ML053220158

Calculation CA06422, Primary and Secondary Isotopic Calculations Rev 000

ML053220158
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Site:	Calvert Cliffs
Issue date:	11/03/2005
From:	Constellation Energy Group
To:	Office of Nuclear Reactor Regulation
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CA06422, Rev 000
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CA06422 Primary and Secondary Isotopic Calculations Calvert Cliffs Nuclear Power, Inc.

November 3, 2005

EN-1-100 Forms Appendix Revision 3 ESP No.: ES200100401 Supp No. 000 Rev. No. 000 Page 1 of 1 FORM 19, CALCULATION COVER SHEET A. INITIATION (Control Doc Type - DCALC) Page 1 of 46 DCALCNo.: CA06422 Revision No.: 000 Vendor-Calculation (Check one): [l Yes 3 No Responsible Group: FOSU Responsible Engineer: Gerard E. Gryczkowski B. CALCULATION ENGINEERING El Civil El Instr & Controls 3 Nuc Engrg DISCIPLINE: El Electrical El Mechanical El Nuc Fuel Mngmt El Other: a Reliability Engrg

Title:

PRIMARY AND SECONDARY ISOTOPIC CALCULATIONS Unit El 1 [l 2 l COMMON Proprietary or Safeguards Calculation E YES A NO Comments: NA Vendor Calc No:: NA . REVISION No.: NA Vendor Name: NA Safety Class (Check one): - SR El AQ a NSR There are assumptions that require Verification during walkdbWn AIT #: NA This calculation SUPERSEDES: NA C. REVIEW AND APPROVAL:

Responsible Engineer: Gerard E. Gryczkowski 3/11/2005 Printed andXDate Independent Reviewer John. R. Massari (/z 0/2/.o Ian M. Sommrnerville Printed Namen). Signat e Date Approval: Phillip I. Wengloski Printed Namrne and Sigfature Date IF the results or conclusions of this calculation or revision might affect a procedure or the basis of a procedure, a Change Notification Form (Form 14) shall be forwarded to the Procedure Development Unit with a summary of the calculation's purpose and results.

t-- -. ,

C.:. *. .:

Rev.0 CA 06422 CA 06422 Rev. 0 Page I of 46 Primary and Secondary Isotopic Calculations

CA 06422 Rev.O Page 2 of 46

2. LIST OF EFFECTIVE PAGES Page Latest Page Latest Page Latest Page Latest Page Latest Rev Rev Rev Rev Rev 001 0 002 0 003 0 004 0 005 0 006 0 007 0 008 0 009 0 010 0 011 0 012 0 013 0 014 0 015 0 016 0 017 0 018 0 019 0 020 0 021 0 022 0 023 0 024 0 025 0 026 0 027 0 028 0 029 0 030 0 031 0 032 0 033 0 034 0 035 0 036 0 037 0 038 0 039 0 040 0 041 0 042 0 043 0 044 0 045 0 046 0

CA06422 Rev.0 Page 3 of 46

3. REVIEWER COMMENTS John Mlassari comments:

(I) RCS 1% Failed Fuel Iodine Activity Fraction (DEQI131-pri, column H) is directly related to the iodine activity fraction in the gap/initial spike rather than an RCS equilibrium for 1% failed fuel. Reg. Guide 1.183 App. E and F section 2.2 call for the use of equilibrium values, and this appears to have been done in the Fort Calhoun submittal (see Ref. 9, pp. 6-8). Fort Calhoun's method for generating these equilibrium activity fractions considered sources of iodine such as leakage from 1% failed fuel and decay of parent and second parent isotopes (Te and Sb), and iodine depletion by decay, purification and neutron absorption. The fraction of the short lived I-134 is much lower in their calculations, which causes I-131 and I-133 to be a higher fraction of the equilibrium iodine activity. An RCS equilibrium activity method similar to Fort Calhoun's was used here for CA05994, and has been applied as a check (peak 1% failure of 5% VAP fuel; neutron absorption and grandparent decay were ignored). The results are consistent with those of Fort Calhoun. Response: Corrected (2) Comment #1 also applies to the iodine activity fractions utilized for the Secondary Iodine Activities (DEQ131-Sec, Column I). Similarly, the noble gas 1% failed fuel RCS activities (NG-pri, Column I) do not appear to be representative of RCS equilibrium conditions (note Xe-133 and Xe-138 RCS activities vs. UFSAR 14.22; Xe-138 has a very short half-life and should not have a concentration similar to Xe-1 33 under RCS equilibrium conditions).

Response: Corrected (3) Reference 13 is not easily retrievable. Response: See Reference 13 (4) The formula for Column G and H for the primary iodine and noble gas activity assumes two removal processes with 100% efficiency, decay and purification. This is true for the former, but not the latter (unless all letdown flow is diverted to the waste processing system). F(i) should be multiplied by a factor of (1-1/DFi) and there should be an additional factor of (I/DFi)*(feed/bleed fraction of F(i))*F(i). For the CVCS purification ion exchanger, NUREG-0017 (Table 1-4) allows a DF 100 for anions, I for noble gases, 2 for Cs and Rb, and 50 for other nuclides. This shouldn't really change your results for iodines. However, it may make a significant difference in noble gases since the ion exchangers do nothing to remove noble gases and the only removal mechanism other than decay is feed-and-bleed. Note however that while the above mentioned change produces a higher RCS noble gas activity with I%

failed fuel (following the branching fraction change discussed below) and is more consistent with FCS and previous CCNPP calculations, it produces a less conservative 100/Ebar OCi/gm because the relative contribution of Kr-88 is lower (i.e., the present method is inaccurate but conservative with regards to the final result). Response: Corrected (5) On page 8, the description of Frcs should be changed from "two" charging pumps to "1.5". Response: Corrected (6) In the primary noble gas sheet and the decay chains on page I1, the assumption that the branching fractions are I for all isotopes causes some equilibrium activities to be miscalculated. For example, it is assumed that 100% of the 1-135 decays to Xe-135m. However, only 15% of I-135 decays to Xe-135m, and the rest decays directlyto Xe-135.

Similarly, only 3% of 1-133 decays to Xe-133m, and the rest decays directly to Xe-133. Finally, only 21% of Kr-85m decays to Kr-85, but this doesn't have a significant impact on the Kr-85 equilibrium activity. This is also the case on the iodine spreadsheet with Te-131m as 78% of that decays directly to 1-13 1, but will not significantly impact the calculated 1-131 equilibrium value. Response: Corrected (7) In column M on the noble gas spreadsheet, the gamma energy for Xe-133m is listed as 0.03 MeV/dis. Lamarsh table 11.3 indicates it is 0.326 MeV/dis. All other values agree with those given in Lamarsh. You may want to check this one. I'm not sure that Lamarsh is correct since a few other references I consulted seem to support the 0.03 MeV/dis value. Response: The 0.03 value is consistent with LOCADOSE. AXIDENT. and iur previous licensing basis. In addition, use of 0.03 makes Ebar smaller. and thus l/Ebar larmer. thus more conservative.

(8) The spreadsheet should show what the actual value of Ebar and 100/Ebar [lCi/gm is based on the 1% failed fuel isotope distribution, and provide a sum of the OCi/gm at the bottom of column Q. The OCi/gm values listed in

CA 06422 Rev.0 Page 4 of 46 column Q do indeed sum to the 100/Ebar OCi/gm value, but this change will help future readers come to that conclusion more readily. Response: OK (9) Change "GIS" in the iodine spreadsheet to "CIS". Response: OK (10) Eliminate extraneous sheets from the Excel file with similar names to those used in the calc to avoid confusion.

Response: OK Ian Sommerville comments:

(1) p. 10 & notes to Table 2; The calculation for Rs appears to be incorrect; the value should be 11.78, not 117.8.

It is recommended that the calculation be performed in the spreadsheet.

Response: Corrected (2) It is recommended that a bold border be placed around the final results.

Response: OK (3) p. 11; Column G is for the SG, not the RCS Response: Corrected

- -

CA 06422 Rev. 0 Page 5 of 46

4. TABLE OF CONTENTS

01. COVER SHEET 01

02. LIST OF EFFECTIVE PAGES 02

03. REVIEWER COMMENTS 03

04. TABLE OF CONTENTS 05

05. INTRODUCTION 06

06. INPUT DATA, TECHNICAL ASSUMPTIONS, AND METHOD OF ANALYSIS 07

07. REFERENCES 14

08. DOCUMENTATION OF COMPUTER CODES 15

09. CALCULATIONS, RESULTS, AND CONCLUSIONS 16

10. ATTACHMENTS 21 ATTACHMENT A: PROGRAM SAS2HED3 21 ATTACHMENT B: FILE CRCB.SED 29 ATTACHMENT C: FILE CRCB.PUN 38 ATTACHMENT D: UNUSED .45 LAST PAGE OF REPORT 46

CA 06422 Rev.0 Page 6 of 46

5. INTRODUCTION Regulatory Guides 1.183 and 1.195 (Refs. 1-2) require that if no or minimal fuel damage is postulated for a particular design basis accident, the activity released should be the maximum coolant activity allowed by the technical specifications or the maximum coolant activity generated by a preexisting or concurrent iodine spike.

Calvert Cliffs Technical Specification 3.4.15 requires that in Modes I and 2 and in Mode 3 with RCS average temperature greater than 5000 F that the Dose Equivalent 1-131 (DEQ I-131) in the primary system be less than I pCi/gm and that the noble gas activity be less than 100/Ebar pCi/gm.

Calvert Cliffs Technical Specification 3.7.14 requires that in Modes 1-4 that the Dose Equivalent 1-131 (DEQ 1-131) in the secondary system be less than 0.1 pCi/gm.

Figure 3.4.15-1 of TS 3.4.15 allows the Dose Equivalent I-131 (DEQ I-131) to be less than 60 pCi/gm in the primary system for up to 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> at hot full power. This is the basis for the Preaccident Iodine Spike PIS, where a reactor trip has occurred prior to the postulated design basis accident and has raised the primary coolant iodine concentration to the maximum value permitted by the technical specifications.

The primary system transient associated with the Main Steam Line Break (MSLB) causes an iodine spike in the primary system. The increase in primary coolant iodine concentration is estimated using a spiking model (Concurrent Iodine Spike CIS) that assumes that the iodine release rate from the fuel rods to the primary coolant (expressed in Curies per unit time) increases to a value 500 times greater than the release rate corresponding to the iodine concentration at the equilibrium value (I uCi/gm DEQ 1-131 per TS 3.4.15). The assumed iodine spike duration should be 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per Refs.1-2. A CIS need not be considered if fuel damage is postulated for the MSLB.

The primary system transient associated with the Steam Generator Tube Rupture (SGTR) causes an iodine spike in the primary system. The increase in primary coolant iodine concentration is estimated using a spiking model (Concurrent Iodine Spike CIS) that assumes that the iodine release rate from the fuel rods to the primary coolant' (expressed in Curies per unit time) increases to a value 335 times greater than the release rate corresponding to the iodine concentration at the equilibrium value (I pCi/gm DEQ 1-131 per TS 3.4.15). The assumed iodine spike duration should be 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per Refs. 1-2. A CIS need not be considered if fuel damage is postulated for the SGTR.

Calculation of the primary iodine activities for 1% failed fuel, for a peak iodine level of I DEQ-1131 pCi/gm per Technical Specification (TS) 3.4.15, for a preaccident iodine spike (PIS) of 60 DEQ-1131 pCi/gm per TS 3.4.15, for a concurrent iodine spike (CIS) of 500 per Regulatory Guides 1.183 and 1.195 (Refs.1-2), and for a CIS of 335 per Regulatory Guides 1.183 and 1.195 (Refs.1-2) is detailed in Table 1. The iodine activities for the 1% failed fuel case, for the peak iodine level of I DEQ-1131 uCi/gm case, and for the PIS of 60 DEQ-4131 uCi/gm case are distributed instantaneously and homogeneously throughout the primary coolant at the beginning of the accident. For the CIS cases, the iodine activities can be released homogeneously and continuously over the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> accident duration, at the beginning of the accident, or in steps spanning the accident duration. Calculation of the secondary iodine activities for a peak iodine level of 0.1 DEQ-1131 pCi/gm per TS 3.7.14 is depicted in Tables 2 and 3. These iodine activities are distributed instantaneously and homogeneously throughout the secondary coolant at the beginning of the accident. Calculation of the primary noble gas activities for 1% failed fuel and for a peak noble gas level of 100/Ebar pCi/gm per TS 3.4.15 is shown in Table 4. The noble gas activities for these cases are distributed instantaneously and homogeneously throughout the primary coolant at the beginning of the accident.

CA 06422 Rev.O Page 7 of 46

6. INPUT DATA, TECHNICAL ASSUMPTIONS, AND METHOD OF ANALYSIS (6.1) SAS2H Edit Code:

The SAS2H/ORIGEN-S libraries include 689 light elements, such as clad and structural materials, 129 actinides, including fuel nuclides and their decay and activation products, and 879 fission product nuclides. It was necessary to generate SAS2H isotopics as a function of loading pattern, burnup, and enrichment; to edit each output for the specified number of actinide and fission product values; to convert the isotopic content from moles to curies/mwth; and to create a summary punch file of the results. This laborious task was simplified by writing the FORTRAN programs SAS2HED3, which accomplished all of the above.

The FORTRAN code listing for SAS2HED3.FOR is included in Attachment A. The program can be compiled and linked via the FORT51 and LINKSI batch files. A copy of FORT51.BAT and LINK51.BAT are included on the accompanying CDROM. The program executable file SAS2HED3.EXE is executed on DOS. The program queries the user for the 8 character SAS2HED3 input file name (e.g. xxxx.SED).

The SAS2HED3 program reads the following data from the input SED file (e.g. See Attachment B):

(1) The 8 character name of the summary punch file generated by SAS2HED3 (e.g. xxxx.PUN - Attachment C) in Format A8.

(2) An 8 character name in Format A8 (Not used in this program).

(3) An 8 character name in Format A8 (Not used in this program).

(4) The 8 chiiacter name of the SAS2H output file (e.g. xxxx.OUT) in Format A8.

(5) The reactor power POWER in MWth.

(6) The number of burnup steps in each of the three cycles of the SAS2H output (N1, N2, N3). The total number of burnup steps NT should correspond to the total number of burnup steps in the SAS2H execution.

(7) The number of assemblies in each of the three batches, each corresponding to a cycle (NAl, NA2, NA3). The total NAT should equal 217.

(8) 592 lines of a sample Nuclear Inventory File ANIF(K). (Not used in this program).

The SAS2HED3 program performs the following functions:

(1) SAS2HED3 edits the number of moles for the following 33 actinides and fission products at each burnup step in SAS2H {BIC(l,J), where 1=l,NT; 1=1,33).

kr 85 kr 85m kr 87 kr 88 br 85 br 87 br 88 se 85 se 87 se 88 sb132 sb133 sbl34 sbl35 tel3l tel3lm tel32 te133 tel33m tel34 tel35 tel38 i131 il32 il33 i134 i135 il38 xel33 xel33m xel35 xel35m xel38 These nuclides comprise the nuclides included in the primary and secondary system and their precursors.

(2) The edited molar quantities are converted to curies/mwth via the following procedure:

(a) The edited molar quantities BIB(I,J) are converted to curies BIC(Ij) for each burnup step 1=1,NT and for each isotope J=1,33 via the following algorithm:

BIC(IJ) = BIB(j,1) * (6.023E+23 atoms/mole)

• CL(J) / (3.7E+10 dis/sec/Ci)

The relevant half-lives CT(J) in seconds extracted from Ref.22 are as follows:

3.3933E+08 1.6128E+04 4.5720E+03 1.0224E+04 1.7220E+02 5.5900E+01 1.6400E+01 3.2000E+01 5.8000E+00 1.5000E+00

CA 06422 Rev.O Page 8 of 46 2.5200E+02 1.5000E+02 0.8000E+00 1.7100E+00 1.5000E+03 1.1664E+05 2.7648E+05 7.4400E+02 3.3240E+03 2.5200E+03 1.9000E+01 1.4000E+00 6.9299E+05 8.2080E+03 7.4880E+04 3.1560E+03 2.3652E+04 6.5000E+00 4.5300E+05 1.8922E+05 3.2760E+04 9.1800E+02 8.4600E+02 The isotopic decay constant is defined by CL(I) = 0.6931472/CT(I)

(b) The maximum activity in curies for each isotope J for cycle I (N=1 ,N 1) is determined and designated B I D(I,3).

Similarly, the maximum activity in curies for each isotope 1 for cycle 2 (N=NI+I,NI+N2) is determined and designated BID(2,J). Finally, the maximum activity in curies for each isotope J for cycle 3 (N=NI+N2+1,NT) is determined and designated BID(3,J).

(c) The activity per unit power in curies per mwth for each isotope J is then calculated via BIE(I,J) = BID(I,J)

• NAI / POWER for once burned fuel BIE(2,J) = BID(2,1)

• NA2 / POWER for twice burned fuel BIE(3,J) =BID(3,J)

• NA3 /POWER for thrice burned fuel BIE(4,J) =BIE(I,J) + BIE(2,J) + BIE(3,J) fortotal core (3) End of execution isotopics in grams wvas also editted from SAS2H and stored as DG(I,J) for J=1,33. The end of execution isotopics in grams was also calculated from the previously editted quantity BIB(NTJ) via the algorithm DG(2,J) = BIB(NT,1)

• CW(J) for J=1,33 where the atomic weight CW(J) is defined as 085 085 087 088 085 087 088 085 087 088 132 133 134 135 131 131 132 133 133 134 135 138 131 132 133 134 135 138 133 133 135 135 131 138 (4) End of execution isotopics in curies wvas also editted from SAS2H and stored as DC(I,J) for 1=1,33. The end of execution isotopics in curies was also calculated from the previously editted quantity B IB(NTJ) via the algorithm DC(2,J) = BIB(NT,J) * (6.023E+23 atoms/mole)

• CL(J) / (3.7E+10 dis/sec/Ci)

(5) The SAS2HED3 code then prints a summary output file (xxx.pun) to unit 6 with the following contents:

(a) The power, the number of bumup steps per cycle, the total number of burnup steps, the number of assemblies per cycle, and the total number of assemblies.

(b) A listing of the isotopic elements.

(c) For each bumup step, the EFPD and the isotopic activity in moles.

(d) For each burnup step, the EFPD and the isotopic activity in curies.

(e) For each isotope, the isotope name, CW(J), CT(J), CL(J), DG(l,J), DG(2,J), DC(I,J), and DC(2,J).

(f) For each isotope, the isotope name, BID(1,J), BID(2,J), BID(3,J), BIE(1,J), BIE(2,J), BIE(3,J), BIE(4,J) 6.2 DEQ 1131 Primary Iodine Activities Table I depicts the calculation of the primary iodine activities for spiking and non-spiking applications. The inputs, technical assumptions, and methodology for the calculation of the primary iodine activities are as follows:

Pow is the peak core power level of 2754 Mwt, which includes a factor of 1.02 to incorporate instrument uncertainty (Ref.7 and UFSAR 3.2.1)

CA06422 Rev.O Page 9 of 46

• Fcp is the charging pump letdown flow for one and a half charging pumps at 120TF and saturation (1.5*44-6=60 gpm) (UFSAR Table 9-1). Note that use of a single charging pump is normal operating procedure at CCNPP at hot full power (HFP). Two charging pumps are sometimes used during boration or dilution operations from HFP. Three charging pumps are never used at HFP and rarely used otherwise, since use of three charging pumps causes the discharge relief valves to be challenged. It is conservatively assumed that all RCS losses are made up by the flow of one and a half charging pumps operating at full capacity.

