potential Radioactive Release Path (TAC No. M80402)," with Safety Evaluation.

2.70 EA-DBD-1.06-02 Rev. 0, "Control Room HVAC Outside Air Damper Leakage Calculation For Various Blade Gap Width and Operating Differential Pressure," July 1995.

2.71 R0-119 Rev 3, Technical Specification Surveillance Procedure, "Inservice Testing of Engineered Safeguards Valves CV-3027 and CV-3056," May 1995.

2.72 RT-71L Rev 1, Technical Specification Surveillance Procedure, "Technical Specification 4.5.3 Pressure Test ofESS Pump Suction Piping," May 1995.

2.73 PS&L Log No. 95-0379; Safety Evaluation: FSAR Table 14.22-2 Rev 17, "Engineered Safeguards Room (ESF) Iodine Reduction Factor (IRF) Basis Correction," April 1995; Cart/Frame G325/0875. · ·

2.74 Memorandum from LTPhillips to TAMeyers, Subject: Control Room HVAC Damper Testing Results - 1995 Refout Revision 2, October 1995.

2.75 EA-TAM-95-06 Rev. 0 "Control Room Unfiltered Inleakage Calculation for the Palisades MHA arid LOCA," October 1995.

2.76 EOP 4.0 Rev. 8, Emergency Operating Procedure; "Loss of Coolant Accident Recovery," August 1995.

2.77 EA-PAH-90-02 Rev. 0 "Cycle 9 Offsite Dose Calculation for the Control Rod Ejection Incident," December 1990.

3.0 Analysis Inputs

. 3.1 The breathing rates used for offsite and control room doses are 3.47x10-4 ma/sec from 0 to 8 hours, l.75xl0-4 ma/sec from 8 to 24 hours, and 2.32xl0-4 ma/sec from 1 to 30 days in accordance with Reference 2.13 and consistent with Reference 2.9.

3 .2 The basis for no fuel melt occurring from a large break LOCA is the cladding not exceeding 2200°F as required by 10 CFR 50.46 (b.) [Ref. 2.10] which is referenced by 10 CFR 50 Appendix K.

3.3 The rated core thermal power, 2530 MWt11, the containment design leak rate, 0.1 %/day, and the containment net free air volume, l.64xl06 ft3 , are from the plant FSAR [Ref. 2.17, sections 1.1, 1.2, & 5.8]. The atmospheric dispersion.factors for 0 to 2 hours at the site boundary is l.55xl0-4 sec/ms and those at the low population zone are l.09x10-5 sec/ms from 0 to 8 hours, 6.94x10-6 sec/ms from 8 to 24 hours, 2.58x10·6

sec/ms from 1 to 4 days, and 6.25xl0-7 sec/ms from 4 to 30 days, also from Reference 2.17 [Tables 2-17 & 2-18].

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3.4 The minim.um sump volume after recirculation is based on the sump mass 2439636 lbm at 39.0 psia and 250.3°F from Reference 2.18, for determination of the concentration of fission products in the recirculation water. Using a specific volume of 0.01701 ft3/lbm from Reference 2.41 yields a corresponding volume of 41498.2 ft3.

3.5 The limit for out of containment ESF leakage into the safeguards rooms following recirculation is 0.2 gpm from the plant Technical Specifications [Ref. 2.2, TS 4.5.3].

3.6 An I.odine Reduction Factor of 2, due to hi-radiation trip of ESF cubicles ventilation system is used for ESF leakage assuming significant leakage occurs through the ESR isolation dampers. See References 2.19 and 2.73.

3. 7 The total SIRWT volume is calculated from :limensions given and measured from Reference 2.20.

3.8 The safeguards suction line flanges extend 4 1/16" off the SIRWT bottom as shown on Ref. 2.21.

3.9 The first-order spray removal coefficients for particulate iodine in containment are 4.43 hrl initially, changing to 0.443 hrl after 98% of the particulate iodine has been removed [Ref. 2.22]. The spray removal coefficient for elemental iodine in containment is 21.3 hrl and that for organic iodine is 0.0, also from Reference 2.22.

3 .10 The long term iodine partition coefficient in containment is conservatively estimated as 1250 from Reference 2.23 [Figure 6] corresponding to a mixing time of - 28 hours. This figure is recommended in SRP 6.5.2 [Ref. 2.24 pg. 6.5.2-11] for determining the long term iodine partition coefficient between the sump and containment atmosphere. This partition coefficient is based on a pH of 7, a sump temperature of 132 °F, and 50% of the total core iodine inventory being deposited in the containment sump as will be discussed later in the analysis. A low sump temperature of 132 °F is conservatively used since the iodine partition coefficient decreases with decreasing temperature hence increasing the amount of iodine available for release from the containment atmosphere. The sump will not reach this temperature until several days after the · accident but is conservatively applied to the sprays at the spray start time. This value is also consistent with that used in References 2.9 and 2.25 and has been previously

. accepted by the NRC.

3.11 The activity source term values (Si) listed in Table 1 for each of the radionuclides of interest are from Reference 2.26 [App. B, pg. B-27]. (Values in Ref. 2.26 for iodine are listed as 50% of the total inventory as noted on page B-2.)

3.12 The radioactive decay constants (A.i) listed in Table 1 are calculated from the half-life (T112) values listed in Reference 2.27 using the equation/..,= ln(2)/(T112). These values are consistent with that used in References 2.9 and 2.25.

3.13 The thyroid and whole body dose rate conversion factors for noble gas isotopes are listed in Table 1 for a semi-infinite cloud and in Table 2 corrected for a 1000 m3 room . They were taken from Reference 2.28 and converted to units of (Rem/sec)/(Ci/m3). The thyroid and whole body inhalation dose conversion factors for iodine isotopes are listed in Table 2. They also came from Reference 2.28, and are converted to units of Rem/Ci-inhaled. The use of the noble gas dose rate conversion factors corrected for a

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1000 m3 room 'is justified by the calculated control room air volume. It should be noted that the whole body. dose cqid dose rate conversion factors for each iodine and noble gas radionuclide, respectively, are the sum of the weighted dose or dose rate factors for all organs and tissues listed for the radionuclide. These values are also consistent with that used in Reference 2.9 and 2.25.

TABLE 1

Isotope Dependent Parameters

Dose Rate Conversion Factors Si Ai (semi-infinite cloud)

Nuclide (Ci/MWt) (min-1) (Rem/sec)/(Ci/m3)

Thyroid Whole Body

Kr-83m 2.998E+03 6.313E-03 O.OOOE-00 3.649E-06

Kr-85m 6.498E+03 2.579E-03 3.083E-02 3.031E-02

Kr-85 2.999E+02 1.230E-07 O.OOOE-00 4.738E-04

Kr-87 1.155E+04 9.084E-03 l.439E-01 1.447E-01

Kr,-88 l.690E+04 4.068E-03 3.803E-01 3.690E-01

Kr-89 1.993E+04 2.194E-01 O.OOOE-00 O.OOOE-00

Xel3lm 1.760E+02 4.065E-05 O.OOOE-00 1.324E-03

Xel33m 1.954E+03 2.198E-04 O.OOOE-00 5.375E-03

Xe-133 5.648E+04 9.177E-05 7.297E-03 6.259E-03

Xel35m l.698E+04 4.513E-02 O.OOOE-00 7.647E-02·

Xe-135 9.781E+03 l.268E-03 O.OOOE-00 4.676E-02

Xe-137 4.705E+04 1.810E-Ol O.OOOE-00 O.OOOE-00

Xe-138 4.433E+04 4.906E-02 1.953E-Ol l.969E-01

1-131 2.938E+04 5.987E-05 N/A N/A

1-132 4.160E+04 5.023E-03 N/A N/A

1-133 4.808E+04 5.554E-04 N/A N/A

1-134 6.218E+04 1.318E-02 N/A N/A

1-135 4.922E+04 l.748E-03 N/A N/A

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TABLE 2

Iodine Dose Conversion Factors & Room-Corrected Noble Gas Dose Rate Conversion Factors

Dose Rate Conversion Factors Corrected for a 1000 m• room (Rem/sec)/(Ci/m3) Nuclide

Thyroid Lungs B Surface B Marrow Skin Eye Lens

Kr-83m O.OOOE-00 O.OOOE-00 6.475E-06 5.653E-6 l.747E-04 l.747E-04

Kr-85m l.233E-03 l.131E-03 l.953E-03 l.850E-03 5.139E-02 !.542E-03

Kr-85 O.OOOE-00 2.056E-05 3.083E-05 2.878E-05 4.728E-02 3.906E-05

Kr-87 5.550E-03 5.756E-03 6.886E-03 6.269E-03 3.392£-01 l.007E-01

Kr-88 1.439E-02 l.336E-02 I.542E-02 !.336E-02 9.456E-02 2.878E-02

Kr-89 O.OOOE-00 O.OOOE-00 O.OOOE-00 O.OOOE-00 O.OOOE-00 O.COOE-00

Xe-13lm O.OOOE-00 I.233E-04 3.597E-04 3.289E-04 l.542E-02 5.344E-04

Xe-133m O.OOOE-00 2.775E-04 6.167E-04 5.653E-04 3.083E-02 7.503E-04

Xe-133 4.317E-04 2.672E-04 6.886E-04 6.269E-04 l.131E-02 6.989E-04

Xe-135m O.OOOE-00 3.392E-03 4.522E-03 4.214E-03 2.672E-02 4.522E-03

Xe-135 O.OOOE-00 !.850E-03 2.981E-03 2.775E-03 6.578E-02 2.467E-03

Xe-137 O.OOOE-00 O.OOOE-00 O.OOOE-00 0.000E-00 O.OOOE-00 O.OOOE-00

Xe-138 7.811E-03 8.119E-03 9.558E-03 8.736E-03 l.644E-Ol 3.186E-02

Inhalation Dose Conversion Factors (Rem/Ci-inhaled)

1-131 !.073E+06 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

1-132 6.290E+03 9.990E+02 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

1-133 l.813E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO

1-134 !.073E+03 5.180E+02 0.00.0E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

1-135 3.145E+04 l.628E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO

~ NUCLEAR PLANT

Whole Body

3.649E-06

l.269E-03

2.314E-5

5.684E-03

I.402E-02

O.OOOE-00

!.915E-04

3.823E-04

3.361E-04

3.618E-03

2.086E-03

O.OOOE-00

7.801E-03

3.256E+04

3.367E+02

5.550E+03

l.106E+02

I.121E+03

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3.14 The free air volume of the control room is approximately 35923 ft3 (1017 m3) as calculated in Reference 2.9 [pg. 25] and 2.25 [pg. 22]. This volume conservatively ignores the volume of the air space in the drop ceiling for the control room area and the volume of the mechanical equipment room (MER) which is also maintained at a positive pressure by the control room HVAC system. A lower volume is conservative since it increases the concentrations of radionuclides in the control room following an accident.

3.15 The total delay time for pressurizing the control room to greater than 0.125" water gauge is 1.26 minutes from Reference 2.29 [pg. 22], which includes a 0.5 second time delay before generation of a containment high pressure (CHP) signal, accompanied by a time delay of 67.4 seconds for diesel generator sequencing and starting the control room air handling units V-95 and V-96, followed by 7.5 seconds for control room pressurization.

3.16 The acceptance criteria for total filtered air flow rate (V-26A & V-26B flow rates) in the control room HVAC system when in emergency mode is 3040 - 3520 cfm. (3200 nominal -5 to + 10 % tolerance) [Ref. 2.44].

3.17 The efficiency of the control room HVAC HEPA/charcoal filters (VF-26A & B) for the emergency intake fresh air make-up and filtered recirculation air is greater than 99% for iodine [Ref. 2.2, Table 4.2.3].

3.18 The control room occupancy factors to account for different control room stay times as the accident progresses are 1.0 from 0 to 24 hours, 0.6 from 24 to 96 hours, and 0.4 from 96 to 720 hours in accordance with SRP 6.4 [Ref. 2.30, Table 6.4-1].

3 .19 The atmospheric dispersion factors for the control room normal and emergency air intakes from Reference 2.31 are listed in Table 3 below. These values are based on measured maximums from wind tunnel tests. The values given in Table 3 for containment releases are applicable for releases from containment and from the auxiliary building_ as described in Reference 2.31.

TABLE3

Atmospheric Dispersion Factors for Control Room Air Intakes

Time Interval

0 - 8 Hrs

8 - 24 Hrs

1 - 4 Days

4 - 30 Days

Containment Releases

Norm. Intake Emer. Intake

7.72xlQ-4 s/m3 2.56x1Q-4 s/m3

4.SSxlQ-4 s/m3 l.5 lxl0-4 s/m3

2.90x10-A s/m3 9.60x1Q-5 s/m3

l.27xl0-4 s/m3 4.22x1Q-5 s/m3

SIRWT Releases

Norm. Intake Emer. Intake

l.32xlQ-2 s/m3 6.35xlQ-4 s/m3

7.78x1Q-3 s/m3 3.74x1Q-4 s/m3

4.95x10-3 s/m3 2.38x10-4 s/m3

2.18x10-3 s/m3 l.OSxlQ-4 s/m3

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3.20 The whole body dose from containment shine at the highest dose point in the control room is obtained from References 2.32 & 2.33. The highest dose point is at the access doors to the control room viewing gallery, which receive a dose of 400 mrem (0.4 rem) over 30 days [Ref. 2.32, pg. 20]. Using this value is conservative since the highest dose point that is actually in the control room is in the southwest corner of the room which receives 13.3 mrem over 30 days [Ref. 2.33, pp. 5-6]. This shine dose is based on the Regulatory Guide 1.4 fission product source term.

3.21 From Reference 2.20, there is a 1" minimum of sand and a 10" concrete pad under the SIRW tank. (Note: the roofis sloped such that at the tank edges there is 2" of sand 10" of concrete and at the center there is 1" of sand and 11" of concrete. Using the 1" sand and 10" concrete is conservative, even though there always exists 12" of material for these two shields.)

3.22

3.23

3.24

3.25

3.26

3.27

3.28

3.29

FroTTI Reference 2.34, the control room roof is a cellular design consisting of two l' slabs of concrete separated by a 4' air space.

The manufactured accuracy of FE-1711 and FE-1712, which are Johnson Controls FMS-A Series flow elements, are ±2% as given in Reference 2.47.

The manufacturer's stated errors for FI'-1711 and FI'-1712 are ±0.5% of full scale for noise, ±1.5% of full scale for static error band, and ±5% of full scale for temperature from Reference 2.48. This results in a total error of ±5.2% after taking the square root of the sum of the squares of the individual errors. (This will be shown to be encompassed by the allowable calibration tolerance.)

The allowable "as-found" tolerance for both FT-1711 and FI'-1712 is ±4% per References 2.49 and 2.50, respectively.

The allowable "as-found" tolerances for FIC-1711 and FIC-1712 are ±5% and ±2% per References 2. 51 and 2. 52, respectively. That for FI C-1 711, being the higher of the two, will be applied to both flow controllers in this analysis to allow treatment of the two HV AC trains as identical for conservatism.

The allowable "as-found" tolerances for FI-1747 and FI-1748 are ±10% and ±4% per References 2.53 and 2.54, respectively. That for FI-1747, being the higher of the two, will. be applied to both flow indicators in this analysis to allow treatment of the two HV AC trains as identical for conservatism.

The allowable "as-found" tolerance for FT-1747 and FI'-1748 is ±2 psig on a 15 psig range per References 2.55 and 2.56. This would correlate to a tolerance of (2/15)-100 = ±13.3%.

From the completed calibrations documented in References 2.57 and 2.58, M&TE Manometer# 8428-00936 was used for calibration of FI'-1712 and FI-1747. FT-1711 and FI-1748 were also calibrated using the same manometer, as documented in WO 24803900 and Reference 2.60 .

3.30 The set fresh air make-up flow rates for the emergency mode of the control room HVAC system are 1010 cfm with 3200 cfm total filtered flow on train A and 1000 cfm with 3000 cfm total filtered flow on train B per References 2.59 and 2.60. The control room

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positive pressure was maintained at 0.27 inches H20 with operation of either train as also documented in those references. However, the recent R0-28 testing [Ref. 2.44] performed in the 1995 REFOUT documented 3100 cfrn total filtered fl.ow on train A and 3200 cfrn total filtered fl.ow on train B. R0-28 does not determine fresh air makeup fl.ow. As will be shown in Assumption 4.35, the fresh air make-up and recirculation fl.ow rates will always remain proportional to the total fl.ow rate through V-26A or V-26B. Hence train A will have 3100/3200*1010 = 978.44 cfrn Fresh air make-up, and train B will have 3200/3000*1000 = 1066.67 cfrn Fresh air make-up.

3.31 M&TE Manometer# 8428-00936 has a tolerance of±0.01 inches ofH20 per Reference 2.61. For a control room positive pressure of 0.27", this would correspond to a tolerance of(0.01/0.27)·100 = ±3.7%.

3.32 EA-TAM-95-06 Rev. 0 [Ref. 2.75] calculates a bounding combined inleakage of 67.6 cfrn past the A-train normal intake isolation dampers and the smoke purge isolation dampers.

4.0

4.1

4.2

4.3

4.4

4.5

4.6

Assumptions

All assumptions inherent in the methodology of the MHACALC code as documented in Reference 2.7 apply to this analysis. (See Assumption #s 4.14 - 4.18 for items which document justification for some deviations from the discussions in Reference 2.7.)

All assumptions inherent in the methodology of the CONDOSE code as documented in Reference 2.8 apply to this analysis.

The core is assumed to operate at 102% of rated power, or 2580.6 MWth.

The event begins with instantaneous release of the source term to the containment building.

For the case of source terms based on Regulatory Guide 1.4 [Ref. 2.13] and Standard Review Plan 15.6.5 Appendices A & B [Ref. 2.35], 100% of the core noble gas inventory is assumed to be released to the containment atmosphere. Also, 25o/o of the core iodine inventory is assumed to be released to the containment atmosphere and 50% of the core iodine inventory is assumed to be released to the containment sump solution. Of the iodine released to the containment atmosphere, 91 % is assumed to be elemental, 5% is assumed to be particulate and 4% is assumed to be organic.

For the case of source terms based on the 10 CFR 50 Appendix K analysis that shows fuel melting will not occur, 100% of the core is assumed to experience DNB and consequently has cladding failure with fission gases in the pellet-clad gap released. For conservatism, 20% of the core inventory of iodine and noble gas is assumed to be in the pellet-clad gap, which is consistent with Reference 2.9. Also to be consistent with Reference 2.9, 100% of the noble gas and 50% of the iodine released from the gap is assumed to be released to the containment atmosphere, with 50% of the iodine released from the gap assumed to be released to the containment sump solution. Of the iodine released to the containment atmosphere, 91 % is assumed to be elemental and 9% organic with 0% particulate since only pellet-clad gap gas release occurs.

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4. 7 The fraction of iodine in the sump solution that is in a volatile form for airborne release in the SIRWT is assumed to be 3.0xl0-4, as recommended in Reference 2.36. (Reference 2.39 is given as attachment 1 to Reference 2.25.) The volatile fraction, however, is conservatively ignored for ESF leakage into the safeguards rooms since the flashing fraction would control the amount of iodine going airborne for some period of time.

4.8 Loss of offsite power occurs coincident with the event.

4.9 Full containment spray flow is assumed to be achieved at 1.0 minute after initiation of the event, accounting for diesel generator sequencing and full flow delivery. Actual time for the worst case is 1.01 minutes (60.49 sec) for 90 % flow from 1 operational spray pump after a loss of off-site power [Ref. 2.37].

4.10 Containment ·sprays are assumed to be terminated 600 minutes ( 10 hours) after initiation of the event to conservatively end removal of iodine from the containment atmosphere. However, the containment spray pumps are assumed to continue to operate for providing HPSI subcooling, such that sump water leakage back to the SIRWT continues. EOP 4.0 [Ref. 2.76] describes the operator actions following a LOCA. This document prescribes that the operators terminate containment sprays after containment pressure is reduced to less than 3.0 psig. This conservatively assumes

, .. ··· that the decision to terminate sprays is not based on iodine activity. From the current containment response analysis for the LOCA [Ref. 2.38], containment pressure is still well above 3.0 psig at 600 minutes.

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4.11 Recirculation is reached in the minimum time of 19 minutes, which causes leakage of sump water outside of containment to begin at the earliest possible time (see attachment 2.2.3 of Ref. 2.77). Reference [2.38] assumes RAS at later than 40 minutes for both left and right channel failure cases.

4.12 The recirculation volume is at Ill1Il1m.um, which conservatively increases the concentration of fission products in the sump water for leakage paths outside of containment.

4.13 For the purpose of determining the fraction of the ESF leakage in the safeguards rooms that flashes, a sump temperature shortly after the peak is used since the sump temperature continuously decreases throughout the event, dropping below boiling temperatures in several hours. The peak post-recirculation sump temperature from the current LOCA containment analysis is approximately 251.4°F at 900 seconds for the right channel failure [Ref. 2.38]. Therefore, a temperature of 228.5°F and pressure of 32.9 psia, corresponding to approximately t = 4000 seconds (or 52 minutes after peak temp) from reference 2.38 are used. This is still conservative since the ESF leakage is accounted for at a constant flashing rate for the entire 30 day duration of the analyzed event.

4.14 The leak rate of post-recirculation sump water back to the SIRWT is assumed to be 2.2 gpm for a conservatively bounding value. R0-119 [Ref2.71] specifies a leak rate limit of 0.1 gpm through the mini-flow recirculation lines from the ESS pumps to the SIRWT. RT-71L [Ref. 2.72] limits the leakage through either SIRWT main discharge line, for an idle train of safety injection, to 1.9 gpm. These two tests were performed in the 1995 refout and met the combined test ·acceptance criteria of 2.116 gpm. (0.116

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gpm accounts for combined test uncertainties) Therefore, the leakage assumed in this analysis is a conservatively bounding value.

4.15 In the MHACALC code, iodine in the air volume of the SIRWT exits the tank at the rate at which air is being displaced from the tank times a multiplication factor to account for diffusion out the vent and changes in air density. This multiplication factor is assumed to be 2, which is consistent with the treatment of ESF leakage in SRP 15.6.5 Appendix B [Ref. 2.35]. This factor seems conservative and was informally agreed to as acceptable in telephone discussions with the NRC as documented in Reference 2.39.

4.16 For calculation of the partition coefficient for the volatile species of iodine in the SIRWT, an air-water interface temperature of 180°F is assumed due to the relatively large amount of sump water leakage into the tank that is assumed. Although no significant heating of the air volume in the SIRWT would be expected, the air-water interface temperature would increase as the amount of sump ·water in the tank increases. Assuming a value of 180°F is considered conservative since the sump solution temperature continually decreases throughout the event, yet the calculated partition coefficient is held constant.

4.17 For the amount of water left in the SIRWT following recirculation, it is assumed that the tank has drained down to the top of the flanges for the main discharge lines which project slightly more than 4" into the tank [Ref. 2.21]. This assumption maximizes the concentration of iodine in the water volume of the SIRWT due· to inleakage and consequently maximizes the quantity of iodine that becomes airborne in the tank to maintain equilibrium partitioning. This assumption is made since the SIRWT outlet control valves on both main discharge lines could leak. The discharge line on the operating train of safety injection could leak water from the SIRWT following tank isolation at recirculation. A~ the same time, the discharge line on the idle train of safety injection could leak sump water into the SIRWT following recirculation due to the scenarios described in Reference 2 .11. This assumption of minimal SIRWT water volume immediately following recirculation is extremely conservative since there is approximately 20,000 gallons left in the SIRWT at recirculation, which would take hours or days to drain down at nominal leak rates. Also, if the discharge line on the operating safety injection train leaks, sump water leakage into the tank from the discharge line of the idle train would exit with the leakage out of the tank through the discharge line on the operating train. However, all of the sump water leakage into the SIRWT is conservatively assumed to remain in the tank.

4.18 No flashing of sump water entering the SIRWT is assumed, consistent with the methodology discussed in Reference 2.7. The total leak rate into the SIRWT discussed in Assumption # 4.14 does not invalidate this assumption, even with the low level of water assumed in the SIRWT following recirculation as described in Assumption # 4.17. This is substantiated by the amount of ambient temperature water that would actually exist in the SIRWT at recirculation, the amount of time it would take for water to leak from the SIRWT following recirculation, and the amount of time it would take for sump water leakage to reach the SIRWT following recirculation. When recirculation begins, approximately 20,000 gallons of water are left in the SIRWT not accounting for the volume of water in the lines· leading to the SIRWT in which sump leakage can occur. It would take many hours, possibly days, before the level in the SIRWT decreases significantly due to leakage out of the tank through the operating train of safety injection. Also, due to the pressure in containment it is likely that leakage from

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the SIRWT would be restricted to some extent due to a manometer effect between containment and the SIRWT. It would also take a considerable amount of time following recirculation before sump water leakage to the SIRWT actually reaches the tank with the small leak rates considered. There is more than 100 feet of pipe through which the leakage must travel. The peak post-recirculation sump temperature for the most limiting LOCA is around 251°F, and within approximately 12 hours the sump temperature would be below the boiling point for atmospheric pressure, 212°F. Considering the low rate of leakage of sump water into the SIRWT and the long time that would be required to drain the ambient temperature water out of the SIRWT, it is not expected that the sump water temperatures would be high enough to cause flashing or significant heat up of the air volume of the tank. In addition, the thin aluminum walls of the SIRWT would transfer heat from the water in the tank to the outside air as sump water i...'11.eakage occurs.

4.19 Iodine re-evolution from the containment sump solution is insignificant since the post-recirculation pH is controlled to 7~ pH ~8. This is accomplished by Tri-Sodium Phosphate baskets located on the containment sump floor. This sump pH control system is passive, i.e. no operator action is necessary.

4.20 The source of radionuclide ingress into the control room when the control room is depressurized is through the normal air intakes.

4.21 Following SRP 6.4 [Ref. 2.30, pg. 6.4-8], the base infiltration rate of air into the control room when depressurized is assumed to be ·one-half the leakage from the control room when pressurized to 1/8" water gauge. A contribution from opening and closing doors does not need to be accounted for since vestibules have been installed on the entrances Reference 2.30 [pg. 6.4-9].

4.22 For control room shine dose calculations from the SIRWT, all of the iodine that leaked through the isolation valves and has not been released from the tank is assumed to be in the water volume of the SIRWT. The piping through which the leakage travels to the tank is therefore ignored since the activity in that volume is assumed to be in the tank and the tank sits on top of the control room.

4.23 The contaminated water volume of the SIRWT for shine dose calculations is assumed to be a homogeneous self-shielding source.

4.24 The SIRWT is conservatively assumed to be directly over the control room for shine dose calculations. It is actually centered closer to the viewing gallery.

4.25 The thin aluminum wall of the SIRWT is assumed to be insignificant for shielding gamma radiation to the control room.

4.26 For calcu~ations of shine dose from the SIRWT, the dose point is taken as 6' off the control room floor, assuming the average operator is 6' tall and standing under the tank.

