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Rev 0 to Engineering Analysis (EA) EA-PAH-91-05, Benchmarking of Mhacalc Code
	ML18058A406
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Site:	Palisades
Issue date:	03/04/1992
From:	; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
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ML18058A401	List: ML18058A399; ML18058A404; ML18058A406; ML18058A408;
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	EA-PAH-91-05, EA-PAH-91-05-R00, EA-PAH-91-5, EA-PAH-91-5-R, NUDOCS 9205050236
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{{#Wiki_filter:* ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 BENCH-MARKING OF THE MHACALC CODE EA-PAH-91-05 April 29, 1992 _,---9205050236 920429 PDR ADOCK 05000255 p PDR

PALISADES NUCLEAR PlANT ENGINEERING ANALYSIS WORK SHEET Title BENCHMARKING OF THE MHACALC CODE INITIATION AND REVIEW \\ -PAH-91-05. eet 1 of 50 Initiated Initiator Review Method Check CJ) Technically Reviewed Reviewer Rev Appd AL t Det Qual Appd By Date Description By Date By Cale Rvw Test By 0 Original Issue &;i,/,_,4 3hA'.2 Kb¥ )( ~ JJl)W~ 'I fi1"1,iJcf.J. ":a.¥ (/ (/ PURPOSE: The objective of this Engineering Analysis is to demonstrate the calculational methodology used to write the MHACALC FORTRAN code and to verify the accuracy of the output from the code through the use of test cases and alternate calculations. PROCEDURE UTILIZED: The guidance of Regulatory Guide 1.4, Rev. 2, the Standard Review Plan, Section 6

5
2, Rev. 2, and differential equations to model radionuclide transport in and out of the containment building.

SUMMARY

OF RESULTS: The MHACALC code was written to calculate the time dependent activity of iodine and noble gas in the containment atmosphere and sump following a LOCA. The code also determines the resultant off site radiation exposure doses, and the time dependent radionuclide release rates for use in control room habitability calculations. Through the use of several test cases and alternate calculations, the code was verified to perform all of the desired functions accurately. The MHACALC code is therefore functionally correct to perform radiological consequence analyses of a LOCA at Palisades in accordance with the Regulatory Guide and Standard Review Plan guidance. SPECIAL MEDIA ATTACHED (DRAWINGS, MICROFICHE, ETC) -- NO x_ YES - List of Attachments included

Section .:t4-3S PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET TABLE OF CONTENTS EA-PAH-91-05 Sheet _2_ of 50 1.0 Objective........................................................................................................................................................ 3 2.0 References..................................................................................................................................................... 3 3.0 Background.................................................................................................................................................... 5 4.0 Analysis Input......................................................................................................................................... ;..... 6 5.0 Assumptions.................................................................................................................................................. 6 6.0 Methodology..................................................................... ~........................................................................... 8 6.1 Releases From Containment Atmosphere............................................................................................ 10 6.2 Releases From Containment Sump........................................................................................................ 14 6.3 Total Release and Doses.......................................................................................................................... 20 6.4 Dose Equivalent Iodine 131..................................................................................................................... 23 7.0 Input Deck Description...................................................................................................... ~....................... 24 8.0 MHACALC Execution............................................................................................................................... 33 9.0 Output Descriction...................................................................................................................................... 34 9.1 Offsite Dose File........................................................................................................................................ 34 9.2 Release Rate Files..................................................................................................................................... 34 9.3 Plotting Data File....................................................................................................................................... 35 10.0 Test Cases and Verification...................................................................................................................... 37 11.0 Summary....................................................................................................................................................... 47 12.0 Conclusion.................................................................................................................................................... 49 13.0 List of Attachments..................................................................................................................................... 50

PALISADES NUCLEAR PI.ANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet _3_ of 50 BENCHMARKING OF THE MHACALC CODE 1.0 OBJECTIVE The objective of this Engineering Analysis is to demonstrate the calculational methodology used to write the MHACALC Fortran code and to verify the accuracy of the output from the code through the use of test cases and hand calculations.

2.0 REFERENCES

2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 Regulatory Guide 1.4, "Assumptions Used For Evaluating The Potential Radiological Consequences of a Loss of Coolant Accident For Pressurized Water Reactors." Rev. 2, June 1974. Letter from A Schwencer (NRC) to D. Bixel (CPCo).

Subject:

Transmittal of Amendment No. 31 and Safety Evaluation. November 1, 1977. Cart./Frame: 2511/1751. EA-P-LOCA-870424, "Calculation of The Offsite Thyroid and Wholebody Doses Due to The Palisades MHA." May 1987. Cart/Frame: 3644/932 NUREG-0800, USNRC Standard Review Plan. Section 15.6.5 Appendix A, Rev. 1 - July 1981. Section 15.6.5 Appendix B, Rev. 1 - July 1981. Section 6.2.4, Rev. 2 - July 1981. Section 6.5.2, Rev. 2 - December 1988. Palisades Plant Technical Specifications. EA-P-LOCA-881024, "Calculation of Offsite Doses Due to The Palisades MHA Including The Effect of The CWRT Vent." October 1988. Palisades Plant Final Safety Analysis Report. Letter from D. P. Hoffman (CPCo.) to D. L. Ziemann (NRC). March 9, 1978. Cart./Frame: 0575/1561. Letter from D. L. Ziemann (NRC) to D. P. Hoffman (CPCo.).

Subject:

Amendment No. 40. April 12, 1978. 2.10 E-PAL-90-035, "RT-88A Test Failure", Palisades Event Report. September 25, 1990.

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 4 of 50 2.11 Code of Federal Regulations, Title 10, Part 20, "Standards for Protection Against Radiation," May 1991. Title 10, Part 100, "Reactor Site Criteria," January 1 1990. 2.12 ICRP Publication 30, "Limits for Intakes of Radionuclides by Workers," Pergamon Press, July 1978. 2.13 NED0-24782, "BWR Owner's Group NUREG-0578 Implementation: Analysis and Positions for Plant Unique Submittals," General Electric Co. 1984. 2.14 NUREG/CR-1413, "A Radionuclide Decay Data Base - Index and Summary Table," Oak Ridge National Laboratory. May 1980. 2.15 RETRAN-02 Computer Code Manual, Volume 3, Rev. 4. November 1988. 2.16 Internal Correspondence WLR92-001, from WLRoberts to PMDonnelly.

Subject:

"Palisades Plant

- Meeting With the NRC on CRHAB, Iodine Removal and SIRW Tank Dose Issues," January 22, 1992. 2.17 Palisades Plant Drawing M-116 Rev 13, "Heating & Ventilation Auxiliary & Containment Plan at Elevation 590'-0"." 2.18 Palisades Plant Drawing M-118 Rev 18, "Heating & Ventilation Auxiliary & Containment Plan at El 607'-6" & 611'-0"." 2.19 Palisades Plant Drawing M-120 Rev 10, "Heating & Ventilation Auxiliary & Containment Building Plan Elevation 625' -0"." 2.20 Palisades Plant Drawing M-122 Rev 4, "Heating & Ventilation Reactor Containment Building Recirculation Risers." 2.21 Palisades Plant Drawing M-123 Rev 4, "Heating & Ventiltation Reactor Containment Building Coolers - Unit V-3 & Unit V-4." 2.22 FD-M-25 Rev C, "Palisades Plant Consumers Power Company Unit 1 Functional Description Containment Air Cooling System," Bechtel Company, September 1968. Located in DCC in the . functional description books. 2.23 EMF-91-177, "Palisades Large Break LOCA/ECCS Analysis With Increased Radial Peaking and -Reduced ECCS Flow," Siemens Nuclear Power Corporation, October 1991. 2.24 NUREG/CR-5106, "User's Guide for the TACTS Computer Code," June 1988. 2.25 NUREG/CR-5732, "Iodine Chemical Forms in LWR Severe Accidents," Oak Ridge National Laboratory, July 1991.

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet _5_ of 50 2.26 EA-PAH-91-06, "Iodine Removal Coefficients for Containment Sprays Based on Standard Review Plan 6.5.2, Revision 2," December 1991. Cart/Frame: F005/2454. 2.27 EA-GCP-91-04, "Maximum and Minimum Containment Sump Volume and Boron Concentration Following a Large Break LOCA," November 1991. 2.28 "CRC Handbook of Chemistry and Physics," 55th edition. CRC Press 1974. 2.29 EA-A-NL-92-012-01, "Benchmarking of the CONDOSE Code for Control Room Habitability Calculations," March 1991. 2.30 Letter from E.C. Beahm (Martin Marietta Energy Systems, Inc.) to Jay Y. Lee (USNRC) dated February 5, 1992. (Attached)

3.0 BACKGROUND

To analyze the radiological consequences of a loss of coolant accident (LOCA), or the maximum hypothetical accident (MHA) as it is sometimes called, numerous calculations must be performed to model the time dependent concentration of radionuclides in the containment atmosphere and the subsequent release of those radionuclides to the environment. The calculations must take into account a vast assortment of parameters, most of which are time dependent. Performing an analysis of the MHA over a large time period, such as 30 days as is necessary, is a long and tedious task for hand calculations if performed accurately. For this reason, the MHACALC code was written. The MHACALC code ("the code") calculates the time dependent activity of iodine and noble gas in the containment atmosphere and sump, and determines the resultant offsite radiation exposure doses by modeling the release paths from containment, for a LOCA type accident. The code also calculates the radionuclide release rates following the accident for use in control room habitability evaluations using the CONDOSE code [Ref. 2.29]. The code can model the release of radionuclides to the environment from containment atmosphere leakage and leakage of engineered safety features (ESF) components such as valve stems, pump seals, etc. The ability to model the release of radionuclides from the Safety Injection and Refueling Water (SIRW) Tank due to valve seat leakage during recirculation was also incorporated into the code after the discovery of a potential leak path to the SIR W Tank, which is vented to the atmosphere. This leak path to the SIR W Tank is documented in Reference 2.10.

4.0 ANALYSIS INPUT PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet ~6~ of 50 4.1 The total airflow through each containment air cooler during MHA conditions, 37,500 ft 3 /min, is from Reference 2.7 [Table 6-8 Rev. 12]. 4.2 The free air volume in containment, l.64E+06 ft3, is from Reference 2.7 [section 5.8.2, Rev. 12]. 4.3 The air volume in containment covered by sprays, l.48E + 06 ft3, which corresponds to 90% of the free air volume is from Reference 2.2. 4.4 The methods for calculating radiation exposure doses to individuals are from ICRP-30 [Ref. 2.12], which contains the most current methods accepted by the NRC as adopted for the newest revision to 10 CFR 20 [Ref. 2.11 ]. 4.5 As long as the pH of the sump is controlled above 7.0, the fraction of iodine reaching the SIRW Tank that will be in volatile form and can evolve out of solution is 3.0E~04 from Reference 2.25 [pg. 26] and Reference 2.30. 5.0 ASSUMPTIONS 5.1 The interaction between the containment atmosphere iodine activity and sump solution activity due to iodine removal by sprays does not need to be accounted for when using Regulatory Guide 1.4 source terms. The results of the NRC's calculations in Reference 2.2 were duplicated in Reference 2.3 [pg. 41] without considering the interaction. This assumption was also recently verified during informal discussions with the NRC [Ref. 2.16]. 5.2 The containment atmosphere can be modeled as a single, well-mixed space if at least 90 % of the containment is covered by sprays and a ventilation system is available for adequate mixing of unsprayed compartments [Ref. 2.4, section 6.5.2]. 5.3 The containment vent path through a clean waste receiver tank with the rupture disc removed does not need to be included as a release path for LOCA doses. Reference 2.4, SRP 15.6.5 Appendix A states that.this path need not be considered if the position of SRP 6.2.4 is met. Since Technical Specifications require this path to be isolated within 25 seconds [Ref. 2.5, Table 3.6.1] and the earliest predicted hot rod burst occurs at 46 seconds for a double ended cold leg guillotine break [Ref. 2.23, Table 2.1], it is assumed that the position of SRP 6.2.4 is met. Also, the calculated dose contribution at the site boundary for this path is 0.02 rem [Ref 2.6]. 5.4 The containment leak rate decreases to 50 % of its initial value 24 hours after a LOCA [Ref. 2.1 ]. 5.5 The removal rate of particulate iodine only changes when the total particulate iodine activity decreases by a factor of 50 from the initial activity [Ref. 2.4, section 6.5.2], or when sprays stop.

PALISADES NUCLEAR PIANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet _7_ of 50 5.6 The removal rate of elemental iodine ends (becomes 0.0) when the ratio of the initial elemental iodine activity to that at some time after sprays begin equals the decontamination factor for elemental iodine [Ref. 2.4, section 6.5.2] (assuming the condition is met before sprays stop.) 5.7 No credit can be taken for spray removal of organic iodine [Ref. 2.4, section 6.5.2]. 5.8 The leak rate from ESP components, taken as the Technical Specification maximum, is multiplied by a factor of 2 for the duration of recirculation after a LOCA [Ref. 2.4, section 15.6.5 App. B]. 5.9 The release of radionuclides ends after 30 days. 5.10 Daughter products are not considered during the radioactive decay of the radionuclides of concern in containment. Daughter product ingrowth capability was also removed from the NRC's TACTS computer code since it is generally not considered in design basis accident analysis [Ref. 2.24]. 5.11 Radionuclides leaking into the SIRW tank from recirculation line valve seat-leakage become homogeneously mixed with the volume of water in the SIR W tank, accompanied by instantaneous equilibrium partitioning of the volatile iodine in the SIR W tank liquid and air volumes. This assumption is conservative since it would take a considerable amount of time for the iodine to mix homogeneously and for the volatile iodine to come to equilibrium with the SIRW tank air volume. 5.12 Since the SIRW tank is aluminum, some heat transfer would occur with the environment, the density of the air in the tank is assumed to remain relatively constant as sump water enters the tank. Density changes could also occur from day to night and vice versa, but would result in some periods forcing air from the tank and some drawing air into the tank. There could also be some diffusion in and out of the vent. To account for this, a user defined multiplication factor is specified for the rate at which the iodine exits the tank. 5.13 During the period of time that the sump water is above 212°F, the valve seat-leakage that flashes will condense before reaching the SIRW tank air volume. The leakage will travel through approximately 60 feet of 6 inch piping filled with water into the SIR W tank containing more than 20000 gallons of water after RAS, all of which will be near ambient temperatures. This is designed for use with very small leakages on the order of a few tenths of a gallon per minute. 5.14 The volume of air displaced from the SIRW tank to the environment equals the volume of water that enters the tank. With the vent protruding from the top of the tank being upside down "U"- shaped, air flow into or out of the tank at steady state conditions would be very low. The iodine, homogeneously mixed in the air, exits the tank at the rate at which air exits times a user defined multiplier to account for any diffusion and add conservatism. 5.15 The containment sump water volume decreases with time due to the leakage out of containment, but is conservatively assumed not to increase due condensation of steam in containment. 5.16 For releases from the SIRW tank, the method of Reference 2.25 [pg. 29, Eqn 25] can be used to calculate the partition factor for the volatile iodine in the tank [Ref. 2.30].

6.0 METHODOLOGY -PALISADES NUCLEAR PI.ANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 8 of 50 To model containment and the radionuclide release paths from containment, two separate regions are considered: the containment atmosphere and the containment sump. Since no regulatory guidance has been given as to whether or not the interaction between the containment atmosphere and containment sump should pe modeled when using Regulatory Guide 1.4 [Ref. 2.1] source terms, References 2.2 and 2.3 are evaluated. In Reference 2.2 [pgs. 25-28] the NRC listed the assumptions, input, and results of their staff's calculations of the doses from a LOCA at Palisades. In Reference 2.3 [pgs. 31-41], the methodology used by the NRC staff was determined by duplicating the NRC staff's results. Excellent agreement with the NRC staff's results were obtained without modeling an interaction between the containment atmosphere and the containment sump [Ref. 2.3, pg. 41]. Also, following the Standard Review Plan 15.6.5 Appendices A & B [Ref. 2.4], the containment atmosphere leakage and the ESF leakage contributions to doses are evaluated separately and then summed to yield the total doses from the incident. Therefore, it is inferred that the regulatory guidance on the source term for the containment sump water conservatively includes the contribution of iodine washed from containment atmosphere by sprays. The containment is thus modeled as two non-interactive regions, the containment atmosphere and the containment sump, each with separate radionuclide release paths to the environment. This was also verified during informal discussions with the NRC [Ref. 2.16]. The containment atmosphere in this model is assumed to be a single, well-mixed space, as opposed to modeling a sprayed region and unsprayed region as was done in Reference 2.3. This assumption takes credit for the methodology of revision 2 to section 6.5.2 of the Standard Review Plan (SRP) [Ref. 2.4]. According to.SRP 6.5.2, a single, well-mixed space can be assumed if the containment sprays cover at least 90 % of the containment building space and a ventilation system is available for mixing unsprayed spaces in containment [Ref. 2.4, 6.5.2-111.1.c]. The significant unsprayed compartments are the containment dome and most parts of the 590' elevation in containment. After a LOCA, the containment air coolers would be operating. VHX-1, 2, & 3 operate off of emergency diesel generator (EDG) 1-2, and VHX-4 operates off of EDG 1-1. For worst case fan operation with EDG 1-2 lost, VHX-4 would still be operating off of EDG 1-1. Service water is not available to VHX-4, but the fan motor will still be sequenced on. Therefore, even with loss of one EDG, at least one containment air cooler will be circulating 37,500 cfm [Ref. 2.7, Table 6-8] of air in containment. For mixing of the containment dome, VHX-3 & 4 tie into a common 10" riser that draws air from the containment dome. This 10" riser can be seen on References 2.17, 2.18, & 2.19. For mixing of the 590' elevation, all of the air coolers have a hinged plate at the bottom of the ducts that draw from the steam generator compartments. The hinged plates are designed to shear their rivets and open in case of gas expansion caused by a pipe break within the steam generator compartments [Ref. 2.22, pg. 3 & Ref. 2.21] to protect the coolers and fans from internal pressures greater than design. This should occur for a large break LOCA, causing the coolers to draw air from the 590' elevation. As can be seen on Reference 2.20, the discharge from the coolers is at the 625' and 668' elevations which are regions that should be covered by sprays. Therefore, between the coolers and the natural convection forces that would be occurring, adequate mixing should occur during a large break LOCA. For the spray coverage of containment, 1.48E+06 ft3 has been used in all previous MHA analyses for Palisades [Refs. 2.3 & 2.6], which corresponds to 90% of the containment net free volume. The basis

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet ~9~ of 50 for this volume could not be found. However, the 90% spray coverage value has been used in MHA calculations submitted to the NRC for review [Ref. 2.8] and has also been used in safety evaluation calculations by the NRC staff for amendments to the Palisades operating license [Refs. 2.2 & 2.9]. It is inferred from those analyses and calculations that 90% spray coverage of the containment air volume has been accepted as appropriate for Palisades since both CPCo and NRC staff used that value. A basic illustration of the containment model used is shown in Figure 1. 11111 Sprays CTMT Atmosphere I l Iodine Removed by Sprays CTMT Sump FIGURE 1 CONTAINMENT RELEASE PATH MODEL Iodine and Noble ~ Gos from CTMT Atmosphere Leakage ESF Rooms Iodine from Valve Seat Leakage to SIRW Tank ..... ~ ~~ ~,. J ~ Iodine from Valve - -stem and Pump Seal Leakage

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 10 of 50 6.1 RELEASES FROM CONTAINMENT ATMOSPHERE The containment atmosphere will contain noble gas and airborne iodine following an accident in which fuel failures occur. The radionuclides of main concern that will be present in the containment atmosphere are the following: Kr-83m, Kr-85m, Kr-85, Kr-87, Kr-88, Kr-89, Xe-13 lm, Xe-133m, Xe-133, Xe-135m, Xe-135, Xe-137, Xe-138, 1-131, 1-132, 1-133, 1-134, and 1-135. For iodine in the containment atmosphere, several removal mechanisms will exist: radioactive decay, removal by containment sprays and surface plateout, and leakage of the containment atmosphere to the environment at the design leak rate. For noble gas in the containment atmosphere, however, only radioactive decay and leakage of the containment atmosphere to the environment at the design leak rate will occur. The normal containment venting path, through a clean waste receiver tank (CWRT) with the rupture disc removed, is not considered for a release path in the model for the code. SRP Section 15.6.5 [Ref. 2.4, 15.6.5-ID.4] states that the containment vent release path should be considered an additional contributor to the LOCA doses if the position of SRP Section 6.2.4 is not met [Ref. 2.4]. Reference 2.23 predicted hot rod burst to occur at 46 seconds for a double ended guillotine cold leg break. Technical Specifications require all containment penetrations, including the CWRT veri.t, to be automatically isolated within 25 seconds [Ref. 2.5, TS 3.6], which is before fuel melting would begin during a LOCA and is within the guidelines of SRP Section 6.2.4. Therefore, it is not necessary to include the containment vent contribution to the calculated doses from a LOCA at Palisades. The dose contribution from the vent path prior to isolation would also be extremely small if it were to be included, -0.02 rem thyroid at the site boundary [Ref. 2.6, pg. 15]. 6.1.1 NOBLE GAS The initial noble gas activity in the containment is calculated by multiplying noble gas source term values (in Ci/M\\Vi) by the rated thermal power of the reactor core and the fraction of the noble gas activity in the core that is released to the containment atmosphere. This initial activity for each noble gas isotope is illustrated in Equation (1). where (1) ~ = the initial noble gas activity in the containment atmosphere, Ci P = the rated thermal power of the reactor core, MWt S = the activity source term of each isotope, Ci/MWt ~ = fraction of the noble gas activity in the core that is released to the containment atmosphere and subscript "i" denotes the individual isotopes in this and all following equations. Considering radioactive decay and leakage from containment as the only removal mechanisms for noble gas in the containment atmosphere, the rate of change of the noble gas activity in the containment atmosphere with time can be represented by the following equation for each noble gas isotope:

where EA-PAH-91-05 PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET Sheet 11 of 50 (2) ~ = noble gas activity in containment at time "t" A = radioactive decay constant, min1 AL = leak rate from the containment atmqsphere, min1 (same as the containment leak rate converted from %/day) This is very similar to the basic representation of radioactive decay except that another 'decay' term has been added to account for leakage from containment. It should be noted, however, that AL is not constant, but can be treated as a constant over a given time interval since its value only changes at certain points in time. When using Regulatory Guide assumptions for LOCA analysis, the containment leak rate, or AL, only changes after 24 hours at which time it becomes 50% of the containment design leak rate [Ref. 2.1]. The MHACALC code ("the code") is programmed to automatically decrease the value of AL by 50% after 24 hours. Treating AL as a constant, Equation (2) can be integrated to result in the following equation, representing the noble gas activity at any point in time of a given time interval: where ~(t)= activity in containment at time "t" into the time interval, Ci NCA ( \\,) = activity in containment at the beginning of the time interval, Ci A and AL are the same as described above. The release rate of each noble gas isotope from the containment atmosphere at a given time is just the activity in the containment atmosphere multiplied by the leak rate from the containment atmosphere as shown below. (4) where Cl=A = noble gas release rate to the environment from the containment atmosphere at time "t", Ci/min Integrating the release rate over a given time interval then results in the total noble gas activity released from the containment atmosphere during the time interval, as shown in Equation (5). where (5) ~ = noble gas activity released to the environment from the containment atmosphere during the time interval, Ci 11 t = the time span from \\i to t, min

6.1.2 IODINE PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 12 of 50 The equations to represent the iodine activity in the containment atmosphere are slightly more complicated than those for noble gas. There are three iodine removal processes taking place, and three chemical species that react differently to the containment sprays. Following the guidance of Reference 2.1, the three chemical species of iodine that would be present after an accident in which fuel damage occurs are elemental, particulate, and organic. The initial activity in the containment atmosphere of each chemical species of each iodine isotope is calculated using the following equation: N!,.i (0) = PSi fCAi f~ (6) where ~ = the initial iodine activity in the containment atmosphere, Ci P = the rated thermal power of the reactor core, M\\Vi S = the activity source term of each isotope, Ci/M\\Vi ~ = fraction of the iodine activity in the core that is released to the containment atmosphere tF = the fraction of the iodine released in each chemical species. superscript "k" denotes iodine chemical species. The time dependent rate of change of iodine activity in the containment atmosphere can be represented by the following equation for each chemical species of each iodine isotope: where ddt N!,.i ( t) = - (Ai+ AL+ A.;) N!,.i ( t) (7) A.s = spray removal coefficient for each iodine chemical species, milf 1 all other variables are the same as defined in the previous section, but are representing iodine isotopes instead of noble gas isotopes. This is very similar to Equation (2) with the exception that another term has been added to account for the removal of iodine from the containment atmosphere by containment sprays, and that each iodine isotope has three chemical species As with Au As for each chemical species can be assumed to be constant over a given time interval since its value only changes at certain points in time, as will be discussed later in this section. The activity of each chemical species of each iodine isotope in the containment atmosphere at any given point in time of a time interval can be found by integrating Equation (7) to result in the following: where (8) ~(t)= activity in containment atmosphere at time "t" into the time interval, Ci ~ (to)= activity in containment atmosphere at beginning of time interval, Ci The total activity of each iodine isotope in the containment atmosphere is just the sum of the activities of each chemical species of the isotope as shown below.

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 13 of 50 (9) The release rate from the containment atmosphere of each iodine isotope at a given time, as shown in Equation (10), is just the activity in the containment atmosphere multiplied by the containment leak rate. (10) where CkA = iodine release rate to the environment from the containment atmosphere at time "t", Ci/min Being similar to the equations for noble gas release, integrating the iodine release rate over a given time interval results in the total iodine activity released from the containment atmosphere during the time interval, as illustrated in Equation (11). QCAi(t) = t J...LNcii<to~ [1-e-(l.1+l.L+l.fl4t] k*1 A i +AL+ As (11) where ~ = iodine activity released to the environment from the containment atmosphere during the time interval, Ci at = the time span from 1<i to t, min After the containment atmosphere iodine activity and the iodine activity released to the environment during a time interval have been calculated, several conditions for iodine must be checked before performing the calculations for the next time interval. As was mentioned previously, the value of As changes at certain points in time. The code is written so that the value of As for elemental iodine can change at time points given in the input to the code. The code also determines when the maximum elemental iodine decontamination factor, which is specified in the input to the code, is reached. From Reference 2.4 [section 6.5.2], the decontamination factor is defined: "as the maximum iodine concentration in the containment atmosphere divided by the concentration of iodine in the containment atmosphere at some time after decontamination." Relative to elemental iodine, this can be interpreted as the ratio of the initial elemental iodine activity in the containment atmosphere to the activity of elemental iodine in the containment atmosphere at some time after sprays begin. Letting the superscript "k" = 1 denote elemental iodine, the following condition is tested for:

where PALISADES NUCLEAR PI.ANT ENGINEERING.ANALYSIS WORK SHEET 5 L N~i (0) i=l _s ____ ::!::DFmax L N~i(t) i=l EA-PAH-91-05 Sheet 14 of 50 (12) DF max = maximum elemental iodine decontamination factor all variables have been previously defined, remembering that the subscript "i" represents the iodine isotopes. When the condition in Equation (12) is met for the value of DF max specified in the input to the code, l~ is set equal to zero for the remainder of the incident. However, if the sump solution pH falls below 7.0, elemental iodine must be assumed to evolve.back into the containment atmosphere. To account for this, l~ can be decreased by an appropriate amount if the condition in Equation (12) has not been met yet. If l~ has been set to zero, a negative value would account for re-evolution. The code is written so that it will not set l~ equal to zero if it is a negative number. For particulate iodine, the superscript "k" = 2 denoting particulate, the ability to change the value of l~ at specified points in time was not included in the code since particulate removal is a mechanical process and not dependent on spray additives or pH. However, the code does change the value of l~ to a second value given in the input to the code when the activity of particulate iodine in the containment atmosphere has been depleted by a factor of 50, in accordance with Reference 2.4 [section 6.5.2]. Being similar to the test for elemental iodine, the following condition is tested for: 5 L N~i (0) _i_=l ____ :::!:: 50.0 5 (13) L N~i ( t) i=l When the condition in Equation (13) is met, the code changes the value of l~. The code is also set up for a time to be specified in the input deck for when containment sprays stop. When that time is reached, if a time is specified, the code sets 15 for elemental and particulate iodine equal to 0.0 (except when l~ has a negative value to account for iodine re-evolution from the sump.) In accordance with the Standard Review Plan, no spray removal for organic iodine can be accredited [Ref. 2.4, section 6.5.2], and l~ for organic iodine is always set equal to 0. 6.2 RELEASES FROM CONTAINMENT SUMP The sump solution is assumed to contain iodine but is not assumed to contain any noble gas, since all of the noble gas would evolve out of the solution into the containment atmosphere. The initial activity of each iodine isotope in the sump solution is represented by the following,:

where EA-PAH-91-05 PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET Sheet 15 of 50 {14) N5 = initial iodine activity in the containment sump, Ci P = the rated thermal power of the reactor core, MWt S = the activity source term of each isotope, Ci/M\\Vi fs = the fraction of the iodine activity in the core that is released to the sump. As mentioned previously, because of the high fraction of iodine that Reference 2.1 gives as being released to the containment sump (50% of the core's iodine), the iodine activity in the sump is treated as being independent of the iodine activity removed from the containment atmosphere by sprays and plateout. Therefore, the only removal mechanisms for iodine from the containment sump solution are radioactive decay and leakage outside of containment when recirculating the sump water. However, with the current plant configuration at Palisades, two paths for leakage outside of containment must be considered once recirculation of the sump water begins. Engineered Safety Features (ESF) leakage of sump water into the east and west safeguards rooms, through components such as valve stems and pump seals, is one out-of-containment release path that must be considered [Ref. 2.4, 15.6.5 App.* B]. The other out-of-containment release path to consider is valve seat-leakage through recirculation lines leading to the SIRW tank [Ref. 2.10], or to any other area outside containment that could ultimately vent to the environment. Considering these removal mechanisms for iodine from the containment sump solution, the time dependent rate of change of iodine activity in the containment sump solution can be represented by Equation (15) for each iodine isotope. Account is also taken for the sump water volume decreasing with time as leakage outside of containment occurs. It is conservatively assumed that condensation of steam in the containment atmosphere does not affect the sump water volume. where outside d ...: -(" LREsF+ LRsRw) ( ) dt N.si*(t) - "'.+ N.s* t 1 V8 (t) 1 (15) = leak rate of sump water through ESF components, ff /min = leak rate of sump water (from valve seat-leakage) to any area containment that can vent to the atmosphere, ff /min = sump water volume, ff As can be seen in this equation, the chemical species of the iodine in the sump water is not important since there are no different removal mechanisms for the different chemical species as there was for iodine in the containment atmosphere with sprays operating. It should be noted that the code multiplies the ESF leak rate, LResF, specified in the input to the code, by a factor of 2 to remain consistent with the requirements of Reference 2.4 [section 15.6.5, App. B]. The code, however, does not multiply the input value for LRsRW by a factor of 2 since it is questionable whether leakage of that sort would fall under the same requirements, and additional conservatism is provided for the SIR W tank release as will be discussed later. To increase its capabilities, the code was written so that up to four values for ESF

olf* Ir!!** It If* !l"'ll:.
.it. -r.-w. -::;;r PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 16 of 50 and SRW leak rates could be specified in the input, along with times at which the values change.

However, all values of LResF will be multiplied by the factor of 2 mentioned above. Now, Equation (15) must be integrated to obtain the activity of each iodine isotope in the containment sump solution at any point in time of a given time interval. By letting a = V5(0) and b = LResF + LRsRW, the second term in the exponential can be expressed in a form similar to that of Reference 2.28 [pg. A-113, #27], which shows: or for this case: J dx = l:.1n (a+bx) a+bx b t t J b dt =b(-l:.) ln(a-bt) I =ln/a-bt) 0 a-bt b 0 a Using this, the integration of Equation (15) can be completed to result in the following expression: where (16) N5 ( t) = activity in containment sump water at time "t" into the time interval, Ci N5 (to)= activity in containment sump water at beginning of the time interval, Ci V5(to) = sump water volume at beginning of time interval, ff A t = the time span from to to t, min. The release of iodine from the sump water to the environment must be considered separately for the two possible release paths. 6.2.1 RELEASES FROM SAFEGAURDS ROOMS The ESF leakage into the safeguards rooms is to account for expected leakage from valve stems, pump seals, and from failure of an ESF passive component, such as a pump seal [Ref. 2.4, SRP 15.6.5, App.

PALISADES NUCLEAR PI.ANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 17 of 50 'B]. For the ESF leakage, the release rate of iodine to the environment at a given time is equal to the iodine concentration in the sump water multiplied by the ESF leak rate, and divided by a partition factor and any applicable retention or decontamination factor. The partition factor accounts for the fact that only a percentage of the iodine will evolve out of the solution into the ESF room atmosphere. The retention factor accounts for the retention of iodine released in the safeguards rooms due to the automatic isolation of the ventilation in the rooms. Credit for a retention factor can be taken because with the ventilation isolated, little air flow out of the rooms should exist, which allows iodine to plate-out on walls and surfaces. After taking credit for the partition and retention factors, the iodine is assumed to be instantaneously released to the environment with no hold up time for traveling through the Auxiliary building. Equation (17) is used to represent the release rate of each iodine isqtope from the ESF rooms at any given time. where cissFi(t) = LRssF Nsi(t) e-J.jt= LREsF Nsi(to) e-A.it (17) DFssFPFssF Vs(t) DFEsFPFEsF Vs(to) '£.sF = iodine release rate to the environment from ESF leakage at time "t", Ci/min DFESF = iodine retention factor for the safeguards rooms due to the automatic isolation of the ventilation PFESF = partition factor for iodine in the sump water released to the safeguards rooms Integrating Equation (17) over a given time interval results in the total activity of each iodine isotope released to the environment from ESF leakage during the time interval. Using Reference 2.28 [pg. A-111, #12], integration of Equation (17) results in the following: where (18) OesF = iodine activity released to the environment from ESF leakage during the time interval, Ci fl. t = the time span from 1(i to t, min. 6.2.2 RELEASES FROM SIRW TANK Leakage of sump water into the SIRW tank is to account for possible seat-leakage of valves in the recirculation lines leading to the SIR W tank, or to any other area outside of containment that is vented to the environment. This potential leak path has not been previously analyzed and the valves in the recirculation lines to the SIRW tank are not currently seat-leak tested (see E-PAL-91-035). The allowable leakage for these valves is expected to be low, less than one gallon per minute. For the seat-leakage of valves isolating the SIRW tank from sump water, it is assumed that as iodine leaks through the valves, homogeneous mixture and equilibrium partitioning occur instantaneously in the SIR W tank and the line leading to the tank. This is a conservative assumption since it would take some amount

.If \\flt. 5 -tl.* ..Jb""'!r".

u.!t*

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 18 of 50 of time for the iodine to mix in the water of the tank and line leading to it, and for equilibrium partitioning of the volatile iodine to occur. The rate at which iodine enters the line leading to the SIR W tank is just the iodine concentration of the sump water multiplied by the total leak rate through the valves. The following equation can be used to represent this leak rate for each iodine isotope: (19) where <iv...v = iodine leak rate through recirculation line valves at time "t", Ci/min. Integrating Equation (19) over a given time interval, as was done to obtain Equation (18), results in a representation of the total activity of each iodine isotope that entered the SIRW tank during the time interval, as shown below. where Q . ( t.) = ft: q' . ( t) dt = [ LRsRW Nsi (ta) l [ 1 - e -). 1 b. t:] VLVi VI.Vi v ( t ) A. t:0 S a 1 (20) Ovt.v = iodine activity that entered the SIRW tank from valve seat-leakage during the time interval, Ci A t = the time span from to to t, min To represent the total activity in the SIR W tank at any point during a time interval, the iodine activity in the tank at the beginning of the time interval and the iodine activity released to the environment from the tank during the time interval need to be considered. If radioactive decay in the SIR W tank is accounted for, a term to decay the activity in the tank at the beginning of the time interval should be included. For conservatism when calculating the iodine activity in the SIRW tank, the iodine released to the environment during a time interval will not be subtracted from the tank activity until the next time interval. The following equation can be used to represent this: where AsRwi ( t) = [AsRwi (ta) - OsRwi (ta)] e-11 b.t: + OVLvi ( t) AsRW = the total iodine activity in the SIR W tank at time "t", Ci AsRW(to) = the total iodine activity in the SIRW tank at "to", Ci (21) OsRW(to) = the iodine activity released through the the SIRW tank vent during the previous time interval, Ci A t = the time span from to to t, min. When the leakage to the SIR W tank begins, OsRW = 0 assuming the iodine initially in the SIR W tank. is negligible. To solve Equation (21) after the leakage begins, the activity released through the vent to the environment during each time interval is needed. Since the SIR W tank vent is a small, uspside down "U"-shaped pipe off the top of the tank, no significant airflow should normally exist in or out of

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 19 of 50 the tank if it remains at a constant water volume. Changes in density could cause air flow out of the tank if the tank heats up as the sun shines on it, but along the same philosophy, air would flow into the tank as it cooled down at night. At very small leak rates, as are expected, the sump water entering the SIRW tank would not be expected to significantly heat up the air of the tank either. Therefore, the activity released through the vent can be characterized by the concentration of iodine in the SIR W tank air volume multiplied by the volume of air displaced from the tank as the water level in the tank increases. However, a multiplication factor will be used to account for diffusion out of the tank or to add conservatism if desired. This multiplication factor can be specified to be any value and will be used as an input to the code. The volume of air displaced from the tank is the same as the volume of sump water that has entered the tank through the recirculation line valves. Since the iodine activity in the SIRW tank is increasing with time, the iodine activity released from the tank to the environment during a time interval is conservatively based on the air concentration in the tank at the end of that time interval. This shown is in the following equation.

where (22) OsRW = the iodine activity released from the SIRW tank during the interval to tot, Ci Cui,. = the iodine concentration in the SIRW tank air volume at time "t", Ci/ff ~ = multiplication factor for the rate at which iodine exits the SIRW tank to account for diffusion through the vent or for added conservatism A t = the time span from to to t, min. Now a correlation between the total iodine activity in the SIRW tank and the iodine activity in the air volume of the SIR W tank is needed. First, it must be understood that only volatile forms of iodine, such as l.z and CH31, will evolve out of the liquid [Ref. 2.25, pg. 30]. Equation (21) can also be used to represent the activity of the volatile iodine in the SIR W tank if the total activity,.t\\;RW, is replaced with the volatile iodine activity, J\\2, and the total iodine activity entering the tank is multiplied by the fraction that is volatile, Ovt.v * ~2 ; where ~2 is the fraction of the iodine in the sump that is in a volatile form. The equilibrium iodine partition coefficient is then used to account for the fraction of the volatile iodine that evolves out of the solution. The equilibrium partition coefficient for a single volatile species of iodine is defined as the ratio of the concentration of that volatile species in the liquid to the concentration of that volatile species in the air at equilibrium [Ref. 2.25, pg. 6]. The volatile form of iodine reaching the SIR W tank and partitioning out of solution would be l.z [Ref. 2.30] since the pH of the sump solution is controlled above a value of 7.0. Therefore, the concentration of l.z in the air can be represented by the concentration of l.z in the liquid divided by the appropriate partition coefficient for the temperature of the water in the SIRW tank. The non-volatile iodine in the SIRW tank will simply remain in solution. Representing the concentrations as activity divided by the volume, the following equation can be used. _A_a_ir_i_(_t_) = __ A..;;;.11=* q=i_(_t_) _ Vair ( t) PFsRW Vliq( t) (23)

where PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 20 of 50 A,. = the l.z activity in the SIR W tank air volume, Ci l\\q = the l.z activity in the SIR W tank liquid volume, Ci V * = the SIRW tank air volume, ff V1q = the SIRW tank liquid volume, ft.3 PF5RW = the l.z partition coefficient in the SIR W tank The total l.z activity for each isotope in the tank at any point in time is just the activity in the air plus the activity in the water. The l.z activity in the SIRW tank liquid volume in Equation (23) can be solved for and substituted into an equation for the total l.z activity as shown below. {24) where 1\\2 = the total l.i activity in the SIR W tank, air plus liquid, volume, Ci Solving Equation (24) for the activity in the SIRW tank air volume and dividing by the SIRW tank air volume yields the iodine concentration in the SIR W tank air volume, all of which will be l.i, as shown below. (25) where V.. (t) can be represented by Vtank - Vuq(t). 6.3 TOTAL RELEASE AND DOSES For noble gas, the total activity released over each time interval is just that released from the containment atmosphere, or ~ shown previously in Equation (5). For iodine, however, the total activity released during each time interval is the sum of that from the containment atmosphere, ESF components, and recirculation line valves as shown previously in Equations (11), {18), & (22) for~' OesF, and OsRW respectively., The code also calculates the release rates of each noble gas and iodine isotope, and creates two output files for direct use as release rate input decks in the CONDOSE code for control room habitability calculations [Ref. 2.29]. However, the release rate equations that were

derived previously in this analysis are not used to calculate the release rates written to the output files.

The reason for not using the release rate equations given previously is that the release rate changes at almost every instant in time with those equations. Instead, the code adds up the release of each radionuclide during a time interval of interest for control room habitability calculations (time intervals are specified in the input to the code) and divides by the time span of the interval. This results in an "averaged", or uniform release rate over each time interval of interest by simply using the total release during that interval. Different release rates are calculated for the two output files for use in control room habitability calculations due to different assumed locations for the releases. The containment. atmosphere leakage of iodine and noble gas and the ESF leakage of iodine are all assumed to be.