• vcp is the specific volume of 0.01620 cf/lbm at the charging pump temperature of 120TF and at saturation (UFSAR Table 9-1 and Ref. 8)

• vrcs is the specific volume of 0.022132 cf/lbm at the reactor coolant conditions of 574.50 F and 2250 psia (UFSAR Table 4.1, UFSAR Figure 4.9, Ref.8)

• Frcs=Fcp*vrcs/vcp=81.97 gpm is the charging pump letdown flow for 1.5 charging pumps at rcs conditions

• vpzr is the specific volume of 0.02703 cf/lbm at the pressurizer conditions of 653°F and 2250 psia (UFSAR Table 4.7 and Ref.8)

• vstp is the specific volume of 0.016018 cf/lbm or 1 gm/cc at standard temperature and pressure (Ref.8)

• Vrcs is the rcs volume of 9576 cf (UFSAR Table 4.1)

• Vpzr is the minimum pressurizer water volume of 600 cf (UFSAR Table 4.7)

• Vtot=Vrcs+Vpzr*vrcs/vpzr-10067.28 cf is the total rcs plus pressurizer water volume at rcs conditions of 574.5°F and 2250 psia (UFSAR Table 4.1, UFSAR Figure 4.9)

• FrcsNtot 1.8141 E-05/sec is the charging pump constant Mrcs=Vtot/vrcs=454870 Ibm is the rcs/pressurizer water mass

• The first section of the spreadsheet calculates the equilibrium activity per unit power via the following decay chains:

• Tel3lm - Tel31 -1 131

• Sbl32 Tel32 1132

• Sbl33 Tel33- I133

• Sbl34 Tel34- 1134

• Sbl35 Tel35 1135

• Column A: Nuclide half lives were extracted from Ref.4.

• Column B: Nuclide activity per core in Ci/Mwt was extracted from the SAS2HED3 edit of the limiting case CRCB from Ref.5.

• Column C: Fuel escape rate coefficients in l/sec per Ref.16 Table II.

• Column D: Nuclide decay constants are defined as ln(2)/A(i).

• Column E: Equilibrium nuclide fractions are assumed to be unity; that is, all of the iodine, antimony, and tellurium isotopes are assumed to be available for release.

• Column F: The primary RCS leak and makeup rate as defined by Frcs/Vtot.

CA06422 Rev.O Page 10 of 46

• Column G: The equilibrium isotopic activity for 1% failed fuel assuming no precursors.

o G(i) = B(i)*E(i)*C(i)*0.01/(D(i)+F(i))

• Column H: The equilibrium isotopic activity for 1% failed fuel assuming precursors.

o H(i) = G(i) + H(i+l)*D(i)/(D(i)+F(i)), where i+l denotes the precursor

• Column 1: Iodine dose conversion factors (DCFs) were extracted from Federal Guidance Report (FGR) 11 Table 2.1 (Ref.10). Note that Alternate Source Terms utilizing DCFs from Refs.10-1 I will be utilized in all control room and offsite dose calculations, thus calculation of dose equivalent 1-131 for both primary and secondary systems must also use FGR DCFs and be incorporated in Technical Specification (TS 1.1).

• Column J: Nuclide half lives wvere extracted from Ref.4.

• Column K: Nuclide decay constants are defined as ln(2)/J(i).

• Column L: Equilibrium RCS source for 1% failed fuel with precursors from Column H.

• Column M: 1% equilibrium RCS nuclide activity in Ci: M(i)=L(i)*Pow

• Column N: 1% equilibrium RCS nuclide activity in Ci/cc: N(i)=M(i)NVtot

• Column 0: 1% equilibrium RCS nuclide activity in microCi/gm: 0(i)=M(i)/Mrcs* 1000000

• Column P: Nuclide activity fraction in RCS: P(i)=N(i)/T(N(i))

• Column Q: Nuclide DCF fraction: Q(i)=I(i)/1(1)

• Column R: Nuclide activity in RCS in utCi/gm for I uCi'gm DEQ 1-131: R(i)=P(i)*l/E(P(i)*Q(i)) perRef.9.

The summation is E(Ri*Qi).

• Column T: Nuclide activity in RCS in Ci for I juCi/gm DEQ 1-13 1: T(i)=R(i)*Mrcs*0.00000 I

• Column S: Nuclide activity in RCS in pCi/cc for I puCi/gm DEQ 1-131: S(i)=T(i)/Vtot* 1000000.

• Column U: Nuclide activity in RCS in pxCi/gm for 60 Ci/gm DEQ 1-31: U(i)=P(i)*60/E(P(i)*Q(i)) per Ref.9. The summation is E(Ui*Qi).

• Column W: Nuclide activity in RCS in Ci for 60 pCi/gm DEQ 1-131: W(i)=U(i)*Mrcs*0.000001

• Column V: Nuclide activity in RCS in lCi/cc for 60 pCi/gm DEQ 1-131: V(i)=W(i)/Vtot*1000000.

• Column X: Nuclide activity in RCS in uCi/cc for I pCi/gmDEQ 1-131: X(i)=S(i)

• Column Y: Nuclide decay constants: Y(i)=K(i)

• Column Z: 500 CIS nuclide activity in pCi/cc/sec: Z(i)=500*(Y(i)+Frcs/Vtot)*X(i). Note that it is assumed that the charging pump makeup rate from 1.5 charging pumps bounds all RCS losses.

• Column Al: 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 500 CIS nuclide activity source in Ci: Al(i)=(Z(i)*8*3600+X(i))*Vtot*0.000001

• Column Bl: 335 CIS nuclide activity in pCi/cc/sec: Bl(i)=335*(Y(i)+FrcsNtot)*X(i). Note that it is assumed that the charging pump makeup rate from 1.5 charging pumps bounds all RCS losses.

CA 06422 Rev.0 Page 11 of 46

• Column Cl: 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 335 CIS nuclide activity source in Ci: C1(i)=(Bl(i)*8*3600+X(i))*Vtot*0.000001 6.3 DEQ I131 Secondary Iodine Activities Tables 2 and 3 depicts the calculation of the secondary iodine activities. The relevant rate equation is as follows:

dIs(i)/dt = Ip(i)*Rps - (X(i)+Rs)*Is(i) where Is(i) and Ip(i) are the secondary and primary activities for Iodine isotope i. Ai) is the decay constant for Iodine isotope i. Rps and Rs are the primary-to-secondary and secondary-to-external leakrates in 1/sec. The inputs, technical assumptions, and methodology for the calculation of the secondary iodine activities are as follows:

• Pow is the peak core power level of 2754 Mwt, which includes a factor of 1.02 to incorporate instrument uncertainty (Ref.7 and UFSAR 3.2.1)

• M2sg is the mass 275942 Ibm of water in 2 steam generators (Ref.13).

• V2sg is the volume of the liquid in the 2 steam generators assuming a density of Igm/cc.

• vstp is the specific volume of 0.016018 cfllbm or I gm/cc at standard temperature and pressure (Ref.8)

• Vrcs is the rcs volume of 9576 cf (UFSAR Table 4.1)

• vrcs is the specific volume of 0.022132 cf/lbm at the reactor coolant conditions of 574.50 F and 2250 psia (UFSAR Table 4.1, UFSAR Figure 4.9, Ref.8)

• Vpzr is the minimum pressurizer water volume of 600 cf (UFSAR Table 4.7)

• vpzr is the specific volume of 0.02703 cfllbm at the pressurizer conditions of 653°F and 2250 psia (UFSAR Table 4.7 and Ref.8)

• Vtot-(Vrcs+Vpzr*vrcs/vpzr)*vstp/vrcs=7286.18 cf is the total rcs plus pressurizer water volume at STP

• Rps = Primary-to-secondary leakrate in 1/sec at STP (200 gpd UFSAR 14.16 and TS 3.4.13)

• Rs = Secondary-to-external flowkrate in 1/sec. = (5.9E+6 Ibm/hr/sg Ref.13)*(2 sg)*(453.592379 gnmlbm)*(l cc/gm Ref.01) *(7.4805 gal/co*(0.0005 condensor partition factor UFSAR 14.16) / (60 min/hr)

/ (28316.85 cc/cf) = 11.783 gpm

• Column A: Iodine dose conversion factors (DCFs) were extracted from Federal Guidance Report (FGR) 11 Table 2.1 (Ref.10). Note that Alternate Source Terms utilizing DCFs from Refs.10-1 I will be utilized in all control room and offsite dose calculations, thus calculation of dose equivalent 1-131 for both primary and secondary systems must also use FGR DCFs and be incorporated in Technical Specification (TS 1.1).

• Column B: Nuclide DCF fraction: B(i)-A(i)/A(I)

• Column C: Nuclide half-lives were extracted from Ref.4.

• Column D: Nuclide decay constants are defined as ln(2)/C(i).

• Column E: RCS Ci DEQ 1-131 source from Section 6.2 Column T.

• Column F: SG DEQ 1-131 source in Ci: F(i)=E(i)*Rpsl(D(i)+Rs)

CA06422 Rev.0 Page 12 of 46

• Column G: SG DEQ 1-131 source in microCi/gm: G(i)=F(i)*1000000/M2sg

• Column H: SG 0.1 microCi/gm DEQ 1-131 source in microCi/gm: H(i)=0.1 *G(i)/f(B(i)*G(i))

6.4 Noble Gas Primary Activities Table 4 depicts the calculation of the primary noble gas activities. The inputs, technical assumptions, and methodology for the calculation of the primary noble gas activities are as follows:

• Pow is the peak core power level of 2754 Mwt, which includes a factor of 1.02 to incorporate instrument uncertainty (Ref.7 and UFSAR 3.2.1)

• Fcp denotes the removal of borated RCS liquid and the insertion of unborated liquid necessary for boron rundown during a cycle. Per ANSI/ANS-18.1-1999 (Ref.17) and NUREG-0017 (Ref.20), letdown to the CVCS system removes no noble gases from the letdown stream in the ion exchangers or in the Volume Control Tank (VCT). The only removal occurs via removal of borated RCS liquid and the insertion of unborated liquid necessary for boron rundown during a cycle. Per NEOP 13 (Ref.18), the boron concentration is 1607 ppm at 0 EFPD and 5.9 ppm at 633 EFPD. The dilution rate is thus calculated via

• dC/dt=-F*CNV

• C = Co

• exp(-t*FNV)

• F = V

• ln(CoIC)/t

• F = (7286.18 ft3)

• In(1607/5.9) / (633

• 24

• 60) = 0.04482 cfm = 0.3353 gpm at STP

• F = 0.3353

• vcp / vstp = 0.3391 gpm at 120°F sat

• vcp is the specific volume of 0.01620 cf/lbm at the charging pump temperature of 120°F and at saturation (UFSAR Table 9-1 and Ref. 8)

• vrcs is the specific volume of 0.022132 cftlbm at the reactor coolant conditions of 574.50 F and 2250 psia (UFSAR Table 4.1, UFSAR Figure 4.9, Ref.8)

• Frcs=Fcp*vrcs/vcp=0.46 is the boron letdown feed-and-bleed flow at RCS conditions

• vpzr is the specific volume of 0.02703 cf/ibm at the pressurizer conditions of 653°F and 2250 psia (UFSAR Table 4.7 and Ref.8)

• vstp is the specific volume of 0.016018 cf/lbm or I gm/cc at standard temperature and pressure (Ref.8)

• Vrcs is the rcs volume of 9576 cf (UFSAR Table 4.1)

• Vpzr is the minimum pressurizer wvater volume of 600 cf (UFSAR Table 4.7)

• Vtot-Vrcs+Vpzr*vrcs/vpzr=10067.28 cf is the total rcs plus pressurizer water volume at rcs conditions of 574.5°F and 2250 psia (UFSAR Table 4.1, UFSAR Figure 4.9)

• FrcsNtot=I1.0280E-07Isec is the removal constant

• The first section of the spreadsheet calculates the equilibrium activity per unit power via the following decay chains and branching fractions (Ref.19):

Se85 - Br85 - Kr85m (0.998)

Kr85 (0.002)

• Kr85m - Kr85 (0.21)

Se87 - Br87 - Kr87 (0.977)

Se88 - Br88 - Kr88 (0.957)

Kr87 (0.043)

- .

CA06422 Rev. 0 Page 13 of 46

• Xel33m - Xe133

• Tel33m - 1133 - Xel33m(0.029)

• Xe133 (0.971)

• Xel35m - Xe135

• Tel35 - 1135 - Xel35m(0.155)

• XeI35 (0.845)

• Te138 - 1138 - XeI38

• Column A: Nuclide half lives were extracted from Ref.4.

• Column B: Nuclide activity per core in Ci/Mwt was extracted from the SAS2HED3 edit of CRCB.

• Column C: Fuel escape rate coefficients in 1/sec per Ref.16 Table II.

• Column D: Nuclide decay constants are defined as ln(2)/A(i).

• Column E: Equilibrium nuclide fractions are assumed to be unity; that is, all of the krypton, xenon, iodine, bromine, tellerium, and selenium isotopes are assumed to be available for release.

• Column F: The primary RCS leak and makeup rate as defined by Frcs/Vtot.

• Column G: The equilibrium isotopic activity for 1% failed fuel assuming no precursors.

o G(i) = B(i)*E(i)*C(i)*0.01/(D(i)+F(i))

• Column H: The equilibrium isotopic activity for 1% failed fuel assuming precursors.

o H(i) = G(i) + H(i+l)*D(i)!(D(i)+F(i)), where i+l denotes the precursor

• Column I: Nuclide half-lives were extracted from Ref.4.

• Column J: Nuclide decay constants are defined as ln(2)/l(i).

• Column K: Equilibrium RCS source for 1% failed fuel with precursors from Column H.

• Column L: Equilibrium RCS source for 1% failed fuel with precursors in Ci: L(i)=K(i)*Pow

• Column M: Nuclide gamma energies in Mev/dis from Refs.14-15.

• Column N: Nuclide beta energies in Mev/dis from Refs.14-15.

• Column 0: Nuclide gamma plus beta energies in Mev/dis: O(i)=M(i)+N(i). Note that the two values at the bottom of the column denote E(Pi*Oi) and <E>= E(Pi*Oi)/ E(Pi)

• Column P: Equilibrium RCS source for I% failed fuel with precursors in Ci: P(i)=L(i)

• Column Q: Nuclide activity in RCS in uCi/gm for 100/Ebar: Q(i)=P(i)*l00/E(P(i)*O(i)) per Ref.9. Note that the value at the bottom of the column denotes 100/<E>= E(Qi) in microCilgm.

• Column R: Nuclide activity in RCS in uCi/cc for 100/Ebar: R(i)=Q(i)/vrcs. Note that the value at the bottom of the column denotes 100/<E>= E(Ri) in microCi/cc.

• Column S: Nuclide activity in RCS in Ci for 100/Ebar: S(i)=R(i)*Vtot*0.00000l. Note that the value at the bottom of the column denotes I 00!<E>= E(Si) in Ci.

CA 06422 Rev.0 Page 14 of 46

7. REFERENCES (01) "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Powver Reactors",

Regulatory Guide 1.183:

(02) "Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light Water Nuclear Power reactors", Regulatory Guide 1.195 (03) TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites" (04) "Chart of the Nuclides", Nuclides and Isotopes Fifteenth Edition, GE Nuclear Energy.

(05) "Control Room Habitability Source Term Calculations", CA06358 (06) "Gas Gap Isotopic Fraction Calculations", CA06421 (07) "Power Levels of Nuclear Power Plants", Regulatory Guide 1.49.

(08) 1967 Steam Tables (09) "Implementation of AST Site Boundary and Control Room Dose for Fort Calhoun Station", Stone & Webster, January 2001.

(10) Federal Guidance Report No.11: Limiting Values of Radionuclide Intake and Air Concentration and DCFs for Inhalation, Submersion, and Ingestion (11) Federal Guidance Report No.12: External Exposure to Radionuclides in Air, Water, and Soil (12) "Application of Technical Specification Definition of Dose Equivalent 1-131", NRM 97022.

(13) CA05725, WEC-222-781 1-A45 Sheet 30: RSG Parameter Listing (14) "Determ-ination of E-Bar", CP-828 Rev.0.

(15) "AXIDENT A Digital Computer Dose Calculation Model", NUS-1954 Rev.3 (16) CE Calculation SE-69-97 1: Fission Product Activity in the Reactor Coolant (17) ANSI/ANS-18.1-1999: ANS Radioactive Source Term for Normal Operation of LWRs (18) NEOP-13 Rev.26 Technical Data Book for Unit 1 Cycle 17 (19) LOCADOSE User's Manual (20) NUREG-0017 Rev.l: Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from PWRs

CA 06422 Rev.0 Page 15 of 46

8. DOCUMENTATION OF COMPUTER CODES No computer codes, except for EXCEL spreadsheets, are utilized in this work.

CA 06422 Rev. 0 Page 16 of 46

9. CALCULATIONS, RESULTS, AND CONCLUSIONS 9.1 DEQ 1131 Primary Iodine Activities Calculation of the primary iodine activities for 1% failed fuel, for a peak iodine level of I DEQ-1131 ,pCi/gmper Technical Specification (TS) 3.4.15, for a preaccident iodine spike (PIS) of 60 DEQ-1131 piCi/gm per TS 3.4.15, for a concurrent iodine spike (CIS) of 500 per Regulatory Guides 1.183 and 1.195 (Refs. 1-2), and for a CIS of 335 per Regulatory Guides 1.183 and 1.195 (Refs.1-2) is shown in Table 1. The iodine activities for the 1% failed fuel case, for the peak iodine level of I DEQ-1131 pCi/gm case, and for the PIS of 60 DEQ-1131 uCi/gm case are distributed instantaneously and homogeneously throughout the primary coolant at the beginning of the accident. For the CIS cases, the iodine activities can be released homogeneously and continuously over the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> accident duration, at the beginning of the accident, or in steps spanning the accident duration.