4.27 The concrete between the SIRWT and the control room is ordinary concrete with a density of 2.35 g/ cms. This is the default density used by the MICROSHIELD code.

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4.28 Any material in the control room drop ceiling is conservatively ignored for the shine dose calculation from the SIRWT.

4.29 The Taylor method for calculating buildup factors is appropriate for the MICROSHIELD code calculations. The concrete roof structure is used as the material basis for buildup calculations since it is the dominant shield and last material between the source and the dose point.

4.30 For shine dose calculations from the SIRWT using the MICROSHIELD, the sand that exists underneath the SIRWT is assumed to be composed of Si02 with a nominal density of94.6 lbm/ft3, or 1.515 g/cm3, from Reference 2.46 [pg 37.4, Table 3].

,

4.31 The measurement error, or tolerance, associated with all M&TE equipment used to calibrate flow transmitters and indicators is assumed to be negligible compared to the error of the equipment being calibrated. An exception to this is the M&TE Manometer which has a much larger error than most other M&TE equipment.

4.32 M&TE Manometer # 8428-00936 that was used in References 2~57 and 2.58 is assumed to have a representative error of any manometer that would be used to calibrate FT-1711, FT-1712, FI-1747 and FI-1748.

4.33 Since no vendor specification was found for the accuracy of FE-1747 and FE-1748, a value of ±5% is assumed. This assumption is based on the vendor specification for FE-1711 and FE-1712 which was found to be ±2%, as discussed in Input# 3.23.

4.34 As can be seen on the revision listing for FI-1747, FT-1747, FI-1748 and,FT-1748 calibration sheets, calibration of the FT was split from the FI on 2/6/92. However, the work orders used to set the emergency mode fresh air make-up flow rate were completed on 9/23/91 [Refs. 2.59 & 2.60]. Therefore, the allowable "as-found" calibration tolerance for FI-1747 and FI-1748 at the time References 2.59 & 2.60 were completed is appropriate for the set fresh air make-up flow rates. The allowable "asfound" calibration tolerance was ± 10% for FI-17 4 7, which is higher than that for FI-1748, prior to splitting the calibration for the FTs as shown on Reference 2.62. For this reason, the tolerance for FT-1747 and FT-1748 discussed in input# 3.28 will not be accounted for.

4.35 The proportion of the recirculation flow and fresh air make-up flow that comprise the total V-26A or V-26B flow rate in the control room HVAC system are assumed to remain constant. This can be assumed since B.D.-5 and D-7 or B.D.-6 and D-14 will always open to the same positions when the respective train is operating in the emergency mode. Therefore, the fresh air make-up and recirculation flow rates will always remain proportional to the total flow rate through V-26A or V-26B.

4.36 The combination of HVAC system flow rates that results in the highest thyroid doses after accounting for system test acceptance criteria and instrument measurement and calibration tolerances is used to ensure conservatism .

4.37 As discussed in Input # 3.32, EA-DBD-1.06-03 Rev. 0 [Ref. 2.75] calculates a bounding combined inleakage of 67.6 cfm past the A-train normal intake isolation dampers and the smoke purge isolation dampers. This analysis accounted for possible changes in the system flow rates which would affect the damper Ap's and hence the

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amount of unfiltered inleakage. However, to provide design margin, the 67.6 cfm unfiltered inleakage will be increased by - 50%. Therefore 100 c:fm control room unfiltered inleakage will be used for determining control room habitability.

5.0 Method of Analysis

This analysis is performed using three computer codes: the MHACALC code [Ref. 2.7] for radiological releases and offsite doses, the CONDOSE code [Ref. 2.8] for control room operator doses due to radionuclide intake into the control room and the MICROSHIELD code [Ref. 2.40] for control room operator doses due to shine from the SIRWT. The offsite and control room doses are first calculated using the MHA fission product source term of Regulatory Guide 1.4 [Ref. 2.13]. The offsite and control room doses using the 10 CFR 50 Appendix K source term are then calculated. This is done to show the magnitude of difference between the doses using the conservative Regulatory Guide source terms and the source terms consistent with the design basis accident analysis for a LOCA.

To perform the calculations for each fission product source term case, ·the MHACALC code is first utilized. The MHACALC code will provide three output files. One will contain the activity in the containment and SIRWT at various points in time, the total activity released to the environment and the total doses at the site boundary and low population zone distance. The other two output files will contain the radionuclide release rates, one for those from the containment plus'auxiliary building (i.e. ESR's) and one for that from the SIRWT.

The CONDOSE code must then be executed once for the releases from the containment plus auxiliary building and once for the releases from the SIRWT. The resultant doses from the

·two CONDOSE cases are added to get the total operator doses from SIRWT, ESR and Containment releases. The CONDOSE code must be executed separately for the different releases since the atmospheric dispersion to the control room air intakes is different for each release location. The CONDOSE code is executed using the bounding unfiltered air leakage rate into the control room from Input # 3.32.

The MICROSHIELD code is then used to calculate shine dose in the control room from the SIRWT. The SIRWT activity at various points in time, from the MHACALC code output, is used as input to the MICROSHIELD code. The MICROSHIELD code gives a total dose rate at each point in time for which the calculations are performed. The calculated dose rates are assumed constant for large time intervals to provide conservative results and reduce the number of calculations that need to be performed. Whole body dose from SIRWT shine calculated using the MICROSHIELD code is then added to the whole body doses predicted by the CONDOSE code to obtain the total whole body dose from all sources.

6.0 Analysis Using Regulatory Guide 1.4 Source Terms

6.1 Offsite Doses Using Regulatory Guide 1.4 Source Terms

The inputs to the MHACALC code for the case of Regulatory Guide 1.4 source terms are described line by line in detail below. Most of the inputs described below are the same as those used in Reference 2.25. The structure for the MHACALC code input deck is obtained from Reference 2. 7.

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The first line of the input deck is the title or description of the case to be executed. Line 2 is the debug option which is specified as 1 for this case since debugging the output is not desired. The third line is the duration of the analysis, which is 43200 minutes (30 days).

The fourth line of the input deck contains the reactor thermal power, containment design leak rate, and the recirculation water volume. The reactor thermal power will be taken as 102o/o of the rated, or 2580.6 MWt as discussed in Assumption# 4.3. The containment design leak rate is 0.1%/day as discussed in Input # 3.3, which the MHACALC code automatically reduces by a factor of 2 after 24 hours to remain consistent with the guidance of SRP 15.6.5 [Ref. 2.35]. Based on a sump mass of 2439636 lbm at 39.0 psia and 250.3°F [Ref. 2.18] as discussed in Input# 3.4, the containment sump volume is taken as a minimum of 41498.2 ft3.

The fifth line contains the percentages of the core inventory of noble gas and iodine released to the containment atmosphere and iodine released to the containment sump, respectively. Following the guidance of Regulatory Guide 1.4 [Ref. 2.13] and SRP 15.6.5 [Ref. 2.35], 100% of the core inventory of noble gas is assumed to be released to the containment atmosphere, 25% of the core inventory of iodine is assumed to be released to the containment atmosphere, and 50% of the core inventory of iodine is assumed to be released to. the containment sump

. solution. These were discussed in Assumption # 4.5.

The sixth line of the input deck contains the fractions of the total iodine released to the containment atmosphere that are in the elemental, particulate and organic forms. Again following the guidance of References 2.13 and 2.35, the percentages are 91 % elemental iodine, 5% particulate iodine, and 4% organic iodine. These values were also discussed in Assumption # 4.5.

The seventh line of the input deck contains the following parameters:

1) the retention factor for iodine released into the safeguards rooms, 2) the iodine partition coefficient for the sump water leakage into the safeguards rooms, 3) the iodine partition coefficient for sump water leakage into the SIRWT, 4) the multiplication factor for the rate at which iodine is released from the SIRWT, 5) the total volume of the SIRWT, 6) the volume of water in the SIRWT at recirculation, and 7) the fraction of iodine ill the sump water reaching the SIRWT that would be in volatile form.

The retention factor for iodine released in the safeguards rooms is 2, as mentioned in Input# 3.6. This value was accepted by the NRC in Reference 2.19 since the ventilation in those rooms automatically isolates upon detection of high radiation. This retention factor is used to account for plateout of iodine onto surfaces in the safeguards rooms since the ventilation rates would be very low after isolation even assuming gross leakage of the dampers [See also Ref. 2.73].

For the iodine partition coefficient in the safeguards rooms Reference 2.35 [SRP 15.6.5, Appendix B] states that the fraction of iodine released to the rooms from ESF leakage should be taken as 10% (partition coefficient = 1 / .1 = 10) or the flashing fraction, whichever is greater, unless a lower fraction can be justified based on actual sump pH. As discussed in Assumption # 4.13, a temperature of 228.5°F and pressure of 32.9 psia are assumed for determining the enthalpy of containment sump solution. This is less than the peak (approximately 251°F), but still conservative since the temperature continually decreases

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throughout the event until no flashing of the leakage would occur. The fraction of ESF leakage flashing to steam is determined by (ru2s.5'F - hf212,F)/h%12,F, which using enthalpy: values from Reference 2.41 and assuming atmospheric pressure in safeguards rooms results in (196.84 - 180.17)/970.3 = 0.01718 or 1.718%. Th.ls would correspond to an instantaneous partition coefficient of 1/.01718 = 58.2, which bounds the iodine partition coefficientfor the sump solution. (The sump solution iodine partition coefficient shown later in this analysis is much higher, which results in less iodine release.) This partition coefficient for the ESF leakage is considered conservative since sump temperature decreases throughout the event, and would eventually be bounded by the sump solution partition coefficient once the leakage stops flashing to steam. The fact that only a fraction of the iodine in the sump water is in a volatile form, as is accounted for in the SIRWT, is conservatively ignored for the ESF leakage since the flashing fraction would be controlling the amount of iodine released for some period of time. ·

The third value on line 7 of the input deck is the iodine partition coefficient for the SIRWT. The iodine partition coefficient for the volatile species of iodine expected in the SIRWT can be _calculated using the following equation from Reference 2.42 [pg. 21], for which the applicability is verified iri Reference 2.36:

Iog10 P = 6.29-0.0149T

where P = ratio bf b in liquid phase to b in the gas phase, or the iodine partition coefficient T =air-water interface temperature, K. · ·

As discussed in Assumption # 4.16, a relatively large amount of sump water leaks into the SIRWT with the leakage rate assumed, therefore the air-water interface temperature is conservatively assumed to be 180°F, or 355.2 K. Using the above equation with this temperature results in an iodine partition coefficient of approximately 10 for the volatile iodine in the SIRWT. This partition. coefficient is conservative due to the high air-water interface temperature assumed, since sump water temperature continually decreases throughout the event. The applicability of this partition coefficient rather than a flashing fraction is discussed in Assumption # 4.18.

The fourth value on line 7 is a multiplication factor for the rate at which iodine in the air volume of the SIRWT exits through the vent. The SIRWT is modeled such that iodine in the air volume exits the tank at the rate at which air is displaced due to the water leaking in. The multiplication factor is utilized to conservatively encompass any diffusion or changes in density that cause air to travel out of the vent. As discussed in Assumption# 4.15, a value of 2 is used for this factor, being consistent with SRP 15.6.5 Appendix B [Ref. 2.35] treatment of ESF- leakage. This factor was informally agreed to as acceptable during telephone conversations with the NRC, as discussed in Reference 2.39.

The.total volume of the SIRWT, which is specified a.S the fifth value on line 7, is calculated in two parts: the cylindrical body portion of the tank and the conical top section of the tank. From Reference 2.20, ·the cylindrical body portion of the SIRWT has a diameter of 46' and height of 24', which yields a volume. of nr2h = 39885.66 ft3. The conical top section of the tank has a slope of%" per foot [Ref. 2.20], which corresponds to a vertical distance of 5.75" for the 23' radius of the tank. Using equation #54 from page 18 of Reference 2.43, the volume of the conical top section of the SIRWT is calculated to be 1/3nr2h = 265.44 ft3. The total volume of the SIRWT is simply the sum of the volumes for the cylindrical portion and the conical section, or 40151.1 fts.

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ANALYSIS CONTINUATION SHEET

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The sixth value on line 7 is the volume of water remaining in the SIRWT following recirculation, which is used to determine the water concentration of iodine as leakage into the tank occurs. Based on the partition coefficient, the water concentration determines the amount of iodine that becomes airborne. As discussed in Assumption # 4.17, it is conservatively assumed that the SIRWT is drained down to the top of the outlet flanges for the main discharge lines which protrude approximately 4" into the tank [Ref. 2.21]. · At the beginning of recirculation there would be approximately 20,000 gallons in the tank, but leakage out to the operating train could cause the level to eventually drain down to 4". Since the MHACALC code is not programmed to handle leakage from the SIRWT, the low level must be specified for the beginning of recirculation. Based on the 23' radius of the SIRWT, the volume of water at 4" of height is nr2h = 554 ft3. The volume of water in the lines leading to the SIRWT through which the leakage must travel are also conservatively ignored in this value.

The last value on line 7 is the fraction of iodine in the sump water reaching the SIRWT that is in volatile form. As discussed in Assumption # 4.7, this fraction is assumed to be 3.0xl0-4

since the sump pH will be controlled above 7 as discussed in Reference 2.36. This fraction is based upon radiolytic conversion, which would dominate the amount of volatile iodine, as b, released as discussed in Reference 2.42.

Line 8 of the input deck contains the appropriate off-site breathing rates for 0 to 8 hours, 8 to 24 hours and 1 to 30 days. As discussed in Input# 3.1, these are 3.47x10-4 m 3 /sec, l.75x10-4 m3/sec and 2.32xl0-4 m3/sec, respectively from Reference 2.13.

The 0 to 2 hour site boundary atmospheric dispersion factor is listed on line 9 of the input deck. This value is l.55xlQ-4 sec/m3, choosing the maximum value for 0 to 2 hours from Reference 2.17 [Table 2-17]. The low population zone atmospheric dispersion factors for 0 to 8 hours, 8 to 24 hours, 1 to 4 days and 4 to 30 days are listed on line 10 of the input deck. Also from Reference 2.17 [Table 2-18], these values for the low population zone are l.09x10-5

sec/m3, 6.94x10-6 sec/m3, 2.58xl0-6 sec/m3 and 6.25x10-7 sec/m3. These values were discussed in Input# 3.3.

The spray removal coefficients for particulate iodine are specified on line 11. Two coefficients are used in accordance with SRP 6.5.2 [Ref. 2.24], an initial removal coefficient and a long term removal coefficient for particulate iodine. The MHACALC code automatically changes to the long term removal coefficient after 98% of the particulate iodine has been removed from the containment atmosphere. As discussed in Input# 3.9, these values are 4.43 hr-1 and 0.443 hr-1 from Reference 2.22.

Lines 12 through 16 of the input deck are for specifying times at which spray removal of elemental iodine starts or changes, and for the corresponding removal coefficients. Only one value for elemental iodine spray removal is used in accordance with SRP 6.5.2 [Ref. 2.24]. The other lines for specifying values were added to the code for versatility. Full containment spray flow is assumed to be achieved at 1.00 minute accounting for diesel generator sequencing and flow delivery. Full spray flow would be achieved in 1.01 minute for the worst case discussed in Assumption# 4.9. The difference in doses for spray start at 1.01 minutes compared to 1.00 spray start is negligible. Therefore, the first value on line 12 used is 1.00 minute. The corresponding removal coefficient for elemental iodine on line 12 is 21.3 hrl froin Reference 2.22 as described in Input# 3.9. Lines 13 through 16 are specified as 0 since only one removal coefficient for elemental iodine is used.

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The maximum iodine decontamination factor for elemental iodine and the time at which containment sprays are terminated are on line 1 7 of the input deck. The maximum iodine decontamination factor is calculated using the following equation from SRP 6.5.2 [Ref. 2.24]:

DF=l+ VsH Ve

where Vs= Containment sump liquid voiume, ft3 Ve= Containment net free volume less Vs, ft3 H = Effective iodine partition coefficient

The iodine partition coefficient is a function of sump solution temperature, iodine concentration, and pH, and can be obtained from Reference 2.23. The pH of the containment sump solution is controlled above 7.0 via TSP baskets on the containment sump floor. For the iodine concentration, the SRP 15.6.5 [Ref. 2.35] assumption of 50% of the core iodine inventory being released to the containment sump is used. From Reference 2.26, which gives the iodine source term as 50% of the total release, the total amount in the containment sump would be 0.03062 g-atom/MWth, which is 79.018 g-atom for 2580.6 MWth. Dividing by the sump volume from Input # 3.4, 41498.2 fts or 1,175,098.3 L, results in 6.72xl0-5 gatom/L. The effective iodine partition coefficient increases with increasing temperature according to Figure 6 of Reference 2.23, so a low sump temperature of 132 °F, or 328.6 K, is used as discussed in Input # 3.10. Considering the temperature and iodine concentration, a point between the two plots on Figure 6 of Reference 2.23 would be appropriate. For conservatism, a value of 3 .1 is chosen from the figure, which corresponds to an effective iodine partition coefficient of - 1250 at a mixing time of 28.5 hours. (Note: The actual sump temperature and hence iodine partition coefficient is much higher during the time where spray removal of iodine is effective 1 minute through the time to DF. However, radiological consequences are maximized by using the low sump temperature for determining H and therefore DF.) Inserting this effective iodine partition coefficient into equation (2), along with the containment sump solution volume of 41498.2 ft3 and _the containment net free air volume of l.64xl06 ft3 [Ref. 2.17], results in a maximum decontamination factor of 32.51. The time at which containment sprays are terminated is specified as 600 minutes after initiation of the event, as discussed in Assumption# 4.10.

The times at which ESF leakage into the safeguards rooms begins and/ or changes, the corresponding ESF leak rates, the times at which sump water leakage into the SIRWT begins and/or changes, and the corresponding leak rates into the SIRWT are listed on lines 18 through 21. On line 18, the time at which ESF leakage starts is specified as 19 minutes for the minimum time to recirculation as discussed in Assumption # 4.11. The corresponding Technical Specification leak rate is 0.2 gpm [Ref. 2.2, TS 4.5.3] as discussed in Input # 3.5. The time on line 18 for leakage into the SIRWT to begin is also assumed to be 19 minutes. The corresponding leak rate to the SIRWT is specified as 2.2 gpm as discussed in Assumption # 4.14. All values on lines 19 through 21 of the input deck are specified as 0 since the ESF and SIRWT leakage is assumed to remain constant after recirculation and throughout the remainder of the incident. It should be noted that the code automatically multiplies the ESF leak rate by a factor of 2 to remain consistent with the guidance of SRP 15.6.5 Appendix B [Ref. 2.35].

On lines 22 through 39 of the input deck are the activity source term, the radioactive decay constant, the thyroid dose or dose rate conversion factor, and the whole body dose or dose

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rate conversion factor for each radionuclide. The radionuclides are specified in the same order as listed in Table 1. For the noble gas isotopes, all four values are listed in Table 1. For iodine, the activity source term and the radioactive decay constants are listed in Table 1, and the thyroid and whole body dose conversion factors are obtained from Table 2.

The number of time intervals for which release rates are to be calculated and written to output files is specified on line 40. For this analysis 11 time intervals are used for the release rates. These time intervals are specified on lines 41 and 42. The times for the intervals to change were chosen such that a new time interval begins at each point in time that the release rates could change by a significant amount, plus a few time points in between. The major points in time to consider for the release rates changing are: the time at which full spray is assumed to be achieved, 1.0 minute; the time at which the control room achieves pressuri..zation in the emergency mode, 1.26 minutes as discussed in Input # 3.15; the approximate time at which the spray removal effectiveness for elemental iodine ends, 12.0 minutes; the time ESF leakage and leakage into the SIRWT begin, 19.0 minutes; the first time at which atmospheric dispersion factors and other parameters change, 480.0 minutes; the time at which containment sprays are assumed to be terminated, 600.0 minutes; the time at which containment atmosphere leak rate changes, 1440.0 minutes; and the last time at which atmospheric dispersion factors and other parameters change, 5760.0 minutes. Several other somewhat arbitrary time points are also specified.

Line 43 of the input deck contains the number of points in time that the containment and SIRWT activities of each of the radionuclides are to be printed in the output file. The values of the total iodine activity in the SIRWT are used for calculating the shine dose to the control room operators. The number of times to be printed is specified as 15. Lines 44 and 45 of the input deck are the corresponding time points for the activities to be printed in the output file. These times were somewhat arbitrarily chosen as 19, 60, 120, 480, 720, 1440, 2880, 4320, 5760, 7200, 14400, 21600, 28800, 36000, and 43200 minutes.

The input deck constructed with the above listed parameters for execution in the MHACALC code has the filename MHA95 DATA. The MHACALC code was executed with the MHA95 DATA input deck on the Reactor & Safety Analysis Engineering Department's IBM 9370-90 mainframe computer. Three output files from the program execution are included on attachment #5: MHA95 LISTING, STAK-MHA DATA and SIRW-MHA DATA. An echo of the input deck is also provided in the MHA95 LISTING file. The fourth output file from the code for creating plots of the containment atmosphere iodine activity versus time was discarded since it was not of interest for this analysis. The MHA95 DATA file contains the containment atmosphere, sump and SIRWT activities at the input specified points in time and the offsite doses from the incident. The STAK-MHA DATA file contains the radionuclide release rates from the containment atmosphere and ESF leakage for the input specified time intervals. The SIRW-MHA DATA file contains the radionuclide release rates from the SIRWT for the input specified time intervals. These two data files of radionuclide release rates are to be used as inputs to the CO NOOSE code for control room habitability' calculations.

The resultant doses at the site boundary (SB) and low population zone distance (LPZ) from the incident are obtained from the MHA95 LISTING file. Since the NRC has not adopted the full ICRP30 methodology for calculating doses from design basis accidents, the doses taken from the listing file are the thyroid doses from inhalation and the whole body doses. The other listed doses incorporate the ICRP30 methodology of adding contributions for internal and external doses to obtain dose equivalent values. The resultant offsite doses from the incident from each release path and the total are listed in Table 4 below. As can be seen, these doses are well within the 300 rem th oid and 25 rem whole bod limits of 10 CFR 100.

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TABLE4

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Site Boundary And Low Population Zone Doses Using Regulatory Guide 1.4 Source Terms

0-2 Hour SB

Thyroid

Whole Body

0 - 30 Days LPZ

Thyroid

Whole Body

Containment Leakage [rem]

11.869

0.287

5.392

0.053

ESF Leakage [rem]

3.210

N/A

3.267

N/A

6.2 Control Room Unf'tltered Air Inleakage

SIRWT Leakage [rem]

0.000

N/A

0.022

N/A

Total Dose [rem]

15.079

0.287

8.680

0.053

Because the· MHA/LOCA assumes the loss of one safety train, there exist two paths for unfiltered air leakage into the control room. at any one time during the control room HV AC emergency mode of operation. Leakage can occur through the A train normal intake isolation dampers D-1 and D-2 and through the smoke purge isolation dampers D-15 and D-16 combination when the A-Train is operational and the B-Train is off. Or, leakage can occur through the B frain normal intake isolation dampers D-8 and D-9 and through the smoke purge isolation dampers D-15 and D-16 combination when the B-Train is operational and the A-Train is off. This was verified by the tests described in reference 2.74.

The only damper leakage calculation prior to the completion of the recent MHA/LOCA analyses [References 2.25 and 2.68], determined the total unfiltered air inleakage to the control room to be U.6 cfm. (see Ref. 2.63]. This was based on the design leakage of the dampers described in the preceding paragraph. However, no assurance was available that the actual damper performance was equivalent to the design performance. For this reason, Specification Change SC-93-034 was completed to install vent locks for damper visual inspections and differential pressure measurements.

To support SC-93-034 and the visual inspections, EA-DBD-1.06-02 Rev. 0 [Ref. 2.70 ] was completed to determine the leakage through the smoke purge and normal intake isolation dampers for various operating differential pressures and dampers blade seal gap widths. This analysis calculates leakage past the dampers in cfm. per linear foot of damper gap width for

• operating pressure ranging from 0.2-5.0 in. H20 and gap widths from 1/64" to 1/8".

During the 1995 Refout the dampers were inspected using the installed VENTLOK's and a Horoscope to determine damper integrity and the existence of any gaps in the damper blade seals. Each damper was visually inspected with the horoscope on one side and a light source

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on the other. The horoscope light was turned off in order to check for light which would indicate the existence of blade seal gaps. This was done for both sides of each damper. No light was seen for any of the dampers. In addition, the CRHVAC system engineer and the author of this EA visually determined that the dampers were in good working condition. Finally, damper Ap's, were measured for each isolation damper set, for operation with the ATrain on and the B-Train Off and vice-versa. All of these activities and results are described in Reference 2.74.

Note: The smoke purge dampers D-15 & 16 are so close together that a VENTLOK could_ not be placed in between them. Therefore one of the dampers was failed open in order to inspect the other damper for integrity and blade gaps.

Fro:p:i. the data obtai..'1.ed dur1.n.g the 1995 REFOUT damper test [Ref. 2.74] and the Sargent & Lundy calculation of damper leak rates for different gap widths and damper Ap's, EA-DBD-1.06-03 Rev. 0 [Ref. 2.75] determined a bounding value of67.60 cfm iP..leakage into the control room.

Reference 2.30 [pg. 6.4-9] suggests that the inleakage rate should be verified if it is calculated to be less than 0.06 volume changes per hour. Using the control room air volume of 35923 ft3 from Input #3.14, 0.06 volume changes per hour would correspond to a rate of approximately 2155 ft3/hr, or 36 cfm. This value is clearly less than the unfiltered air leakage value used in this analysis.

6.3 Control Room Doses Using Regulatory Guide 1.4 Source Terms

The CONDOSE code is used to predict the control room operator doses due to radioactivity that enters the control room. The CONDOSE code requires two input decks for each execution. The first input deck contains all of the physical parameters of the control room and radionuclides and the second input deck contains only the radionuclide release rates. Input decks for the radionuclide release rates from the containment plus ~afeguards rooms and for the release rates from the SIRWT are given as output from the MHACALC code: STAKMHA DATA and SIRW-MHA DATA, respectively. The input deck with the physical parameters for the CONDOSE code is described line by line below. However, separate input decks must be constructed for the release from the containment plus safeguards rooms and the release from the SIRWT since different a~ospheric dispersion factors are used for each. The only differences in these two input decks are the input deck description and the atmospheric dispersion factors, which are described for both input decks in the appropriate paragraphs below. The structure for the input decks is obtained from Reference 2.8.

The first line of the input deck is simply the title or case description. Note that separate titles are specified for the containment plus safeguards rooms release case and the SIRWT release case. The second line of the input deck is the air volume of the control room envelope. This volume includes the control room, the viewing gallery and the technical support center since the control room habitability system services all of these areas. As discussed in Input# 3.14, a conservative value was previously calculated to be 35923 ft3 in References 2.9 & 2.25 .

The third line of the input deck allows up to three different breathing rates and the 3 times at which these different breathing rates begin. As discussed in Input# 3.1 , the breathing rates used for control room doses are 3.47xl0-4 ma/sec from 0 to 8 hours, l.75x10-4 ma/sec from 8 to 24 hours, and 2.32xl0-4 ma/sec from 1 to 30 days in consistent with Reference 2.9.