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 21 of 50 released from the location of the stack, with the release rates being calculated and written to one output file. The valve seat-leakage to the SIR W tank releases from a completely different location, being directly above the control room. Therefore, the release rates of iodine from the SIRW tank are calculated separately and written to a separate output file. Offsite doses must be calculated at the site boundary (SB) for the first 2 hours after the accident, and at the low population zone distance (LPZ) for the duration of the release [Ref. 2.11]. Thyroid and whole body doses are calculated at each. Since the distance between the two assumed release locations is much smaller than the the distance to either offsite location, no differences for offsite atmospheric dispersion factors are accounted for due to the difference between the two release locations. For calculating the offsite dose, the methods and dose conversion factors of ICRP-30 [Ref. 2.12] are used. This is the same methodology as used in the most recent revision to 10 CFR 20 [Ref. 2.11]. Submersion doses are calculated for exposure to clouds of noble gas, and inhalation doses are calculated for inhalation of iodine. The dose calculated to each individual organ or tissue from inhalation or ingestion of a radionuclide is called the committed dose equivalent (CDE) using this methodology. If the CDE to each organ that receives a dose is multiplied by an appropriate weighting factor for the particular organ, and the product of the weighting factors and the CDEs are summed, the committed effective dose equivalent (CEDE) to the whole body is obtained. The CEDE relates the dose to organs from intake of a radionuclide to the stochastic effects if the whole body were irradiated uniformly. The dose calculated to each organ or tissue from external exposure from submersion in a cloud of noble gas is called the deep-dose equivalent. The deep-dose equivalent to each organ or tissue can also be multiplied by an appropriate weighting for each organ and summed to yield the total whole body dose from external radiation. The total effective dose equivalent (TEDE) to the whole body is then the sum of the CEDE and the total whole body dose from external radiation. For the analysis of offsite doses after design basis accident, the dose to the thyroid and that to the whole body are the doses of main concern since the 10 CFR 100 [Ref. 2.11] limits are specified for those. For inhalation of iodine, the CDE to the thyroid and the CEDE are calculated by the code separately for each of the three release paths and for total release. For external exposure to noble gas, the deep-dose equivalent to the thyroid and the dose to the whole body are calculated by the code for containment atmosphere leakage only since no noble gas is assumed present in the sump. The whole body dose from exposure to noble gas and the CEDE from inhalation of iodine are then summed to yield the TEDE. The intake of each iodine isotope during a time interval is found by multiplying the appropriate breathing rate by the atmospheric dispersion factor and the activity of each isotope released during the time interval, which can be gathered from the units of each. The CDE to the thyroid from the intake is then found by multiplying the amount of each isotope inhaled by the committed dose equivalent per unit intake (dose conversion factor) for each isotope, as can be seen in Reference 2.12 [Part 1, pg. 8]. This is shown in the following equation: HThy, 50 :::: DCFinh BR ~ Q {26)

where -it* ~* 1i* !!:: \\!.~*-.. u.lf.. *'""'Ir..,,..,.. ;;;;;!J:. PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 22 of 50 ~,50 = committed dose equivalent to the thyroid from inhalation of each iodine isotope during the time interval, Rem DCF~ = thyroid inhalation dose conversion factor for each iodine isotope, or committed dose equivalent per unit intake, Rem/Ci-inhaled BR = appropriate breathing rate for the time interval of interest, m3 /sec x/O = atmospheric dispersion factor, for SB or LPZ, for the time interval, sec/rrf Q =activity of each iodine isotope released during the time interval for each release path, Ci. The CDE to the thyroid from each iodine isotope and each time interval is then added to yield the total CDE to the thyroid from each iodine release path. That from each release path is then added to give the total CDE to the thyroid from the event. For calculation of the CEDE from the inhalation of iodine, Equation (26) is still used, but the dose conversion factor that is used in the equation is different. The dose conversion factor from ICRP-30 for calculating the CEDE from each iodine isotope is the sum of weighted dose conversion factors for every organ listed for the iodine isotope. The weighted dose conversion factor for each organ is simply the dose conversion factor multiplied by the weighting factor appropriate for each organ. Summing the weighted dose conversion factors makes calculating the CEDE quite easy. The alternate method for calculating the CEDE is to calculate the dose received by every organ that receives a dose from each isotope, then multiply the dose to each of the organs by the appropriate weighting factor, and sum the results. These calculations are performed separately for the SB and LPZ, using the appropriate atmospheric dispersion factors, keeping in mind that the SB dose is only calculated for the first two hours of the event. The dose to the whole body from external exposure received during a time interval can be found by multiplying the activity released by the atmospheric dispersion factor and the dose rate conversion factor. This is similar to the formulas shown in Reference 2.1, except that the disintegration energy and units conversion are lumped into one parameter for the ICRP-30 methodology. This equation for dose to the whole body from external exposure is shown below. where (27) Hwa = deep-dose equivalent to the whole body from exposure to each noble gas isotope during the time interval, Rem DCF sub = whole body dose rate conversion factor for submersion in a cloud, or dose equivalent rate from exposure to a unit concentration, of each noble gas isotope, (rem/sec)/(Ci/m 3 ) x /0 = atmospheric dispersion factor as defined for Equation (26) Q = represents the total activity of each noble gas isotope released during the time interval, Ci This equation is also used for the deep-dose equivalent to the thyroid from noble gas, just with dose rate conversion factors for the thyroid as opposed to whole body equivalent. As was mentioned above for calculating the CEDE from inhalation, the dose rate conversion factor for the dose to the whole

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 23 of 50

~----------------

body from external exposure to each noble gas isotope should be the sum of the weighted dose rate conversion factors for every organ listed in ICRP-30 for the isotope. The total dose to the whole body from external exposure is calculated by summing the dose received from each radionuclide and each time interval. As is done for the CDE to the thyroid, the dose to the whole body is calculated separately for the SB and LPZ using the appropriate atmospheric dispersion factors. The TEDE is then calculated by summing the CEDE received from the total iodine release and the dose to the whole body received from the noble gas release. The breathing rates and atmospheric dispersion factors are treated in accordance with Reference 2.1. Three breathing rates are to specified in the input to the code: 0 to 8 hour value, 8 to 24 hour value, and a value for 24 hours to the end of the event. Four LPZ atmospheric dispersion factors are specified in the input to the code: 0 to 8 hour value, 8 to 24 hour value, 1 to 4 day value, and 4 to 30 day value. The code automatically uses the appropriate values for each time interval, provided that they are specified correctly in the input deck. The SB atmospheric dispersion factor has only one value since SB doses are only calculated for 0 to 2 hours. 6.4 DOSE EQUIVALENT IODINE 131 The code has also been programmed with the ability to create an output deck that can be used directly as an input deck to the RETRAN code PLOTER module for creating and printing plots of the iodine acitivty in the containment atmosphere versus time. However, with five iodine isotopes and three chemical species for each isotope, a large number of plots would have to be made. Therefore, the dose equivalent iodine 131 activity is used. Dose equivalent iodine 131 (DE 1-131) activity can be defined as the activity of 1-131 that would result in the same dose to the thyroid as the collective doses from the individual iodine isotopes present. This can be represented by the following equation: where DCFn32 DCFz133 DCFz134 DCFn35 NDE z131 = Nz131 + C Nz132 + Nz133 + DCF NI134 + DCF Nz135 (28) D 'Fz131 DCFz131 I131 z131 Noe 1131 = dose equivalent 1-131 activity, Ci N = activity of each iodine isotope, Ci DCF = thyroid inhalation dose conversion factor for each iodine isotope, Rem/Ci-inhaled. The code calculates the DE 1-131 activity for elemental iodine, particulate iodine, organic iodine, and the total. The code writes DE 1-131 activities to an output deck at the first two time steps. After the first two time steps, the code compares the DE-131 activities for each of the types to the activity at the last time step that it wrote to the output deck. Whenever the activity changes by + or - 3% the code writes to the output deck the activity at that time step and at the immediately previous time step if it has not been written already. The reason for writing the activity at the immediately previous time step is to avoid a misrepresenting plot if there is a drastic change in activity over any one time interval.

-lf'.lf*lf:.5-.""llf A *. """if: PALISADES NUCLEAR PI.ANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 24 of 50 The code also writes to the output deck all of the other information required to use it directly as the input deck to the RETRAN code PLOTER module without having to make any changes. This is discussed in more detail later in this analysis. 7.0 INPUT DECK DESCRIPTION The input deck is described line by line below. For each parameter of the input deck, the variable name used in the code, the Fortran format for the read statement, and a description of the limitations for the parameter is given. Recommended values are also given for each parameter, with references if appropriate. Examples of the input decks for the test cases can be seen on the attached microfiche. line 1 TITLE [A80] TITLE is just a description of the input deck or the case to be executed, and will be printed at the top of the output deck. line 2 DEBUG [14] DEBUG is the input for the debug option. A value of 0 will cause the code to write almost every variable at every point in time to the output deck. This will generate thousands of lines of output, and the code will not finish execution if the execution is for a large number of time steps. Any value greater than 0 for the debug option will result in normal execution of the code. line 3 DURATION [110] DURATION is the number of time steps that program execution is to occur for. The code counts by one minute time steps, so DURATION is the amount of time, in minutes, that the calculations are to be performed for. A normal execution for a LOCA or the MHA is for 30 days, or 43200 minutes. Generally, this value will be 43200 unless using the debug option set to 0. If the debug option is used, set to 0, a value of 300 or less is recommended for DURATION, as execution will be terminated before complete if a much larger value is used.

line 4 PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET POWER, CONTLR, VSUMP [Fl0.1, Fl0.2, Fl0.1] EA-PAH-91-05 Sheet 25 of 50 POWER is the thermal power of the reactor in units of M\\Vi. Generally, for accident analyses, a 2% power uncertainty is assumed so that 102% of the rated thermal power of the reactor is used. Since 2530 MWt is the rated thermal power of Palisades, 2580.6 should normally be used for MHA analyses. CONTLR is the containment leak rate in units of %/day. The design leak.rate at Palisades is 0.1 %/day [Ref. 2.7, section 5.8] which should generally be used for all applications. VSUMP is the volume of sump water in the containment to be recirculated, in units of ft3. Using a minimum value is conservative since it would increase the concentration of iodine in the solution. This value can be obtained for current plant conditions from Reference 2.27. The minimum value after recirculation begins is normally appropriate. line 5 FNG, FIA, FIS [3F10.1] FNG is the fraction of the core's noble gas inventory that is released to the containment atmosphere, in %. For MHA calculations, this value should always be 100.0% following the guidance of References 2.1and2.4. FIA is the fraction of the core's iodine inventory that is released to the containment atmosphere, in %. This value should always be 25.0% when performing MHA calculations in accordance with References 2.1 and 2.4. FIS is the fraction of the core's iodine inventory that is released to the containment sump and mixed in the containment sump solution, in %. This value should always be 50.0% when performing MHA calculations in accordance with Reference 2.4. line 6 FCF(l), FCF(2), FCF(3) [3F10.1] FCF is the fraction of the iodine released to the containment atmosphere that is in each chemical form. FCF(l) is the fraction of the iodine in the containment atmosphere in elemental form, in%. This value is 91.0% following the guidance of References 2.1 and 2.4. FCF(2) is the fraction of the iodine in the containment atmosphere in particulate form, in %. This value is 5.0% following the guidance of References 2.1 and 2.4.

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 26 of 50 FCF(3) is the fraction of the iodine in the containment atmosphere in organic form, in %. This value is 4% following the guidance of References 2.1 and 2.4. line 7 DFESF, PFESF, PFSRW, KSUBD, VTANK, VSRWLIQ, FI2 [6F10.1,E10.2] DFESF is the iodine decontamination factor, or retention factor, for any ESF leakage, accredited due to automatic isolation of the ventilation in the safeguards rooms and the subsequent plate-out of iodine. For MHA calculations, the NRC has given Palisades credit for a value of 2.0 for this factor [Ref. 2.2, pg. 26]. If no retention factor is to be conservatively used for ESF leakage (assuming all of the iodine released from the solution exits the rooms), a value of 1.0 should be specified. PFESF is the iodine partition factor for ESF leakage. This is used to account for the fact that only part of the iodine will evolve out of solution. For MHA calculations, Reference 2.4 [section 15.6.5] directs the use of a value of 10.0 if the water temperature of the leakage is below 212°F. If the water temperature of the leakage is above 212°F, Reference 2.4 directs the use of whichever is greater, the factor of 10.0 or a factor accounting for the fraction flashing to steam, from which the factor of 10 would probably be more limiting. However, Reference 2.4 [15.6.5] also states that other values can be justified based on actual sump pH. Since the ESF leakage is sump water, the same partition coefficient factor used in containment is appropriate, and should be much larger than 10. The flashing fraction may tum out to be more limiting when compared to the containment sump partition factor. If no ESF leakage partition factor is used (conservatively assuming all of the iodine evolves out of solution), a value of 1.0 should be specified. PFSR W is the equilibrium partition factor for the volatile forms of iodine for leakage through the recirculation lines to the SIRW tank. Reference 2.25 can be consulted for determination of partition coefficients. For the volatile l..z, Reference 2.25 and Reference 2.30 describe methods for calculating the partition coefficient. Any other decontamination factor that may become applicable for recirculation line leakage can be used in conjunction with the partition factor by multiplying the partition factor and the decontamination factor together. If no partition or decontamination factor is to be used for the recirculation line leakage, or if that leak path is not applicable, a value of 1.0 should be specified. KSUBD is a user defined multiplication factor to enhance the rate at which iodine exits the SIRW Tank. The code has been written such that the iodine exits the tank at the rate which air is being. displaced. The rate at which iodine is exiting the tank will be multiplied by this factor. It can be used to add conservatism or to acount for any diffusion out of the SIRW Tank vent that would occur. From infromal telephone discussions with the NRC, a factor of 2 as is specified by the Standard Review Plan for ESF leakage would conservatively encompass uncertainty in diffusion out of the SIR W tank vent. If no factor to account for additional release from the tank is to be used, a value of 1.0 should be specified. VTANK is the entire volume of the SIRW tank, in ft3. This value includes air space, and not just usable water volume. This value will be used for calculating the air volume in the tank, which is needed to

-ii: ll a* II'.:'. li"'l.I. .,II;.,,..~, It.If* PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 27 of 50 determine the iodine concentration, as a function of time after leakage of sump water into the tank begins. The total air volume in the tank can easily be calculated from the dimensions of the tank. Even if SIRW tank leakage is not going to be accounted for, a dummy value greater than 1.0 needs to be specified. VSRWLIQ is the volume of water present in the SIRW tank when RAS (recirculation actuation signal) is generated, in ft3. When the tank is isolated after RAS, approximately 20000 gallons of water should be left [Ref. 2.5, TS 2.16]. The actual value in the SIRW tank and the lines leading to it should be calculated. Even if SIRW tank leakage is not going to be accounted for, a dummy value greater than 1.0 and less than VTANK needs to be specified. FI2 is the fraction of the total iodine activity entering the SIRW tank that is in a volatile form. If all of the iodine entering the SIRW tank is conservatively assumed to be in a volatile form, a value of 1.00E+OO should be specified. If the sump water is controlled at a pH:<!: 7 and the SIRW tank pH is around 5, the predominant volatile form will be ~ and a value of 3.00E-04 is appropriate [Ref. 2.25, pg. 26 & Ref. 2.30]. The value of 3.00E-04 is more of a bounding value, and a more conservative value should be considered if very high leak rates into the SIR W tank or very high dose rates in the SIRW tank are expected. Specifying a value of O.OOE+OO will prevent any iodine release from the SIRW tank from being accounted for. line 8 BREATH(l), BREATH(2), BREATH(3) [3E10.2] BREATH is the breathing rate to be used in the thyroid dose calculations during each time interval. BREATH(l) is the 0 to 8 hour breathing rate, in units of m3 /sec. Following the guidance of Reference 2.1, this value should always be 3.47E-04 m 3 /sec. BREATH(2) is the 8 to 24 hour breathing rate, in units of m3 /sec. Following the guidance of Reference 2.1, this value should always be 1.75E-04 m3 /sec.. BREATH(3) is the breathing rate from 1 day throughout the duration of the incident, in units of m 3 /sec. Following the guidance of Reference 2.1, this value should always be 2.32E-04 m 3 /sec. line 9 CIBQSB [El0.2] CHIQSB is the 0 to 2 hour site boundary atmospheric dispersion factor, in units of sec/m3

This should be the maximum value for 0 to 2 hours at the site boundary listed in Reference 2.7 [Table 2-17].

line 10 PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET LPZCHI(l), LPZCHI(2), LPZCHI(3), LPZCHI(4) [4E10.2] EA-PAH-91-05 Sheet 28 of 50 LPZCHI is the low population zone atmospheric (LPZ) dispersion factor to be used for the thyroid and whole body dose calculations during each time interval. LPZCHI(l) is the 0 to 8 hour LPZ atmospheric dispersion factor, in units of sec/rrr. This should be the maximum value for 0 to 8 hours at the LPZ listed in Reference 2.7 [Table 2-18]. LPZCHI(2) is the 8 to 24 hour LPZ atmospheric dispersion factor, in units of sec/m3

This should be the maximum value for 8 to 24 hours at the LPZ listed in Reference 2.7 [Table 2-18].

LPZCHl(3) is the 1 to 4 day LPZ atmospheric dispersion factor, in units of sec/m3

This should be the maximum value for 1 to 4 days at the LPZ listed in Reference 2.7 [Table 2-18].

LPZCHl(4) is the 4 to 30 day LPZ atmospheric dispersion factor, in units of sec/m3

This should be the maximum value for 4 to 30 days at the LPZ listed in Reference 2.7 [Table 2-18].

line 11 SPRAPR(l), SPRAPR(2) [Fl0.2, F10.3] SPRAPR is the spray removal coefficient for particulate iodine. SPRAPR(l) is the spray removal coefficient for particulate iodine when containment sprays begin, in units of ht1

This coefficient should be calculated in accordance with Reference 2.4 [section 6.5.2] and is dependent upon the fall height of the spray drops, the containment net free volume, the spray flow rate, and the diameter of the spray drops. Reference 2.26 is the most recent calculation of all spray removal coefficients, and is in accordance with Reference 2.4 [section 6.5.2].

SPRAPR(2) is the spray removal coefficient for particulate iodine after 98% of the particulate iodine has been removed from the containment atmosphere (depleted by a factor of 50), in units of hf1, following the methodology of Reference 2.4 [section 6.5.2]. Its value should be the value used for SPRAPR(l) reduced by a factor of 10 following Reference 2.4. lines 12 - 16 TEL(k), SPRAEL(k) [110, F10.3] TEL(k) are five times from the initiation of the event, in minutes, at which the elemental iodine removal by sprays starts and changes. TEL( 1) should be the time at which full sprays are achieved in containment, generally around 1 minute. Following the methodology of Reference 2.4 [section 6.5.2], the removal coefficient for elemental iodine should not change from the time full sprays are achieved until the maximum elemental iodine decontamination factor (discussed in Section 6.1.2) is reached.

PALISADES NUCLEAR Pl.ANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 29 of 50 However, if the pH of the sump water is predicted to fall below 7.0 and iodine re-evolution must be accounted for, the times at which the pH falls below 7.0 can be specified in conjunction with an adjusted value for the spray removal coefficient. If only one spray removal coefficient is used and iodine re-evolution will not occur, TEL(l) on line 12 should be the time at which full sprays are achieved *and a value of 0 should be specified for TEL(2), TEL(3), TEL(4), and TEL(5) on lines 13 - 16 respectively.

All values should be specified as whole numbers and chosen conservatively if the actual value is not a whole number (i.e. if full spray is achieved at 1.5 min., use 2 min.) SPRAEL(k) are five spray removal coefficients for elemental iodine, in units of hr-1, starting at each of the corresponding times of TEL(k). This coefficient should be calculated in accordance with Reference 2.4, which has been done in Reference 2.26. Generally, only one value should be used, SPRAEL(l), when using the guidelines of Reference 2.4 [section 6.5.2] and maintaining the sump solution pH above 7.0. Should the pH of the sump water be predicted to fall below 7.0, the re-evolution of elemental must be accounted for in one of tw~ ways. If spray removal is still occuring while the pH is below 7.0, the removal coefficient can be decreased by an appropriate amount. However, if the pH is below 7.0 after spray removal has stopped, a negative value for the removal coefficient can be used to account for the re-evolution. Since there is no standard methodology for determining iodine re-evolution rates, the appropriate values would have to be determined at such time that they were used. These values can be specified with the corresponding times at which it occurs. A value of 0.0 should usually be specified for SPRAEL(2), SPRAEL(3), SPRAEL(4), and SPRAEL(5) on lines 13 - 16 respectively, if they are not going to be used. The value of SPRAEL(k) will automatically be set equal to 0.0 when the maximum elemental decontamination factor is reached, as discussed in Section 6.1.2 of this analysis, unless the value of SPRAEL(k) is negative to account for re-evolution. line 17 DFMAX, STOPSPRA [Fl0.2, 110] DFMAX is the maximum elemental iodine decontamination factor. This factor determines the time at which containment sprays are no longer effective for removing elemental iodine. When the maximum elemental iodine decontamination factor is reached, the code will set the spray removal coefficient for elemental iodine equal to 0.0 for the remainder of the event, unless the removal coefficient is negative to account for iodine re-evolution. This occurs regardless of the times and values specified in lines 13 - 16 of the input deck. The value of this factor should also be calculated in accordance with the guidelines of Reference 2.4 [section 6.5.2]. STOPSPRA is the time at which operators are assumed to terminate the containment spray, in minutes. When this time is reached, all spray removal of iodine is set equal to 0.0, except for that of elemental iodine when it has a negative value to account for iodine re-evolution. This value should be specified as 0 if a spray stop time is not going to specified. Generally, the condition for DFMAX is reached before 24 hours so a time for stopping the sprays only ends particulate iodine removal. The value must be specified as a whole number and chosen conservatively if the actual value is not a whole number (i.e. if sprays stop at 1440.5 min., use 1440 min.)

lines 18 - 21 nit-ii-I\\' It:::. ":!!'* ..11\\..-Wt;;'.;.ll:..::;i;. PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET TESF(k), LRESF(k), TSIRW(k), LRSRW(k) [I10,F10.1,110,F12.3] EA-PAH-91-05 Sheet 30 of 50 TESF(k) are four times from initiation of the event, in minutes, that the ESF leak rate starts, changes, and/ or stops. The first value will be the time at which recirculation of sump water begins and can be any value including 0, but should normally be the minimum time to RAS of 19 minutes assuming that time 0 is the beginning of the accident. For MHA calculations in accordance with Reference 2.4 [section 15.6.5], only one value, TESF(l) on line 18, should be specified since the Technical Specification maximum leakage is to be assumed to start at recirculation and continue for the remainder of the event. If the ESF leak rate is not assumed to change throughout the event, the values of TESF(2), TESF(3), and TESF(4) on lines 19 -21, respectively, should be specified as 0. All values must be specified as whole numbers and should be chosen conservatively if the actual value is not a whole number (i.e. if leakage starts at 19.5 min., use 19 min.) LRESF(k) are four possible ESF component leak rates, in units of gpm. Normally, only one value will be used, LRESF(l) on line 18, which should be equal to the Technical Specification limit of 0.2 gpm [Ref. 2.5, TS 4.5]. More than one leak rate can be specified to correspond with the times of TESF(k) if the leak rate is assumed to change for some reason. If only one ESF leak rate is being used, LRESF(2), LRESF(3), and LRESF(4) on lines 19 -21, respectively should be specified as 0.0. It should be noted that the code automatically multiplies the value of LRESF(k) by a factor of 2 in accordance with Reference 2.4 [section 15.6.5]. The code also automatically changes the units to ff /min to be consistent with all volumes used for calculations. TSIRW(k) are four times from initiation of the event, in minutes, that the recirculation line leak rate starts, changes, and/or stops. This was added to encompass the recirculation line valve seat-leakage and may not be applicable depending on any future plant modifications to mitigate this leakage. If this leakage is not applicable, values of 0 should be specified for TSIRW(k) on lines 18 - 21. Values of 0 should also be specified for the remainder of the times if less that four times will be used. Note though, that a value of 0 can be specified to start the leakage if a corresponding value of LRSRW(k) is specified. All values must be specified as whole numbers and should be chosen conservatively if the actual value is not a whole number (i.e. if leakage starts at 19.5 min., use 19 min.) LRSRW(k) are four possible recirculation line leak rates, in units of gpm. The leak rate can be specified to change at the times corresponding to values of TSIRW(k), or 0.0 can be specified if the leak rate is not applicable. Values of 0.0 should also be specified for all leak rates corresponding to a TSIRW(k) value of 0. The code does not multiply this leak rate by a factor of 2, as LRESF(k) is, since the Standard Review Plan does not* specifically address this type of leakage. This value is also automatically changed to units of ft3 /min by thy code.. lines 22 - 39 SOURCE(i), LAMBDA(i), DCF(thyroid,i), DCF(whole body,i) [4F10.1]

PALISADES NUCLEAR PI.ANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 31 of 50 SOURCE(i) is the source term for each radionuclide, in units of Ci/MW1* The order in which the radionuclides occur is shown below. These values have generally been taken from Reference 2.13 for all accident analyses at Palisades, due to the unavailability of plant specific calculations. LAMBDA(i) is the radioactive decay constant for each radionuclide, in units of miii1

These values can be obtained from Reference 2.14.

DCF(thyroid,i) is the thyroid committed dose equivalent dose conversion factor for inhalation of iodine and the thyroid deep-dose rate conversion factor for submersion in a cloud of noble gas. The units for the input deck Rem/Ci-inhaled for iodine isotopes and (Rem/sec)/(Ci/rrf) for noble gas isotopes. These values must be obtained from Reference 2.12 for the thyroid organ, noting that the units must be converted for use in the input deck. These values are for the noble gas isotopes on lines 22 - 34, and for iodine isotopes on lines 35 through 39. DCF(whole body,i) is the committed effective dose equivalent dose conversion factor for inhalation of iodine and the whole body equivalent dose rate conversion factor for submersion in a cloud of noble gas. The units must be the same as for the thyroid dose and dose rate conversion factors. These values are not simply listed in Reference 2.12. These values for each radionuclide must be obtained from Reference 2.12 by summing the weighted dose (or dose rate) conversion factors for every organ that receives dose from the radionuclide. The units listed in Reference 2.12 must also be converted for use in the input deck. It should be noted that Kr-89 and Xe-137 do not have dose conversion factors in ICRP30, and therefore do not result in a dose. These two nuclides were originally included in the code for using now outdated dose calculation methods and were not removed when the code was written to use ICRP30 methodology. The dose conversion factors for this two nuclides should be simply specified as O.OOOE-00. The order of the radionuclides for lines 22 through 39 are as follows: line 22 - Kr-83m line 23 - Kr-85m line 24 - Kr-85 line 25 - Kr-87 line 26 - Kr-88 line 27 - Kr-89 line 28 - Xe-13 lm line 29 - Xe-133m line 30 - Xe-133 line 31 - Xe-135m line 32 - Xe-135 line 33 - Xe-137 line 34 - Xe-138 line 35 - 1-131 line 36 - 1-132 line 37 - 1-133 line 38 - 1-134 line 39 - 1-135

line 40 INTRVALS [110] PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 32 of 50 INTR V ALS is the number of time inteivals that radionuclide release rates are to be calculated for and written to output files for use in the CONDOSE code for control room habitability calculations. This can be any value up to 100, but need not be that many. Since the code calculates the radionuclide release rates by adding the total activity of each radionuclide released during a time period and dividing by the length of the time period, the time inteivals should be chosen to correspond with most of the points in time that the release rates will change by any large amount. Consideration should also be given to times at which the control room HV AC system flow rates or other parameters change. This will provide the smallest amount of error for control room habitability calculations in situations where the release rate suddenly changes from very high to very low or vice versa. Times at which the release rates change by very much w9uld be times such as: when spray removal of iodine begins or changes, when ESF or SIRW tank leakage begins or changes, when atmospheric dispersion factors change, and etc. Times should also be specified when important parameters for control room habitability calculations change, such as: when control room HV AC system flow rates or filter efficiencies change, when breathing rates change, when control room occupancy factors change, and etc. Reference 2.29 should be consulted for more detail on the control room parameters. A value of 0 should be specified if no release rates are needed for control room habitability calculations. line 41 - ? T2(1)........ T2(8) [8F10.2] T2(9)........ T2(16) [8F10.2] etc. T2(k) are the beginning and ending times, in minutes, for each of the time inteivals for which the radionuclide release rates are to be calculated and written to output decks. The output decks are for direct use as input decks of the CONDOSE code for control room habitability calculations. The times are specified with 8 values per line, and the total number of values listed should be 1 + INTR V ALS specified in line 40. If 0 is specified in line 40, no times are to be specified for T2(k) and NPRINT should be specified on line 41. Also, none of the times specified should exceed the value of DURATION specified in line 3. The first time should always be 0.00 and the last time inteival should always be 43200.00. These values do not need to be specified as whole numbers. next line NPRINT [110] NPRINT is the number of points in time, other than time zero, that the activity of each radionuclide in the containment atmosphere, sump, and SIR W tank are to be printed in the output listing from the

PALISADES NUCLEAR Pl.ANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 33 of 50 code. Any number from 0 to 30 points in time can be specified, remembering that time zero is automatically printed. H a value greater than 30 is specified, execution of the code - will terminate and an error message will be given in the output. last lines TPRINT(NPRINT) [8110] TPRINT(NPRINT) are up to 30 times, in minutes, at which the activity of each radionuclide in the containment atmosphere, sump, and SIR W tank are to be printed to the output deck. Eight values are specified per line, and the code will only read the number of values specified NPRINT. Zero should not be specified as the first time, since the code automatically prints the time zero activities. Also, none of the times specified here can be greater than time specified as the DURATION in line 3. If a value greater than the DURATION specified in line three is given, execution of the code will terminate and an error message will be given in the output. All values must be specified as whole numbers. 8.0 MHACALC EXECUTION The MHACALC code is located in VMS. The code was compiled in double precision using the AUTODBL(12220) specification. There are two exec files for execution of the code, MHA EXEC and MHAB EXEC, both in the same location as the code. The MHA EXEC creates a VMBATCH SUBMIT to execute the code as a batch job, and the MHAB EXEC executes the MHACALC code. A listing of the MHACALC code, MHA EXEC and, MHAB EXEC are provided on the attached microfiche. To execute the code, type MHA and hit enter. The filename of the input deck is then requested in the format: Filename Filetype Minidisk-Number. An example of the proper format will be given on the screen. At this point, CANCEL can be entered to abort execution of the code. The next prompt requests all VMBATCH options. Hitting the enter key will continue execution of the code. When execution of the code is finished, four output decks will be returned. One output deck will have the same filename as the input deck, but the filetype will be LISTING. This will be the results of the 0 xAG{nother output deck will have the filename and filetype - STACKRR DATA This file contains the radionuclide release rates from the containment atmosphere and ESF leakage for the time intervals specified in the input deck, and can be used as an input deck to the CONDOSE code for control room habitability calculations. The third file will have the filename and filetype - SIRWRR DATA, and will contain the radionuclide release rates from the SIR W tank for the same time intervals as the STACKRR DATA deck, also for use in the CONDOSE code. The last output deck will have the filename and filetype - RPLOT DATA. This file is setup in the format required for the RETRAN code PLOTER module, and contains all of the data needed to plot the dose equivalent iodine 131 activity in containment versus time. These output files are discussed in the following section.

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET 9.0 OUTPUT DESCRIPTIONS EA-PAH-91-05 Sheet 34 of 50 As mentioned above, four output files are produced from execution of the code. One output deck will contain the offsite doses and related information. Two will contain the radionuclide release rates, one for containment and ESF leakage and one for SIR W tank releases, during the time intervals specified in the input deck. The other will contain all of the data needed to plot the dose equivalent iodine 131 activity in containment versus time using the RETRAN code PLOTER module. 9.1 OFFSITE DOSES FILE The name of this file will be the same as the input deck used, with the filetype being - LISTING. This file will vary in length, from 4 to 18 pages, depending upon the input specification of how many points in time to print the activity in containment. If zero time points are specified to print out the activity in containment, the minimum length of this file will be 4 pages. The first page will always be an echo of the input deck, to ensure the accuracy of the information read by the code. The first li x"'G{ page will contain the title specified on the first line of the input deck. After the title, the second page of the output will contain the initial activities of all of the radionuclides in the containment atmosphere and the containment sump, listed in units of Curies. After the initial activities, the activities in the containment atmosphere, containment sump, and the SIR W tank at each of the times specified in the input deck will be listed, if additional times to print the activities are listed. The second to last page of this output deck will contain the total activity of each radionuclude released from each path, in units of Curies. After the total activity released, the Committed Dose Equivalent (CDE) to the thyroid, the deep-dose equivalent to the thyroid, and the total of the two will be listed for each release path and the total, at the site boundary (SB). Then the Committed Effective Dose Equivalent (CEDE), the external whole body dose and the Total Effective Dose Equivalent (TEDE) will be listed for each release path and the total, at the site boundary. Below this, the same will be repeated, except all of the doses will be for the low population zone (LPZ) distance. Care should be taken when chasing dose values from this page. For whole body dose, if only the external dose to the whole body dose is desired, then the values listed for whole body dose should be used. If the contribution from internal dose is desired for inclusion in the whole body dose, the TEDE or total effective dose equivalent value should be used. The last line on this page will be the time specified in the input deck for sprays to stop or the time at which the maximum elemental iodine decontamination factor was reached, whichever is reached first. The last page of this file is just the program execution summary. Examples of this output deck can be seen on the attached microfiche. 9.2 RELEASE RATE FILES The filename and filetype of these two files will be STACKRR DATA. If more than one execution of the MHACALC code will be made, the name of these files will have to be changed each time. These files will vary in length depending upon how many time intervals were specified for release rates, and

j ft*lf ~ ie.flc: .,...:.W--il:"..lr*O* PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 35 of 50 will contain the release rate of each of the radionuclides of main concern for each of the time intervals specified in the input deck. The STACK.RR DATA deck contains the radionuclide release rates from the containment and from ESF leakage, which are assumed to be released from the location of the stack, not accounting for stack height (not assumed an elevated release). The SIRWRR DATA deck contains the radionuclide release rates from the SIR W tank. The release rates are calculated as uniform release rates over each time interval by dividing the activity released from the respective release paths during each time interval by the time span of each time interval. The release rates are given in units of µCi/hr, and the files are created for direct use in the CONDOSE code for control room habitability calculations. Separate files are created for the stack release rates and the SIR W tank release rates because the atmospheric dispersion relative to the control room intakes will be different for the two assumed release locations. The format of the release rates in these output decks is such that for each time interval there are three lines of release rates for the radionuclides. Therefore, every fourth line of the files starts the release rates for a different time interval. The radionuclides in each time interval are in the following order: time interval 1 line 1 - [Kr-83m] [Kr-85m] [Kr-85] [Kr-87] [Kr-88] [Kr-89] line 2 - [Xe-131m] [Xe-133m] [Xe-133] [Xe-135m] [Xe-135] [Xe-137] line 3 - [Xe-138] [l-131] [1-132] [l-133] [1-134] [l-135] time interval 2 line 4 - [Kr-83m] [Kr-85m] [Kr-85] [Kr-87] [Kr-88] [Kr-89] line 5 - [Xe-131m] [Xe-133m] [Xe-133] [Xe-135m] [Xe-135] [Xe-137] line 6 - [Xe-138] [1-131] [1-132] [I-133] [l-134] [l-135] etc. The release rates are listed as such for each of the specified time intervals. The SIRW DATA deck will contain all zeros for the release rates of noble gas isotopes since no noble gas is assumed to be present in the sump solution. The release rates of all radionuclides in that input deck will be zeros until the time at which leakage starts is reached. An example of these output decks can be seen on the attached microfiche as the third and fourth documents under the heading CASE1. 9.3 PLOTIING DATA FILE The filename and filetype of this file will be RPLOT DATA If more than one execution of the MHACALC code will be made, the name of this file must also be changed each time. This file will be constructed in the format required for execution in the RETRAN code PLOTER module. When the RETRAN code PLOTER module is executed using this file as the input deck, two figures will be printed. The first figure will contain three plots of dose equivalent iodine 131 activity in containment versus time; one plot for each chemical species of iodine. The second figure will contain one plot of the dose equivalent iodine 131 activity in containment versus time, with the plot being the sum of the three chemical species, or the total iodine activity. The plots of the three chemical species. will be for the first 400 minutes to present a clear comparison of the effect of spray removal on the different

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 36 of 50 chemical species of iodine. The plot of the total dose equivalent iodine 131 activity will be for the first 1440 minutes, or 24 hours, after which only radioactive decay will most likely be affecting the activity. The plots of the three chemical species can also be performed for 24 hours with a minor change to this data file, as will be discussed later. Notice should also be given to the scale of each axis of the figures. Since one figure is for the comparison of the effect of sprays on the different chemical species and one is for understanding of the overall effect, different scales were used for each axis of each figure. The length of this file will vary, depending on the number of data points to be plotted. Two data points for each of the chemical species of iodine, and for the total, will be listed for each time that the activity changed by + or - 3%, up to 24 hours. The number of data points given for each plot will be specified after the input card number for the plot data, then each line following will contain one time with a corresponding data point. A comment line will be given before each set of data points, specifying which plot the data points represent. A description of the data cards in this deck is listed below. These data cards are described by card number, using data variable names consistent with the RETRAN-02 manual [Ref. 2.15]. Problem Control and Description Card. 010001 LDMP NDSET NFRAME NPLOTC NPLOTD _;NPEDIT NPTABL LDMP = -3 = given by Reference 2.15 NDSET = 0 = number of tape data sets from which data is to be plotted NFRAME = 2 = number of frames requested NPLOTC = 4 = number of plot curve requests NPLOTD = 0 = number of combination plot curve requests NPEDIT = 0 = option flag for tabular edits of curve data NPTABL = 4 = number of tabular input data sets Plot Data Table Cards 12XXOO NDATA TDATA(l) TDATA(2) XX = data table number 01, 02, 03, or 04 NDATA = number of data points TDATA(l) = independent variable TDATA(2) = dependent variable Independent Axis Specification Data Cards 02XX01 XVAR XREG XLINOG XLENG XMIN XMAX XLABL XX = frame* number 01 or 02 XVAR = dummy variable = 'ABCD' for frame 01 = 'EFGH' for frame 02 XREG = dummy value = 0 XLINOG =linear or logarithmic request flag= 'LIN' for frame 01 = 'LOG' for frame 02 XLENG = length of independent axis, inches = 8.0 XMIN = minimum value of independent axis = 0.0 for frame 01 = 1.0 for frame 02 XMAX = maximum value of independent axis = 400.0 for frame 01 = 1440.0 for frame 02 XLABL =independent axis label = 'TIME (MINUTES)' Dependent Axis Specification Data Cards 03XXYO YLINOG YLENG YMIN YMAX YLABL XX = frame number 01 or 02 Y = dependent axis number for frame XX = 1, 2, or 3 for frame 01 = 1 for frame 02

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 37 of 50 VLINOG = linear or logarithmic request flag= 'LOG' for frame 01 axes 1, 2, and 3 = 'LIN' for frame 02 VLENG = length of dependent axis, inches = 5.0 VMIN = minimum value of dependent axis = l.E+03 for frame 01 axes 1, 2, and 3 = 0. for frame 02 VMAX = maximum value of dependent axis = 3.E+07 for frame 01 axes 1, 2, and 3 = 30.0 for frame 02 VLABL =dependent axis label = 'ELEMENTAL (CURIES)' for frame 01 axis 1 = 'PARTICULATE (CURIES)' for frame 01 axis 2 = 'ORGANIC (CURIES)' for frame 01 axis 3 = 'TOTAL DE 1-131 (MEGA-CURIES)' for frame 02 Plot Curve Request Data Cards 4XXVOS VVARC IVREGC IDSETC VSCTRN VSCMAG

comment XX = frame number 01 or 02 V = dependent axis number for frame XX = 1, 2, or 3 for frame 01 = 1 for frame 02 S = sequence number for plot on frame XX= 1, 2, or 3 for frame 01 = 1 for frame 02 VVARC = dummy variable = 'TABL' IVREGC = dummy value = 0 IDSETC = data table number from which variable is retrieved, -XX from card 12XXOO

= -1 for frame 01 plot 1 = -2 for frame 01 plot 2 = -3 for frame 01 plot 3 = -4 for frame 02 plot 1 These specifications can be changed prior to executing the RE1RAN code PLOTER module, if so desired. H the time for the three plots of the chemical species is to be extended further than 400 minutes, card number 020101 parameter XMAX can be changed. H a different title is desired for the two figures, the second to last line should be changed. If any other information is to be changed, the RE1RAN manual [Ref. 2.15] should be consulted. To execute the RE1RAN code PLOTER module, type the name RETRAN and hit enter. A menu will appear giving choices of which routine to execute. To chose the plotting routine, type: Filename Filetype Minidisk-Number PD. The filename, filetype, and minidisk-number should be name of the file containing the plotting data (RPLOT DATA 191 is the name given by the code), followed by the letters PD. When execution is complete, the figures will automatically be printed on the Reactor Engineering HP laser printer. Examples of this output deck can be seen on the attached microfiche. 10.0 TEST CASES AND VERIFICATION To verify the accuracy of the calculations performed by the code, three test cases were executed. These test cases were then verified by alternate calculations or knowledge of the behavior expected. Test case 1 was used to verify the accuracy of all calculations performed by the code, and the input deck was

therefore set up to make use of all of the calculations performed by the code. Test case 2 was used to

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 38 of 50 ensure that the spray stop time (STOPSPRA in the input deck) performs the desired function of terminating all spray removal of iodine. Test case 3 was used to ensure that a negative spray removal coefficient would adequately model iodine re-evolution from the sump solution if the pH of the solution is predicted to fall below 7. The name of the input deck used for each of the three test cases is listed below. 10.1 TEST CASE 1 Case 1 - ClMCALC DATA Case 2 - C2MCALC DATA Case 3 - C3MCALC DATA Test case 1 was created to verify all of the calculations that the code performs. The input deck for this test case, as mentioned above is ClMCALC DATA. This input deck is listed on the attached microfiche. The parameters in this input deck are described line by line, below. Most of the parameters used are taken from Reference 2.6. line 1: CASE 1: BENCHMARK RUN OF MHACALC CODE This is just the title given to this case. line 2: 1 This line specifies that the debug option is not to be used since a value greater than 0 is specified. line 3: 43200 This line specifies that the calculations are to be performed for 43200 minutes, or 30 days. line 4: 2530. 0 0.10 40304. 5 This line specifies the rated thermal power of the core, 2530 MWt as used in Reference 2.6 [pg. 34]. The next value is the containment leak rate, 0.1 %/day, which converts to 6.944E-07 min1 as used in Reference 2.6 [pg. 37 (LAMLl and LAMI2 values)]. The third value on this line is the volume of the sump, 40304.5 ft.3, corresponding to 3.015E + 05 gallons as used for the recirculation volume in Reference 2.6 [pg. 37]. line 5: 100.0 25.0 50.0 This line specifies the fraction of the core's noble gas inventory released to the containment atmosphere as 100%, the fraction of the core's iodine inventory released to the containment atmosphere as 25%, and the fraction of the core's iodine inventory released to the containment sump as 50%. These values are the same as those used in Reference 2.6 [pg. 33]. line 6: 95.5 2.5 2.0 This line specifies the elemental fraction of iodine as 95.5%, the particulate fraction as 2.5%, and the organic fraction as 2.0% as used in Reference 2.6 [pg. 37]. line 7: 2.0 10.0 1.0 2.0 38767.2 3739.3 3.00E-01 l

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 39 of 50 The first value on this line is the iodine decontamination, or retention factor for ESF leakage, 2 as used in Reference 2.6 [pg. 33]. The second value on this line is the iodine partition factor for ESF leakage, 10 as used in Reference 2.6 [pg. 37]. The third value on this line is the partition factor for recirculation line valve leakage and was arbitrarily chosen as 1.0. The fourth value on this line is the multiplication factor for the rate at which iodine exits the SIRW tank, and was arbitrarily chosen as 2.0. The fifth value on this line represents the total volume of the SIRW tank and was arbitrarily chosen as 38767.2 ft3. The sixth value on this line is the volume of water present in the SIR W tank at RAS, and was arbitrarily chosen as 3739.3 ft3. The last value on this line is the fraction of the iodine entering the SIRW tank in a volatile form and was arbitrarily chosen as 3.00E-01. line 8: 3.47E-04 l.75E-04 2.32E-04 This line specifies the 0 to 8 hour breathing rate as 3.47E-04 m3 /sec, the 8 to 24 hour breathing rate as 1.75E-04 m 3 /sec, and the breathing rate from 1 to 30 days as 2.32E-04 m3 /sec. These values are as used in Reference 2.6 [pg. 33]. line 9: I. SSE-04 This line specifies the 0 to 2 hour site boundary atmospheric dispersion factor as 1.55E-04 sec/m3 as used in Reference 2.6 [pg 33]. line 10: I.09E-05 6.94E-06 2.58E-06 6.25E-07 This line specifies the 0 to 8 hour LPZ atmospheric dispersion factor as 1.09E-05 sec/m 3 , the 8 to 24 hour LPZ atmospheric dispersion factor as 6.94E-06 sec/m3, the 1 to 4 day LPZ atmospheric dispersion factor as 2.58E-06 sec/m3, and the 4 to 30 day LPZ atmpspheric dispersion factor as 6.25E-07 sec/m3 as used in Reference 2.6 [pg. 33]. line 11: 1.00 0.00 The first value on this line is the spray removal coefficient for particulate iodine when the containment sprays begin, 1.0 ht1 , which coverts to 1.667£-02 min1 as used in Reference 2.6 [pg. 34 ]. The second value on this line is the spray removal coefficient for particulate iodine after 98% of the particulate iodine has been removed from the containment atmosphere, and was chosen as 0.0 since Reference 2.6 ended particulate iodine removal at the same time as elemental iodine removal. line 12: 1

0. 420 line13:

5 10.000 line 14: 19 0.000 line 15: 720

0. 420 line 16:

O O. 000 The first value on line 12 is the time at which full sprays are achieved, 1 minute [Ref. 2.6, pg. 35], and the second value is the spray removal coefficient for elemental iodine when full sprays start, 0.42 hr-1, which converts to 7.0E-3 min1 as used in Reference 2.6 [pg. 34]. Line 13 specifies the first time at which the spray removal coefficient for elemental iodine changes, 5 minutes, and the value the coefficient changes to 10.0 ht1, which converts to 1.667£-01 min1 as used in Reference 2.6 [pg. 34-35]. Lines 14 and 15 specify two more times at which the spray removal coefficient for elemental iodine change and the values the coefficient changes to, as used in Reference 2.6 [pg. 34-35]. Line 16 simply contains zeros so as to not change the spray removal rate again.