Tahbl 1- Cami~latinn nf Primarv Indina Activitip.- for CIS and PIS Halflife(sec) No(Ci/MWt) R(/sec) lam(/sec) feg F(/sec) N1 (CUIMWt) N2(CiIMWt A B C D E F G H 1131 6.9299E+05 2.7629E+04 2.30E-08 1.0002E-06 1.00 1.8141 E-05 3.3199E-01 3.3217E-01 Tel31 1.5000E+03 2.2584E+04 1.40E-09 4.6210E-04 1.00 1.8141 E-05 6.5837E-04 3.4935E-03 Te-131m 1.1664E+05 5.0686E+03 1.40E-09 5.9426E-06 1.00 1.8141 E-05 2.9464E-03 1132 8.2080E+03 3.9464E+04 2.30E-08 8.4448E-05 1.00 1.8141 E-05 8.8477E-02 1.1031E-01 Te-132 2.7648E+05 3.9110E+04 1.40E-09 2.5070E-06 1.00 1.8141E-05 2.6518E-02 2.6526E-02 Sb-132 2.5200E+02 1.2711 E+04 1.40E-09 2.7506E-03 1.00 1.8141E-05 6.4273E-05 1133 7.4880E+04 5.5715E+04 2.30E-08 9.2568E-06 1.00 1.8141 E-05 4.6772E-01 4.6789E-01 Te-133 7.4400E+02 3.1336E+04 1.40E-09 9.3165E-04 1.00 1.8141E-05 4.6190E-04 5.1800E-04 Sb-133 1.50002+02 1.8954E+04 1.40E-09 4.621OE-03 1.00 1.8141 E-05 5.7200E-05 1134 3.1560E+03 6.2858E+04 2.30E-08 2.1963E-04 1.00 1.8141E-05 6.0804E-02 6.3104E-02 Te-134 2.5200E+03 5.2156E+04 1.40E-09 2.7506E-04 1.00 1.8141E-05 2.4904E-03 2.4905E-03 Sb-134 8.0000E-01 3.8184E+03 1.40E-09 8.6643E-01 1.00 1.8141E-05 6.1697E-08 1135 2.3652E+04 5.2964E+04 2.30E-08 2.9306E205 1.00 1.8141E-05 2.5674E-01 2.5675E-01 Te-135 1.9000E+01 2.7415E+04 1.40E-09 3.6481E-02 1.00 1.8141 E-05 1.0515E-05 1.0569E-05 Sb-135 1.7100E+00 1.5559E+03 1.40E-09 4.0535E-01 1.00 1.8141E-05 5.3735E-08 ActivILI for 1% Failed Fuel FGR-11 RCS RCS RCS RCS DCF Halflife lambda Source Source Activity Activity Rem/Ci sec 1/sec CUMWt Ci CUcc microCigm I J K L M N 0 1-131 3.2893E+04 6.9299E+05 1.0002E-06 3.3217E-01 9.1480E+02 3.2090E-06 4.4337E+00 1-132 3.811 OE+02 8.2080E+03 8.4448E-05 1.1031E-01 3.0380E+02 1.0657E-06 1.4724E+00 1-133 5.8460E+03 7.4880E+04 9.2568E-06 4.6789E-01 1.2886E+03 4.5202E-06 6.2453E+00 1-134 1.3135E+02 3.1 560E+03 2.1963E-04 6.3104E-02 1.7379E+02 6.0963E-07 8.4230E-01 1-135 1.2284E+03 2.3652E+04 2.9306E-05 2.5675E-01 7.0709E+02 2.4804E-06 3.4270E+00

.__ 1.1885E-05 Activity for I and 60 MicroCi/gm DEQ 1131 11mi croCMgm DEQ 1131 60 microCi/gm DEQ 1131 RCS FGR-1 I DEQ DE0 DEQ DEQ DEQ DEQ Activity l DCF 1131 1131 1131 1131 1131 1131 fraction Fraction microCilgm microCi/cc Ci microCi/gm microCi/cc Ci

CA 06422 Rev.0 Page 17 of 46 P a R S T U V W 1-131 0.2700 1.0000E+00 0.7789 0.5638 1.6071E+02 46.7356 33.8258 9.6428E+03 1-132 0.0897 1.1586E-02 0.2587 0.1872 5.3372E+01 15.5206 11.2333 3.2023E+03 1-133 0.3803 1.7773E-01 1.0972 0.7941 2.2638E+02 65.8314 47.6467 1.3583E+04 1-134 0.0513 3.9933E-03 0.1480 0.1071 3.0532E+01 8.8786 6.4261 1.8319E+03 1-135 0.2087 3.7345E-02 0.6021 0.4358 1.2422E+02 36.1240 26.1455 7.4534E+03 1.0000 1.0000 60.0000

_ CIS Spiking Factor of 500 CIS Spiking Factor of 335

_ RCS CIS 8 Hr CIS CIS 8 Hr CIS Activity lambda Source Source Source Source

_ microCi/cc 1/sec uCi/cc-s Ci pCilcc-s CI X Y Z Al B1 r C11 1-131 0.5638 1.0002E-06 5.3956E-03 4.4459E+04 3.6150E-03 2.9841E+04 1-132 0.1872 8.4448E-05 9.6034E-03 7.8899E+04 6.4343E-03 5.2880E+04 1-133 0.7941 9.2568E-06 1.0878E-02 8.9540E+04 7.2886E-03 6.0066E+04 1-134 0.1071 2.1963E-04 1.2733E-02 1.0457E+05 8.5309E-03 7.0070E+04 1-135 0.4358 2.9306E-05 1.0338E-02 8.4998E+04 6.9263E-03 5.6990E+04 Pow(mwt) 2754 RG 1.49 1 UFSAR 3.2.1 Frcs(gpm-gps) 81.97 1.3662 Fcplvrcs/vcp Fcp(gpm) 60 . UFSART9.1 12OFsaturation pressure vcp(cfbmj . 0.01620 Steam Table c} 120F saturation pressure Vtot(cf-gal-cc) 10067.28 7.5308E+04 2.8507E+08 Vrcs+Vpzxvrcs/vpzr 0 574.5 F and 2250 psia Vrcs(cf) 9576 UFSAR T4.1 vrcs(cflbm) 0.022132 Steam Tables 574.5 F and 2250 psia - UFSAR T4.1 F4.9 Vpzr(cf) 600 UFSAR T4.7 vpzr(cf/lbm) 0.02703 Steam Tables @ 653 F and 2250 psia - UFSAR T4.7 vstp(cfbm) 0.016018 Steam Tables (> 1 gm/cc FrcsNtot(1Isec) 1.8141 E-05 FrcsNtot Mrcs(lbm-gm) 4.5487E+05 2.0633E+08 I Vtot/vrcs C1 (cc/cf) 28316.85 _ _ _ Steam Tables C2 (gal/cf) 7.48052 Steam Tables C3(gmiibm) 453.592379 Steam Tables 9.2 DEQ 1131 Secondary Iodine Activities Calculation of the secondary iodine activities for a peak iodine level of 0.1 DEQ-1131 pCilgm per TS 3.7.14 is shown in Table 2. These iodine activities are distributed instantaneously and homogeneously throughout the secondary coolant at the beginning of the accident. Note that the primary-to-secondary leakrate must be set to 1.58 gpm to attain a secondary equilibrium DEQ 1-131 activity of 0.1 microCi/gm (Table 3). Using the TS 3.4.13 limit of 200 gpd results in a peak equilibrium DEQ 1-131 activity of 0.0088 microCilgm (Table 2).

Table 2: Calculation of Secondary Iodine Activities I I I I T I r 7 RCS _ _ SG I T r __r l DE2 1-131 SG SG DEQ 1-131 l FGR-11 FGR11 l T 1 microCigm 2DE 1-131 DEQ 1-131 0.1 microCgmI

_ DCF I DCF Halflife lambda I Source I Source I Source I Source l

CA 06422 Rev.0 Page 18 of 46 Rem/Ci Fraction sec 1/sec Ci Ci pCi/gm tCi/gm A B C D E F G H 1-131 3.2893E+04 1.OOOOE+00 6.9299E+05 1.0002E-6 1.6071 E+02 9.8358E-1 7.8583E-3 8.9260E-02 1-132 3.811 OE+02 1.1586E-02 8.2080E+03 8.4448E-5 5.3372E+01 2.5078E-2 2.0036E-4 2.2758E-03 1-133 5.8460E+03 1.7773E-01 7.4880E+04 9.2568E-6 2.2638E+02 6.3269E-1 5.0549E-3 5.7417E-02 1-134 1.3135E+02 3.9933E-03 3.1560E+03 2.1963E-4 3.0532E+01 5.7486E-3 4.5928E-5 5.2168E-04 1-135 1.2284E+03 3.7345E-02 2.3652E+04 2.9306E-5 1.2422E+02 1.4969E-1 1.1959E-3 1.3584E-02 8.8038E-3 1.OOOOE-01 Pow(mwt) 2754 RG 1.49/ UFSAR 3.2.1 Failed fuel(ff) 0.01 M2sg(1bm-gm) 275942.00 1.2517E+08 WEC 222-7811-A45 Sheet 30 V2sg(cf-gal-cc) 4420.1664 3.3065E+04 1.2517E+08 2SG vols at STP = M2sg * (1 cc/gm) vstp(cfAbm) 0.016018 Steam Tables @ 1 gm/cc Vtot(cfgal-cc) 7286.18 5.4504E+04 2.0632E+08 (Vrcs+Vpzxvrcs/vpz)'vstp/vrrcs @ STP Vrcs(cf) 9576 UFSAR T4.1 vrcs(cf/lbm) 0.022132 Steam Tables @ 574.5 F and 2250 psia - UFSAR T4.1 F4.9 Vpzr(cf) 600 UFSAR T4.7 vpzr(cfAbm) 0.02703 Steam Tables @ 653 F and 2250 psla - UFSAR T4.7 Rps(gpm-1/sec) 0.138888889 4.2470E-08 Primary-to-secondary leakrate at STP Rs(gpm-1/sec) 11.783 5.9393E-06 Secondary-to-outside leakrate C1 (cc/cf) 28316.85 Steam Tables C2 (gal/cf) 7.48052'. Steam Tables C3(gm/lbm) 453.592379 Steam Tables

_ _ *Table 3: Calculation of Secondary Iodine Activities RCS SG DEQ 1-131 SG SG DEQ 1-131 FGR-11 FGR-11 1microCV m DEQ 1-131 DEQ 1-131 0.1 microCUm DCF DCF Halflife lambda Source Source Source Source Rem/Cl Fraction sec 1/sec Ci Ci microCVgm microCilgm A B C D E F G H 1-131 3.2893E+04 1.OOOOE+00 6.9299E+05 1.0002E-6 1.6071 E+02 1.1189E+01 8.9395E-2 8.9260E-02 1-132 3.8110E+02 1.1586E-02 8.2080E+03 8.4448E-5 5.3372E+01 2.8529E-01 2.2793E-3 2.2758E-03 1-133 5.8460E+03 1.7773E-01 7.4880E+04 9.2568E-6 2.2638E+02 7.1975E+00 5.7504E-2 5.7417E-02 1-134 1.3135E+02 3.9933E-03 3.1560E+03 2.1963E-4 3.0532E+01 6.5396E-02 5.2248E-4 5.2168E-04 1-135 1.2284E+03 3.7345E-02 2.3652E+04 2.9306E-5 1.2422E+02 1.7028E+00 1.3605E-2 1.3584E-02 1.00155E-1 1.00OOE-01 Pow(mwt) 2754 RG 1.49 / UFSAR 3.2.1 Failed fuel(ff) 0.01 M2sg(1bm-gm) 275942.00 1.2517E+08 WEC 222-7811 -A45 Sheet 30 V2sg(cf-gal-cc) 4420.1664 3.3065E+04 1.2517E+08 2SG vols at STP = M2sg * (1 cc/gm) vstp(cf/lbm) 0.016018 Steam Tables @ 1 gm/cc Vtot(cf-gal-cc) 7286.18 5.4504E+04 2.0632E+08 (Vrcs+Vpzxvrcs/vpz)-vstp/vrrcs @ STP Vrcs(cf) 9576 UFSAR T4.1 vrcs(cf/bm) 0.022132 Steam Tables @ 574.5 F and 2250 psia - UFSAR T4.1 F4.9

CA 06422 Rev.0 Page 19 of 46 Vpzr(cf) 600 UFSAR T4.7 vpzr(cflbm) 0.02703 Steam Tables @ 653 F and 2250 psia - UFSAR T4.7 Rps(gpm-1/sec) 1.58 4.8314E-07 Primary-to-secondary leakrate at STP Rs(gpm-1/sec) 11.783 5.9393E-06 Secondary-to-outside leakrate Cl (cc/cl) 28316.85 Steam Tables C2 (gal/cf) 7.48052 11 1 Steam Tables C3(gm/lbm) 453.592379 1 1 I Steam Tables 93 Noble Gas Primary Activities Calculation of the primary noble gas activities for 1% failed fuel and for a peak noble gas level of I 00/Ebar ,Ci/gm per TS 3.4.15 is shown in Table 4. The noble gas activities for these cases are distributed instantaneously and homogeneously throughout the primary coolant at the beginning of the accident.

Table 4: Calculation of Primary Noble Gas Activities Halflife(sec) No(Ci/MWt) R(Isec) lam(Isec) feg F(Isec) Ni (CVMWt) N2(Ci/MWt)

A B C D E F G H Kr-85m 1.6128E+04 7.9679E+03 6.50E-08 4.2978E-05 1.00 1.0280E-07 1.2022E-01 1.2067E.01 Br-85 1.7220E+02 7.9566E+03 2.30E-08 4.0252E-03 1.00 1.0280E-07 4.5462E-04 4.5464E-04 Se-85 3.2000E+01 3.3017E+03 1.40E-11 2.1661 E-02 1.00 1.0280E-07 2.1340E-08 Kr-85 3.3933E+08 3.7076E+02 6.50E-08 2.0427E-09 1.00 1.0280E-07 2.2986E+00 2.2991E+00 Kr-85m 1.6128E+04 6.50E-08 4.2978E-05 1.00 1.0280E-07 1.2067E-01 Kr-87 4.5720E+03 1.6208E+04 6.50E-08 1.5161E-04 1.00 1.0280E-07 6.9443E-02 6.9679E-02 Br-87 5.5900E+01 1.2874E+04 2.30E-08 1.2400E-02 1.00 1.0280E-07 2.3879E-04 2.3880E-04' Se-87 5.8000E+00 4.6922E+03 1.40E-11 1.1951E-01 1.00 1.0280E-07 5.4968E-09 Kr-88 1.0224E+04 2.2658E+04 6.50E-08 6.7796E-05 1.00 1.0280E-07 2.1691E-01 2.1697E-01 Br-88 1.6400E+01 1.2891 E+04 2.30E-08 4.2265E-02 1.00 1.0280E-07 7.0151E-05 7.0151 E-05 Se-88 1:5000E+00 2.5632E+03 1.40E-11 4.6210E-01 1.00 1.0280E-07 7.7656E-10 Xe-I 33 4.5300E+05 5.5707E+04 6.50E-08 1.5301E-06 1.00 1.0280E-07 2.2175E+01 2.3739E+01 Xe-133m 1.8922E+05 6.50E-08 3.6632E-06 1.00 1.0280E-07 3.3819E-01 Xe-133m 1.8922E+05 1.7354E+03 6.50E-08 3.6632E-06 1.00 1.0280E-07 2.9953E-01 3.3819E-01 1-133 7.4880E+04 5.5715E+04 2.30E-08 9.2568E-06 1.00 1.0280E-07 1.3691 E+00 1.3708E+00 Te-133m 3.3240E+03 2.5447E+04 1.40E-09 2.0853E-04 1.00 1.0280E-07 1.7076E-03 Xe-135 3.2760E+04 1.7708E+04 6.50E-08 2.1158E-05 1.00 1.0280E-07 5.4137E-01 5.6710E-01 Xe-135m 9.1800E+02 6.50E-08 7.5506E-04 1.00 1.0280E-07 7.4212E-02 Xe-135m 9.1800E+02 1.1635E+04 6.50E-08 7.5506E-04 1.00 1.0280E-07 1.0015E-02 7.4212E-02 i-135 2.3652E+04 5.2964E+04 2.30E-08 2.9306E-05 1.00 1.0280E-07 4.1422E-01 4.1423E-01 Te-135 1.9000E+01 2.7415E+04 1.40E-09 3.6481E-02 1.00 1.0280E-07 1.0521E-05 Xe138 8.4600E+02 4.9330E+04 6.50E-08 8.1932E-04 1.00 1.0280E-07 3.9130E-02 3.9160E-02 1-138 6.5000E+00 1.3523E+04 2.30E-08 1.0664E-01 1.00 1.0280E-07 2.9167E-05 2.9195E-05 Te-138 1.4000E+00 1.0113E+03 1.40E-09 4.9511E-01 1.00 1.0280E-07 2.8596E-08 Halflife lambda RCS RCS V 0 Gamma+Beta Source Source Energy Energy Energy . -

sec 1/sec CI/MWT Ci Mev/dis Mev/dis Mev/dis I J K L M N 0 Kr-85m 1.6128E+04 4.2978E-05 1.20672-01 3.3233E+02 0.156 0.233 3.8900E-01 Kr-85 3.3933E+08 2.0427E-09 2.29912+00 6.3318E+03 0.0021 0.223 2.25100E4

CA06422 Rev.0 Page 20 of 46 Kr-87 4.5720E+03 1.5161 E-04 6.9679E-02 1.9190E+02 1.375 1.050 2.4250E+00 Kr-88 1.0224E+04 6.7796E-05 2.1697E-01 5.9754E+02 1.743 0.341 2.0840E+00 Xe-133 4.5300E+05 1.5301E-06 2.3739E+01 6.5377E+04 0.030 0.146 1.7600E-01 Xe-133m 1.8922E+05 3.6632E-06 3.3819E-01 9.3139E+02 0.033 0.155 1.8800E-01 Xe-135 3.2760E+04 2.1158E-05 5.6710E-01 1.5618E+03 0.246 0.322 5.6800E-01 Xe-135m 9.1800E+02 7.5506E-04 7.4212E-02 2.0438E+02 0.422 0.097 5.1900E-01 Xe138 8.4600E+02 8.1932E-04 3.9160E-02 1.0785E+02 2.870 0.800 3.6700E+00

.__ __1.6336E+04 1% . 2.1598E-01 Failed Fuel 100/Ebar 100/Ebar 100/Ebar RCS Activity Activity Activity Acbivity Ci microCi/gm microCi/cc Ci P a R S Kr-85m 3.3233E+02 2.0344E+00 1.4724E+00 4.1975E+02 _

Kr-85 6.3318E+03 3.8761 E+01 2.8054E+01 7.9975E+03 Kr-87 1.9190E+02 1.1747E+00 8.5022E-01 2.4238E+02 Kr-88 5.9754E+02 3.6579E+00 2.6475E+00 7.5473E+02 Xe-133 6.5377E+04 4.0021 E+02 2.8966E+02 8.2574E+04 Xe-133m 9.3139E+02 5.7016E+00 4.1266E+00 1.1764E+03 Xe-135 1.5618E+03 9.5607E+00 6.9197E+00 1.9726E+03 Xe-135m 2.0438E+02 1.2511 E+00 9.0553E-01 2.5814E+02 Xe138 .1.0785E+02 6.6019E-01 4.7782E-01 -1.3622E+02 . . . . . . .

7.5636E+04 -4.6301E+02 3.3511 E+02 9.5532E+04  : .

100/Ebar 4.6301E+02 . . .

Ebar 2.1598E-01 .