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The number of control room occupancy factors to be used is listed on line 7 of the input deck. As discussed in Input # 3.18, 3 occupancy factors are used consistent with Reference 2.30.

The times at which each of the occupancy factors starts and/ or changes followed by the corresponding occupancy factors are on lines 8 through 10 of the input deck. To start, 0.0 minutes, the occupancy factor is 1.0. At 1440.0 minutes the occupancy factor changes to 0.6 and at 5760.0 minutes the occupancy factor changes to 0.4.

Line 11 of the input deck contains the number of atmospheric dispersion factors that are to be used. It is standard practice to use 4 atmospheric dispersion factors as can be seen in Reference 2.30. Lines 12 through 15 of the input deck contain the times that each atmospheric dispersion factor starts and/ or changes followed by the corresponding atmospheric dispersion factors for the control room normal air intake, remote air intake and a miscellaneous location of unfiltered air lnleakage, respectively. All of these atmospheric dispersion factors must correspond to the same release point for the radioactive contamination. Therefore, different values are used in the input decks for the containment plus safeguards rooms release case and the SIRWT release case. The values are listed in Table 3, under Input # 3.19. The values from Table 3 listed as containment releases are applied to the containment plus safeguards rooms release case and the values listed as SIRWT releases are applied to the SIRWT releases.

The number of points in time for which the control room HVAC system flow rates are to be specified is contained on line 16 of the input deck. For this analysis, 2 points in time are used: the initial flow rates while the control room is depressurized due to loss of offsite power, and the flow rates once pressurization in the emergency mode is achieved since a LOCA would generate a CHP (containment high pressure) signal which in turn would automatically switch the control room HVAC system to emergency mode. Lines 17 and 18 of the input deck contain the times that the control room HVAC system flow rates are to be· specified for and the corresponding flow rates for the control room normal air intake, emergency air intake, filtered recirculation air and a miscellaneous unfiltered air inleakage, respectively.

For the first time, 0.0 minutes on line 17 of the input deck, the control room is assumed to be depressurized due to loss of offsite power. The only air assumed to be entering the control room during this depressurized period is the base infiltration rate, which is unfiltered air assumed to be entering through the normal air intakes. As described in Assumption# 4.21, the base infiltration rate is assumed to be one-half of the leakage from the control room when pressurized to 1/8" water gauge. When the control room is maintained at a constant pressure, the leakage from the control room must equal the fresh air make-up. Therefore, when the control room is maintained at 0.125" water gauge, one-half of the fresh air make-up would be the base infiltration rate. As discussed in Input # 3.30, a fresh air make-up flow rate of 1010 cfm., as indicated on FI-1747, maintained the control room at 0.27" water gauge. As shown on Attachment 1 to this analysis, the indication on FI-174 7 has a total loop uncertainty of±l l.8%. Since a higher base infiltration rate allows more contaminated air into the control room, the fresh air make-up flow rate that maintains 0.27" water gauge is assumed to be on the high range of the uncertainty, or 1129.2 cfm.. Assuming flow rate to be proportional to the square root of differential pressure, the fresh air make-up flow rate at 0.125" water gauge pressure can be estimated to be (1129.2)(0.125/0.27) 16 = 768.3 cfm.. Taking one-half of this value would result in a base infiltration rate of 384.2 cfm.. Since the base infiltration rate is assumed to enter through the control room normal air intake, 384.2 cfm is specified as the first flow rate on line 1 7 with the following three flow rates specified as 0.0 cfm..



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For the time on line 18 of the input deck, 1.26 minutes is specified for the time at which pressurization in the emergency mode is achieved as discussed in Input # 3.15. The unfiltered air leakage into the control room through the normal air intake isolation dampers is 100.0 cfm.. This value is the result of adding 48% (which is -50%) margin to the Input # 3.32 value of67.6 cfm. as described in Assumption# 4.37. The fresh air make-up flow rate from the emergency air intake and the filtered recirculation air flow rate are determined from the acceptance criteria of Reference 2.44 in conjunction with measured system flow rates documented in Reference 2.29 and instrumentation uncertainties calculated in Attachment 1. There is an entire range of possible flow rates due to the uncertainties associated with the indicated flow rates and the acceptance criteria in the current surveillance test procedure. Attachment 2 to this analysis determines the possible ranges for the flow rates and provides the determination of cases that must be executed to determine which set of flow rates is most conservative. As discussed in .Attachment 2, there are four cases of different fresh air makeup and filtered recirculation air flow rates that must be evaluated to determine which is the worst case (i.e. worst thyroid dose since this is limiting dose). Each of the four cases were executed with the unfiltered air inleakage rate of 100.0 cfm.. The results of these cases showed that the lower end of the acceptance criteria in Reference 2.44 for total filtered flow rate yielded the worst results. Specifically, the filtered recirculation air from the control room is the dominating factor when assuming high rates of unfiltered air inleakage (since the case with the lowest recirculation flow rate resulted in the worst calculated doses). The flow rates specified on line 18 of the input deck for the worst case are 100.0 cfm for the normal air intake, 1132.7 cfm. for the emergency air intake, 1674.4 cfm. for the filtered recirculation air and 0.0 cfm for miscellaneous unfiltered air leakage (since all unfiltered air enters through the normal intake isolation and smoke purge isolation dampers).

Note: The four different CR-HVAC flow cases described in Attachment 2, are also included on attachment #5 as CR-FLOWl, CR-FLOW2, CR-FLOW3, and CR-FLOW4 LISTING.

Line 19 of the input deck contains the number of points in time for which.filter efficiencies are to be specified. Since the control room HVAC system charcoal filters are required by Technical Specifications [Ref. 2.2] to remain 2 99% efficient for iodine as discussed in Input# 3.17, only 1 time is specified. Line 20 contains the start time of the efficiencies, 0.0 minutes,. and three corresponding filter efficiencies for the control room normal intake air followed by three filter efficiencies for the emergency intake fresh air make-up and filtered recirculation air. The three filter efficiencies for each air intake are for the three possible types of radionuclides that would be released following a major accident: noble gas, halogens (iodine), and solids respectively. For the control room normal air intake, since no filter exists for the current plant configuration, all three efficiencies are 0.000. For the emergency intake fresh air make-up and filtered recirculation air, the filter efficiencies are 0.000 for noble gas, 0.990 for iodine, and 0.990 for solids or particulates. The efficiency for noble gas is 0.000 since it will simply pass through charcoal and HEPA filters.

On line 21 of the input deck is the number of points in time that the radionuclide concentrations in the control room and' the accumulated operator doses are to be printed in the output file. This value is specified as 0 for this analysis since only the total dose in the control room over the 30 day period of the analysis is of interest.

Line 22 of the input deck conta:lns the number of time intervals for which the radionuclide release rates will be specified in the input deck that contains the radionuclide release rates. This value is 11, corresponding to the value on line 40 of the MHA95 DATA input deck for the MHACALC code. Lines 23 and 24 are the beginning and end times of the time intervals.

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PALISADES NUCLEAR POwER PLANT ANALYSIS CONTINUATION SHEET

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These values correspond to the values on lines 41and42 of the MHA95 DATA input deck for the MHACALC code. These values are 0.00, 1.00, 1.26, 12.00, 19.00, 480.00, 600.00, 1440.00, 5760.00, 14400.00, 28800.00 and 43200.00.

The number of radionuclides for which release rates are specified and an identifier to specify the units in which the release rates are given are contained on line 25 of the input deck. The number of radionuclides is 18 since that is the number of radionuclides that the MHACALC code .considers and provides release rates for. The identifier that specifies the units of the radionuclide release rates is 1, corresponding to µCi/Hr.

Line 26 contains the total number of radionuclides to be considered for the calculations in the control room habitability area. For this analysis, this is the same as the number of radionuclides for which release rates are given by the MHACALC code, 18.

Lines 27 through 98 of the input deck contain the radionuclide constant data. The radionuclide data must be given in the same order that the radionuclides are given for the release rates output from the MHACALC code, which is the same order as listed in Tables 1 & 2 of this analysis. For each radionuclide, there are four lines of data. The first data line for each radionuclide contains the radionuclide name followed by an identifier for the radionuclide given for the consecutive order that they are specified in, starting with 1. The second data line for each radionuclide contains the inhalation dose conversion factors listed in Table 2 for the thyroid, lungs, bone surface, bone marrow, skin, eye lens and whole body, respectively. Since noble gas does not rt:sult in an inhalation dose, all of these values are 0.0 for the noble gas isotopes, on lines 27 through 78. For the iodine isotopes on lines 79 through 98, these values are listed in Table 2. The third data line for each radionuclide contains dose rate conversion factors for submersion in a radioactive cloud. For the noble gas isotopes, these values are listed in Table 2. For the iodine isotopes, since they do not result in a significant submersion dose per ICRP 30 [Ref. 2.28], these values are specified as 0.0. The fourth data line for each radionuclide contains an identifier for the form of the radionuclide, the radioactive decay constant, the identifier of the primary daughter product if applicable, and the production fraction for the primary daughter product if applicable. The identifier for the form of each radionuclide is 1 for noble gas and 2 for iodine [Ref. 2.8]. The radioactive decay constants for each radionuclide are listed in Table 1. The primary daughter product identifier and production factor are specified as 0 since daughter products are not being considered.

The input decks constructed with the above listed parameters for execution in the CONDOSE code have the filenames CRMHA95 DATA and CRMHA95A DATA for use with the STAK-MHA DATA and SIRW-MHA DATA release rate decks, respectively. As mentioned previously, the input deck titles and the atmospheric dispersion factors are the only parameters that differ between the two input decks. The CONDOSE code was executed once with the CRMHA95 DATA and STAK-MHA DATA decks and once with the CRMHA95A DATA and SIRW-MHA DATA decks on the Reactor & Safety Analysis Engineering Department's IBM 9370-90 mainframe computer. The output files from execution of the CONDOSE code for the two cases, CRMHA95 LISTING and CRMHA95A LISTING, contain echoes of the input files, and are listed on attachment #5. The output files from the additional cases executed with different control room HVAC system flow rates, which also echo the input files, are also li,sted on attachment #5, but were only executed with the STAK-MHA DATA release rate deck to determine which case yielded worst results.

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The resultant control room operator thyroid doses due to inhalation of iodine are obtained by adding the inhalation thyroid doses from the CRMHA95 LISTING and CRMHA95A LISTING files for the containment plus safeguards rooms leakage and SIRWT leakage, respectively. The total thyroid inhalation dose is 23.31 rem. The whole body dose from the radioactivity that entered the control room is obtained by adding the whole body submersion doses from the two listing files, which results in 0.05 rem. However, a shine dose contribution from the containment building and from the SIRWT (which resides on the control room roof) must also be included in the whole body dose. As discussed in Input# 3.20, a bounding value for the shine contribution from the containment building is 0.40 rem. Now the shine dose from the SIRWT must be calculated.

The SIRWT shine dose to the control room operators is calculated. using the MICROSHIELD code [Ref. 2.40]. The MiCROSHIELD code provides the dose rate, in mrem/hour, for the inputs specified. Inpµts for the code are specified interactively. The major inputs for the MICROSHIELD code are the type a_nd geometry of the source and shields, the activities of the radionuclides present in the source, dimensions of the source, the thicknesses of materials between the source and the receptor point, the material composition and density of the source and shields, the buildup factor method to be used, aµd the material for which the buildup factor calculations will be based. The activities of the radionuclides pres~nt in the SIRWT air and water volumes are obtained from the MHA95 LISTING file output of the MHACALC code. As described in Assumption #s 4.22 and 4.23, all of the activity in the SIRWT air and water volumes is conservatively assumed to be evenly distributed in the water volume for the purpose of shine dose calculations.

First, the geometry to be used to model the source of shine must be specified. The MICROSHIELD geometry used is a cylindrical source with shine from the end through slab shields. The dimensions of the source and shielding materials are then specified, followed by

·a case title. As described in Input# 3.21, there is al" minimum of sand under the SIRWT, followed by a 1 O" concrete slab on the roof above the control room. The control room roof is a cellular design consisting of l' of concrete followed by a 4' air space and another l' of concrete, as discussed in Input# 3.22. The 10" concrete slab and the l' concrete top of the cellular roof are treated as a single shield. Thus, the shields modeled between the tank and the control room are l" of sand, 22" of concrete, 48" o_f air and 12" of concrete. From Reference 2.45, it can be seen that the control room has a total height of 12', ignoring the drop ceiling. As discussed in Assumption# 4.26, the shine dose point is taken as 6' off of the floor, leaving a 6' air space between the control room concrete ceiling and the receptor point. The MICROSHIELD code accommodates up to five shields, including the source if it is a volume source, and will automatically insert an air space if the distance to the receptor is greater than the sum of the shield thicknesses. The SIRWT is considered a self-shielding source since the activity is assumed to be distributed in 4" of water that remains in the tank. (There is actually a much higher amount of water that continuously decreases throughout the event.) Including the water height in the SIRWT, and conservatively ignoring the changes in water level as valve leakage enters the tank, the total distance between the top of the source and the receptor point is 159". The model used for the MICROSHIELD geometry inputs is shown in Figure 1 below. The shields are labeled as they are on the interactive screen for the MICROSHIELD input. It should be noted that the MICROSHIELD code does not have a default sand material for shielding, so a material had to be made. As discussed in Assumption # 4.30, a material named sand was created using a composition of Si02 and default density of 1.515 g/cc.

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Figure 1

MICROSHIELD Geometry

T1(Water)=4"

72" Air space TS (Concrete) = 12"

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T4 (Air gap) = 48"

After specifying the geometry and dimensions of the source and shields, the method for buildup factor calculations, the material on which the buildup calculations are based, the point-kemal integration parameters must be specified. The Taylor method was chosen and the concrete was chosen as the material basis for the buildup calculations. The concrete was chosen as the material basis for buildup calculations since it is the dominant shield material and is the last material between -the source and dose point, as recommended in Reference 2.40 [pg. 6-5]. For the point-kemal integration parameters, the number of angular and radial segments were both chosen as 11. These parameters were chosen by starting with the default values and increasing the values, executing the code each time, until the results stopped changing which indicated the closest convergence. Reference 2.40 [pg. 5-6] also states that specifying the integration parameters as 11 should be sufficient for most cases.

A MICROSHIELD case input file was created for each of the times at which the activity in the SIRWT was listed in MHA95 LISTING file, starting at the first time after recirculation begins, 60 minutes. Each of the case input files was given the name xxxxMIN.MSH, where the xxxx corresponds to the minute value of the times for which the activity in the SIRWT is specified. For each of the case input files, all input parameters except the iodine activity and the case title were left the same.

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After all of the case input files were created with the MICROSHIELD code, an input queue for a batch run of all of the cases was created. This input queue was created in the MICROSHIELD code by "Prepare an input queue for a Batch run" option of the main menu and choosing all of the input case files. This input queue was then executed as a batch run. The summary output from the batch run containing the calculated dose rate for each case is provided as Attachment 3 to this analysis, with the printout of each individual case given in Attachment 4. As can be seen on the summary in Attachment 3, the calculated dose rate in the control room increases for each of the cases until 480 minutes due to the increasing iodine concentration in the SIRWT. The calculated dose rate then decreases throughout to 43200 minutes due to decay of the high energy gamma emitters that have short half-lives. Since the dose rate only increases with time for the first 8 hours and decreases with time for the following 712 hours for which the calculations are performed, the dose rate calculated at each time pohJ.t is assumed to be constant until the nex-t time point at which the dose rate is calculated. For the time from 19 minutes, when leakage to the SIRWT began, to 60 minutes, the calculated dose rate for 60 minutes will be used since no data was obtained for earlier times. By applying the calculated dose rates in this manner, a conservative value will be obtained. The calculation of the total dose received in the control room, using the results of the MICROSHIELD executions, is shown in Table 5 below. The dose rate for each time is multiplied by the time interval, an appropriate units conversion factor for minutes to hours, and the control room occupancy factor to obtain the total dose received by a control room operator over a time interval. The results from each time interval are then summed as shown below.

TABLE 5

Shine Dose To The Control Room From The SIRWT Using Regulatocy Guide 1.4 Source Terms

Time Interval MSHIELD Dose Rate Occupancy Interval Dose Case File (mrem/hr) Factor (mrem)

Begin (min) End (min)

19. 60. 60MIN l.7172E+Ol 1.0 11.73

60. 120. 60MIN l.7172E+Ol 1.0 17.17

120. 480. 120MIN 3.2736E+Ol 1.0 196.42

480. 720. 480MIN 6.2518E+Ol 1.0 250.07

720. 1440. 720MIN 6.1430E+Ol 1.0 737.16

1440. 2880. 1440MIN 3.7149E+Ol 0.6 534.95

2880. 4320. 2880MIN 9.4770E+OO 0.6 136.47

4320. 5760. 4320MIN 3.8031E+OO 0.6 54.76

5760. 7200. 5760MIN 2.3648E+OO 0.4 22.70

7200. 14400. 7200MIN l.7511E+OO 0.4 84.05

14400. 21600. 14400MIN l.2124E+OO 0.4 58.20

21600. 28800. 21600MIN l.1553E+OO 0.4 55.45

28800 . 36000. 28800MIN l.0007E+OO 0.4 48.03

36000. 43200. 36000MIN 7.9422E-Ol 0.4 38.12

Total Dose= 2,245.29

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[§; NUCLEAR PLANT

As can be seen in Table 5, the total whole body shine dose in the control room from the SIRWT over 30 days was calculated to be 2.25 rem using the Regulatory Guide 1.4 [Ref. 2.13] assumptions for fission product source term release. This is considered to be a conservatively bounding value due to the assumptions made and the large time intervals used for the calculations. The total control room shine dose to the whole body is obtained by adding that from SIRWT shine to the shine dose from the co;ntainment building (discussed in Input # 3.20) and the submersion dose from radioactive contaminants that entered the control room (calculated in two cases executed with the CONDOSE code). This results in a total shine dose of2.25 + 0.4 + 0.05 = 2.70 Rem.

7.0 Analysis Using 10 CFR 50 Appendix K Analysis Source Terms

7 .1 Offsite Doses Using Appendix K Source Terms

Most inputs to the MHACALC code for the case of Appendix K source terms are the same as for the case of Regulatory Guide 1.4 source terms. The lines of the input deck and the inputs that are different from those for the Regulatory Guide 1.4 source term case are described below, with the exception of the title line which also changed. In addition, justification is provided for inputs which would have been expected to change with the Appendix K source term, but have not been changed due to the value used for the Regulatory Guide 1.4 case being more conservative .

The percentages of the core inventory of noble gas and iodine released to the containment atmosphere and iodine released to the containment sump on line five 9f the input deck are the most significant difference between the Appendix K and Regulatory Guide 1.4 source terms. Since the Appendix K LOCA analysis [Ref. 2.10] demonstrates that the melting temperature of the fuel is not predicted to be exc.eeded, it is assumed that 100% of the core experiences departure from nucleate boiling (DNB) with Sl:lbsequent cladding failure. As discussed in Assumption# 4.6, 20% of the core inventory of iodine and noble gas is assumed to be in the pellet-clad gap of the fuel. Since 100% of the noble gas in the pellet-clad gap is assumed to be released to the containment atmosphere, the 20% present is the gap is specified as the first value. For iodine, regulatory guidance is based on 50% of the iodine being released to the containment atmosphere with 25% initial wall plateout, and 50% being released to the containment sump. For this case, initial wall plateout is ignored since the fission products in the gap are mostly gaseous in form. Therefore, 50% of the iodine released from the pellet-clad gap is assumed to be released to the containment atmosphere and 50% to the containment sump, which corresponds to 10% of the total core inventory to each since 20% of the total is assumed to exist in the gap.

The ·fractions of the total iodine released to the containment atmosphere that are in the elemental, particulate and organic forms listed on line six of the input deck are also different from the case using Regulatory Guide 1.4 source terms. As discussed in Assumption# 4.6, 91 % of the iodine released is assumed to be in the elemental form with 0% in particulate form and 9% in organic form. This assumption is conservative since there is no removal mechanism credited for organic iodine in the containment atmosphere other than radioactive decay.

The maximum iodine decontamination factor of 32.51, for elemental iodine, listed on line 17 of the input deck is the same as that used for the Regulatory Guide 1.4 source term case. This is conservative for the Appendix K source terms.



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All other values are identical to those used for the Regulatory Guide 1.4 source term case. The input .. deck constructed with these parameters for execution in the MHACALC code has the filename LOCA95 DATA. The MHACALC code was executed with the LOCA95 DATA input deck on the Reactor & Safety Analysis Engineering Department's IBM 9370-90 mainframe computer. Three output files from program execution are included in attachment #5: LOCA95 LISTING, STAK-LOC DATA and SIRW-LOC DATA. An echo of the input deck is also provided in the LOCA95 LISTING file. The fourth output file from the code for creating plots of the containment atmosphere iodine activity versus time was discarded since it was not of interest for this analysis. The three output files named above contain the same information as those described earlier in this analysis for the Regulatory Guide 1.4 source term case. The resultant offsite doses from the incident from each release path and the total are listed in Table 6 below. As can be seen, these doses are a small fraction of the 10 CFR 100 limits.

TABLE6

Site Boundary And Low Population Zone Doses Using Appendix K Source Terms

Containment ESF Leakage Leakage [rem] [rem]

SIRWT Leakage [rem]

Total Dose [rem]

· ·· . 0-2 Hour SB

•

Thyroid

Whole Body

0 - 30 Days LPZ

Thyroid

Whole Body

6.833

0.057

3.676

0.011

0.642

N/A

0.653

N/A

7 .2 Control Room Doses Using Appendix K Source Terms

0.000

N/A

0.004

N/A

7.475

0.057

4.334

0.011

Use of the CONDOSE code for the Appendix K source term case is basically the same as that done for the Regulatory Guide 1.4 source term case. The input decks with the physical parameters for the CONDOSE code are identical to those created for the Regulatory Guide 1.4 source term case except for the filenames and title lines of the input decks. Using 100.0 cfm unfiltered air inleakage, the file CRLOCA95 DATA was created for use with the STAK-LOC DATA file and the file CRLOC95A DATA was created for use with the SIRW-LOC DATA file. The CONDOSE code was executed once with the CRLOCA95 DATA and STAK-LOC DATA decks and once with the CRLOC95A DATA and SIRW-LOC DATA decks on the Reactor & Safety Analysis Engineering Department's IBM 9370-90 mainframe computer. The output files from execution of the CONDOSE code for the two cases, CRLOCA95 LISTING and CRLOC95A LISTING, which include echoes of the input files, are included on attachment #5.

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The resultant control room operator thyroid doses due to inhalation of iodine are obtained by adding the inhalation thyroid doses from the CRLOC95 LISTING and CRLOC95A LISTING files for the containment plus safeguards rooms leakage and SIRWT leakage, respectively. The total thyroid inhalation dose is 11.29 rem using the Appendix K source term with 100.0 cfm of unfiltered air leakage into the control room. This is less than half of the thyroid dose predicted with the MHA source term. The whole body dose from the radioactivity that entered the control roqm is obtained by adding the whole body submersion doses from the two listing files, which results in 0.01 rem. The shine dose from the containment building and the SIRWT would obviously be much less with the Appendix K source term than with the Regulatory Guide 1.4 source term. Therefore, those determined for the Regulatory Guide 1.4 source term case are conservatively applied to this case as bounding values. This would yield a total control room whole body dose that is le:;;s than 2.25 + 0.4 + 0.01 = 2.66 rem for the case of Appendix K source term with iOO.O c:fm unfiltered air leakage into the control room.

8.0 Summary and Conclusions

An analysis of the MHA was performed using the Regulatory Guide 1.4 source term and corresponding conservative inputs and assumptions to determine the radiological consequences of a maximum hypothetical accident. For comparison purposes, an analysis was then performed using a source term based on the 10CFR50 Appendix K LBLOCA analysis that justifies that no fuel melting would occur in the most limiting design basis accident. The results of these calculations are summarized below.

Table7

Control Room Doses for the MHA and LBLOCA

Site Boundary Low Population Zone Control Room

Event

Limits

MHA

LB LO CA

Thyroid [rem]

300

15.08

7.48

(SB)

WB [rem]

25

0.29

0.06

(LPZ)

Thyroid WB Thyroid [rem] [rem] [rem]

300 25 30

8.68 0.05 23.31

4.33 0.01 11.29

9.0 List of Attachments

1. 2. 3. 4. 5 .

Calculation of Loop Uncertainties for CR HVAC Flow Indication, 1 page. Range of Possible Flow Rates for CR HVAC System, 2 pages. MICROSHIELD Batch Run Summary, 2 pages. MICROSHIELD Case Printouts, 27 pages. Listing of CO NOOSE and MHACALC Files, 59 pages.

WB [rem]

5

2.70

2.66

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ATTACHMENT 1

Calculation of Loop Uncertainties for CR HVAC Flow Indication

1.) Fresh Air Make-up Flow as Indicated by FI-17 4 7 or FI-17 48

Note: FT-17 4 7 & FT-1748 are included in the FI tolerance as discussed in Assumption # 4.34.

a) FE-1747 & FE-1748 Accuracy= ±5% (Assumption# 4.33)

b) FI-1747 & FI-1748 "As-found" Calibration Tolerance= ±10% (Input# 3.27) M&TE Manometer Tolerance= ±3.7% (Input# 3.31)

Total FI Tolerance= J(lO / + (3. 7 / = ±10.663%

Total Loop Uncertainty For FI -1747 (FI -1748) Indication= J(5 f + (10.663/ = ±11. 777 %

2.) Total V-26A or V-26B Filtered Flow as Indicated by FIC-1711 or FIC-1712

a) FE-1711 & FE-1712 Accuracy= ±2% (Input# 3.23)

b) FT-1711 & FT-1712 "As-found" Calibration Tolerance= ±4% (Input# 3.25) M&TE Manometer Tolerance= ±3.7% (Input# 3.31)

TotalFTTolerance = J(4 f + (3. 7 / = ±5.449%

Note: This allowable FI uncertainty is greater than vendor specified accuracy described in Input # 3.24.

c) FIC-1711 & FIC-1712 "As-found" Calibration Tolerance= ±5% (Input# 3.26)

TotalLoopUncertaintyForFIC-171l(FIC-1712)Indication = J(2 f + (5.5 f + (5 / = ±7.661%

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ATTACHMENT 2

Range of Possible Flow Rates for CR HV AC System

t!; NUCLEAR PLANT

To determine the range of possible flow rates for the emergency mode of the control room HVAC system, first the measured values must be evaluated for both trains of the system. As discussed in Input # 3.30, for train A, 3100 cfm and 978.44 cfm are used for the total filtered and fresh air make-up flow, respectively. For train B values of 3200 cfm and 1066.67 cfm are used for the total filtered and fresh air make-up flow, respectively. Due to the uncertain,ties, there is a possible range for both of the measured flow rates in each train. Since the fresh air make-up flow rate is assumed to remain proportional to the total flow rate (Assumption # 4.35), it is t..1ie ratio of the t-wo over the entire range of flow rates that is of interest as shown below.