~ ltlJ;7*-

.tL. -ir--.. *,,:W.

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET line 17:

25. 57 0

EA-PAH-91-05 Sheet 40 of 50 The first value on this line specifies the maximum elemental iodine decontamination factor as 25.57 as used in Reference 2.6 [pg. 23]. The second value on this line is the time at which containment sprays, and all spray removal of iodine is terminated and is chosen as 0 to allow the maximum elemental iodine decontamination factor terminate the spray removal of elemental iodine. line 18: 19 0.2 19 1.0 line 19: 0

0. 0 1440

0. 0 line 20:

0 0. 0 0 0. 0 line 21: 0 0.0 0 0.0 The first value on line 18 specifies the time at which ESF leakage starts, 19 minutes, and the second value specifies the ESF leak rate when the leakage starts, 0.2 gpm, as used in Reference 2.6 [pg. 33]. The third and fourth values on line 17 specify the time at which recircultion line valve leakage begins and the leak rate when the leakage begins, arbitrarily chosen as 19 minutes and 1 gpm respectively. On line 19, the first and second values are specified as 0 to indicate that the ESF leak rate does not change, but the third and fourth values are arbitrarily specified as 1440 minutes and 0.0 gpm to indicate that the recirculation line leakage stops. All values in lines 20 and 21 are specified as 0 to indicate that the ESF and recirculation line leak rates do not change again for the duration of the calculations. line 22: 2.998E+03 6.2llE-03 O.OOOE-00 3.649E-06 line 23: 6.498E+03 2.579E-03 1.233E-03 1.269E-03 line 24: 2.999E+02 1.230E-07 O.OOOE-00 2.314E-05 line 25: 1.155E+04 9.120E-03 5.550E-03 5.684E-03 line 26: l.690E+04 4.068E-03 l.439E-02 l.402E-02 line 27: l.993E+04 2.201E-Ol O.OOOE-00 O.OOOE-00 line 28: l.760E+02 4.038E-05 O.OOOE-00 l.915E-04 line29: l.954E+03 2.198E-04 O.OOOE-00 3.823E-04 line30: 5.648E+04 9.169E-05 4.317E-04 3.361E-04 line 31: 1.698E+04 4.530E-02 O.OOOE-00 3.618E-03 line 32: 9. 781E+03 1.271E-03 O.OOOE-00 7.914E-03 line 33: 4.705E+04 l.SOOE-01 O.OOOE-00 O.OOOE-00 line 34: 4.433E+04 4.881E-02 7.SllE-03 7.801E-03 line 35: 2.938E+04 5.986E-05 l.073E+06 3.256E+04 line36: 4.160E+04 5.045E-03 6.290E+03 3.367E+02 line 37: 4.808E+04 5.554E-04 l.813E+05 5.550E+03 line 38: 6.218E+04 1.318E-02 l.073E+03 l.106E+02 line39: 4.922E+04 l.754E-03 3.145E+04 l.121E+03 On each line is listed the source term, the radioactive decay constant, the thyroid dose (or dose rate for noble gas) conversion factor, and the sum of the weighted dose (or dose rate) conversion factors for each of the 18 radionuclides of main concern. The order of the radionuclides was given in section 7.0 of this analysis. The source term and radioactive decay constant values are the same as those used in Reference 2.6 [pgs. 34 & 42]. The dose and dose rate conversion factors are from Reference 2.12, converted to conventional units.

line 40: 24 PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 41 of 50 On line 40 is the number of time intervals for which radionuclide release rates are to be calculated. line 41:

0. 00 line 42:

75. 00 line43:

195.00 line 44: 43200. 00 1.00 90.00 210.00 2.28 105.00 240.00 5.00 120.00 480.00 19.00 135.00 720.00 30.00 150.00 1440.00 45.00 165.00 1800.00 60.00 180.00 5760.00 On each of these lines are the arbitrarily chosen start and stop times (minutes) for the 24 time intervals for which the radionuclide release rates are to be calculated and written to an output deck. line 45: 24 This line specifies the arbitrarily chosen number of points in time that the activity of each radionuclide in containment is to be written to the output deck. line 46: line 47: line 48: 2 90 210 3 105 240 5 120 480 19 135 720 30 150 1440 45 165 1800 60 180 5760 75 195 . 43200 On these three lines are the arbitrarily chosen points in time at which the activity of each radionuclide in containment is to be written to the output deck. The four output decks from the execution of MHACALC with the ClMCALC DATA input deck are listed on the attached microfiche. The names of the release rate output files and the plotting data file were changed to ClSTACKR DATA, ClSIRWR DATA, and ClMPLOT DATA to indicate case 1. contains all of the hand calculations to verify these three output decks. Pages 1 through 37 of Attachment 1 contain the calculations to verify ClMCALC LISTING, ClSTACKR DATA, and ClSIRWR DATA, and pages 38 through 51 contain the calculations to verify ClMPLOT DATA To verify the output, the activity of each of the radionuclides in the containment atmosphere and the release rate of each of the radionuclides must be caluclated for each of the time intervals and times listed in lines 41 through 44 and 46 through 48 of the input deck. First the initial acitivity of each radionuclide in the containment atmosphere and containment sump is calculated using Equations (1), (6), & (14) for the noble gas and iodine isotopes, where P corresponds to POWER in the input deck, S corresponds to SOURCE in the input deck,~ corresponds to FNG/100 for noble gas and FIA/100 for iodine in the input deck, and fs corresponds to FIS/ 100 in the input deck. Also fcF corresponds to FCF /100 in the input deck, and the total iodine activity for each isotope is just the sum of the activity of each of the three chemical forms. The results of these calculations, shown on page 1 of Attachment 1, were compared to the initial containment activities given in ClMCALC LISTING showing excellent agreement. The activity of each radionuclide released from 0 to 1 minutes is then calculated from the initial containment activity using Equation (5) for each noble gas isotope and Equation (11) for each iodine isotope. In these equations, AL corresponds to CONTLR in the input deck converted to mirf 1, A1 corresponds to LAMBDA in the input deck, As corresponds to SPRAPR in the input deck for particulate iodine converted to mirf1, SPRAEL in the input deck for elemental iodine converted to mirf1, and As always = 0.0 for organic iodine. Since full sprays are not achieved until 1 minute, from

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 42 of 50 line 12 of the input deck, all values of As = 0.0 during first time interval. The release rate from 0 to 1 minutes is then just the activity released divided by the duration of the interval, converted to units of µCi/hr. The results of these calculations, shown on page 2 of Attachment 1, were compared to the release rates for the first time interval given in ClSTACKR DATA, showing excellent agreement also. The activity of each radionuclide in containment at 1 minute is then calculated using Equation (3) for noble gas in the containment atmosphere, Equation (8) for iodine in the containment atmosphere, and Equation (16) for iodine in the containment sump. Equation (9) is then used to calculate the total activity of each iodine isotope. In Equation (16), LResF corresponds to LRESF in the input deck and ~ corresponds to LRSRW in the input deck, both converted to ft3 /min. As given on line 18 of the input deck, however, LRESF and LRSRW do not begin until 19 minutes and are zero before that time. Vs corresponds to VSUMP in the input deck, but decreases after ESF and SR W leakage start. After 1 minute, spray removal of iodine in the containment atmosphere starts as is indicated on line 12 of the input deck. The value of As for particulate iodine is specified on line 11 of the input deck, 1.0 hf 1 which must be converted to min1

The value of As for elemental iodine is specified on line 12 of the input deck, 0.42 hf1 which must also be converted to min1
The value of As for organic iodine will always be zero. Using Equations (3), (8), & (16), the activity of each radionuclide in containinent was calculated at 2 minutes, again showing excellent agreement will the values given in ClMCALC LISTING. The activity released from 1 to 2 minutes was then calculated. However, the next interval for release rates is 1 to 2.28 minutes, so the calculations are repeated for the activity at 3 minutes and the activity released from 2 to 3 minutes. The release rate from 1 to 2.28 minutes was then calculated using the equation shown on page 6 of Attachment 1. Again very good agreement was shown with the values given in ClMCALC LISTING and ClSTACKR DATA, with some very small differences due to rounding error since the code keeps track of more significant digits than was carried by my calculator.

These calculations were continued for each of the times and time intervals that the containment atmosphere activity and the release rates were specified to be written in the output decks. It is noted that at 5 minutes, As for elemental iodine changes to 10.0 hf 1 , which converts to 0.167 miii 1 , as specified on line 13 of the input deck. At 19 minutes, as specified on line 14 of the input deck, As for elemental iodine changes to 0.0. Also at 19 minutes, as specified on line 18 of the input deck, LRESF and LRSRW take on values. As discussed in section 6.2 of this analysis, the value of LRESF is multiplied by a factor of 2 by the code resulting in LResF = (0.2)(2)(0.13368) = 0.053472 ff /min. The value of

LRsRW becomes (1.0)(0.13368) = 0.13368 ft3 /min.

Comparing the calculated contaiment activity of each radionuclide to that given in ClMCALC LISTING for 19 minutes, the roundoff error in the hand calculations for the iodine activity was starting to become more significant. The roundoff error was becoming more significant since the activity of each chemical species of each iodine isotope is calculated using exponential terms and the roundoff error keeps increasing from using the results of each of the previous hand calculations. Therefore, the debug option of the code was executed using the ClMCALC DATA input deck with DEBUG on line 2 specified as O. The debug option was used so that the activity of each chemical species of each iodine isotope that

the code calculated could be used. Since the debug option produces hundreds of pages of output, the page with the iodine activity at 19 minutes is given in Attachment 1 on page 8A The values for the iodine activity of each chemical species shown on page 8A of Attachment 1 were then used for the.

calculations of the activities at 30 minutes.

PALISADES NUCLEAR Pl.ANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 43 of 50 Since the values of LRes,. and LRsRW are non-zero after 19 minutes, the release of radionuclides from these paths must be included in the calculations after 19 minutes. The activity of each radionuclide released from ESF leakage is calculated using Equation (18), where DFESF and PFesF correspond to DFESF and PFESF on line 7 of the input deck. The total activity of each iodine isotope in the SIRW tank from recirculation line valve seat-leakage is calculated using Equation (21), with the intial SIRW tank activity and release being 0.0. The activity of the volatile fraction of each iodine isotope in the SIRW tank is calculated using Equation (21) again, but multiplying the second part of the equation by the fraction of the total iodine in the sump water that is volatile, or FI2 from line 7 of the input deck. The concentration of each iodine isotope in the SIR W tank air volume is then calculated using Equation (25), where PFSRW corresponds to PFSRW, Vua initially corresponds to VSRWLIQ, and VAIR initially corresponds to VTANK minus Vua' all on line 7 of the input deck. The activity released from the SIRW tank is then calculated using Equation (22), where kc corresponds to KSUBD on line 7 of the input deck. It should be noted that as all other calculations can be performed as one calculation of a large time interval, calculatio~ of the sump and SIRW tank activities, and the ESF and SIRW tank releases must be calculated over 1 minute increments to avoid large error. This is due to the inter-dependence of the equations on the values at the previous time step. A simple basic program was written to perform the ESF and SIR W tank release calculations over any given time interval to verify the values calculated by the code. A listing of this basic program and a calculation over a 1 minute time step to verify it are listed in Attachment 2. The calculated values continued to show very good agreement with the values given in ClMCALC LISTING, ClSTACKR DATA, and ClSIRWR DATA until 210 minutes, at which time the iodine activities were somewhat off. Since As for elemental iodine was set equal to 0.0 after 19 minutes and As for organic iodine never changes from 0, spray removal of particulate iodine must have changed between 195 and 210 minutes. From section 6.1.2 of this analysis, the value of As for particulate iodine changes when the condition in Equation (13) is met. The value that As for particulate iodine changes to is the second value given on line 11 of the input deck, 0.0 in ClMCALC DATA As can be seen on page 21 of Attachment 1, the condition of Equation (13) was met between 195 and 210 minutes. To find the correct values of the particulate activity of each iodine isotope, the output of the debug option execution that was mentioned previously was used. The page from the debug option output that contains the iodine activity at 210 minutes is given in Attachment 1 on page 21A. The values for particulate iodine activity on page 21A were then used to calculate the activity at 240 minutes, resulting in values that agreed with that in ClMCALC LISTING, ClSTACKR DATA, and ClSIRWR DATA. After 720 minutes, as is given on line 15 of the input deck, the value of As for elemental iodine should change from 0.0 to 0.42 ht1

However, checking the condition of Equation (12), the value of DFmax given on line 16 of the input deck the condition has be exceeded prior to 720 minutes. This is shown on page 24 of Attachment 1. This is also verified by the last line of the output deck ClMCALC LISTING which gives the time at which DF max was reached as 421 minutes. As is discussed in section 6.1.2 of this analysis, after that condition has been met, As for elemental iodine is set equal to zero for the remainder of the incident.

After 1440 minutes (24 hours), two parameters change. The code automatically decreases AL by a factor of 2, as discussed in section 6.1.1 of this analysis. The value of AL then becomes 3.472E-07 min1

Also at 1440 minutes, as is given on line 19 of the input deck, the value of LRsnw changes to 0.0. This ends

L PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 44 of 50 the recirculation line valve leakage, and no additional activity is released through the SIRW tank. The release rates of all radionuclides are 0.0 for each time interval in the ClSIRWR DATA file after 1440 minutes. The calculations continued to be in very good agreement with the values given in ClMCALC LISTING and ClSTACKR DATA for the containment activity and the release rates out to the last time point, 43200 minutes. This concludes that the code properly calculates the time dependant depletion of the radionuclides and the release rates of the radionuclides from the two assumed release locations. However, the activity of the radionuclides released and the resultant offsite doses must now be verified. The activity released from each release path for each iodine isotope is totaled on pages 29 and 30 and that of noble gas on page 31 of Attachment 1, showing the total during time intervals at which dose calculation parameters change (breathing rate and atmospheric dispersion factors change at certain points in time) and a cummulative total released over the 43200 minutes. The cummulative totals for each isotope and release path shown on page 32 of Attachment 1 are also in good agreement with the values given in ClMCALC LISTING. The iodine activity released from the containment atmosphere was calculated to be slightly higher than that listed in the output, but is attributed to roundoff differences and the spray removal coefficients changing between the time intervals for which hand calculations were performed. The doses are calculated for 0 to 2 hours at the site boundary (SB) and for 0 to 30 days at the low population zone (LPZ). Inhalation committed dose equivalent (CDE) to thyroid and committed effective dose equivalent (CEDE) to the whole body from each of the iodine isotopes is calculated using Equation (26) where DCFlnh corresponds to DCF on lines 35 through 39 of the input deck, BR corresponds to BREATH on line 8, and x./Q corresponds to CHIQSB or LPZCHI on lines 9 and 10 of the input deck. The external dose from each of the noble gas isotopes is calculated using Equation (27) where DCF Sib corresponds to DCF on lines 22 through 34 of the input deck. Doses at the site boundary are calculated using CHIQSB from line 9 of the input deck and the first value of BREATH on line 8. Doses at the low population zone must be calculated in intervals. The first interval is 0 to 8 hours using the first value of BREATH on line 8 and the first value of LPZCHI on line 10 of the input deck. The second interval is 8 to 24 hours using the second value of BREATH on line 8 and the second value of LPZCHI on line 10. The third interval is 1 to 4 days using the third value of BREA TH on line 8 and the third value of LPZCHI on line 10. The last time interval is 4 to 30 days using the third value of BREATH on line 8 and the fourth value of LPZCHI on line 10. The results of the hand calculations for the site boundary doses are shown on page 32 of Attachment 1 for the thyroid dose and on page 33 for the whole body. These calculated values are in good agreement with the values listed in ClMCALC LISTING. The results of the hand calculations for the low population zone doses are shown on pages 34 and 35 of Attachment 1 for the thyroid doses and pages 36 and 37 for the whole body doses. These values are also in good agreement with the values listed in ClMCALC LISTING. The CEDE and thyroid dose from inhalation of iodine released from the containment atmosphere were calculated to be slightly higher than that given in the output, but is expected due to the total calculated releases being slightly higher. The little differences between the other hand calculated values and the values given in the output deck can be attributed to consistent roundoff error throughout the calculations. This concludes that the code properly calculates the radionuclide releases and offsite doses.

-<l*if.!1'_'78; ..,.;:...-r-.:..'F-" PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 45 of 50 The last calculations that need to be verified are the dose equivalent 1-131 activities given in the output deck ClMPLOT DATA for use in the RETRAN code PLOTER module. Dose equivalent 1-131 activity is calculated using Equation (28). To verify the values in ClMPLOT DATA, at each of the times that the containment atmosphere activity was calculated, the dose equivalent 1-131 activity for elemental, particulate, organic, and total iodine have also been calculated as shown in pages 38 through 51 of. At each of the times that the dose equivalent 1-131 activities were calculated by hand, the calculated values were compared to the values in ClMPLOT DATA for each of the chemical species and the total. These showed close agreement. However, only 23 time points were calculated by hand, whereas many more time points are gi':7en in ClMPLOT DATA. Therefore, an input deck for the RETRAN code PLOTER module was made using the hand calculated dose equivalent 1-131 activities at the 23 time points, filename - PLOTCHK DATA. The PLOTCHK DATA input deck is listed on pages 52 through 54 of Attachment 1. The two plots output by the RETRAN code PLOTER module execution using PLOTCHK DATA are shown on pages 55 and 56 of Attachment 1. The containment atmosphere activity plots in Attachment 1 can be compared to the plots on pages 1 and 2 of Attachment 3, created from execution of the RETRAN code PLOTER module using ClMPLOT DATA as the input deck, showing excellent agreement. This concludes that the code calculates the dose equivalent 1-131 containment atmosphere activities correctly and writes the RPLOT DATA output deck in the proper format for the RETRAN code PLOTER module. 10.2 TEST CASE 2 Test case 2 was created to verify that if a stop time for containment sprays is used in the input deck to the MHACALC code, that all spray removal of iodine would be terminated setting the values of the spray removal coefficients to 0.0. The input deck for this test case is C2MCALC DATA and is listed on the attached microfiche. This input deck is almost identical to the input deck for test case 1, with the parameters that are different being discussed below. line 1: CASE 2: VERIFICATION OF THE SPRAY STOP TIME This line is just the title and is changed appropriately for this test case. line 14: line 15: 00.0 000.0 0.000 0.000 These lines are changed to values of 0.0 so that the elemental iodine spray removal rate specified on line 13 will continue until DF max is reached or a spray stop time is reached, which ever is first. line 16: 25.57 24.0 The second value on this line, STOPSPRA, has been changed from 0 to a value of 24 minutes. Changing this value to 24 minutes causes the spray removal of elemental and particulate iodine to be terminated at 24 minutes.* line 40: 00 The value of INTR V ALS has been changed to 00 to prevent the code from creating release rate files since they are not needed for this test case.

line 41: 00 PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 46 of 50 The value of NPRINT was changed to 00 to prevent the containment atmosphere activity from being sent to the output deck at a number of times. The containment atmosphere activity at different points in time is unnecessary since a se~arate output deck is created for plotting it with the RETRAN code PLOTER module. The MHACALC code was executed using the C2MCALC DATA input deck. The C2MCALC LISTING output deck is listed on the attached microfiche. No release rate files were created since the value of INTR V ALS on line 40 of the input deck was specified as 00. The output deck set up for use in the RETRAN code PLOTER module, however, was necessary and was renamed C2MPLOT DATA C2MPLOT DATA is also listed on the attached microfiche. To evaluate the time at which spray removal of iodine ended, the last page of the C2MCALC LISTING output deck can be examined._ As can be seen, C2MCALC LISTING gives the time at which the DFriiax or the spray stop time was reached as 24 minutes. This is the same time as specified in the input deck, but it must be verified that the spray removal of iodine was terminated at that time. The only difference between the spray stop time being reached and the DF max being reached is that when the spray stop time is reached, spray removal of elemental and particulate iodine is terminated. When the DF max is reached, only that for elemental iodine is terminated. The RETRAN code PLOTER module was executed using the C2MPLOT DATA deck, with the resultant plots shown in Attachment 4. As can be seen on page 1 of Attachment 4, the elemental iodine activity and the particulate iodine activity stop decreasing sharply at 24 minutes. This verifies that the spray stop time performs its desired function. 10.3 TEST CASE 3 Test case 3 was created to verify that use of a negative value for the elemental iodine spray removal coefficient could adequately model iodine re-evolution from the sump solution to the containment atmosphere. This situation can occur if the sump solution pH is allowed to fall below 7.0 at any time during a LOCA, or the MHA The input deck for this test case is C3MCALC DATA and is listed on the attached microfiche. This input deck is very similar to the input deck for test case 2. The parameters that are different are explained below. line 1: CASE 4: VERIFICATION OF IODINE RE-EVOLUTION This line is just the title and again was changed appropriately for this test case. line 12:

1. 0

10. 000 line 13:

19.0 5.000 line 14:

45. O

-1. 000 line 15: 150. O

0. 000 The second value of line 12 was changed to 10 to give the elemental iodine a large spray removal coefficient so that a rapid decrease in elemental iodine activity can be seen. On line 13, the first time at which the elemental iodine spray removal coefficient changes was arbitrarily chosen as 19 minutes with a spray removal coefficient of 5 ht1 to slow the decrease in the elemental iodine activity before

PALISADES NUCLEAR Pl.ANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 47 of 50 the value of DFma is reached. On line 14, 45 minutes was arbitrarily chosen as the time at which elemental iodine re-evolution would occur with a negative spray removal coefficient of -1.0 ht1 so that re-evolution does not occur at too rapid of a rate. On line 15, 150 minutes was arbitrarily chosen as the time at which elemental iodine re-evolution would terminate. line 16: 25.57 1440.0 The second value on this line was arbitrarily set at 1440 minutes for the spray stop time in case spray removal of particulate iodine continued. The MHACALC code was executed using the C3MCALC DATA input deck. The C3MCALC LISTING output deck is listed on the attached microfiche. As with case 2, no release rate files were created since they were not needed for this test case. The output deck set up for use in the RETRAN code PLOTER module is necessary, however. This output deck was renamed C3MPLOT DATA and is also listed on the attached microfiche. To evaluate the re-evolution of elemental iodine, the plots of the iodine activity versus time are used. Therefore, the RETRAN code PLOTER module was executing using the C3MPLOT DATA deck. The resultant plots from this execution are shown in Attachment 5. H page 1 of Attachment 5 is examined, the elemental iodine activity behaves exactly as would be expected considering the values specified on lines 12 through 15 of C3MCALC DATA. The elemental iodine activity decreases very sharply from approximately 1 to 19 minutes. The decrease is then less sharp for just a few minutes before leveling off. The reason for the elemental iodine activity leveling off is that the DF max value is reached at 22 minutes, as can be seen on C3MCALC LISTING, which terminates elemental iodine removal. At 45 minutes, the elemental iodine starts increasing at approximately the same rate as the particulate iodine is decreasing. This is as expected since the particulate iodine removal rate is 1.0 ht1 and the elemental iodine re-evolution rate is 1.0 ht1, or removal rate of -1.0 ht1

At 150 minutes the elemental iodine activity levels off again since at that time the removal coefficient is set to 0. The particulate iodine activity levels off at around 200 minutes, which is due to the condition in Equation (13) being met. At that time the particulate iodine removal coefficient changes to the sec.and value specified on line 11, which is 0, in C3MCALC DATA It is interesting to view the effect that the changing elemental iodine activity has on the total iodine activity shown on page 2 of Attachment 5. For this case, the elemental iodine activity was always greater that that of the other chemical forms and was therefore dominating on the plot of total iodine activity. This case has confirmed that the MHACALC code can also properly model elemental iodine re-evolution into the containment atmosphere if the rate at which re-evolution is to occur can be determined.

11.0

SUMMARY

The MHACALC code was written to calculate the time dependent activity of iodine and noble gas in the containment atmosphere and sump following a LOCA. The containment atmosphere was modeled as a single, well-mixed space. This is accepted by the Standard Review Plan since the containment sprays cover at least 90% of the containment building space and the air coolers are available to circulate

PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 48 of 50 the sprayed and unsprayed regions. The containment atmosphere activity and the sump activity are modeled as non-interactive, intended for use with Regulatory Guide and Standard Review Plan activity source terms. Modeling the atmosphere and sump as non-interactive means that the activity removed by containment sprays will not be added to the activity of the sump solution since the sump activity will be assumed high enough to account for the interaction when using regulatory guidance on the activity source terms. Three removal mechanisms are modeled for the iodine in the containment atmosphere: radioactive decay, removal by containment sprays and surface plateout, and leakage of the containment atmosphere to the environment. For noble gas in the containment atmosphere, only radioactive decay and leakage of the containment atmosphere are considered. An output deck is created for direct use in the RETRAN code plotting routine which creates plots of the iodine activity versus time. Plots of the dose equivalent 1-131 activity for each chemical species and for the total are created. The MHACALC code also determines the resultant offsite radiation exposure doses by modeling the possible release paths from containment. The code can model the release of radionuclides to the environment from leakage of the containment atmosphere, leakage of ESF components into the safeguards rooms during recirculation of sump water, and seat-leakage of valves in the recirculation lines to the SIRW tank during recirculation of sump water. The doses are calculated using the methodology and dose conversion factors of ICRP30. Using the ICRP30 methodology, doses are calculated as the committed dose equivalent (CDE) to the thyroid, the deep-dose equivalent to the thyroid, the committed effective dose equivalent (CEDE) to the whole body, external dose to the whole body, and the total effective dose equivalent (TEDE). The CDE to the thyroid is from inhalation of iodine, and the CEDE relates the dose to all organs from inhalation of iodine to a whole body dose. The deep-dose equivalent to the thyroid is contribution from submersion in a cloud of noble gas, and the external dose to the whole body is dose from submersion in a noble gas cloud. The TEDE adds the contribution to the whole body dose from internal organs to that to the whole body externally. The doses were all calculated separately for each release path. The code also calculates the release rates of the radionuclides of concern for specified time intervals and writes them to two output decks, one containing release rates from containment and ESF leakage and one containing release rates from the SIR W tank, for use in the CONDOSE code which performs control room habitability calculations. The methodology used to write the MHACALC code was described in full detail and the input deck for the code was explained line by line also giving limitations and suggested values for each parameter. To verify the functions*performed by the code, three test cases were executed. The first test case made use of all of the calculations that the code performs and was verfied by alternate calculations for every value sent as output from the code. The second test case was used to verify that by specifying a containment spray stop time in the input deck, the removal of elemental and particulate iodine would be terminated at the desired time. The test case confirmed that the spray stop time function of the code works correctly also. The third test case was to verify that a negative elemental iodine spray removal coefficient specified in the input deck would model re-evolution of elemental iodine, and results verified that the code did so correctly.

12.0 CONCLUSION

PALISADES NUCLEAR PI.ANT ENGINEERING ANALYSIS WORK SHEET EA-PAH-91-05 Sheet 49 of SO All of the calcuclations that the MHACALC code performs have been verified by alternate calculations that show agreement for all values. All of the desired functions that the code will perform have also been verified showing that the code performs the functions correctly. Therefore, the MHACALC code is functionally correct for performing radiological analysis of LOCA's at Palisades in accordance with Regulatory Guide and Standard Review Plan guidance.

""'ll'*W,a"".'ff .Ji';.."T:('.'. **.~* PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS WORK SHEET LIST OF ATIACHMENTS EA-PAH-91-05 Sheet 50 of 50

1.

Test Case 1 Verification of TR YMHA DATA Deck Execution With Hand Calculations, 57 pages.

2.

Basic program and verification to perform alternate sump activity release calculations 4 pages.

3.

Test Case 1 RETRAN Plots of ClMPLOT DATA Deck, 2 pages.

4.

Test Case 2 RETRAN Plots of C2MPLOT DATA Deck, 2 pages.

5.

Test Case 3 RETRAN Plots of C3MPLOT DATA Deck, 2 pages.

6.

Letter from E.C. Beahm (Martin Maietta Energy Systems, Inc.) to Jay Y. Lee (NRC) dated February 5, 1992, 3 pages.

7.

Form 3698 9-89, Palisades Nuclear Plant Engineering Analysis Checklist, 1 page.

8.

Procedure No. 9.11 Attachment 5, Technical Review Checklist, 1 page.

9.

Form 3110 1-82, NOD Document Review Sheet, 67 pages.

10.

Microfiche Titled - EA-PAH-91-05 MHACALC CODE BENCHMARK, 1 fiche.

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.. ---- j-ft;,_ ::: __ f. /~?'4'-S Af~:.: ?.'/flG,..S N:../N =-..5. tf_'l;£"+~ ~#/C _./, - /V,,, -:s. ~/~~.-s '..,~. .. /VJ~r _. S./tl-1'4".,.S'. A/Q ~41i'2e.,.S ..,, = . /V,$' ?.Str/tt!'".,G /V1NI ~/J',£~S N~.1JI' ~ ~ fb:1E.,..5 EA- &#-?/-OS Sheet _£_/_ of -S" 6 Rev# ______ _ Reference/Comment /f/,4'/.:V = 2.334~+7_.J.. ~?1.~~+S'. -t.. l/d'tf~c--1-s ~-2-4'.//lfc~; Form 3650 6-89
/'1701 e/e/114hl!;I 4.;, :=. /. ?;25 E~? ~~ ~ ;!. 382£".,.";I Me ;: ~,,8/f&,,.;i ~~., ~~..,== 3. ~19#.,.? ~::: 2.6~SE~7 ~£~ = 2.3&;J2~+.,.. = 19 .i"1"?1 ~~' := /.171£,,.~ N':a: ;;'. l.53C' ~6 . 1r =- :i. ;;147r... ~ M.J.:r E :- 2. '?.S~G~~ '111'1 " =
!. ?/

?.£~~
'1'.!l.S Form 3650 6-89 Ar/~C#,,,,eA/r.f PALISADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET EA - R?#'-'f'/-IP.S Sheet 12._ of...;;;:.S:.....6=--- !7~t:{;.1t,/a r~ I At~ = #, 3'38,r,,.5 ,,.,;"' ::; 5.,,~ £., 5' _M{,:: 7. 4?$.2E~S ,f/f;.. :: I. IN:ZE~5' ~
7,

Z l't'/ E~s 41;,~./ = S, r!~r.5 7
~~. A/!:1 = 3. ¥38/F.,.5 A//;.:.V, ~%8L""S~~
~~/:, = 5. S7.JF.,.S~~
~ = s:troE~s H~ = 5. S7;JE+S Rev # ______ _ Ql'f!(H1~ M=I' = 3. 7/6' £1'S /I{;& : S./.32E~S ~ '= 6.~,SE~s p~ =:. 7,3~~E~$' ~" :=6.172E"'S 1i. ~ "": ~ ~S?E-r§ M~I' :: 3. ?/~E"'S p,;a : 9, ;11r,,.5 .#~:: 6.Pl./Es6S" /ft:t- = l./23tt"'S ~~ ~ ~.8}22E~S Reference/Comment
4;,:: /.G7&E"*"~ ~~ =-:?.Kl3.,£y#~ ~ 1t!" ::: 2.11?..3 E.,,.~ ~";$
~~,,1~~
~~=.2. 385 E..1-tf NJ-'4'~~
~
~~.t.6"~E.,,.tf~~
!= ~~,:: l.b6f'5.J.6 ,.J,,ia: /.#$9'E.,.~ ./.!" :' ~-~7/tf"... ~ .N,.s.:r I" ':: /. Ps ?£..iii 'NI'/ Form 3650 6-89 '9'7'""~C#/l?&r#r 1 PALISADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET EA- !Jf#:V-os Sheet.113 of 5 6:__ ) ~~ :,?$<Pe.,1S At~ ~ J. ~8?E~S M~ =,//.~//E-6.S AJJ;.y = /,(~83BS ~~
~~.li.SS~Er'S I~~
(/,.;, = ~-

:Z:l.S*-'".F u~. =,1'. $/$.£>6-f pf;, : 3. S6/F~.S
~~~ =~~
2.~&>?t!T.15' H~ =

3. Q.SSI"'>'.$
~~Rev#-------- A{_;, "1.S~.3£"~.S ~~~
~~s. 961 #£<<"~~
,.Y~ ::. S.:19?.e~s ~;. ::.S: '141~ G""5" At~/ :: 3. '71P7e.,,.S ~'" ::,/_J /131£.,6-$ /Vl.l:JI At?~ =.s. 93/.T~.S ~111 = 4?.341'i'£-6$ p,3~ ~~ ; S. 751/'E~...S-Reference/Comment
4;,.:. /,6~~F .,#lff ~f;_ :::- /. 75(J?E~tf 6,e ::=,,2.t'//?r.. ~ ~3~ _,,1
~~1.6/r:l6e.,1~~~
NJ.J4f ~::: ;.5.:?-f!F*M ! = -;r.5' ~f, :: /. ~66 E.,.tf' ..c1:~: /. t:,,<~e~6 .,,V,~ -=..?. 6~?6~6 ~ : /..:J/8E.,.~ 'la'I ,!s:,7. 4'.S$E~ Form 3650 6-89 .::t !i2!l:J' --?-r/'1'C#/>/F#/ 1 PALISADES NUCLEAR PLANT EA-.?lf'£-f'/-e:7..5 Sheet 1<4 of $6 ANALYSIS CONTINUATION SHEET ) At~ ; /. 73/.r~s At~ = .i $/B e-.... s "':_, = ;?. ;r.Sdl.l"o#~ ,,.,, = /.£~9.r... s ~ ~.7-~.?tflE.. s 7 .1?.:: /-34rE.,.:S /f/l~I Al~. = /. 3/.3 c....s .Al~ :,2./;lf"E~S Alf~ = /.41~6£.,.S //~ =/. PIJl&.,..S Rev#-------- M~I' =
~~3. 7~ e.,..s~~
~~,,.~ = 3.91??£.. 5 ~3& ~~~
~~.S.$B:3e.... s~~
~~=:. 3..56~&.-s /V~., .110~~
~~5-~~5 E...-S~~
~~/V.1iJI ,,y;~,, :: 3. ?d?&> e,,..s ?,,.,,.,,,,&.,,,.$' /VIJ11 - v*our . 611~~
~~s.9.3~&.,.S N.-.~~~
,,./0 : 3,.fi'.:lrE.. S ~3"1 .IP -:: S. ~5?e .... S N1~ Reference/Comment
t;=;::\\ cans:!'1r5 9 f;;;!;;:/ Power lllllCNIGAll'S l'llWEltHI& l'flllllilt5S /::. 9'~ /'101 e/eP?~AZ';/ 4;, :./.~6?E~6 ,..v;f.z. :::. /. 6&~ c.,~ ~:s ;;:: ;l.btt;:S E.,,.~ ~~<9"::. /. i!il9.2 E~~ ~::,2. 314' &... 6 JF - RIJl"/:JI - -~j,#'"t:..16 i't ~i~* :\\":~'"tr; ~r/;l?c#~EN'r ; ... ::It.-11";..!l PALISADES NUCLEAR PLANT EA - ~#-f'!'-tPf Sheet _£L__ of.s ~ ANALYSIS CONTINUATION SHEET pd(t;(;..v/a i-~ 7 Al~ ; /. &J~t9 e-~s ~~ :;,. 4'/llf? &-6,,,, Ah~= /.b4't!f1£o#S Alf',.,, = 6.. B/..3E....y ~~ ::: /..Sdf 7£ ~s ~'" - /I/All~/- ~37~£-;-$" Rev# ______ Reference/Comment 01Jl4_A1c. 11t:I' = 3.b?7&.....S /II.:& = 3.3.Y/4"1'5 ~ ~ 6. ?$'tfe.,..s Al~ ~ 2. 41&.:? <,,.s Al/' :: s. 3/~E .,,a,s Iii Al,:,,,, = 1': 85.3~-;5 AJ,S/31.: ;2./D'-?'~~6 + l.;376-~..,tS ~#S.3E+S.= :Z;8t!97E.;6 != /i!PS P?U'J eh ~f, :: /..6.if 2 ~.,16' l#ta.: /. 3?~e,,.tt ,A/,~: 2. 6#3 E--6 ~:~'=' 8-Br?&,,..s 4;_1..,/ = 2~/r~E..,,.(f'. 7 w~(/eulaz'"~ AJ,':1 =$./S~.F,,.9 ,vf;. = 6.#4/.5,CY'? ,A//;, : /. ;l~ ?F.,-,s AllJ, = ~~e.,.41 d~ = /./~3,.-s AJ:,,,/ ::'. /, t!Pt"1 E-15 .Ak.r...,, = 2./?6£.;~ r /. 6J(,?.;-5 Form 3650 6-89 ~r.¥!/i.:'l 'C M~/ = 3-P?~£:1'5 P,:a :: 3.tRPP&~s ~JI :: S. ?.3$/Fr.:S N~33 /ft:" = /. ?~&~s ~~ ;.S./?f'E,,.5. ~10 /VN,,,,- ~835&~5 + f.#.3S~-/-.5 = ;2, 7~6'E~tff
@) F0'5.1t.~ consumers Power l'llWEllllllli lllllCHll&AWS AlDliltESS 4;,. =/.6~~£,,.~ .. 1£ ::i- /. 2?J&.,#~ ,,,,,2. .. 1& :::=.,2.56'.7 £,,.6 N,,~~ ~~4' ::: ?. 2,~ & ~.s ~:; 2. ;t?/£11'~ /3S ""4~':: /,658c.,,.~ Alt~:. /. /f,$~"'6 .,,V,~ =- ;. s~/ £~6 r =- s: f?'?e,,..s 'la'I Form 3650 6-89 1.53.:t. ~r~#.A?GV'r.$ PALISADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET EA - /ff',L-t'/- ~s Sheet q~ of..s<' ) /ft~ ;: b.3+'.S E~.P A6{z ::; ~ '?~2 4".. '9' .. 11' : ?. 78SF,..<ll N-' ..,, ::.<. "??dic..-<fl N-¥ k::: 46'?ifll"~, I + Al"' = ¢ ?3r ""Y U~s: 3.:S~E.,.'9' ~:
~~!.SS'?F,,.~~~
~~~ = /. ;r§JE.-1' //~ = 6.5?~.&1'+' Rev#-------- M=/ = 3.6f/#£"rl'S .. ~ = ~.$';?/<£,,.$' ~.SC .,,,; -: s.~P4l *-*S ~.316 ,Al~ = /.~/,;r..... s- ,1 J IP~~
~~,5.,!9-1'41' t5° J14.S~~
/V.1i6 M~/ = J,~H 4" ~.s ,1/'1 "7 *"-.7&.,.5 /Vl.1:11 - ,,c.1:'61* .11 = S.~&&~~ N"'.s3 /ft:~= /. 3;r;tF..,,.S ~~ = #. ?n &-*s Referenc'e.'Com ment
4;, = /.656' er~tr AJ;~:::. /.///F~~ Al,:., ;:::,2.:S;2&:? £.,,6 ~~4" :: ~ 9&16 e<#-S ~::: :l. /.:SSe~"' ~;, :: /,~ S+' E~b ,.;:~: /.&(3dld!'~i5 A{~':'..2. 499 &~tf' r ~ 4-4' 7~ r~.s- .,a'I Form 3650 6-89 ,,.;; rT.;Pc#~&.ur 1 .:i.532 PALISADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET EA -,Z:W//-Yett/5 Sheet ~;r of.5 ~ I ~~ ; J,941/ £.,,,.4' M~ ~ 2,S7~E~t' ,.,, ::::.S: B~ E,,,...Y N/,.3 ,.,, = /./.394"',,,..+' N/,¥ ~~ ;: ~ ?,,,a-.....y I Af,'; /.: 2. 969 £,,,. 4' .u~. = /.8Ple~+'
~~j;, : 9..SlllrE.,,,.~~~
~~~ = ';;! ;?7'?~J H~ = 3. ?,l'~F~.P Rev# ______ _ M:I' = J,'5Bs E,,,.5 .. JI~~
~~2* +'~8$.d"~~
~~~,3/t ~~~
~~s. 5'i'6 ~~s~~
~~,Al~ = /. &?B?e.-..5 Al.:. : ~?I/SF~ At~,, = 3,~#.2e.,f$'~~
f/,fa