Pow(mwt) 2754 ,

Vtot(cf-gal-cc) 10067.28 7.5308E+04 2.8507E+08 Vrcs+Vpzx-vrcshvpzr @ 574.5 F and 2250 psia Vrcs(cf) 9576 UFSAR T4.1 -

vrcs(dclbm-cctgm) 0.022132 1.381656 Steam Tables (a 574.5 F and 2250 psia Vpzr(cf) 600 UFSAR T4.7 vpzr(cflbm) 0.02703 Steam Tables @ 653 F and 2250 psia vstp(cf/bm) 0.016018 Steam Tables @ 1 gm/cc Fcp(gpm) 0.34 UFSAR T9.1 @ 120F saturation pressure vcp(cf/lbm) 0.01620 Steam Table @ 120F saturation pressure Frcs(gpm-gps) 0.46 0.0077 Fcp-vrcshcp FrcsNtot(l/sec) 1.0280E-07 FrcsNtot C1 (cc/cl) 28316.85 Steam Tables C2 (gal/cf) 7.48052 Steam Tables C3(gm/lbm) 453.592379 Steam Tables

CA 06422 Rev.0 Page 21 of 46

10. ATTACHMENTS AITACHMENT A PROGRAM SAS2HED3 PROGRAM SAS2HED3 C'..' * *"*""** +** ** * ** *** ****** +**.* *.* *.* .*.***+****.** * *** **

C' D:\CRHVAC\SAS2H1ED\SAS2H1ED3.FOR C' COMPILECOMMANDIS FORT51 SAS2HED3 C LINK51 SAS211ED3 C' EDIT SAS2H OUTPUT FOR MOLES OF ACTIVITY C' CONVERT MOLES TO CURIES/MWTH C. PRINT INPUT FOR RADTRAD DIMENSION AIA(33),B IA(50),BI B(50,33),B2A(8),XX(8),BI C(50,33)

DIMENSION CW(33),CL(33),CT(33),DG(2,33),DC(2,33),B I D(3,33)

DIMENSION BI E(4,33),ANIF(592)

CHARACTER AIA*8,AIB*8,AIC*14,AID'9,AIE 16,AIF*34,AIG31 CHARACTER A2A*8,A2C*14,A2D'9,A2E*16,A2F*34,A2G*31 CHARACTER A I'29,A21'29,AIJ'29,A2J*29,AIK*30,A2K*30,AIL*8 CHARACTER B I A I0,B2A I0,B3A I0,ANIF*80 DATAAIAI kr85',' kr85m',' kr87': kr88,' br85',

I br87': br88', se85', se87': se88',

2 sbl32,' sbl33', sbl34' sbl35' tel31 ',

3 tel31m',' tel32' tel33': tel33mr', tel34',

4 ' tel35': tel38 i.131 i l32 : il33 ,

5 i134,' il35' il38' xel33' xel33m',

6 xel35',' xel35m': xel38Y DATA CT/3.3933E+08,1.6128E+04,4.5720E+03,1.0224E+04,1 ;7220E+02 I, 5.5900E+01,1.6400E+oi,3.2000E+0i,5.8000E+00:1.5000E+00 2; 2.5200E+02,1.5000E+02,0.8000E+00,1.7100E+00,1.5000E+03 3, 1.1664E+05,2.7648E+05,7.4400E+02,3.3240E+03,2.5200E+03 4, 1.9000E+01,1.4000E+00,6.9299E+05,8.2080E+03,7.4880E+04 5, 3:1560E+03,2.3652E+04;6.5000E+00,4.5300E+05,1.8922E+05 6, 3.2760E+04,9.1800E+02,8.4600E+02/ .

DATA CWV/085.,085.,087.,088.,085.,087.,088.,085.,087.,088.

I, 132.,133.,134.,135.,131.,131.,132.,133..133.,134.

2, 135.,138.,131.,132.,133.,134.,135.,138.,133.,133.

3, 135.,135.,131.,138./

DATA Al Brtotals V DATA AlCtlight elements/

DATA Al D/'actinides7 DATA Al E'fission products'/

DATA AlFrnuclide concentrations, gram atoms7 DATA Al G/basis - single reactor assembly/

DATA AlHP V DATA Al LVnuclide concentrations, grams/

DATA AllJnuclide radioactivity, curies/

DATA Al K.basis -single reactor assembly'/

DATAAlLtotal yI DATA B3AP I/

DATA CA/6.023E+23/,CC/3.7E+ 10/

CALL START C' OPEN ALL FILES TO BE USED:

• C' 6 = PRINTED OUTPUT (OPENED IN SUBROUTINE START) '

CO 7= PUNCH OUTPUT FOR EXCEL (OPENED IN SUBROUTINE START)

• C' 8 = PUNCII OUTPUT FOR NIF (OPENED IN SUBROUTINE START) '

CO 9 = SAS2H OUTPUT FILE (OPENED IN SUBROUTINE START)

• C' 10 = INPUT FILE (OPENED IN SUBROUTINE START)

• C " "" " * * *** ** ** *+* * ** ** *+***** * ***+**+* +** ******* ** *******

C READ INPUT DATA READ(10,*) POWER WRITE(6,500) POWER READ(10,') N 1.N2,N3 NT=NI +N2+N3

CA06422 Rev.O Page 22 of 46 WRITE(6,501) NI ,N2,N3,NT READ(I 0,*) NA 1,NA2,NA3 NAT=NAI +NA2+NA3 WRITE(6,502) NAI ,NA2,NA3,NAT READ(I 0,503) (ANIF(I),I=I ,592) 500 FORMAT(2X:POWER = ,F8.3,' MWTil')

501 FORMAT(2X,'NI = ',18J,2X,'N2 =',18J 1,2X,'N3 = '.18J,2X,'NT = ',18) 502 FORMAT(2X,'NAI = ,18J,2X,NA2 =',18J I,2X,'NA3 = ',18J,2X,'NAT = ',18) 503 FORMAT(A80)

.*.

C"*"'* *.+*'***** b *** ***** * ***+** *+***** .* ** * *** *.****.......................................*

C INnITALIZE VARIABLES DO 10 1=1,50 DO 10J=1,33 BI B(IJ)=0.0 10 BIC(IJ)=0.0 DO II J=1,33 11 CL(J)=0.6931472/CT(J)

DO 12 1=1,2 DO 12 J=1,33 DG(IJ)=0.0 12 DC(1J)=0.0 DO 13 1=1,3 DO 13 J=1,33 13 B I D(IJ)=0.0 IN--O C READ UGiT ELEMENTS GRAM ATOM SAS2il DATA 20 READ(9520,END=990) A2C IF(A2C.NE.AIC) GO TO 20 520 FORN1AT(96X,A14)

READ(9,521,END=990) A2F IF(A2F.NE.A I F) GO TO 20 521 FORNlAT(t/,43X.A34)

READ(9,522,END=990) A2G IF(A2G.NE.AIG) GO TO 20 522 FORMAT(43XA31)

READ(9,530) (B2A(1),1=I,8)

DO 30 1=1,8 IF(B2A(I).NE.B3A) GO TO 30 IX=I-I GO TO 31 30 CONTINUE WRiTE(6,53 1)

CALL EXIT 31 CONTINUE 530 FORMAT(IOX,8A10) 531 FORMAT(2X:ERROR CODE 524)

IN=IN+I BIA(IN)=B2A(IX) 38 CONTINUE DO 32 K=1,51 READ(9,532) A2A,(XX(I),l=I ,IX) 532 FORN1AT(2X,A8,8E10.2)

IF(A2A.EQ.A I B) GO TO 39 DO 33 JN=1,33 IF(A2A.NE.A I A(JN)) GO TO 33 B I B(INJNY=B I B(INJN)+XX(IX)

GO TO 32 33 CONTINUE 32 CONTINUE READ(9,525) 525 FORN1AT(///II)

GO TO 38 39 CONTINUE C READ ACTINIDE GRAM ATOM SAS211 DATA

CA 06422 Rev.0 Page 23 of 46 40 READ(9,540,END--990) A2D IF(A2D.NE.A ID) GO TO 40 540 FORMAT(IOIX,A9)

READ(9,54 1,END=990) A2F IF(A2F.NE.AIF) GO TO 40 541 FORMAT(//.43XA34)

READ(9,542,END'=990) A2G IF(A2G.NE.AIG) GO TO 40 542 FORMAT(43XA31)

READ(9,543) 543 FORMAT(I X) 58 CONTINUE DO 52 K=1,51 READ(9,552) A2A,(XX(I)J=I IX) 552 FORMAT(2XA8,8E10.2)

IF(A2A.EQ.AI B) GO TO 59 DO 53 JN=I,33 IF(A2A.NE.A I A(JN)) GO TO 53 BIB(INJN)=BIB(INJN)+XX(IX)

GO TO 52 53 CONTINUE 52 CONTINUE READ(9,555) 555 FORMAT(/////)

GO TO 58 59 CONTINUE C* *'*** ***s** .*. ** *e** es ...

• • • • ****+*+* *** ** *

• 5**+*** ~*s**5***

C READ FISSION PRODUCT GRAM ATOM DATA 60 READ(9,560,END=990) A2E IF(A2E.NE.AI E) GO TO 60 560 FORMAT(94X,A16)

READ(9,561,END=990) A2F IF(A2F.NE.AIF) GO TO 60 561 FORMAT(//,43XA34)

READ(9,562,END=990) A2G IF(A2G.NE.AIG) GO TO 60 562 FORMAT(43XA31)

READ(9,563) 563 FORMAT(IX) 78 CONTINUE DO 72 K=1,51 READ(9,572) A2A,(XX(I).=I ,IX) 572 FORMAT(2X.A8,8E1 0.2)

IF(A2A.EQ.AI B) GO TO 79 DO 73 JN=1,33 IF(A2A.NE.AIA(JN)) GO TO 73 BIB(INJN)=BI B(INJN)+XX(IX)

GO TO 72 73 CONTINUE 72 CONTINUE READ(9,575) 575 FORMAT(/I///)

GO TO 78 79 CONTINUE IF(IN.LT.NT) GO TO 20 C*5**'+****5* * * **

• 55* * *

• • *5*5*5 **** *5*5*4 ** *5*5*5*4***

• 5*5*5***

C READ LIGIT ELEMENTS GRAM SAS21 DATA 80 READ(9,580,END=990) A2C IF(A2C.NE.AIC) GO TO 80 580 FORNAT(96X,A14)

READ(9,581,END=990) A21 IF(A21.NE.AI I) GO TO 80 581 FORN1AT(//,44XA29)

READ(9,582,END=990) A2K IF(A2K.NE.AI K) GO TO 80 582 FORMAT(44X,A30)

READ(9,583) 583 FORN1AT(IX)

CA 06422 Rev.0 Page 24 of 46 85 CONTINUE DO 86 K=1,53 READ(9,584) A2AXX(I) 584 FORMAT(2X,A8,E1 0.2)

IF(A2A.EQ.Al L) GO TO 89 DO 87 IN=1,33 IF(A2A.NE.AIA(JN)) GO TO 87 DG(IJN)-DG((IJN)+XX(1)

GO TO 86 87 CONlINUE 86 CONTINUE READ(9,585) 585 FORNIAT(I/I/f)

GO TO 85 89 CONTINUE C* "** "* "4 " "** " " "* " ** **** ** **** ** ** * ******** *+*** ** ** ** ** **

• e*.*

C READ IGIT ELEMENTS CURIE SAS21 DATA 90 READ(9,590,END=990) A2C IF(A2C.NE.AIC) GO TO 90 590 FORMAT(96X,A14)

READ(9,591,END=990) A2J IF(A21.NE.A IJ) GO TO 90 591 FORMAT(//,46XA29)

READ(9,592,END=990) A2K IF(A2K.NE.AI K) GO TO 90 592 FORMAT(46XA30)

READ(9,593) 593 FORMAT(IX) 95 CONTINUE DO 96 K=1,53 READ(9,594) A2A,XX(I) 594 FORMAT(2XA8,E10.2)

IF(A2A.EQ.AI L) GO TO 99 DO 97 JN=1,33 IF(A2A.NE.AIA(JN)) GO TO 97 DC(IJN)=DC(IJN)+XX(I)

GOTO96 97 CONTINUE 96 CONTINUE READ(9,595) 595 FORMAT(/////)

GO TO 95 99 CONTINUE C READ ACTINIDE GRAM SAS21 DATA 100 READ(9,600,END=990) A2D IF(A2D.NE.AI D) GO TO 100 600 FORMAT(IOIX,A9)

READ(9,601,END=990) A21 IF(A21.NE.AI1) GO TO 100 601 FORMAT(//,44XA29)

READ(9,602,END=990) A2K IF(A2K.NE.AIK)GO TO 100 602 FORMIAT(44XA30)

READ(9,603) 603 FORMAT(IX) 105 CONTINUE DO 106 K= I,53 READ(9,604) A2AXX( 1) 604 FORMAT(2XA8,E 10.2)

IF(A2A.EQ.A1IL) GO TO 109 DO 107 JN=1,33 IF(A2A.NE.AIA(JN)) GO TO 107 DG(IJN)=DG(IJN)-XX(1)

GO TO 106 107 CONTINUE 106 CONTINUE READ(9,605)

CA 06422 Rev.O Page 2S of 46 605 FORM AT(I///)

GO TO 105 109 CONTINUE C* '** **4*4* '*4** 4* * *4** ** ***4*4*4+**4*4 ***4*4*4*4*4**4**.......*

C READ ACTINIDE CURIE SAS211 DATA 110 READ(9,610,END=990) A2D IF(A2D.NE.AID) GO TO 110 610 FORN1AT(IOIX,A9)

READ(9,61 1,END=990) A2J IF(A2J.NE.AIJ) GO TO 110 611 FORMAT(//,46XA29)

READ(9,612,END=990) A2K IF(A2K.NE.AlK) GO TO 110 612 FORMAT(46XA30)

READ(9,613) 613 FORMAT(IX) 115 CONTINUE DO 116 K=1,53 READ(9,614) A2A,XX(I) 614 FORN1AT(2XA8,EIO.2)

IF(A2A.EQ.A I L) GO TO 119 DO 117 JN=1,33 IF(A2A.NE.AIA(JN)) GO TO 117 DC(I ,JN)=DC(I.JN)XX(1)

GOTO 116 117 CONTINUE 116 CONTINUE READ(9,615) 615 FORNMAT(////I)

GOTO 115 119 CONTINUE C READ FISSION PRODUCT GRAM SAS2H DATA 120 READ(9,620,END=990) A2E IF(A2E.NE.AIE) GO TO 120 620 FORMAT(94XA16)

READ(9,62 1,END=990) A21 IF(A21.NE.AI I) GO TO 120 621 FORh1AT(//,44XA29)

READ(9,622,END=990) A2K IF(A2K.NE.AIK) GO TO 120 622 FORMAT(44XA30)

READ(9,623) 623 FORMAT(IX) 125 CONTINUE DO 126 K=1,53 READ(9,624) A2AXX(I) 624 FORMAT(2X,A8,EIO.2)

IF(A2A.EQ.AIL) GO TO 129 DO 127 JN=1,33 IF(A2A.NE.AIA(JN)) GO TO 127 DG(I JN)=DG(I JN)+XX(1)

GO TO 126 127 CONTINUE 126 CONTINUE READ(9,625) 625 FORMAT(III/I)

GO TO 125 129 CONTINUE C READ FISSION PRODUCTS CURIE SAS211 DATA 130 READ(9,630,END=990) A2E IF(A2E.NE.AI E) GO TO 130 630 FORMAT(94XA16)

READ(9,63 I,EN D=990) A2J IF(A2J.NE.A IJ) GO TO 130 631 FORMAT(//,46XA29)

READ(9,632,END=990) A2K

CA06422 Rev.0 Page 26 of 46 IF(A2K.NE.AIK) GO TO 130 632 FORMAT(46XA30)

READ(9,633) 633 FORMAT(IX) 135 CONTINUE DO 136 K=1,53 READ(9,634) A2A,XX(I) 634 FORMAT(2XA8,EIO.2)

IF(A2A.EQ.A IL) GO TO 139 DO 137 JN=1,33 IF(A2A.NE.AI A(JN)) GO TO 137 DC(IJN)=DC(I JN)+-XX(1)

GOTO 136 137 CONTINUE 136 CONTINUE READ(9,635) 635 FORMAT(////I)

GO TO 135 139 CONTINUE C. * *'* " " "* '* * *4*+**4*4*4*** *4*4*4*4**** ** *4*4*44....................*4.......*

• , **,*,*,,*,,,

C CALCULATE GRAM DATA 990 CONTINUE DO 140 J=1,33 140 DG(2J)=BBIB(NTJ)*CW(J)

C * "****+*"* *4*44*4*** 4*4** *4*4* *** *4*4*** **4* * **4*4* ** ..............................................

• .*.*

C CALCULATE CURIE DATA DO 150 J=1,33 150 DC(2J)=B I B(NTJ)*CL(J)*CA/CC C*' *"* **

"4 *444*44*4*44*44*44+*

"4 '* * * ** *4**** ** .. * .. *44*..4*4*4*4*4* ,*

C CALCULATE DETAILED CURIE DATA DO 160 I= ,NT DO 160 J=1,33 160 B I C(IJ)=B I B(1J)CL(J)*CA/CC DO 170 J=1,33 XX(l)-BIC(1J)

DO 171 1=2,NI 171 IF(XX(I ).LT.BI C(IJ)) XX( )=BI C(IJ)

BID(I J)=XX(1)

IF(N2.EQ.0) GO TO 170 NX=NI+I NXI=NX+I NY=NI+N2 XX(2)=B IC(NXJ)

DO 172 I=NXINY 172 IF(XX(2).LT.BIC(IJ)) XX(2)=1BIC(IJ)

BI D(2J)=XX(2)

IF(N3.EQ.0) GO TO 170 NX=NI+N2+1 NXI=NX+I NY=NI+N2+N3 XX(3)=BIC(NXJ)

DO 173 I=NXINY 173 IF(XX(3).LT.BIC(IJ)) XX(3y=BIC(IJ)

BI D(3J)=XX(3) 170 CONTINUE DO 175 J=1,33 BI E(IJ)=BI D(IJ)*NAIIPOWER Bl E(2j)=BI D(2J)*NA2/POWER BIE(3J)=BID(3j)*NA3/POWER Bl E(4J)=BI E(l J)+BIE(2J)+BIE(3,J) 175 CONTINUE C PRINT DATA TO UNIT 6 WRITE(6,352) AIA WRITE(6,353)

DO 300 I=l,IN WRITE(6.350) BIA(I)

WRITE(6,35 1)(B I B(IJ)J=1,33)

CA 06422 Rev.0 Page 27 of 46 300 CONTINUE WRITE(6,354)

DO 305 I=l,NT WRITE(6,350) BIA(I)

WRITE(6,351) (B IC(lJ)J=1I,33) 305 CONTINUE 350 FORMAT(/,2XA 10) 351 FORMAT(2XIP12EI0.2) 352 FORMAT(12(2XA8))

353 FORMAT(1,2X,'ASSEMBLY ISOTOPIC DATA IN GRAM ATOMS) 354 FORMAT(/,2X,'ASSEMBLY ISOTOPIC DATA IN CURIES')

WRITE(6,355)

DO 310 J=1.33 310 WRITE(6,356) AlA(J), CW(J),CT(J),CL(J)

I ,DG(I J),DG(2j),DC(1 J),DC(2J) 355 FORMAT(//,3X,'ISOTOPE',7XAT Wr: DECAY(SEC): LAMBDA(I/S)'

1,' SAS2HIGRAMS ', CALCGRAMS' 2,' SAS21 CURIES',' CALC CURIES')

356 FORMAT(2XA8,F12.2,1 P2E12.2,1 P4EI5.4)

WRITE(6,370)

DO 320 J=l,33 320 WRITE(6,37 1) Al A(J),(B I D(IJ),I=1 ,3),(B I E(14),I=I ,4) 370 FORMAT(//,3X:ISOTOPE',6X,:ASSM Cl I',6X,'ASSM Cl 2' 1,6X,:ASSM Cl 3',2XBATCH ClMW 1',2X,'BATCH CUMW 2' 2,2X:BATClI ClMW 3',2X,'BATCH CI/MW T) 371 FORMAT(2X,A8,1P7EI5.4)

• ""* * .* S* S*+* * * **** * * ** ***+**5* ** ****** * ******+**..*.......

