ML053200298
| ML053200298 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/03/2005 |
| From: | Constellation Energy Group |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| CA06449, Rev 000 | |
| Download: ML053200298 (138) | |
Text
Enclosure (1)
CA06449 MHA Radiological Consequences Design Basis Calculation Using AST Calvert Cliffs Nuclear Power, Inc.
November 3, 2005
EN-1-100 Forms Appendix Revision 3 ESP No.: IES200100401 Supp No.
I 000 Rev. No.
000 Page of FORM 19, CALCULATION COVER SHEET A. INITIATION (Control Doc Type-DCALC)
Page I of 137 DCALC No.:
CA06449 Revision No.:
000 Vendor Calculation (Check one):
El Yes 1
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 al Other:
El Reliability Engrg
Title:
MAXIMUM HYPOTHETICAL ACCIDENT USING ALTERNATE SOURCE TERMS Unit El I El 2 s
COMMON Proprietary or Safeguards Calculation El YES 3 NO Comments:
NA Vendor Calc No.:
NA REVISION No.:
NA Vendor Name:
NA Safety Class (Check one):
s SR E AQ El NSR There are assumptions that require Verification during walkdown:
AIT#:
NA This calculation SUPERSEDES:
NA C. REVIEW AND APPROVAL:
L Responsible Engineer:
Gerard E. Gryczkowski 07/06/2005 Print Name and Sign Date Independent Reviewer:
2, J
/
f
/
Printed Name and RDate Approval:
j 1 Printed game nd Sigatu 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.
CA06449 Rev. 000 Page 2
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CA06449 Rev. 000 Page 3
- 3. REVIEWER COMMENTS (1) P. 9 - 6B.01 - Please be more specific regarding the table in the reference; It appears as if some nuclides are missing from the reference.
Response: Ref.5 Attachment H specified in Section 6B.01.
(2) p. 12, Please be more specific regarding the "Containment Fan Cooler startup", since there are other Containment Fan Cooler startups which are different on p. 1 5 & 16 Response: In section 6.C.11, "containment fan cooler startup" changed to "filter fan startup."
(3) p. 8, Please explain that all sources except the H2Purge line path use 63 nuclides but the H2 purge line uses just the 14 noble gases and lodines per RG 1.183, Para --
Response: The source terms for each pathway are described in their individual sections and differ among the pathways.
(4) p. 19 or 20 - please explain that the leakrate of 1.1772E-03 cfm is modified by the flashing fraction of 10% to become 1.1772E-04 Response: Section 6.D.12 now makes reference to this fact.
(5) p. 22, Please correct the equation for w to say "w = ", rather than "Y="
Response: Done (6) p. 22, please determine the correct value for F. The table says 1685.55 and the file says 1645.
Response: 1645 is correct. The table has been fixed.
(7) p. 22, In the table, the value of.2272 is not the ratio of molecular weight of air to the molecule weight of the mixture and does not appear to be used for anything.
Response: It is the mole fraction of air in the containment equal to Pa/P and is used in Ml\\Vmix. Clarified in the table.
(8) p. 22, Table - there are two different values of rho or density in the table Response: A roundoff problem. Corrected.
(9) p. 36, Please expand on the explanation of how the filter shine computations are performed to account for the dose as a function of time. It is not really intuitively obvious Response: See Section 9.G (10) The control room inleakage coefficient should be 4.719474E4. It is correct in the file Attachments T - V Response: Ok
CA06449 Rev.000 Page 4
- 4. TABLE OF CONTENTS
- 01. COVER SHEET I
- 02. LIST OF EFFECTIVE PAGES 2
- 03. REVIEWER COMMENTS 3
- 04. TABLE OF CONTENTS 4
- 05. INTRODUCTION 6
- 06. INPUT DATA 8
06.A General Input 8
06.B MHA Containment Pathway 9
06.C M HA Ventilation StackPathway 13 06.D MHA RWT Pathway 17 06.E MHA Hydrogen Purge Line Pathway 20 06.F MHA Containment Shine 22 06.G MHA Plume Shine 23 06.H MHA Control Room Filter Shine 25
- 07. TECHNICAL ASSUMPTIONS 28
- 08. REFERENCES 29