TrainA:

FIC-1711 Flow 3100+7.661% = 3337.49 cfm 3100-7.661% = 2862.51 cfm

Smallest ratio 863.21/3337.49 = 0.25864

Train B:

FIC-1712 Flow 3200+7.661% = 3445.15 cfm 3200-7.661% = 2954.85 cfm

Smallest ratio 941.05/3445.15 = 0.27315

FI-1747 Flow 978.44+11.777% = 1093.67 cfm 978.44-11.777% = 863.21 cfm

Largest ratio 1093.67 /2862.51 = 0.38207

FI-1748 Flow 1066.67+11.777% = 1192.29 cfm 1066.67-11.777% = 941.05 cfm

Largest ratio 1192.29/2954.85 = 0.40350

(Note:' Using the numbers measured in References 2.59 and 2.60 will give the exact. same ratios calculated above.)

The two extremes for the ratio of fresh air make-up flow rate to total filtered flow rate considering data from both trains of the control room HVAC system are 0.25847 to 0.40376. This range must now be applied over the allowable range for the total filtered fl.ow rate. As discussed in Input # 3.16, the surveillance test acceptance criteria for total filtered fl.ow rate as measured on FIC-1711 and FIC-1712 is 3040 to 3520 cfm. · However, this acceptance criteria does not account for the uncertainty associated with fl.ow rates indicated by FI C-1 711 and FIC-1712. Accounting for the measurement uncertainty, the range expands to 3040-7.661% = 2807.11 cfm to 3520+7.661% = 3789.67 cfm. Applying the largest and smallest ratio calculated above to both ends of the range of allowable total filtered flow rates results in the system fl.ow rates shoWn below.

For 2807 .11 cfm total filtered flow:

0.27315(2807.11) = 726.0 cfm fresh air make-up 2807.11-726.0 = 2081.1 cfm recirculation

0.40350 2807.11 =1132.7 cfm fresh air make-u 2807.11-1227.1 = 1674.4 cfm recirculation

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For 3789.67 cfm total :filtered flow:

§; NUCLEAR PLANT

0.27315(3789.67) = 980.2 cfm. fresh air make-up 3789.67-980.2 = 2809.5 cfm recirculation

0.40350(3789.67) = 1529.l cfm. fresh air make-up 3789.67-1529.1 = 2260.5 c:fm recirculation

Each of the above calculated four cases for system flow rates must be evaluated to determine which results in the highest control room operator doses. There is a definite trade-off between the amount of fresh air brought in through the :filters and the amount of control room air that is recirculated through the :filters. If there is a high concentration of contaminants in the control room, increasing the recirculation flow through the :filters aids in cleaning up the control room air. The fresh air that is brought in is also filtered so that it is relatively clean air compared to the control room if there is a high concentration of contaminants. Also, for every cfm. of fresh air that enters the control room, a cfm of contaminated control room air exists through penetrations. Therefore, increasing fresh air make-up flow may aid in cleaning up the control room air if there is a high concentration of contaminants in the control room compared with that which is not removed by the charcoal :filters. For these reasons each of the four cases listed above must be evaluated.

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ATTACHMENT 3

MICROSHIELD BATCH RUN SUMMARY

fii NUCLEAR PLANT

MICROSHIELD BATCH RUN LOG EA-TAM-95-05 =============================Sheet 41 Rev# _o_

• Batch run started on Monday, November 13, 1995 at 4:00 p.m.

Thirteen files initially in the queue.

CASE FILE START TIME ELAPSED GEOM DOSE (mr/hr) SENS. CYCLE ======== ========== ======= ---- ============ ===========

1 60MIN 4:00 p.m. 0:00:15 10 l.7172e+Ol (n/a) 2 120MIN 4:00 p.m. 0:00:15 10 3.2736e+Ol (n/a) 3 480MIN 4:00 p.m. 0:00:15 10 6.2518e+Ol (n/a) 4 720MIN 4:01 p.m. 0:00:15 , 10 6.1430e+Ol (n/a) ./

5 1440MIN 4:01 p.m. 0:00:15 10 3.7149e+Ol (n/a) 6 2880MIN 4:01 p.m. 0:00:15 10 9.4770e+OO (n/a) 7 4320MIN 4:02 p.m. 0:00:15 10 3.803le+OO (n/a) 8 5760MIN 4:02 p.m. 0:00:15 10 2.3648e+OO (n/a) 9 7200rv1IN 4:02 p.m. 0:00:15 10 l.75lle+OO (n/a)

10 14400MIN 4:03 p.m. 0:00:15 10 l.2124e+OO (n/a) 11 21600MIN 4:03 p.m. 0:00:15 10 l.1553e+OO (n/a)· 12 28800MIN 4:03 p.m. 0:00:15 10 1 .. 0007e+OO (n/a) 13 36000MIN 4:04 p.m. 0:00:15 10 7.9422e-01 (n/a)

Batch run completed on Monday, November 13, 1995 at 4:04 p.m.

TOTAL EXECUTION TIME: 0:04:35

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ATTACHMENT 4

:MICR.OSHIELD CASE PRINTOUTS

I

•

'• , '· •

Page. File_ Run date: Run time:

Microshield 3.13 =================

(Conslliners Power Company - #037) 1·

60MIN .MSH November 13, 1995 4:00 p.m.

File Ref: Date:

By: Checked:

CASE: Updated MHA JCO Analysis - SIRWT Shine @ 60 minutes

GEOMETRY 10: Cylindrical source from end - slab shields

Distance to detector ........................ . x 403.860 Source cylinder radius ...................... . R 701.040 source cylinder length ................ -· .... . Tl 10.160 Thickness of setortd shield .........•......... T2 ·2.540 Thickness of third shield ................... . T3 55.880 Thickness of fourth shield ..•................ T4 121.920 Thickness of fifth shield ................... . TS 30.480 Microshield inserted air gap ................ . air 182.880

Source Volume: 1.56866e+7 cubic centimeters

Material

Air Aluminum Carbon concrete Hydrogen Irori Lead Lithium

. Nickel Tin Titanium Tungsten Urania ·

-Uranium Water Zirconium sand

MATERIAL DENSITIES (g/cc) :

Source Shield 2 Shield 3 Shield 4

1.0

2.350

1.5150

EA-TAM-95-05 Sheet 43 Rev# _o_

.001220

Shield 5

2.350

I I

cm. II

II .---'·

II

II

II

II

II

_Air gap

.001220

•

•

•

Page 2 File: 60MIN.MSH CASE: Updated MHA JCO Analysis - SIRWT Shine @ 60 minutes

BUILDUP FACTOR: based on TAYLOR method. ·Using· the characteristics.of the materials in shield 5.

INTEGRATION PARAMETERS:

Number of angle segments (Npsi)....... ... . . . . . . 11 ·Number of radial segments (Nradius) . . . . ... . . . . . 11.

SOURCE NUCL~DES:

Nuclide C~ies Nuclide Curies Nuclide Curies

I-13i · l.0380e+04 I-132 l.1570e+04 I-133 l.7440e+04 I-134 1. 0640e+04 I-135 1.6630e+04

RESULTS:

Group #

Ene-rgy Activity Dose point flux MeV/(sq cm)/sec

Dose rate (mr/hr)

1 2 3 4 5 6 7 8 9

10 11 12 13 14 15 16 17 18 19 20

(MeV) (photons/sec)

2. u,11 1.6224 1.1702

"'8487 •

16587 .5204 .. 3724 .2.786 . 2164 .1.355

TOTALS:

3.335e+13 3.184e+14 6.258e+14' 1. 291e+15 7.816e+14 8.071e+l4 4.014e+14 6.803e+13 1.755e+13 1. 995e+13

4.364e+15

2.354e+03 S.437e+03 1.516e+03 S.158e+02 7.418e+Ol 1.SSSe+Ol 4.819e-Ol 5.631e-03 1. 255e-04 . 3.797e-07

9.913e+03


3.74Se+oo 9.392e+OO 2.822e+OO l.027e+OO 1. 540e-01 3.188e-02 9. 909.e-04 1.120e-OS 2.362e-07 6.31le-10

1. 717e+Ol .

'i

• Microshield 3.13 =================

(Consumers Power Company - #037) Page 1 File Ref: File 120MIN .MSH -Run date: November 13, 1995 Run time: 4:00 p.m.

Date: _!_!_ . By:

Checked:

CABE: Updated MHA JCO Analysis - SIRWT Shine _@ 120 minutes

GEOMETRY- 10: Cylindrical source from end slab.shields

Distance to detector ........................ . x 403.860 Source cylinder radius ....... ; .............. . R 701.040 Source cylinder length ................ ~ ..... . Tl 10.160 Thickness of second shield .................. . T2 2.540 Thickness of third shield ................... . T3_ 55.880 Thicikness of fourth shield ....... ~ .......... . T4 121.920 .Thickness of fifth shield .. ~ ................ . TS 30.480 Microshield insert~d air gap ................ . air 182.880

Source Volume: l.56866e+7 cubic centimeters

Material

Air Aluminum Carbon ·Concrete Hydrog_en Iron Lead Lithium Nickel Tin Titanium Tungsten Urania uranium Water· Zirconium sand


Source Shield 2 Shield 3 Shi.eld 4 . Shield 5

.001220

2.350 2 .350

1..0

1:5150


cm. II

II

II

II

II

II

II

\Air gap

.001220

•

/.

••


BUILDUP FACTOR: based on TAYLOR method. Using the characteristics of the materials in shield 5.

INTEGRATION PARAMETERS:.

Number of angle segments.· (Npsi) .· ........... : . . 11 Number of radial segments. (Nradius) . . . . . . . . . . . 11

SOURCE NUCLIDES:

Nuclide Curies Nuclide Curies Nuclide Curies

~-131 2.6940e+04 I-132 2.1080e+04 I-133 4.1550e+04 I-134 1.1890e+04 I-135 3.68.90e+04

RESULTS:

Group Energy Activity Dose point flux Dose rafe # (MeV) (photons/sec) MeV/ (sq cm)/sec (_mr/hr)·

- - - - - ------1 2.1371 2 1.6209 3 1.1766 4 .8444 5 .6603 6 .. 5214 7 . 3711 8 .2815 9 .2183

10 .1359 11 12 13· 14 15 16 17

·-:. :,

18 ·-.. 19 20

TOTALS:

- - - - - - - - - - - - - . - - - - - - - - - - - - - - - -6 ·. 478e+13 4.624e+03 6.077e+14 1.033e+04 1. 238e+15 3.087e+03 1.894e+15 7.353e+02. 1.360e+15 1.307e+02 1.763e+15 3 .. 443e+Ol 9.277e+14 1.077e+OO 1.441e+14 1.333e-02 3.48~e+13 2.697e-04 2.301e+13 4_.624e-07

--------- ---------8.058e+15 1 .. 894e+04

EA-TAM-95-05 Sheet 46 . Rev# _o_

- - - - - - - - -7.347e+OO 1. 784e+Ol 5.739e+OO 1. 465e+OO 2.713e-Ol 7.059e-02 2.215e-03 2.654e-05 5.087e-07 7.693e-10

- - - - - - - - -3.274e+Ol

•

•

•

Microshield 3.13 =================

(Consumers Power Company - #037) Page 1 File Ref: F.ile 4"80MIN .MSH Run date: November 13, 1995 Run time: 4:01 p.m.

Date: __ / __ /_ By:

Checked:



Distance to detector ........................ . x 403.860 cm. Source cylinder radius ...................... . R 701.040 II

Source cylinder length ...................... . Thickness of second shield ............ ~ ..... .

Tl 10.160 II

T2 2.540 II

Thickness of third shield ................... . T3 55.880 II

Thickness of fourth shield ................... . T4 121.920 II

Thickness of· fifth shield ................... . TS 30.480 II

Microshield inserted air gap ................ . air 182.880 II

Source.Volume: 1.56866e+7 cubic centimeters


Material Source Shield 2 Shield 3 Shield 4 Shield 5 . Air gap

Air Aluminum Carbon Concrete Hydrogen Iron Lead Lithium Nickel Tin Titanium Tungsten Urania Uranium Water Zirconium sand

1. 0

2.350

1. 5150


.001220 .001220

2.350

••• Page 2 . File: 480MIN.MSH

CASE: Updated MHA JCO Analysis -· SIRWT Shine @ 480 minutes

BUILDUP FACTOR: based-on TAYLOR method. Using the characteristics·. of the materials in shield s.


Number of angle segments (Npsi) ............... 11 Number of radial segments (Nradius) . . . . . .. . . . . . 11


• Microshield 3.13 =================

(Consumers Power Company - #037) 1 File Ref: Page

File Run date:

720MIN .MSH. November 13, 1995 4:01 p.m.

Date: By:

_!_! __

Run time: Checked:



Distance to detector .... , ................... . x 403.860 Source cylinder r~dius ...................... . R 701.040 Source cylinder length.···············-·· ... . ~hickness of second shield .................. .

Tl 10.160 T2 2.540

Thickn~ss of third shield ................... . T3 55.880 Thickness of fourth shield ..... ~········ .... . T4 121. 920 Thickness of fifth shield ................... . TS 30.480 r .. 1.icroshield inserted air· gap.- . .............. . air 182.880



cm. II

II ,, ..

.> II

II

II

II

II

. . . . Material Source .Shield 2 Shield 3 Shield 4 Shield 5 ;,Air gap

Air· Aluminum Carbon Concrete Hydrogen Iron Lead Lithium. Nickel Tin Titanium Tungsten Urania Uranium Water Zirconium sand.

1.0

·-·:·:.,·.---..

2.350

1. 5150

EA-TAM-95-05 Sheet 49 · Rev# _o_

.001220 ~ 001220

2. 350 ..

•

•

•


BUILDUP FACTOR: based on TAYLOR method. using the characteristics of the materials in shield 5.


Number of angle segments (Npsi)...... .. . . .. . . . 11 Number of radial segments (Nradius) . . . . . . . . . . . 1-1

SOURCE NUCL2DES:


I-131 l.8040e+05 I-132 7.1850e+03 I-133 2.0670e+05 I-134 3.0350e+Ol I-135 8.9700e+04

RESULTS:

Group #

Energy (MeV)

Activity (photons/sec)

Dose point flux MeV/(sq cm)/sec

Dose rate (mr/hr)

1 2 3 4 5 6 7 8 9

10 11 12 13 14 15 16 17 18 19 20

2.1919 1.6379 1.1860

.8556

.6615

.5229

.3681

.2867

. 2164

.1474

TOTALS:

9.855e+13 1.126e+15 2.656e+15 1.108e+15 1.224e+15 7.180e+15 5.622e+15 S.6Sle+14 8.367e+13 6.837e+ll

1. 966e+16

EA-TAM-95-05

7.803e+03 2.023e+04 6.907e+03 4.641e+02 1.188e+02 1.429e+02 6.066e+OO 6.413e-02. 6.006e-04 6.450e-08

3.567e+04

Sheet 50 Rev# _o_

1.227e+Ol 3.487e+Ol 1. 282e+Ol 9.225e-01 2.465e-01 2.932e-01 1. 248e- 02 1.280e-04 1.130e-06 1.107e-10

6.143e+Ol

•

• ,, ,

•

Microshield 3.13 =================

Page 1 (Consumers Power Company - #037)

File 1440MIN.MSH Run date: November 13, 1995 Run time:, 4:01 p.m.

File Ref: Date:

By: Checked:

CASE: Updated MHA JCO Analysis - SIRWT Shine @ 1440 minut,es

GEOMETRY,10: Cylindrical source from end - slab shields

· Distance to detector ........................ . x 403.860 Source ~ylinder radius .. ~ ................... . Source-cylinder lerigth .......•....... , ...... . .Thickness of second shield .............. ~ ... . Thickness of t~ird shield ....... ~ ......... -~·

R 701.040 Tl , 10 .160 T2 2.540 T3 55.880

Thitkness of fourth shield ..........•........ Thickness of fifth shield ................... .

T4 121.920 TS 30.480

Microshield inserted air gap ................ . air 182.880

S,ource Votu..rne: 1. 56866e+7 cubic centimeters

Material

Air' Aluminum Carbon Concrete Hydrogen' Iron·

-Lead Lithium Nickel Tin Titanium Tungsten

.Urania uranium Water Zirconium sand·

MATERIAL DENSITIES _(g/cc) :

Source Shield ~ Shield 3

1. 0

·, _.'.;;

2.350

1.5150

EA-TAM-95-05 Sheet Sl Rev# _o_

Shield 4

.001220

Shield 5

2.350

I I

cm. II

II -~

II

II

II

" II "

, Air gap_·

.001220

•

•

•

Page 2 File": 1440MIN.MSH CASE: Updated MHA'JCO Analysis - SIRWT Shine @ 1440 minutes



Number of. angle segments (Npsi) . . . . . . . . . . . . . . . 11 Number of radial segments (Nradius). ........ .. 11

SOURCE NUCL.IDES:


I-131 3.5020e+05 I-132 3.9140e+02 I-133 2.8090e+05 r-134 4.6530e-03 I-135 5.1650e+04

RESULTS:

Group #

Energy Activity · Dose point flux MeV/(sq .cm)/sec

Dose rate (mr/hr)

1 2 3 4 5 6 ,7 8 9

10 11 12 13 14 15 16 17 18 19 20

(MeV) (photons/sec)

2~2057 1.6422 1.1954

. 8682

.6581

.5229

.3673

.2874

.2042

.1484

TOTALS:

5.259e+13 6 . .359e+14 1.790e+15 8.738e+14 1.524e+15 9.466e+15 1.070e+16 9.021e+14 7.212e+13 3.431e+10

2.602e+16

EA-TAM-95-05

4.274e+03 1.158e+04 4. 85-7e+03 3.990e+02 1.440e+02 1.884e+02 l.131e+Ol 1.052e-01 3 .179e-o4-3. 740e-09

2.145e+04

Sheet 52 Rev# _o_

6.702e+OO 1.995e+Ol 8 .. 994e+OO 7. 911e- Oi . 2.990e-Ol 3.864e-Ol 2.327e-02 2.102e-04 5.893e-07 6.437e-12

3.715e+01

• Microshield 3.13 =================

(Consumers Power Company - #037) Page 1 File Ref: File 2880MIN.MSH Run date: November 13, 1995 Run time: 4:02 ~.m.

Date: _!_! __ By:

Checked:



Distance to detector .................... ~-- .. x 403.860 Source cylinder radius ...................... . R 701. 040 Source cylinder length ...................... . Tl 10.160 Thickness of second shield ......... ···'··· .. . Thickness of third shield ................... .

T2 2 .. 540 T3 55.880

Thickness of fourth shield .................. . T4 121.920 Thickness of fifth shield ................... . TS 30.480 Microshield inserted air gap ................ . air 182.880


Material



Source Shield 2 Shield 3 Shield 4 Shield 5

.001220

2.350 2.350

1.0

1. 5150


cm. II

II

II

II

II

II

II

.Air gap

.001220

•

•

Page 2 File: 2880MIN.MSH CASE: Updated MHA JCO Analysis - SIRWT Shine @ 2880 minu.tes



Number of angle segments (Npsi) ........ ~ ... ~.. 11 Number of radial segments (Nradius) .... ~...... 11

SOURCE NUCLIDES:


I-1~1 6.4690e+05 I-132 5.6920e-01 I-133 2.5410e+05 I-134 5.3590e-ll IT135 8.3920e+03

RESULTS:

Group Energy Activity Dose point flux MeV/(sq crn)/sec

Dose rate (mr/hr) # . (MeV) (photons/sec)

1 2

·3 4 5 6 7 8 9

10 11 12 13 14 15 16 17 18 19 20

2.2072 1.6427 1.2251

.8689

.6548 .. 5228

.3670

.2882

.1838

.1484

TOTALS:

8.475e+12 1. 031e+14 6.501e+14 6.429e+14 2.477e+15 8.485e+15 1.959e+16 1.504e+15 6.953e+13 4.989e+07

3.353e+16

6.907e+02 1. 8Ble+03" 2.015e+03 2.949e+02 2.278e+02 1.686e+02 2.054e+Ol 1.810e-01

, a. 903e-os· 5.440e-12

5.299e+03

EA-TAM-95-05 Sheet · 54 Rev# _o_

l.083e+OO 3.240e+OO 3.708e+OO 5.847e-Ol

. 4. 734e- 01 3.458e-,Ql 4.225e-02 3.617e-04 1.608e-07 9.362e-15

9.477e+OO

•

•

Microshield 3.13 =================

(Consumers Power Company - #037) Page 1 File Ref: File . 4320MIN.MSH Run date: November 13, 1995 Run time: 4:02 p.m.

Date: __ /_/_ By:-

Checked: ~~~~~-

CASE: Updated MHA JCO Analysis - SIRWT Shine_@ 4320 minutes


Distance to detector .. ~ ..................... . x 403.860 Source cylinder .radius ...................... . R 701.040 Source cylinder length .......... ~ ........... . Tl 10.160 Thickness of second shield ...... · ...... · ...... . T2 2.540 Thickness of third shield ......... ~ ......... . T3 55.880 Thickness of fourth shield ... -............ ~ .. . T4 121.920 Thickness of fifth shield ............•....... TS 30.480 Microshield inserted air gap ................ . air i82.880


Material

Air Aluminum Carbon Concrete Hydrogen Iron. Lead Lithium Nickel Tin Titanium Tungsten Urania _ Uranium Water Zirconium sand

MATERIAL DENSITIES -(g/cc) :

Sou~ce Shield 2 Shield 3 Shield 4 Shield 5

.001220

2.350 2. 350 -

1.0

1-. 5150


cm. II

II•

II

II

II

II

II

. Air gap

.001220

--1

I

File: 4320MIN.MSH CASE: Updated MHA JCO Analysis - SIRWT Shine @ 4320 minutes

• BUILDUP FACTOR: based on TAYLOR method. Using the characteristics of the materials in shield 5.


Number of angle segments (Npsi). .. . . . . . .. . . . . . 11 Number of radial segments (Nradius) ........... 11

SOURCE NUCL_IDES:

Nuclide Curies Nuclide Curies. Nuclide Curies ------- - - - - - - - - - - ------- - - - - - - - - - - ------- - - - - - - - - - -I-131 8.9220e+05 I-132 6.1800e-04 I-133 1.7170e+05 I-134 4.6080e-19 I-135 1.0180e+03

RESULTS:

Group Energy Activity Dose point flux Dose·rate # (MeV) (photons/sec) MeV I (sq cm)/sec (mr/hr)

- - - - - ------ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -.i 1 2.2072 1.028e+12 8.378e+Ol 1.314e-Ol 2 1. 6427 1.251e+13 2.281e+02 3.930e-01

/ 3 1.2433 3.218e+14 1. 088e+o3 1.995e+OO 4 .8688 4.183e+14 1. 918e+02 3.802e-01 5 .6531 3.235e+15 2.935e+02 6.lOle-01 6 .5226 5.779e+15 1.146e+02 2.351e-Ol 7 .3670 2.698e+16 2.825e+Ol 5.812e-02 8 .2887 2.029e+15 2.482e-01 4.960e-04 9 .1801 8.817e+13 8.814e-05 1. 585e-: 07

10 .1484 5.416e+04 5.907e-15 1.017e-17 11 12 13 14 15 16 17 18 19 20

- - - - - - - - - - - - - - - - - - - - - - - - - - -TOTALS: 3.886e+16 2.028e+03 3.803e+OO

• EA-TAM-95-05 Sheet 56 Rev# _o_

•

• 7

Microshield 3.13 =================

(Consumers Power Company - #037) Page File Run date: Run time:

1. 5760MIN.MSH November 13, 1995 4:02 p.m.

File Ref: Date:

By: Checked:



Distance to detector ........................ . x 403.860 Source cylinder radius ...................... . R 701.040 Source -cylinder length ................ -...... . Tl 10.160 Thickness of secortd shield .......... · ........ . T2 2.540 Thickne$S of third shield ................... . T3 55.880 Thickness of fourth shield .............. ~ ... . T4 121.920 Thickness of fifth shield ................... . TS 30.480 Microshield inserted air gap ................ . air 182.880

Source.volume: 1.56866e+7 cubic centimeters

Material




.001220

2.350 2.350

1.0

1.5150


I I

cm. II

II

II

II

II

II

II

·Air gap

.001220

. Page 2 File: 5760MIN.MSH CASE: Updated MHA JCO Analysis - SIRWT Shine @ 5760 minutes



Number of angle segments (Npsi) .... .. ... .. .. . . 11 Number of radial segments (Nradius) ... .. .. .. . . 11

SOURCE NUCLIDES:


I-131 1.0930e+06 I-132 5.9580e-07 I-133 1.0300e+05 I-134

Group #

1 2 3 4 5 6 7 8 9

10 11 12 13 14 15 16 17 18 19 20

O.OOOOe+OO I-135 1.0960e+02

..

RESULTS:

Energy Activity Dose point flux MeV/(sq cm)/sec (MeV) (photons/sec)

2.1423 1.6393 1.2485

.8762

.6528

.5226

.3672 .. 2919 .2576 .1797

TOTALS:

1.341e+ll 1.323e+12 1.801e+14 2.321e+14 3.873e+15 3.528e+15 3.285e+16 2.647e+15 1.367e+13 1.071e+14

4.343e+16

9.670e+OO 2.387e+Ol 6.236e+02 1.119e+02 3:5ose+o2 6.997e+Ol 3.462e+Ol 3.668e-Ol 4.989e-04 1.043e-04

1.22Se+03


Dose rate (mr/hr)

1.535e-02 4.114e-02 1.143e+OO 2.215e-01 7.287e-01 1.435e-Ol 7.122e-02 7.344e-04 9.816e-07 1.874e-07

2.36Se+OO

,. ' I

' <•\ I ..

Microshield 3.13 =================

(Consumers Power Company - #037) Page 1 File Ref: File 7200MIN.MSH Run date: November 13, 1995 Run time: 4:03 p.m.

Date: _/_/_ By:

Checked:



Distance to detector ........................ . x 403.860 Source cylinder radius ...................... . R 701. 040 Source cylinder length ...................... . Tl 10.160 Thickness of second shield ............ ~ ..... . T2 2.540 Thickness of third shield ................... . T3 55.880 Thickness of fourth shield .................. . T4 121.920 Thickness of fifth shield ................... . TS 30.480 Microshield inserted air gap ................ . air 182.880


Material




.001220

2.350 2.350

1.0

1. 5150

EA-TAM-95-05 Sheet 59 Rev# _O_

cm. II

II

II

II

II

II

II

. Air gap

.001220

•


BUILDUP FACTOR: based on TAYLOR method. Using. the characteristics of the materials in shield s·.