C PRINT DATA TO UNIT 7 FOR EXCEL c DO330J=1,65 c 330 WRITE(7,380) B I E(4j) c 380 FORMAT(IPEI5.5)

C""** " "* " "'* ** " '** *5** *** *** ** *** * ** S ** * * ** ** *e** * ** ** ** ****................................

. .. .

C PRINT DATA IN UNIT 8 FOR RADTRAD c DO 340 K=1,6 c 340 WRITE(8,390) ANIF(K) c KT=6 cDO 342 J=1,65 c DO 343 K=l ,5 c KT=KT+I c 343 WRITE(8,390) ANIF(KT) c KT=KT+I c WRITE(8,392) BIE(4j) c DO 344 K=1.3 c KT=KT+ I c 344 WRITE(8,390) ANIF(KT) c 342 CONTINUE c WRITE(8,390) ANIF(592) c 390 FORMAT(A80) c 392 FORMAT(2X,IPEI0.4)

C"'

• 5*** * ** ** ****** ** *

'"* *** **S* ****** **** *

• • • ** ..............................................

• .*

C END OF PROGRAM 995 CONTINUE CLOSE(6) c CLOSE(7) c CLOSE(8)

CLOSE(9)

CLOSE(10)

STOP END SUBROUTINE START C

C " " "* "* '* ****

" " "** " " ** ** **

• * ** **

• **

• SS**S*** e***S * * **...

C' C' ROUTINE TO GET TIIE REQUIRED DATA TO GET STARTED

• C*

• C CIIARACT1-R INFP*8,INFE*8,INFN*8,INFO*8,INFI*8

CA 06422 Rev. 0 Page 28 of 46 10 CONTINUE PRINT I I I I FORMAT(f////,2XWHlAT IS THE NAME OF THE INPUT FILE:

+ '(8 CHARACTERS LENGTH)'/, ? )

READ(-,50) INFI 50 FORMAT(A8)

IF(IERROR .EQ. 0) GO TO 12 PRINT 60 60 FORMAT(' CANNOT FIND FILE PLEASE TRY AGAIN',/I))

GO TO 10 12 OPEN(I 0,FILE=INFISTATUS='OLD',IOSTAT=IERROR)

READ(10,50) INFP READ(10,50) INFE READ(10,50) INFN READ(10,50) INFO OPEN(6,FILE=INFP,STATUS='UNKNOWN')

c OPEN(7,FILE=INFE,STATUS='JNKNOWN')

c OPEN(8,FILE=INFN,STATUS='UNKNOWN')

OPEN(9,FILE=INFOSTATUS='OLD',IOSTAT=IERROR)

RETURN END

CA06422 Rev.O Page 29 of 46 ATTACHMENT B FILE CRCB.SED CRCB.PUN CRCB.XLS CRCB.NIF CRCB.OUT 2754.0 1511 7 73 72 72 Nuclide Inventory Name:

Normalized MACCS Sample 3412 MWth PWR Core Inventory Power Level:

O.IOOOE+0O Nuclides:

65 Nuclide 001:

Co-58 7

0.6117120000E+07 0.5800E+02 0.2553E+03 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 002:

Co-60 7

0.1663401096E+09 0.6000E+02 0.1953E+03 none 0.OOOOE+00 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 003:

Kr-85 1

0.3382974720E+09 0.8500E+02 0.1960E+03 none 0.OOOOE+00 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 004:

Kr-85m I

0.1612800000E+05 0.8500E+02 0.9181E+04 Kr-85 0.2100E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 005:

Kr-87 I

0.4578000000E+04 0.8700E+02 0.1678E+05 Rb-87 O.IOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 006:

Kr-88 I

0.1022400000E+05 0.8800E+02

CA 06422 Rev.0 Page 30 of 46 0.2269E+05 Rb-88 0.lOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 007:

Rb-86 3

0.1612224000E+07 0.8600E+02 0.1496E+02 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 008:

Sr-89 S

0.4363200000E+07 0.8900E+02 0.2844E+05 none 0.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 009:

Sr-90 5

0.9189573120E+09 0.9000E+02 0.1535E+04 Y-90 O.lOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 010:

Sr-91 5

0.3420000000E+05 0.9100E+02 0.3656E+05 Y-91m 0.5800E+00 Y-91 0.4200E+00 none O.OOOOE+00 Nuclide 011:

Sr-92 5

0.9756000000E+04 0.92003E+02 0.3805E+05 Y-92 0.1000E+01 none O.OOOE+00 none O.OOOOE+00 Nuclide 012:

Y-90 9

0.2304000000E+06 0.9000E+02 0.1647E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 013:

Y-91 9

0.5055264000E+07 0.9100E+02 0.3465E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 014:

CA 06422 RevcO Page 31 of 46 Y-92 9

0.1274400000E+05 0.9200E+02 0.3819E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 015:

Y-93 9

0.3636000000E+05 0.9300E+02 0.4320E+05 Zr-93 0.lOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 016:

Zr-95 9

0.5527872000E+07 0.9500E+02 0.4377E+05 Nb-95m 0.7000E-02 Nb-95 0.9900E+00 none O.OOOOE+00 Nuclide 017:

Zr-97 9

0.6084000000E+05 0.9700E+02 0.4562E+05 Nb-97m 0.9500E+00 Nb-97 0.5300E-01 none O.OOOOE+00 Nuclide 018:

Nb-95 9

0.3036960000E+07 0.9500E+02 0.4138E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 019:

Mo-99 7

0.2376000000E+06 0.9900E+02 0.4830E+05 Tc-99m 0.8800E+00 Tc-99 0.1200E+00 none O.OOOOE+00 Nuclide 020:

Tc-99m 7

0.2167200000E+05 0.9900E+02 0.4169E+05 Tc-99 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 021:

Ru-103 7

0.3393792000E+07 0.1030E1+03 0.3598E+05

CA06422 Rev.O Page 32 of 46 Rh-103m 0.IOOOE+0I none O.OOOOE+00 none O.OOOOE+00 Nuclide 022:

Ru-105 7

0.1598400000E+05 0.1050E+03 0.2340E+05 Rh-105 0.IOOOE+OI none O.OOOOE+00 none O.OOOOE+00 Nuclide 023:

Ru-106 7

0.3181248000E+08 0.1060E+03 0.8175E+04 Rh-106 0.IOOOE+0O none O.OOOOE+00 none O.OOOOE+00 Nuclide 024:

Rh-105 7

0.1272960000E+06

0. 1050E+03 0.1621E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 025:

Sb-127 4

0.3326400000E+06 0.1270E+03 0.2208E+04 Te-127m 0.1800E+00 Te-127 0.8200E+00 none O.OOOOE+00 Nuclide 026:

Sb-129 4

0.1555200000E+05 0.1290E+03 0.7820E+04 Te-129m 0.2200E+00 Te-129 0.7700E+00 none O.OOOOE+00 Nuclide 027:

Te-127 4

0.3366000000E+05 0.1270E+03 0.2132E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 028:

Te-1 27m 4

0.9417600000E+07 0.1270E+03 0.2823E+03 Te-127 0.9800E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 029:

Te-129

CA 06422 Rev. 0 Page 33 of 46 4

0.4176000000E+04 0.1290E+03 0.7341 E+04 1-129 O.IOOOE+01 none O.00OE+00 none O.OOOOE+OO Nuclide 030:

Te-129m 4

0.2903040000E+07 0.1290E+03 0.1935E+04 Te-129 0.6500E+00 1-129 0.3500E+00 none O.OOOOE+00 Nuclide 031:

Te-131m 4

0.1080000000E+06 0.1310E+03 0.3707E+04 Te-131 0.2200E+00 1-131 0.7800E+00 none O.OOOOE+00 Nuclide 032:

Te-132 4

0.2815200000E+06 0.1320E+03 0.3690E+05 1-132 O.IOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 033:

1-131 2

0.6946560000E+06 0.1310E+03 0.2540E+05 Xe-131m 0.1100E-01 none O.00OE+00 none O.OOOOE+00 Nuclide 034:

1-132 2

0.8280000000E+04 0.1320E+03 0.3743E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOE+00 Nuclide 035:

1-133 2

0.7488000000E+05 0.1330E+03 0.5370E+05 Xe-133m 0.2900E-01 Xe-133 0.9700E+00 none O.OOOOE+00 Nuclide 036:

1-134 2

0.3156000000E+04 0.1340E+03 0 5893E+05 none O.OOOOE+00

- -

CA 06422 Rev. 0 Page 34 of 46 none O.OOOOE+00 none O.OOOOE+00 Nuclide 037:

1-135 2

0.2379600000E+05 0.1350E+03 0.5063E+05 Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none O.OOOOE+00 Nuclide 038:

Xe-133 0.4531680000E+06 0.1330E+03 0.5372E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 039:

Xe-135 0.3272400000E+05 0.1350E+03 0.1008E+05 Cs-135 0.IOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 040:

Cs-134 3

0.6507177120E+08 0.1340E+03 0.3425E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 041:

Cs-136 3

0.1131840000E+07 0.1360E+03 0.1042E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 042:

Cs-137 3

0.9467280000E+09 0.1370E+03 0.1915E+W4 Ba-137m 0.9500E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 043:

Ba-139 6

0.4962000000E+04 0.1390E+03 0.4976E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 044:

Ba-140 6

CA 06422 Rev.O Page 35 of 46 0.1100736000E+07 0.1400E+03 0.4924E+05 La-140 0.IOOOE+OI none O.OOOOE+00 none O.OOOOE+00 Nuclide 045:

La-140 9

0.1449792000E+06 0.1400E+03 0.5032E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 046:

La-141 9

0.1414800000E+05 0.1410E+03 0.4615E+05 Ce-141 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 047:

La-142 9

0.5550000000E+04 0.1420E+03 0.4449E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 048:

Ce-141 8

0.2808086400E+07 0.1410E+03 0.4476E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 049:

Ce-143 8

0.1188000000E+06 0.1430E+03 0.4352E+05 Pr-143 0.IOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 050:

Ce-144 8

0.2456352000E+08 0.1440E+03 0.2697E+05 Pr-144m 0.1800E-01 Pr-144 0.9800E+00 none O.OOOOE+00 Nucl ide 051:

Pr-143 9

0.1 171584000E+07 0.1430E+03 0.4273E+05 none O.OOOOE+00 none O.OOOOE+00

CA06422 Rev.0 Page 36 of 46 none O.OOOOE+00 Nuclide 052:

Nd-147 9

0.9486720000E+06 0.1470E+03 0.1911 E+05 Pm-147 O.IOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 053:

Np-239 8

0.2034720000E+06 0.2390E+03 0.5120E+06 Pu-239 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 054:

Pu-238 8

0.2768863824E+10 0.2380E+03 0.2902E+02 U-234 O.IOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 055:

Pu-239 8

0.7594336440E+12 0.2390E+03 0.6545E+01 U-235 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 056:

Pu-240 8

0.2062920312E+12 0.2400E+03 0.8254E+01 U-236 O.IOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 057:

Pu-241 8

0.4544294400E+09 0.2410E+03 0.1390E+04 U-237 0.2400E-04 Am-241 O.OOOE+01 none O.OOOOE+00 Nuclide 058:

Am-241 9

0.1363919472E+1 I 0.2410E+03 0.9181 E+00 Np-237 O.IO0OE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 059:

Cm-242 9

0.1406592000E+08

CA 06422 Rev.0 Page 37 of 46 0.2420E+03 0.3514E+03 Pu-238 O.IOOOE+01 none O.OOOOE+00 none O.OOOOE+OO Nuclide 060:

Cm-244 9

0.571508136E+9 0.2440E+03 0.2056E+02 Pu-240 O.IOOOE+01 none 0.OOOOE+0O none O.OOOOE+OO Nuclide 061:

Kr-83m 1

6.6960000000E+03 0.8300E+02 I .OOOOE+00 Kr-83 O.IOOOE+0I none O.OOOOE+00 none O.OOOOE+00 Nuclide 062:

Xe-131m I

1.0282000000E+06 0.1310E+03 I .OOOOE+00 Xe-131 0.IOOOE+OI none O.OOOOE+00 none O.OOOOE+00 Nuclide 063:

Xe-133m 1.8922000000E+05 0.1330E+03 I .OOOOE+00 Xe-133 O.IOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 064:

Xe-135m I

9.1800000000E+02 0.1350E+03 1.OOOOE+00 Xe-135 O.IOOOE+OI none O.OOOOE+00 none O.OOOOE+00 Nuclide 065:

Xe-138 8.4600000000E+02 0.1380E+03 I .OOOOE+00 none O.OOOOE+0O none O.OOOOE+00 none 0.OOOOE+00 End of Nuclear Inventory File

CA 06422 Rev.0 Page 38 of 46 ATTACHMENT C FILE CRCB.PUN POWER = 2754.000 MWTHI NI = 15 N2 = II N3 = 7 NT = 33 NAI = 73 NA2 = 72 NA3 = 72 NAT = 217 kr85 kr85m kr87 kr8S br85 br87 br88 se85 se87 se88 sbl32 sbl33 sbl34 sbl35 tc131 tel31m tel32 tel33 tel33m tel34 tel35 tel38 il31 i132 il33 il34 il35 il38 xel33 xel33m xel35 xeI35m xel38 ASSEMBLY ISOTOPIC DATA IN GRAM ATOMS 46.2 d 9.23E-03 2.47E-04 1.44E-04 4.54E-04 2.64E-06 1.41E-06 4.23E-07 2.06E-07 5.45E408 7.46E-09 4.51E406 4.89E-06 5.42E-09 4.25E-09 5.25E-05 5.90E-04 1.64E-02 3.85E-45 1.40E-04 2.27E-04 8.50E-07 2.12E-09 2.67E-02 4.84E-04 6.68E-03 3.24E-04 1.99E-03 1.43E-07 3.80E-02 4.51E-04 8.26E-04 1.45E-05 7.02E-45 92.4 d 1.81E-02 2.38E-04 1.39E-04 4.37E-04 2.55E-06 1.35E-06 4.04E-07 I.98E-07 5.20E-08 7.13E-09 4.58E-06 4.76E-06 5.23E-09 4.15E-09 5.27E-05 6.37E-04 1.65E-02 3.80E-05 1.39E-04 2.23E-04 8.38E-07 2.09E409 2.75E-02 4.88E-04 6.66E-03 3.21E-04 1.99E-03 1.41E-07 3.81E-02 4.55E-04 8.31E-04 1.48E-05 6.92E-05 138.6 d 2.67E402 2.31E-04 1.34E-04 4.22E-04 2.47E-06 1.31E-06 3.89E-07 1.91E-07 5.OOE-08 6.86E-09 4.64E-06 4.66E406 5.08E-09 4.08E-09 5.29E-05 6.75E-04 1.66E-02 3.77E-05 1.38E-04 2.19E-04 8.28E-07 2.06E-09 2.78E-02 4.91E-04 6.65E-03 3.19E-04 1.98E-03 1.40E-07 3.80E-02 4.58E-04 8.31E-04 1.50E-05 6.83E-05 184.8 d 3.49E-02 2.25E-04 1.30E-04 4.09E-04 2.40E-06 1.27E-06 3.75E-07 1.85E-07 4.82E-08 6.63E-09 4.69E-06 4.58E-06 4.96E-09 4.03E-09 5.30E-45 7.06E-04 1.67E-02 3.74E-05 1.37E-04 2.15E-04 8.21E-07 2.04E-09 2.81E-02 4.94E-04 6.64E-03 3.18E-04 1.98E-03 1.38E-07 3.80E-02 4.61E-04 8.28E-04 1.52E-05 6.76E-05 230.9 d 4.29E-02 2.19E-04 1.27E-04 3.97E-04 2.34E-06 1.23E-06 3.63E-07 1.80E-07 4.65E-08 6.42E-09 4.73E406 4.51E-06 4.85E-09 3.99E-09 5.31E-05 7.33E-04 1.68E-02 3.71E-05 1.36E-04 2.13E-04 8.15E-07 2.03E-09 2.83E-02 4.96E-04 6.63E-03 3.16E-04 1.98E-03 1.37E-07 3.80E-02 4.63E-04 8.21E-04 1.54E-05 6.70E-05 277.1 d 5.05E-02 2.14E404 1.23E-04 3.86E-04 2.28E-06 1.19E-06 3.52E-07 1.75E-07 4.51E-08 6.24E-09 4.77E-06 4.45E-06 4.76E-09 3.96E-09 5.32E-05 7.56E-04 1.68E-02 3.69E4-5 1.35E-04 2.10E404 8.10E-07 2.02E-09 2.84E-02 4.98E-04 6.61E-03 3.15E-04 1.97E-03 1.36E-07 3.79E-02 4.64E-04 8.13E-04 1.56E-05 6.64E-05 323.3 d 5.80E-02 2.09E-04 1.20E-04 3.76E-04 2.23E-06 1.16E-06 3.42E-07 1.71E-07 4.37E-08 6.07E-09 4.80E-06 4.40E-06 4.68E-09 3.93E-09 5.32E405 7.76E-04 1.68E-02 3.66E-05 1.34E-04 2.08E-04 8.05E-07 2.02E-09 2.86E-02 5.OOE-04 6.60E-03 3.13E-04 1.97E-03 1.36E-07 3.79E-02 4.66E-04 8.02E-04 1.57E-05 6.59E-05 369.5 d 6.52E-02 2.04E-04 1.17E404 3.67E-04 2.17E-06 1.13E406 3.32E-07 1.67E-07 4.25E-08 5.91E-09 4.83E-06 4.35E-06 4.61E-09 3.91E-09 5.33E-05 7.94E-04 1.69E-02 3.65E-05 1.33E-04 2.05E-04 8.02E-07 2.02E-09 2.87E-02 5.01E-04 6.59E-03 3.12E-04 1.97E-03 1.35E-07 3.78E-02 4.67E-04 7.89E-04 1.58E405 6.55E-05 415.7 d 7.22E-02 1.99E-04 l.l5E-04 3.58E-04 2.13E-06 I.IIE-06 3.23E-07 1.63E-07 4.13E-08 5.76E-09 4.86E-06 4.31E-06 4.54E-09 3.90E-09 5.33E-05 8.10E-04 1.69E-02 3.63E-05 1.33E-04 2.04E-04 7.99E-07 2.02E-09 2.88E-02 5.02E-04 6.58E-03 3.1 1E-04 1.97E-03 1.35E-07 3.78E402 4.68E-04 7.75E-04 1.59E-05 6.50E-05 461.9 d 7.90E-02 1.95E-04 1.12E-04 3.50E-04 2.08E-06 1.08E-06 3.15E-07 1.59E-07 4.02E-08 5.62E-09 4.88E-06 4.28E-06 4.49E-09 3.89E-09 5.33E-05 8.24E-04 1.69E-02 3.61E-05 1.32E-04 2.02E-04 7.96E-07 2.02E-09 2.89E-02 5.03E-04