~~E~S M~ = S, 6.S~E~.5
/ft:., = 8. f 3~&.-.P ~~ ~ ~ 16'/ e'.s Reference/Comment
(@ tF'~".1t:S11;t cansumerr Power IPllW/EIUl!lli MICHIGAll'S PflOlillUS 4f, = /,652 E+* ,.,£ ;::i. ?..S??&.!-5 ~,z.. ,.1e ::= 2.~?8e+~ N,,~s ~~.,,::: J.3lilt'~'l1'5 ~:;; 2.414'1'&.. ~ ~f,:: /.t/5/e"'~ ,.;,:~::. 8. BS..3 E~.s
~~J£ : ;2. P.S 7 e,,..~~~
~~A',3,:r E ~,2. 7//6,.S 'la'/ ,,!_s= /. f~/,.,.~ Form 3650 6-89~~
~~"fr, "1 rrAc#/1?£4/-r.f~~
~~.:l5.::i3 PALISADES NUCLEAR PLANT EA~~
~~M#-?7-.05 Sheet f8 of..s 6 ANALYSIS CONTINUATION SHEET~~
~~) Al~ ;: ;? *.3:2~ E~t' ,,.v;{a ::; /..34'.3.F,,,.+' ,.1, = 3.f'8/F.,.? AQl.J .J' = 4,~.S:JF"~ N/.7¥ k::.2.8iTtJl&+<f 7,,v;,1 = /.8/d?e"'1' ,.1P - f'r~ f;rr.,..3 N,7s * ~~~
~~2.~BBE~9" A!}, = 2, 9?3E"'.3~~
~ = :?./??~++' Rev# ______ _ M:,, = J.~ ??tr.. 5 /I(;& : 2./;l/E"'.S ~ 5:51/~E.,,S .Al~ ::; 7.-"..3 e-~9 ~J" = ~.S+'t'/,,,...5 /V,1,il At~.1 = .:J.~ ;z~&...s .AJ,/11 = h?~~e~s ~~ =.s..Y.SBe"'.s ./lf:fl = ii'. 41/I&~ t' ~.d '= ¥. 4/,-,;J&".. S Reference/Comment
e/e,,,,~~I 4;,;::. /.6.54>~""'5 ~~ ~ B..7tPBe... 5 Me ::: ;2. ¥37E~" /.,., ~~'9':; 2. 2:26E~5 ~::: /, ?3~E~I/' A'£.131 = ;2./.2'9'c r.6 A4~1 :: /..6 ~9E"'6 N::: 7.'4JS9£.AS .Jlf' =' ;i,::J'17£~'5 M.s~ .,:11 = /.1'?8.£~.s Form 3650 6-89 c /lrrA-C#'rYE#r.f 1,:::.:it: 3114, PALISADES NUCLEAR PLANT EA - $,#-?/-a-:r Sheet t:.? __ of 5 & __ ANALYSIS CONTINUATION SHEET O,(l.t:.4.t:&.1t.~ r~ I 4~: /,~61"E""~ At~ :; ~
~~r:;;rtJ?E,,.~~~
AJ,' :: ;:z, 4-'.S~E~~ Al/;.-= ;? *.23?~~.3 ft'~;:: /.?.:SJE..,_-1' 41;,~I:..:l,/~EY-11 I AJ/;1 = /.bh/E.,,,4' Al~- = "7. /~.&'bJ ~ = 2. ~/..?E,,..Y ~ = /. 5~9e-... 3 .N~ = /.'.s3e-.-I' Rev#-------- Ql"f.~1"'e,.. ,? _M=/ = 3,~ '?J E...:S /JI;& :: /.$23,e,,.5 ~ ~5.~JE.,..S ,A/~ :: ~?J9E"'1" .M."'
~~= "" 3fi);z"£~5~~
,~ ,)/,~ - 1£1'/ - ~r.z$E7'..S At~/ = 3.~b3tF~s M::. = /.S6$E,,,.S ,d~: 5,.3.A'A'E""S d:#JI = 3.3~£.;.Y ~~:: ~tiJN.e~s Reference/Comment
(@ F[lf.5:it:1f: consumers Power l'flWEllHI& MICHll/iAll'S l'ffOlilUSS -r::. ~#19 ~01 e /e,,,,t!!h~ I 4;, =- /.625&~6 Al,~ :;;.;?./&se"'.s ~%, ::=,7. tD'f$e w#6 ~~.,.:: 6.33~£~3 ~;:; /. ~&Be-;6 JF - RN"~- 2.'9/efE~6 j;.~i35 ."1-rr~~.rA/"r f PALISADES NUCLEAR PLANT EA - &,!/-?/-.cJ5 Sheet $&<. of....5=-..;6~- ANALYSIS CONTINUATION SHEET pt1e!:tcv/a r~ 7 At~.:: /.,(';37$7'+' A6{a :: ;l. //lie"" 3 M~ = ;?,//,;/ E"i' 41 Alf,.,, :: 6.376t:r,,./ ~~ := /.,;l/6E,,.~ A/11'1 '~I ::: ;:<, ~3/ E -r ¢ Rev # ______ _ Ol°ll.41 e. M:/ = 3.6/&?E~S A{.;& :: -¥. h 7/ £"9",Y ~ ~~S?~~.5" .N~ :;I /,4"~6~3 ~;. = ;?.ib6.7L°"'.5° ./I d NIE/ - -r, /;l??e>'.5 Reference/Comment A/n,,, = 2,19/6E-.<tt 2.t!9JA9f' + 9,4??Er.5 =.2. '76'r'c...-If" != 7~ 0 ~ ~~ ~~' :: /. 6~.:l E~6' I _ /4° '1V1:112.: 6. 26SE..,..Y /Yf~: i,5'36£~6 ?:~~,2.678£.;-2
!

I
'/35 - 7. T'.28 £.,.S 4:,,,:,, = I. f.'.Jt°~7'6 wdt'(:ukz'"P. / A11'1 = /,6/.34~~ Al~.= 6'3/11(£.,.:2 ,M:, : /.,4/#E~. ~ =2.61~&,,./!R .N~ = ";{981~~.3 ~ NlllF/JI:: /, 9~?tF..,..9' 01".J!aA '<:! M~/ = 3,SS$E... 5 A/,:11 = /,3,.:2.F.... ~ ,d~ = £ &7SE~5" /ft:f':..S:~'!'Se-'I A/,~::/, 76Bif"-6S ~1P - /VIM"- 'f/,,299£.,.S ~""' =./. 936&6 +- ./.f11'9c,,..~.t1.:znG.s- = 2. 38S".£"-'"~ Form 3650 6-89
lt'.::'!f;'ll'\\ll:;;;;ii1'1~. 1£:*~ ~~.tt _.,,.. ~ consumers Power PflWEIUNli MIClllGA#"S l'flll6RESS Al,~::: t$'.J?~~(._ "/8:#Z: /,~~E .. 3_ *-. A/,f, = /..2MG,.~ ~::::.,Z~f,?&-:-~---L"._. Form 3650 6-89 A~C#~tF#r.f PALISADES NUCLEAR PLANT ANALYSIS CONTINUATION SHEET EA - &L-!Y-as Sheet ef/ of..S§._ __ Al:,:: A,'.sf_,~.,,.~ -- ~~ = /.~~8&'..,./ ' ~~
~~_h~.36e;,.~_.~~
i _AJJ;~=- :t.tll31£~1/.; ____ _ .M.- - ~~:ts~ r~- _ _. Rev# ______ _ -* ~J'I =- 3~ +'4'~&~.S .Alk =-3,~IJ!s>e.- 2 . ~~ -=,?.rJ4!F~S -.A?ffl.: -~.P'?//8-.3 H/~* = ~,1!$1"~, Reference/Comment
FILE: CHKPLOT DATA Al VM/IS 5.1
~~VERIFICATION OF CIMPLOT DATA FOR CASE I~~
~~=MHACALC DATA PLOTS 010001 -3 0 2 4 0 0 4~~
~~TABLE I - ELEMENTAL IODINE 120100 23~~
+
0.
~~2.370E+07 +~~
~~1. 2.370E+07~~
+
2.
~~2.353E+07 +~~
3.
~~2.336E+07 +~~
5.
~~2.302E+07 +~~
~~19.~~
~~2.224E+06 +~~
~~30.~~
~~2.217E+06 +~~
~~45.~~
~~2.209E+06 +~~
~~60.~~
~~2.202E+06 +~~
~~75.~~
~~2.193E+06 +~~
~~90.~~
2.184E+06 + 105. 2.176E+06 + 120. 2.168E+06 + 135. 2.160E+06 + 150. 2.152E+06 + 165. 2.144E+06 + 180. 2.137E+06 + 195. 2.130E+06 + 210. 2.124E+06 + 240. 2.112E+06 + 480. 2.016E+06 + 720. l.936E+06 +
1440,