Number of angle segments (Npsi) ............... 11 Number of radial segments (Nradius) ........... 11

Nuclide -------

-I-131 I-134

Group #

- - .;. - -1 2 3 4 5 6 7 8 9

10 11 12 13 14 15 16 17 18 19 20

SOURCE NUCLIDES:

Curies Nuclide Curies Nuclide ~ - - - - - - - - - ------- . - - - - - - - - - - -------

.1. 2540e+06 I-132 S.3830e-10 I-133 O.OOOOe+OO I-135 1.1070e+Ol

RESULTS:

Energy Activity Dose point flux (MeV) (photons/sec) MeV/ (sq cm)/sec ------2.1423 1. 6393 1.2491

. 8760

.6521

.5220

. 3672 ~2919 .2578 .1797

.. ,.-.

.. -·-.

TOTALS:

- - - - - - - - - - - - - - - - - - - - - - - - - - - - -1.355e+10 9.767e-Ol 1. 336e+ll 2.411e+oo 1.001e+14 3.477e+02 1. 302e+14 . 6.269e+Ol 4.374e+15 3.936e+02 2.069e+15 4.070e+Ol 3.767e+16 3.969e+Ol 3.034e+15 4.207e-Ol 7.647e+12 2.807e-04 1.229e+14 1.197e-: 04

-- - - - - - - - - - - - - -- - -4.751e+16 8.882e+02


Curies - - - - - - - - - -5.7910e+04

Dose rate (mr/hr)

- - - - - - - - -1.550e-03 4.155e-03 6.371e-01 1.241e-Ol 8.183e-Ol 8.347e-02 8.164e-02 8.423e-04

·5.523e-01· 2.150e-07

- - - - - - - - -1.751e+OO

•• /

Microshield 3.13 =================

(Consumers Power Company - #037) Page 1 File Ref: File 14400MIN.MSH Run date: November 13, 1995 Run time: 4:03 p.m.

Date: _! __ / __ By:

Checked:



Distance to detector ......................... X Source cylinder radius ....................... R Source cylinder length ............... ~·· ..... Tl Thickness of second shield ... ···~·· ... ~ ...... T2 Thickness of third shield .................... T3 Thickness of fourth shield .............. ~· ... T4 Thickness of fifth shield .................... TS Microshield inserted air gap ... ; ...... ·~· .. ·~ air

403.860 701.040 10.160

2.540 55.880

121.920 30.480

182.880

Source Volume: l.56866e+7 cubic centimeters

Material

Air Aluminum Carbon Concrete Hydrogen Iron Lead Lithium Nickel Tin Titanium Tungsten Urania Uranium water Zirconium sand



.001220

2.350 ,, 2 .3.50

1. 0

1. 5150


cm.

,·

Air gap

.001220

!




Number of angle segments (Npsi) .......... ~ .. .. 11 Number of radial segments (Nradius) .......... ~ 11

SOURCE NUCLIDES:


I-131 1.6310e+06 I-132 O .. OOOOe+OO I-133 2.1260e+03 I-134

Group #

1 2 3 4 5 6 7 8 9

10 11 12 13 14 15 16 17 18 19 20

O.OOOOe+OO I-135 7.5810e-05

Eriergy (MeV)

2.2072 1. 6427 1.2829

.9061

.7267

.631.6

.5077

.3670

.2891

.1797

TOTALS:

RESULTS:

Activity (photons/sec)

7.656e+04 9.315e+05 3.125e+l.2 4.226e+12 1.091.e+lS 4.583e+15 2.193e+14 4.927e+16 3.653e+15 1.598e+14

5.898e+l.6

Dose point flux MeV/(sq cm)/sec

6.239e-06 1..699e-05 1..274e+Ol 2.497e+OO 1..790e+02 3.390e+02 3.581.e+OO 5.158e+Ol. 4.537e-01. 1. 557e- 04

5.889e+02


Dose rate (mr/hr)

9.782e-09 2.927e·-oa 2.321e-02 4.91.3e-03 3.661e-01 7.038e-Ol 7.333e-03 1.. 061e-01 9.070e-04 2.797e-07

1.. 212e+OO

Microshield 3.13 =================

Page 1 (Consumers Power Company - #037)

File Ref: File 21600MIN.MSH Run date: November 13, 1995 Run time: 4:03 p.m.

Date:_;_;_· By:

Checked:



Distance to detector ......................... X Source cylinder radius ................ : ...... R Source cylinder length ....................... Tl Thickness of second shield ............ : ...... T2 Thickness of third shield .................... T3 Thickness of fourth shield ..... ; ...... ~ ...... T4 Thickness of fifth shield .................... TS Microshield inserted a ~ .... ga'"' . - ~~ - ___ l:="_· •••••••••••••••• air

403.860 701.040 10.160

2.540 55.880

121. 920 30.480

182. 88_0


Material

Air Aluminum Carbon Concrete Hydrogen

.Iron Lead Lithium Nickel Tin Titanium Tungsten Urania Uranium Water Zirconium sand

MATERIAL DENSITIES (g/cc):

Source Shield 2 Shield 3

1. 0

2.350

1.5150


Shield 4

.001220

Shield 5

2.350

cm.

.Air gap

.001220




Number of angle segments (~psi)............... 11 Number of radial segments (Nradius).... .. . . . . . 11

SOURCE NUCLIDES:


I-131 1.5910e+06 I-132 O.OOOOe+OO I-133 5.8510e+Ol --- I--134 0. OOOOe+OO -I-135 3.892-0e-10

RESULTS:

Group #

Energy Activity Dose point flux MeV/(sq cm)/sec

Dose rate (mr/hr)

1 2 3 4 5 6 7 8 9

10 11 12 13 14 15 16 17 18 19 20

(MeV) (photons/sec)

2.2072 1. 6427 1. 2829

. 9061

.7266

.6332

.5078

.3670

.2891

.1797

TOTALS:

3.930e-01 4.782e+OO 8.600e+10 1.163e+ll 1.061e+15 4.405e+15 2.123e+14 4.806e+16 3.563e+15 1.559e+14

5.746e+16

3.203e-11 8.722e-11 3.507e-Ol 6.872e-02 1.740e+02 3.310e+02 3.472e+OO 5.031e+Ol 4. 426e-01· 1. 518e- 04

5.597e+02


5.022e-14 1. 503e-13 6.387e-04 1. 352e-04 3.559e-01 6.872e-Ol 7.109e-03 1. 035e- 01 8.848e-04 2.728e-07

1.lSSe+OO

•

__ ,

Microshield 3.13 =================

(Consumers Power Company - #037) Page 1 File 28800MIN.MSH Run date: November 13, 1995 Run time: 4:04 p.m.

File Ref: Date:

By: Checked:

CASE: Updated MHA JCO Analysis - SIRwr Shine @ 28800 minutes


Distance to detector ........................ . x 403.860 Source cylinder radius .................... ; .. R 701.040 Source cylinder length ....................... . Thickness of second shield ....... -........... .

Tl 10.160 T2 2.540

Thickness of third shield ................... . T3 55.880 Thickness of fourth shield .................. . T4 121.920 Thickness of fifth shield ................... . TS 30.480 Microshield inserted_ air_ gap .. _ ...... _ ... _._ •. __ .. _. a:i,:r 182.880 - -

Sourc:;e- Volume: 1. 5686_6e+7 cubic centimeters

Material

Air Alliminum Carbon Concrete Hydrogen Iron Lead Lithium Nickel Tin Titanium Tungsten Urania Uranium Water Zirconium sand


Source Shield 2 Shield 3 Shield 4

.001220

2.350

1. 0

1.5150


Shield 5

2.350

I I

cm. II

II

II /

II

II

II

II

_Air gap

.001220

File: 28800MIN.MSH CASE:· Updated MHA JCO Analysis - SIRWT Shine @ 28800 minutes



Number of .angle segments (Npsi) .............. . Number of radial segments (Nradius) .......... .

SOURCE NUCIJIDES:

11 11


I-131 I-134

Group #

1 2 3 4 5 6 7 8 9

10 11 12 13 14 15 16 17 18 19 20

1.3790e+06 I-132 O.OOOOe+OO I-133 --0.0-000e+OO ----I-135 - ----1.77-60e-l-5

RESULTS:

Energy Activity Dose point flux MeV/(sq cm)/sec (MeV) (photons/sec)

2.2072 1. 6427 1.2829

.9061

.7266

.6333

.5078

.3670

.2891

.1797

TOTALS:

1. 794e- 06 2.182e-05 2.103e+09 2.845e+09 9.197e+14 3.817e+15 1.839e+14 4.166e+16 3.088e+15 1.351e+14

4.980e+16

EA-TAM-95-05

1. 462e-16 3.980e-16 8.576e-03 1. 681e- 03 1.508e+02 2.869e+02 3.009e+OO 4.361e+Ol 3.836e-Ol· 1.316e-04

4.847e+02

Sheet 66 Rev# _o_

1.4310e+OO

Dose rate (mr/hr)

2.292e-19 6.856e-19 1.562e-05 3.307e-06 3.084e-01 5.956e-Ol 6.160e-03 8.972e-02 7.669e-04 2.365e-07

1. OOle+OO

I

!

•

•

•

Microshield 3.13 =================

(Consumers Power Company - #037) Page 1 File . 36000MIN.MSH Run date: November 13, 1995 Run time: 4:04 p.m.

File Ref: Date:

By: Checked:



Distance to detector •........................ X 403.860 Source cylinder radius ....................... R 701. 040 Source cylinder length ....................... Tl 10.160 Thickness of second shield ........... : ....... T2 2.540 Thickness of third shield .................... T3 55.880 Thickness of fourth shield ................... T4 121.920 Thickness of fifth shield .................... TS 30.480 Microshield inserted air gap ................. air 182.880

-sourc-e. Volume: 1. 56866e+7 cubic centimeters

Material ·

Air Aluminum Carbon Concrete Hydrogen Iron Lead Lithium Nickel Tin Titanium Tungsten Urania Uranium

.Water Zirconium sand


Source Shield 2 Shield 3

1.0

2.350

1.5150


Shield 4

.001220

..

Shield 5

2.350

I I

cm. II

II

II ,/

.11

II

II

II

Air gap

.001220

••

•

•

. Page 2 File: 36000MIN.MSH CASE: Updated MHA JCO Analysis - SIRWT Shine @ 36000 minutes



Number of angle segments (Npsi)........... .. . . 11 Number of radial segments (Nradius) ........... 11

SOURCE NUCLJ:DES:


I-131 1.1200e+06 I-132 O.OOOOe+OO I-133 3.2800e-02 I-134 O.OOOOe+OO I-135 O.OOOOe+OO

RESULTS:

Group #

Energy Activity Dose point flux MeV/(sq cm)/sec

Dose rate (mr/hr)

1 2 3 4 5 6 7 8 9

10 11 12 13 14 15 16 17 18 19 20

(MeV) (photons/sec)

1. 2829 1.0215

.8673

.6514

.5078

.4245

.3671

.2903

.2578

.1797

TOTALS:

4.821e+07 1.094e+07 7.665e+07 3.847e+15 1. 4.94e+14 5.605e+06 3.373e+16 2.612e+l5 4.326e+06 l.097e+14

4.045e+l6

EA-TAM-95-05

1. 966e-04 1. 344e-05 3.478e-05 3.442e+02 2:444e+OO 2.134e-08 3.544e+Ol 3.405e-01 1.590e-10 1.069e-04

3.824e+02

Sheet 68 Rev# _o_

3.581e-07 2.583e-08 6.898e-08 7.156e-Ol 5.003e-03 4.370e-11 7.291e-02 6.Slle-04 3.129e-13 1. 921e- 07

7.942e-Ol

• I

~·

• .'

•

ATTACHMENT 5

MHACALC AND CONDOSE FILE LISTINGS

EA-TAM-95-05 Sheet 69 Rev# 0

•

•

Listing of files (in order) for EA-TAM-95-05 Rev. 0

MHA95 LISTING A STAK-MHA DATA A SIRW-MHA DATA A CRMHA95 LISTING A CRMHA95A LISTING A LOCA95 LISTING A STAK-LOC DATA A SIRW-LOC DATA A CRLOCA95 LISTING A CRLOC95A LISTING A CR-FLOW1 LISTING A CR-FLOW2 LISTING A CR-FLOW3 LISTING A CR-FLOW4 LISTING A

EA-TAM-95-05 Sheet 70 Rev# __Q__

•

•

•

MHA95 LISTING A

EA-TAM-95-05, MHA RG 1.4 SOURCE TERM, 2.2 GPM TO SIRWT 1 43200

2580.6 0.10 41498.2 100.0 25.0 50.0 91.0 5.0 4.0 2.0 58.2 10.0 2.0 40151.1 554.0 0.30E-03

0.35E-03 0.18E-03 0.23E-03 0.15E-03 O. l lE-04 0.69E-05 0.26E-05 0.62E-06

4.43 0.443 1 21.300 0 0.000 0 0.000 0 0.000 0 0.000

32.51 600 19 0,2 19 2.200 0 0.0 0 0.000 0 0.0 0 0.000 0 0.0 0 0.000

0.300E+04 0.63 lE-02 O.OOOE+OO 0.365E-05 0.650E+04 0.258E-02 0.308E-01 0.303E-01 0.300E+03 0.123E-06 O.OOOE+OO 0.474E-03 0.116E+05 0.908E-02 0.144E+OO 0.145E+OO 0.169E+05 0.407E-02 0.380E+OO 0.369E+OO O. l 99E+05 0.219E+OO O.OOOE+OO O.OOOE+OO O. l 76E+03 0.406E-04 O.OOOE+OO 0.132E-02 0.195E+04 0.220E-03 O.OOOE+OO 0.537E-02 0.565E+05 0.918E-04 0. 730E-02 0.626E-02 O. l 70E+05 0.451E-01 O.OOOE+OO 0. 765E-O 1 0.978E+04 0.127E-02 O.OOOE+OO 0.468E-01 0.471E+05 0.181E+OO O.OOOE+OO O.OOOE+OO 0.443E+05 0.491E-01 0.195E+OO 0.197E+OO 0.294E+05 0.599E-04 0.107E+07 0.326E+05 0.416E+05 0.502E-02 0.629E+04 0.337E+03 0.481E+05 0.555E-03 0.181E+06 0.555E+04 0.622E+05 0.132E-010.107E+040.111E+03 0.492E+05 O. l 75E-02 0.315E+05 O. l 12E+04

11 0.00 1.00 1.26 12.00 19.00 480.00 600.00 1440.00

5760.00 14400.00 28800.00 43200.00 15 19 60 120 480 720 1440 2880 4320

5760 7200 14400 21600 28800 36000 43200 1 EA-TAM-95-05, MHA RG 1.4 SOURCE TERM, 2.2 GPM TO SIRWT

INITIAL ACTIVITIES IN CONTAINMENT

TIME= 0 MIN ACTIVITY IN CONTAINMENT


•

•

•

CTMT. ATM. SUMP ACTIVITY ACTIVITY

ISOTOPE (Ci) (Ci) -------- ---------- ----------Kr-83m 0.7737E+07 Kr-85m 0.1677E+08 Kr-85 0.7739E+06 Kr-87 0.2981E+08 Kr-88 0.4361E+08 Kr-89 0.5143E+08 Xe-131m 0.4542E+06 Xe-133m 0.5042E+07 Xe-133 0.1458E+09 Xe-135m 0.4382E+08 Xe-135 0.2524E+08 Xe-137 0.1214E+09 Xe-138 0.1144E+09 I-131 0.1895E+08 0.3791E+08 I-132 0.2684E+08 0.536~Et08 I-133 0.3102E+08 0.6204E+08 I-134 0.4012E+08 0.8023E+08 I-135 0.3175E+08 0.6351E+08

TIME= 19 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK

1

CTMT.ATM. ACTIVITY

ISOTOPE (Ci) --------

Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132 I-133 I-134 I-135

0.6862E+07 0.1597E+08

0.7739E+06 0.2508E+08 0.4037E+08 0.7958E+06

0.4538E+06 0.5021E+07

0.1455E+09 0.1859E+08

0.2464E+08 0.3897E+07 0.4504E+08

0.1503E+07 0.1936E+07 0.2436E+07 0.2479E+07 0.2438E+07

SUMP ACTIVITY

(Ci)

0.3787E+08 0.4879E+08 0.6139E+08 0.6246E+08 0.6143E+08

SIRWTANK ACTIVITY

(CI)

O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.0000E+OO O.OOOOE+OO



•

•

CTMT. ATM. ACTIVITY

ISOTOPE (Ci)

Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-13lm Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132 I-133 I-134 I-135

0.5297E+07 0.1436E+08

0.7739E+06 0.1728E+08 0.3417E+08 0.9866E+02

0.4531E+06 0.4976E+07

0.1449E+09 0.2922E+07

0.2339E+08 0.2333E+04 0.6026E+07

0.1270E+07 0.1335E+07 0.2017E+07 0.1223E+07 0.1922E+07

SUMP ACTIVITY

(Ci)

0.3776E+08 Q.3970Et08 0.5998E+08 0.3637E+08 0.5717E+08

SIRWTANK ACTIVITY

(CI)

0.1098E+05 0.1157E+OS _ 0.1744E+05 0.1064E+05 0.1663E+OS

TIME = 120 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK

1

CTMT. ATM. ACTIVITY

ISOTOPE (Ci) --------Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132 I-133 I-134 I-135

0.3627E+07 0.1230E+08

0.7738E+06 0.1002E+08 0.2676E+08 0.1893E-03

0.4519E+06 0.4911E+07

0.1441E+09 0.1948E+06

0.2168E+08 0.4481E-01 0.3174E+06

0.1258E+07 0.9817E+06 0.1939E+07 0.5514E+06 0.1721E+07

SUMP. ACTIVITY

(Ci)

0.3761E+08 · 0.2935E+08

0.5799E+08 0.1649E+08 0.5145E+08

SIRWTANK ACTIVITY

(CI)

0.2694E+05 0.2108E+05 0.4155E+05 0.1189E+05 0.3689E+05


EA-TAM-95-05 Sheet 73 Rev# __Q__

•

.,

•

CTMT.ATM. ACTIVITY

ISOTOPE (Ci)

Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-13lm Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132 I-f33 I-134 I-135

0.3736E+06 0.4861E+07

0.7736E+06 0.3806E+06 0.6186E+07 O.OOOOE+OO

0.4453E+06 0.4536E+07

0.1394E+09 0.1713E-Ol

0.1373E+08 O.OOOOE+OO 0.6779E-02

0.1219E+07 0.1593E+06 0.1572E+07 0.4747E+04 0.9079E+06

SUMP ACTIVITY

(Ci)

0.3669E+08 0.4797E+07 0.4734E+08 0.1429E+06 0.2734E+08

SIRWTANK ACTIVITY

(CI)

0.1203E+06 Q.15'7'7E+05 __ 0.1553E+06 0.4719E+03 0.8974E+05


1

CTMT. ATM. ACTIVITY

ISOTOPE (Ci) --------Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-13lm Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132 I-133 I-134 I-135

0.8209E+05 0.2617E+07

0.7735E+06 0.4301E+05 0.2330E+07 O.OOOOE+OO

0.4409E+06 0.4302E+07

O.l364E+09 0.3386E-06

0.1012E+08 O.OOOOE+OO 0.5218E-07

0.1201E+07 0.4770E+05 0.1375E+07 0.2006E+03 0.5965E+06

SUMP ACTIVITY

(Ci)

0.3610E+08 0.1434E+07 0.4135E+08 0.6033E+04 0.1793E+08

SIRWTANK ACTIVITY

(CI)

0.1804E+06 0.7185E+04 0.2067E+06 0.3035E+02 0.8970E+05



•

•

•

CTMT. ATM. ACTIVITY

ISOTOPE (Ci)

Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-13lm Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132

-- -I--133

I-134 I-135

0.8711E+03 0.4085E+06

0.7730E+06 0.6207E+02 0.1245E+06 O.OOOOE+OO

0.4279E+06 0.3671E+07

0.1276E+09 O.OOOOE+OO

0.4061E+07 O.OOOOE+OO O.OOOOE+OO

0.1149E+07 0.1281E+04 0.9214E+06 0.1517E-01 0.1694E+06

SUMP ACTIVITY

(Ci)

0.3436E+08 0.3831E+05 0.2755E+08 0.4535E+OO 0.5064E+07

SIRWTANK ACTIVITY

(CI)

0.3502E+06 0 ._3914 E+03 0.2809E+06 0.4653E-02 0.5165E+05


1

CTMT. ATM . ACTIVITY


0.9813E-01 0.9957E+04

0.7725E+06 0.1293E-03 0.3555E+03 O.OOOOE+OO

0.4034E+06 0.2673E+07

O. l 117E+09 O.OOOOE+OO


0.1054E+07 0.9249E+OO 0.4139E+06 0.8672E-10 0.1366E+05

SUMP ACTIVITY

(Ci)

0.3114E+08 0.2733E+02 0.1223E+08 0.2563E-08 0.4036E+06

SIRWTANK ACTIVITY

(CI)

0.6469E+06 0.5692E+OO 0.2541E+06

0.5359E-10 0.8392E+04


EA-TAM-95-05 Sheet 75 Rev# __Q_

•

•

•

CTMT. ATM. ACTIVITY

ISOTOPE (Ci)


0.1105E-04 0.2427E+03

0.7720E+06 0.2694E-09 0.1015E+Ol O.OOOOE+OO

0.3803E+06 0.1947E+07



0.9663E+06 0.6677E-03

-- -0.1859E+06 0.4957E-18 0.1102E+04

SUMP ACTIVITY

(Ci)

SIRWTANK ACTIVITY

(CI)

0.2822E+08 0.8922E+06 O_. l 950E-Q_l __ 0.6_l80E-03_ 0.5429E+07 O. l 717E+06 0.1448E-16 0.4608E-18 0.3217E+05 0.1018E+04

TIME.= 5760 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK

CTMT. ATM. SUMP SIRWTANK ACTIVITY ACTIVITY ACTIVITY

ISOTOPE (Ci) (Ci) (CI) -------- ---------- ---------- --------Kr-83m 0.1245E-08 Kr-85m 0.5915E+Ol Kr-85 0.7714E+06 Kr-87 0.5614E-15 Kr-88 0.2899E-02 Kr-89 O.OOOOE+OO Xe-131m 0.3585E+06 Xe-133m 0.1418E+07 Xe-133 0.8570E+08 Xe-135m O.OOOOE+OO Xe-135 0.1695E+05 Xe-137 O.OOOOE+OO Xe-138 O.OOOOE+OO I-131 0.8860E+06 0.2556E+08 0.1093E+07 I-132 0.4820E-06 0.1390E-04 0.5958E-06 I-133 0.8352E+05 0.2409E+07 0.1030E+06 I-134 O.OOOOE+OO O.OOOOE+OO 0.0000E+OO I-135 0.8884E+02 0.2563E+04 0.1096E+03

1



•

•

•

CTMT. ATM. ACTIVITY

ISOTOPE (Ci)


-I-133 I-134 I-135

0.1403E-12 0.1442E+OO

0.7709E+06 O.OOOOE+OO 0.8279E-05 O.OOOOE+OO

0.3379E+06 0.1033E+07



0.8124E+06 0.3480E-09 o.3752t+o-5 O.OOOOE+OO 0.7165E+Ol

SUMP ACTIVITY

(Ci)

0.2315E+08 0.9916E-08 -- - --0.1069E+07 O.OOOOE+OO 0.2042E+03

SIRWTANK ACTIVITY

(CI)

0.1254E+07 0.5383E:-09_ 0.5791E+05 O.OOOOE+OO 0.1107E+02


1

CTMT.ATM . ACTIVITY


O.OOOOE+OO 0.1240E-08


0.2516E+06 0.2117E+06


0.2950E+OO O.OOOOE+OO O.OOOOE+OO

0.5266E+06 O.OOOOE+OO 0.6862E+03 O.OOOOE+OO 0.2445E-04

SUMP ACTIVITY

(Ci)


SIRWTANK ACTIVITY

(CI)

0.1631E+07 O.OOOOE+OO 0.2126E+04 O.OOOOE+OO

0.7581E-04



•

•

•

CTMT.ATM. ACTIVITY

ISOTOPE (Ci)



0.7657E+06 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO

0.1873E+06 0.4338E+05

0.1992E+08 · O.OOOOE+OO 0.3190E-04 O.OOOOE+OO O.OOOOE+OO


SUMP ACTIVITY

(Ci)

0.8522E+07 O.OOOOE+_OO 0.3133E+03 O.OOOOE+OO 0.2083E-08

SIRWTANK ACTIVITY

(CI)

0.1591E+07 O.OOOOE+OO ___ _ 0.5851E+02 O.OOOOE+OO

0.3892E-09


1

CTMT. ATM. ACTIVITY

ISOTOPE (Ci)


O.OOOOE+OO O.OOOOE+OO


0.1394E+06 0.8890E+04


0.3450E-08 O.OOOOE+OO O.OOOOE+OO

0.2213E+06 O.OOOOE+OO 0.2296E+OO O.OOOOE+OO 0.2847E-15

SUMP ACTIVITY

(Ci)

0.5130E+07 O.OOOOE+OO 0.5322E+Ol O.OOOOE+OO 0.6601E-14

SIRWTANK ACTIVITY

(CI)

0.1379E+07 O.OOOOE+OO 0.1431E+Ol 0.0000E+OO

0.1776E-14



•

•

CTMT. ATM. ACTIVITY

ISOTOPE (Ci)


-- --I-133 ---

I-134 I-135



0.1038E+06 0'.1822E+04




-o.4-199E-02 O.OOOOE+OO O.OOOOE+OO

SUMP ACTIVITY

(Ci)

0.3069E+07 O.OOOOE+OO o.89-84E-Ol O.OOOOE+OO 0.2079E-19

SIRWTANK ACTIVITY

(CI)

0.1120E+07 O:OOQOE+OQ_



1

CTMT.ATM. ACTIVITY

ISOTOPE (Ci)

Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 1-131 I-13.2 I-133 I-134 I-135



0.7724E+05 0.3734E+03



0.9297E+05 O.OOOOE+OO 0.7680E-04 O.OOOOE+OO O.OOOOE+OO

SUMP ACTIVITY

(Ci)


SIRWTANK ACTIVITY

(CI)



1 TOTAL ACTIVITY OF EACH RADIONUCLIDE RELEASED (Ci) ISOTOPE CTMT ATM ESF ROOMS SIRW TANK

Kr-83m 0.8509E+03


•

•

Kr-85m 0.4459E+04 Kr-85 0.1187E+05 Kr-87 0.2278E+04 Kr-88 0.7433E+04 Kr-89 0.1628E+03 Xe-13lm 0.3411E+04 Xe-133m 0.1011E+05 Xe-133 0.6071E+06 Xe-135m 0.6743E+03 Xe-135 0.1270E+05 Xe-137 0.4658E+03 Xe-138 0.1619E+04 1-131 0.7344E+04 0.6474E+04 0.9566E+02 1-132 0.3164E+03 0.1075E+03 0.5237E-Ol 1-133 0.2073E+04 0.1224E+04 0.4532E+Ol 1-134 0.2415E+03 0.5246E+02 0.9930E-02 1-135 0.8867E+03 0.3891E+03 0.5200E+OO

RESULTANT OFFSITE DOSES FROM THE EVENT (Rem)

CTMT ESF SIRWT ATM LEAKAGE LEAKAGE TOTAL

0-2 Hr SB

Thyroid (inhalation) Thyroid (submersion)