CA 06422 Rev. 0 Page 39 of 46 6.57E-03 3.10E-04 1.97E-03 1.34E-07 3.77E-02 4.69E-04 7.59E-04 1.60E-05 6.46E-05 508.1 d 8.55E-02 1.91E-04 l.OE-04 3.42E-04 2.04E-06 1.06E-06 3.07E-07 1.56E-07 3.92E-08 5.49E-09 4.90E-06 4.24E-06 4.43E-09 3.88E-09 5.33E-05 8.37E-04 1.69E-02 3.60E-05 1.32E-04 2.00E-04 7.94E-07 2.02E-09 2.90E-02 5.04E-04 6.56E-03 3.09E-04 1.96E-03 1.34E-07 3.77E-02 4.70E-04 7.43E-04 1.61E-05 6.43E-05 554.3d 9.19E-02 1.87E-04 1.07E-04 3.34E-04 2.00E-06 1.03E-06 2.99E-07 1.52E-07 3.82E-08 5.37E-09 4.92E-06 4.21E-06 4.38E-09 3.88E-09 5.33E-05 8.48E-04 1.70E-02 3.58E-05 1.31E-04 1.98E-04 7.92E-07 2.03E-09 2.91E-02 5.04E-04 6.55E-03 3.08E-04 1.96E-03 1.34E-07 3.76E-02 4.71E-04 7.25E-04 1.62E-05 6.39E-05 600.5 d 9.81E-02 1.83E-04 1.05E-04 3.26E-04 1.96E-06 1.OIE-06 2.92E-07 1.49E-07 3.72E-08 5.25E-09 4.94E-06 4.18E-06 4.34E-09 3.88E-09 5.33E-05 8.59E-04 1.70E-02 3.57E-05 1.31E-04 1.97E-04 7.91E-07 2.042-09 2.91E-02 5.05E-04 6.54E-03 3.07E-04 1.96E-03 1.33E-07 3.76E-02 4.72E-04 7.07E-04 1.63E-05 6.36E-05 646.7d 1.04E-0 1.80E-04 1.03E-04 3.19E-04 1.92E-06 9.87E-07 2.85E-07 1.46E-07 3.63E-08 5.13E-09 4.95E-06 4.15E-06 4.30E-09 3.88E-09 5.33E-05 8.70E-04 1.70E-02 3.55E-05 1.30E-04 1.95E-04 7.89E-07 2.04E-09 2.92E-02 5.05E-04 6.53E-03 3.06E-04 1.96E-03 1.33E-07 3.75E-02 4.72E-04 6.89E-04 1.64E-05 6.32E-05 668.3 d 1.07E-01 1.78E-04 1.02E-04 3.16E-04 1.90E-06 9.77E-07 2.81E-07 1.44E-07 3.59E-08 5.09E-09 4.97E-06 4.15E-06 4.29E-09 3.89E-09 5.33E-05 8.75E-04 1.70E-02 3.55E-05 1.30E-04 1.95E-04 7.90E-07 2.06E-09 2.92E-02 5.09E-04 6.50E-03 3.06E-04 1.96E-03 1.33E-07 3.94E-02 5.15E-04 6.83E-04 1.64E-05 6.31 E-05 702.7 d l.OE-01 1.25E-04 7.12E-05 2.21E-04 1.33E-06 6.85E-07 1.97E-07 1.OIE-07 2.53E-08 3.66E-09 3.54E-06 2.98E-06 3.11E-09 2.90E-09 3.81E-05 6.27E-04 1.21E-02 2.53E-05 9.20E-05 1.38E-04 5.67E-07 1.58E-09 2.13E-02 3.62E-04 4.63E-03 2.18E-04 1.40E-03 9.58E-08 2.83E-02 3.68E-04 6.54E-04 1.17E-05 4.48E-05 767.4 d 1.15E-01 1.22E-04 6.94E-05 2.15E-04 1.29E-06 6.67E-07 1.912E-0 9.86E-08 2.45E-08 3.56E-09 3.55E-06 2.95E-06 3.07E-09 2.89E-09 3.81E-05 6.38E-04 1.21E-02 2.52E-05 9.15E-05 1.37E-04 5.65E-07 1.58E-09 2.07E-02 3.61E-04 4.64E-03 2.17E-04 1.40E-03 9.56E-08 2.67E-02 3.44E-04 6.44E-04 1.18E-05 4.45E-05 832.0d 1.20E-01 1.19E-04 6.77E-05 2.09E-04 1.26E-06 6.50E-07 1.86E-07 9.62E-08 2.38E-08 3.47E-09 3.56E-06 2.93E-06 3.03E-09 2.89E-09 3.81E-05 6.46E-04 1.21E-02 2.51E-05 9.12E-05 1.36E-04 5.64E-07 1.58E-09 2.07E-02 3.61E-04 4.63E-03 2.16E-04 1.39E-03 9.54E-08 2.67E-02 3.44E-04 6.33E-04 1.18E-05 4.43E-05 896.7 d 1.25E-01 1.16E-04 6.61E-05 2.04E-04 1.24E-06 6.34E-07 1.81E-07 9.40E-08 2.32E-08 3.39E-09 3.57E-06 2.91E-06 3.00E-09 2.88E-09 3.81E-05 6.53E-04 1.21E-02 2.50E-05 9.08E-05 1.35E-04 5.63E-07 1.58E-09 2.08E-02 3.62E-04 4.62E-03 2.15E-04 1.39E-03 9.52E-08 2.67E-02 3.45E-04 6.20E-04 1.19E-05 4.40E-05 961.4d 1.29E-01 1.14E-04 6.47E-05 1.99E-04 1.21E-06 6.19E-07 1.76E-07 9.18E-08 2.25E-08 3.31E-09 3.59E-06 2.89E-06 2.97E-09 2.88E-09 3.81E-05 6.60E-04 1.21E-02 2.49E-05 9.04E-05 1.34E-04 5.62E-07 1.59E-09 2.08E-02 3.62E-04 4.62E-03 2.14E-04 1.39E-03 9.50E-08 2.66E-02 3.45E-04 6.06E-04 1.19E-05 4.38E-05 1026.0 d 1.34E-01 1.1IE-04 6.32E-05 1.95E-04 1.19E-06 6.05E-07 1.71E-07 8.98E-08 2.19E-08 3.23E-09 3.60E-06 2.87E-06 2.94E-09 2.88E-09 3.80E-05 6.66E-04 1.21E-02 2.48E-05 9.01E-05 1.33E-04 5.61E-07 1.59E-09 2.08E-02 3.62E-04 4.61E-03 2.14E-04 1.39E-03 9.49E-08 2.66E-02 3.45E-04 5.92E-04 1.20E-05 4.36E-05 1090.7 d 1.38E-01 1.09E-04 6.19E-05 1.90E-04 1.16E-06 5.92E-07 1.67E-07 8.79E-08 2.14E-08 3.16E-09 3.60E-06 2.86E-06 2.92E-09 2.87E-09 3.80E-05 6.71E-04 1.21E-02 2.47E-05 8.98E-05 1.32E-04 5.60E-07 1.59E-09 2.08E-02 3.62E-04 4.60E-03 2.13E-04 1.39E-03 9.48E-08 2.66E-02 3.46E-04 5.77E-04 1.20E-05 4.34E-05 1155.4d 1.42E-01 1.07E-04 6.06E-05 1.86E-04 1.14E-06 5.79E-07 1.63E-07 8.60E-08 2.08E-08 3.09E-09 3.61E-06 2.84E-06 2.89E-09 2.87E-09 3.80E-05 6.77E-04 1.21E-02 2.46E-05 8.95E-05 1.31E-04 5.59E-07 1.59E-09 2.09E-02 3.62E-04 4.59E-03 2.131.-04 1.39E-03 9.46E-08 2.65E-02 3.46E-04 5.62E-04 1.21E4-5 4.32E-05 1220.1 d

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CA 06422 Rev.0 Page 40 of 46 1.46E-01 1.05E-04 5.93E-05 1.82E-04 1.12E-06 5.66E-07 1.59E-07 8.42E-08 2.03E-08 3.02E-09 3.62E-06 2.82E-06 2.87E-09 2.87E-09 3.80E-05 6.82E-04 1.21 E-02 2.46E-05 8.91E-05 1.30E-04 5.58E-07 1.59E-09 2.09E-02 3.62E-04 4.59E-03 2.12E-04 1.39E-03 9.45E-08 2.65E-02 3.46E-04 5.46E-04 1.21E-05 4.30E-05 1284.7 d 1.50E-01 1.03E-04 5.81 E-05 1.78E-04 1.09E-06 5.54E-07 1.55E-07 8.25E-08 1.98E-08 2.96E-09 3.63E-06 2.81E-06 2.84E-09 2.87E-09 3.79E-OS 6.86E-04 1.21 E-02 2.45E-05 8.88E-05 1.30E-04 5.57E-07 1.59E-09 2.09E-02 3.62E-04 4.58E-03 2.11 E-04 1.392-03 9.44E-08 2.65E-02 3.46E-04 5.30E-04 1.21E-05 4.29E-05 1336.6 d 1.53E-01 1.0IE-04 5.71 E-05 1.75E-04 1.08E-06 5.44E-07 1.52E-07 8.11E-08 1.94E-08 2.92E-09 3.63E-06 2.802-06 2.84E-09 2.88E-09 3.79E-05 6.90E-04 1.21 E-02 2.44E-05 8.86E-05 1.29E-04 5.57E-07 1.61E-09 2.09E-02 3.62E-04 4.57E-03 2.11E-04 1.38E-03 9.45E-08 2.64E-02 3.42E-04 5.22E-04 1.22E-05 4.272-05 1358.0 d 1.53E-01 6.02E-05 3.40E-OS 1.04E-04 6.38E-07 3.25E-07 9.08E-08 4.83E-08 1.17E-08 1.81E-09 2.172-06 1.70E-06 1.75E-09 1.81 E-09 2.27E-05 4.09E-04 7.32E-03 IA72-05 5.28E-05 7.74E-05 3.37E-07 1.04E-09 1.40E-02 2.202-04 2.72E2-03 1.26E-04 8.29E-04 5.72E-08 1.73E-02 2.222-04 4.70E-04 7.27E-06 2.55E-05 1465.7 d 1.56E-01 5.88E-05 3.32E-05 1.0 1 E-04 6.24E-07 3.16E-07 8.81E-08 4.71 E-08 1.14E-08 1.75E-09 2.17E-06 1.69E-06 1.72E-09 1.80E-09 2.27E-05 4.14E-04 7.27E-03 1.46E-05 5.26E-05 7.68E-05 3.36E-07 1.03E-09 1.25E-02 2.17E-04 2.73 E-03 1.26E-04 8.28E-04 5.70E-08 1.59E-02 2.22E-04 4.63E-04 7.292-06 2.54E-05 1573.5 d 1.58E-01 5.77E-05 3.25E-05 9.90E-05 6.11 E-07 3.09E-07 8.57E-08 4.61E-08 1.10-08 1.71E-09 2.18E-06 1.67E-06 1.70E-09 1.79E-09 2.27E-05 4.18E-04 7.27E-03 1.45E-05 5.24E-05 7.62E-05 3.35E-07 1.02E-09 1.26E-02 2.17E-04 2.73E-03 1.25E-04 8.27E-04 5.68E-08 1.59E-02 2.23E-04 4.54E-04 7.32E-06 2.53E-05 1681.3 d 1.60E-01 5.66E-05 3.18E-05 9.68E-05 6.00E-07 3.02E-07 8.35E-08 4.52E-08 1.07E-08 1.67E-09 2.18E-06 1.66E-06 1.68E-09 1.77E-09 2.27E-05 4.21 E-04 7.27E-03 1.45E-05 5.23E-OS 7.57E-05 3.34E-07 1.02E-09 1.26E-02 2.17E-04 2.72E-03 1.25E-04 8.26E-04 5.66E-08 1.59E-02 2.23E-04 4.44E-04 7.342-06 2.52E-05 1789.1 d 1.62E-01 5.56E-05 3.12E-05 9.49E-05 5.89E-07 2.962-07 8.152-08 4.43E-08 1.05E-08 1.63E-09 2.19E-06 1.65E-06 1.67E-09 1.76E-09 2.27E-05 4.24E-04 7.27E-03 1.44E-05 5.21E-05 7.53E-05 3.33E-07 1.0IE-09 1.26E-02 2.17E-04 2.72E-03 1.25E-04 8.252-04 5.65E-08 1.59E-02 2.23E-04 4.33E-04 7.36E-06 2.51E-05 1896.9 d 1.63E-01 5.47E-05 3.06E4-5 9.30E-05 5.79E-07 2.90E-07 7.96E-08 4.35E-08 1.02E-08 1.59E-09 2.19E-06 1.64E-06 1.65E-09 1.75E-09 2.27E-05 4.26E-04 7.26E-03 1.44E-05 5.20E-05 7.49E-05 3.32E-07 9.99E-10 1.26E-02 2.17E-04 2.71E-03 1.24E-04 8.24E-04 5.64E-08 1.592-02 2.23E-04 4.21E-04 7.38E-06 2.50E-05 2004.9 d 1.65E-01 5.38E-05 3.01 E-05 9.12E-05 5.69E-07 2.85E-07 7.79E-08 4.27E-08 9.99E-09 1.57E-09 2.19E-06 1.64E-06 1.64E-09 1.76E-09 2.26E-05 4.27E-04 7.26E-03 1.44E-05 5.18E-05 7.45E-05 3.32E-07 1.OIE-09 1.26E-02 2.17E-04 2.71E-03 1.24E-04 8.23E-04 5.64E-08 1.58E-02 2.23E-04 4.15E-04 7.38E-06 2.49E-05 ASSEMBLY ISOTOPIC DATA IN CURIES 46.2 d 3.07E+02 1.73E+05 3.55E+05 5.01E+05 1.73E+05 2.85E+05 2.91 E+05 7.26E+04 1.06E+05 5.61E+04 2.02E+05 3.68E405 7.64E+04 2.80E+04 3.95E+05 5.71E+04 6.69E+05 5.84E+05 4.75E+05 1.02E+06 5.05E+05 1.71E+04 4.35E+05 6.65E+05 1.0IE+06 1.16E+06 9.49E+05 2.48E+05 9.47E+05 2.69E+04 2.84E+05 1.78E+05 9.36E+05 92.4 d 6.02E+02 1.67E+05 3.43E+05 4.82E+05 1.67E+05 2.72E+05 2.78E+05 6.98E+04 1.0 1 E+05 5.36E+04 2.05E+05 3.58E+05 7.38E+04 2.74E+04 3.96E+05 6.16E+04 6.73E+05 5.76E+05 4.72E+05 9.98E+05 4.98E405 1.68E+04 4.482+05 6.71E+05 1.00E+06 1.15E+06 9.49E+05 2.45E+05 9.49E+05 2.71E+04 2.86E+05 1.82E+05 9.23E+05 138.6 d 8.88E+02 1.621.+05 3.31E+05 4.66E+05 1.62E+05 2.64E+05 2.68E+05 6.73E+04 9.73E+04 5.16E+04 2.08E+05 3.51E+05 7.16E+04 2.691+04 3.98E+05 6.53E+04 6.77E+05 5.72E+05 4.68E+05 9.81 E+05 4.92E+05 1.66E+04 4.53E+05 6.75E+05 I.00E+06 1.141 +06 9.45E+05 2.43E+05 9.47E+05 2.73E+04 2.86E+05 1.84E+05 9.11 E+05 184.8 d 1.16E+03 1.571.+05 3.21E+05 4.51E+05 1.57E+05 2.56E+05 2.58E+05 6.52E+04 9.38E+04 4.99E+04 2.10E+05 3.45E+05