1. 748E+06
~~TABLE 2 - PARTICULATE IODINE 120200 23~~
+
0.
~~6.206E+05 + I. 6.205E+05 +~~
2.
~~6.098E+05 +~~
3.
~~5.994E+05 +~~
5.
~~5.790E+05 +~~
~~19.~~
~~4.575E+05 +~~
~~30.~~
~~3.797E+05 +~~
~~45.~~
~~2.945E+05 +~~
~~60.~~
~~2.285E+05 +~~
~~75.~~
~~l.773E+05 +~~
~~90.~~
~~l.376E+05 + 105. l.067E+05 + 120. 8.284E+04 + 135. 6.429E+04 + 150. 4.990E+04 + 165. 3.873E+04 + 180. 3.007E+04 +~~
~~195.~~
~~2.334E+04 + 210. 2.141E+04 + 240. 2.127E+04 + 480. 2.031E+04 + 720. l.949E+04 + 1440. l.760E+04~~
~~TABLE 3 - ORGANIC IODINE~~
~~F059~~
~~t53S FILE: CHKPLOT. DATA Al VM/IS 5.1 120300 23~~
+
0.
~~4.965E+05 + I. 4.964E+05 +~~
2.
~~4.963E+05 +~~
~~3. 4.962E+05~~
+
5.
~~4.959E+05 +~~
~~19.~~
~~4.940E+05 +~~
~~30.~~
~~4.926E+05 +~~
~~45.~~
~~4.907E+05 +~~
~~60.~~
~~4.888E+05 +~~
~~75.~~
~~4.870E+05 +~~
~~90.~~
4.853E+05 + 105. 4.835E+05 + 120. 4.819E+05 + 135. 4.802E+05 + 150. 4.786E+05 + 165. 4.771E+05 + 180. 4.755E+05 + 195. 4.740E+05 + 210. 4.725E+05 + 240. 4.692E+05 + 480. 4.479E+05 + 720. 4.299E+05 + 1440. 3.882E+05
~~TABLE 4 - TOTAL IODINE 120400 23~~
+
0.
~~2.482E+07 + L 2.482E+07 +~~
2.
~~2.464E+07 +~~
3.
~~2.446E+07 +~~
5.
~~2.4IOE+07 +~~
~~19. 3.176E+06~~
+
~~30.~~
~~3.089E+06 +~~
~~45.~~
~~2.994E+06 +~~
~~60.~~
~~2.919E+06 +~~
~~75.~~
~~2.857E+06 +~~
~~90.~~
2.807E+06 + 105. 2.766E+06 + 120. 2.733E+06 + 135. 2.705E+06 + 150. 2.68IE+06 + 165. 2.660E+06 + 180. 2.643E+06 + 195. 2.627E+06 + 210. 2.618E+06 + 240. 2.603E+06 + 480. 2.484E+06 + 720. 2.385E+06 + 1440. 2.154E+06 020101 'ABCD' 0 'LIN' 8.0 0.0 400.0 'TIME (MINUTES)' 030110 'LOG' 5.0 I.E+03 3.E+07 'ELEMENTAL (CURIES)' 030120 'LOG' 5.0 I.E+03 3.E+07 'PARTICULATE (CURIES)' 030130 'LOG' 5.0 I.E+03 3.E+07 'ORGANIC (CURIES)' 401101 'TABL' 0 -1
~~PLOT TABLE I ON FRAME I~~
~~. /I T7AC/l/l'fc#T 1 FILE: CHKPLOT DATA Al VM/IS 5.1 401202 'TABL' 0 -2~~
~~PLOT TABLE 2 ON FRAME 1 401303~~
~~'TABL' 0 -3~~
~~PLOT TABLE 3 ON FRAME 1 020201~~
~~'EFGH' 0 'LOG' 8.0 1.0 1440.0 'TIME (MINUTES)' 030210 'LIN' 5.0 0. 30.0 'TOTAL DE 1-131 (MEGA-CURIES)' 402101 'TABL' 0 -4 0. 1.E-06~~
~~PLOT TABLE 4 ON FRAME 2~~
=PLOT CHECK - CTMT ATMOSPHERE DOSE EQUIV 1-131 ACTIVITY vlT -/~/1-~/-e;'.5 ~e :S~ d°5tf
Fll59 CJRGANIC (CURIESJ 103 101.f 105 106 107 108 I I I ii II I I I 111 Ii I I I I 11111 I I I I 11111 I 1111111 PARTICULATE (CURIESJ A 103 101.f 105 106 107 108 II 11111 I 11111111 I I I I I ii II I I I I 11111 I 1111111 ELEMENTAL (CURIESJ 103 101.f 105 106 107 108 0 r U1 GI 0 -I ("")
r:
~~rT'I ("") ~ 0 0 ("") -I 3: -I~~
~~n U1 0~~
~~-I -I 3: GI 3: (./) rTJ~~
~~i:::~~
~~rT'I 3:N _o~~
~~0 zo rT'I c~~
~~0 -I GI rT'I (./) (./) rT'I N rT'I U1 0 0 c - I - w 0 w 0~~
n
("") -I - w U1 -I 0
1-- 1-u a: - (Y") - I - Cl w w (/) 0 0 w 0:: w
I:
~~a.. (/) 0 ::c l-a: 1-~~
~~c 1-u~~
~~~ u LLJ~~
I:
~~u l-o ......J a.. OE ~z 91 Zl 9 (S3I~no-~03WJ 1£1-I 30 l~lDl (/) w I-N oZ -- -0 0~~
c w

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FILE: BENCHMHA.BAS

PAGE: 1 of 1

Length: 2405
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~~1 to 78 Created: 02/14/-:30 Queued: 02/14/9~~
48 10 REM PROGRAM TO CALCULATE MHA ESF & SIRW RELEASES OVER A TIME INTERVAL 15 DIM QSRW(5),QESF(5),LAMl(5),N(5),ASRW(5),Al2(5),Q(5),C(5),NUCS(5) 20 VTANK = 38767.2 30 VRAS = 3739.3 35 PFESF=10 36 DFESF=2 40 PFSRW = 1 45 KSUBD = 2 46 Fl2 =.3 50 LRSRW =.13368 55 LRESF =.053472 60 INPUT 11START TIME OF INTERVAL 11;ST 70 INPUT"END TIME OF INTERVAL"; ET 75 INPUT"SUMP VOLUME AT BEGINING OF INTERVAL, FT**311;VSUMP 80 DT=ET-ST 90 VLIQ=VRAS+(LRSRW*(ST-19))
100 VAIR=VTANK-VLIQ 101 FOR 1=1 TO 5 102 READ NUCS(I) 103 NEXT I 104 DATA 1-131, 1-132, 1-133, 1-134, 1-135 110 FOR 1=1 TO 5 115 QSRW(I )=01 117 QESF( I )=01 118 Q(l)=OI 120 READ LAMI (I) 130 NEXT I 140 DATA 5.986E-5, 5.045E-3, 5.554E-4, 1.318E-2, 1.754E-3 170 INPUT"INITIAL SIRW ACTIVITY OF EACH IODINE";ASRW(1),ASRW(2),ASRW(3),ASRW(4), ASRW(5) 175 INPUT 111NITIAL 12 SIRW ACTIVITY OF EACH IODINE";Al2(1),Al2(2),Al2(3),Al2(4), Al2(5) 180 INPUT" INITIAL SUMP ACTIVITY OF EACH IODINE";NC 1),N(2),N(3),N(4),N(5) 190 FOR 1=1 TO 5 200 C(l)=Al2(1)/(VAIR+PFSRW*VLIQ) 205 Q(l)=C(l)*LRSRW*KSUBD*1 210 NEXT I 220 FOR J=2 TO DT+1 230 VLIQ=VRAS+LRSRW*(ST+J-1-19) 240 VAIR=VTANK-VLIQ 250 FOR 1=1 TO 5 260 QESF(l)=QESF(l)+((LRESF*N(l))/(PFESF*DFESF*VSUMP*LAMl(l)))*(1-EXP(-1* LAMI( I))) 270 ASRW(l)=(ASRW(l)-Q(l))*EXP(-LAMl(l)*1)+(LRSRW*NCl)/(LAMl(l)*VSUMP))* (1-EXP(-1*LAMl(I))) 271 IF (ASRW(l)<9.999999E-21) THEN ASRW(l)=O! 275 Al2(1)=(Al2(1)-Q(l))*EXP(-LAM1(1)*1)+(F12*LRSRW*N(l)/(LAMl(l)*VSUMP))* (1-EXP(-1*LAMl(I))) 276 IF (Al2(1)<9.999999E-21) THEN Al2(1)=0! 280 C(l)=Al2(1)/(VAIR+PFSRW*VLIQ) 282 Q(l)=C(l)*LRSRW*KSUBD*1 285 QSRW(l)=QSRW(l)+Q(I) 287 N(l)=N(l)*((VSUMP-(LRESF+LRSRW)*1)/VSUMP)*EXP(-1*(LAMl(I))) 290 NEXT I 295 VSUMP = VSUMP-(LRESF+LRSRW)*1 300 NEXT J 410 PRINT USING 11 \\ \\";"NUC", 11 Asrw Qesf"," Qsrw"," Nslll'p" 415 FOR 1=1 TO 5 419 PRINT USING 11\\ \\ 11;NUC$(1); 11 II I Al2 420 PRINT USING "- _ ##.####* *** 11;ASRW(I >;Al2( I );CCI); 425 PRINT USING "- _ ####.####";QESF(l);QSRW(I); 426 PRINT USING "- _ #.####""""";N(I) 430 NEXT I 435 PRINT "VSUMP =11;VSUMP, 11VLIQ =";VLIQ, 11VAIR =";VAIR 437 PRINT II II II II I 440 PRINT"START NEXT INTERVAL AT END OF THIS ONE (Y or N) 711 450 XS=INPUT$(1) 460 IF X$="N" THEN 600 470 ST=ET 480 INPUT"END OF NEXT TIME INTERVAL";ET 490 DT=ET-ST 500 FOR 1=1 TO 5 520 QSRW(l)=OI 530 QESF(l)=OI 540 NEXT I 550 GOTO 220 600 END Cair ", r t
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Ok RUN C T TIME OF INTERVAL? 30 TIME OF INTERVAL? 31 VOLUME AT BEGINING OF INTERVAL, FT**3? 40302.44 ITIAL SIRW ACTIVITY OF EACH IODINE? l.3531E3,l.6543E3,2.183E3,l.9452E3,2.157E3 INITIAL 709E2 INITIAL NUC I-131 I-132 I-133 I-134 I-135 VSUMP = I2 SIRW ACTIVITY OF EACH IODINE? 4.0592E2,4.9628E2,6.5487E2,5.8355E2,6.4 SUMP ACTIVITY OF EACH IODINE? 3.709E7,4.523E7,5.981E7,5.296E7,5.907E7 Asrw AI2 Cair Qesf Qsrw Nsump l.4760E+03 4.4279E+02 l.1422E-02 2.4598 0.0031 0.3709E+08 l.7956E+03 5.3867E+02 l.3895E-02 2.9929 0.0037 0.4500E+08 2.3801E+03 7.1400E+02 l.8418E-02 3.9668 0.0049 0.5978E+08 2.0942E+03 6.2826E+02 l.6206E-02 3.4902 0.0043 0.5227E+08 2.3490E+03 7.0468E+02 l.8177E-02 3.9152 0.0049 0.5897E+08 40302.26 VLIQ = 3740.904 VAIR = 35026.3 START NEXT INTERVAL AT END OF THIS ONE (Y or N) ? Ok lLIST 2RUN 3LOAD" 4SAVE" 5CONT 6,"LPTl 7TRON 8TROFF 9KEY OSCREEN
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~~LOCAt. (~~
~~). . LONG DISTANCE. ( ~ '=-\\*"' .:*'.tr~~
~~'*r PLEASE TYPE OR US! SOLO FELD TIP PIN.~~
~~( TELECOPIES WILL NOT* BE RETURNED.) TO LOCATION~~
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~~2. ______________________________________ ~~~
~~FAX # VERIFICATION --------~~
~~3. __________________ --.,.._ ________ _..-.,_,, ____._~~
FAX #~-----~~----.-------- VERIFICAlJIION ---------------- 4*-----~----------------------------~--- FAX #-----------------~--- VERIFICATION --------~------- s*-------------------------------------...... ------ FAX #----------------------- VERIFICATION ________________ _ NUMBER OF PAGES ~ AND COVER SHEET P'ROM ..;:y o..s,e 4ns S 52 (1S~RC2.: PHONE*EXT. sC&-(o~~ . I ' *'(*:: .. ) I 1\\1. i'.t' c*:.
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MARTIN MARlmA INIAGIY IYITEMI, INC. Mr.lf.1Y.LM U.S.~ RlplatorJ ~ Mail Stop 10 D4 Wsah!nsiozi, DC 2l!'5 DelrJar. Bp: P' I ?§I 8 Si22 TO I.a I lollow*u.J:I to our C.Jtpho111 c:omenatfou, I wm outlme I teD!mlque for oalcu~tina iodme p1rtftlonln1 fD a Safety Injootfoa RefuellnJ Watet Tank. The 1top1 of tbe caleulatJon are a foJloM:
1.
Caleulate the concenttatfon ot fodiDe fn redtculatial water. ru wU1 be the ouriea of Iodine JA COAteinmesit dJ\\ISded by the volwu of l'Klrculatia, w.~. To calo\\alate wries ot fodinc in Mnt11fllmt"11t, ~ would ~ommend that JQ\\J use tho co&al core bMDtoey ot lodmo muJtipUod bJ 032. nae r.etor o.m oom11 rn. N1.1UOtca*5747 {J)eoember 1991) b1 It P. Nourbe!cbaab tor a PWR ~.preuure Mq\\llQOI. ~.
2.
~~Calculate tht totaJ O\\Uill ot lodme loabd into the RINellng Water TIU. Thia fa the curi* per unit wtume calculated le *top 1 aualtfplied bJ tbc total \\IOlumo leaked.~~
3.
Calcula&.e tbe cmtia ot Iodine u ~ that Wll lcakM Imo tbe llefucliq Wat<<. Tank. Jfor thla we reootnrQend a frac:tlon of 3 x 10'4 ot the total curies leaked into the taak (u c:alc\\llatcd ' ID step a). nu lactor ii baaed on NVREG/CR..m2(July1991) by Buhm et al. and appUea co the oue where pH control bu~ the pH at -.1.0.
4.
Calculaie the pmitk>Diq o( tbe OUriel of Ii In the R.cf\\aelln1 Water Tank. ID thfl cal~"lation. It fl sate to auwne that the ~ wn1 act bydrolpe to produce iodtde (I") and fodate (IO,'). 1-auae of the ;H of 5 IA the tank. The pardUora QQeflkticmt fbr I:a ea be obtained from BquatJon 26 of NtJUOICR-5732. We mq mumc 111 amblnt tCporlture of 25* C (289 K). and th>> wou1ct pa a partition coemoilAt for It ol 70.8. By UlirlJ the definition or patt:itlcm ~t. wo ou obtain it. curicl ol icdm m tbt llefuellq Tank pa: ........ oodn'.. bJa*.......... ' ~ TM curiel 11 ~ loUod into Chi Wik (c.k:ul1f.Od m ltep 3) mmt bl either ID tho Pt or~ the water: .* ~ I'.
I.
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t-:::~os-9 Form 3698 9-89 PALISADES NUCLEAR PLANT ENGINEERING ANALYSIS CHECKLIST Items Affected By This EA Other EAs
2.
~~Design Documents Elec E-38 through E-49~~
3.
Design Documents Mech M259, M664, M665 4.0 LICENSING DOCUMENTS 4.1 Final Safety Analysis Report (FSAR) 4_2 Technical Specifications 4.3 Standing Order 54 5.0 PROCEDURES 5.1 Administrative Procedures 5.2 Working Procedures 5.3 Tech Spec Surveillance Procedures 6.0 OTHER DOCUMENTS Q-List .2 Plant Drawings Equipment Data Base 6.4 Spare Parts (StockJMMS) 6.5 Fire Protection Program Report (FPPR) 6.6 Design Basis Documents 6.7 Operating Checklists 6.8 SPCC/PIPP Oil and Hazardous Material Spill Prevention Plan 6.9 EEQ Documents Affected Revision Yes No Required 0 181 0 Ja 0 !El 0 f:) 0 g:i 0 g:i 0 ~ 0 ~ 0 ~ 0 ~ 0 ~ 0 {('.) 0 15(/ 0 ~ 0 ~ 0 ~ 0 Kl 0 g1 Do any of the following documents need to be generated as a result of this EA: Yes No
1.
~~Corrective Action Document? 0 RI Reference~~
2.
~~Safety Evaluation? 0 Kl' Reference~~
3.
~~EEQ Evaluation Sheet? 0 g Reference Is PRC Review ofthis EA Required? 0 ~ Identify* ompleted By _ _,./k ~,_~_..,..L ........ ~=--'=--------------~~
~~Identify-Section, No, Drawing, Document, etc.~~
Closeout Date zd~z_
TECHNJCjL BEYIEJf CHECgLIST EA - /?1/1-9/-a.5 REV. 22 Proc No 9.11 Revision 5 Page l of 1 This checklist provides guidance for the review of engineering analyses. Answer questions Yes or No, or N/A if they do not apply. Document all cements on a 3110 Form. Satisfactory resolution of co11111ents and completion of this checklist is noted by the Technically Reviewed signature on the Initiation and Review record block of Font 3619.
1. Have the proper input codes, standards and design principles been specified?

2. Have the input codes, standards and design principles been properly applied?

3. Are all inputs and assumptions valid and th1 basts for their use documented?

4. Is Vendor information used as input addressed correctly in th* analysis?

5.
~~If th1 analysis argument departs frOll Vendor Info...ation/Raco111111ndations, ts th1 departure justtf1cat1on docU1111nted?~~
6. Ar* assumptions accurately described and r11sonabl1?

7.
~~Has th1 us1 of ang1neertng judg... nt been docu.antld and justtfted?~~
~~8. Ar* all constants, vartabl1s and formulas correct and properly appl11d?~~
~~I (Y, N, N/A) y 'I y y~~
9.
~~Have any *tnor (tnstgntftcant) errors been td1nttftld? If ~ yes; Identify on the 3110 Fon1 anclJusttfy their instgntftcance. l~~
~~10. Does analysts involve welding? If Yes; verify the following tnfon11ttoa ts accurately r1presentld on the analysts drawing (OUtput document).~~
Type of Veld

Stu of Wild

MabPial Being Jotnld

Thtclmess of Material Bltng Joined

Location of Veld(s)

Appropriate Veld Symbology
~~11.~~
~~Has the objective of the analysts bl1n.. t?~~
~~12.~~
Have admtntstrattve r1qutr1111nts such as numbering and fol'll&t been sattsftld? '/
NUCLEAR OPER S DEPARTMENT coPc Document Number Revision Revision Number Item Page and/or Number Section Number 0 6-hre EA Ol.. ,As-5vmph~vi 5. / 3 ,+,.sv1*1p11i*~ 5: ~ 1~~~akJ*~~~n. ~-~-*_,_~_~_e_c_M_~_._,_~e_i_s_~_~_o~_c_l_~_~_~_0_~~~-~~~~~~~~~~~~~~~~~ 1-----c+-------t-jc.+ -::O~~ec.~d-/o vHX3 <t //HX-Lj_ '/ov ~h<A)J a5cer-fu/,,, whdlAe;r of'.Mof ffv, av-r f~o-i.J----¥'.r<:Ul~./ C -5ec{~-&~---=:!.J-._...£.I<O_J..cZ_£-r-----1 t------+----------1,.,1,,, aaciJ,,J c,.J,-;,,,,,; _t..,41'.",h lo wY f!i,; vc/ow,~ _ Tiie G?:'~otdirM -*-fU.'~~~~ -~=--F,/:1"~;~~,t~ ;~~.~~~~~;,; o~~~~,~:,r~~;:~:~~1~~ -~;::c~~;~~~~~----l
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NUCLEAR OPE NS DEPARTMENT Documen eview Sheet Document Number Revision u-ftfll -"11-os-Item Page and/or Number Section Number Comments Date Date qOcC?/ ~~ Form 3110 1-82
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PALISADES NUCLEAR PLANT TECHNICAL SPECIFICATION SURVEILLANCE PROCEDURE Proc No DWC-2 Revision 12 Page 7 of 8 _______________ 1_1_T_LE_: __ P_c_s_RAD 10CH EM_I_s_TR_Y_ANAL vs_1_s ______________ __ 5.2.7 Analyze for dose equivalent 1-131 as follows:
a.
~~Perform ganma analysis of sample. Ganma Spectrum Tag Word Number: ___ _ File Number: ---- Sample Taken By:------'------'---- Signature Date Time~~
b.
Calculate Iodine Dose Equivalent factor using ganvna spectrum results using the formula listed below: Data Results 1-131 (µci/ml) x 1.0000.. __ _ I-132 (µci/ml) x 0.0361 = __ _ I-133 (µci/ml) x 0.2700 = __ _ 1-134 (µci/ml) x 0.0169
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~~1-135 (µci/ml) x 0.0838~~
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~~1-131 Dose Equivalent Factor~~
~~. 1-135 Analysis Performed By: ------'----- Signature Date Calculation Verified By: ------'----- Signature Date~~
c.
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d.
If specific activity is ~ 1.0 microcurie per gram dose equivalent 1-131, sample frequency shall be increased to once every four hours. 5.3 Complete Attachment 3, "PCS Chemistry Analysis" and Attachment 4, "PCS Activity Analysis" of Chemistry Procedure CH 1.5, "Operational Chemistry Logs, Records, Graphs, Labels and Data Sheets." 5.4 Laboratory Supervisor shall complete Acceptance Criteria and Operability Sheets.
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. U.S. DEP~Rn.mn OF COMMERCE ffational T~chnical li1formatiun Sert'ice TlD-l-Hi-14 CALCULATION or DISTANCE FACTOHS FOR POWER AND TE~T l\\EACT0£{ SITES j.j. Dinunno, ct al Atomic Energy Commission Washington, D. C. March !962 HEALTH PHYSICS REFERENCE LIBRAFY NUCLE.l\\..~ AC'l'IV!T!ES DE?ARTHE~'T
Table III Dose to Critical Orten Per Iodin* Curie I~bahd Iodi"n* ~/A.i(rads.curie-1 ) Isotope T (11ec) V.. e l}l 6.57 :'. ia' i.r.s :r. io6 I'() l}Z 8.}9 x ic' .5*}5 :r. )0.. ,,.,3*6 l}} It 7.52 :r. 10 lt.O x lrY
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c. External Gaema Dos~ C.alculatioae The external galllll& radiatioo dose at the exclusiOG and lo* populatina ~one dietancee due to !iaaion producta cout..t.ined in tbe reactor building *ere deter-ained in the !ollowing llaDn~r. The eource or radiation waa conaiJered to be thoae Ciaa;on proct~cte released !roa the pr1t'Bry ayattm to the contain=ent bW.lding**krypton, xenon, iodi.neo, and & uiixt~e or the remir.ing 11Mlid 11 mixed riaaion products.
~~From a point ao~rce or rsdistior.*given o!f by a &jlGCific ~~mo:na. e~i~tiri~ isotope, the dose rate at a distance1 d (metera)1away in air is ~iven by. ecouatiOll (10). 2 2 z,.r. d (meter ) *********,~~
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ClMCALC.DAT r;tk CASE 1: BENCHMARK RUN OF MHACALC CODE ()e\\>v_? 1 Lil. '1.{ Jg.y . ovrJw1 4 3 2 0 0 ,..~t c_,-\\J ..Jsu"'f 2530.0p,wen 0.10 40304.5 100. 0 F'NG -~' 25. 0 FIA 1:.. Af-: 50. 0 Fl.5 i:.....,... p 95
5 fcr{i) eiftll.,d./. 2

5 flF(~)P"'i-.J.J. 2

0 FtF(3)o'2*'L t<rl,,
2. 0 Of?Ei6P-

10. 0 l'FcsF

1. 0 P~11.w

2. 0 3.47E-04 1.75E-04 2.32E-04 13,..J-'1CO,li),l3)

1. 55E-04 c.1-1:i:QJ"e.
~~set(... J V-ra* ~ 1 fl.) 38767.2 lls~w,lit W 3739.3~~
1. 09E-05

6. 94E-06

2. 58E-06

6. 25E-07 Ln'GttI OJ, (i)J (]Ji!) su:/""3

1. 00 srf.!~S~\\lli 0. 000 SPAAfl\\(iJ,.fi.. o.f!.J~r\\J.<.,
~~h.- I. I -/ skAA*p...Y.a;. l T~L(*)~~
~~0. 420 SPM61.(*) el,>., *.-~~
~~hV' 5 16l!2J 10. 000 sfAAe<.llJ 19 T1it.l3J o. ooo seP-A-a(J) 7 2 0 JEL(<l) 0~~
~~4 2 0 5fllJtGl.(t.(}~~
~~. _o -:i:~c~L.-o.* o.oo __ $_P!#L(s)~~
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~~0 Sit>PfPRh 19 T'G5F(l) 0~~
~~2 Ll\\ssp-(1) 19 TSlf\\*.tf/I) 1. 000 LR5Rw (1) 0 T&Sl'(.2)~~
0. 0 (2) 1440 1Sh1.11"(<)0. 000 11 (z) 0 T&S\\"(~

0. 0 11
~~(~ 0 15rRvJ(3) 0. 000 11 t3J 0 T65F(l/)~~
~~0. 0~~
~~(~) 0 T5l({W(IJ) 0. 000 11 C4 ) ~.1 2. 998E+03 6. 211E-03 0. OOOE-0~~
~~3. 649E-06 SwY'<eCi);~~
~~.~~ 6.498E+03 2.579E-03 1.233E-03 l.269E-03 ~~ 2.999E+02 1.230E-07 O.OOOE-00 2.314E-05 ~fil.155E+04 9.120E-03 5.550E-03 5.684E-03 K,-6~ 1. 690E+04 4. 068E-03~~
~~439 -0~~
~~1. 402E-02~~
~<<8'11. 993E+04 2. 201E-Ol 0. OOOE-00 0. OOOE-00 ,-t>l-..i 1. 760E+02 4. 038E-05 0. OOOE-00 1. 15E-04 ~-0 1.954E+03 2.198E-04 O.OOOE-00 3.823E-04 ~ 648E+04 9.169E-05 4.317E-O 3.361E-04 c 698E+04 4.530E-02 O.OOOE-00 3.618E-03 f.dµ 9. 781E+03 1. 271E-03 0. OOOE-00 7. 914E-03 1o-1}7 4. 705E+04 1. 800E-Ol 0. OOOE-00 0. OOOE-00 ~.nt4.433E+04 4.881E-02 .811E-03 7.801E~03 -1 2.938E+04 .986E-05 1.073E+06 3.256E+04 ~1i 4.160E+04 .045E-03 6.290E+03 3.367E+02 -~ 4.808E+04 .554E-04 1.813E+05 5.550E+03 ~l 6.218E+04 .318E-02 1.073E+03 1.106E+02 ~v 4.922E+04 1.754E-03 3.145E+04 1.121E+03 24 r,J-t-v~b o.oo -r:/(1)
1. 00 T;i{2) 2.28 5.00

75. 00 TQ£<1)

90. 00 T~(/IJ) 105. 00 120.00 195. 00 n.C*V 210. 00 240.00 480.00 r ('1i) 43200. 00 "
~~J..iJ Jiiiv0t.1ii 2 4 ft/f~IJJ J 1'"' I 2 '{i'IW'J (J)~~
~~3 /Hifl'I ~~~
5 19 90 105 120 135 210 240 480 720 Page 1 19.00 135.00 720.00 30 150 1440 30.00 150.00 1440.00 45 165 1800 F.r.< 3.00E-01 45.00 165.00 1800.00 60 180 5760 60.00 180.00 5760.00 75 195 43200
c c
c.
c c c c c c c 410 700 01 02 c 410 c c c c c c c c c 411 OUTPUT CONTAINMENT AND SIRW TANK ACTIVITY AT SPECIFIED TIMES IF (NPRINT.NE.O.AND.NPRINT.GE.KPRINT) THEN IF ((TPRINT(KPRINT).EQ. (J-1)).0R.(TPRINT(KPRINT).EQ.J).OR. + (TPRINT(KPRINT).EQ.(J+l))) THEN WRITE(6,614) J DO 410 NUCLIDE=l,18 IF (NUCLIDE.GT.13) THEN WRITE(6,620) NUCNAME(NUCLIDE), NCA(NUCLIDE), + NIS(NUCLIDE), ASRW(NUCLIDE) WRITE(6,700) QIA(NUCLIDE), QIESF(NUCLIDE), + QISRW(NUCLIDE), AI2(NUCLIDE) WRITE(6,700) NIA(NUCLIDE,l), NIA(NUCLIDE,2), + NIA(NUCLIDE,3), VSUMP WRITE(6,701) QSTACK(NUCLIDE), Q(NUCLIDE) ELSE WRITE(6,620) NUCNAME(NUCLIDE), NCA(NUCLIDE), + QSTACK(NUCLIDE), Q(NUCLIDE) WRITE(6,700) DDETH(l), DEWB(l), DDETH(2), DEWB(2) END IF CONTINUE WRITE(6,702) WRITE(6,700) CDECA(l), CDEESF(l), CDESRW(l), CDETH(l) WRITE(6,700) CEDECA(l), CEDEESF(l), CEDESRW(l), CEDE(l) WRITE(6,700) CDECA(2), CDEESF(2), CDESRW(2), CDETH(2) WRITE(6,700) CEDECA(2), CEDEESF(2), CEDESRW(2), CEDE(2) WRITE (6,621) IF (TPRINT(KPRINT).EQ.J) THEN KPRINT=KPRINT+l ENDIF r ENDIF ENDIF FORMAT(8X,4(7X,Ell.4)) FORMAT(8X,2(7X,Ell.4)) FORMAT(/) IF (NPRINT.NE.O.AND.NPRINT.GE.KPRINT.AND.TPRINT(KPRINT).EQ.J) WRITE(6,614) J DO 410 NUCLIDE=l,18 IF (NUCLIDE.GT.13) THEN WRITE(6,620) NUCNAME(NUCLIDE), NCA(NUCLIDE), + NIS(NUCLIDE), ASRW(NUCLIDE) ELSE WRITE(6,620) NUCNAME(NUCLIDE), NCA(NUCLIDE) ENDIF CONTINUE KPRINT=KPRINT+l LPAGE=LPAGE+l INSERT PAGE BREAK AFTER ACTIVITY HAS BEEN PRINTED 2 TIMES IF (LPAGE.EQ.2) THEN WRITE (6,621) LPAGE=O ENDIF ENDIF DO 411 NUCLIDE = 14,18 QIA(NUCLIDE)=O.O NCA(NUCLIDE)=O.O CONTINUE MHA06680 THENMHA06690 MHA06700 MHA06710 MHA06720 MHA06730 MHA06740 MHA06750 MHA06760 MHA06770 MHA06780 MHA06790 MHA06800 MHA06810 MHA06820 - MHA06830 MHA06840 MHA06850 MHA06860 MHA06870 MHA06880 MHA06890 MHA06900 MHA06910
CASE 1: BENCHMARK RUN OF MHACALC CODE 1 43200 2530.0 0.10 40304.5 100.0 25.0 50.0 95.5 2.5 2.0 2.0 10.0 1.0 2.0 38767.2 0.35E*03 0.18E-03 0.23E*03 0.15E-03 0.11E-04 0.69E*05 0.26E-05 0.62E*06 1.00 0.000 1 0.420 5 10.000 19 0.000 720 0.420 0 0.000 25.57 0 19 0.2 19 1.000 0 0.0 1440 0.000 0 0.0 0 0.000 0 0.0 0 0.000 0.300E+04 0.621E-02 O.OOOE+OO 0.365E-05 0.650E+04 0.258E-02 0.123E-02 0.127E-02 0.300E+03 0.123E-06 O.OOOE+OO 0.231E-04 0.116E+05 0.912E-02 0.555E-02 0.568E-02 0.169E+05 0.407E-02 0.144E-01 0.140E-01 0.199E+05 0.220E+OO O.OOOE+OO O.OOOE+OO 0.176E+03 0.404E-04 O.OOOE+OO 0.191E-03 0.195E+04 0.220E-03 O.OOOE+OO 0.382E-03 0.565E+05 0.917E-04 0.432E-03 0.336E-03 0.170E+05 0.453E-01 O.OOOE+OO 0.362E-02 0.978E+04 0.127E-02 O.OOOE+OO 0.791E-02 0.471E+05 0.180E+OO O.OOOE+OO O.OOOE+OO 0.443E+05 0.488E-01 0.781E-02 0.780E-02 0.294E+05 0.599E-04 0.107E+07 0.326E+05 0.416E+05 0.505E-02 0.629E+04 0.337E+03 0.481E+05 0.555E-03 0.181E+06 0.555E+04 0.622E+05 0.132E-01 0.107E+04 0.111E+03 0.492E+05 0.175E-02 0.315E+05 0.112E+04 24 0.00 1.00 2.28 5.00 75.00 90.00 105.00 120.00 195.00 210.00 240.00 480.00 43200.00 24 2 3 5 19 90 1~ 1~ 1~ 210 240 . 480 720 CASE 1: BENCHMARK RUN OF MHACALC CODE 19.00 135.00 720.00 30 150 1440 3739.3 0.30E+OO 30.00 45.00 150.00 165.00 1440.00 1800.00 45 60 165 180 1800 5760 INITIAL ACTIVITIES IN CONTAINMENT
FILE: C1MCALC.LST

PAGE: 1 of 28

Length: 195230
Lines Created: 02/26/9.:14 bytes.
~~Queued: 02/26/9~~
~~22 1 to 110 60.00 180.00 5760.00 75 195 43200 TIME =~~
0 MIN ACTIVITY IN CONTAINMENT ISOTOPE ...,.'>kr-83m Kr-85m -7 Kr-85 Kr-87 Kr-88 4 Kr-89 -q Xe-131m Xe-133m Xe-133 Xe-135m --7' Xe-135 Xe-137 Xe-138 -7 1-131 1-132 (fa. 1-133 1-134 ..-;i 1-135 CTMT. ATM. ACTIVITY (Ci) 0.7585E+07 0.1644E+08 0.7587E+06 0.2922E+08 0.4276E+08 0.5042E+08 0.4453E+06 0.4944E+07 0.1429E+09 0.4296E+08 0.247SE+08 0.1190E+09 0.1122E+09 0.1858E+08 0.2631E+08 0.3041E+08 0.3933E+08 0.3113E+08 SUMP ACTIVITY (Ci) 0.3717E+08 0.5262E+08 0.6082E+08 0.7866E+08 0.6226E+08 TIME = 1 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE Kr-83m
,-.-,'"> Kr-85m Kr-85

-c> Kr-87
~~-:;> Kr-88 Kr-89 Xe-131m ......,, Xe-133m Xe-133 Xe-135m Xe-135 CTMT. ATM. SUMP SIRW TANK ACTIVITY ACTIVITY ACTIVITY (Ci) ll~ (Ci) " ~i.~' (Cl) ~~~

~~I;'~~

tlJ; -------- Q 0.7538E+07"~'- 0.5251E+01dl- ~ t> 0.1843E-03 ~Gl\\\\, 0.2192E-03 "(l(v:'~ I 0.1296E=Q4{J6i0i: 0.1541E-04 -06 "' :i. 0.1640E+08 0.1140E+02 0.1140E+02 0.1843E-03 0.2192E-03 0.1296E-04 0.1541E-04
0. 7587E+06 0.5269E+OO 0.5269E+OO 0.1843E*03 0.2192E-03 0.1296E*04 0.1541E-04 0.2896E+08 0.2020E+02 0.2020E+02 0.1843E-03 0.2192E-03 0.1296E-04 0.1541E-04 0.4258E+08 0.2963E+02 0.2963E+02 0.1843E-03 0.2192E-03 0.1296E*04 0.1541E*04 0.4046E+08 0.3143E+02 0.3143E+02 0.1843E-03 0.2192E-03 0.1296E-04 0.1541E*04 0.4453E+06 0.3092E+OO 0.3092E+OO 0.1843E-03 0.2192E-03 0.1296E*04 0.1541E-04 0.4943E+07 0.3433E+01 0.3433E+01 0.1843E-03 0.2192E-03 0.1296E-04 O.i541E-04 0.1429E+09 0.9923E+02 0.9923E+02 0.1843E*03 0.2192E-03 0.1296E*04 0.1541E*04 0.4106E+08 0.2917E+02 0.2917E+02 0.1843~0.2192E*03 0.1296E~-O
~0.1541E-04 ~o~ 0.1717E+02 . :.!~ 0.1843E-03 0.2192E*03 0.1296E-1 0.1541E-04 oV.
Xe-137 . -:;> Xe-138 1-131 1-132 1-133 1-134 1-135 0.9943E+08 0.7565E+02 0.7565E+02 0.1843E-03 0.2192E-03 0.1296E-04 0.1541E-04 0.1068E+09 0.7602E+02 0.7602E+02 0.1843E-03 0.2192E-03 e0.1296E-04 0.1541E-04 0.1858E+08 N-f:.A 0.3716E+08>-'**j O.OOOOE+OO N~vl 0.1290E+02 Gi.:f': O.OOOOE+OO a::c,~ O.OOOOE+OO 10;::6~IJJ O.OOOOE+OO,4T~ 0.1775E+08 Am.l 0.4645E+061~r1>.l 0.3716E+06 """~ >* 0.4030E+05 v:~*,...f 0.1290E+02 1Qs1""< 0.1290E+02 Q 0.2618E+08 0.5236E+08 O.OOOOE+OO 0.1823E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2500E+08 0.6545E+06 0.5236E+06 0.4030E+05 0.1823E+02 0.1823E+02 0.3039E+08 0.6079E+08 O.OOOOE+OO 0.2111E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2903E+08 0.7598E+06 0.6079E+06 0.4030E+05 0-2111E+02 0.2111E+02 0.3881E+08 0.7763E+08 O.OOOOE+OO 0.2713E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3707E+08 0.9703E+06 0.7763E+06 0.4030E+05
0. 2713E+02

0. 2713E+02 0.3108E+08 0.6215E+08 O.OOOOE+OO 0.2160E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2968E+08 0.7769E+06 0.6215E+06 0.4030E+05 0.2160E+02 0.2160E+02 01.....:J"I:
~~0.9949E+OO.:. ;cf' 0.3069E-010* o.* 0.6996E-01."j-?. 0.2159E-02~~
P"
~~{1:~~;>. ~ O.OOOOE+OOt ob~~~~
0. OOOOE+OO C'*
~~O.OOOOE+OO *)- 1, O.OOOOE+OO ',~*~ O.OOOOE+OO c.""r-,it:*'1 O.OOOOE+OO 0 ' 0~~
~~0. OOOOE+OO *)- :.~~
~~O.OOOOE+OO. I~~~
~~0. 9949E+OO G~*-~~~
0.3069E-01 c** 0 ' 0.6996E-01 *)-7.. 0.2159E-02. TIME = 2 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) 0.7491E+07 0.5218E+01 0.5218E+01 0.3638E-03 0.4328E-03 0.2559E-04 0.3043E-04 0.1636E+08 0.1137E+02 0.1137E+02 0.3638E-03 0.4328E-03 0.2559E-04 0.3043E-04 0.7587E+06 0.5269E+OO 0.5269E*OO 0.3638E-03 0.4328E-03 0.2559E-04 0.3043E-04 0.2869E+08 0.2002E+02 0.2002E+02 0-3638E-03 0.4328E-03 0.2559E-04 0.3043E-04 0.4241E+08 0.2951E+02 0.2951E+02 0_3638E-03 0.4328E-03 0.2559E-04 0.3043E-04 0.3247E+08 0.2522E+02 0.2522E+02 0.3638E-03 0.4328E-03 0.2559E-04 0.3043E-04 0.4452E+06 0.3092E+OO 0.3092E+OO 0-3638E-03 0.4328E-03 0.2559E-04 0.3043E-04 0.4941E+07 0.3432E+01 0.3432E+01
~~FILE: C1MCALC.LST Created: 02/26/9-:14 bytes~~~
~~Queued: 02/26/9~~
22
PAGE: 2 of 28

Length: 195230
Lines 111 to 220 0.3638E-03 0.4328E-03 0.2559E-04 0.3043E-04 Xe-133 0.1429E+09 0.9922E+02 0.9922E+02 0.3638E-03 0.4328E-03 0.2559E-04 0.3043E-04 Xe-135m 0.3924E+08 0.2788E+02 0.2788E+02 0.3638E-03 0.4328E-03 0.2559E-04 0.3043E-04 Xe-135 0.2468E+08 0.1715E+02 0.1715E+02 0.3638E-03 0.4328E-03 0.2559E-04 0.3043E-04 Xe-137 0.8305E+08 0.6319E+02 0.6319E+02 0.3638E-03 0.4328E-03 0.2559E-04 0.3043E-04 Xe-138 0.1017E+09 0.7239E+02 0.7239E+02 TIME =
0.3638E-03 0.4328E-03 0.2559E-04 0.3043E-04 1-131 0.1845E+08 0.3716E+08 O.OOOOE+OO .1286E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1762E+ 8 (0.4568E+Q6J (0.3716E+O?i] 0.4030E+05 0.1286E+02 0.1286E+02 1-132 0.2586E+08 0.5210E+08 O.OOOOE+OO 0.1807E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2470E+08 0.6404E+06 0.5210E+06 0.4030E+05 0.1807E+02 0.1807E+02 1-133 0.3016E+08 0.6075E+08 O.OOOOE+OO 0.2103E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2881E+08 0.7469E+06 0.6075E+06 0.4030E+05 0.2103E+02 0.2103E+02 1-134 0.3803E+08 0.7661E+08 O.OOOOE+OO 0.2668E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3633E+08 0.9418E+06 O. 7661E+06 0.4030E+05 0.2668E+02 0.2668E+02 1-135 080E+08 0.6205E+08 O.OOOOE+OO 0.2149E+02 0 OOOE+OO O.OOOOE+OO O.OOOOE+OO O. 2E+OB 0 627E+O (0.6205E+O~ 0.4030E+05. 0.2149E+02 0.2149E+02 0.1986E+01 0.6127E-01 0.1397E+OO 0.4309E-02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1986E+01 0.6127E-01 0.1397E+OO 0.4309E-02 3 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.7445E+07 0.5186E+01 0.5186E+01 0.5387E-03 0.6410E-03 0.3788E-04 0.4508E-04 Kr-85m 0.1631E+08 0.1134E+02 0.1134E+02 0.5387E-03 0.6410E-03 0.3788E-04 0.4508E-04 Kr-85 0.7587E+06 0.5269E+OO 0.5269E+OO 0.5387E-03 0.6410E-03 0.3788E-04 0.4508E-04 Kr-87 0.2843E+08 0.1984E+02 0.1984E+02 0.5387E-03 0.6410E-03 0.3788E-04 0.4508E-04
FILE: C1MCALC.LST

PAGE: 3 of 28

Length: 195230
Lines Created: 02/26/-:14 bytes.
Queued: 02/26/9 6:22 221 to 330 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 1-131 1-132 1-133 1-134 1-135 0.4224E+08 0.2939E+02 0.2939E+02 0.5387E-03 0.6410E-03 0.3788E-04 0.4508E-04 0.2605E+08 0.2024E+02 0.2024E+02 0.5387E-03 0.6410E-03 0.3788E-04 0.4508E-04 0.4452E+06 0.3092E+OO 0.3092E+OO 0.5387E-03 0.6410E-03 0.3788E-04 0.4508E-04 0.4940E+07 0.3431E+01 0.3431E+01 0.5387E-03 0.6410E-03 0.3788E-04 0.4508E-04 0.1429E+09 0.9921E+02 0.9921E+02 0.5387E-03 0.6410E-03 0.3788E-04 0.4508E-04 0.3750E+08 0.2664E+02 0.2664E+02 0.5387E-03 0.6410E-03 0.3788E-04 0.450BE-04 0.2465E+08 0.1713E+02 0.1713E+02 0.5387E-03 0.6410E-03 0.3788E-04 0.4508E-04 0.6937E+08 0.5278E+02 0.5278E+02 0.5387E-03 0.6410E-03 0.3788E-04 0.4508E-04 0.9688E+08 0.6895E+02 0.6895E+02 0.5387E-03 0.6410E-03 0.3788E-04 0.450BE-04 0.1832E+08 0.3716E+08 O.OOOOE+OO 0.1277E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1750E+08 0.4493E+06 0.3716E+06 0.4030E+05 0.1277E+02 0.1277E+02 0.2555E+08 0.5183E+OB O.OOOOE+OO 0.1785E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2441E+OB 0.6267E+06 0.5183E+06 0.4030E+05 0.1785E+02 0.1785E+02 0.2993E+OB 0.6072E+08 O.OOOOE+OO 0.2087E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2859E+08 0.7341E+06 0.6072E+06 0.4030E+05 0.2087E+02 0.2087E+02 0.3727E+OB 0.7561E+08 O.OOOOE+OO 0.2615E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3560E+08 0.9141E+06 0.7561E+06 0.4030E+05 0.2615E+02 0.2615E+02 0.3053E+08 0.6194E+08 O.OOOOE+OO 0.2130E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2916E+08 0.7488E+06 0.6194E+06 0.4030E+05 0.2130E+02 0.2130E+02 0.2970E+01 0.9162E-01 0.2088E+OO 0.6443E-02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2970E+01 0.9162E-01 0.2088E+OO 0.6443E-02 TIME = 4 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK CTMT. ATM. SUMP SIRW TANK ACTIVITY ACTIVITY ACTIVITY ISOTOPE (Ci) (Ci) (Cl) Kr-83m 0.7399E+07 0.5154E+01 0.5154E+01 0.7092E-03 0.8442E-03 0.4987E-04 0.5937E-04 Kr-85m 0.1627E+08 0.1131E+02 0.1131E+02 0.7092E-03 0.8442E-03 0.4987E-04 0.5937E-04 Kr-85 0.7587E+06 0.5269E+OO 0.5269E+OO 0.7092E-03 0.8442E-03 0.4987E-04 0.5937E-04 Kr-87 0.2817E+08 0.1966E+02 0.1966E+02 0.7092E-03 0.8442E-03 0.4987E-04 0.5937E-04 Kr-88 0.4207E+08 0.2927E+02 0.2927E+02 0.7092E-03 0.8442E-03 0.4987E-04 0.5937E-04 Kr-89 0.2091E+08 0.1624E+02 0.1624E+02 0.7092E-03 0.8442E-03 0.4987E-04 0.5937E-04 Xe-131m 0.4452E+06 0.3092E+OO 0.3092E+OO 0.7092E-03 0.8442E-03 0.4987E-04 0.5937E-04 Xe-133m 0.4939E+07 0.3430E+01 . 0.3430E+01 0.7092E-03 0.8442E-03 0.4987E-04 0.5937E-04 Xe-133 0.1428E+09 0.9920E+02 0.9920E+02 0.7092E-03 0.8442E-03 0.4987E-04 0.5937E-04 Xe-135m 0.3584E+08 0.2546E+02 0.2546E+02 0.7092E-03 0.8442E-03 0.4987E-04 0.5937E-04 Xe-135 0.2462E+08 0.1711E+02 0.1711E+02 0.7092E-03 0.8442E-03 0.4987E-04 0.5937E-04 Xe-137 0.5794E+08 0.4409E+02 0.4409E+02 0.7092E-03 0.8442E-03 0.4987E-04 0.5937E-04 Xe-138 0.9226E+08 0.6566E+02 0.6566E+02 0.7092E-03 0.8442E-03 0.4987E-04 0.5937E-04 1-131 0.1819E+08 0.3716E+08 O.OOOOE+OO 0.1268E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1737E+OB 0.441BE+06 0.3716E+06 0.4030E+05 0.1268E+02 0.1268E+02 1-132 0.2524E+OB 0.5157E+08 O.OOOOE+OO 0.1764E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2411E+OB 0.6132E+06 0.5157E+06 0.4030E+05 0.1764E+02 0.1764E+02 1-133 0.2970E+08 0.6069E+08 O.OOOOE+OO 0.2071E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2838E+OB 0.7216E+06 0.6069E+06 0.4030E+05 0.2071E+02 0.2071E+02 1-134 0.3652E+08 0.7462E+08 O.OOOOE+OO 0.2562E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3489E+08 0.8872E+06 0.7462E+06 0.4030E+05 0.2562E+02 0.2562E+02 1-135 0.3026E+08. 0.6183E+08 O.OOOOE+OO 0.2111E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2891E+08 0.7352E+06 0.6183E+06 0.4030E+05 0.2111E+02 0.2111E+02 0.3946E+01 O.OOOOE+OO O.OOOOE+OO 0.3946E+01 0.1217E+OO O.OOOOE+OO O.OOOOE+OO 0.1217E+OO 0.2775E+OO O.OOOOE+OO O.OOOOE+OO 0.2775E+OO 0.8561E-02 O.OOOOE+OO O.OOOOE+OO 0.8561E-02