- 09. METHODS OF ANALYSIS 33 09.A RADTRAD Containment Pathway Computations 33 09.B RADTRAD Ventilation Stack Pathway Computations 33 09.C RADTRAD RWT Pathway Computations 34 09.D RADTRAD Hydrogen Purge Line Pathway Computations 34 09.E MICROSHIELD Containment Shine Computations 35 09.F MICROSHIELD Plume Shine Computations 35 09.G MICROSHIELD Control Room Filter Shine Computations 36
- 10. CALCULATIONS 38
- 11. DOCUMENTATION OF COMPUTER CODES 41 I.A RADTRAD 41 I I.B MICROSHIELD 41
- 12. RESULTS 42 12.A CONTAINMENT PATHWAY 42 12.B HYDROGEN PURGE LINE PATHWAY 42 12.C PENETRATION ROOM-VENTILATION STACK PATHWAY 42 12.D REFUELING WATER TANK PATHWAY 42 12.E CONTAINMENT SHINE 42 12.F PLUME SHINE 43 12.G CONTROL ROOM FILTER SHINE 43
- 13. CONCLUSIONS 44
- 14. ATTACHMENTS 45
CA06449 Rev. 000 Page 5
ATTACHMENT A: MAXIMUM HYPOTHETICAL ACCIDENT PRIMARY RELEASE ACTIVITIES 45 ATTACHMENT B1: NUCLEAR INVENTORY FILE CRCB63.NIF 46 ATTACHMENT C: RELEASE FRACTION AND TIMING FILE MHACTMT.RFT 57 ATTACHMENT D: CONVERSION FACTORS FILE FGR63.INP 58 ATTACHMENT E: OUTPUT FILE MHACTMT.oO 72 ATTACHMENT F: OUTPUT FILE MHAVS.oO 74 ATTACHMENT G: RELEASE FRACTION AND TIMING FILE MHARWT.RFT 76 ATTACHMENT H: OUTPUT FILE MHARWT.oO 77 ATTACHMENT I: NUCLEAR INVENTORY FILE PRI14.NIF 79 ATTACHMENT J: RELEASE FRACTION AND TIMING FILE MHAHP.RFT 82 ATTACHMENT K: CONVERSION FACTORS FILE FGR14.lNP 83 ATTACHMENT L: OUTPUT FILE MHAHP.oO 87 ATTACHMENT M: ETP 97-064R CONTROL ROOM INLEAKAGE RESULTS 89 ATTACHMENT N: ETP 01-035R PERFLUOROCARBON TRACER GAS TESTING 105 ATTACHMENT 0: CONTAINMENT TO PENETRATION ROOM LEAKAGE CALCULATION 111 ATTACHMENT P: LOCAL LEAKRATE TEST RESULTS 112 ATTACHMENT Q: MICROSHIELD CONTAINMENT SHINE SOURCE TERM 114 ATTACHMENT R: MICROSHIELD PLUME SHINE SOURCE TERM 116 ATTACHMENT S: MICROSHIELD CONTROL ROOM FILTER SHINE SOURCE TERM 118 ATTACHMENT T: MICROSHIELD CONTROL ROOM FILTER DOSES - PARTICULATE 120 ATTACHMENT U: MICROSHIELD CONTROL ROOM FILTER DOSES - ELEMENTAL 121 ATTACHMENT V: MICROSHIELD CONTROL ROOM FILTER DOSES - ORGANIC 122 ATTACHMENT W: MICROSIIELD CONTAINMENT SHINE OUTPUT FILES 123 ATTACHMENT X: MICROSHIELD PLUME SHINE OUTPUT FILES 127 ATTACHMENT Y: MICROSHIELD CONTROL ROOM FILTER OUTPUT FILES 131 ATTACHMENT Z: MICROSHIIELD CONTROL ROOM FILTER OUTPUT FILES - IODINE ONLY 135 LAST PAGE OF REPORT 137
CA06449 Rev.000 Page 6
- 5. INTRODUCTION 10 CFR 100 requires that each nuclear unit perform an MHA analysis to determine the two hour exclusion area boundary dose, which is limited to 25 rem whole body and 300 rem thyroid.
10 CFR 50 Appendix A GDC 19 requires that a control room shall be provided from which actions can be taken to operate the nuclear unit safely under normal conditions and to maintain it in a safe condition under accident conditions. Adequate radiation protection shall be provided to permit access and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of 5 rem whole body, or its equivalent to any part of the body, for the duration of the accident.
Chapter 14.24 of the UFSAR constitutes a safety evaluation based on a Maximum Hypothetical Accident (MHA) which involves a gross release of fission products from the fuel to the containment. During an accidental release, air containing radionuclides may enter the control room through inleakage into the control room ventilation system. The control room thyroid, whole body, and beta skin doses must meet 10 CFR 50 APP.A GDC 19 limits. Similarly, during an accidental release, air containing radionuclides may travel offsite. The offsite thyroid, whole body, and beta skin doses must meet 10 CFR 100 limits.
The current design-basis offsite dose calculations from the containment leakage pathway for a MHA is documented in Ref.40. The corresponding control room thyroid dose exceeded 10 CFR 50 APP.A GDC 19 limits. However, an interim engineering analysis for thyroid dose for control room habitability crediting Self Contained Breathing Apparatuses (SCBAs) wvas performed in Ref.66 and accepted by the NRC in Ref.67. This calculation was further modified in Ref.68 to incorporate the higher control room inleakage term of 3500 cfm. Thus the time to don SCBAs was reduced to 32 minutes post-MHA to meet 10 CFR 50 App.A GDC 19 limits.