CA 06422 Rev.0 Page 41 of 46 7.00E+04 2.66E+04 3.99E+05 6.83E+04 6.82E+05 5.67E+05 4.65E+05 9.63E+05 4.88E+05 1.64E+04 4.58E+05 6.79E+05 l.OOE+06 1.14E+06 9.45E+05 2.40E+05 9.47E+05 2.75E+04 2.85E+05 1.87E+05 9.02E+05 230.9 d 1.43E+03 1.53E+05 3.13E+05 4.38E+05 1.53E+05 2.48E+05 2.50E+05 6.35E+04 9.05E+04 4.83E+04 2.12E+05 3.39E+05 6.84E+04 2.63E+04 3.99E+05 7.09E+04 6.86E+05 5.63E+05 4.62E+05 9.54E+05 4.84E+05 1.64E+04 4.61E+05 6.82E+05 9.99E+05 1.13E+06 9.45E+05 2.38E+05 9.47E+05 2.76E+04 2.83E+05 1.89E+05 8.94E+05 277.1 d 1.68E+03 1.50E+05 3.04E+05 4.26E+05 1.49E+05 2.40E+05 2.42E+05 6.17E+04 8.77E+04 4.69E+04 2.14E+05 3.35E+05 6.71 E+04 2.61 E+04 4.00E+05 7.31E+04 6.86E+05 5.60E+05 4.58E+05 9.40E+05 4.81E+05 1.63E+04 4.62E+05 6.85E+05 9.96E+05 1.13E+06 9.40E+05 2.36E+05 9.44E+05 2.77E+04 2.80E+05 1.92E+05 8.86E+05 323.3 d 1.93E+03 1.46E+05 2.96E+05 4.15E+05 1.46E+05 2.34E+05 2.35E+05 6.03E+04 8.50E+04 4.57E+04 2.15E+05 3.31E+05 6.60E+04 2.59E+04 4.OOE+05 7.51 E+04 6.86E+05 5.55E+05 4.55E+05 9.31E+05 4.78E+05 1.63E+04 4.66E+05 6.87E+05 9.95E+05 1.12E+06 9.40E+05 2.36E+05 9.44E+05 2.78E+04 2.76E+05 1.93E+05 8.79E+05 369.5 d 2.17E+03 1.43E+05 2.89E+05 4.05E+05 1.42E+05 2.28E+05 2.28E+05 5.89E+04 8.27E+04 4.45E+04 2.16E+05 3.27E+05 6.50E+04 2.58E+04 4.01E+05 7.68E+04 6.90E+05 5.54E+05 4.51E+05 9.18E+05 4.76E+05 1.63E+04 4.67E+05 6.89E+05 9.93E+05 1.12E+06 9.40E+05 2.34E+05 9.42E+05 2.78E+04 2.72E+05 1.94E+05 8.74E+05 415.7 d 2.40E+03 1.39E+05 2.84E+05 3.95E+05 1.40E+05 2.24E+05 2.22E+05 5.75E+04 8.03E+04 4.33E+04 2.18E+05 3.24E+05 6.40E+04 2.57E+04 4.01E+05 7.84E+04 6.90E+05 5.51E+05 4.51E+05 9.13E+05 4.74E+05 1.63E+04 4.69E+05 6.90E+05 9.92E+05 1.IIE+06 9.40E+05 2.34E+05 9.42E+05 2.79E+04 2.67E+05 1.95E+05 8.67E+05 461.9 d 2.63E+03 1.36E+05 2.76E+05 3.86E+05 1.36E+05 2.18E+05 2.17E+05 5.61E+04 7.82E+04 4.23E+04 2.19E+05 3.22E+05 6.33E+04 2.57E+04 4.01E+05 7.97E+04 6.90E+05 5.47E+05 4.48E+05 9.04E+05 4.73E+05 1.63E+04 4.71E+05 6.91E+05 9.90E+05 1.1IE+06 9.40E+05 2.33E+05 9.39E+05 2.80+W04 2.61E+05 1.97E+05 8.62E+05 508.1 d 2.84E+03 1.34E+05 2.71E+05 3.77E+05 1.34E+05 2.14E+05 2.11E+05 5.50E+04 7.63E+04 4.13E+04 2.19E+05 3.19E+05 6.25E+04 2.56E+04 4.01E+05 8.1OE+04 6.90E+05 5.46E+05 4.48E+05.8.96E+05 4.72E+05 1.63E+04 4.72E+05 6.93E+05 9.88E+05 I.IOE+06 9.35E+05 2.33E+05 9.39E+05 2.80E+04 2.56E+05 1.98E+05 8.58E+05 554.3 d 3.06E+03 1.31E+05 2.64E+05 3.69E+05 1.31E+05 2.08E+05 2.06E+05 5.36E+04 7.43E+04 4.04E+04 2.20E+05 3.17E+05 6.18E+04 2.56E+04 4.01E+05 8.20E+04 6.94E+05 5.43E+05 4.45E+05 8.87E+05 4.70E+05 1.64E+04 4.74E+05 6.93E+05 9.87E+05 I.IOE+06 9.35E+05 2.33E+05 9.37E+05 2.81E+04 2.50E+05 1.99E+05 8.52E+05 600.5 d 3.26E+03 1.28E+05 2.59E+05 3.60E+05 1.28E+05 2.04E+05 2.01 E+05 5.25E+04 7.24E+04 3.95E+04 2.21E+05 3.14E+05 6.12E+04 2.56E+04 4.01E+05 8.312E+04 6.94E+05 5.41 E+05 4.45E+05 8.82E+05 4.70E+05 1.64E+04 4.74E+05 6.94E+05 9.85E+05 I.IOE+06 9.35E+05 2.31 E+05 9.37E+05 2.81 E+04 2.44E+05 2.00E+05 8.48E+05 646.7 d 3.46E+03 1.26E+05 2.54E+05 3.52E+05 1.26E+05 1.99E+05 1.96E+05 5.15E+04 7.06E+04 3.86E+04 2.22E+05 3.12E+05 6.06E+04 2.56E+04 4.01E+05 8.42E+04 6.94E+05 5.38E+05 4.41 E+05 8.73E+05 4.69E+05 1.64E+04 4.75E+05 6.94E+05 9.84E+05 1.09E+06 9.35E+05 2.31E+05 9.34E+05 2.81 E+04 2.37E+05 2.02E+05 8.43E+05 668.3 d 3.56E+03 1.25E+05 2.52E+05 3.49E+05 1.24E+05 1.97E+05 1.93E+05 5.08E+04 6.98E+04 3.83E+04 2.23E+05 3.12E+05 6.05E+04 2.57E+04 4.01E+05 8.46E+04 6.94E+05 5.38E+05 4.41 E+05 8.73E+05 4.69E+05 1.66E+04 4.75E+05 7.00E+05 9.79E+05 1.09E+06 9.35E+05 2.31E+05 9.81 E+05 3.07E+04 2.35E+05 2.02E+05 8.42E+05 702.7 d 3.66E+03 8.75E+04 1.76E+05 2.44E+05 8.71 E+04 1.38E+05 1.36E+05 3.56E+04 4.92E+04 2.75E+04 1.59E+05 2.24E+05 4.39E+04 1.91E+04 2.87E+05 6.07E+04 4.94E+05 3.84E+05 3.12E+05 6.18E+05 3.37E+05 1.27E+04 3.47E+05 4.98E+05 6.98E+05 7.79E+05 6.68E+05 1.66E+05 7.05E+05 2.19E+04 2.25E+05 1.44E+05 5.98E+05 767.4 d 3.82E+03 8.54E+04 1.71E+05 2.37E+05 8.45E+04 1.35E+05 1.31 E+05 3.48E+04 4.77E+04 2.68E+04 1.59E+05 2.22E+05 4.33E+04 1.91E+04 2.87E+05 6.17E+04 4.94E+05 3.82E+05 3.11 E+05 6.13E+05 3.36E+05 1.27E+04 3.37E+05 4.96E+05 6.99E+05 7.76E+05 6.68E+05 1.66E+05 6.65E+05 2.05E+04 2.22E+05 1.45E+05 5.94E+05

CA 06422 Rev.0 Page 42 of 46 832.0 d 3.99E+03 8.33E+04 1.67E+05 2.31E+05 8.26E+04 1.31 E+05 1.28E+05 3.39E+04 4.63E+04 2.61E+04 1.59E+05 2.20E+05 4.27E+04 1.91E+04 2.87E+05 6.25E+04 4.94E+05 3.81E+05 3.10E+05 6.09E+05 3.35E+05 1.27E+04 3.37E+05 4.96E+05 6.98E+05 7.72E+05 6.63E+05 1.66E+05 6.65E+05 2.05E+04 2.18E+05 1.45E+05 5.91E+05 896.7 d 4.16E+03 8.12E+04 1.63E+05 2.25E+05 8.13E+04 1.28E+05 1.25E+05 3.31E+04 4.51E+04 2.55E+04 1.60E+05 2.19E+05 4.23E+04 1.90E+04 2.87E+05 6.32E+04 4.94E+05 3.79E+05 3.08E+05 6.04E+05 3.34E+05 1.27E+04 3.39E+05 4.98E+05 6.96E+05 7.69E+05 6.63E+05 1.65E+05 6.65E+05 2.06E+04 2.14E+05 1.46E+05 5.87E+05 961.4 d 4.29E+03 7.98E+04 1.60E+05 2.20E+05 7.93E+04 1.25E+05 1.21 E+05 3.24E+04 4.38E+04 2.49E+04 1.61E+05 2.17E+05 4.19E+04 1.90E+04 2.87E+05 6.38E+04 4.94E+05 3.78E+05 3.07E+05 6.00E+05 3.34E+05 1.28E+04 3.39E+05 4.98E+05 6.96E+05 7.65E+05 6.63E+05 1.65E+05 6.63E+05 2.06E+04 2.09E+05 1.46E+05 5.84E+05 1026.0 d 4.46E+03 7.77E+04 1.56E+05 2.15E+05 7.80E+04 1.22E+05 1.18E+05 3.17E+04 4.26E+04 2.43E+04 1.61E+05 2.16E+05 4.15E+04 1.90E+04 2.86E+05 6.44E+04 4.94E+05 3.76E+05 3.06E+05 5.96E+05 3.33E+05 1.28E+04 3.39E+05 4.98E+05 6.95E+05 7.65E+05 6.63E+05 1.65E+05 6.63E+05 2.06E+04 2.04E+05 1.47E+05 5.82E+05 1090.7 d 4.59E+03 7.63E+04 1.53E+05 2.10E+05 7.60E+04 1.19E+05 1.15E+05 3.10E+04 4.16E+04 2.38E+04 1.61E+05 2.15E+05 4.12E+04 1.89E+04 2.86E+05 6.49E+04 4.94E+05 3.75E+05 3.05E+05 5.91E+05 3.33E+05 1.28E+04 3.39E+05 4.98E+05 6.93E+05 7.62E+05 6.63E+05 1.65E+05 6.63E+05 2.06E+04 1.99E+05 1.47E+05 5.79E+05 1155.4 d 4.72E+03 7.49E+04 1.50E+05 2.05E+05 7.47E+04 1.17E+05 1.12E+05 3.03E+04 4.05E+04 2.32E+04 1.62E+05 2.14E+05 4.08E+04 1.89E+04 2.86E+05 6.55E+04 4.94E+05 3.73E+05 3.04E+05 5.87E+05 3.32E+05 1.28E+04 3.40E+05 4.98E+05 6.92E+05 7.62E+05 6.63E+05 1.64E+05 6.60E+05 2.06E+04 1.94E+05 1.49E+05 5.76E+05 1220.1 d 4.85E+03 7.35E+04 1.46E+05 2.01E+05 7.34E+04 1.14E+05 1.09E+05 2.97E+04 3.95E+04 2.27E+04 1.62E+05 2.12E+05 4.05E+04 1.89E+04 2.86E+05 6.60E+04 4.94E+05 3.73E+05 3.02E+05 5.82E+05 3.31E+05 1.28E+04 3.40E+05 4.98E+05 6.92E+05 7.58E+05 6.63E+05 1.64E+05 6.60E+05 2.06E+04 1.88E+05 1.49E+05 5.74E+05 1284.7 d 4.99E+03 7.21E+04 1.43E+05 1.96E+05 7.14E+04 1.12E+05 1.07E+05 2.91E+04 3.85E+04 2.23E+04 1.63E+05 2.11E+05 4.01E+04 1.89E+04 2.85E+05 6.64E+04 4.94E+05 3.72E+05 3.01 E+05 5.82E+05 3.31 E+05 1.28E+04 3.40E+05 4.98E+05 6.90E+05 7.54E+05 6.63E+05 1.64E+05 6.60E+05 2.06E+04 1.83E+05 1.49E+05 5.72E+05 1336.6 d 5.09E+03 7.07E+04 1.41E+05 1.93E+05 7.08E+04 I.IOE+05 1.05E+05 2.86E+04 3.77E+04 2.20E+04 1.63E+05 2.11E+05 4.01E+04 1.90E+04 2.85E+05 6.67E+04 4.94E+05 3.70E+05 3.01 E+05 5.78E+05 3.31E+05 1.30E+04 3.40E+05 4.98E+05 6.89E+05 7.54E+05 6.58E+05 1.64E+05 6.58E+05 2.04E+04 1.80E+05 1.50E+05 5.70E+05 1358.0 d 5.09E+03 4.21E+04 8.39E+04 1.15E+05 4.18E+04 6.56E+04 6.25E+04 1.70E+04 2.28E+04 1.36E+04 9.72E+04 1.28E+05 2.47E+04 1.19E+04 1.71E+05 3.96E+04 2.99E+05 2.23E+05 1.79E+05 3.47E+05 2.00E+05 8.38E+03 2.28E+05 3.02E+05 4.10E+05 4.50E+05 3.95E+05 9.93E+04 4.31E+05 1.32E+04 1.62E+05 8.94E+04 3.40E+05 1465.7 d 5.19E+03 4.11E+04 8.19E+04 1.IIE+05 4.09E+04 6.38E+04 6.06E+04 1.66E+04 2.22E+04 1.32E+04 9.72E+04 1.27E+05 2.43E+04 1.19E+04 1.71E+05 4.00E+04 2.97E+05 2.21 E+05 1.79E+05 3.44E+05 2.00E+05 8.30E+03 2.04E+05 2.98E+05 4.11E+05 4.50E+05 3.95E+05 9.89E+04 3.96E+05 1.32E+04 1.59E+05 8.96E+04 3.39E+05 1573.5 d 5.25E+03 4.04E+04 8.02E+04 1.09E+05 4.00E+04 6.24E+04 5.90E+04 1.63E+04 2.14E+04 1.29E+04 9.762+04 1.26E+05 2.40E+04 1.18E+04 1.71E+05 4.04E+04 2.97E+05 2.20E+05 1.78E+05 3.41 E+05 1.99E+05 8.22E+03 2.05E+05 2.98E+05 4.11E+05 4.47E+05 3.95E+05 9.86E+04 3.96E+05 1.33E+04 1.56E+05 9.00E+04 3.37E+05 1681.3 d 5.32E+03 3.96E+04 7.85E+04 1.07E+05 3.93E+04 6.10E+04 5.74E+04 1.59E+04 2.08E+04 1.26E+04 9.76E+04 1.25E+05 2.37E+04 1.17E+04 1.71E+05 4.07E+04 2.97E+05 2.20E+05 1.78E+05 3.39E+05 1.98E+05 8.22E+03 2.05E+05 2.98E+05 4.10E+05 4.47E+05 3.94E+05 9.83E+04 3.96E+05 1.33E+04 1.53E+05 9.02E+04 3.36E+05 1789.1 d 5.39E+03 3.89E+04 7.70E+04 1.05E+05 3.86E+04 5.97E+04 5.61E+04 1.56E+04 2.04E+04 1.23E+04 9.81E+04 1.24E+05 2.36E+04 1.16E+04 1.71E+05 4.10E+04 2.97E+05 2.18E+05 1.77E+05 3.37E+05 1.98E+05 8.14E+03 2.05E+05 2.98E+05

CA06422 Rev.O Page 43 of 46 4.10E+05 4.47E+05 3.94E+05 9.81E+04 3.96E+05 1.33E+04 1.49E+05 9.05E+04 3.35E+05 1896.9 d 5.42E+03 3.83E+04 7.55E+04 1.03E+05 3.79E+04 5.85E+04 5.48E+04 1.53E+04 1.98E+04 1.20E+04 9.81E+04 1.23E+05 2.33E+04 1.15E+04 1.71E+05 4.12E+04 2.96E+05 2.18E+05 1.77E+05 3.35E+05 1.97E+05 8.05E+03 2.05E+05 2.98E+05 4.08E+05 4.43E+05 3.93E+05 9.79E+04 3.96E+05 1.33E+04 1.45E+05 9.07E+04 3.33E+05 2004.9 d 5.49E+03 3.76E+04 7.43E+04 1.0IE+05 3.73E+04 5.75E+04 5.36E+04 1.51E+04 1.94E+04 1.18E+04 9.81E+04 1.23E+05 2.31E+04 1.16E+04 1.70E+05 4.13E+04 2.96E+05 2.18E+05 1.76E+05 3.34E+05 1.97E+05 8.14E+03 2.05E+05 2.98E+05 4.08E+05 4.43E+05 3.93E+05 9.79E+04 3.94E+05 1.33E+04 1.43E+05 9.07E+04 3.32E+05 ISOTOPE AT WT DECAY(SEC) LAMBDA(1/S) SAS2H GRAMS CALC GRAMS SAS2}1 CURIES CALC CURIES kr85 85.00 3.39E+08 2.04E-09 1.4000E+01 1.4025E+01 5.5100E+03 5.4865E+03 kr85m 85.00 1.61E+04 4.30E-05 4.5700E-03 4.5730E-03 3.7600E+04 3.7639E+04 kr 87 87.00 4.57E+03 1.52E-04 2.6200E-03 2.6187E-03 7.4100E+04 7.4284E+04 kr 88 88.00 1.02E+04 6.78E-05 8.0200E-03 8.0256E-03 1.0100E+05 1.0065E+05 br 85 85.00 1.72E+02 4.03E-03 4.8400E-05 4.8365E-05 3.7300E+04 3.7283E+04 br 87 87.00 5.59E+01 1.24E-02 2.48002-05 2.4795E-05 5.7700E+04 5.7527E+04 br 88 88.00 1.64E+01 4.232-02 6.8500E-06 6.8552E-06 5.3300E+04 5.3596E+04 se 85 85.00 3.20E+01 2.17E-02 3.6300E-06 3.6295E-06 1.5200E+04 1.5056E+04 se 87 87.00 5.80E+00 1.20E-01 8.6900E-07 8.69132-07 2.0100E+04 1.9435E+04 se 88 88.00 1.50E+00 4.62E-01 1.3800E-07 1.3816E-07 1.1800E+04 1.1810E+04 sb132 132.00 2.52E+02 2.75E-03 2.8900E-04 2.8908E-04 9.8100E+04 9.8057E+04 sbl33 133.00 1.50E+02 4.62E-03 2.1800E-04 2.1812E-04 1.2300E+05 1.2336E+05 sbl34 134.00 8.00E-01 8.66E-01 2.2000E-07 2.1976E-07 2.1800E+04 2.3131E+04 sbl35 135.00 1.71E+00 4.052-01 2.3800E-07 2.3760E-07 1.1600E+04 1.1613E+04 tel31 131.00 1.50E+03 4.62E-04 2.9600E-03 2.9606E-03 1.7000E+05 1.7000E+05 tel3im 131.00 1.17E+05 5.94E-06 5.6000E-02 5.5937E-02 4.4700E+04 4.1306E+04 te132 132.00 2.76E+05 2.51 E-06 9.5800E-01 9.5832E-01 2.9100E+05 2.9628E+05 tel33 133.00 7.44E+02 9.32E-04 1.9100E-03 1.9152E-03 2.1600E+05 2.1839E+05 te133m 133.00 3.32E+03 2.09E-04 6.8900E-03 6.8894E-03 1.7600E+05 1.7584E+05 tel34 134.00 2.52E+03 2.75E-04 9.9800E-03 9.9830E-03 3.3500E+05 3.3357E+05 tel35 135.00 1.90E+01 3.65E-02 4.4800E-05 4.4820E-05 1.9700E+05 1.9716E+05 tel38 138.00 1.40E+00 4.95E-01 1.3900E-07 1.3938E-07 8.1400E+03 8.1401E+03 W131 131.00 6.93E+05 I.OOE-06 1.6500E+00 1.6506E+00 2.0400E+05 2.0515E+05 il32 132.00 8.21E+03 8.44E-05 2.8600E-02 2.8644E-02 2.9800E+05 2.9830E+05 il33 133.00 7.49E+04 9.26E-06 3.6000E-01 3.6043E-01 4.0800E+05 4.0836E+05 il34 134.00 3.16E+03 2.20E-04 1.6600E-02 1.66162-02 4.4400E+05 4.4332E+05 il35 135.00 2.37E+04 2.93E-05 1.1100E-01 1.1110E-01 3.9300E+05 3.9262E+05 1138 138.00 6.50E+00 1.07E-01 7.7800E-06 7.7832E-06 9.8000E+04 9.7904E+04 xel33 133.00 4.53E+05 1.53E-06 2.1000E+00 2.1014E+00 3.9400E+05 3.9355E+05 xel33m 133.00 1.89E+05 3.66E-06 2.9600E-02 2.9659E-02 1.3300E+04 1.3298E+04 xe135 135.00 3.28E+04 2.12E-05 5.6100E-02 5.60252-02 1.4200E+05 1.4294E+05 xeI35m 135.00 9.18E+02 7.55E-04 9.9700E-04 9.9630E-04 9.0800E+04 9.0709E+04 xel38 131.00 8.46E+02 8.192-04 3.43002-03 3.26192-03 3.32002+05 3.3210E+05 ISOTOPE ASSM Cl I ASSM Cl 2 ASSM Cl 3 BATCH Cl/MW I BATCH Cl/MW 2 BATCH CVMW 3 BATCH Cl/MW T kr 85 3.5579E+03 5.0875E+03 5.4865E+03 9.4310E+01 1.3301E+02 1.4344E+02 3.7076E+02 kr 85m 1.7280E+05 8.7451E+04 4.2117E+04 4.5805E+03 2.2863E+03 1.1011E+03 7.9679E+03 kr 87 3.5538E+05 1.7572E+05 8.3909E+04 9.4200E+03 4.5939E+03 2.1937E+03 1.62082+04 kr88 5.0104E+05 2.4390E+05 1.1478E+05 1.3281E+04 6.3764E+03 3.0007E+03 2.2658E+04 br 85 1.7298E+05 8.7148E+04 4.1805E+04 4.5853E+03 2.2784E+03 1.0929E+03 7.9566E+03 br87 2.8461E+05 1.3827E+05 6.5601E+04 7.5440E+03 3.6148E+03 1.7150E+03 1.2874E+04 br88 2.9103E+05 1.3554E+05 6.2471E+04 7.7142E+03 3.5435E+03 1.6332E+03 1.2891E+04 se 85 7.2636E+04 3.5613E+04 1.7031E+04 1.9254E+03 9.3106E+02 4.4525E+02 3.3017E+03 se 87 1.0602E+05 4.92192+04 2.2761E+04 2.8104E+03 1.2868E+03 5.9506E+02 4.6922E+03 se 88 5.6116E+04 2.7531E+04 1.3615E+04 1.4875E+03 7.1977E+02 3.5595E+02 2.5632E+03 sbl32 2.2253E+05 1.6253E+05 9.8057E+04 5.8986E+03 4.2492E+03 2.5636E+03 1.2711E+04 sbl33 3.6784E+05 2.2416E+05 1.2788E+05 9.7502E+03 5.8604E+03 3.3432E+03 1.8954E+04 sbl34 7.6444E+04 4.3864E+04 2.4682E+04 2.0263E+03 1.1468E+03 6.4529E+02 3.8184E+03 sbl35 2.8043E+04 1.9135E+04 1.1943E+04 7.4334E+02 5.0027E+02 3.1224E+02 1.5559E+03 tel31 4.0093E+05 2.8660E+05 1.7075E+05 1.0628E+04 7.4927E+03 4.4642E+03 2.2584E+04 tel31m 8.4644E+04 6.6748E+04 4.1306E+04 2.2437E+03 1.7450E+03 1.0799E+03 5.0686E+03 tel32 6.9378E+05 4.9381E+05 2.9873E+05 1.8390E+04 1.2910E+04 7.8100E+03 3.9110E+04 tel33 5.8388E+05 3.8369E+05 2.2294E+05 1.5477E+04 1.0031E+04 5.8284E+03 3.1336E+04