Total Thyroid Dose =

CEDE (inhalation) Whole Body Dose

11.869 3.210 0.272 N/A

12.140 3.210

0.365 0.099 0.287 N/A

0.000 N/A

0.000

0.000 N/A

15.079 0.272

15.351

0.464 0.287

-----------------------------------------------------------------------TEDE (whole body eq) 0.653 0.099 0.000 0.751

0-30 Day LPZ

Thyroid (inhalation) 5.392 3.267 0.022 8.680 Thyroid (submersion) 0.050 N/A N/A 0.050 -----------------------------------------------------------------------Total Thyroid Dose = 5.442 3.267 0.022 8.731

CEDE (inhalation) 0.164 0.099 0.001 0.265 Whole Body Dose 0.053 N/A N/A 0.053 -----------------------------------------------------------------------TEDE (whole body eq) 0.218 0.099 0.001 0.318

TIME AT WHICH DFmax OR THE SPRAY STOP TIME WAS REACHED = 12 MINUTES • 1 ***This is the console file for job JOBI 178(1178). ***

EA-TAM-95-05 Sheet 80 Rev# _Q_

•

•

•

TIME IS 12:41:19 EDT WEDNESDAY 10/11/95 CONNECT= 00:00:04 VIRTCPU= 000:00.09 TOTCPU= 000:00.21 DASD 120 LINKED R/O; R/W BY TAMEYERS; R/O BY VMBATOOl DMSACP723I X (120) R/O DMSACP723I W (121) R/O DMSLI0740I Execution begins ... MHA RUN COMPLETED

TIME IS 12:44:59 EDT WEDNESDAY 10/ 11/95 CONNECT= 00:03:44 VIRTCPU= 003:26.34 TOTCPU= 003:27.44


•

•

•

STAK-MHA DATA A

0.321E+09 0.698E+09 0.322E+08 0.124E+10 0.181E+l0 0.192E+10 0.189E+08 0.210E+09 0.607E+l0 0.179E+l0 0.105E+l0 0.463E+l0 0.465E+l0 0.790E+09 0.112E+l0 0.129E+l0 0.166E+l0 0.132E+10 0.319E+09 0.696E+09 0.322E+08 0.123E+l0 0.181E+l0 0.155E+l0 0.189E+08 0.210E+09 0.607E+l0 0.171E+l0 0.105E+l0 0.386E+l0 0.443E+l0 0.675E+09 0.948E+09 0.llOE+lO 0.140E+10 0.113E+l0 0.309E+09 0.687E+09 0.322E+08 0.117E+l0 0.177E+l0 0.628E+09 0.189E+08 0.210E+09 0.607E+l0 0.137E+10 0.104E+l0 0.178E+l0 0.348E+l0 0.229E+09 0.317E+09 0.373E+09 0.457E+09 0.380E+09 0.292E+09 0.671E+09 0.322E+08 0.108E+l0 0.171E+l0 0.787E+ci8

- 0.189E+08 0.209E+09 0.606E+l0 0.911E+09 0.103E+l0 0.327E+09 0.224E+10 0.659E+08 0.864E+08 0.107E+09 0.114E+09 0.107E+09 0.929E+08 0.389E+09 0.322E+08 0.246E+09 0.759E+09 0.328E+06 0.187E+08 0.199E+09 0.593E+l0 0.372E+08 0.777E+09 0.195E+07 0.830E+08 0.768E+08 0.393E+08 0.111E+09 0.215E+08 0.869E+08 0.109E+08 0.174E+09 0.322E+08 0.966E+07 0.204E+09 O.OOOE+OO 0.185E+08 0.187E+09 0.578E+l0 0.131E+OO 0.531E+09 O.OOOE+OO 0.478E-Ol 0.750E+08 0.739E+07 0.939E+08 0.147E+06 0.506E+08 0.137E+07 0.607E+08 0.322E+08 0.698-E+06 0.448E+08 O.OOOE+OO 0.181E+08 0.168E+09 0.553E+ 10 0.837E-04 0.302E+09 O.OOOE+OO 0.190E-04 0.728E+08 0.126E+07 0.725E+08 0.544E+04 0.238E+08 0.665E+03 0.764E+06 0.161E+08 0.330E+02 0.148E+06 O.OOOE+OO 0.817E+07 0.493E+08 0.219E+10 O.OOOE+OO 0.154E+08 O.OOOE+OO O.OOOE+OO 0.414E+08 0.242E+04 0.143E+08 0.109E-Ol 0.917E+06 0.476E-09 0.553E+Ol 0.160E+08 0.149E-15 0.172E-02 O.OOOE+OO 0.629E+07 0.132E+08 0.123E+l0 O.OOOE+OO 0.322E+05 O.OOOE+OO O.OOOE+OO 0.283E+08 0.455E-06 0.707E+06 O.OOOE+OO 0.241E+03 O.OOOE+OO 0.696E-09 0.160E+08 O.OOOE+OO 0.556E-18 O.OOOE+OO 0.396E+07 0.133E+07 0.446E+09 O.OOOE+OO 0.337E+OO O.OOOE+OO O.OOOE+OO 0.145E+08 O.OOOE+OO 0.352E+04 O.OOOE+OO 0.398E-04 O.OOOE+OO O.OOOE+OO 0.158E+08 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.219E+07 0.560E+05 0.118E+09 O.OOOE+OO 0.394E-08 O.OOOE+OO O.OOOE+OO 0.609E+07 O.OOOE+OO O.ll8E+Ol O.OOOE+OO 0.465E-15


• SIRW-MHA DATA A

O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.bOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.140E+05 0.463E+04 0.195E+05 0.127E+04 0.138E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

______ Q.DDDE±n0_0.3_08E±05_0.3HOE±04_0.385E±05_0.58'.ZE±02-0.207E±05---------------0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

•

•

O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.554E+05 0.747E+03 0.536E+05 0.279E+Ol 0.165E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.142E+06 0.435E+Ol 0.406E+05 0.183E-04 0.197E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.202E+06 0.239E-08 0.431E+04 O.OOOE+OO 0.132E+Ol O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.153E+06 O.OOOE+OO 0.336E+02 O.OOOE+OO 0.367E-06 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.780E+05 O.OOOE+OO 0.145E-01 O.OOOE+OO O.SSSE-17


•

•

•

CRMHA95 LISTING A

MHA source rg 1.4 term, STACK release, 67.6 cfm with 48% margin (100) 0.359E+05

3 0.00 0.35E-03

480.00 0.18E-03 1440.00 0.23E-03

3 0.00

1440.00 5760.00

4

1.0 0.6 0.4

0.00 0. 77E-03 0.26E-03 O.OOE+OO 480.00 0.46E-03 0.15E-03 O.OOE+OO 1440.00 0.29E-03 0.96E-04 O.OOE+OO 5760.00 0.13E-03 0.42E-04 O.OOE+OO

2 0.00 384.2 0.0 0.0 0.0 1.26 100.0 1132.7 _1674_.'f _Q.O

1 0.00 0.000 0.000 0.000 0.000 0.990 0.990

0 11

0.00 1.00 1.26 12.00 19.00 480.00 600.00 1440.00 5760.00 14400.00 28800.00 43200.00

18 1 18

Kr-83m 1 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.648E-05 0.565E-05 O. l 75E-03 O. l 75E-03 0.365E-05

1 0.631E-02 0 0.000 Kr-85m 2 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.123E-02 0.113E-02 0.195E-02 0.185E-02 0.514E-Ol 0.154E-02 0.127E-02

1 0.258E-02 0 0.000 Kr-85 3 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.206E-04 0.308E-04 0.288E-04 0.473E-Ol 0.391E-04 0.231E-04

1 0.123E-06 0 0.000 Kr-87 4 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.555E-02 0.576E-02 0.689E-02 0.627E-02 0.339E+OO 0.10 lE+OO 0.568E-02

1 0.908E-02 0 0.000 Kr-88 5 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.144E-Ol 0.134E-Ol 0.154E-Ol 0.134E-Ol 0.946E-Ol 0.288E-Ol 0.140E-Ol

1 0.407E-02 0 0.000. Kr-89 6 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO o:oooE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

1 0.219E+OO 0 0.000 Xe-13lm 7 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.123E-03 0.360E-03 0.329E-03 0.154E-Ol 0.534E-03 0.191E-03


•

•

•

1 0.406E-04 0 0.000 Xe-133m 8 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.277E-03 0.617E-03 0.565E-03 0.308E-01 0.750E-03 0.382E-03

1 0.220E-03 0 0.000 Xe-133 9 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.432E-03 0.267E-03 0.689E-03 0.627E-03 0.113E-01 0.699E-03 0.336E-03

1 0.918E-04 0 0.000 Xe-135m 10 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.339E-02 0.452E-02 0.421E-02 0.267E-01 0.452E-02 0.362E-02

1 0.451E-01 0 0.000 Xe-135 11 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.185E-02 0.298E-02 0.278E-02 0.658E-01 0.247E-02 0.209E-02

1 0.127E-02 0 0.000 Xe-137 12 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO o:ooo_E+90 O_.OOOE±OO _O.O_OOE+OO

1 0.181E+OO --- 0 0.000 Xe-138 13 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.781E-02 0.812E-02 0.956E-02 0.874E-02 0.164E+OO 0.319E-01 0.780E-02

1 0.491E-01 0 0.000 I-131 14 0.107E+07 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.326E+05 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

2 0.599E-04 0 0.000 I-132 15 0.629E+04 0.999E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.337E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

2 0.502E-02 0 0.000 I-133 16 0.181E+06 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.555E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

2 0.555E-03 0 0.000 I-134 17 0.107E+04 0.518E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.111E+03 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

2 0.132E-Ol 0 0.000 I-135 18 0.315E+05 0.163E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O. l 12E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

2 O. l 75E-02 0 0.000 ECHO OF RELEASE RATES IN THE FOLLOWING ORDER: Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132 I-133 I-134 I-135 0.321E+09 0.698E+09 0.322E+08 0.124E+10 0.181E+l0 0.192E+l0 0.189E+08 0.210E+09 0.607E+l0 0.179E+10 0.105E+l0 0.463E+l0 0.465E+l0 0.790E+09 0.112E+10 0.129E+l0 0.166E+10 0.132E+10 0.319E+09 0.696E+09 0.322E+08 0.123E+10 0.181E+10 0.155E+10 0.189E+08 0.210E+09 0.607E+10 0.171E+10 0.105E+10 0.386E+l0 0.443E+10 0.675E+09 0.948E+09 O.llOE+lO 0.140E+10 0.113E+l0

EA-TAM-95-05 Sheet 85 Rev# ___Q_

•

•

0.309E+09 0.687E+09 0.322E+08 O. ll 7E+ 10 0.177E+ 10 0.628E+09 0.189E+08 0.210E+09 0.607E+10 0.137E+l0 0.104E+10 0.178E+10 0.348E+l0 0.229E+09 0.317E+09 0.373E+09 0.457E+09 0.380E+09 0.292E+09 0.671E+09 0.322E+08 0.108E+10 0.171E+10 0.787E+08 0.189E+08 0.209E+09 0.606E+10 0.911E+09 0.103E+10 0.327E+09 0.224E+l0 0.659E+08 0.864E+08 0.107E+09 0.114E+09 0.107E+09 0.929E+08 0.389E+09 0.322E+08 0.246E+09 0.759E+09 0.328E+06 0.187E+08 0.199E+09 0.593E+10 0.372E+08 0.777E+09 0.195E+07 0.830E+08 0.768E+08 0.393E+08 0.111E+09 0.215E+08 0.869E+08 0.109E+08 0.174E+09 0.322E+08 0.966E+07 0.204E+09 O.OOOE+OO 0.185E+08 0.187E+09 0.578E+ 10 0.13 lE+OO 0.531E+09 O.OOOE+OO 0.478E-01 0.750E+08 0.739E+07 0.9~9E+08 0.147E+06 0.506E+08 0.137E+07 0.607E+08 0.322E+08 0.698E+06 0.448E+08 O.OOOE+OO 0.181E+08 0.168E+09 0.553E+10 0.837E-04 0.302E+09 O.OOOE+OO 0.190E-04 0.728E+08 0.126E+07 0.725E+08 0.544E+04 0.238E+08 0.665E+03 0. 764E+06 0.161E+08 0.330E+02 0.148E+06 O.OOOE+OO 0.817E+07 0.493E+08 0.219E+l0 O.OOOE+OO 0.154E+08 O.OOOE+OO O.OOOE+QO 0.414E+08 0.242E+04 0.143E+08 0.109E-01 0.917E+06 0.476E-09 0.553E+Ol 0.160E+08 0.149E-15 0.172E-02 O.OOOE+OO 0.629E+07 0.132E+08 0.123E+ 10 O.OOOE+OO 0.322E+05 O.OOOE+OO O.OOOE+OO 0.283E+b8 0.45SE.:o6 -0.707E+o6-o:oo(rn+oo 0.241E+03 O.OOOE+OO 0.696E-09 0.160E+08 O.OOOE+OO 0.556E-18 O.OOOE+OO 0.396E+07 0.133E+07 0.446E+09 O.OOOE+OO 0.337E+OO O.OOOE+OO O.OOOE+OO 0.145E+08 O.OOOE+OO 0.352E+04 O.OOOE+OO 0.398E-04 O.OOOE+OO O.OOOE+OO 0.158E+08 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.219E+07 0.560E+05 0.118E+09 O.OOOE+OO 0.394E-08 O.OOOE+OO O.OOOE+OO 0.609E+07 0.000E+OO 0.118E+Ol O.OOOE+OO 0.465E-15 1 MHA source rg 1.4 term, STACK release, max inleak determination

SUMMARY OF CONTROL ROOM OPERATOR DOSES

SUBMERSION TOTAL INHALATION DOSE

(Rem) DOSE DOSE

(Rem) (Rem) ORGAN --------- --------- ---------

Thyroid 22.3279 0.0526 22.3805 Lung 0.0206 0.0490 0.0696 Bone Surface 0.0000 0.0777 0.0777 Bone Marrow 0.0000 0.0698 0.0698 Beta Skin N/A 1.2143 1.2143 Eye Lens N/A 0.1562 0.1562 Whole Body 0.6806 * 0.0542 0.7348 **

* - The whole body inhalation dose is the Committed Effective Dose Equivalent. **- The total value for whole body dose is the Total Effective Dose Equivalent. 1 ***This is the console file for job JOB1419(1419). ***

• TIME rs 10:43:40 EDT WEDNESDAY 11/01/95


•

•

CONNECT= 00:00:08 VIRTCPU= 000:00.09 TOTCPU= 000:00.24 DMSACP723I X (120) R/O DMSLI0740I Execution begins ... CONDOSE RUN COMPLETED

TIME IS 11:01:26 EDT WEDNESDAY 11/01/95 CONNECT= 00:17:54 VIRTCPU= 004:20.26 TOTCPU= 004:21.95


•

•

•

CRMHA95A LISTING A

EA-TAM-95-05,RG 1.4 source, SIRWT release, 67.6 with 48% margin (100) 0.359E+05

3 0.00 0.35E-03

480.00 0.18E-03 1440.00 0.23E-03

3 0.00

1440.00 5760.00

4

1.0 0.6 0.4

0.00 0.13E-01 0.63E-03 O.OOE+OO 480.00 0. 78E-02 0.37E-03 O.OOE+OO 1440.00 0.50E-02 0.24E-03 O.OOE+OO 5760.00 0.22E-02 0. l lE-03 O.OOE+OO

2 0.00 384.2 0.0 0.0 0.0 1.26 100.0 1132.7 1674.4 0.0 - 1

0.00 0.000 0.000 0.000 0.000 0.990 0.990 0 11

0.00 1.00 1.26 12.00 19.00 480.00 600.00 1440.00 --5760.00 14400.00 28800.00 43200.00

18 1 18


1 0.631E-02 0 0.000 Kr-85m 2 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.123E-02 0.113E-02 0.195E-02 0.185E-02 0.514E-Ol 0.154E-02 0.127E-02



1 0.908E-02 0 0.000 Kr-88 5 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.144E-Ol 0.134E-Ol 0.154E-Ol 0.134E-Ol 0.946E-Ol 0.288E-Ol 0.140E-Ol

1 0.407E-02 0 0.000 Kr-89 6 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

1 0.219E+OO 0 0.000 Xe-13lm 7 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.123E-03 0.360E-03 0.329E-03 0.154E-Ol 0.534E-03 0.191E-03


•

•

•

1 0.406E-04 0 0.000 Xe-133m 8 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.277E-03 0.617E-03 0.565E-03 0.308E-01 0.750E-03 0.382E-03

1 0.220E-03 0 0.000 Xe-133 9 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.432E-03 0.267E-03 0.689E-03 0.627E-03 0.113E-01 0.699E-03 0.336E-03

1 0.918E-04 0 0.000 Xe-135m 10 O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.339E-02 0.452E-02 0.421E-02 0.267E-01 0.452E-02 0.362E-02

1 0.451E-01 0 0.000 Xe-135 11 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.185E-02 0.298E-02 0.278E-02 0.658E-01 0.247E-02 0.209E-02

1 0.127E-02 0 0.000 Xe-137 12 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO o.009_E+OO O.QOOE+OO O.OOOE+no O.OOOE+OO -

10.lSlE+OO 0 0.000 Xe-138 13 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.781E-02 0.812E-02 0.956E-02 0.874E-02 0.164E+OO 0.319E-Ol 0.780E-02


2 0.599E-04 0 0.000 I-132 15 0.629E+04 0.999E+03 O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.337E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

2 0.502E-02 0 0.000 I-133 16 0.181E+06 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0 .. 555E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

2 0.555E-03 0 0.000 I-134 17 0.107E+04 0.518E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.lllE+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO


2 O. l 75E-02 0 0.000 ECHO OF RELEASE RATES IN THE FOLLOWING ORDER: Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-13lm Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132 I-133 I-134 I-135

O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO


•

•

O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.140E+05 0.463E+04 0.195E+05 0.127E+04 0.138E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.308E+05 0.300E+04 0.385E+05 0.587E+02 0.207E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.554E+05 0.747E+03 0.536E+05 0.279E+Ol 0.165E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.142E+06 0.435E+Ol 0.406E+05 0.183E-04 0.197E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

_ Q.OOOE+QO O.OOOE+QO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.202E+06 0.239E-08 0.431E+04 O.OOOE+OO 0.132E+Ol O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.153E+06 O.OOOE+OO 0.336E+02 O.OOOE+OO 0.367E-06 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.780E+05 O.OOOE+OO 0.145E-01 0.000E+OO 0.555E-17 1 EA-TAM-95-05, MHA RG 1.4 source, SIRWT release, max inleak detrmination



(Rem) DOSE DOSE

(Rem) (Rem) ORGAN --------- --------- ---------


* - The whole body inhalation dose is the Committed Effective Dose Equivalent. **- The total value for whole body dose is the Total Effective Dose Equivalent. 1*** This is the console file for job JOB1420(1420). ***

• TIME IS 10:44:00 EDT WEDNESDAY 11/01/95

EA-TAM-95-05 Sheet 90 Rev# ____Q_

•

• ' 1.

f

•




•

•

LOCA95A LISTING A

EA-TAM-95-05, LOCA APPENDIX K SOURCE TERM, 2.2 GPM TO SIRWT 1 43200

2580.6 0.10 41498.2 20.0 10.0 10.0 91.0 0.0 9.0 2.0 58.2 10.0 2.0 40151.1 554.0 0.30E-03

0.35E-03 0.18E-03 0.23E-03 0.15E-03 0.llE-04 0.69E-05 0.26E-05 0.62E-06

4.43 0.443 1 21.300 0 0.000 0 0.000 0 0.000 0 0.000

32.51 600 19 0.2 19 2.200 0 -o.o ff --0.-00-0 0 0.0 0 0.000 0 0.0 0 0.000

0.300E+04 0.631 E-02 O.OOOE+OO 0.365E-05 0.650E+04 0.258E-02 0.308E-01 0.303E-01 0.300E+03 0.123E-06 O.OOOE+OO 0.474E-03 0.116E+05 0.908E-02 0.144E+OO 0.145E+OO 0.169E+05 0.407E-02 0.380E+OO 0.369E+OO 0.199E+05 0.219E+OO O.OOOE+OO O.OOOE+OO O. l 76E+03 0.406E-04 O.OOOE+OO 0.132E-02 0.195E+04 0.220E-03 O.OOOE+OO 0.537E-02 0.565E+05 0.918E-04 0. 730E-02 0.626E-02 0.170E+05 0.451E-01O.OOOE+OO0.765E-01 0.978E+04 0.127E-02 O.OOOE+OO 0.468E-01 0.471E+05 0.181E+OO O.OOOE+OO O.OOOE+OO 0.443E+05 0.491E-Ol 0.195E+OO 0.197E+OO 0.294E+05 0.599E-04 0.107E+07 0.326E+05 0.416E+05 0.502E-02 0.629E+04 0.337E+03 0.481E+05 0.555E-03 0.181E+06 0.555E+04 0.622E+05 0.132E-010.107E+040.111E+03 0.492E+05 O. l 75E-02 0.315E+05O.l12E+04

11 0.00 1.00 1.26 12.00 19.00 480.00 600.00 1440.00

5760.00 14400.00 28800.00 43200.00 15 19 60 120 480 720 1440 2880 4320

5760 7200 14400 21600 28800 36000 43200 1 EA-TAM-95-05, LOCA APPENDIX K SOURCE TERM, 2.2 GPM TO SIRWT

INITIAL ACTIVITIES IN CONTAINMENT

TIME= 0 MIN ACTIVI1Y IN CONTAINMENT


•

• , /

•

CTMT. ATM. SUMP ACTIVITY ACTIVITY

ISOTOPE (Ci) (Ci) -------- ---------- ----------Kr-83m 0.1547E+07 Kr-85m 0.3354E+07 Kr-85 0.1548E+06 Kr-87 0.5961E+07 Kr-88 0.8722E+07 Kr-89 0.1029E+08 Xe-131m 0.9084E+05 Xe-133m 0.1008E+07 Xe-133 0.2915E+08 Xe-135m 0.8764E+07 Xe-135 0.5048E+07 Xe-137 0.2428E+08 Xe-138 0.2288E+08 1-131 0.7582E+07 0.7582E+07 I-132 0.1074E+08 0.1074E+08 I-133 0.1241E+08 0.124IE+08 I-134 0.1605E+08 0.1605E+08 I-135 0.1270E+08 0.1270E+08


1

CTMT.ATM . ACTIVITY

ISOTOPE (Ci)


0.1372E+07 0.3193E+07

0.1548E+06 0.5016E+07 0.8074E+07 0.1592E+06

0.9077E+05 0.1004E+07

0.2910E+08 0.3718E+07

0.4928E+07 0.7794E+06 0.9008E+07

0.8795E+06 O.ll33E+07 0.1426E+07 0.1451E+07 0.1427E+07

SUMP ACTIVITY

(Ci)

0.7573E+07 0.9758E+07 0.1228E+08 0.1249E+08 0.1229E+08

SIRWTANK ACTIVITY

(CI)

O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO



•

I-

•

•

CTMT.ATM. ACTIVITY


0.1059E+07 0.2873E+07

0.1548E+06 0.3456E+07 0.6833E+07 0.1973E+02

0.9061E+05 0.9952E+06

0.2899E+08 0.5844E+06

0.4678E+07 0.4665E+03 0.1205E+07

0.8774E+06 0.9223E+06 0;1394E+07 0.8451E+06 0.1328E+07

SUMP ACTIVITY

(Ci)

0.7552E+07 0.7939E+07 0.1200E+08 0.7274E+07 0.1143E+08

SIRWTANK ACTIVITY

(CI)

0.2195E+04 0.2313E+04 ·a:348BE+04 0.2128E+04 0.3326E+04


1

CTMT.ATM. ACTIVITY


0.7253E+06 0.2461E+Q7

0.1548E+06 0.2004E+07 0.5353E+07 0.3785E-04

0.9039E+05 0.9822E+06

0.2883E+08 0.3897E+05

0.4335E+07 0.8962E-02 0.6348E+05

0.8742E+06 0.6823E+06 0.1348E+07 0.3832E+06 0.1196E+07

SUMP ACTIVITY

(Ci)

0.7521E+07 0.5870E+07 0.1160E+08 0.3297E+07 0.1029E+08

SIRWTANK ACTIVITY

(CI)

0.5388E+04 0.4216E+04 0.8311E+04 0.2378E+04 0.7378E+04



•

•

•

CTMT.ATM. ACTIVITY

ISOTOPE (Ci)

Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-13lm Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 1-131 1-132

. 1-133 1-134 I-135

0.7472E+05 0.9722E+06

0.1547E+06 0.7612E+05 0.1237E+07 O.OOOOE+OO

0.8905E+05 0.9072E+06

0.2788E+08 0.3425E-02

0.2746E+07 O.OOOOE+OO 0.1356E-02

0.8553E+06 0.1118E+06 0.1103E+07 0.3332E+04 0.6372E+06

SUMP ACTIVITY

(Ci)

0.7339E+07 0.9595E+06 0.9467E+07 0.2859E+05 0.5468E+07

SIRWTANK ACTIVITY

(CI)

0.2407E+05 0.3155E+04 0.3106E+o5 0.9438E+02 O. l 795E+05 .