TIME = 5 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr*83m 0.7353E+07 0.5122E+01 0.5122E+01 0.8755E-03 0.1043E-02 0.6157E-04 0.7332E-04 Kr-85m 0.1623E+08 0.1128E+02 0.1128E+02 0.8755E-03 0.1043E-02 0.6157E-04 0.7332E-04 Kr-85 0.7587E+06 0.5269E+OO 0.5269E+OO 0.8755E-03 0.1043E-02 0.6157E-04 0.7332E-04 Kr-87 0.2792E+08 0.1948E+02 0.1948E+02 0.8755E-03 0.1043E-02 0.6157E-04 0.7332E-04 Kr-88 0.4190E+08 0.2915E+02 0.2915E+02 0.8755E-03 0.1043E-02 0.6157E-04 0.7332E-04 Kr-89 0.1678E+08 0.1303E+02 0.1303E+02 0.8755E-03 0.1043E-02 0.6157E-04 0.7332E-04 Xe-131m 0.4452E+06 0.3092E+OO 0.3092E+OO 0.8755E-03 0.1043E-02 0.6157E-04 0.7332E-04 Xe-133m 0.4938E+07 0.3430E+01 0.3430E+01 0.8755E-03 0.1043E-02 0.6157E-04 0.7332E-04 Xe-133 0.1428E+09 0.9919E+02 0.9919E+02 0.8755E-03 0.1043E-02 0.6157E-04 0.7332E-04 Xe-135m 0.3425E+08 0.2433E+02 0.2433E+02 0.8755E-03 0.1043E-02 0.6157E-04 0.7332E-04 Xe-135 0.2459E+08 0.1709E+02 0.1709E+02 0.8755E-03 0.1043E-02 0.6157E-04 0.7332E-04 Xe-137 0.4840E+08 0.3682E+02 0.3682E+02 0.8755E-03 0.1043E-02 0.6157E-04 0.7332E-04 Xe-138 0.8787E+08 0.6253E+02 0.6253E+02 0.8755E-03 0.1043E-02 0.6157E-04 0.7332E-04 1-131 0.1806E+08 0.3715E+08 O.OOOOE+OO 0.1258E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1725E+08 0.4345E+06 0.3715E+06 0.4030E+05 0.1258E+02 0.1258E+02 1-132 0.2494E+08 0.5131E+08 O.OOOOE+OO 0.1742E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2383E+08 0.6000E+06 0.5131E+06 0.4030E+05 0.1742E+02 0.1742E+02 1-133 0.2948E+08 0.6065E+08 O.OOOOE+OO 0.2055E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2816E+08 0.7093E+06 0.6065E+06 0.4030E+05 0.2055E+02 0.2055E+02 1-134 0.3579E+08 0.7364E+08 O.OOOOE+OO 0.2511E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3419E+08 0.8611E+06 0.7364E+06 0.4030E+05 0.2511E+02 0.2511E+02 1-135 0.3000E+08 0.6172E+08 O.OOOOE+OO 0.2092E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2866E+08 0.7217E+06 0.6172E+06 0.4030E+05 0.2092E+02 0.2092E+02 0.4916E+01 O.OOOOE+OO O.OOOOE+OO 0.4916E+01
FILE: C1MCALC.LST Created: 02/26/.:14

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Length: 195230
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~~Queued: 02/26/~~
~~22 331 to 440 TIME =~~
0.1516E+OO 0.3457E+OO 0.1066E-01 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1516E+OO 0.3457E+OO 0.1066E-01 18 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.6783E+07 0.4725E+01 0.4725E+01 0.2727E-02 0.3262E-02 0.1917E-03 0.2294E-03 Kr-85m 0.1569E+08 0.1091E+02 0.1091E+02 0.2727E-02 0.3262E-02 0.1917E-03 0.2294E-03 Kr-85 0.7587E+06 0.5269E+OO 0.5269E+OO 0.2727E-02 0.3262E-02 0.1917E-03 0.2294E-03 Kr-87 0.2480E+08 0.1730E+02 0.1730E+02 0.2727E-02 0.3262E-02 0.1917E-03 0.2294E-03 Kr-88 0.3974E+08 0.2765E+02 0.2765E+02 0.2727E-02 0.3262E-02 0.1917E-03 0.2294E-03 Kr-89 0.9595E+06 0.7453E+OO 0.7453E+OO 0.2727E-02 0.3262E-02 0.1917E-03 0.2294E-03 Xe-131m 0.4450E+06 0.3090E+OO 0.3090E+OO 0.2727E-02 0.3262E-02 0.1917E-03 0.2294E-03 Xe-133m 0.4924E+07 0.3420E+01 0.3420E+01 0.2727E-02 0.3262E-02 0.1917E-03 0.2294E-03 Xe-133 0.1427E+09 0.9907E+02 0.9907E+02 0.2727E-02 0.3262E-02 0.1917E-03 0.2294E-03 Xe-135m 0.1901E+08 0.1350E+02 0.1350E+02 0.2727E-02 0.3262E-02 0.1917E-03 0.2294E-03 Xe-135 0.2419E+08 0.1681E+02 0.1681E+02 0.2727E-02 0.3262E-02 0.1917E-03 0.2294E-03 Xe-137 0.4662E+07 0.3547E+01 0.3547E+01 0.2727E-02 0.3262E-02 0.1917E-03 0.2294E-03 Xe-138 0.4659E+08 0.3315E+02 0.3315E+02 0.2727E-02 0.3262E-02 0.1917E-03 0.2294E-03 1-131 0.2696E+07 0.3713E+08 O.OOOOE+OO 0.1995E+01 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1975E+07 0.3496E+06 0.3713E+06 0.4030E+05 0.1995E+01 0.1995E+01 1-132 0.3489E+07 0.4806E+08 O.OOOOE+OO 0.2589E+01 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2556E+07 0.4525E+06 0.4806E+06 0.4030E+05 0.2589E+01 0.2589E+01 1-133 0.4372E+07 0.6022E+08 O.OOOOE+OO 0.3236E+01 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3203E+07 0.5670E+06 0.6022E+06 0.4030E+05 0.3236E+01 0.3236E+01 1-134 0.4505E+07 0.6205E+08 O.OOOOE+OO 0.3356E+01 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3300E+07 0.5842E+06 0.6204E+06 0.4030E+05 0.3356E+01 0.3356E+01
1-135 0.4380E+07 0.6033E+08 O.OOOOE+OO 0.3244E+01 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3209E+07 0.5680E+06 0.6033E+06 0.4030E+05 0.3244E+01 0.3244E+01 0.1034E+02 0.3189E+OO 0.7272E+OO 0.2243E-01 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1034E+02 0.3189E+OO 0.7272E+OO 0.2243E-01 TIME = 19 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE 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 1-132 1-133 CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) 0.6741E+07 0.4696E+01 0.4696E+01 0.2850E-02 0.3411E-02 0.2004E-03 0.2398E-03 0.1565E+08 0.1088E+02 0.1088E+02 0.2850E-02 0.3411E-02 0.2004E-03 0.2398E-03 0.7587E+06 0.5269E+OO 0.5269E+OO 0.28SOE-02 0.3411E-02 0.2004E-03 0.2398E-03 0.2457E+08 0.1714E+02 0.1714E+02 0.2850E-02 0.3411E-02 0.2004E-03 0.2398E-03 0.3958E+08 0.2754E+02 0.2754E+02 0.2850E-02 0.3411E-02 0.2004E-03 0.2398E-03 0.7699E+06 0.5981E+OO 0.5981E+OO 0.2850E-02 0.3411E-02 0.2004E-03 0.2398E-03 0.4449E+06 0.3090E+OO 0.3090E+OO 0.2850E-02 0.3411E-02 0.2004E-03 0.2398E-03 0.4923E+07 0.3419E+01 0.3419E+01 0.2850E-02 0.3411E-02 0.2004E-03 0.2398E-03 0.1426E+09 0.9906E+02 0.9906E+02 0.2850E-02 0.3411E-02 0.2004E-03 0.2398E-03 0.1817E+08 0.1291E+02 0.1291E+02 0.2850E-02 0.3411E-02 0.2004E-03 0.2398E-03 0.2416E+08 0.1679E+02 0.1679E+02 0.2850E-02 0.3411E-02 0.2004E-03 0.2398E-03 0.3894E+07 0.2963E+01 0.2963E+01 0.2850E-02 0.3411E-02 0.2004E-03 0.2398E-03 0.4437E+08 0.3157E+02 0.3157E+02 0.2850E-02 0.3411E-02 0.2004E-03 0.2398E-03 0.2386E+07 0.3712E+08 O.OOOOE+OO 0.1762E+01 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1671E+07 0.3438E+06 0.3712E+06 0.4030E+05 0.1762E+01 0.1762E+01 0.3074E+07 0.4781E+08 O.OOOOE+OO 0.2275E+01 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.2153E+07 0.4428E+06 0.4781E+06 0.4030E+05 0.2275E+01 0.2275E+01 0.3869E+07 0.6018E+08 O.OOOOE+OO
~~FILE: C1MCALC.LST Created: 02/26/~~
~~Queued: 02/26/~~
PAGE: 5 of 28

Length: 195230 bytes.
Lines 441 to 550 TIME =
1-134 1-135 0.2857E+01 O.OOOOE+OO O.OOOOE+OO 0.2710E+07 0.5573E+06 0.6018E+06 0.2857E+01 0.2857E+01 0.3936E+07 0.6123E+08 O.OOOOE+OO 0.2925E+01 O.OOOOE+OO O.OOOOE+OO 0.2757E+07 0.5670E+06 0.6123E+06 0.2925E+01 0.2925E+01 0.3871E+07 0.6022E+08 O.OOOOE+OO 0.2860E+01 O.OOOOE+OO O.OOOOE+OO 0.2712E+07 0.5577E+06 0.6022E+06 0.2860E+01 0.2860E+01 0.1048E+02 0.3231E+OO 0.7367E+OO 0.2272E-01 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 29 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.6335E+07 0.4413E+01 0.4413E+01 O.OOOOE+OO 0.4030E+05 O.OOOOE+OO 0.4030E+05 O.OOOOE+OO 0.4030E+05 0.1048E+02 0.3231E+OO 0.7367E+OO 0.2272E-01 0.3973E-02 0.4770E-02 0.2794E-03 0.3355E-03 Kr-85m 0.1525E+08 0.1061E+02 0.1061E+02 0.3973E-02 0.4770E-02 0.2794E-03 0.3355E-03 Kr-85 0.7587E+06 0.5269E+OO 0.5269E+OO 0.3973E-02 0.4770E-02 0.2794E-03 0.3355E-03 Kr-87 0.2243E+08 0.1565E+02 0.1565E+02 0.3973E-02 0.4770E-02 0.2794E-03 0.3355E-03 Kr-88 0.3800E+08 0.2644E+02 0.2644E+02 0.3973E-02 0.4770E-02 0.2794E-03 0.3355E-03 Kr-89 0.8522E+05 0.6620E-01 0.6620E-01 0.3973E-02 0.4770E-02 0.2794E-03 0.3355E-03 Xe-131m 0.4447E+06 0.3089E+OO 0.3089E+OO 0.3973E-02 0.4770E-02 0.2794E-03 0.3355E-03 Xe-133m 0.4912E+07 0.3412E+01 0.3412E+01 0.3973E-02 0.4770E-02 0.2794E-03 0.3355E-03 Xe-133 0.1425E+09 0.9897E+02 0.9897E+02 0.3973E-02 0.4770E-02 0.2794E-03 0.3355E-03 Xe-135m 0.1155E+08 0.8204E+01 0.8204E+01 0.3973E-02 0.4770E-02 0.2794E-03 0.3355E-03 Xe-135 0.2385E+08 O. 1657E+02
0. 1657E+02 0.3973E-02 0.4770E-02 0.2794E-03 0.3355E-03 Xe-137 0.6437E+06 0.4897E+OO 0.4897E+OO 0.3973E-02 0.4770E-02 0.2794E-03 0.3355E-03 Xe-138 0.2723E+08 0.1938E+02 0.1938E+02 0.3973E-02 0.4770E-02 0.2794E-03 0.3355E-03 1-131 0.2332E+071/cA 0.3710E+08NJ:S 0.1231E+04 Ml?."-'

0. 1621E+01 Qr:1, 0.2461E+01 Q16SF-0.2546E-02 ~r :;cu1 0.3692E+03 Ar.:l
~~'TI Q U1 ~ h~ (.fl~~
0.
Q
FILE: C1MCALC.LST

PAGE: 6 of 28

Length: 195230
Lines Created: 02/26/-:14 bytes.
~~Queued: 02/26/~~
22 551 to 660 0.1670E+07 YT'd.

0. 2908E+06 i,:r.1..;i 0.3710E+06 /;L~ ~

0. 4030E+05..\\..-<
0.4083E+011~sT.id1. 0.4085E+01 Q 1-132 0.2858E+07 0.4546E+08 0.1512E+04 0.1992E+01 0.3023E+01 0.3127E-02 0.4535E+03 0.2047E+07 0.3563E+06 0.4546E+06 0.4030E+05 0.5015E+01 0.5018E+01 1-133 0.3762E+07 0.5985E+08 0.1986E+04 0.2616E+01 0.3971E+01 0.4108E-02 0.5957E+03 0.2695E+07 0.4691E+06 0.5985E+06 0.4030E+05 0.6587E+01 0.6591E+01 1-134 0.3374E+07 0.5367E+08 0.1792E+04 0.2361E+01 0.3584E+01 0.3707E-02 0.5376E+03 0.2417E+07 0.4207E+06 0.5367E+06 0.4030E+05 0.5945E+01 0.5949E+01 1-135 0.3720E+07 0.5917E+08 0.1964E+04 0.2588E+01 0.3929E+01 0.4064E-02 0.5893E+03 0.2664E+07 0.4638E+06 0.5917E+06 0.4030E+05 0.6517E+01 0.6521E+01 0.1173E+02 0.1889E+01 0.1074E-02 0.1362E+02 0.3618E+OO 0.5817E-01 0.3308E-04 0.4200E+OO 0.8251E+OO 0.1328E+OO 0.7553E-04 0.9580E+OO 0.2544E-01 0.4091E-02 0.2326E-05 0.2953E-01 UIME = 30 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) 0.6295E+07 0.4385E+01 0.4385E+01 0.4076E-02 0.4896E-02 0.2866E-03 0.3443E-03 0.1522E+08 0.1058E+02 0.1058E+02 0.4076E-02 0.4896E-02 0.2866E-03 , 0.3443E-03 0.7587E+06 0.5269E+OO 0.5269E+OO 0.4076E-02 0.4896E-02 0.2866E-03 0.3443E-03 0.2223E+08 0.1551E+02 0.1551E+02 0.4076E-02 0.4896E-02 0.2866E-03 0.3443E-03 0.3784E+08 0.2633E+02 0.2633E+02 0.4076E-02 0.4896E-02 0.2866E-03 0.3443E-03 0.6839E+05 0.5312E-01 0.5312E-01 0.4076E-02 0.4896E-02 0.2866E-03 0.3443E-03 0.4447E+06 0.3088E+OO 0.3088E+OO 0.4076E-02 0.4896E-02 0.2866E-03 0.3443E-03 0.4911E+07 0.3411E+01 0.3411E+01 0.4076E-02 0.4896E-02 0.2866E-03 0.3443E-03 0.1425E+09 0.9896E+02 0.9896E+02 0.4076E-02 0.4896E-02 0.2866E-03 0.3443E-03 0.1104E+08 0.7841E+01 0.7841E+01 0.4076E-02 0.4896E-02 0.2866E-03 0.3443E-03 0.2382E+08 0.1655E+02 0.1655E+02 TIME = Xe-137 Xe-138 1-131 1-132 1-133 1-134 1-135 0.4076E-02 0.5376E+06 0.4076E-02 0.2593E+08 0 0 6E-O
0.
~~27E+07 0.1618E+01~~
0.1670E+07 0.4079E+01 0.2838E+07 0.1978E+01 0.2037E+07 0.4986E+01 0.3752E+07 0.2609E+01 0.2693E+07 0.6578E+01 0.3323E+07 0.2325E+01 0.2385E+07 0.5862E+01 0.3706E+07 0.2578E+01 0.2660E+07 0.6500E+01 0.1186E+02 0.3656E+OO 0.8338E+OO 0.2571E-01 0.4896E-02 0.4091E+OO 0.4896E-02 0.1846E+02 0
~~0.3710E+08 0.2461E+01~~
~~0. 2860E+06,,_~~
0.4082E+01 0.4523E+08 0.3008E+01 0.3487E+06 0.4989E+01 0.5981E+08 0.3969E+01 0.4611E+06 0.6583E+01 0.5297E+08 0.3537E+01 0.4083E+06 0.5866E+01 0.5907E+08 0.3922E+01 0.4554E+06 0.6505E+01 0.2077E+01 0.6398E-01 0.1461E+OO 0.4499E-02 0.2866E-03 0.4091E+OO 0.2866E-03 0.1846E+02 0.2866E-03 0.1354E+04 0.2800E-02 0.3710E+06 0.1654E+04 0.3423E-02 0.4523E+06 0.2183E+04 0.4516E-02 0.5981E+06 0.1945E+04 0.4025E-02 0.5297E+06 0.2157E+04 0.4463E-02 0.5907E+06 0.1289E-02 0.3969E-04 0.9063E-04 0.2791E-05 44 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.5771E+07 0.4020E+01 0.4020E+01 0.3443E-03 0.3443E-03 0.3443E-03 0.4061E+03 0.4030E+05 0.4963E+03 0.4030E+05 0.6549E+03 0.4030E+05 0.5836E+03 0.4030E+05 0.6471E+03 0.4030E+05 0.1394E+02 0.4296E+OO 0.9800E+OO 0.3021E-01 0.5389E-02 0.6502E-02 0.3790E-03 0.4573E-03 Kr-85m 0.1468E+08 0.1020E+02 0.1020E+02 0.5389E-02 0.6502E-02 0.3790E-03 0.4573E-03 Kr-85 0.7587E+06 0.5269E+OO 0.5269E+OO 0.5389E-02 0.6502E-02 0.3790E-03 0.4573E-03 Kr-87 0.1956E+08 0.1365E+02 0.1365E+02 0.5389E-02 0.6502E-02 0.3790E-03 0.4573E-03 Kr-88 0.3575E+08 0.2488E+02 0.2488E+02 0.5389E-02 0.6502E-02 0.3790E-03 0.4573E-03 Kr-89 0.3139E+04 0.2438E-02 0.2438E-02 0.5389E-02 0.6502E-02 0.3790E-03 0.4573E-03 Xe-131m 0.4445E+06 0.3087E+OO 0.3087E+OO 0.5389E-02 0.6502E-02 0.3790E-03 0.4573E-03
FILE: C1MCALC.LST Created: 02/26/.:14

PAGE: 7 of 28

Length: 195230 bytes.
~~Queued: 02/26/~~
22
Lines 661 to 770 Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 1-131 1-132 1-133 1-134 1-135 0.4896E+07 0.3400E+01 0.3400E+01 0.5389E-02 0.6502E-02 0.3790E-03 0.4573E-03 0.1423E+09 0.9883E+02 0.9883E+02 0.5389E-02 0.6502E-02 0.3790E-03 0.4573E-03 0.5853E+07 0.4158E+01 0.4158E+01 0.5389E-02 0.6502E-02 0.3790E-03 0.4573E-03 0.2340E+08 0.1626E+02 0.1626E+02 0.5389E-02 0.6502E-02 0.3790E-03 0.4573E-03 0.4326E+05 0.3291E-01 0.3291E-01 0.5389E-02 0.6502E-02 0.3790E-03 0.4573E-03 0.1309E+08 0.9319E+01 0.9319E+01 0.5389E-02 0.6502E-02 0.3790E-03 0.4573E-03 0.2266E+07 0.3706E+08 0.3074E+04 0.1575E+01 0.2459E+01 0.6359E-02 0.9220E+03 0.1669E+07 0.2263E+06 0.3707E+06 0.4030E+05 0.4034E+01 0.4040E+01 0.2576E+07 0.4214E+08 0.3504E+04 0.1795E+01 0.2803E+01 0.7248E-02 0.1051E+04 0.1898E+07 0.2573E+06 0.4215E+06 0.4030E+05 0.4598E+01 0.4605E+01 0.3628E+07 0.5935E+08 0.4923E+04 0.2522E+01 0.3938E+01 0.1018E-01 0.1477E+04 0.2672E+07 0.3623E+06 0.5935E+06 0.4030E+05 0.6461E+01 0.6471E+01 0.2692E+07 0.4404E+08 0.3676E+04 0.1884E+01 0.2941E+01 0.7605E-02 0.1103E+04 0.1983E+07 0.2689E+06 0.4404E+06 0.4030E+05 0.4825E+01 0.4832E+01 0.3523E+07 0.5763E+08 0.47S3E+04 0.2451E+01 0.3827E+01 0.9896E-02 0.1435E+04 0.2595E+07 0.3519E+06 0.5764E+06 0.4030E+05 0.6278E+01 0.6288E+01 0.1356E+02 0.4182E+OO 0.9539E+OO 0.2941E-01 0.4712E+01 0.1451E+OO 0.3314E+OO 0.1020E-01 0.6330E-02 0.1948E-03 0.4452E-03 0.1370E-04 0.1828E+02 0.5634E+OO 0.1286E+01 0.3962E-01 HME =
45 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY CCI) Kr-83m 0.5735E+07 0.3995E+01 0.3995E+01 0.5476E-02 0.6608E-02 0.3851E-03 0.4647E-03 Kr-85m 0.1464E+08 0.1018E+02 0.1018E+02 0.5476E-02 0.6608E-02 0.3851E-03 0.4647E-03 Kr-85 0.7587E+06 0.5269E+OO 0.5269E+OO 0.5476E-02 0.6608E-02 0.3851E-03 0.4647E-03 Kr-87 0.1938E+08 0.1352E+02 0.1352E+02 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 1-131 1-132 1-133 1-134 1-135 0.5476E-02 0.3560E+08 0.5476E-02 0.2519E+04 0.5476E-02 0.4445E+06 0.5476E-02 0.4895E+07 0.5476E-02 0.1423E+09 0.5476E-02 0.5594E+07 0.5476E-02 0.2337E+08 0.5476E-02 0.3613E+OS 0.5476E-02 0.1247E+08 0.5476E-02 0.2262E+07 0.1572E+01 0.1669E+07 0.4031E+01 0.2559E+07 0.1783E+01 0.1888E+07 0.4572E+01 0.3620E+07 0.2517E+01 0.2671E+07 0.6453E+01 0.2653E+07 0.1856E+01 0.1957E+07 0.4758E+01 0.3511E+07 0.2443E+01 0.2591E+07 0.6263E+01 0.1368E+02 0.4219E+OO 0.9623E+OO 0.2967E-01 0.6608E-02 0.2477E+02 0.6608E-02 0.1956E-02 0.6608E-02 0.3087E+OO 0.6608E-02 0.3400E+01 0.6608E-02 0.9883E+02 0.660BE-02 0.3974E+01 0.6608E-02 0.1624E+02 0.6608E-02 0.2749E-01 0.6608E-02 0.8875E+01 0.6608E-02 0.3706E+08 0.2459E+01 0.2225E+06 0.4038E+01 0.4193E+08 0.2789E+01 0.2518E+06 0.4580E+01 0.5931E+08 0.3936E+01 0.3561E+06 0.6463E+01 0.4346E+08 0.2902E+01 0.2610E+06 0.4766E+01 0.5753E+08 0.3820E+01 0.3454E+06 0.6273E+01 0.4900E+01 0.1509E+OO 0.3446E+OO 0.1061E-01 0.3851E-03 0.2477E+02 0.3851E-03 0.1956E-02 0.3851E-03 0.3087E+OO 0.3851E-03 0.3400E+01 0.3851E-03 0.9883E+02 0.3851E-03 0.3974E+01 0.3851E-03 0.1624E+02 0.3851E-03 0.2749E-01 0.3851E-03 0.8875E+01 0.3851E-03 0.3196E+04 0.6613E-02 0.3706E+06 0.3625E+04 0.7500E-02 0.4193E+06 0.5117E+04 0.1059E-01 0.5932E+06 0.3mE+04 0.7806E-02 0.4347E+06 0.4966E+04 0.1027E-01 0.5754E+06 0.6835E-02 0.2104E-03 0.4807E-03 0.1479E-04 TIME = 59 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY CCI) 0.4647E-03 0.4647E-03 0.4647E-03 0.4647E-03 0.4647E-03 0.4647E-03 0.4647E-03 0.4647E-03 0.4647E-03 0.4647E-03 0.9589E+03 0.4030E+05 0.1088E+04 0.4030E+05 0.1535E+04 0.4030E+05 0.1132E+04 0.4030E+05 0.1490E+04 0.4030E+05 0.1859E+02 0.5729E+OO 0.1307E+01 0.4029E-01 11 Q U1 1'1 ~ Qi Q r~
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 1-132 1-133 1-134 1-135
FILE: C1HCALC.LST

PAGE: 8 of 28.
~~Length: 195230 bytes.~~
~~Lines 771 to 880 Created: 02/26/.:14 Queued:~~
02/26/9 ~:22 0.5258E+07 0.3662E+01 0.3662E+01 0.6604E-02 0.8003E-02 0.4644E-03 0.5628E-03 0.1412E+08 0.9817E+01 0.9817E+01 0.6604E-02 0.8003E-02 0.4644E-03 0.5628E-03 0.7587E+06 0.5269E+OO 0.5269E+OO 0.6604E-02 0.8003E-02 0.4644E-03 0.5628E-03 0.1706E+08 0.1190E+02 0.1190E+02 0.6604E-02 0.8003E-02 0.4644E-03 0.5628E-03 0.3363E+08 0.2340E+02 0.2340E+02 0.6604E-02 0.8003E-02 0.4644E-03 0.5628E-03 0.1156E+03 0.8979E-04 0.8979E-04 0.6604E-02 0.8003E-02 0.4644E-03 0.5628E-03 0.4442E+06 0.3085E+OO 0.3085E+OO 0.6604E-02 0.8003E-02 0.4644E-03 0.5628E-03 0.4880E+07 0.3389E+01 0.3389E+01 0.6604E-02 0.8003E-02 0.4644E-03 0.5628E-03 0.1421E+09 0.9870E+02 0.9870E+02 0.6604E-02 0.8003E-02 0.4644E-03 0.5628E-03 0.2967E+07 0.2108E+01 0.2108E+01 0.6604E-02 0.8003E-02 0.4644E-03 0.5628E-03 0.2296E+08 0.1595E+02 0.1595E+02 0.6604E-02 0.8003E-02 0.4644E-03 0.5628E-03 0.2907E+04 0.2212E-02 0.2212E-02 0.6604E-02 0.8003E-02 0.4644E-03 0.5628E-03 0.6297E+07 0.4481E+01 0.4481E+01 0.6604E-02 0.8003E-02 0.4644E-03 0.5628E-03 0.2214E+07 0.3703E+08 0.4913E+04 0.1538E+01 0.2457E+01 0.1016E-01 0.1474E+04 0.1667E+07 0.1761E+06 0.3703E+06 0.4030E+05 0.3995E+01 0.4005E+01 0.2336E+07 0.3907E+08 0.5197E+04 0.1627E+01 0.2599E+01 0.1075E-01 0.1559E+04 0.1759E+07 0.1858E+06 0.3907E+06 0.4030E+05 0.4226E+01 0.4237E+01 0.3519E+07 0.5885E+08 0.7811E+04 0.2446E+01 0.3906E+01 0.1616E-01 0.2343E+04 0.2650E+07 0.2798E+06 0.5886E+06 0.4030E+05 0.6351E+01 0.6367E+01 0.2161E+07 0.3614E+08 0.4827E+04 0.1511E+01 0.2413E+01 0.9985E-02 0.1448E+04 0.1627E+07 0.1718E+06 0.3614E+06 0.4030E+05 0.3925E+01 0.3935E+01 0.3356E+07 0.5613E+08 0.7455E+04 0.2334E+01 0.3727E+01 0.1542E-01 0.2236E+04 0.2528E+07 0.2669E+06 0.5614E+06 0.4030E+05 0.6062E+01 0.6077E+01 0.1534E+02 0.4729E+OO 0.1079E+01 0.3325E-01 0.7525E+01 0.2316E+OO 0.5292E+OO 0.1628E-01 0.1593E-01 0.4900E-03 0.1120E-02 0.3446E-04 0.2288E+02 0.7049E+OO 0.1609E+01 0.4957E-01 TIME = 60 HIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTHT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.5225E+07 0.3640E+01 0.3640E+01 0.6680E-02 0.8097E-02 0.4697E-03 0.5694E-03 Kr-85m 0.1408E+08 0.9792E+01 0.9792E+01 0.6680E-02 0.8097E-02 0.4697E-03 0.5694E-03 Kr-85 0.7587E+06 0.5269E+OO 0.5269E+OO 0.6680E-02 0.8097E-02 0.4697E-03 0.5694E-03 Kr-87 0.1691E+08 0.1179E+02 . 0.1179E+02 0.6680E-02 0.8097E-02 0.4697E-03 0.5694E-03 Kr-88 0.3350E+08 0.2331E+02 0.2331E+02 0.6680E-02 0.8097E-02 0.4697E-03 0.5694E-03 Kr-89 0.9275E+02 0.7205E-04 0.7205E-04 0.6680E-02 0.8097E-02 0.4697E-03 0.5694E-03 Xe-131m 0.4442E+06 0.3085E+OO 0.3085E+OO 0.6680E-02 0.8097E-02 0.4697E-03 0.5694E-03 ' Xe-133m 0.4879E+07 0.3388E+01 0.3388E+01 0.6680E-02 0.8097E-02 0.4697E-03 0.5694E-03 Xe-133 0.1421E+09 0.9869E+02 0.9869E+02 0.6680E-02 0.8097E-02 0.4697E-03 0.5694E-03 Xe-135m 0.2835E+07 0.2014E+01 0.2014E+01 0.6680E-02 0.8097E-02 0.4697E-03 0.5694E-03 xe-135 0.2293E+08 0.1593E+02 0.1593E+02 0.6680E-02 0.8097E-02 0.4697E-03 0.5694E-03 Xe-137 0.2428E+04 0.1848E-02 0.1848E-02 0.6680E-02 0.8097E-02 0.4697E-03 0.5694E-03 Xe-138 0.5997E+07 0.4268E+01 0.4268E+01 0.6680E-02 0.8097E-02 0.4697E-03 0.5694E-03 1-131 0.2211E+07 0.3703E+08 0.5036E+04 0.1536E+01 0.2457E+01 0.1042E-01 0.1511E+04 0.1667E+07 0.1731E+06 0.3703E+06 0.4030E+05 0.3993E+01 0.4003E+01 1-132 . 0.2321E+07 0.3887E+08 0.5300E+04 0.1617E+01 0.2586E+01 0.1097E-01 0.1590E+04 0.1751E+07 0.1818E+06 0.3888E+06 0.4030E+05 0.4203E+01 0.4214E+01 1-133 0.3512E+07 0.5882E+08 0.8002E+04 0.2441E+01 0.3903E+01 0.1655E-01 0.2400E+04 0.2649E+07 0.2751E+06 0.5883E+06 0.4030E+05 0.6345E+01 0.6361E+01 1-134 0.2129E+07 0.3566E+08 0.4883E+04 0.1490E+01 0.2382E+01 0.1010E-01 0.1465E+04 0.1606E+07 0.1668E+06 0.3567E+06 0.4030E+05 0.3871E+01 0.3881E+01 1-135 0.3346E+07 0.5603E+08 0.7628E+04 0.2327E+01 0.3721E+01 0.1578E-01 0.2288E+04 0.2523E+07 0.2620E+06 0.5604E+06 0.4030E+05 0.6048E+01 0.6064E+01
TIME = 0.1546E+02 0.4765E+OO 0.1087E+01 0.3351E-01 0.7712E+01 0.2373E+OO 0.5423E+OO 0.1669E-01 0.1672E-01 0.5144E-03 0.1176E-02 0.3618E-04 0.2319E+02 0.7143E+OO 0.1631E+01 0.5023E-01 74 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE 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 1-132 1-133 1-134 CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) 0.4790E+07 0.3337E+01 0.3337E+01 0.7688E-02 0.9356E-02 0.5406E-03 0.6579E-03 0.1358E+08 0.9445E+01 0.9445E+01 0.7688E-02 0.9356E-02 0.5406E-03 0.6579E-03 0.7587E+06 0.5269E+OO 0.5269E+OO 0.7688E-02 0.9356E-02 0.5406E-03 0.6579E-03 0.1488E+08 0.1038E+02 0.1038E+02 0.7688E-02 0.9356E-02 0.5406E-03 0.6579E-03 0.3164E+08 0.2202E+02 0.2202E+02 0.7688E-02 0.9356E-02 0.5406E-03 0.6579E-03 0.4257E+01 0.3307E-05 0.3307E-05 0.7688E-02 0.9356E-02 0.5406E-03 0.6579E-03 0.4439E+06 0.3083E+OO 0.3083E+OO 0.7688E-02 0.9356E-02 0.5406E-03 0.6579E-03 0.4864E+07 0.3378E+01 0.3378E+01 0.7688E-02 0.9356E-02 0.5406E-03 0.6579E-03 0.1419E+09 0.9856E+02 0.9856E+02 0.7688E-02 0.9356E-02 0.5406E-03 0.6579E-03 0.1504E+07 0.1068E+01 0.1068E+01 0.7688E-02 0.9356E-02 0.5406E-03 0.6579E-03 0.2252E+08 0.1565E+02 0.1565E+02 0.7688E-02 0.9356E-02 0.5406E-03 0.6579E-03 0.1954E+03 0.1487E-03 0.1487E-03 0.7688E-02 0.9356E-02 0.5406E-03 0.6579E-03 0.3028E+07 0.2155E+01 0.2155E+01 0.7688E-02 0.9356E-02 0.5406E-03 0.6579E-03 0.2173E+07 0.3699E+08 0.6750E+04 0.1510E+01 0.2455E+01 0.1396E-01 0.2025E+04 0.1666E+07 0.1370E+06 0.3700E+06 0.4029E+05 0.3964E+01 0.3978E+01 0.2128E+07 0.3622E+08 0.6625E+04 0.1482E+01 0.2409E+01 0.1371E-01 0.1987E+04 0.1631E+07 0.1341E+06 0.3623E+06 0.4029E+05 0.3891E+01 0.3905E+01 0.3428E+07 0.5836E+08 0.1065E+05 0.2382E+01 0.3873E+01 0.2203E-01 0.3195E+04 0.2628E+07 0.2161E+06 0.5837E+06 0.4029E+05 0.6256E+01 0.6278E+01 0.1742E+07 0.2965E+08 0.5446E+04 0.1218E+01 0.1980E+01 0.1127E-01 0.1634E+04 0.1335E+07 0.1098E+06 0.2966E+06 0.4029E+05
~~FILE: C1MCALC.LST Created: 02/26/~~
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PAGE: 9 of 28

Length: 195230 bytes.
~~Queued: 02/26/~~
22
~~Lines 881 to 990 TIME =~~
1-135 0.3199E+01 0.3210E+01 0.3211E+07 0.5467E+08 0.9984E+04 0.2233E+01 0.3631E+01 0.2065E-01 0.2995E+04 0.2462E+07 0.2025E+06 0.5468E+06 0.4029E+05 0.5864E+01 0.5885E+01 0.1708E+02 0.5263E+OO 0.1201E+01 0.3701E-01 0.1033E+02 0.3177E+OO 0.7263E+OO 0.2234E-01 0.2984E-01 0.9175E-03 0.2099E-02 0.6452E-04 0.2744E+02 0.8449E+OO 0.1930E+01 0.5941E-01 75 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.4760E+07 0.3316E+01 0.3316E+01 0.7756E-02 0.9442E-02 0.5454E-03 . 0.6640E-03 Kr-85m 0.1355E+08 0.9420E+01 0.9420E+01 0.7756E-02 0.9442E-02 0.5454E-03 0.6640E-03 Kr-85 0.7587E+06 0.5269E+OO 0.5269E+OO 0.7756E-02 0.9442E-02 0.5454E-03 0.6640E-03 Kr-87 0.1474E+08 0.1029E+02 0.1029E+02 0.7756E-02 0.9442E-02 0.5454E-03 0.6640E-03 Kr-88 0.3151E+08 0.2193E+02 0.2193E+02 0.7756E-02 0.9442E-02 0.5454E-03 0.6640E-03 Kr-89 0.3416E+01 0.2653E-05 0.2653E-05 0.7756E-02 0.9442E-02 0.5454E-03 0.6640E-03 Xe-131m 0.4439E+06 0.3083E+OO 0.3083E+OO 0.7756E-02 0.9442E-02 0.5454E-03 0.6640E-03 Xe-133m 0.4863E+07 0.3377E+01 0.3377E+01 0.7756E-02 0.9442E-02 0.5454E-03 0.6640E-03 Xe-133 0.1419E+09 0.9855E+02 0.9855E+02 0.7756E-02 0.9442E-02 0.5454E-03 0.6640E-03 Xe-135m 0.1437E+07 0.1021E+01 0.1021E+01 0.7756E-02 0.9442E-02 0.5454E-03 0.6640E-03 Xe-135 0.2249E+08 0.1563E+02 0.1563E+02 0.7756E-02 0.9442E-02 0.5454E-03 0.6640E-03 Xe-137 0.1632E+03 0.1242E-03 0.1242E-03 0.7756E-02 0.9442E-02 0.5454E-03 0.6640E-03 Xe-138 0.2884E+07 0.2052E+01 0.2052E+01 0.7756E-02 0.9442E-02 0.5454E-03 0.6640E-03 1-131 0.2171E+07 0.3699E+08 0.6872E+04 0.1508E+01 0.2454E+01 0.1422E-01 0.2061E+04 0.1666E+07 0.1347E+06 0.3700E+06 0.4029E+05 0.3963E+01 0.3977E+01 1-132 0.2115E+07 0.3604E+08 0.6712E+04 0.1473E+01 0.2397E+01 0.1388E-01 0.2013E+04 0.1623E+07 0.1313E+06 0.3604E+06 0.4029E+05 0.3870E+01 0.3884E+01
FILE: C1MCALC.LST

PAGE: 10 of 28

Length: 195230
Lines Created: 02/26/
bytes. Queued: 02/26/ 991 to 1100 ****************
14

22 1-133 0.3422E+07 0.5832E+08 0.1084E+05 0.2379E+01 0.3871E+01 0.2242E-01 0.3251E+04 0.2627E+07 0.2124E+06 0.5834E+06 0.4029E+05 0.6250E+01 0.6272E+01 1-134 0.1717E+07 0.2926E+08 0.54nE+04 0.1201E+01 0.1955E+01 0.1132E-01 0.1642E+04 0.1318E+07 0.1066E+06 0.2927E+06 0.4029E+05 0.3156E+01 0.3167E+01 1-135 0.3202E+07 0.5457E+08 0.1015E+05 0.2227E+01 0.3624E+01 0.2099E-01 0.3044E+04 0.2458E+07 0.1988E+06 0.5459E+06 0.4029E+05 0.5851E+01 0.5872E+01 0.1720E+02 0.1051E+02 0.3092E-01 0.2n4E+02 0.5298E+OO 0.3234E+OO 0.9507E-03 0.8542E+OO 0.1209E+01 0.7394E+OO 0.2174E-02 0.1951E+01 0.3726E-01 0.2274E-01 0.6685E-04 0.6007E-01 TIME =
89 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE 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 CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) 0.4364E+07 0.3040E+01 0.3040E+01 0.8678E-02 0.1060E-01 0.6102E-03 0.7457E-03 0.1307E+08 0.9086E+01 0.9086E+01 0.8678E-02 0.1060E-01 0.6102E-03 0.7457E-03 0.7587E+06 0.5269E+OO 0.5269E+OO 0.8678E-02 0.1060E-01 0.6102E-03 0.7457E-03
0. 1298E+08

0. 9053E+01

0. 9053E+01 0.8678E-02 0.1060E-01 0.6102E-03 0.7457E-03 0.2977E+08 0.2071E+02 0.2071E+02 0.8678E-02 0.1060E-01 0.6102E-03 0.7457E-03 0.1568E+OO 0.1218E-06 0.1218E-06 0.8678E-02 0.1060E-01 0.6102E-03

0. 7457E-03 0.4437E+06 0.3081E+OO 0.3081E+OO 0.8678E-02 0.1060E-01 0.6102E-03 0.7457E-03 0.4848E+07 0.3367E+01 0.3367E+01 0.8678E-02 0.1060E-01 0.6102E-03 0.7457E-03 0.1417E+09 0.9842E+02 0.9842E+02 0.8678E-02 0.1060E-01 0.6102E-03 0.7457E-03 0.7622E+06 0.5415E+OO 0.5415E+OO 0.8678E-02 0.1060E-01 0.6102E-03 0.7457E-03 0.2210E+08 0.1536E+02 0.1536E+02 0.8678E-02 0.1060E-01 0.6102E-03 0.7457E-03 0.1313E+02 0.9990E-05 0.9990E-05 0.8678E-02 0.1060E-01 0.6102E-03 0.7457E-03 0.1456E+07 0.1036E+01 0.1036E+01 0.8678E-02 0.1060E-01 0.6102E-03 0.7457E-03 0.2141E+07 0.3696E+08.
0.8583E+04 TIME = 1-132 1-133 1-134 1-135 0.1487E+01 0.2452E+01 0.1664E+07 0.1066E+06 0.3940E+01 0.3957E+01 0.1775E-01 0.3697E+06 0.1945E+07 0.3358E+08 0.7817E+04 0.2574E+04 0.4029E+05 0.1355E+01 0.2234E+01 0.1617E-01 0.2345E+04 0.1512E+07 0.9685E+05 0.3359E+06 0.4029E+05 0.3588E+01 0.3604E+01 0.3352E+07 0.5787E+08 0.1344E+05 0.2329E+01 0.3841E+01 0.2781E-01 0.4032E+04 0.2606E+07 0.1669E+06 0.5788E+06 0.4029E+05 0.6170E+01 0.6198E+01 0.1409E+07 0.2433E+08 0.5688E+04 0.9856E+OO 0.1625E+01 0.1177E-01 0.1706E+04 0.1096E+07
0. 7018E+05 0.2434E+06 0.4029E+05 0.2611E+01 0.2623E+01 0.3084E+07 0.5325E+08 0.1238E+05 0.2145E+01 0.3536E+01 0.2560E-01 0.3712E+04 0."2398E+07 0.1536E+06 0.5326E+06 0.4029E+05 0.5681E+01 0.5707E+01 0.1879E+02 0.5786E+OO 0.1321E+01 0.4069E-01 0.1312E+02 0.4034E+OO 0.9226E+OO 0.2837E-01 0.4803E-01 0.1476E-02 0.3378E-02 0.1038E-03 0.3195E+02 0.9835E+OD 0.2247E+01 0.6916E-01 90 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM.
ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRll TANK ACTIVITY (Cl) Kr-83m 0.4337E+07 0.3021E+01 0.3021E+01 0.8741E-02 0.1068E-01 0.6147E-03 0.7514E-03 Kr-85m 0.1303E+08 0.9063E+01 0.9063E+01 0.8741E-02 0.1068E-01 0.6147E-03 0.7514E-03 Kr-85 0.7587E+06 0.5269E+OO 0.5269E+OO 0.8741E-02 0.1068E-01 0.6147E-03 0.7514E-03 Kr-87 0.1286E+08 0.8971E+01 0.8971E+01 0.8741E-02 0.1068E-01 0.6147E-03 0.7514E-03 Kr-88 0.2965E+08 0.2063E+02 0.2063E+02 0.8741E-02 0.1068E-01 0.6147E-03 0.7514E-03 Kr-89 0.1258E+OO 0.97nE-07 0.97nE-07 0.8741E-02 0.1068E-01 0.6147E-03 0.7514E-03 Xe-131m 0.4436E+06 0.3081E+OO 0.3081E+OO 0.8741E-02 0.1068E-01 0.6147E-03 0.7514E-03 Xe-133m 0.4846E+07 0.3366E+01 0.3366E+01 0.8741E-02 0.1068E-01 0.6147E-03 0.7514E-03 Xe-133 0.1417E+09 0.9842E+02 0.9842E+02 0.8741E-02 0.1068E-01 0.6147E-03
~~0. 7514E-03 Xe-135m 0.7285E+06 0.5175E+OO 0.5175E+OO 0.8741E-02 0.1068E-01 0.6147E-03 0.7514E-03~~
Xe-135 Xe-137 Xe-138 1-131 1-132 1-133 1-134 1-135 0.2207E+OB 0.1534E+02 0.1534E+02 0.8741E-02 0.1068E-01 0.6147E-03 0.7514E-03 0.1097E+02 0.8344E-05 0.8344E-05 0.8741E-02 0.1068E-01 0.6147E-03 0.7514E-03 0.1387E+07 0.9B69E+OO 0.9B69E+OO 0.8741E-02 0.1068E-01 0.6147E-03 0.7514E-03 0.2139E+07 0.3695E+OB O.B705E+04 0.14B6E+01 0.2452E+01 0.1B01E-01 0.2611E+04 0.1664E+07 0.1048E+06 0.3696E+06 0.4029E+05 0.3938E+01 0.39;6E+01 0.1934E+07 0.3341E+08 0.7889E+04 0.1347E+01 0.2222E+01 0.1632E-01 0.2366E+04 0.1505E+07 0.9477E+05 0.3342E+06 0.4029E+05 0.3569E+01 0.3585E+01 0.3347E+07 0.5784E+08 0.1363E+05 0.2326E+01 0.3839E+01 0.2B19E-01 0.4087E+04 0.2605E+07 0.1641E+06 0.5785E+06 0.4029E+05 0.6165E+01 0.6193E+01 0.1390E+07 0.2401E+08 0.5694E+04 0.9719E+OO 0.1604E+01 0.1178E-01 0.1708E+04 0.1081E+07 0.6812E+05 0.2402E+06 0.4029E+05 0.2576E+01 0.2588E+01 0.3076E+07 0.5315E+08 0.1253E+05 0.2139E+01 0.3530E+01 0.2592E-01 0.3759E+04 0.2394E+07 0.1508E+06 0.5317E+06 0.4029E+05 0.5669E+01 0.5695E+01 0.1890E+02 0.5821E+OO 0.1329E+01 0.4093E-01 0.1331E+02 0.4091E+OO 0.9357E+OO 0.2877E-01 0.4940E-01 0.1518E-02 0.3474E-02 0.1068E-03 0.3225E+02 0.9927E+OO 0.2268E+01 0.6981E-01 TIME = 104 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE Kr-B3m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) 0.3975E+07 0.2769E+01 0.2769E+01 0.9595E-02 0.1177E-01 0.6747E-03 0.8278E-03 0.1257E+08 0.8741E+01 0.8741E+01 0.9595E-02 0.1177E-01 0.6747E-03 0.8278E-03 0.7587E+06 0.5269E+DD 0.5269E+OO 0.9595E-02 0.1177E-01 0.6747E-03 0.8278E-03 0.1132E+08 0.7895E+01 0.7895E+01 0.9595E-02 0.1177E-01 0.6747E-03 0.8278E-03 0.2801E+08 0.1949E+02 0.1949E+02 0.9595E-02 0.1177E-01 0.6747E-03 0.8278E-03 0.5773E-02 0.4485E-08 0.4485E-08 0.9595E-02 0.1177E-01 0.6747E-03 0.8278E-03 0.4434E+06 0.3079E+OO 0.3079E+OO
~~FILE: C1MCALC.LST Created: 02/26/~~
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Length: 195230 bytes.
~~Queued: 02/26/~~
22
Lines 1101 to 1210 ****************
~~0.9595E-02 0.1177E-01 0.6747E-03 0.8278E-03 Xe-133m 0.4832E+07 0.3356E+01 0.3356E+01 0.9595E-02~~
0. 1177E-01 0.6747E-03 0.8278E-03 Xe-133 0.1415E+09 0.9829E+02 0.9829E+02 0.9595E-02 0.1177E-01 0.6747E-03 0.8278E-03 Xe-135m 0.3B63E+06 0.2745E+OO 0.2745E+OO 0.9595E-02 0.1177E-01 0.6747E-03 0.8278E-03 Xe-135 0.2168E+08 0.1507E+02 0.1507E+02 0.9595E-02 0.1177E-01 0.6747E-03 0.8278E-03 Xe-137 0.8824E+OO 0.6714E-06 0.6714E-06 0.9595E-02 0.1177E-01 0.6747E-03 0.8278E-03 Xe-138 0.7002E+06 0.4983E+OO 0.4983E+OO TIME =
0.9595E-02 0.1177E-01 0.6747E-03 0.8278E-03 1-131 0.2115E+07 0.3692E+08 0.1041E+05 0.1469E+01 0.2450E+01 0.2154E-01 0.3123E+04 0.1663E+07 0.8294E+05 0.3693E+06 0.4029E+05 0.3920E+01 0.3941E+01 1-132 0.1783E+07 0.3113E+08 0.8801E+04
0. 1242E+01 0.2071E+01 0.1820E-01 0.2640E+04 0.1402E+07 0.6993E+05 0.3114E+06 0.4029E+05 0.3313E+01 0.3331E+01 1-133 0.3288E+07 0.5738E+08 0.1619E+05 0.2284E+01 0.3809E+01 0.3348E-01 0.4855E+04 0.2585E+07 0.1289E+06 0.5740E+06 0.4029E+05 0.6094E+01 0.6127E+01 1-134 0.1144E+07 0.1997E+08 0.5668E+04 O. 7998E+OO 0.1334E+01 0.1172E-01 0.1700E+04 0.8992E+06 0.4485E+05 0.1997E+06 0.4029E+05 0.2134E+01 0.2145E+01 1-135 0.2971E+07 0.51B6E+08 0.1464E+05 0.2066E+01 0.3445E+01 0.3028E-01 0.4391E+04 0.2336E+07

0. 1165E+06 0.5188E+06 0.4029E+05 0.5510E+01 0.5541E+01 0.2046E+02 0.6301E+OO 0.1439E+01 0.4431E-01 0.1590E+02 0.4888E+OO 0.1118E+01 0.3437E-01 0.7047E-01 0.2165E-02 0.4956E-02 0.1522E-03 0.3643E+02 0.1121E+01 0.2562E+01 0.7883E-01 105 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM.
ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.3951E+07 0.275ZE+01 0.2752E+01 0.9654E-OZ 0.1185E-01 0.6789E-03 0.8331E-03 Kr-85m 0.1254E+08 0.8719E+01 0.8719E+01 0.9654E-OZ 0.1185E-01 0.6789E-03 0.8331E-03 Kr-85 0.7587E+06 0.5269E+OO 0.5269E+OO 0.9654E-02 0.1185E-01 0.6789E-03 0.8331E-03
Kr-87 0.1121E+08 0.7824E+01 0.7824E+01 0.9654E*02 0.1185E-01 0.6789E-03 Kr-88 0.2789E+08 0.1941E+02 0.1941E+02 0.9654E-02 0.1185E-01 0.6789E-03 Kr-89 0.4633E-02 0.3599E-08 0.3599E-08 0.9654E-02 0.1185E-01 0.6789E-03 Xe-131m 0.4434E+06 0.3079E+OO 0.3079E+OO 0.9654E-02 0.1185E*01 0.6789E-03 Xe-133m 0.4830E+07 0.3355E+01 0.3355E+01 0.9654E-02 0.1185E-01 0.6789E-03 Xe-133 0.1415E+09 0.9828E+02 0.9828E+02 0.9654E-02 0.1185E-01 0.6789E-03 Xe-135m 0.3692E+06 0.2623E+OO 0.2623E+OO 0.9654E-02 0.1185E-01 0.6789E-03 Xe-135 0.2165E+08 0.1505E+02 0.1505E+02 0.9654E-02 0.1185E-01 0.6789E-03 Xe-137 0.7370E+OO 0.5608E*06 0.5608E-06 0.9654E-02 0.1185E-01 0.6789E-03 Xe-138 0.6668E+06 0.4746E+OO 0.4746E+OO 0.9654E-02 0.1185E-01 0.6789E-03 1-131 0.2114E+07 0.3692E+08 0.1053E+05 0.1468E+01 0.2450E+01 0.2179E-01 0.1663E+07 0.8157E+05 0.3693E+06 0.3918E+01 0.3940E+01 1-132 0.1773E+07 0.3097E+08 0.8859E+04 0.1235E+01 0.2060E+01 0.1833E-01 0.1395E+07 0.6843E+05 0.3098E+06 0.3295E+01 0.3314E+01 1-133 0.3284E+07 0.5735E+08 0.1637E+OS 0.2282E+01 0.3807E+01 0.3386E-01 0.2583E+07 0.1267E+06 0.5737E+06 0.6089E+01 0.6123E+01 1-134 0.1128E+07 0.1970E+08 0.5659E+04 0.7888E+OO 0.1316E+01 0.1171E-01 0.8875E+06 0.4353E+05 0.1971E+06 0.2105E+01 0.2117E+01 1-135 0.2964E+07 0.5177E+08 0.1478E+05 0.2061E+01 0.3439E+01 0.3058E-01 0.2332E+07 0.1144E+06 0.5179E+06 0.5499E+01 0.5530E+01 0.2057E+02 0.1609E+02 0.7212E-01 0.6335E+OO 0.4945E+OO 0.2215E-02 0.1447E+01 0.1131E+01 0.5072E-02 0.4455E-01 0.3477E-01 0.1558E-03 TIME = 119 HIN ACTIVITY IN CONTAINMENT ANO SIRW TANK CTHT. ATM. SUMP SIRW TANK ACTIVITY ACTIVITY ACTIVITY ISOTOPE (Ci) (Ci) (Cl) 0.8331E*03 0.8331E-03 0.8331E*03 0.8331E-03 0.8331E-03 0.8331E-03 0.8331E-03 0.8331E-03 0.8331E-03 0.8331E-03 0.3160E+04 0.4029E+05 0.2657E+04 0.4029E+05 0.4910E+04 0.4029E+05 0.1697E+04 0.4029E+05 0.4434E+04 0.4029E+05 0.3673E+02 0.1130E+01 0.2583E+01 0.7948E-01