CA 06422 Rev'.0 Page 44 of 46 tel33m 4.7523E+05 3.1229E+05 1.7923E+05 1.2597E+04 8.1645E+03 4.6857E+03 2.5447E+04 tel34 1.0164E+06 6.1790E+05 3.4656E+05 2.6941E+04 1.6154E+04 9.0604E+03 5.2156E+04 tel35 5.0478E+05 3.3672E+05 2.0013E+05 1.3380E+04 8.8031E+03 5.2322E+03 2.7415E+04 tcl38 1.7086E+04 1.2976E+04 8.3819E+03 4.5290E+02 3.3924E+02 2.1913E+02 1.0113E+03 il31 4.7544E+05 3.4681E+05 2.2795E+05 1.2602E+04 9.0669E+03 5.9595E+03 2.7629E+04 il32 6.9971E+05 4.9763E+05 3.0243E+05 1.8547E+04 1.3010E+04 7.9066E+03 3.9464E+04 il33 1.0066E+06 6.9918E+05 4.1137E+05 2.6681E+04 1.8279E+04 1.0755E+04 5.5715E+04 1134 1.1584E+06 7.7939E+05 4.5047E+05 3.0705E+04 2.0376E+04 1.1777E+04 6.2858E+04 il35 9.4934E+05 6.6788E+05 3.9548E+05 2.5164E+04 1.7461E+04 1.0339E+04 5.2964E+04 il38 2.4823E+05 1.6630E+05 9.9293E+04 6.5799E+03 4.3477E+03 2.5959E+03 1.3523E+04 xel33 9.8137E+05 7.0490E+05 4.3091E+05 2.6013E+04 1.8429E+04 1.1266E+04 5.5707E+04 xel33m 3.0710E+04 2.1944E+04 1.3298E+04 8.1402E+02 5.7370E+02 3.4765E+02 1.7354E+03 xel35 2.8622E+05 2.2525E+05 1.6188E+05 7.5867E+03 5.8890E+03 4.2321E+03 1.7708E+04 xel35m 2.0158E+05 1.4995E+05 9.0709E+04 5.3431E+03 3.9203E+03 2.3715E+03 1.1635E+04 xel38 9.3627E+05 5.9751E+05 3.4010E+05 2.4818E+04 1.5621E+04 8.8915E+03 4.9330E+04

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4 Enclosure (13)

Compact Disk Containing Input Data for DBA Calculations Calvert Cliffs Nuclear Power, Inc.

November 3, 2005

- PI ATTACHMENT (2)

MARKED-UP TECHNICAL SPECIFICATION PAGES iii 1.1-3 3.4.15-1 3.4.15-3 3.4.15-4 3.7.10-1 3.7.10-2 3.7.11-1 3.7.11-2 3.9.3-1 5.5-18 5.5-19 5.5-20 5.5-24 Calvert Cliffs Nuclear Power, Inc.

November 3, 2005

INSERT I The TEDE (Total Effective Dose Equivalent) inhalation dose conversion factors used for this calculation shall be those listed in Table 2.1 in the column headed "effective" of Federal Guidance Report 11, ORNL, 1988, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion."

INSERT 2

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N TE--- -

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Penetration flow path(s) providing direct access from the containment atmosphere to the outside atmosphere may be unisolated under administrative controls.

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- -- -- -_ -- -- - -- - - - - - - -- -- -- - - - - - - - - - - - - - - - - - - - _ - - -

TABLE OF CONTENTS 3.5.5 Trisodium Phosphate (TSP) .......................... 3.5.5-1 3.6 CONTAINMENT SYSTEMS .................................... 3.6.1-1 3.6.1 Containment ........................................ 3.6.1-1 3.6.2 Containment Air Locks .............................. 3.6.2-1 3.6.3 Containment Isolation Valves ....................... 3.6.3-1 3.6.4 Containment Pressure ............................... 3.6.4-1 3.6.5 Containment Air Temperature ........................ 3.6.5-1 3.6.6 Containment Spray and Cooling Systems .............. 3.6.6-1 3.6.7 Deleted 3.6.8 Iodine Removal System (IRS) ........................ 3.6.8-1 3.7 PLANT SYSTEMS .......................................... 3.7.1-1 3.7.1 Main Steam Safety Valves (MSSVs) ................... 3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs) ................ 3.7.2-1 3.7.3 Auxiliary Feedwater (AFW) System ................... 3.7.3-1 3.7.4 Condensate Storage Tank (CST) ...................... 3.7.4-1 3.7.5 Component Cooling (CC) System ...................... 3.7.5-1 3.7.6 Service Water (SRW) System ......................... 3.7.6-1 3.7.7 Saltwater (SW) System .............................. 3.7.7-1 3.7.8 ontrol Room Emergency Ventilation System (CREVS).. 3.7.8-1 3.7.9 Control Room Emergency Tem erature Syste (CRETS).. 3.7.9-1 3.7.10

~t-xrout-F-iltration System (PUEFS) . . . .. 01 3.7.11 Spent Fu (SFPEVS) ..... 3.7.11-1 3.7.12 Penetration Room Exhaust Ventilation System (PREVS) . ......................................... 3.7.12-1 3.7.13 Spent Fuel Pool (SFP) Water Level ...... ............ 3.7.13-1 3.7.14 Secondary Specific Activity ........................ 3.7.14-1 3.7.15 Main Feedwater Isolation Valves (MFIVs) ............ 3.7.15-1 3.7.16 Spent Fuel Pool (SFP) Boron Concentration .......... 3.7.16-1 3.7.17 Spent Fuel Pool (SFP) Storage ...................... 3.7.17-1 3.8 ELECTRICAL POWER SYSTEMS ............................... 3.8.1-1 3.8.1 AC Sources-Operating ......... ..................... 3.8.1-1 3.8.2 AC Sources-Shutdown .......... ..................... 3.8.2-1 3.8.3 Diesel Fuel Oil ............. ....................... 3.8.3-1 3.8.4 DC Sources-Operating ......... ..................... 3.8.4-1 3.8.5 DC Sources-Shutdown .......... ..................... 3.8.5-1 3.8.6 Battery Cell Parameters ............................ 3.8.6-1 3.8.7 Inverters-Operating .......... ..................... 3.8.7-1 CALVERT CLIFFS - UNIT 1 iii Amnedment Nco. 267 CALVERT CLIFFS - UNIT 2 Amemdmemt Nc. 24G

Definitions 1.1 1.1 Definitions DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present d ip tis caloculd iont ha r9c2, "Calculatioatof t ihtaneoFamintrs forf toe and- Test Rpactor SSitc."

E-AVERAGE DISINTEGRATION Eshall be the average (weighted in proportion to ENERGY the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives > 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

ENGINEERED SAFETY FEATURE The ESF RESPONSE TIME shall be that time interval (ESF) RESPONSE TIME from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

La The maximum allo able containment leakage rate, of containment air weight per day at the calculated peak containment pressure (P.) .

CALVERT CLIFFS - UNIT 1 1.1-3 AJWcndment Pie. 2'44 CALVERT CLIFFS - UNIT 2 Amendment Ne3. 212

- - -

RCS Specific Activity 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Specific Activity LCO 3.4.15 The specific activity of the reactor coolant shall be within limits.

APPLICABILITY: MODES 1 and 2, MODE 3 with RCS average temperature (Tayg) Ž 5000 F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT I-131 ------------ NOTE ------------

> 2 .Ci/gm. LCO 3.0.4 is not applicable.

A.1 Verify DOSE Once per EQUIVALENT I-131 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> within the acceptable region of Figure 3.4.15-1.

AND A.2 Restore DOSE 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> EQUIVALENT I-131 to within limit.

CALVERT CLIFFS - UNIT 1 3.4.15-1 Amcndmnet No. 22 CALVERT CLIFFS - UNIT 2 Amendment Nio. 201

-

RCS Specific Activity 3.4.15 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.15.2 --------------- NOTE-------------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT I-131 14 days specific activity

• pCi/gm.

AND Between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after THERMAL POWER change of 2 15% RTP within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period SR 3.4.15.3 -------------------NOTE-------------------

Not required to be performed until 31 days after a minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for 2 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Determine E from a sample taken in MODE 1 184 days after a minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for 2 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

CALVERT CLIFFS - UNIT 1 3.4.15-3 A-Mnmantimn NOr go CALVERT CLIFFS - UNIT 2 Amondmant No. 202

RCS Specific Activity 3.4.15 I.-

-4

-4

-J I-6-4

-

tz

-4 U

-r (i

C>

C-0.

-4 e-V-4

-J I-j ILi Lii LU 0n 0~

20 30 40 50 60 70 80 90 100 PERCENT OF RATED THERMAL POWER Figure 3.4.15-1 (page 1 of 1)

Reactor Coolant DOSE EQUIVALENT I-131 Specific Activity Limit Versus Percent of RATED THERMAL POWER With Reactor Coolant Specific Activity 2 Ci/gm DOSE EQUIVALENT I-131 CALVERT CLIFFS - UNIT 1 3.4.15-4 Aeendmcnt 0No. 22; CALVERT CLIFFS - UNIT 2 Amcndment P18. 201

EG-JPR.s 7 PLANT SYSTEMS '-- X.

3.7 . Emergency Core Cooling System (ECCS) Pump Room Exhaust Filtrat n System (PREFS)

LCO 3.7.10 ECCS PREFS shall be OPERABLE.

APPLICABILITY: MODES , 2, 3, and 4.

ACTIONS CONDITION REQUIRV ACTION COMPLETION TIME A. One ECCS PREFS A.1 R ore ECCS PREFS 7 days exhaust fan ha t fan to OPERABLE inoperable. status.

B. ECCS PREFS inoperable B.1 Restore ECCS REFS to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for reasons other OPERABLE status.

than Condition A.

C. Required A ion and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associa d Completion Time t met. AND C.2 Be in MODE 5. 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> I.AiLVLI L.LJI i ..) Ufft !i AeindmeiinL No. 227 CALLVERT CLI6rr - UNIT 1 Amcedment Na. 29o

TILVMrM tiIi i -i UIdif 1 3.7.10-a hf:iiediieir-l Nu. 227 CALVERT cLIrr- UNIT 2 AmJendet Ne. 201

- .

SFPEVS 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Spent Fuel Pool Exhaust Ventilation System (SFPEVS)

LCO 3.7.11 The SFPEVS shall be OPERABLE and in operation.

APPLICABILITY: During movement of recently irradiated fuel assemblies in the Auxiliary Building.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. On- CFPVS charcoal A.1 Verify OPERABLE SFPEVS Immediately adsorbre bank train is in operation.

OR A.2 Suspend movement of Immediately One SFPEVS exhaust recently irradiated fan inoperable. fuel assemblies in the Auxiliary Building.

koe WFEVS xas B. No OPERABLE SFPEVS B.1 Suspend movement of Immediately train. recently irradiated fuel assemblies in the OR Auxiliary Building.

No OPERABLE SFPEVS train in operation.

CALVERT CLIFFS - UNIT 1 3.7.11-1 AFmendment Pi. 2A7 CALVERT CLIFFS - UNIT 2 Amcndmct N. 234

SFPEVS 3.7.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify an OPERABLE SFPEVS train is in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> operation.

SR 3.7.11. ired SFPEVS fil accorf a taccor inc etf-at wi4tK j~ther_

T Venti ion

,,--- so> r ating SR 3.7.11.3 Verify each SFPEVS fan can maintain a 24 months measurable negative pressure with respect to atmospheric pressure.

CALVERT CLIFFS - UNIT 1 3.7.11-2 Amnndmcnt 9N 927 CALVERT CLIFFS - UNIT 2 Afflendfe-' No. 201,

Containment Penetrations 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Containment Penetrations LCO 3.9.3 The containment penetrations shall be in the following status:

a. 1. The equipment hatch closed and held in place by a minimum of four bolts, or

2. The containment outage door is capable of being closed under administrative control;

b. One door in the emergency air lock is closed;

---

NOTE ----------------------------

The emergency air lock temporary closure device can be used in place of an emergency air lock door.

c. The personnel air lock shall be either:

1. closed by one personnel air lock door, or

2. capable of being closed by an OPERABLE personnel air lock door under administrative control. I

d. Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:

1. closed by a manual or automatic isolation valve, blind flange, or equivalent, or

2. capable of being closed by an OPERABLE Containment Purge Valve Isolation System.

APPLICABILITY: During CORE ALTERATIONS, During movement of irradiated fuel assemblies within containment.

CALVERT CLIFFS - UNIT 1 3.9.3-1 Iftendmet Nza. 242 CALVERT CLIFFS - UNIT 2 7Aflezndlmt NF. 21-

Programs and Manuals 5.5 5.5 Programs and Manuals chemical release in any ventilation zone communicating with the system.

Tests described in Specification 5.5.11.c shall be performed once per 18 months for ventilation systems other than the IRS and 24 months for the IRS; after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation; after any structural maintenance on the HEPA filter or charcoal adsorber housing; and following painting, fire, or chemical release in any ventilation zone communicating with the system.

Tests described in Specification 5.5.11.d shall be performed once per 18 months for ventilation systems other than the IRS and 24 months for the IRS.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Ventilation Filter Testing Program test frequencies.

a. Demonstrate for each of the ESF systems that an inplace test of the HEPA filters shows a penetration and system bypass

< 1.0% when tested in accordance with Regulatory Positions C.5.a and C.5.c of Regulatory Guide 1.52, Revision 2, and ANSI N510-1975, at the system flowrate specified as follows +/- 10%:

ESF Ventilation System Flowr Control Room Emergency Ventilation System Penetration Room Exhaust Venti ation 2,000 cfm System (PREVS) gy - t I Htilation- 200 IRS ~20,000 cfm

b. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < 1.0% when tested in accordance with Regulatory Positions C.5.a and C.5.d of Regulatory Guide 1.52, CALVERT CLIFFS - UNIT 1 5.5-18 ArJemeint lie. 259 CALVERT CLIFFS - UNIT 2 Amecndmnet Pi. 236

Programs and Manuals 5.5 5.5 Programs and Manuals Revision 2, and ANSI N510-1975, at the system flowrate specified as follows +/- 10%:

ESF VAntilation Svqtpm

,_...._ ._.._, _... Flowrate II 20,000 cfm

c. Demonstrate for each of the ESF systems within 31 days after removal that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration less than the value specified below when tested in accordance with ASTM D3803-1989 at a temperature of 300 C and greater than or equal to the relative humidity specified as follows:

ESF Ventilation System Penetrations RH

d. For each of the ESF systems, demonstrate the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested in accordance with Regulatory Guide 1.52, CALVERT CLIFFS - UNIT 1 5.5-19 *aemerdnt Pie. 259 CALVERT CLIFFS - UNIT 2 Amendment No. 236

Programs and Manuals 5.5 5.5 Programs and Manuals Revision 2, and ANSI N510-1975 at the system flowrate specified as follows +/- 10%:

ESF Ventilation System Delta P Flowrate 0 CREVS 4 inwg cfm PREVS6 inwg 2,000 cfm S6inwg 20,000 cfm 5.5.12 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides control for potentially explosive gas mixtures contained in the Waste Gas Holdup System and the quantity of radioactivity contained in gas storage tanks. The gaseous radioactivity quantities shall be determined following the methodology in the ODCM.

The program shall include:

a. The limits for concentrations of oxygen in the Waste Gas Holdup System and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion); and

b. A surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank is less than or equal to 58,500 curies noble gases (considered as Xe-133).

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance Frequencies.

CALVERT CLIFFS - UNIT 1 5.5-20 AnenJdm~ent No. 2J9 CALVERT CLIFFS - UNIT 2 1 dment No. 236 fanen

Programs and Manuals 5.5 5.5 Programs and Manuals 1992 Type A test shall be performed no later than June 14, 2007.

b. Unit 1 is excepted from post-modification integrated leakage rate testing requirements associated with steam generator replacement.

c. Unit 2 is excepted from post-modification integrated leakage rate testing requirements associated with steam generator replacement.

The peak calculated containment internal pressure for the design basis loss-of-coolant accident, Pas is 49.4 psig. The containment design pressure is 50 psig.

The maximum allowable containment leakage rate, L,, shall b percent of containment air weight per day at P..

Leakage rate acceptance criteria are:

a. Containment leakage rate acceptance criterion is

• 1.0 La.

During the first unit startup following testing, in accordance with this program, the leakage rate acceptance criterion are

• 0.60 La for Types B and C tests and

• 0.75 La for Type A tests.

b. Air lock testing acceptance criteria are:

1. Overall air lock leakage rate is

• 0.05 La when tested at 2 P- -

2. For each door, leakage rate is

• 0.0002 La when pressurized to 2 15 psig.

The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

CALVERT CLIFFS - UNIT 1 5.5-24 aendment Ne. 259 CALVERT CLIFFS - UNIT 2 Amendment No. 236