1



0.1642E+05 0.5235E+06

0.1547E+06 0.8602E+04 0.4660E+06 O.OOOOE+OO

0.8817E+05 0.8605E+06

0.2727E+08 0.6771E-07

0.202SE+07 O.OOOOE+OO 0.1044E-07

0.8430E+06 0.3349E+05 0.9656E+06 0.1409E+03 0.4188E+06

SUMP ACTIVITY

(Ci)

0.7219E+07 0.2868E+06 0.8269E+07 0.1207E+04 0.3587E+07

SIRWTANK ACTIVITY

(CI)

0.3608E+05 0.1437E+04 0.4133E+05 0.6069E+Ol 0.1794E+05



•

•

•

CTMT.ATM. SUMP SIRWTANK ACTIVITY ACTIVITY ACTIVITY

ISOTOPE (Ci) (Ci) (CI) -------- ---------- ---------- --------Kr-83m 0.1742E+03 Kr-85m 0.8170E+05 Kr-85 0.1546E+06 Kr-87 0.1241E+02 Kr-88 0.2490E+05 Kr-89 O.OOOOE+OO Xe-131m 0.8559E+05 Xe-133m 0.7341E+06 Xe-133 0.2552E+08 Xe-135m O.OOOOE+OO Xe-135 0.8123E+06 Xe-137 O.OOOOE+OO Xe-138 O.OOOOE+OO I-131 0.8070E+06 0.6873E+07 0.7005E+05 I-132 0.8996E+03 0.7661E+04 0. 7828E+0_2 I-133 0.64 70E+Ofr 0.5510E+07 0:56-17E+o5 I-134 0.1065E-01 0.9070E-Ol 0.9305E-03 I-135 0.1189E+06 0.1013E+07 0.1033E+05


1

CTMT.ATM. ACTIVITY

ISOTOPE (Ci)


0.1963E-01 0.1991E+04

0.1545E+06 0.2586E-04 0.7110E+02 O.OOOOE+OO

0.8068E+05 0.5347E+06



0.7400E+06 0.6494E+OO 0.2906E+06 0.6089E-10 0.9591E+04

SUMP ACTIVITY

(Ci)

0.6228E+07 0.5466E+Ol 0.2446E+07 0.5125E-09 0.8072E+05

SIRWTANK ACTIVITY

(CI)

0.1294E+06 0.1138E+OO 0.5083E+05

0.1072E-10 0.1678E+04



•

•

•

CTMT. ATM. ACTIVITY

ISOTOPE (Ci)

Kr-83m Kr-85m Kr-~5 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe~l38 I-131 I-132 I-133 I-134 I-135

0.2211E-05 0.4854E+02

0.1544E+06 0.5389E-10 0.2030E+OO O.OOOOE+OO

0.7606E+05 0.3894E+06



0.6785E+06 0.4688E-03 0.1306E+06 0.3482E-18 0.7735E+03

SUMP ACTIVITY

(Ci)

0.5643E+07 0.3899E-02 0.1086E+07 0.2896E-17 0.6433E+04

SIRWTANK ACTIVITY

(CI)

0.1784E+06 0.1236E-03 0.3434E+05

0.9217E-19 0.2036E+03


1


ISOTOPE (Ci) --------Kr-83m Kr-85m Kr-:85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132 I-133 I-134 I-135

0.2491E-09 0.1183E+Ol

0.1543E+06 0.1123E-15 0.5798E-03 O.OOOOE+OO

0.7170E+05 0.2836E+06

O.l 714E+08. O.OOOOE+OO


0.6222E+06 0.3384E-06 0.5864E+05 O.OOOOE+OO 0.6238E+02

SUMP ACTIVITY

(Ci)

0.5112E+07 0.2781E-05 0.4819E+06 0.0000E+OO 0.5126E+03

SIRWTANK ACTIVITY

(CI)

0.2185E+06 0.1192E-06 0.2060E+05 O.OOOOE+OO 0.2193E+02



••

•

•

CTMT.ATM. SUMP SIRWTANK ACTIVITY ACTIVITY ACTIVITY

ISOTOPE (Ci) (Ci) (CI) -------- ---------- ---------- --------Kr-83m 0.2806E-13 Kr-85m 0.2883E-Ol Kr-85 0.1542E+06 Kr-87 0.0000E+OO Kr-88 0.1656E-05 Kr-89 O.OOOOE+OO Xe-13lm 0.6759E+05 Xe-l33m 0.2066E+06 Xe-133 0.1501E+08 Xe-135m O.OOOOE+OO. Xe-135 0.5456E+03 Xe-137 O.OOOOE+OO Xe-138 O.OOOOE+OO I-131 0.5705E+06 0.4630E+07 0.2507E+06 I-132 0.2443E-09 0.1983E-08 0.1077E-09 I-133 0.2634E+05 0.2138E+06 0.1158E+05 I-134 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO I-135 0.5031E+Ol 0.4084E+02 0.2213E+Ol


1

CTMT.ATM. ACTIVITY

ISOTOPE (Ci) --------Kr-83m Kr:..8sm Kr-85-Kr-87 Kr-88 Kr-89 Xe-13lm Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 1-132 I-133 I-134 I-135



0.5031E+OS 0.4233E+05


0.5900E-Ol O.OOOOE+OO · O.OOOOE+OO

0.3698E+06 O.OOOOE+OO 0.4818E+03 O.OOOOE+OO O. l 717E-04

SUMP ACTIVITY

(Ci)


SIRWTANK ACTIVITY

(CI)

0.3263E+06 O.OOOOE+OO 0.4253E+03 O.OOOOE+OO

0.1516E-04



•

•

•

CTMT. ATM. SUMP SIRWTANK ACTIVITY ACTIVITY ACTIVITY

ISOTOPE (Ci) (Ci) (CI) -------- ---------- ---------- --------Kr-83m O.OOOOE+OO Kr-85m 0.2133E-17 Kr-85 0.1531E+06 Kr-87 0.0000E+OO Kr-88 0.0000E+OO Kr-89 0.0000E+OO Xe-13lm 0.3745E+05 Xe-133m 0.8676E+04 Xe-133 0.3984E+07 Xe-135m O.OOOOE+OO Xe-135 0.6381E-05 Xe-137 O.OOOOE+OO Xe-138 O.OOOOE+OO I-131 0.2397E+06 0.1704E+07 0.3182E+06 I-132 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO I-133 0.8813E+Ol 0.6267E+02 O.ll 70E+02 I-134 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO I-135 0.5859E-10 0.4166E-09 0.7784E-10


1

CTMT. ATM. ACTIVITY



0.1526E+06 0.0000E+OO 0.0000E+OO O.OOOOE+OO

0.2788E+05 0.1778E+04



0.1554E+06 O.OOOOE+OO 0.1612E+OO O.OOOOE+OO 0.1999E-15

SUMP ACTIVITY

(Ci)

SIRWTANK ACTIVITY

(CI)

0.1026E+07 O.OOOOE+OO 0.1064E+Ol 0.0000E+OO 0.1320E-14

0.2757E+06 O.OOOOE+OO 0.2862E+OO O.OOOOE+OO

0.3551E-15



•

•

•

CTMT.ATM. ACTIVITY

ISOTOPE (Ci)


0.0000E+OO O.OOOOE+OO


0.2075E+05 0.3644E+03



0.1007E+06 O.OOOOE+OO 0.2948E-02 0.0000E+OO O.OOOOE+OO

SUMP ACTIVITY

(Ci)

SIRWTANK ACTIVITY

(CI)

0.6137E+06 O.OOOOE+OO O. l 797E-Ol O.OOOOE+OO 0.0000E+OO


0.6559E-02 . O.OOOOE+OO O.OOOOE+OO


1

CTMT.ATM. ACTIVITY

ISOTOPE (Ci)



0.1516E+06 0.0000E+OO 0.0000E+OO O.OOOOE+OO

0.1545E+05 0.7467E+02



0.6528E+05 O.OOOOE+OO 0.5392E-04 0.0000E+OO 0.0000E+OO

SUMP ACTIVITY

(Ci)

SIRWTANK ACTIVITY

(CI)




1 TOTAL ACTIVITY OF EACH RADIONUCLIDE RELEASED (Ci) ISOTOPE CTMT ATM ESF ROOMS SIRW TANK .

Kr-83m 0.1702E+03


•

• ./

•

Kr-85m 0.8918E+03 Kr-85 0.2375E+04 Kr-87 0.4557E+03 Kr-88 0.1487E+04 Kr-89 0.3256E+02 Xe-13lm 0.6822E+03 Xe-133m 0.2022E+04 Xe-133 0.1214E+06 Xe-135m 0.1349E+03 Xe-135 0.2541E+04 Xe-137 0.9317E+02 Xe-138 0.3239E+03 I-131 0.5137E+04 0.1295E+04 0.1913E+02 I-132 0.1952E+03 0.2151E+02 0.1047E-Ol I-133 0.1423E+04 0.2447E+03 0.9064E+OO I-134 0.1318E+03 0.1049E+02 0.1986E-02 I-135 0.5895E+03 0.7781E+02 0.1040E+OO

RESULTANT OFFSITE DOSES FROM THE EVENT (Rem)

CTMT ESF SIRWT ATM LEAKAGE LEAKAGE TOTAL

0-2 Hr SB




TEDE (whole body eq)

0-30 Day LPZ




6.833 0.642 0.054 N/A

6.888 0.642

0.210 0.020 0.057 N/A

0.268 0.020

3.676 0.653 0.010 N/A

3.687 0.653

0.112 0.020 0.011 N/A

0.000 N/A

0.000

0.000 N/A

0.000

0.004 N/A

0.004

0.000 N/A

7.475 0.054

7.530

0.230 0.057

0.287

4.334 0.010

4.344

0.132 0.011

-----------------------------------------------------------------------TEDE (whole body eq) 0.123 0.020 0.000 0.143

TIME AT WHICH DFmax OR THE SPRAY STOP TIME WAS REACHED= 12 MINUTES l*** This is the console file for job JOB1202(1202). ***


•

•

TIME IS 07:52:25 EDT THURSDAY 10/12/95 CONNECT= 00:00:04 VIRTCPU= 000:00.09 TOTCPU= 000:00.23 DASO 120 LINKED R/O; R/W BY TAMEYERS; R/O BY 002 USERS DMSACP723I X (120) R/O DMSACP723I W (121) R/O DMSLI0740I Execution begins ... MHA RUN COMPLETED

TIME IS 08:00:05 EDT THURSDAY 10/ 12/95 CONNECT= 00:07:43 VIRTCPU= 003:19.82 TOTCPU= 003:21.83


•

•

STAK-LOC DATA A

0.643E+08 0.140E+09 0.645E+07 0.247E+09 0.363E+09 0.385E+09 0.378E+07 0.420E+08 0.121E+l0 0.357E+09 0.210E+09 0.926E+09 0.930E+09 0.316E+09 0.446E+09 0.517E+09 0.664E+09 0.529E+09 0.639E+08 0.139E+09 0.645E+07 0.245E+09 0.361E+09 0.309E+09 0.378E+07 0.420E+08 0.121E+l0 0.341E+09 0.210E+09 0.772E+09 0.886E+09 0.270E+09 0.380E+09 0.442E+09 0.561E+09 0.452E+09 0.618E+08 0.137E+09 0.645E+07 0.234E+09 0.354E+09 0.126E+09 0.378E+07 0.420E+08 0.121E+10 0.274E+09 0.209E+09 0.356E+09 0.697E+09 0.965E+08 0.134E+09 0.158E+09 0.192E+09 0.160E+09 0.585E+08 0.134E+09 0.645E+07 0.216E+09 0.341E+09 0.157E+08 0.378E+07 0.419E+08 0.121E+l0 0.182E+09 0.206E+09 0.654E+08 0.448E+09 0.367E+08 0.481E+08 0.595E+08 0.633E+08 0.598E+08 0.186E+08 0.778E+08 0.645E+07 0.491E+08 0.152E+09 0.656E+05 0.375E+07 0.398E+08 0.119E+10 0.745E+07 0.155E+09 0.389E+06 0.166E+08 0.411E+08 0.209E+08 0.596E+08 0.113E+08 0.464E+08 0.218E+07 0.348E+08 0.645E+07 0.193E+07 0.408E+08 O.OOOE+OO 0.370E+07 0.373E+08 0.116E+l0 0.262E~Ol 0.106E+09 O.OOOE+OO 0.957E-02 0.404E+08 0.398E+07 0.506E+08 0.793E+05 0.272E+08 0.274E+06 0.121E+08 0.644E+07 0.140E+06 0.895E+07 O.OOOE+OO 0.363E+07 0.336E+08 0.11 lE+lO 0.167E-04 0.604E+08 O.OOOE+OO 0.380E-05 0.392E+08 0.677E+06 0.391E+08 0.293E+04 0.128E+08 0.133E+03 0.153E+06 0.322E+07 0.659E+Ol 0.295E+05 O.OOOE+OO 0.163E+07 0.987E+07 0.439E+09 O.OOOE+OO 0.308E+07 O.OOOE+OO O.OOOE+OO 0.189E+08 0.110E+04 0.651E+07 0.497E-02 0.418E+06 0.951E-10 O.lllE+Ol 0.321E+07 0.298E-16 0.344E-03 O.OOOE+OO 0.126E+07 0.264E+07 0.246E+09 O.OOOE+OO 0.644E+04 O.OOOE+OO O.OOOE+OO 0.129E+08 0.207E-06 0.322E+06 0.000E+OO O. l 10E+03 O.OOOE+OQ 0.139E-09 0.319E+07 O.OOOE+OO 0.108E-18 O.OOOE+OO 0.792E+06 0.267E+06 0.892E+08 O.OOOE+OO 0.673E-Ol O.OOOE+OO O.OOOE+OO 0.658E+07 O.OOOE+OO 0.160E+04 0.000E+OO 0.18 lE-04 O.OOOE+OO O.OOOE+OO 0.3 l 7E+07 O.OOOE+OO 0.000E+OO O.OOOE+OO 0.439E+06 0.112E+05 0.237E+08 O.OOOE+OO 0.787E-09 O.OOOE+OO O.OOOE+OO 0.277E+07 O.OOOE+OO 0.536E+OO O.OOOE+OO 0.211E-15

EA-TAM-95-05 Sheet I 03 Rev# 0

•

•

SIRW-LOC DATA A

O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO. 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.280E+04 0.927E+03 0.391E+04 0.254E+03 0.276E+04 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.615E+04 0.600E+03 0.770E+04 0.117E+02 0.413E+04 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.lllE+OS 0.149E+03 0.107E+OS 0.558E+OO 0.329E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.284E+OS 0.869E+OO 0.813E+04 0.365E-05 0.394E+03 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.405E+OS 0.478E-09 0.862E+03 O.OOOE+OO 0.264E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.305E+OS O.OOOE+OO 0.672E+Ol O.OOOE+OO 0.735E-07 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.156E+OS O.OOOE+OO 0.29 lE-02 O.OOOE+OO 0.102E-17


•

•

•

CRLOCA95 LISTING A

EA-TAM-95-05, LOCA APP K src, STACK rr, 67.6 cfm with 48% margin(lOO) 0.359E+05

3 0.00 0.35E-03

480.00 0.18E-03 1440.00 0.23E-03

3 0.00

1440.00 5760.00

4

1.0 0.6 0.4

0.00 0.77E-03 0.26E-03 O.OOE+OO 480.00 0.46E-03 0.15E-03 0.00E+OO 1440.00 0.29E-03 0.96E-04 O.OOE+OO 5760.00 0.13E-03 0.42E-04 O.OOE+OO

2 0.00 384.2 0.0 0.0 0.0 1.26 100.0 1132.7 1674.4 0.0

1 0.00 0.000 0.000 0.000 0.000 0.990 0.990

0 11

0.00 5760.00

18 18

1.00 1.26 12.00 19.00 480.00 600.00 1440.00 14400.00 28800.00 43200.00

1

Kr-83m 1 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.648E-05 0.565E-05 O. l 75E-03 O. l 75E-03 0.365E-05

1 0.63 lE-02 0 0.000 Kr-85m 2 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.123E-02 0.113E-02 0.195E-02 0.185E-02 0.514E-01 0.154E-02 0.127E-02

1 0.258E-02 0 0.000 Kr-85 3 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.206E-04 0.308E-04 0.288E-04 0.473E-01 0.391E-04 0.231E-04

1 0.123E-06 0 0.000 Kr-87 4 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.555E-02 0.576E-02 0.689E-02 0.627E-02 0.339E+OO O.lOlE+OO 0.568E-02

1 0.908E-02 0 0.000 Kr-88 5 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.144E-01 0.134E-01 0.154E-01 0.134E-01 0.946E-01 0.288E-01 0.140E-01

. 1 0.407E-02 0 0.000 Kr-89 6 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

1 0.219E+OO 0 0.000 Xe-131m 7 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.123E-03 0.360E-03 0.329E-03 0.154E-01 0.534E-03 0.19 lE-03


•

•

1 0.406E-04 0 0.000 Xe-133m 8 O.OOOE+OG O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.277E-03 0.617E-03 0.565E-03 0.308E-01 0.750E-03 0.382E-03

1 0.220E-03 0. 0.000 Xe-133 9 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.432E-03 0.267E-03 0.689E-03 0.627E-03 O. l 13E-O 1 0.699E-03 0.336E-03

1 0.918E-04 0 0.000 Xe-135m 10 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.339E-02 0.452E-02 0.421E-02 0.267E-01 0.452E-02 0.362E-02

1 0.451E-01 0 0.000 Xe-135 11 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.185E-02 0.298E-02 0.278E-02 0.658E-01 0.247E-02 0.209E-02

1 0.127E-02 0 0.000 Xe-137 12 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO

l 0.181E+OO 0 0.000 Xe-138 13 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.781E-02 0.812E-02 0.956E-02 0.874E-02 0.164E+OO 0.319E-01 0.780E-02

1 0.491E-01 0 0.000 I-131 14 0.107E+07 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.326E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO

2 0.599E-04 0 0.000 ·I-132 15 0~629E+04 0.999E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.337E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO



2 0.132E-01 0 0.000 I-135 18 0.315E+05 0.163E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.112E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

2 O. l 75E-02 0 0.000 ECHO OF RELEASE RATES IN THE FOLLOWING ORDER: Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132 1-133 I-134 I-135 0.643E+08 0.140E+09 0.645E+07 0.247E+09 0.363E+09 0.385E+09 0.378E+07 0.420E+08 0.121E+10 0.357E+09 0.210E+09 0.926E+09 0.930E+09 0.316E+09 0.446E+09 0.517E+09 0.664E+09 0.529E+09 0.639E+08 0.139E+09 0.645E+07 0.245E+09 0.361E+09 0.309E+09 0.378E+07 0.420E+08 0.121E+10 0.341E+09 0.210E+09 0.772E+09 0.886E+09 0.270E+09 0.380E+09 0.442E+09 0.561E+09 0.452E+09


•

•

0.618E+08 0.137E+09 0.645E+07 0.234E+09 0.354E+09 0.126E+09 0.378E+07 0.420E+08 0.121E+10 0.274E+09 0.209E+09 0.356E+09 0.697E+09 0.965E+08 0.134E+09 0.158E+09 0.192E+09 0.160E+09 0.585E+08 0.134E+09 0.645E+07 0.216E+09 0.341E+09 0.157E+08 0.378E+07 0.419E+08 0.121E+10 0.182E+09 0.206E+09 0.654E+08 0.448E+09 0.367E+08 0.481E+08 0.595E+08 0.633E+08 0.598E+08 0.186E+08 0.778E+08 0.645E+07 0.491E+08 0.152E+09 0.656E+05 0.375E+07 0.398E+08 0.119E+10 0.745E+07 0.155E+09 0.389E+06 0.166E+08 0.411E+08 0.209E+08 0.596E+08 0.113E+08 0.464E+08 0.218E+07 0.348E+08 0.645E+07 0.193E+07. 0.408E+08 O.OOOE+OO 0.370E+07 0.373E+08 0.116E+10 0.262E-01 0.106E+09 O.OOOE+OO 0.957E-02 0.404E+08 0.398E+07 0.506E+08 0.793E+05 0.272E+08 0.274E+06 0.121E+08 0.644E+07 0.140E+06 0.895E+07 O.OOOE+OO 0.363E+07 0.336E+08 0.11lE+10 0.167E-04 0.604E+08 O.OOOE+OO 0.380E-05 0.392E+08 0.677E+06 0.391 E+08 0.293E+04 0.128E+08 0.133E+03 0.153E+06 0.322E+07 0.659E+Ol 0.295E+05 O.OOOE+OO 0.163E+07 0.987E+07 0.439E+09 O.OOOE+OO 0.308E+07 O.OOOE+OO O.OOOE+OO 0.189E+08 0.110E+04 0.651E+07 0.497E-02 0.418E+06 0.951E-10 0.1 llE+Ol 0.321E+07 0.298E-16 0.344E-03 O.OOOE+OO 0.126E+07 0.264E+07 0.246E+09 O.OOOE+OO 0.644E+04 O.OOOE+OO O.OOOE+OO 0.129E+08 0.207E-06 0.322E+06 O.OOOE+OO O. l 10E+03 O.OOOE+OO 0.139E-09 0.319E+07 O.OOOE+OO 0.108E-18 O.OOOE+OO 0.792E+06 0.267E+06 0.892E+08 O.OOOE+OO 0.673E-01 O.OOOE+OO O.OOOE+OO 0.658E+07 O.OOOE+OO 0.160E+04 O.OOOE+OO 0.181E-04 O.OOOE+OO O.OOOE+OO 0.317E+07 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.439E+06 0.112E+05 0.237E+08 O.OOOE+OO 0.787E-09 O.OOOE+OO O.OOOE+OO 0.277E+07 O.OOOE+OO 0.536E+OO O.OOOE+OO 0.211E-15 1 EA-TAM-95-05, LOCA APP K src, STACK rr, 67.6 cfrn with 48% margin(lOO)


ORGAN Thyroid Lung

INHALATION DOSE

(Rem) ---------11.0890 0.0104

SUBMERSION TOTAL DOSE DOSE

(Rem) (Rem) --------- ---------

0.0105 11.0995 0.0098 0.0202

Bone Surface 0.0000 0.0156 0.0156 Bone Marrow 0.0000 0.0140 0.0140 Beta Skin N/A 0.2431 0.2431 Eye Lens N/A 0.0312 0.0312 Whole Body 0.3381 * 0.0109 0.3489 **

* - The whole body inhalation dose is the Committed Effective Dose Equivalent. **- The total value for whole body dose is the Total Effective Dose Equivalent. l*** This is the console file for job JOB1439(1439). ***

TIME IS 09:01:33 EDT WEDNESDAY 11/ 15/95


•

•

CONNECT= 00:00:04 VIRTCPU= 000:00.09 TOTCPU= 000:00.21 DMSACP723I X (120) R/O DMSLI0740l Execution begins ... CONDOSE RUN COMPLETED



•

•

•

CRLOC95A LISTING A

EA-TAM-95-05, LOCA APP K src, SIRWT rr, 67.6 cfm with 48% margin (100) 0.359E+05

3 0.00 0.35E-03

480.00 0.18E-03 1440.00 0.23E-03

3 0.00 1.0

1440.00 0.6 5760.00 0.4

4 0.00 0.13E-01 0.63E-03 O.OOE+OO

480.00 0.78E-02 0.37E-03 O.OOE+OO 1440.00 0.50E-02 0.24E-03 O.OOE+OO 5760.00 0.22E-02 O. l lE-03 O.OOE+OO

2 0.00 384.2 0.0 0.0 0.0 1.26 100.0 1132.7 1674.4 0.0

1 0.00 0.000 0.000 0.000 0.000 0.990 0.990

0 11

0.00 5760.00

18 18

1.00 1.26 12.00 19.00 480.00 600.00 1440.00 14400.00 28800.00 43200.00

1


1 0.63 lE-02 0 0.000 Kr-85m 2 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.123E-02 0.113E-02 0.195E-02 0.185E-02 0.514E-Ol 0.154E-02 0.127E-02



1 0.908E-02 0 0.000 Kr-88 5 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.144E-01 0.134E-01 0.154E-01 0.134E-01 0.946E-01 0.288E-01 0.140E-01

1 0.407E-02 0 0.000 Kr-89 6 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

1 0.219E+OO 0 0.000 Xe-131m 7 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.123E-03 0.360E-03 0.329E-03 0.154E-01 0.534E-03 0.191E-03


•

•

1 0.406E-04 0 0.000 Xe-133m 8 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.277E-03 0.6 l 7E-03 0.565E-03 0.308E-O 1 0. 750E-03 0.382E-03

1 0.220E-03 0 0.000 Xe-133 9 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO 0.000E+OO 0.432E-03 0.267E-03 0.689E-03 0 .. 627E-03 0.113E-Ol 0.699E-03 0.336E-03

1 0.918E-04 0 0.000 Xe-135m 10 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.339E-02 0.452E-02 0.421E-02 0.267E-Ol 0.452E-02 0.362E-02

1 0.451E-Ol 0 0.000 xe.:.135 11 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.185E-02 0.298E-02 0.278E-02 0.658E-Ol 0.247E-02 0.209E-02

1 0.127E-02 0 0.000 Xe-137 12 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO

1 0.181E+OO 0 0.000 Xe-138 13 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.78iE-02 0.812E-02 0.956E-02 0.874E-02 0.164E+OO 0.319E-Ol 0.780E-02

1 0.491E-Ol 0 0.000 I-131 14 0.107E+07 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.326E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+rio O.OOOE+OO O.OOOE+OO O.OOOE+OO

2 0.599E-04 0 0.000 ,; . I-132 15 0.629E+04 0.999E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.337E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

2 0.502E-02 0 0.000 I-133 16 0.181E+06 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.555E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO

2 0.555E-03 0 0.000 I-134 17 0.107E+04 0.518E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.lllE+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

2 0.132E-O 1 0 0.000 I-135 18 0.315E+05 0.163E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O. l 12E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO


O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO


•

•.......