~~FILE: C1HCALC.LST Created: 02/26/~~
14

22
PAGE: 12 of 28

Length: 195230 bytes.
~~Queued: 02/26/9~~
Lines 1211 to 1320 ****************
~~Kr-83m 0.3622E+07 0.2523E+01 0.2523E+01 0.1045E*01 0.1287E-01~~
0. 7349E*03 0.9051E*03 Kr-85m 0.1209E+08 0.8410E+01 0.8410E+01 0.1045E*01 0.1287E-01

0. 7349E*03 0.9051E-03 Kr-85 0.7587E+06 0.5269E+OO 0.5269E+OO 0.1045E-01 0.1287E*01

0. 7349E-03 0.9051E*03 Kr-87 0.9870E+07 0.6886E+01 0.6886E+01 0.1045E-01 0.1287E-01 0.7349E-03 0.9051E-03 Kr-88.
~~0.2635E+08 0.1833E+02 0.1833E+02 0.1045E-01 0.1287E-01 0.7349E-03 0.9051E*03 Kr-89 0.2126E-03 0.1652E-09 0.1652E-09 0.1045E*01~~
~~0.1287E-01 o*. 7349E*03 0.9051E*03 Xe-131m 0.4431E+06 0.3077E+OO~~
~~. 0.3077E+OO 0.1045E-01 0.1287E-01 0.7349E*03 0.9051E-03 Xe-133m 0.4816E+07 0.3345E+01 0.3345E+01 0.1045E-01 0.1287E-01~~
0. 7349E-03 0.9051E-03 Xe-133 0.1413E+09 0.9815E+02 0.9815E+02 0.1045E-01 0.1287E-01 0.7349E-03 0.9051E-03 Xe-135m 0.1958E+06 0.1391E+OO 0.1391E+OO 0.1045E-01 0.1287E-01 O. 7349E*03 0.9051E*03 Xe-135 0.2127E+08 0.1478E+02 0.1478E+02 0.1045E-01 0.1287E-01 0.7349E-03 0.9051E-03 Xe-137 0.5930E-01 0.4512E-07 0.4512E-07 0.1045E-01 0.1287E-01 0.7349E-03 0.9051E-03 Xe-138 0.3367E+06 0.2396E+OO 0.2396E+OO 0.1045E-01 0.1287E-01 0.7349E-03 0.9051E-03 1-131 0.2095E+07 0.3688E+08 0.1224E+05 0.1455E+01 0.2448E+01 0.2532E-01 0.3671E+04 0.1661E+07 0.6454E+05 0.3690E+06 0.4029E+05 0.3903E+01 0.3929E+01 1-132 0.1639E+07 0.2886E+08 0.9599E+04 0.1141E+01 0.1920E+01 0.1985E-01 0.2879E+04 0.1300E+07 0.5049E+05 0.2887E+06 0.4029E+05 0.3061E+01 0.3081E+01 1-133 0.3232E+07 0.5690E+08 0.1889E+05 0.2246E+01 0.3778E+01 0.3907E*01 0.5664E+04 0.2563E+07 0.9957E+05 0.5693E+06 0.4029E+05 0.6023E+01 0.6062E+01 1-134 0.9305E+06 0.1638E+08 0.5472E+04 0.6506E+OO 0.1094E+01 0.1132E-01 0.1641E+04 0.7379E+06 0.2866E+05 0.1639E+06 0.4029E+05 0.1745E+01 0.1756E+01 1-135 0.2869E+07 0.5051E+08 0.1677E+05 0.1994E+01 0.3355E+01 0.3470E-01 0.5031E+04 0.2275E+07 0.8838E+05 0.5053E+06 0.4029E+05 0.5350E+01 0.5384E+01 0.2212E+02 0.1867E+02 0.9713E*01 0.4089E+02 0.6808E+OO 0.5738E+OO 0.2983E*02 0.1258E+01 0.1555E+01 0.1313E+01 0.6831E-02 0.287SE+01 0.4788E-01 0.4035E-01 0.2097E*03 0.8844E*01
TIME= 120 MIN ACTIVITY JN CONTAINMENT AND SIRM TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRM TANK ACTIVITY (CJ) Kr-83m 0.3599E+07 0.2507E+01 0.2507E+01 0.1051E-01 0.1294E-01 0.7387E-03 0.9101E-03 Kr-85m 0.1206E+08 0.8388E+01 0.8388E+01 0.1051E-01 0.1294E-01 0.7387E-03 0.9101E-03 Kr-85 0.7587E+06 0.5269E+OO 0.5269E+OO 0.1051E-01 0.1294E-01 0.7387E-03 0.9101E-03 Kr-87 0.9781E+07 0.6823E+01 0.6823E+01 0.1051E-01 0.1294E-01 0.7387E-03 0.9101E-03 Kr-88 0.2624E+08 0.1826E+02 0.1826E+02 0.1051E-01 0.1294E-01 0.7387E-03 0.9101E-03 Kr-89 0.1706E-03 0.1325E-09 0.1325E-09 0.1051E-01 0.1294E-01 0.7387E-03 0.9101E-03 Xe-131m 0.4431E+06 0.3077E+OO 0.3077E+OO 0.1051E-01 0.1294E-01 0.7387E-03 0.9101E-03 Xe-133m 0.4815E+07 0.3344E+01 0.3344E+01 0.1051E-01 0.1294E-01 0.7387E-03 0.9101E-03 Xe-133 0.1413E+09 0.9814E+02 0.9814E+02 0.1051E-01 0.1294E-01 0.7387E-03 0.9101E-03 Xe-135m 0.1872E+06 0.1330E+OO 0.1330E+OO 0.1051E-01 0.1294E-01 0.7387E-03 0.9101E-03 Xe-135 0.2124E+08 0.1476E+02 0.1476E+02 0.1051E-01 0.1294E-01 0.7387E-03 0.9101E-03 Xe-137 0.4953E-01 0.3769E-07 0.3769E-07 0.1051E-01 0.1294E-01 0.7387E-03 0.9101E-03 Xe-138 0.3207E+06 0.2282E+OO 0.2282E+OO 0.1051E-01 0.1294E-01 0.7387E-03 0.9101E-03 1-131 0.2094E+07 0.3688E+08 0.1236E+05 0.1454E+01 0.2448E+01 0.2557E-01 0.3707E+04 0.1661E+07 0.6347E+05 0.3690E+06 0.4029E+05 0.3902E+01 0.3928E+01 1-132 0.1630E+07 0.2871E+08 0.9646E+04 0.1135E+01 0.1910E+01 0.1995E-01 0.2893E+04 0.1293E+07 0.4941E+05 0.2872E+06 0.4029E+05 0.3045E+01 0.3065E+01 1-133 0.3229E+07 0.5687E+08 0.1906E+05 0.2243E+01 0.3775E+01 0.3943E-01 0.5718E+04 0.2562E+07 0.9787E+05 0.5689E+06 0.4029E+05 0.6019E+01 0.6058E+01 1-134 0.9178E+06 0.1617E+08 0.5454E+04 0.6418E+OO 0.1080E+01 0.1128E-01 0.1636E+04 0.7283E+06 0.2782E+05 0.1617E+06 0.4029E+05 0.1722E+01 0.1733E+01 1-135 0.2862E+07 0.5042E+08 0.1691E+05 0.1990E+01 0.3349E+01 0.3498E-01 0.5072E+04 0.2271E+07 0.8677E+05 0.5044E+06 0.4029E+05 0.5339E+01 0.5374E+01
FILE: C1MCALC.LST Created: 02/26/

PAGE: 13 of 28

Length: 195230 bytes.
~~Queued: 02/26/~~
Lines 1321 to 1430 ****************
TIME = 0.2223E+02 0.6842E+OO 0.1563E+01 0.4811E-01 0.1886E+02 0.5795E+OO 0.1326E+01 0.4075E-01 0.9906E-01 0.3042E-02 0.6966E-02 0.2139E-03 134 MIN ACTIVITY IN CONTAINMENT AND SJRM TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRM TANK ACTIVITY (CJ) Kr-83m 0.3300E+07 0.2299E+01 0.2299E+01
14

22 0.4118E+02 0.1267E+01 0.2896E+01 0.8908E-01 0.1051E-01 0.1294E-01 0.7912E-03 0.9783E-03 Kr-85m 0.1164E+08 0.8090E+01 0.8090E+01 0.1051E-01 0.1294E-01 0.7912E-03 0.9783E-03 Kr-85 0.7587E+06 0.5269E+OO 0.5269E+OO 0.1051E-01 0.1294E-01 0.7912E-03 0.9783E-03 Kr-87 0.8608E+07 0.6005E+01 0.6005E+01 0.1051E-01 0.1294E-01 0.7912E-03 0.9783E-03 Kr-88 0.2479E+08 0.1725E+02 0.1725E+02 0.1051E-01 0.1294E-01 0.7912E-03 0.9783E-03 Kr-89

0. 7830E-05 0.6082E-11 0.6082E-11 0.1051E-01 0.1294E-01 0.7912E-03 0.9783E-03 Xe-131m 0.4428E+06 0.3075E+OO 0.3075E+OO 0.1051E-01 0.1294E-01 0.7912E-03 0.9783E-03 Xe-133m 0.4800E+07 0.3333E+01 0.3333E+01 0.1051E-01 0.1294E-01 0.7912E-03 0.9783E-03 Xe-133 0.1411E+09 0.9802E+02 0.9802E+02 0.1051E-01 0.1294E-01 0.7912E-03 0.9783E-03 Xe-135m 0.9926E+05 0.7051E-01 0.7051E-01 0.1051E-01 0.1294E-01 0.7912E-03 0.9783E-03 Xe-135 0.2087E+08 0.1450E+02 0.1450E+02 0.1051E-01 0.1294E-01 0.7912E-03 0.9783E-03 Xe-137 0.3985E-02 0.3032E-08 0.3032E-08 0.1051E-01 0.1294E-01 0.7912E-03 0.9783E-03 Xe-138 0.1619E+06 0.1152E+OO 0.1152E+OO 0.1051E-01 0.1294E-01 0.7912E-03 0.9783E-03 1-131 0.2079E+07 0.3685E+08 0.1406E+05 0.1444E+01 0.2446E+01 0.2908E-01 0.4217E+04 0.1660E+07 0.5022E+05 0.3687E+06 0.4028E+05 0.3890E+01 0.3919E+01 1-132 0.1509E+07 0.2675E+08 0.1023E+05 0.1051E+01 0.1780E+01 0.2117E-01 0.3069E+04 0.1205E+07 0.3646E+05 0.2676E+06 0.4028E+05 0.2831E+01 0.2852E+01 1-133 0.3183E+07 0.5643E+08 0.2154E+OS 0.2212E+01 0.3746E+01 0.4455E-01 0.6460E+04 0.2542E+07 0.7690E+OS 0.564SE+06 0.4028E+OS 0.5958E+01 0.6002E+01 1-134 0.7583E+06 0.1344E+08 0.5164E+04 0.5302E+OO 0.8981E+OO 0.1068E-01 0.1549E+04
0.6055E+06 0.1832E+05 0.1345E+06 0.4028E+05 0.1428E+01 0.1439E+01 1*135 0.2775E+07 0.4920E+08 0.1879E+05 0.1929E+01 0.3268E+01 0.3886E-01 0.2216E+07 0.6704E+05 0.4922E+06 0.5197E+01 0.5236E+01 0.2223E+02 0.6842E+OO 0.1670E+01 0.5140E-01 0.1886E+02 0.5795E+OO 0.1507E+01 0.4631E-01 0.9906E-01 0.3042E*02 0.9000E-02 0.2763E-03 0.5635E+04 0.4028E+05 0.4118E+02 0.1267E+01 0.3187E+01 0.9799E-01 TIME = 135 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE 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 1-132 CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) 0.3279E+07 0.2284E+01 0.2284E+01 0.1051E-01 0.1294E-01 0.7949E-03 0.9830E-03 0.1161E+08 0.8070E+01 0.8070E+01 0.1051E-01 0.1294E-01 0.7949E-03 0.9830E-03 0.7587E+06 0.5268E+OO 0.5268E+OO 0.1051E-01 0.1294E-01 0.7949E-03 0.9830E-03 0.8530E+07 0.5951E+01 0.5951E+01 0.1051E-01 0.1294E-01 0.7949E-03 0.9830E-03 0.2469E+08 0.1718E+02 0.1718E+02 0.1051E-01 0.1294E-01 0.7949E-03 0.9830E-03 0.6283E-05 0.4881E-11 0.4881E-11 0.1051E-01 0.1294E-01 0.7949E-03 0.9830E-03 0.4428E+06 0.3075E+OO 0.3075E+OO 0.1051E-01 0.1294E-01 0.7949E-03 0.9830E-03 0.4799E+07 0.3333E+01 0.3333E+01 0.1051E-01 0.1294E-01 0.7949E-03 0.9830E-03 0.1411E+09 0.9801E+02 0.9801E+02 0.1051E-01 0.1294E-01 0.7949E-03 0.9830E-03 0.9486E+05 0.6739E-01 0.6739E*01 0.1051E-01 0.1294E-01 0.7949E*03 0.9830E-03 0.2084E+08 0.1448E+02 0.1448E+02 0.1051E-01 0.1294E-01 0.7949E-03 0.9830E*03 0.3329E-02 0.2533E-08 0.2533E-08 0.1051E-01 0.1294E-01 0.7949E-03 0.9830E-03 0.1542E+06 0.1097E+OO 0.1097E+OO 0.1051E-01 0.1294E-01 0.7949E-03 0.9830E-03 0.2078E+07 0.3685E+08 0.1418E+05 0.1443E+01 0.2446E+01 0.2934E-01 0.4254E+04 0.1660E+07 0.4938E+05 0.3686E+06 0.4028E+05 0.3889E+01 0.3918E+01 0.1501E+07 0.2662E+08 0.1027E+05. 0.1045E+01 0.1771E+01 0.2124E-01 0.3080E+04 0.1199E+07 0.3567E+05 0.2663E+06 0.4028E+05
FILE: C1MCALC.LST Created: 02/26/-:14

PAGE: 14 of 28

Length: 195230 bytes.
~~Queued: 02/26/9~~
22
Lines 1431 to 1540 *****************
TIME = 0.2816E+01 0.2837E+01 1-133 0.3180E+07 0.5640E+08 0.2171E+05 0.2210E+01 0.3744E+01 0.4491E*01 0.2540E+07 0.7559E+05 0.5642E+06 0.5954E+01 0.5999E+01 1-134 0.7481E+06 0.1327E+08 0.5140E+04 0.5231E+OO 0.8864E+OO 0.1063E-01 0.5976E+06 0.1778E+05 0.1327E+06 0.1409E+01 0.1420E+01 1-135 0.2769E+07 0.4911E+08 0.1892E+05 0.1925E+01 0.3262E+01 0.3913E*01 0.2212E+07 0.6582E+05 0.4913E+06 0.5187E+01 0.5227E+01 0.2223E+02 0.1886E+02 0.9906E-01 0.6842E+OO 0.5795E+OO 0.3042E*02 0.1678E+01 0.1520E+01 0.9155E-02 0.5164E-01 0.4671E-01 0.2810E-03 149 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.3006E+07 0.2094E+01 0.2094E+01 0.6512E+04 0.4028E+05 0.1542E+04 0.4028E+05 0.5674E+04 0.4028E+05 0.4118E+02 0.1267E+01 0.3207E+01 0.9862E-01 0.1051E-01 0.1294E-01 0.8442E-03 0.1048E-02 Kr-85m 0.1119E+08 0.7783E+01 0.7783E+01 0.1051E-01 0.1294E-01 0.8442E-03 0.1048E-02 Kr-85 0.7587E+06 0.5268E+OO 0.5268E+OO 0.1051E-01 0.1294E-01 0.8442E-03 0.1048E-02 Kr-87 0.7508E+07 0.5237E+01 0.5237E+01 0.1051E-01 0.1294E-01 0.8442E-03 0.1048E-02 Kr-88 0.2332E+08 0.1623E+02 0.1623E+02 0.1051E-01 0.1294E-01 0.8442E-03 0.1048E-02 Kr-89 0.2884E-06 0.2240E*12 0.2240E-12 0.1051E-01 0.1294E-01 0.8442E-03 0.1048E-02 Xe*131m 0.4426E+06 0.3073E+OO 0.3073E+OO 0.1051E-01 0.1294E-01 0.8442E-03 0.1048E-02 Xe*133m 0.4784E+07 0.3322E+01 0.3322E+01 0.1051E-01 0.1294E-01 0.8442E-03 0.1048E*02 Xe-133 0.1409E+09 0.9788E+02 0.9788E+02 0.1051E-01 0.1294E-01 0.8442E*03 0.1048E-02 Xe-135m 0.5031E+05 0.3574E-01 0.3574E-01 0.1051E-01 0.1294E*01 0.8442E*03 0.1048E-02 Xe-135 0.2047E+08 0.1423E+02 0.1423E+02 0.1051E-01 0.1294E-01 0.8442E-03 0.1048E*02 Xe-137 0.2678E-03 0.2038E-09 0.2038E*09 0.1051E-01 0.1294E-01 0.8442E-03 0.1048E*02 Xe-138 0.7785E+OS 0.5541E-01 0.5541E*01 0.1051E-01 0.1294E-01 0.8442E-03 0.1048E*02
d.
~1 ~ ~ Ci Q
1-131 1-132 1-133 1-134 1-135 0.2066E+07 0.3681E+08 0.1588E+05 0.1435E+01 0.2444E+01 0.3285E-01 0.4763E+04 0.1658E+07 0.3907E+05 0.3683E+06 0.4028E+05 0.3878E+01 0.3911E+01 0.1392E+07 0.2480E+08 0.1073E+05 0.9690E+OO 0.1650E+01 0.2218E-01 0.3217E+04 0.1117E+07 0.2632E+05 0.2481E+06 0.4028E+05 0.2619E+01 0.2642E+01 0.3140E+07 0.5596E+08 0.2415E+05 0.2181E+01 0.3715E+01 0.4994E-01 0.7241E+04 0.2521E+07 0.5939E+05 0.5598E+06 0.4028E+05 0.5897E+01 0.5947E+01 0.6190E+06 0.1103E+08 0.4790E+04 0.4328E+OO 0.7370E+OO 0.9907E-02 0.1437E+04 0.4969E+06 0.1171E+05 0.1104E+06 0.4028E+05 0.1170E+01 0.1180E+01 0.2689E+07 0.4791E+08 0.2069E+05 0.1869E+01 0.3183E+01 0.4279E-01 0.6204E+04 0.2158E+07 0.5086E+05 0.4794E+06 0.4028E+05 0.5052E+01 0.5095E+01 0.2223E+02 0.6842E+OO 0.1784E+01 0.5490E-01 0.1886E+02 0.5795E+OO 0.1701E+01 0.5224E-01 0.9906E-01 0.3042E-02 0.1146E-01 0.3517E-03 0.4118E+02 0.1267E+01 0.3497E+01 0.1075E+OO TIME = 150 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) 0.2987E+07 0.2081E+01 0.2081E+01 0.1051E-01 0.1294E-01 0.8476E-03 0.1052E-02 0.1116E+08 0.7763E+01 0.7763E+01 0.1051E-01 0.1294E-01 0.8476E-03 0.1052E-02 0.7587E+06 0.5268E+OO 0.5268E+OO 0.1051E-01 0.1294E-01 0.8476E-03 0.1052E-02 0.7439E+07 0.5190E+01 0.5190E+01 0.1051E-01 0.1294E-01 0.8476E-03 0.1052E-02 0.2322E+08 0.1616E+02 0.1616E+02 0.1051E-01 0.1294E-01 0.8476E-03
0.1052E-02 0.2314E-06 0.1797E-12 0.1797E-12 0.1051E-01 0.1294E-01 0.8476E-03 0.1052E-02 0.4425E+06 0.3073E+OO 0.3073E+OO 0.1051E-01 0.1294E-01 0.8476E-03 0.1052E-02 0.4783E+07 0.3322E+01 0.3322E+01 0.1051E-01 0.1294E-01 0.8476E-03 0.1052E-02 0.1409E+09 0.9787E+02 0.9787E+02 0.1051E-01 0.1294E-01 0.8476E-03 0.1052E-02 0.4808E+05 0.3416E-01 0.3416E-01

FILE: C1MCALC.LST Created: 02/26/

PAGE: 15 of 28

Length: 195230 bytes.
~~Queued: 02/26/~~
Lines 1541 to 1650 *****************
TIME = 0.1051E-01 0.1294E-01 0.8476E-03 0.1052E-02 Xe-135 0.2045E+08 0.1421E+02 0.1421E+02 0.1051E-01 0.1294E-01 0.8476E-03 0.1052E-02 Xe-137 0.2237E-03 0.1702E-09 0.1702E-09 0.1051E-01 0.1294E-01 0.8476E-03
o.1052E-02 xe-138 o.7415E+05 o.52m-01 o.52m-01 0.1051E-01 0.1294E-01 0.8476E-03 0.1052E-02 1-131 0.2065E+07 0.3681E+08 0.1600E+05 0.1434E+01 0.2443E+01 0.3310E-01 0.4799E+04 0.1658E+07 0.3842E+05 0.3683E+06 0.4028E+05 0.3878E+01 0.3911E+01 1-132 0.1384E+07 0.2468E+08 0.1075E+05 0.9639E+OO 0.1642E+01 0.2224E-01 0.3225E+04 0.1112E+07 0.2576E+05 0.2469E+06 0.4028E+05 0.2606E+01 0.2628E+01 1-133 0.3137E+07 0.5593E+08 0.2432E+05 0.2180E+01 0.3713E+01 0.5030E-01 0.7293E+04 0.2519E+07 0.5838E+05 0.5595E+06 0.4028E+05 0.5893E+01 0.5943E+01 1-134 0.6107E+06 0.1089E+08 0.4764E+04 0.4270E+OO 0.7274E+OO 0.9853E-02 0.1429E+04 0.4904E+06 0.1136E+05 0.1089E+06 0.4028E+05 0.1154E+01 0.1164E+01 1-135 0.2683E+07 0.4783E+08 0.2081E+05 0.1865E+01 0.3178E+01 0.4304E-01 0.6241E+04 0.2155E+07 0.4993E+05 0.4785E+06 0.4028E+05 0.5043E+01 0.5086E+01 0.2223E+02 0.6842E+OO 0.1792E+01 0.5513E-01 0.1886E+02 0.5795E+OO 0.1714E+01 0.5264E-01 0.9906E-01 0.3042E-02 0.1164E-01 0.3571E-03 0.4118E+02 0.1267E+01 0.3517E+01 0.1081E+OO 164 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM.
ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.2739E+07 0.1908E+01 0.1908E+01 0.1051E-01 0.1294E-01 0.8941E-03 0.1114E-02 Kr-85m o.10m+os 0.7488E+01 0.7488E+01 0.1051E-01 0.1294E-01 0.8941E-03 0.1114E-02 Kr-85 0.7586E+06 0.5268E+OO 0.5268E+OO 0.1051E-01 0.1294E-01 0.8941E-03 0.1114E-02 Kr-87 0.6548E+07 0.4568E+01 0.4568E+01 0.1051E-01 0.1294E-01 0.8941E-03 0.1114E-02 Kr-88 0.2194E+08 0.1527E+02 0.1527E+02 0.1051E-01 0.1294E-01 0.8941E-03 0.1114E-02 Kr-89 0.1062E-07 0.8249E-14 0.8249E-14 0.1051E-01 0.1294E-01 0.8941E-03 0.1114E-02
Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 1-131 1-132 1-133 1-134 1-135 0.4423E+06 0.3072E+OO 0.3072E+OO 0.1051E-01 0.1294E-01 0.8941E-03 0.1114E-02 0.4768E+07 0.3312E+01 0.3312E+01 0.1051E-01 0.1294E-01 0.8941E-03 0.1114E-02 0.1407E+09 0.9774E+02 0.9774E+02 0.1051E-01 0.1294E-01 0.8941E-03 0.1114E-02 0.2550E+05 0.1812E-01 0.1812E-01 0.1051E-01 0.1294E-01 0.8941E-03 0.1114E-02 0.2009E+08 0.1396E+02 0.1396E+02 0.1051E-01 0.1294E-01 0.8941E-03 0.1114E-02 0.1800E-04 0.1370E-10 0.1370E-10 0.1051E-01 0.1294E-01 0.8941E-03 0.1114E-02 0.3744E+05 0.2664E-01 0.2664E-01 0.1051E-01 0.1294E-01 0.8941E-03 0.1114E-02 0.2055E+07 0.3678E+08 0.1770E+05 0.1427E+01 0.2441E+01 0.3660E-01 0.5307E+04 0.1657E+07 0.3040E+05 0.3680E+06 0.4028E+05 0.3869E+01 0.3905E+01 0.1285E+07 0.2299E+08 0.1109E+05 0.8946E+OO 0.1530E+01 0.2294E-01 0.3326E+04 0.1036E+07 0.1901E+05 0.2300E+06 0.4028E+05 0.2425E+01 0.2448E+01 0.3101E+07 0.5549E+08 0.2671E+05 0.2154E+01 0.3684E+01 0.5524E-01 0.8009E+04 0.2500E+07 0.4587E+05 0.5552E+06 0.4028E+05 0.5839E+01 0.5894E+01 0.5058E+06 0.9051E+07 0.4384E+04 0.3536E+OO 0.6048E+OO 0.9068E-02 0.1315E+04 0.4078E+06 0.7482E+04 0.9056E+05 0.4028E+05 0.9584E+OO 0.9675E+OO 0.2608E+07 0.4667E+08 0.2248E+05 0.1813E+01 0.3100E+01 0.4648E-01 0.6740E+04 0.2102E+07 0.3858E+05 0.4669E+06 0.4028E+05 0.4913E+01 0.4960E+01 0.2223E+02 0.6842E+OO 0.1897E+01 0.5836E-01 0.1886E+02 0.5795E+OO 0.1894E+01 0.5815E-01 0.9906E-01 0.3042E-02 0.1422E-01 0.4360E-03 0.4118E+02 0.1267E+01 0.3805E+01 0.1169E+OO TIME = 165 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.2722E+07 0.1896E+01 0.1896E+01 0.1051E-01 0.1294E-01 0.8973E-03 0.1118E-02 Kr-85m 0.1074E+08 O. 7469E+01 O. 7469E+01 0.1051E-01 0.1294E-01 0.8973E-03 0.1118E-02 Kr-85 0.7586E+06 0.5268E+OO 0.5268E+OO
FILE: C1MCALC.LST Created: 02/26/

PAGE: 16 of 28.
~~Length: 195230 bytes. Queued: 02/26/~~
Lines 1651 to 1760 ****************
14

22 0.1051E-01 0.1294E-01 0.8973E-03 0.1118E-02 Kr-87 0.6488E+07 0.4526E+01 0.4526E+01 0.1051E-01 0.1294E-01 0.8973E-03 0.1118E-02 Kr-88 0.2185E+08 0.1520E+02 0.1520E+02 0.1051E-01 0.1294E-01 0.8973E-03 0.1118E-02 Kr-89 0.8522E-08 0.6620E-14 0.6620E-14 0.1051E-01 0.1294E-01 0.8973E-03 0.1118E-02 Xe-131m 0.4423E+06 0.3071E+OO 0.3071E+OO 0.1051E-01 0.1294E-01 0.8973E-03 0.1118E-02 Xe-133m 0.4767E+07 0.3311E+01 0.3311E+01 0.1051E-01 0.1294E-01 0.8973E-03 0.1118E-02 Xe-133 0.1407E+09 0.9774E+02 0.9774E+02 0.1051E-01 0.1294E-01 0.8973E-03 0.1118E-02 Xe-135m 0.2437E+05 0.1731E-01 0.1731E-01 0.1051E-01 0.1294E-01 0.8973E-03 0.1118E-02 Xe-135 0.2006E+08 0.1394E+02 0.1394E+02

0. 1051E-01 0.1294E-01 0.8973E-03 0.1118E-02 Xe-137 0.1503E-04 0.1144E-10 0.1144E-10 0.1051E-01 0.1294E-01 0.8973E-03 0.1118E-02 Xe-138 0.3565E+OS 0.2537E-01 0.2537E-01 0.1051E-01 0.1294E-01 0.8973E-03 0.1118E-02 1-131 0.2055E+07 0.3678E+08 0.1782E+OS 0.1427E+01 0.2441E+01 0.3685E-01 0.5344E+04 0.1657E+07 0.2990E+OS 0.3680E+06 0.4028E+05 0.3868E+01 0.3905E+01 1-132 0.1278E+07 0.2288E+08 0.1111E+OS 0.8899E+OO 0.1522E+01 0.2298E-01 0.3332E+04 0.1031E+07 0.1860E+05 0.2289E+06 0.4028E+05 0.2412E+01 0.2435E+01 1-133 0.3098E+07 0.5546E+08 0.2688E+05 0.2153E+01 0.3682E+01 0.5559E-01 0.8060E+04 0.2498E+07 0.4509E+05 0.5549E+06 0.4028E+05 0.5835E+01 0.5890E+01 1-134 0.4991E+06 0.8933E+07 0.4357E+04 0.3489E+OO 0.5969E+OO 0.9010E-02 0.1307E+04 0.4024E+06 0.7262E+04 0.8938E+05 0.4028E+05 0.9458E+OO 0.9548E+OO 1-135 0.2603E+07 0.4659E+08 0.2259E+OS 0.1809E+01 0.3095E+01 0.4672E-01 0.677SE+04 0.2099E+07 0.3787E+OS 0.4661E+06 0.4028E+OS 0.4904E+01 0.4951E+01 0.2223E+02 0.6842E+OO 0.1905E+01 0.5859E-01 0.1886E+02 0.5795E+OO 0.1907E+01 0.5855E-01 0.9906E-01 0.3042E-02 0.1441E-01 0.4420E-03 TIME =
179 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK CTMT. ATM. ACTIVITY SUMP ACTIVITY SIRW TANK ACTIVITY 0.4118E+02 0.1267E+01 0.3826E+01 0.1176E+OO
ISOTOPE 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 1-132 1-133 1-134 1-135 (Ci) (Ci) CCI) 0.2495E+07 0.1738E+01 0.1738E+01 0.1051E*01 0.1294E-01 0.9411E-03 0.1177E*02 0.1036E+08 0.7204E+01 0.7204E+01 0.1051E-01 0.1294E-01 0.9411E-03 0.1177E*02 0.7586E+06 0.5268E+OO 0.5268E+OO 0.1051E-01 0.1294E-01 0.9411E-03 0.1177E-02 0.5710E+07 0.3984E+01 0.3984E+01 0.1051E-01 0.1294E-01 0.9411E-03 0.1177E-02 0.2064E+08 0.1436E+02 0.1436E+02 0.1051E-01 0.1294E-01 0.9411E*03 0.1177E-02 0.3911E-09 0.3038E*15 0.3038E-15 0.1051E*01 0.1294E-01 0.9411E*03 0.1177E-02 0.4420E+06 0.3070E+OO 0.3070E+OO 0.1051E-01 0.1294E-01 0.9411E-03 0.1177E-02 0.4752E+07 0.3301E+01 0.3301E+01 0.1051E-01 0.1294E-01 0.9411E*03 0.1177E-02 0.1406E+09 0.9761E+02 0.9761E+02 0.1051E-01 0.1294E*01 0.9411E-03 0.1177E-02 0.1293E+05 0.9182E*02 0.9182E-02 0.1051E-01 0.1294E-01 0.9411E-03 0.1177E-02 0.1971E+08 0.1369E+02 0.1369E+02 0.1051E-01 0.1294E-01 0.9411E-03 0.1177E-02 0.1210E-05 0.9204E-12 0.9204E-12 0.1051E-01 0.1294E-01 0.9411E-03 0.1177E-02 0.1800E+05 0.1281E-01 0.1281E*01 0.1051E-01 0.1294E-01 0.9411E-03 0.1177E-02 0.2047E+07 0.3674E+08 0.1951E+05 0.1421E+01 0.2439E+01 0.4035E*01 0.5851E+04 0.1655E+07 0.2366E+05 0.3677E+06 0.4027E+05 0.3861E+01 0.3901E+01 0.1187E+07 0.2131E+08 0.1135E+05 0.8267E+OO 0.1419E+01 0.2347E-01 0.3403E+04 0.9603E+06 0.1372E+05 0.2133E+06 0.4027E+05 0.2245E+01 0.2269E+01 0.3065E+07 0.5502E+08 0.2923E+05 0.2129E+01 0.3654E+01 0.6044E-01 0.8764E+04 0.2479E+07 0.3543E+05 0.5506E+06 0.4027E+05 0.5783E+01 0.5844E+01 0.4137E+06 0.7427E+07 0.3970E+04 0.2892E+OO 0.4963E+OO 0.8210E-02 0.1190E+04 0.3346E+06 0.4782E+04 0.7432E+05 0.4027E+05 0.7855E+OO 0.7938E+OO 0.2532E+07 0.4545E+08 0.2416E+05 0.176DE+01 0.3020E+01 0.4996E-01 0.7244E+04 0.2048E+07 0.2926E+05 0.4548E+06 0.4027E+D5 0.4780E+01 0.4830E+01 0.2223E+02 0.6842E+OO D.2010E+01 0.6179E-01 0.1886E+02 0.5795E+OO 0.2086E+01 0.6404E-01 0.9906E*01 0.3042E*02 0.1726E*01 0.5292E*03 0.4118E+02 0.1267E+01 0.4113E+01 0.1264E+OO
FILE: C1MCALC.LST Created: 02/26/-:14

PAGE: 17 of 28

Length: 195230 bytes.
~~Queued: 02/26/ 6:22~~
Lines 1761 to 1870 ***************** **********
TIME = 180 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr*83m 0.2480E+07 0.1727E+01 0.1727E+01 0.1051E-01 0.1294E*01 0.9442E*03 0.1181E*02 Kr-85m 0.1033E+08 '0.7185E+01 0.7185E+01 0.1051E*01 0.1294E-01 0.9442E-03 0.1181E*02 Kr-85 0.7586E+06 0.5268E+OO 0.5268E+OO 0.1051E-01 0.1294E*01 0.9442E-03 0.1181E*02 Kr-87 0.5659E+07 0.3948E+01 0.3948E+01 0.1051E*01 0.1294E-01 0.9442E*03 0.1181E-02 Kr-88 0.2056E+08 0.1430E+02 0.1430E+02 0.1051E-01 0.1294E-01 0.9442E*03 0.1181E-D2 Kr-89 0.3138E-09 0.2438E-15 0.2438E*15 0.1051E-01 0.1294E-01 0.9442E*03 0.1181E-02 Xe-131m 0.4420E+06 0.3070E+OO 0.3070E+OO 0.1051E-01 0.1294E-01 0.9442E*03 0.1181E*02 Xe-133m 0.4751E+07 0.3300E+01 0.3300E+01 0.1051E-01 0.1294E-01 0.9442E*03 0.1181E*02 Xe-133 0.1405E+09 0.9760E+D2 0.9760E+02 0.1051E-01 0.1294E-01 0.9442E*03 D.1181E*D2 Xe-135m 0.1235E+05 0.8776E-02 0.8776E-02 0.1051E-01 0.1294E-01 0.9442E*03 D.1181E*02 Xe-135 0.1968E+08 0.1368E+02 0.1368E+02 0.1051E-01 0.1294E-01 0.9442E-03 D.1181E-02 Xe-137 0.1010E*05 0.7688E-12 0.7688E*12 0.1051E*01 0.1294E*01 0.9442E*03 0.1181E*D2 Xe-138 0.1715E+05 0.1220E*01 0.1220E*01 0.1051E*01 0.1294E*01 0.9442E*03 0.1181E*02 1*131 0.2046E+07 0.3674E+08 0.1963E+05 0.1421E+01 0.2439E+01 0.4060E*01 0.5887E+04 0.1655E+07 0.2326E+05 0.3676E+06 0.4027E+05 0.3860E+01 0.3901E+01 1*132 0.1181E+07 0.2121E+08 0.1136E+05 0.8223E+OO 0.1411E+01 D.2349E*01 0.3407E+04 0.9554E+06 0.1343E+05 0.2122E+06 0.4027E+05 0.2234E+01 0.2257E+01 1*133 0.3063E+07 0.5499E+08 0.2939E+05 0.2128E+01 0.3652E+01 0.6079E*01 0.8814E+04 0.2478E+07 0.3482E+05 0.5503E+06 0.4027E+05 0.5779E+01 0.5840E+01 1*134 D.4082E+06 0.7330E+07 0.3942E+04 0.2854E+OO 0.4898E+OO 0.8153E*02 D.1182E+04 0.3302E+06 0.4641E+04 0.7334E+05 0.4027E+05 0.7752E+OO 0.7834E+OO 1*135 0.2527E+07 0.4537E+08 0.2426E+05 0.1757E+01 0.3015E+01 0.5018E*01 0.7276E+04 0.2044E+07 0.2873E+05 0.4540E+06 0.4027E+05 0.4771E+01 0.4821E+01
FILE: C1MCALC.LST Created: 02/26/-:14

PAGE: 18 of 28

Length: 195230 bytes.
~~Queued: 02/26/9~~
22
Lines 1871 to 1980 *****************
0.2223E+02 0.6842E+OO 0.2017E+01 0.6202E-01 0.1886E+02 0.5795E+OO 0.2099E+01 0.6443E-01 0.9906E-01 0.3042E-02 0.1747E-01 0.5357E-03 0.4118E+02 0.1267E+01 0.4133E+01 0.1270E+OO TIME = 194 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.2273E+07 0.1583E+01 0.1583E+01 0.1051E-01 0.1294E-01 0.9855E-03 0.1236E-02 .Kr-85m 0.9967E+07 0.6930E+01 0.6930E+01 0.1051E-01 0.1294E-01 0.9855E-03 0.1236E-02 Kr-85 0.7586E+06 0.5268E+OO 0.5268E+OO 0.1051E-01 0.1294E-01 0.9855E-03 0.1236E-02 Kr-87 0.4980E+07 0.3474E+01 0.3474E+01 0.1051E-01 0.1294E-01 0.9855E-03 0.1236E-02 Kr-88 0.1942E+08 0.1351E+02 0.1351E+02 0.1051E-01 0.1294E-01 0.9855E-03 0.1236E-02 Kr-89 0.1440E-10 0.1119E-16 0.1119E-16 0.1051E-01 0.1294E-01 0.9855E-03 0.1236E-02 Xe-131m 0.4417E+06 0.3068E+OO 0.3068E+OO 0.1051E-01 0.1294E-01 0.9855E-03 0.1236E-02 Xe-133m 0.4737E+07 0.3290E+01 0.3290E+01 0.1051E-01 0.1294E-01 0.9855E-03 0.1236E-02 Xe-133 0.1404E+09 0.9747E+02 0.9747E+02 0.1051E-01 0.1294E-01 0.9855E-03 0.1236E-02 Xe-135m 0.6551E+04 0.4654E-02 0.4654E-02 0.1051E-01 0.1294E-01 0.9855E-03 0.1236E-02 Xe-135 0.1934E+08 0.1344E+02 0.1344E+02 0.1051E-01 0.1294E-01 0.9855E-03 0.1236E-02 Xe-137 0.8129E-07 0.6185E-13 0.6185E-13 0.1051E-01 0.1294E-01 0.9855E-03 0.1236E-02 Xe-138 0.8657E+04 0.6161E-02 0.6161E-02 0.1051E-01 0.1294E-01 0.9855E-03 0.1236E-02 1-131 0.2040E+07 0.3671E+08 0.2132E+05 0.1417E+01 0.2437E+01 0.4409E-01 0.6393E+04 0.1654E+07 0.1841E+05 0.3673E+06 0.4027E+05 0.3854E+01 0.3898E+01 1-132 0.1098E+07 0.1976E+08 0.1151E+05 0.7644E+QO 0.1315E+01 0.2379E-01 0.3450E+04 0.8903E+06 0.9908E+04 0.1977E+06 0.4027E+05 0.2080E+01 0.2103E+01 1-133 0.3032E+07 0.5456E+08 0.3170E+OS 0.2106E+01 0.3623E+01 0.6556E-01 0.9506E+04 0.2458E+07 0.2736E+05 0.5460E+06 0.4027E+05 0.5730E+01 0.5795E+01 1-134 0.3386E+06 0.6094E+07 0.3563E+04 TIME = 1-135 0.2367E+OO 0.4073E+OO 0.2746E+06 0.3056E+04 0.6440E+OO 0.6514E+OO 0.7369E-02 0.6099E+05 0.2460E+07 0.4427E+08 0.2573E+05 0.1068E+04 0.4027E+05 0.1710E+01 0.2942E+01 0.5322E-01
0. 7717E+04 0.1995E+07 0.2220E+05 0.4430E+06 0.4027E+05 0.4651E+01 0.4705E+01 0.2223E+02 0.6842E+OO 0.2121E+01 0.6521E-01 0.1886E+02 0.5795E+OO 0.2278E+01 0.6991E-01 0.9906E-01 0.3042E-02 0.2059E-01 0.6311E-03 0.4118E+02 0.1267E+01 0.4420E+01 0.1357E+OO 195 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM.
ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.2259E+07 0.1574E+01 0.1574E+01 0.1051E-01 0.1294E-01 0.9884E-03 0.1240E-02 Kr-85m 0.9941E+07 0.6912E+01 0.6912E+01 0.1051E-01 0.1294E-01 0.9884E-03 0.1240E-02 Kr-85 0.7586E+06 0.5268E+OO 0.5268E+OO 0.1051E-01 0.1294E-01 0.9884E-03 0.1240E-02 Kr-87 0.4935E+07 0.3443E+01 0.3443E+01 0.1051E-01 0.1294E-01 0.9884E-03 0.1240E-02 Kr-88 0.1934E+08 0.1346E+02 0.1346E+02 0.1051E-01 0.1294E-01 0.9884E-03 0.1240E-02 Kr-89 0.1156E-10 0.8978E-17 0.8978E-17 0.1051E-01 0.1294E-01 0.9884E-03 0.1240E-02 Xe-131m 0.4417E+06 0.3068E+OO 0.3068E+OO 0.1051E-01 0.1294E-01 0.9884E-03 0.1240E-02 Xe"133m 0.4736E+07 0.3289E+01 0.3289E+01 0.1051E-01 0.1294E-01 0.9884E-03 0.1240E-02 Xe-133 0.1403E+09 0.9747E+02 0.9747E+02 0.1051E-01 0.1294E-01 0.9884E-03 0.1240E-02 Xe-135m 0.6261E+04 0.4448E-02 0.4448E-02 0.1051E-01 0.1294E-01 0.9884E-03 0.1240E-02 Xe-135 0.1931E+08 0.1342E+02 0.1342E+02 0.1051E-01 0.1294E-01 0.9884E-03 0.1240E-02 Xe-137 0.6790E-07 0.5166E-13 0.5166E-13 0.1051E-01 0.1294E-01 0.9884E-03 0.1240E-02 Xe-138 0.8245E+04 0.5867E-02 0.5867E-02 0.1051E-01 0.1294E-01 0.9884E-03 0.1240E-02 1-131 0.2039E+07 0.3670E+08 0.2144E+05 0.1416E+01 0.2437E+01 0.4434E-01 0.6429E+04 0.1654E+07 0.1810E+05 0.3673E+06 0.4027E+05 0.3853E+01 0.3897E+01 1-132 0.1092E+07 0.1966E+08 0.1151E+05 0.7605E+OO 0.1309E+01 0.2381E-01 0.3452E+04
0.8858E+06 0.9695E+04 0.1967E+06 0.4027E+05 0.2069E+01 0.2093E+01 1-133 0.3030E+07 0.5453E+08 0.3186E+05 0.2105E+01 0.3621E+01 0.6590E*01 0.9555E+04 0.2457E+07 0.2689E+05 0.5457E+06 0.4027E+OS 0.5726E+01 0.5792E+01 1-134 0.3341E+06 0.6015E+07 0.3536E+04 0.2336E+OO 0.4019E+OO 0.7314E*02 0.1061E+04 0.2710E+06 0.2966E+04 0.6019E+05 0.4027E+05 0.6355E+OO 0.6429E+OO 1*135 0.2455E+07 0.4419E+08 0.2584E+05 0.1707E+01 0.2936E+01 0.5343E*01 0.7747E+04 0.1991E+07 0.2179E+05 0.4422E+06 0.4027E+05 0.4643E+01 0.4696E+01 0.2223E+02 0.1886E+02 0.9906E*01 0.4118E+02 0.6842E+OO 0.5795E+OO 0.3042E*02 0.1267E+01 0.2128E+01 0.2291E+01 0.2082E*01 0.4440E+01 0.6544E*01 0.7030E*01 0.6382E*03 0.1364E+OO TIME
~~209 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE 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 CTMT. ATM.~~
ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY CCI) 0.2071E+07 0.1443E+01 0.1443E+01 0.1051E-01 0.1294E*01 0.1027E*02 0.1294E-02 0.9588E+07 0.6667E+01 0.6667E+01 0.1051E*01 0.1294E*01 0.1027E*02 0.1294E*02 0.7586E+06 0.5268E+OO 0.5268E+OO 0.1051E*01 0.1294E*01 0.1027E*02 0.1294E*02 0.4343E+07 0.3030E+01 0.3030E+01 0.1051E*01 0.1294E*01 0.1027E*02 0.1294E*02 0.1827E+08 0.1271E+02 0.1271E+02 0.1051E*01 0.1294E*01 0.1027E*02 0.1294E*02 0.5304E*12 0.4120E*18 0.4120E*18 0.1051E-01 0.1294E*01 0.1027E-02 0.1294E*02 0.4415E+06 0.3066E+OO 0.3066E+OO 0.1051E*01 0.1294E*01 0.1027E*02 0.1294E*02 0.4721E+07 0.3279E+01 0.3279E+01 0.1051E*01 0.1294E*01 0.1027E*02 0.1294E*02 0.1402E+09 0.9734E+02 0.9734E+02 0.1051E*01 0.1294E*01 0.1027E-02 0.1294E*02 0.3321E+04 0.2359E*02 0.2359E*02 0.1051E*01 0.1294E*01 0.1027E*02 0.1294E*02 0.1897E+08 0.1318E+02 0.1318E+02 0.1051E*01 0.1294E*01 0.1027E*02 0.1294E*02 0.5463E*08 0.4157E*14 0.4157E*14 0.1051E*01 0.1294E*01 0.1027E*02 0.1294E*02 0.4163E+04 0.2963E*02 0.2963E*02
FILE: C1MCALC.LST Created: 02/26/.:14

PAGE: 19 of 28

Length: 195230 bytes.
~~Queued: 02/26/9~~
22
L;nes 1981 to 2090 ****************
TIME = 1-131 1*132 1*133 1*134 1*135 0.1051E*01 0.1294E*01 0.1027E*02 0.1294E*02 0.2036E+07 0.3667E+08 0.2313E+05 0.1414E+01 0.2435E+01 0.4783E*01 0.6935E+04 0.1652E+07 0.1664E+OS 0.3670E+06 0.4027E+OS 0.3849E+01 0.3897E+01 0.1017E+07 0.1832E+08 0.1158E+OS 0.7080E+OO 0.1219E+01 0.2395E*01 0.3473E+04 0.8254E+06 0.8312E+04 0.1833E+06 0.4027E+05 0.1927E+01 0.1951E+01 0.3004E+07 0.5411E+08 0.3413E+05 0.2087E+01 0.3593E+01 0.7058E*01 0.1023E+05 0.2438E+07 0.2455E+05 0.5415E+06 0.4027E+05 0.5680E+01 0.5751E+01 0.2776E+06 0.5001E+07 0.3174E+04 0.1941E+OO 0.3342E+OO 0.6565E*02 0.9519E+03 0.2253E+06 0.2269E+04 O.SOOSE+OS 0.4027E+OS 0.5283E+OO 0.5349E+OO 0.2394E+07 0.4312E+08 0.2721E+05 0.1664E+01 0.2865E+01 0.5628E*01 0.8160E+04 0.1943E+07 0.1956E+OS 0.4315E+06 0.4027E+OS 0.4529E+01 0.4585E+01 0.2223E+02 0.6842E+OO 0.2232E+01 0.6860E*01 0.1886E+02 0.5795E+OO 0.2469E+01 0.7576E*01 0.9906E*01 0.3042E*02 0.2420E*01 0.7417E*03 0.4118E+02 0.1267E+01 0.4725E+01 0.1451E+OO 210 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr*83m 0.2058E+07 0.1434E+01 0.1434E+01 0.1051E*01 0.1294E*01 0.1030E*02 0.1297E*02 Kr-85m 0.9564E+07 0.6650E+01 0.6650E+01 0.1051E*01 0.1294E*01 0.1030E*02 0.1297E*02 Kr-85 0.7586E+06 0.5268E+OO 0.5268E+OO 0.1051E*01 0.1294E*01 0.1030E*02 0.1297E*02 Kr-87 0.4304E+07 0.3003E+01 0.3003E+01 0.1051E*01 0.1294E*01 0.1030E*02 0.1297E*02 Kr-88 0.1819E+08 0.1266E+02 0.1266E+02 0.1051E*01 0.1294E*01 0.1030E-02 0.1297E*02 Kr-89 0.4256E*12 0.3306E*18 0.3306E*18 0.1051E*01 0.1294E*01 0.1030E*02 0.1297E*02 Xe-131m 0.4415E+06 0.3066E+OO 0.3Q66E+OO 0.1051E*01 0.1294E*01 0.1030E*02 0.1297E*02 Xe*133m 0.4720E+07 0.3278E+01 0.3278E+01 0.1051E*01 0.1294E*01 0.1030E*02 0.1297E*02 Xe-133 0.1401E+09 0.9733E+02 0.9733E+02 0.1051E*01 0.1294E*01 0.1030E*02 0.1297E*02
l<e*135m l<e-135 l<e-137 l<e-138 1-131 1*132 1-133 1-134 1-135 0.3174E+04 0.2255E*02 0.2255E*02 0.1051E*01 0.1294E*01 0.1030E*02 0.1297E*02 0.1895E+08 0.1317E+02 0.1317E+02 0.1051E*01 0.1294E*01 0.1030E*02 0.1297E*02 0.4563E*08 0.3472E*14 0.3472E*14 0.1051E*01 0.1294E*01 0.1030E*02 0.1297E*02 0.3965E+04 0.2821E*02 0.2821E*02 0.1051E*01 0.1294E*01 0.1030E*02 0.1297E-02 0.2036E+07 0.3667E+08 0.2325E+05 0.1414E+01 0.2435E+01 0.4807E*01 0.6971E+04 0.1652E+07 0.1664E+05 0.3670E+06 0.4027E+05 0.3848E+01 0.3897E+01 0.1012E+07 0.1823E+08 0.1158E+05 0.7045E+OO 0.1213E+01 0.2395E*01 0.3473E+04 0.8212E+06 0.8270E+04 0.1824E+06 0.4027E+05 0.1918E+01 0.1942E+01 0.3002E+07 0.5408E+08 0.3429E+05 0.2086E+01 0.3591E+01 0.7091E*01 0.1028E+05 0.2437E+07 0.2454E+05 0.5412E+06 0.4027E+05 0.5677E+01 0.5748E+01 0.2740E+06 0.4935E+07 0.3149E+04 0.1915E+OO 0.3298E+OO 0.6513E*02 0.9444E+03 0.2224E+06 0.2239E+04 0.4939E+05 0.4027E+05 0.5214E+OO 0.5279E+OO 0.2390E+07 0.4304E+08 0.2731E+05 0.1661E+01 0.2860E+01 0.5648E*01 0.8189E+04 0.1939E+07 0.1953E+05 0.4307E+06 0.4027E+05 0.4521E+01 0.4578E+01 0.2223E+02 0.6842E+OO 0.2239E+01 0.6883E*01 0.1886E+02 0.5795E+OO 0.2482E+01 0.7614E*01 0.9906E-01 0.3042E*02 0.2445E-01 0.7494E-03 0.4118E+02 0.1267E+01 0.4745E+01 0.1457E+OO TIME = 239 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE Kr*83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 ~-------- CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) 0.1719E+07 0.1197E+01 0.1197E+01 0.1051E*01 0.1294E*01 0.1105E*02 0.1401E*02 0.8874E+07 0.6171E+01 0.6171E+01 0.1051E*01 0.1294E*01 0.1105E*02 0.1401E*02 0.7586E+06 0.5268E+OO 0.5268E+OO 0.1051E*01 0.1294E*01 0.1105E*02 0.1401E*02 0.3304E+07 0.2305E+01 0.2305E+01 0.1051E*01 0.1294E*01 0.1105E*02 0.1401E*02 0.1617E+08 0.1125E+02 0.1125E+02 0.1051E*01 0.1294E*01 0.1105E*02 0.1401E*02 0.7194E*15 0.5588E*21 0.5588E*21
~~FILE: C1MCALC.LST Created: 02/26/~~
14

22
PAGE: 20 of 28

Length: 195230 bytes.
~~Queued: 02/26/9~~
Lines 2091 to 2200 *****************
TIME = l<e*131m l<e-133m xe-133 l<e-135m l<e-135 l<e-137 l<e-138 1-131 1-132 1-133 1-134 1-135 0.1051E*01 0.1294E*01 0.1105E-02 0.1401E*02 0.4409E+06 0.3062E+OO 0.3062E+OO 0.1051E*01 0.1294E*01 0.1105E-02 0.1401E*02 0.4690E+07 0.3257E+01 0.3257E+01 0.1051E*01 0.1294E*01 0.1105E*02 0.1401E*02
0. 1398E+09 0.9707E+02 0.9707E+02 0.1051E*01

0. 1294E*01

0. 1105E*02 0.1401E*02 0.8531E+03 0.6061E*03 0.6061E*03

0. 1051E*01 O. 1294E*01 0.1105E*02 0.1401E*02 0.1826E+08

0. 1269E+02 0.1269E+02 0.1051E*01

0. 1294E*01 0.1105E*02 O. 1401E*02 o.2468e-10

o. 18m-16 o.1a11e-16 0.1051E*01

0. 1294E*01 0.1105E*02

0. 1401E*02 0.9626E+03 0.6851E*03 0.6851E*03 0.1051E*01 0.1294E*01 0.1105E*02 0.1401E*02 0.2032E+07 0.3660E+08 0.2673E+05 0.1411E+01 0.2430E+01 0.5527E*01 0.8014E+04 0.1649E+07 0.1661E+05 0.3663E+06 0.4026E+05 0.3842E+01 0.3897E+01 0.8742E+06 0.1574E+08 0.1153E+05 0.6086E+OO 0.1048E+01 0.2383E-01 0.3456E+04 0.7094E+06 0.7144E+04 0.1576E+06 0.4026E+05 0.1657E+01 0.1680E+01 0.2954E+07 0.5321E+08 0.3887E+05 0.2052E+01 0.3534E+01 0.8037E*01 0.1165E+05 0.2398E+07 0.2415E+05 0.5325E+06 0.4026E+05 0.5586E+01 0.5667E+01 0.1870E+06 0.3367E+07 0.2475E+04 0.1307E+OO 0.2251E+OO 0.5118E*02 0.7422E+03 0.1517E+06 0.1528E+04 0.3370E+05 0.4026E+05 0.3558E+OO 0.3609E+OO 0.2271E+07 0.4090E+08 0.2989E+05 0.1579E+01 0.2718E+01 0.6182E*01 0.8964E+04 0.1843E+07 0.1856E+05 0.4094E+06 0.4026E+05 0.4297E+01 0.4359E+01 0.2223E+02 0.6842E+OO 0.2453E+01 0.7536E*01 0.1886E+02 0.5795E+OO 0.2849E+01 0.8739E*01 0.9906E*01 0.3042E*02 0.3228E*01 0.9888E*03 0.4118E+02 0.1267E+01 0.5334E+01

0. 1637E+OO 240 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE Kr*83m Kr-85m" CTMT. ATM.
ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) 0.1708E+07 0.1190E+01 0.1190E+01 0.1051E*01 0.1294E*01 0.1107E*02 0.1404E*02 0.8852E+07 0.6155E+01 0.6155E+01 0.1051E*01 0.1294E*01 0.1107E*02 0.1404E*02
Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 1-131 1-132 1-133 1-134 1-135 0.7586E+06 0.5268E+OO 0.5268E+OO 0.1051E-01 0.1294E-01 0.1107E-02 0.1404E-02 0.3274E+07 0.2284E+01 0.2284E+01 0.1051E-01 0.1294E-01 0.1107E-02 0.1404E-02 0.1610E+08 0.1121E+02 0.1121E+02 0.1051E-01 0.1294E-01 0.1107E-02 0.1404E-02 0.5773E-15 0.4484E-21 0.4484E-21 0.1051E-01 0.1294E-01 0.1107E-02 0.1404E-02 0.4409E+06 0.3062E+OO 0.3062E+OO 0.1051E-01 0.1294E-01 0.1107E-02 0.1404E-02 0.4689E+07 0.3256E+01 0.3256E+01 0.1051E-01 0.1294E-01 0.1107E-02 0.1404E-02 0.1398E+09 0.9706E+02 0.9706E+02 0.1051E-01 0.1294E-01 0.1107E-02 0.1404E-02 0.8153E+03 0.5792E-03 0.5792E-03 0.1051E-01 0.1294E-01 0.1107E-02 0.1404E-02 0.1824E+08 0.1267E+02 0.1267E+02 0.1051E-01 0.1294E-01 0.1107E-02 0.1404E-02 0.2061E-10 0.1568E-16 0.1568E-16 0.1051E-01 0.1294E-01 0.1107E-02 0.1404E-02 0.9167E+03 0.6524E-03 0.6524E-03 0.1051E-01 0.1294E-01 0.1107E-02 0.1404E-02 0.2032E+07 0.3660E+08 0.2685E+05 0.1411E+01 0.2430E+01 0.5552E-01 0.8050E+04 0.1649E+07 0.1661E+05 0.3663E+06 0.4026E+05 0.3842E+01 0.3897E+01 0.8698E+06 0.1566E+08 0.1152E+05 0.6055E+OO 0.1043E+01 0.2382E-01 0.3454E+04 0.7059E+06 0.7108E+04 0.1568E+06 0.4026E+05 0.1648E+01 0.1672E+01 0.2953E+07 0.5318E+08 0.3902E+05 0.2051E+01 0.3532E+01 0.8069E-01 0.1170E+05 0.2396E+07 0.2413E+05 0.5322E+06 0.4026E+05 0.5583E+01 0.5664E+01 0.1845E+06 0.3323E+07 0.2454E+04 0.1290E+OO 0.2221E+OO 0.5074E-02 0.7358E+03 0.1498E+06 0.1508E+04 0.3326E+05 0.4026E+05 0.3511E+OO 0.3562E+OO 0.2267E+07 0.4083E+08 0.2998E+05 0.1576E+01 0.2714E+01 0.6199E-01 0.8989E+04 0.1840E+07 0.1853E+05 0.4086E+06 0.4026E+05 0.4289E+01 0.4351E+01 0.2223E+02 0.6842E+OO 0.2460E+01 0.7558E-01 0.1886E+02 0.5795E+OO 0.2862E+01 0.8777E-01 0.9906E-01 0.3042E-02 0.3257E-01 0.9976E-03 0.4118E+02 0.1267E+01 0.5355E+01 0.1644E+OO TIME = 479 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK CTMT. ATM. SUMP SIRW TANK
FILE: C1MCALC.LST Created: 02/26/-:14

PAGE: 21 of 28

Length: 195230 bytes.
~~Queued: 02/26/ 6:22~~
Lines 2201 to 2310 ****************
ISOTOPE 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 1-132 1-133 1-134 1-135 ACTIVITY (Ci) ACTIVITY (Ci) ACTIVITY (Cl) 0.3870E+06 0.2696E+OO 0.2696E+OO 0.1051E-01 0.1294E-01 0.1511E-02 0.2007E-02 0.4778E+07 0.3322E+01 0.3322E+01 0.1051E-01 0.1294E-01 0.1511E-02 0.2007E-02 0.7584E+06 0.5267E+OO 0.5267E+OO 0.1051E-01 0.1294E-01 0.1511E-02 0.2007E-02 0.3701E+06 0.2582E+OO 0.2582E+OO 0.1051E-01 0.1294E-01 0.1511E-02 0.2007E-02 0.6090E+07 0.4238E+01 0.4238E+01 0.1051E-01 0.1294E-01 0.1511E-02 0.2007E-02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1511E-02 0.2007E-02 0.4366E+06 0.3032E+OO 0.3032E+OO 0.1051E-01 0.1294E-01 0.1511E-02 0.2007E-02 0.4448E+07 0.3089E+01 0.3089E+01 0.1051E-01 0.1294E-01 0.1511E-02 0.2007E-02 0.1367E+09 0.9494E+02 0.9494E+02 0.1051E-01 0.1294E-01 0.1511E-02 0.2007E-02 0.1619E-01 0.1150E-07 0.1150E-07 0.1051E-01 0.1294E-01 0.1511E-02 0.2007E-02 0.1346E+08 0.9351E+01 0.9351E+01 0.1051E-01 0.1294E-01 0.1511E-02 0.2007E-02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1511E-02 0.2007E-02 0.7868E-02 0.5600E-08 0.5600E-08 0.1051E-01 0.1294E-01 0.1511E-02 0.2007E-02 0.2003E+07 0.3604E+08 0.5508E+05 0.1391E+01 0.2396E+01 0.1138E+OO 0.1650E+05 0.1626E+07 0.1637E+05 0.3610E+06 0.4022E+05 0.3787E+01 0.3901E+01 0.2604E+06 0.4686E+07 0.7179E+04 0.1813E+OO 0.3123E+OO 0.1484E-01 0.2151E+04 0.2113E+06 0.2128E+04 0.4694E+05 0.4022E+05 0.4936E+OO 0.5084E+OO 0.2585E+07 0.4651E+08 0.7111E+05 0.1796E+01 0.3093E+01 0.1470E+OO 0.2131E+05 0.2098E+07 0.2113E+05 0.4660E+06 0.4022E+05 0.4889E+01 0.5036E+01 0.7905E+04 0.1422E+06 0.2188E+03 0.5526E-02 0.9518E-02 0.4522E-03 0.6557E+02 0.6416E+04 0.6461E+02 0.1425E+04 0.4022E+05 0.1504E-01 0.1550E-01 0.1491E+07 0.2682E+08 0.4102E+05 0.1036E+01 0.1784E+01 0.8478E-01 0.1229E+05 0.1210E+07 0.1218E+05 0.2687E+06 0.4022E+05 0.2820E+01 0.2905E+01 0.2223E+02 0.6842E+OO 0.4172E+01 0.1279E+OO 0.1886E+02 0.5795E+OO 0.5811E+01 0.1778E+OO 0.9906E-01 0.3042E-02 0.1362E+OO 0.4161E-02 0.4118E+02 0.1267E+01 0.1012E+02 0.3098E+OO
TIME = 480 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.3846E+06 0.2679E+OO 0.2679E+OO 0.1051E-01 0.1294E-01 0.1513E-02 0.2008E-02 Kr-85m 0.4766E+07 0.3314E+01 0.3314E+01 0.1051E-01 0.1294E-01 0.1513E-02 0.2008E-02 Kr-85 0.7584E+06 0.5267E+OO 0.5267E+OO 0.1051E-01 0.1294E-01 0.1513E-02 0.2008E-02 Kr-87 0.3668E+06 0.2559E+OO 0.2559E+OO 0.1051E-01 0.1294E-01 0.1513E-02 0.2008E-02 Kr-88 0.6065E+07 0.4220E+01 0.4220E+01 0.1051E-01 0.1294E-01 0.1513E-02 0.2008E-02 Kr-89 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1513E-02 0.2008E-02 Xe-131m 0.4366E+06 0.3032E+OO 0.3032E+OO 0.1051E-01 0.1294E-01 0.1513E-02 0.2008E-02 Xe-133m 0.4447E+07 0.3089E+01 0.3089E+01 0.1051E-01 0.1294E-01 0.1513E-02 0.2008E-02 Xe-133 0.1367E+09 0.9493E+02 0.9493E+02 0.1051E-01 0.1294E-01 0.1513E-02 0.2008E-02 Xe-135m 0.1547E-01 0.1099E-07 0.1099E-07 0.1051E-01 0.1294E-01 0.1513E-02 0.2008E-02 Xe-135 0.1344E+08 0.9339E+01 0.9339E+01 0.1051E-01 0.1294E-01 0.1513E-02 0.2008E-02 Xe-137 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1513E-02 0.2008E-02 Xe-138 0.7493E-02 0.5333E-08 0.5333E-08 0.1051E-01 0.1294E-01 0.1513E-02 0.2008E-02 I-131 0.2003E+07 0.3604E+08 0.5519E+05 0.1391E+01 0.2396E+01 0.1141E+OO 0.1654E+05 0.1625E+07 0.1637E+05 0.3610E+06 0.4022E+OS 0.3787E+01 0.3901E+01 I-132 0.2591E+06 0.4662E+07 0.7158E+04 0.1804E+OO 0.3107E+OO 0.1479E-01 0.2145E+04 0.2103E+06 0.2118E+04 0.4670E+OS 0.4022E+OS 0.4911E+OO 0.5059E+OO I-133 0.2584E+07 0.4649E+08 0.7122E+05 0.1795E+01 0.3091E+01 0.1472E+OO 0.2134E+05 0.2097E+07 0.2112E+OS 0.4657E+06 0.4022E+05 0.4886E+01 0.5033E+01 I-134 0.7802E+04 0.1404E+06 0.2164E+03 0.5454E-02 0.9394E-02 0.4473E-03 0.6485E+02 0.6332E+04 0.6376E+02 0.1406E+04 0.4022E+OS 0.1485E-01 0.1529E-01 1-135 0.1488E+07 0.2677E+08 0.4104E+OS 0.1034E+01 0.1781E+01 0.8481E-01 0.1230E+OS 0.1208E+07 0.1216E+OS 0.2682E+06 0.4022E+OS
~~FILE: C1MCALC.LST Created: 02/26/..~~
14
PAGE: 22 of 28

Length: 195230 bytes.
~~Queued: 02/26/~~
22
Lines 2311 to 2420 ****************
0.2815E+01 0.2223E+02 0.6842E+OO 0.4179E+01 0.1281E+OO 0.2900E+01 0.1886E+02 0.5795E+OO 0.5823E+01 0.1782E+OO 0.9906E-01 0.3042E-02 0.1368E+OO 0.4179E-02 0.4118E+02 0.1267E+01 0.1014E+02 0.3104E+OO TIME = 719 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.8716E+OS 0.6071E-01 0.6071E*01 0.1051E-01 0.1294E-01 0.1650E*02 0.2237E-02 Kr-85m 0.2573E+07 0.1789E+01 0.1789E+01 0.1051E-01 0.1294E-01 0.1650E-02 0.2237E-02
Kr-85 0.7583E+06 0.5266E+OO 0.5266E+OO 0.1051E*01 0.1294E-01 0.1650E-02 0.2237E-02 Kr-87 0.4147E+05 0.2893E-01 0.2893E-01 0.1051E-01 0.1294E-01 0.1650E-02 0.2237E-02 Kr-88 0.2294E+07 0.1596E+01 0.1596E+01 0.1051E-01 0.1294E-01 0.1650E-02 0.2237E-02 Kr-89 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1650E-02 0.2237E-02 Xe-131m 0.4323E+06 0.3002E+OO 0.3002E+OO 0.1051E-01 0.1294E-01 0.1650E-02 0.2237E-02 Xe-133m 0.4219E+07 0.2930E+01 0.2930E+01 0.1051E-01 0.1294E-01 0.1650E-02 0.2237E-02 Xe-133 0.1337E+09 0.9286E+02 0.9286E+02 0.1051E-01 0.1294E-01 0.1650E-02 0.2237E-02 Xe-135m 0.3073E-06 0.2183E-12 0.2183E-12 0.1051E-01 0.1294E-01 0.1650E-02 0.2237E-02 Xe-135 0.9918E+07 0.6892E+01 0.6892E+01 0.1051E-01 0.1294E-01 0.1650E-02 0.2237E-02 Xe-137 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1650E*02 0.2237E-02 Xe-138 0.6431E-07 0.4577E-13 0.4577E-13 0.1051E-01 0.1294E-01 0.1650E-02 0.2237E-02 1-131 0.1974E+07 0.3548E+08 0.8260E+OS 0.1371E+01 0.2362E+01 0.1706E+OO 0.2474E+05 0.1602E+07 0.1613E+05 0.3558E+06 0.4017E+05 0.3733E+01 0.3903E+01 I-132 0.7758E+OS 0.1395E+07 0.3254E+04 0.5401E-01 0.9304E-01 0.6721E-02 0.9746E+03 0.6296E+05 0.6341E+03 0.1398E+05 0.4017E+05 0.1471E+OO 0.1538E+OO I-133 0.2262E+07 0.4066E+08 0.9468E+OS 0.1571E+01 0.2707E+01 0.1956E+OO 0.2836E+05 0.1836E+07 0.1849E+05 0.4078E+06 0.4017E+05 0.4278E+01 0.4474E+01
1-134 1-135 0.3343E+03 0.6009E+04 0.1408E+02 0.2337E-03 0.4025E-03 0.2908E-04 0.4216E+01 0.2713E+03 0.2732E+01 0.6025E+02 0.4017E+05 0.6362E-03 0.6653E-03 0.9782E+06 0.1758E+08 0.4096E+05 0.6799E+OO 0.1171E+01 0.8461E-01 0.1227E+05 0.7939E+06 0.7995E+04 0.1763E+06 0.4017E+05 0.1851E+01 0.1936E+01 0.2223E+02 0.6842E+OO 0.4706E+01 0.1441E+OO 0.1886E+02 0.5795E+OO 0.6n9E+01 0.2058E+OO 0.9906E-01 0.3042E*02 0.1911E+OO 0.5834E-02 0.4118E+02 0.1267E+01 0.1163E+02 0.3558E+OO TIME = 720 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr*83m 0.8662E+05 0.6034E-01 0.6034E-01 0.1051E-01 0.1294E-01 0.16SOE-02 0.2238E-02 Kr-85m 0.2566E+07 0.1784E+01 0.1784E+01 0.1051E-01 0.1294E-01 0.1650E-02 0.2238E-02 Kr-85 0.7583E+06 0.5266E+OO 0.5266E+OO 0.1051E-01 0.1294E-01 0.1650E-02 0.2238E-02 .Kr-87 0.4109E+05 0.2867E-01 0.2867E-01 0.1051E-01 0.1294E-01 0.1650E-02 0.2238E-02 Kr-88 0.2284E+07 0.1590E+01 0.1590E+01 0.1051E-01 0.1294E-01 0.1650E-02 0.2238E-02 Kr-89 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1650E-02 0.2238E-02 Xe-131m 0.4323E+06 0.3002E+OO 0.3002E+OO 0.1051E-01 0.1294E-01 0.1650E-02 0.2238E-02 Xe-133m 0.4218E+07 0.2929E+01 0.2929E+01 0.1051E-01 0.1294E-01 0.1650E-02 0.2238E-02 Xe-133 0.1337E+09 0.9285E+02 0.9285E+02 0.1051E-01 0.1294E-01 0.1650E-02 0.2238E-02 Xe-135m 0.2937E-06 0.2086E-12 0.2086E-12 0.1051E-01 0.1294E-01 0.1650E-02 0.2238E-02 Xe-135 0.9905E+07 0.6883E+01 0.6883E+01 0.1051E-01 0.1294E-01 0.1650E-02 0.2238E-02 Xe-137 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1650E-02 0.2238E-02 Xe-138 0.6125E-07 0.4359E-13 0.4359E-13 0.1051E-01 0.1294E-01 0.1650E-02 0.2238E-02 1-131 0.1974E+07 0.3548E+08 0.8271E+05 0.1371E+01 0.2361E+01 0.1708E+OO 0.2477E+05 0.1602E+07 0.1613E+05 0.3558E+06 0.4017E+05 0.3732E+01 0.3903E+01 1-132 0.7719E+05 0.1388E+07 0.3242E+04
FILE: C1MCALC. LST Created: 02/26/

PAGE: 23 of 28

Length: 195230 bytes.
~~Queued: 02/26/9~~
Lines 2421 to 2530 *****************************
1-133 1-134 1-135 0.5374E-01 0.9257E-01 0.6265E+05 0.6309E+03 0.1463E+OO 0.1530E+OO 0.6697E-02 0.1391E+05 0.2261E+07 0.4064E+08 0.9476E+05 0.9711E+03 0.4017E+05 0.1571E+01 0.2706E+01 0.1957E+OO 0.2838E+05 0.1835E+07 0.1848E+05 0.4075E+06 0.4017E+05 0.4276E+01 0.44nE+01 0.3299E+03 0.5930E+04 0.1391E+02 0.2306E-03 0.3973E-03 0.2874E-04 0.4167E+01 0.2677E+03 0.2696E+01 0.5946E+02 0.4017E+05 0.6279E-03 0.6566E-03 0.9765E+06 0.1755E+08 0.4095E+05 0.6787E+OO 0.1169E+01 0.8458E-01 0.1226E+05 0.7925E+06 0.7981E+04 0.1760E+06 0.4017E+05 0.1848E+01 0.1933E+01 0.2223E+02 0.6842E+OO 0.4708E+01 0.1442E+OO 0.1886E+02 0.5795E+OO 0.6733E+01 0.2059E+OO 0.9906E-01 0.3042E-02 0.1913E+OO 0.5842E-02 0.4118E+02 0.1267E+01 0.1163E+02 0.3560E+OO TIME = 1439 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.9953E+03 0.6933E-03 0.6933E-03 0.1051E-01 0.1294E-01 0.1886E-02 0.2613E-02 Kr-85m 0.4015E+06 0.2792E+OO 0.2792E+OO 0.1051E-01 0.1294E-01 0.1886E-02 0.2613E-02 Kr-85 0.7579E+06 0.5263E+OO 0.5263E+OO 0.1051E-01 0.1294E-01 0.1886E-02 0.2613E-02 Kr-87 0.5831E+02 0.4068E-04 0.4068E-04 0.1051E-01 0.1294E-01 0.1886E-02 0.2613E-02 Kr-88 0.1225E+06 0.8527E-01 0.8527E-01 0.1051E-01 0.1294E-01 0.1886E-02 0.2613E-02 Kr-89 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1886E-02 0.2613E-02 Xe-131m 0.4197E+06 0.2915E+OO 0.2915E+OO 0.1051E-01 0.1294E-01 0.1886E-02 0.2613E-02 Xe-133m 0.3600E+07 0.2500E+01 0.2500E+01 0.1051E-01 0.1294E-01 0.1886E-02 0.2613E-02 Xe-133 0.1251E+09 0.8688E+02 0.8688E+02 0.1051E-01 0.1294E-01 0.1886E-02 0.2613E-02 Xe-135m O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1886E-02 0.2613E-02 Xe-135 0.3970E+07 0.2758E+01 0.2758E+01 0.1051E-01 0.1294E-01 0.1886E-02 0.2613E-02 Xe-i37
0. OOOOE+OO

0. OOOOE+OO

0. OOOOE+OO 0.1051E-01 0.1294E-01 0.1886E-02 0.2613E-02
Xe-138 1-131 1-132 1-133 1-134 1-135 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E*01 0.1294E-01 0.1886E*02 0.2613E-02 0.1890E+07 0.3387E+08 0.1604E+06 0.1312E+01 0.2262E+01 0.3307E+OO 0.4795E+05 0.1534E+07 0.1545E+05 0.3406E+06 0.4004E+05 0.3574E+01 0.3905E+01 0.2051E+04 0.3677E+05 0.1745E+03 0.1428E-02 0.2461E-02 0.3598E-03 0.5217E+02 0.1665E+04 0.1676E+02 0.3697E+03 0.4004E+05 0.3889E-02 0.4249E-02 0.1516E+07 0.2717E+08 0.1287E+06 0.1053E+01 0.1815E+01 0.2653E+OO 0.3847E+05 0.1230E+07 0.1239E+05 0.2732E+06 0.4004E+05 0.2868E+01 0.3133E+01 0.2527E-01 0.4529E+OO 0.2158E-02 0.1766E-07 0.3044E-07 0.4450E-08 0.6453E-03 0.2051E-01 0.2065E-03 0.4555E-02 0.4004E+05 0.4811E-07 0.5256E-07 0.2765E+06 0.4957E+07 0.2349E+05 0.1922E+OO 0.3313E+OO 0.4843E-01 0.7022E+04 0.2244E+06 0.2260E+04 0.4985E+05 0.4004E+05 0.5235E+OO 0.5719E+OO 0.2223E+02 0.6842E+OO 0.6180E+01 0.1890E+OO 0.1886E+02 0.5795E+OO 0.9270E+01 0~2831E+OO 0.9906E-01 0.3042E-02 0.46nE+OO 0.1423E-01 0.4118E+02 0.1267E+01 0.1592E+02 0.4863E+OO TIME = 1440 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.9891E+03 0.6890E-03 0.6890E-03 0.1051E-01 0.1294E-01 0.1886E-02 0.2614E-02 Kr-85m 0.4005E+06 0.2785E+OO 0.2785E+OO 0.1051E*01 0.1294E-01 0.1886E-02 0.2614E-02 Kr-85 0.7579E+06 0.5263E+OO 0.5263E+OO 0.1051E-01 0.1294E-01 0.1886E*02 0.2614E-02 Kr-87 0.5778E+02 0.4031E-04 0.4031E-04 0.1051E*01 0.1294E-01 0.1886E-02 0.2614E-02 Kr-88 0.1220E+06 0.8492E-01 0.8492E-01 0.1051E-01 0.1294E-01 0.1886E-02 0.2614E-02 Kr-89 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1886E-02 0.2614E-02 Xe-131m 0.4197E+06 0.2915E+OO 0.2915E+OO 0.1051E-01 0.1294E-01 0.1886E-02 0.2614E-02 Xe-133m 0.3599E+07 0.2499E+01 0.2499E+01 0.1051E-01 0.1294E-01 0.1886E*02 0.2614E-02 Xe-133 0.1251E+09 0.8688E+02 0.8688E+02
~~FILE: C1MCALC.LST Created: 02/26/~~
~~.:14~~
PAGE: 24 of 28

Length: 195230 bytes.
~~Queued: 02/26/9~~
Lines 2531 to 2640 ****************
~~22 0.1051E-01 0.1294E*01 0.1886E-02 0.2614E*02~~
Xe-135m O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E*01 0.1886E*02 0.2614E-02 Xe-135 0.3965E+07 0.2755E+01 0.2755E+01 0.1051E*01 0.1294E*01 0.1886E*02 0.2614E-02 Xe-137 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E*01 0.1886E-02 0.2614E-02 Xe-138 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1886E*02 0.2614E-02 1*131 0.1890E+07 0.3387E+08 0.1605E+06 0.1312E+01 0.2262E+01 0.3309E+OO 0.4798E+05 0.1534E+07 0.1544E+05 0.3406E+06 0.4004E+05 0.3574E+01 0.3905E+01 1-132 0.2041E+04 0.3658E+05 0.1737E+03 0.1421E-02 0.2449E*02 0.3582E-03 0.5194E+02 0.1656E+04 0.1668E+02 0.3679E+03 0.4004E+05 0.3870E-02 0.4228E-02 1-133 0.1515E+07 0.2715E+08 0.1287E+06 0.1052E+01 0.1814E+01 0.2653E+OO 0.3847E+05 0.1230E+07 0.1238E+05 0.2731E+06 0.4004E+05 0.2866E+01 0.3131E+01 1-134 0.2494E-01 0.4470E+OO 0.2132E*02 0.1743E-07 0.3005E-07 0.4395E-08 0.6373E*03 0.2024E-01 0.2038E*03 0.4495E-02 0.4004E+05 0.4748E-07 0.5187E-07 1-135 0.2761E+06 0.4948E+07 0.2346E+05 0.1919E+OO 0.3307E+OO 0.4838E-01 0.7014E+04 0.2240E+06 0.2256E+04 0.4976E+05 0.4004E+05 0.5226E+OO 0.5710E+OO 0.2223E+02 0.6842E+OO 0.6182E+01 0.1890E+OO 0.1886E+02 0.5795E+OO 0.9274E+01 0.2832E+OO 0.9906E-01 0.3042E*02 0.4677E+OO 0.1425E*01 0.4118E+02 0.1267E+01 0.1592E+02 0.4865E+OO TIME = 1799 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM.
ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.1064E+03 0.3705E-04 0.3705E*04 0.1051E-01 0.1294E*01 0.1904E-02 0.2636E-02 Kr-85m 0.1587E+06 0.5516E*01 0.5516E*01 0.1051E-01 0.1294E-01 0.1904E*02 0.2636E-02 Kr-85 0.7577E+06 0.2631E+OO 0.2631E+OO 0.1051E-01 0.1294E-01 0.1904E-02 0.2636E*02 Kr-87 0.2187E+01 0.7628E-06 0.7628E-06 0.1051E-01 0.1294E-01 0.1904E-02 0.2636E-02 Kr-88 0.2833E+05 0.9856E-02 0.9856E-02 0.1051E-01 0.1294E-01 0.1904E-02 0.2636E*02
FILE: C1MCALC.LST Created: 02/26/

PAGE: 25 of 28

Length: 195230 bytes.
~~Queued: 02/26/~~
Lines 2641 to 2750 *****************************
Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 1-131 1-132 1-133 1-134 1-135 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1904E-02 0.2636E-02 0.4136E+06 0.1436E+OO 0.1436E+OO 0.1051E-01 0.1294E-01 0.1904E-02 0.2636E-02 0.3325E+07 0.1155E+01 0.1155E+01 0.1051E-01 0.1294E-01 0.1904E-02 0.2636E-02 0.1210E+09 0.4203E+02 0.4203E+02 0.1051E-01 0.1294E-01 0.1904E-02 0.2636E-02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1904E-02 0.2636E-02 0.2512E+07 0.8727E+OO 0.8727E+OO 0.1051E-01 0.1294E-01 0.1904E-02 0.2636E-02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1904E-02 0.2636E-02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.1904E-02 0.2636E-02 0.1849E+07 0.3314E+08 0.1571E+06 0.6421E+OO 0.2214E+01 O.OOOOE+OO 0.4696E+05 .0.1501E+07 0.1511E+05 0.3333E+06 0.4002E+05 0.2856E+01 0.2856E+01 0.3336E+03 0.5977E+04 0.2840E+02 0.1161E-03 0.4003E-03 O.OOOOE+OO 0.8491E+01 0.2707E+03 0.2726E+01 0.6013E+02 0.4002E+05 0.5164E-03 0.5164E-03 0.1241E+07 0.2224E+08 0.1054E+06 0.4310E+OO 0.1486E+01 O.OOOOE+OO 0.3152E+05 0.1007E+07 0.1014E+05 0.2237E+06 0.4002E+05 0.1917E+01 0.1917E+01 0.2197E-03 0.3937E-02 0.1878E-04 0.7680E-10 0.2648E-09 O.OOOOE+OO 0.5616E-05 0.1783E-03 0.1796E-05 0.3961E-04 0.4002E+05 0.3416E-09 0.3416E-09 0.1471E+06 0.2635E+07 0.1250E+05 0.5111E-01 0.1762E+OO O.OOOOE+OO 0.3737E+04 0.1193E+06 0.1202E+04 0.2651E+05 0.4002E+05 0.2273E+OO 0.2273E+OO 0.2223E+02 0.6842E+OO 0.6351E+01 0.1942E+OO 0.1886E+02 0.5795E+OO 0.9855E+01 0.3009E+OO 0.9906E-01 0.3042E-02 0.4677E+OO 0.1425E-01 0.4118E+02 0.1267E+01 0.1667E+02 0.5093E+OO TIME = 1800 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE. CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.1057E+03 0.3682E-04 0.3682E-04 0.1051E-01 0.1294E-01 0.1904E-02 0.2636E-02 Kr-85m 0.1582E+06 0.5502E-01 0.5502E-01 Kr-85 Kr-87 Kr-88 Kr-89 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 1-131 1-132 1-133 1-134 1-135 0.1051E-01
0. 7577E+06 0.1051E-01 0.2167E+01 0.1051E-01 0.2821E+05 0.1051E-01 O.OOOOE+OO 0.1051E-01 0.4136E+06 0.1051E-01 0.3325E+07 0.1051E-01 0.1210E+09 0.1051E-01 O.OOOOE+OO 0.1051E-01 0.2509E+07 0.1051E-01 O.OOOOE+OO 0.1051E-01 O.OOOOE+OO 0.1051E-01 0.1849E+07 0.6421E+OO 0.1501E+07 0.2856E+01 0.3319E+03 0.1155E-03 0.2694E+03 0.5138E-03 0.1240E+07 0.4308E+OO D.1007E+07 0.1916E+01 0.2169E-03 0.7580E-10 0.1760E-03 0.3371E-09 0.1468E+06 0.5102E-01 0.1191E+06 0.2269E+OO 0.2223E+02 0.6842E+OO 0.6351E+01 0.1942E+OO 0.1294E-01 0.2631E+OO 0.1294E-01 0.7558E-06 0.1294E-01 0.9816E-02 0.1294E-01 O.OOOOE+OO 0.1294E-01 0.1436E+OO 0.1294E-01 0.1154E+01 0.1294E-01 0.4202E+02 0.1294E-01 O.OOOOE+OO 0.1294E-01 0.8716E+OO 0.1294E-01 O.OOOOE+OO 0.1294E-01 O.OOOOE+OO 0.1294E-01 0.3313E+08 0.2214E+01 0.1511E+05 0.2856E+01 0.5947E+04 0.3983E-03 0.2712E+01 0.5138E-03 0.2222E+08 0.1485E+01 0.1014E+05 0.1916E+01 0.3886E-02 0.2613E-09 0.1772E-05 0.3371E-09 0.2630E+07 0.1759E+OO 0.1200E+04 0.2269E+OO 0.1886E+02 0.5795E+OO 0.9857E+01 0.3009E+OO 0.1904E-02 0.2631E+OO 0.1904E-02 0.7558E-06 0.1904E-02 0.9816E-02 0.1904E-02 O.OOOOE+OO 0.1904E-02.
0.1436E+OO 0.1904E-02 0.1154E+01 0.1904E-02 0.4202E+02 0.1904E-02 O.OOOOE+OO 0.1904E-02 0.8716E+OO 0.1904E-02 O.OOOOE+OO 0.1904E-02 O.OOOOE+OO 0.1904E-02 0.1570E+06 O.OOOOE+OO 0.3333E+06 0.2826E+02 O.OOOOE+OO 0.5982E+02 0.1054E+06 O.OOOOE+OO 0.2236E+06 0.1854E-04 O.OOOOE+OO 0.3909E-04 0.1248E+05 O.OOOOE+OO 0.2646E+05 0.9906E-01 0.3042E-02 0.4677E+OO 0.1425E-01 TIME = 5759 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK 0.2636E-02 0.2636E-02 0.2636E-02 0.2636E-02 0.2636E-02 0.2636E-02 0.2636E-02 0.2636E-02 0.2636E-02 0.2636E-02 0.2636E-02 0.2636E-02 0.4695E+05 0.4002E+05 0.8448E+01 0.4002E+05 0.3150E+05 0.4002E+05 0.5542E-05 0.4002E+05 0.3730E+04 0.4002E+05 0.4118E+02 0.1267E+01 0.1668E+02 0.5094E+OO Q ~fl '° ~ m r.; r ~.
ISOTOPE 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 1-132 1-133 1-134 1-135 CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) 0.2211E-08 0.7700E-15 0.7700E-15 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 0.5814E+01 0.2021E-05 0.2021E-05 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 0.7563E+06 0.2626E+OO 0.2626E+OO 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 0.4514E-15 0.1575E-21 0.1575E-21 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 0.2854E-02 0.9930E-09 0.9930E-09 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 0.3520E+06 0.1222E+OO 0.1222E+OO 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 0.1391E+07 0.4829E+OO 0.4829E+OO 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 0.8406E+08 0.2919E+02 0.2919E+02 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 0.1635E+05 0.5681E-02 0.5681E-02 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 0.1457E+07 0.2600E+08 0.1239E+06 0.5059E+OO 0.1747E+01. O.OOOOE+OO 0.3705E+05 0.1182E+07 0.1191E+05 0.2626E+06 0.3981E+05 0.2252E+01 0.2252E+01 0.7017E-06 0.1252E-04 0.5983E-07 0.2443E-12 0.8433E-12 O.OOOOE+OO 0.1789E-07 0.5695E-06 0.5735E-08 0.1265E-06 0.3981E+05 0.1088E-11 0.1088E-11 0.1374E+06 0.2452E+07 0.1169E+05 0.4772E-01 0.1647E+OO O.OOOOE+OO 0.3494E+04 0.1115E+06 0.1123E+04 0.2477E+05 0.3981E+05 0.2125E+OO 0.2125E+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3981E+05 O.OOOOE+OO O.OOOOE+OO 0.1414E+03 0.2523E+04 0.1203E+02 0.4913E-04 0.1696E-03 O.OOOOE+OO 0.3597E+01 0.1147E+03 0.1155E+01 0.2548E+02 0.3981E+05 0.2187E-03 0.2187E-03 0.2223E+02 0.6842E+OO 0.7879E+01 0.1886E+02 0.5795E+OO 0.1513E+02 0.9906E-01 0.3042E-02 0.4677E+OO 0.4118E+02 0.1267E+01 0.2347E+02
~~FILE: C1MCALC.LST Created: 02/26/~~
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Length: 195230 bytes.
~~Queued: 02/26/9~~
22
~~Lines 2751 to 2860 0.2406E+OO 0.4610E+OO 0.1425E-01 0.7158E+OO TIME = 5760 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM.~~
~~ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m 0.2197E-08~~
~~0. 7652E-15 O. 7652E-15 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 Kr-85m 0.5799E+01 0.2016E-05~~
. 0.2016E-05 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 Kr-85 0.7563E+06 0.2626E+OO 0.2626E+OO 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 Kr-87 0.4473E-15 0.1560E-21 0.1560E-21 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 Kr-88 0.2842E-02 0.9889E-09 0.9889E-09 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 Kr-89 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 Xe-131m 0.3520E+06 0.1222E+OO 0.1222E+OO 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 Xe-133m 0.1390E+07 0.4828E+OO 0.4828E+OO 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 Xe-133 0.8406E+08 0.2919E+02 0.2919E+02 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 Xe-135m
0. OOOOE+OO

0. OOOOE+OO

0. OOOOE+OO 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 Xe-135 0.1633E+05 0.5673E-02 0.5673E-02 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 Xe-137 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2059E-02 0.2774E-02 Xe-138 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E*01 0.2059E*02 0.2774E-02 1*131 0.1457E+07 0.2600E+08 0.1239E+06 0.5059E+OO 0.1746E+01 O.OOOOE+OO 0.3704E+05 0.1182E+07 0.1191E+05 0.2626E+06 0.3981E+05 0.2252E+01 0.2252E+01 I* 132 0.6982E*06 0.1246E*04 0.5952E*07 0.2430E-12 0.8390E*12 O.OOOOE+OO 0.1780E*07 0.5666E-06 0.5706E*08 0.1258E-06 0.3981E+05 0.1082E*11 0.1082E*11 1*133 0.1373E+06 0.2451E+07 0.1168E+05 0.4770E*01 0.1647E+OO O.OOOOE+OO 0.3492E+04 0.1114E+06 0.1122E+04 0.2475E+05 0.3981E+05 0.2123E+OO 0.2123E+OO 1*134 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3981E+05 O.OOOOE+OO O.OOOOE+OO 1*135 0.1411E+03 0.2519E+04 0.1201E+02 0.4904E-04 0.1693E*03 O.OOOOE+OO 0.3591E+01
0.1145E+03 0.1153E+01 0.2544E+02 0.3981E+OS 0.2183E-03 0.2183E-03 0.2223E+02 0.1886E+02 0.9906E-01 0.4118E+02 0.6842E+OO 0.5795E+OO 0.3042E-02 0.1267E+01 0.7880E+01 0.1513E+02 0.4677E+OO 0.2348E+02 0.2406E+OO 0.4610E+OO 0.1425E-01 0.7158E+OO TIME = 43199 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Kr-85m O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Kr-85 0.7431E+06 0.2580E+OO 0.2580E+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Kr-87 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Kr-88 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Kr-89 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Xe-131m 0.7662E+05 0.2660E-01 0.2660E-01 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Xe-133m 0.3661E+03 0.1271E-03 0.1271E-03 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Xe-133 0.2680E+07 0.9305E+OO 0.9305E+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Xe-135m O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Xe-135 0.3479E-16 0.1209E-22 0.1209E-22 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Xe-137 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Xe-138 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 1-131 0.1529E+06 0.2626E+07 0.1318E+05 0.5310E-01 0.1857E+OO O.OOOOE+OO 0.3939E+04 0.1241E+06 0.1250E+04 0.2757E+05 0.3781E+05 0.2388E+OO 0.2388E+OO 1-132 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3781E+05 O.OOOOE+OO O.OOOOE+OO 1-133 0.1263E-03 0.2169E-02 0.1089E-04 0.4388E-10 0.1535E-09 O.OOOOE+OO
0.3255E-05 0.1025E-03 0.1033E-05 0.2277E-04 0.3781E+05

FILE: C1MCALC.LST Created: 02/26/.:14

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Length: 195230 bytes.
~~Queued: 02/26/ ~:22~~
Lines 2861 to 2970 ****************
1-134 1-135 0.1973E-09 0.1973E-09 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3781E+05 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3781E+OS O.OOOOE+OO O.OOOOE+OO 0.2223E+02 0.6842E+OO 0.9052E+01 0.2762E+OO 0.1886E+02 0.5795E+OO 0.1919E+02 0.5843E+OO 0.9906E-01 0.3042E-02 0.4677E+OO 0.1425E-01 0.4118E+02 0.1267E+01 0.2871E+02 0.8747E+OO TIME = 43200 MIN ACTIVITY IN CONTAINMENT AND SIRW TANK ISOTOPE CTMT. ATM. ACTIVITY (Ci) SUMP ACTIVITY (Ci) SIRW TANK ACTIVITY (Cl) Kr-83m O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Kr-85m O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Kr-85 0.7431E+06 0.2580E+OO 0.2580E+OO 0.1051E-01 0.1294E-01 0.2142E-02 . 0.2840E-02 Kr-87 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Kr-88 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Kr-89 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Xe-131m 0.7661E+05 0.2660E-01 0.2660E-01 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Xe-133m 0.3660E+03 0.1271E-03 0.1271E-03 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Xe-133 0.2679E+07 0.9304E+OO 0.9304E+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Xe-135m
0. OOOOE+OO

0. OOOOE+OO

0. OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Xe-135 0.3474E-16 0.1207E-22 0.1207E-22 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Xe-137 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 Xe-138 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.1051E-01 0.1294E-01 0.2142E-02 0.2840E-02 1-131 0.1529E+06
. 0.2626E+07 0.1318E+OS 0.5310E-01 0.1857E+OO O.OOOOE+OO 0.3939E+04 0.1241E+06 0.1250E+04 0.2756E+05 0.3781E+05 0.2388E+OO 0.2388E+OO
1-132 1-133 1-134 1-135 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3781E+05 O.OOOOE+OO O.OOOOE+OO 0.1263E-03 0.2168E-02 0.1088E-04 0.4386E-10 0.1534E-09 O.OOOOE+OO 0.3253E-05 0.1025E-03 0.1032E-05 0.2276E-04 0.3781E+05 0.1972E-09 0.1972E-09 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3781E+05 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO 0.3781E+05 O.OOOOE+OO O.OOOOE+OO 0.2223E+02 0.6842E+OO 0.9052E+01 0.2762E+OO 0.1886E+02 0.5795E+OO 0.1919E+02 0.5843E+OO 0.9906E-01 0.3042E-02 0.4677E+OO 0.1425E-01 0.4118E+02 v 0.1267E+01 0.2871E+02 0.8747E+OO TOTAL ACTIVITY OF EACH RADIONUCLIDE RELEASED (Ci) ISOTOPE CTMT ATM ESF ROOMS SIRW TANK 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 1-132 1-133 1-134 1-135 0.8479E+03 0.4372E+04 0.1164E+05 0.2225E+04 0.7287E+04 0.1591E+03 0.3357E+04 0.9911E+04 0.5956E+06 0.6586E+03 0.1243E+05 0.4592E+03 0.1596E+04 0.1211E+05 0.5637E+03 0.3464E+04 0.4562E+03 0.1510E+04 0.3804E+05 0.6287E+03 0.7188E+04 0.3082E+03 0.2278E+04 0.2425E+03 0.1283E+02 0.2503E+03 0.2434E+01 0.9540E+02 RESULTANT OFFSITE DOSES FROM THE EVENT (Rem) CTMT ESF SIRWT ATM LEAKAGE LEAKAGE TOTAL 0-2 Hr SB Thyroid (inhalation) 22.226 18.858 0.099 41.183 Thyroid (submersion) 0.011 N/A N/A 0.011 i/ ii
FILE: C1MCALC.LST Created: 02/26/

PAGE: 28 of 28

Length: 195230 bytes.
~~Queued: 02/26/9~~
Lines 2971 to 3063 *****************************
Total Thyroid Dose = 22.237 18.858 0.099 41.193 CEDE (inhalation) 0.684 0.579 0.003 1.267.v"' Whole Body Dose 0.013 N/A N/A 0.013 TEDE (whole body eq) 0.697 0.579 0.003 1.280 0-30 Day LPZ Thyroid (inhalation) 9.052 19.193 0.468 28.713 Thyroid (submersion) 0.002 N/A N/A 0.002 Total Thyroid Dose = 9.054 19.193 0.468 28.715 CEDE (inhalation) 0.276 0.584 0.014 l*t 0.8;;*.\\ Whole Body Dose 0.003 N/A N/A 0.003 TEDE (whole body eq) 0.279 0.584 0.014 1.270 TIME AT WHICH DFmax OR THE SPRAY STOP TIME WAS REACHED = 421 MINUTES
This is the console file for job JOB8486(8486). ***
TIME IS 17:36:25 EDT WEDNESDAY 02/26/92 CONNECT= 00:00:04 VIRTCPU= 000:00.10 TOTCPU= 000:00.26 DASO 120 LINKED R/O; R/W BY SDWINTER; R/0 BY VMBAT001 DMSACP7231 X (120) R/O DMSACP7231 W (121) R/0 DMSLI07401 Execution begins *** MHA RUN COMPLETED TIME IS 17:44:30 EDT WEDNESDAY 02/26/92 CONNECT= 00:08:09 VIRTCPU= 003:25.23 TOTCPU= 003:27.39}}

ML18058A406

Contents

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SUMMARY

2.0 REFERENCES

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Subject:

Subject:

3.0 BACKGROUND

SUMMARY

12.0 CONCLUSION

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ML18058A406

Text

SUMMARY

2.0 REFERENCES

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Subject:

Subject:

3.0 BACKGROUND

SUMMARY

12.0 CONCLUSION

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