O.OOOE+OO O.OOOE+OO O.OOOE+OO ci.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.280E+04 0.927E+03 0.391E+04 0.254E+03 0.276E+04 O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO

. O.OOOE+OO 0.615E+04 0.600E+03 0.770E+04 0.117E+02 0.413E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O. l l 1E+05 0.149E+03 0.107E+05 0.558E+OO 0.329E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.284E+05 0.869E+OO 0.813E+04 0.365E-05 0.394E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.405E+05 0.478E-09 0.862E+03 O.OOOE+OO 0.264E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.305E+05 O.OOOE+OO 0.672E+Ol O.OOOE+OO 0.735E-07 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+Ob O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.156E+05 O.OOOE+OO 0.29 lE-02 O.OOOE+OO 0.102E-17 1 EA-TAM-95-05, LOCA APP K src, SIRWT rr, 67.6 cfm with 48% margin (100)


ORGAN Thyroid Lung

INHALATION DOSE

(Rem)

---------0.1972

0.0000

SUBMERSION TOTAL DOSE DOSE

(Rem) (Rem)

--------- ---------0.0000 0.1972

0.0000 0.0000 Bone Surface 0.0000 0.0000 0.0000 Bone Marrow 0.0000 0.0000 0.0000 Beta Skin N/A 0.0000 0.0000 Eye Lens N/A 0.0000 0.0000 Whole Body 0.0060 * 0.0000 0.0060 **


TIME IS 09:01:53 EDT WEDNESDAY 11/ 15/95


•


TIME IS 09: 10:48 EDT WEDNESDAY 11/ 15/95 CONNECT= 00:08:58 VIRTCPU= 004:26.33 TOTCPU= 004:27.93


•

•

CR-FLOWl LISTING A

EA-TAM-95-05, CR Flow sensitivity, 726.0 Fresh air and 2081.1 recirc 0.359E+05

3 0.00 0.35E-03

480.00 0.18E-03 1440.00 0.23E-03

3 0.00 1.0

1440.00 0.6 5760.00 0.4

4 0.00 0. 77E-03 0.26E-03 O.OOE+OO

480.00 0.46E-03 0.15E-03 O.OOE+OO 1440.00 0.29E-03 0.96E-04 O.OOE+OO 5760.00 0.13E-03 0.42E-04 O.OOE+OO

2 0.00 384.2 0.0 0.0 0.0 1.26 100.0 726.0 2081.1 0.0

l 0.00

0 11

0.00 5760.00

18 18

0.000 0.000 0.000 0.000 0.990 0.990

1.00 1.26 12.00 19.00 480.00 600.00 1440.00 14400.00 28800.00 43200.00

1




1 0.123E-06 0 0.000 Kr-87 4 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.SSSE-02 0.576E-02 0.689E-02 0.627E-02 0.339E+OO O.lOlE+OO 0.568E-02


1 0.407E-02 0 0.000 Kr-89 6 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO

1 0.219E+OO 0 0.000 Xe-13lm 7 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.123E-03 0.360E-03 0.329E-03 0.154E-Ol 0.534E-03 0.191E-03


• 1 0.406E-04 0 0.000

Xe-133m 8 O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.277E-03 0.617E-03 0.565E-03 0.308E-Ol 0.750E-03 0.382E-03

1 0.220E-03 0 0.000 Xe-133 9 O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO 0.432E-03 0.267E-03 0.689E-03 0.627E-03 O. ll3E-Ol 0.699E-03 0.336E-03

1 0.918E-04 0 0.000 Xe-135m 10 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.339E-02 0.452E-02 0.42 lE-02 0.267E-O 1 0.452E-02 0'.362E-02

1 0.451E-Ol 0 0.000 Xe-135 11 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.185E-02 0.298E-02 0.278E-02 0.658E-Ol 0.247E-02 0.209E-02

1 0.127E-02 0 0.000 Xe-137 12 O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

1 0.181E+OO 0 0.000 Xe-138 13 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.781E-02 0.812E-02 0.956E-02 0.874E-02 0.164E+OO 0.319E-Ol 0.780E-02

1 0.491E-Ol 0 0.000 I-131 14 0.107E+07 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.326E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO



2 0.555E-03 0 0.000 I-134 17 0.107E+04 0.518E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.l 11E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

2 0.132E-O 1 0 0.000 I-135 18 0.315E+05 0.163E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.112E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO


0.321E+09 0.698E+09 0.322E+08 0.124E+l0 0.181E+l0 0.192E+l0 0.189E+08 0.210E+09 0.607E+l0 0.179E+10 0.105E+10 0.463E+l0 0.465E+l0 0.790E+09 0.112E+10 0.129E+10 0.166E+10 0.132E+l0 0.319E+09 0.696E+09 0.322E+08 0.123E+l0 0.181E+l0 0.155E+l0 0.189E+08 0.210E+09 0.607E+l0 0.171E+l0 0.105E+l0 0.386E+l0 0.443E+l0 0.675E+09 0.948E+09 O.llOE+lO 0.140E+10 0.113E+10


• 0.309E+09 0.687E+09 0.322E+08 O. ll 7E+ 10 O. l 77E+ 10 0.628E+09 0.189E+08 0.210E+09 0.607E+10 0.137E+10 0.104E+10 0.178E+10 0.348E+10 0.229E+09 0.317E+09 0.373E+09 0.457E+09 0.380E+09 0.292E+09 0.671E+09 0.322E+08 0.108E+10 0.171E+10 0.787E+08 0.189E+08 0.209E+09 0.606E+l0 0.911E+09 0.103E+10 0.327E+09 0.224E+l0 0.659E+08 0.864E+08 0.107E+09 0.114E+09 0.107E+09 0.929E+08 0.389E+09 0.322E+08 0.246E+09 0.759E+09 0.328E+06 0.187E+08 0.199E+09 0.593E+l0 0.372E+08 0.777E+09 0.195E+07 0.830E+08 0.768E+08 0.393E+08 0.111E+09 0.215E+08 0.869E+08

.0.109E+08 0.l 74E+09 0.322E+08 0.966E+07 0.204E+09 O.OOOE+OO 0.185E+08 0.187E+09 0.578E+ 10 0.13·1E+OO 0.531E+09 O.OOOE+OO 0.478E-01 0.750E+08 0.739E+07 0.939E+08 0.147E+06 0.506E+08 0.137E+07 0.607E+08 0.322E+08 0.698E+06 0.448E+08 O.OOOE+OO 0.181E+08 0.168E+09 0.553E+ 10 0.837E-04 0.302E+09 O.OOOE+OO 0.190E-04 0.728E+08 0.126E+07 0.725E+08 0.544E+04 0.238E+08 0.665E+03 0.764E+06 0.161E+08 0.330E+02 0.148E+06 O.OOOE+OO 0.817E+07 0.493E+08 0.219E+l0 O.OOOE+OO 0.154E+08 O.OOOE+OO O.OOOE+OO 0.414E+08 0.242E+04 0.143E+08 0.109E-01 0.917E+06 0.476E-09 0.553E+Ol 0.160E+08 0.149E-15 0.172E-02 O.OOOE+OO 0.629E+07 0.132E+08 0.123E+l0 O.OOOE+OO 0.322E+05 O.OOOE+OO O.OOOE+OO 0.283E+08 0.455E-06 0.707E+06 O.OOOE+OO 0.241E+03 O.OOOE+OO 0.696E-09 0.160E+08 O.OOOE+OO 0.556E-18 O.OOOE+OO 0.396E+07 0.133E+07 0.446E+09 O.OOOE+OO 0.337E+OO O.OOOE+OO O.OOOE+OO 0.145E+08 O.OOOE+OO 0.352E+04 O.OOOE+OO 0.398E-04 O.OOOE+OO O.OOOE+OO 0.158E+08 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.219E+07 0.560E+05 0.118E+09 O.OOOE+OO 0.394E-08 O.OOOE+OO O.OOOE+OO 0.609E+07 O.OOOE+OO 0.118E+Ol O.OOOE+OO 0.465E-15 1 EA-TAM-95-05, CR Flow sensitivity, 726.0 Fresh air and 2081.1 recirc



(Rem) DOSE DOSE

(Rem) (Rem) ORGAN --------- --------- ---------

Thyroid 22.0782 0.0541 22,1323 Lung 0.0204 0.0502 0.0705 Bone Surface 0.0000 0.0804 0.0804 Bone Marrow 0.0000 0.0722 0.0722 Beta Skin N/A 1.2561 1.2561 Eye Lens N/A . 0.1572 0.1572 Whole Body 0.6730 * 0.0557 0.7287 **


• TIME IS 16:25:41 EDT WEDNESDAY 11/15/95


• CONNECT= 00:00:07 VIRTCPU= 000:00.09 TOTCPU= 000:00.22 DMSACP723I X (120) R/O DMSLI0740I Execution begins ... CONDOSE RUN COMPLETED

TIME IS 16:42:02 EDT WEDNESDAY 11/15/95 CONNECT= 00: 16:28 VIRTCPU= 004:20.49 TdTCPU= 004:22.52


• CR-FLOW2 LISTING A

EA-TAM-95-05, CR Flow sensitivity, 1132.7 fresh air and 1674.4 recirc 0.359E+05

3 0.00 0.35E-03

480.00 0.18E-03 1440.00 0.23E-03

3 0.00

1440.00 5760.00

4

1.0 0.6 0.4

0.00 0.77E-03 0.26E-03 O.OOE+OO 480.00 0.46E-03 0.15E-03 O.OOE+OO 1440.00 0.29E-03 0.96E-04 O.OOE+OO 5760.00 0.13E-03 0.42E-04 O.OOE+OO

2 0.00 384.2 0.0 0.0 0.0 1.26 100.0 1132.7 1674.4 0.0

l 0.00 0.000 0.000 0.000 0.000 0.990 0.990

0 11

0.00 5760.00

18 18

1.00 1.26 12.00 19.00 480.00 600.00 1440.00 14400.00 28800.00 43200.00

1





1 0.908E-02 0 0.000 Kr-88 5 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.144E-01 0.134E-Ol 0.154E-01 0.134E-01 0.946E-Ol 0.288E-Ol 0.140E-Ol

1 0.407E-02 0 0.000 Kr-89 6 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO

1 0.219E+OO 0 0.000 Xe-13lm 7 O.OOOE+OO O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.123E-03 0.360E-03 0.329E-03 0.154E-Ol 0.534E-03 0.191E-03

EA-TAM-95-05 Sheet 11 7 Rev# __Q_

• 1 0.406E-04 0 0.000

Xe-133m 8 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.277E-03 0.617E-03 0.565E-03 0.308E-01 0.750E-03 0.382E-03

1 0.220E-03 0 0.000 Xe-133 9 O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.432E-03 0.267E-03 0.689E-03 0.627E-03 O. l 13E-O 1 0.699E-03 0.336E-03

1 0.918E-04 0 0.000 Xe-135m 10 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.339E-02 0.452E-02 0.421E-02 0.267E-01 0.452E-02 0.362E-02

1 0.451E-01 0 0.000 Xe-135 11 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.185E-02 0.298E-02 0.278E-02 0.658E-01 0.247E-02 0.209E-02

1 0.127E-02 0 0.000 Xe-137 12 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO

1 0.181E+OO 0 0.000 Xe-138 13 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO 0.781E-02 0.812E-02 0.956E-02 0.874E-02 0.164E+OO 0.319E-Ol 0.780E-02

1 0.491E-01 0 0.000 I-131 14 0.107E+07 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.326E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO



2 0.555E-03 0 0.000 I-134 17 0.107E+04 0.518E+03 O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO 0.111E+03 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO

2 0.132E-O 1 0 0.000 I-135 18 0.315E+05 0.163E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O. l 12E+04 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

2 O. l 75E-02 0 0.000 ECHO OF RELEASE RATES IN THE FOLLOWING ORDER: Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132 I-133 I-134 I-135 0.321E+09 0.698E+09 0.322E+08 0.124E+10 0.181E+10 0.192E+10 0.189E+08 0.210E+09 0.607E+10 0.179E+l0 O.lOSE+lO 0.463E+10 0.465E+10 0.790E+09 0.112E+10 0.129E+10 0.166E+l0 0.132E+10 0.319E+09 0.696E+09 0.322E+08 0.123E+l0 0.181E+l0 0.155E+10 0.189E+08 0.210E+09 0.607E+l0 0.171E+10 0.lOSE+lO 0.386E+10 0.443E+10 0.675E+09 0.948E+09 O.llOE+lO 0.140E+10 0.113E+10


-• 0.309E+09 0.687E+09 0.322E+08 0.117E+10 0.177E+l0 0.628E+09 0.189E+08 0.210E+09 0.607E+l0 0.137E+l0 0.104E+l0 0.178E+l0 0.348E+ 10 0.229E+09 0.3 l 7E+09 0.373E+09 0.457E+09 0.380E+09 0.292E+09 0.671E+09 0.322E+08 0.108E+l0 0.171E+l0 0.787E+08 0.189E+08 0.209E+09 0.606E+10 0.911E+09 0.103E+l0 0.327E+09 0.224E+ 10 0.659E+08 0.864E+08 0.107E+09 0.114E+09 0.107E+09 0.929E+08 0.389E+09 0.322E+08 0.246E+09 0.759E+09 0.328E+06 0.187E+08 0.199E+09 0.593E+l0 0.372E+08 0.777E+09 0.195E+07 0.830E+08 0.768E+08 0.393E+08 0.111E+09 0.215E+08 0.869E+08 0.109E+08 O. l 74E+09 0.322E+08 0.966E+07 0.204E+09 O.OOOE+OO 0.185E+08 O.l87E+09 0.578E+10 0.131E+OO 0.531E+09 O.OOOE+OO 0.478E-01 0.750E+08 0.739E+07 0.939E+08 0.147E+06 0.506E+08 0.137E+07 0.607E+08 0.322E+08 0.698E+06 0.448E+08 O.OOOE+OO 0.181E+08 0.168E+09 0.553E+ 10 0.837E-04 0.302E+09 O.OOOE+OO 0.190E-04 0.728E+08 0.126E+07 0.725E+08 0.544E+04 0.238E+08 0.665E+03 0.764E+06 0.161E+08 0.330E+02 0.148E+06 O.OOOE+OO 0.817E+07 0.493E+08 0.219E+l0 O.OOOE+OO 0.154E+08 O.OOOE+OO O.OOOE+OO 0.414E+08 0.242E+04 0.143E+08 0.109E-01 0.917E+06 0.476E-09 0.553E+Ol 0.160E+08 0.149E-15 0.172E-02 O.OOOE+OO 0.629E+07 0.132E+08 0.123E+ 10 O.OOOE+OO 0.322E+05 O.OOOE+OO O.OOOE+OO 0.283E+08 0.455E-06 0.707E+06 O.OOOE+OO 0.241E+03 O.OOOE+OO 0.696E-09 0.160E+08 O.OOOE+OO 0.556E-18 O.OOOE+OO 0.396E+07 0.133E+07 0.446E+09 O.OOOE+OO 0.337E+OO O.OOOE+OO O.OOOE+OO 0.145E+08 O.OOOE+OO 0.352E+04 O.OOOE+OO 0.398E-04 O.OOOE+OO O.OOOE+OO 0.158E+08 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.219E+07 0.560E+05 0.118E+09 O.OOOE+OO 0.394E-08 O.OOOE+OO O.OOOE+OO 0.609E+07 O.OOOE+OO 0.118E+Ol O.OOOE+OO 0.465E-15 1 EA-TAM-95-05, CR Flow sensitivity, 1132.7 fresh air and 1674.4 recirc



(Rem) DOSE DOSE

(Rem) (Rem) ORGAN --------- --------- ---------

Thyroid 22.3279 0.0526 22.3805 Lung 0.0206 0.0490 0.0696 Bone Surface 0.0000 0:0777 0.0777 Bone Marrow 0.0000 0.0698 0.0698 Beta Skin N/A 1.2143 1.2143 Eye Lens N/A 0.1562 0.1562 Whole Body 0.6806 * 0.0542 0.7348 **

* - The whole body inhalation dose is the Committed Effective Dose Equivalent. **- The total value for whole body dose is the Total Effective Dose Equivalent. l*** This is the console file for job JOB1446(1446). ***

• TIME IS 16:25:55 EDT WEDNESDAY 11/ 15/95


•

I

•


TIME IS 16:42:23 EDT WEDNESDAY 11/ 15/95 CONNECT= 00:16:31 VIRTCPU= 004:20.12 TOTCPU= 004:21.75


• CR-FLOW3 LISTING A

EA-TAM-95-05 CR flow sensitivity, 980.2 Fresh Air and 2809.5 recirc 0.359E+05

3 0.00 0.35E-03

480.00 0.18E-03 1440.00 0.23E-03

3 0.00

1440.00 5760.00

4

1.0 0.6 0.4

0.00 0.77E-03 0.26E-03 0.00E+OO 480.00 0.46E-03 0.15E-03 O.OOE+OO 1440.00 0.29E-03 0.96E-04 O.OOE+OO 5760.00 0.13E-03 0.42E-04 O.OOE+OO

2 0.00 384.2 0.0 0.0 0.0 1.26 100.0 980.2 2809.5 0.0

l 0.00

0 11

0.00 5760.00

18 18

0.000 0.000 0.000 0.000 0.990 0.990

1.00 1.26 12.00 19.00 480.00 600.00 1440.00 14400.00 28800.00 43200.00

1






1 0.407E-02 0 0.000 Kr-89 6 O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

1 0.219E+OO 0 0.000 Xe-13lm 7 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.123E-03 0.360E-03 0.329E-03 0.154E-Ol 0.534E-03 0.191E-03


I~'

j

•

•

1 0.406E-04 0 0.000 Xe-133m 8 O.OOOE+OO 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.277E-03 0.617E-03 0.565E-03 0.308E-01 0.750E-03 0.382E-03

1 0.220E-03 0 0.000 Xe-133 9 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.432E-03 0.267E-03 0.689E-03 0.627E-03O.l13E-01 0.699E-03 0.336E-03

1 0.918E-04 0 0.000 Xe-135m 10 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.339E-02 0.452E-02 0.421E-02 0.267E-01 0.452E-02 0.362E-02


1 0.127E-02 0 0.000 Xe-137 12 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

i 0.181E+OO 0 0.000 Xe-138 13 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.781E-02 0.812E-02 0.956E-02 0.874E-02 0.164E+OO 0.319E-01 0.780E-02






2 O. l 75E-02 0 0.000 ECHO OF RELEASE RATES IN THE FOLLOWING ORDER: Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-13lm Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 1-132 I-133 I-134 I-135 0.321E+09 0.698E+09 0.322E+08 0.124E+10 0.181E+l0 0.192E+10 0.189E+08 0.210E+09 0.607E+l0 0.179E+10 0.105E+10 0.463E+10 0.465E+10 0.790E+09 0.112E+10 0.129E+l0 0.166E+10 0.132E+10 0.319E+09 0.696E+09 0.322E+08 0.123E+l0 0.181E+l0 0.155E+10 0.189E+08 0.210E+09 0.607E+10 0.171E+10 0.105E+10 0.386E+l0 0.443E+10 0.675E+09 0.948E+09 0.110E+l0 0.140E+l0 0.113E+10


.J 0.309E+09 0.687E+09 0.322E+08 O. ll 7E+ 10 O. l 77E+ 10 0.628E+09 0.189E+08 0.210E+09 0.607E+10 0.137E+l0 0.104E+l0 0.178E+l0 0.348E+ 10 0.229E+09 0.317E+09 0.373E+09 0.457E+09 0.380E+09 0.292E+09 0.671E+09 0.322E+08 0.108E+l0 0.171E+10 0.787E+08 0.189E+08 0.209E+09 0.606E+10 0.911E+09 0.103E+10 0.327E+09 0.224E+l0 0.659E+08 0.864E+08 0.107E+09 0.114E+09 0.107E+09 0.929E+08 0.389E+09 0.322E+08 0.246E+09 0.759E+09 0.328E+06 0.187E+08 0.199E+09 0.593E+10 0.372E+08 0.777E+09 0.195E+07 0.830E+08 0.768E+08 0.393E+08 0.111E+09 0.215E+08 0.869E+08 0.109E+08 0.174E+09 0.322E+08 0.966E+07 0.204E+09 O.OOOE+OO 0.185E+08 0.187E+09 0.578E+10 0.131E+OO 0.531E+09 O.OOOE+OO 0.478E-01 0.750E+08 0.739E+07 0.939E+08 0.147E+06 0.506E+08 0.137E+07 0.607E+08 0.322E+08 0.698E+06 0.448E+08 O.OOOE+OO 0.181E+08 0.168E+09 0.553E+10 0.837E-04 0.302E+09 O.OOOE+OO 0.190E-04 0.728E+08 0.126E+07 0.725E+08 0.544E+04 0.238E+08 0.665E+03 0.764E+06 0.161E+08 0.330E+02 0.148E+06 O.OOOE+OO 0.817E+07 0.493E+08 0.219E+l0 O.OOOE+OO 0.154E+08 O.OOOE+OO O.OOOE+OO 0.414E+08 0.242E+04 0.143E+08 0.109E-01 0.917E+06 0.4 76E-09 0.553E+O 1 0.160E+08 0.149E-15 O. l 72E-02 O.OOOE+OO 0.629E+07 0.132E+08 0.123E+ 10 O.OOOE+OO 0.322E+05 O.OOOE+OO O.OOOE+OO 0.283E+08 0.455E-06 0.707E+06 O.OOOE+OO 0.241E+03 O.OOOE+OO 0.696E-09 0.160E+08 O.OOOE+OO 0.556E-18 O.OOOE+OO 0.396E+07 0.133E+07 0.446E+09 O.OOOE+OO 0.337E+OO O.OOOE+OO O.OOOE+OO 0.145E+08 O.OOOE+OO 0.352E+04 O.OOOE+OO 0.398E-04 O.OOOE+OO O.OOOE+OO 0.158E+08 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.219E+07 0.560E+05 0.118E+09 O.OOOE+OO 0.394E-08 O.OOOE+OO O.OOOE+OO 0.609E+07 O.OOOE+OO 0.118E+Ol O.OOOE+OO 0.465E-15 1 EA-TAM-95-05 CR flow sensitivity, 980.2 Fresh Air and 2809.5 recirc



(Rem) DOSE DOSE

(Rem) (Rem) ORGAN --------- --------- ---------


* - The whole body inhalation dose is the Committed Effective Dose Equivalent. **- The total value for whole body dose is the Total Effective Dose Equivalent. 1 *** This is the console file for job J 0B144 7 ( 144 7). ***

• TIME IS 16:26:31 EDT WEDNESDAY 11/ 15/95


•

CONNECT= 00:00: 15 VIRTCPU= 000:00.09 TOTCPU= 000:00.23 DMSACP723l X (120) R/O DMSLI0740I Execution begins ... CONDOSE RUN COMPLETED

TIME IS 16:42:59 EDT WEDNESDAY 11/15/95 CONNECT= 00: 16:43 VIRTCPU= 004:22.14 TOTCPU= 004:23.58


•

I. ·' ,

CR-FLOW4 LISTING A

EA-TAM-95-05, CR Flow sensitivity, Fresh Air 1529.1 and 2260.5 recirc 0.359E+05

3 0.00 0.35E-03

480.00 0.18E-03 1440.00 0.23E-03

3 0.00 1.0

1440.00 0.6 5760.00 0.4

4 0.00 0. 77E-03 0.26E-03 O.OOE+OO

480.00 0.46E-03 0.15E-03 O.OOE+OO 1440.00 0.29E-03 0.96E-04 O.OOE+OO 5760.00 0.13E-03 0.42E-04 O.OOE+OO

2 0.00 384.2 0.0 0.0 0.0 1.26 100.0 1529. l 2260.5 0.0

1 .l

0.00 0.000 0.000 0.000 0.000 0.990 0.990 0 11

0.00 1.00 1.26 12.00 19.00 480.00 600.00 1440.00 5760.00 14400.00 28800.00 43200.00

18 1 18


1 0.631E-02 0 0.000 Kr-85m 2 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.123E-02 0.113E-02 0.195E-02 0.185E-02 0.514E-01 0.154E-02 0.127E-02



1 0.908E-02 0 0.000 Kr-88 5 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.144E-01 0.134E-01 0.154E-01 0.134E-Ol"0.946E-01 0.288E-01 0.140E-01

1 0.407E-02 0 0.000 Kr-89 6 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

1 0.219E+OO 0 0.000 Xe-131m 7 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

- 0.000E+OO 0.123E-03 0.360E-03 0.329E-03 0.154E-01 0.534E-03 0.191E-03


'\

• 1 0.406E-04 0 0.000

Xe-133m 8 O.OOOE+OO 0.000E+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO 0.277E-03 0.617E-03 0.565E-03 0.308E-01 0.750E-03 0.382E-03

1 0.220E-03 0 0.000 Xe-133 9 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.432E-03 0.267E-03 0.689E-03 0.627E-03 0.113E-Ol 0.699E-03 0.336E-03

1 0.918E-04 0 0.000 Xe-135m 10 0.000E+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.339E-02 0.452E-02 0.421E-02 0.267E-01 0.452E-02 0.362E-02


1 0.127E-02 0 0.000 Xe-137 12 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.000E+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO

l 0.181E+OO 0 0.000 Xe-138 13 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.781E-02 0.812E-02 0.956E-02 0.874E-02 0.164E+OO 0.319E-01 0.780E-02

1 0.491E-01 0 0.000 I-131 14 0.107E+07 O.OOOE+oo O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.326E+05 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO





2 O. l 75E-02 0 0.000 ECHO OF RELEASE RATES IN THE FOLLOWING ORDER: Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I-132 1-133 I-134 I-135 0.321E+09 0.698E+09 0.322E+08 0.124E+10 0.181E+10 0.192E+l0 0.189E+08 0.210E+09 0.607E+10 0.179E+10 O.lOSE+lO 0.463E+10 0.465E+l0 0.790E+09 0.112E+l0 0.129E+10 0.166E+10 0.132E+10 0.319E+09 0.696E+09 0.322E+08 0.123E+10 0.181E+10 0.155E+l0 0.189E+08 0.210E+09 0.607E+l0 0.171E+l0 0.105E+l0 0.386E+l0 0.443E+10 0.675E+09 0.948E+09 0.llOE+lO 0.140E+l0 0.113E+l0


• 0.309E+09 0.687E+09 0.322E+08 0.117E+10 0.177E+l0 0.628E+09 0.189E+08 0.210E+09 0.607E+10 0.137E+10 0.104E+l0 0.178E+l0 0.348E+l0 0.229E+09 0.317E+09 0.373E+09 0.457E+09 0.380E+09 0.292E+09 0.671E+09 0.322E+08 0.108E+l0 0.171E+l0 0.787E+08 0.189E+08 0.209E+09 0.606E+l0 0.911E+09 0.103E+10 0.327E+09 0.224E+ 10 0.659~+08 0.864E+08 0.107E+09 0.114E+09 0.107E+09 0.929E+08 0.389E+09 0.322E+08 0.246E+09 0.759E+09 0.328E+06 0.187E+08 0.199E+09 0.593E+l0 0.372E+08 0.777E+09 0.195E+07 0.830E+08 0.768E+08 0.393E+08 0.111E+09 0.215E+08 0.869E+08 0.109E+08 O. l 74E+09 0.322E+08 0.966E+07 0.204E+09 O.OOOE+OO d.185E+08 0.187E+09 0.578E+ 10 0.13 lE+OO 0.531E+09 O.OOOE+OO 0.478E-Ol 0.750E+08 0.739E+07 0.939E+08 0.147E+06 0.506E+08 0.137E+07 0.607E+08 0.322E+08 0.698E+06 0.448E+08 O.OOOE+OO 0.181E+08 0.168E+09 0.553E+10 0.837E-04 0.302E+09 O.OOOE+OO 0.190E-04 0.728E+08 0.126E+07 0.725E+08 0.544E+04 0.238E+08 0.665E+03 0.764E+06 0.161E+08 0.330E+02 0.148E+06 O.OOOE+OO 0.817E+07 0.493E+08 0.219E+l0 O.OOOE+OO 0.154E+08 O.OOOE+OO O.OOOE+OO 0.414E+08 0.242E+04 0.143E+08 0.109E-01 0.917E+06 0.476E-09 0.553E+Ol 0.160E+08 0.149E-15 o:l72E-02 O.OOOE+OO 0.629E+07 0.132E+08 0.123E+l0 O.OOOE+OO 0.322E+05 O.OOOE+OO O.OOOE+OO 0.283E+08 0.455E-06 0.707E+06 O.OOOE+OO 0.241E+03 O.OOOE+OO 0.696E-09 0.160E+08 O.OOOE+OO 0.556E-18 O.OOOE+OO 0.396E+07 0.133E+07 0.446E+09 O.OOOE+OO 0.337E+OO O.OOOE+OO O.OOOE+OO 0.145E+08 O.OOOE+OO 0.352E+04 O.OOOE+OO 0.398E-04 O.OOOE+OO O.OOOE+OO 0.158E+08 O.OOOE+OO O.OOOE+OO O.OOOE+OO 0.219E+07 0.560E+05 0.118E+09 O.OOOE+OO 0.394E-08 O.OOOE+OO O.OOOE+OO 0.609E+07 O.OOOE+OO 0.118E+Ol O.OOOE+OO 0.465E-15 1 EA-TAM-95-05, CR Flow sensitivity, Fresh Air 1529.1 and 2260.5 recirc



(Rem) DOSE DOSE

(Rem) (Rem) ORGAN --------- --------- ---------



~ TIME IS 16:26:37 EDT WEDNESDAY 11/ 15/95


•


TIME IS 16:43:57 EDT WEDNESDAY 11/ 15/95 CONNECT= 00: 17:28 VIRTCPU= 004:21.53 TOTCPU= 004:22.93


attachment 1 consumers power company engineering … · these dampers were _also measured with the...

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