/
There is a potential for an unmonitored release pathway resulting from the post-LOCA leakage of isolation valves in the Safety Injection or Containment Spray system recirculation lines to the Refueling Water Tank (RWT), which is vented directly to the atmosphere (Ref.36). During the recirculation phase, sump water is recirculated through the ECCS pumps and could leak through various valves and reach the RWT. The two pathways include the two valves in series in the minimum flow recirculation line header (MOV659/660) and the valve from the containment spray pumps (S1459). Ref.69 evaluated offsite doses from these pathways assuming a nominal leakage of 0.1 gpm from each pathway.
Based on conservative assumptions, a 2-hour exclusion area boundary (EAB) dose of 0.11 rem thyroid and a 30-day low population zone (IPZ) dose of 9.4 rem thyroid were calculated. Control room doses were not calculated in Ref.69. Ref.70 calculated the offsite and control room doses due to the RWT pathway, using less conservative leakage rates and methodologies. Additional calculations were performed in Refs. 34, 71, and 72 using different control room assumptions; however, since the time to RAS bounded the time to don SCBAs, the control room doses were not important.
If the 4" hydrogen purge line is open at the start of an MHA, there is the possibility of blowdowvn through the 4" hydrogen purge line.
This pathway was included in the design basis calculation Ref.40.
Ref.73 calculated a minimum clad rupture time of 26.3 sec post-LOCA.
Ref.74 is a TMOI) which changed the stroke length of MOV6900 and MOV6901 from 4" to 3" and which assured a total closure time (SIAS signal of 2.4 sec via Ref.32 +
EDG startup of 10 sec via Ref.32 4 MOV stroke time of 12.5 sec via Ref.75) to less than 26 sec. Thus there will be no activity release through the 4" hydrogen purge line post-LOCA.
Previously, power reactor licensees have typically used the U.S.A.E.C Technical Information Document TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites," (Ref. 8) as the basis for Design Basis Analysis (DBA) source terns. TID-14844 is referenced in 10 CFR 100.11, the power reactor siting regulation, which contains offsite dose limits in terrms of whole body and thyroid doses.
In December 1999, the Nuclear Regulatory Commission (NRC) issued a new regulation, 10 CFR 50.67, "Accident Source Term," which provided a mechanism for licensed power reactors to replace the traditional accident source term used in their DBA analyses with an Alternate Source Term (AST) methodology. Regulatory guidance for the implementation of these ASTs is provided in Regulatory Guide (RG) 1.183. "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors" (Ref.08). Section 50.67 of 10 CFR requires a licensee seeking to use AST to
CA06449 Rev.OOO Page 7
apply for a license amendment and requires that the application contain an evaluation of the consequences of affected DBAs. As part of the implementation of the AST, the Total Effective Dose Equivalent (TEDE) acceptance criterion of 10 CFR 50.67 replaces the previous whole body and thyroid dose guidelines of 10 CFR 100.11 and 10 CFR 50, Appendix A, GDC-19 for the loss-of-coolant accident (LOCA), the main steam line break (MSLB), the steam generator tube rupture (SGTR), the seized rotor event (SRE), the fuel handling accident (FHA), and the control element assembly ejection accident (CEAEE). The TEDE accident dose criteria are listed in Table 6 of RG 1 183 for offsite doses and in 10 CFR 50.67 for control room doses, which limit is 5 Rem TEDE.
The current work utilizes the alternate source term methodology of 10 CFR 50.67 and Regulatory Guide 1.183 to calculate offsite and control room doses for an MHA. Per RG 1.183, the TEDE analysis should include all sources of radiation that will cause exposure to control room personnel. In this work, the following pathways are analyzed:
Containment pathway Hydrogen Purge Line (HPL) pathway Ventilation Stack (VS) pathway Refueling Water Tank (RWT) pathway Containment Shine Plume Shine Control Room Filter Shine A bounding control room inleakage value of 3500 cfm was assumed. The following modifications and TS changes are proposed to comply with regulatory requirements.
Modification of the control room emergency ventilation system to a nominal 10000 cfm flow with a 90%
filtration efficiency for elemental and organic iodine and 99% for particulate iodine was credited.
Also credited was installation of automatic isolation dampers and radiation monitors at Access Controls 11 and 13 on the Auxiliary Building Roof. This modification limits activity ingress into the control room to either the West Road Inlet or the Turbine Building, thus limiting the atmospheric dispersion coefficient value.
The Technical Specification (TS 3.4.15) limit for RCS activity was reduced from 1.0 pCi/gm to 0.5 pCi/gm.
The maximum allowable containment leakage rate La contained in the Containment Leakage Rate Testing Program of TS 5.5.16 was reduced from 0.20 percent per day at Pa to 0.16 percent per day at Pa.
The exclusion area boundary (EAB), low population zone (LPZ), and control room (CR) doses for the design-basis MHA are detailed in the following table.
I MHA Results I
Results EAB LPZ CR Rem Rem Rem Containment Pathway 1.8988 0.4958 3.9682 Penetration Room Pathway 0.1838 0.0485 0.3968 RWT Pathway 1.9676E-05 1.8560E-03 3.2979E-01 Hydrogen Purge Pathway 6.4918E-05 1.5283E-05 7.7048E-05 Containment Shine 0.0547 Plume Shine 0.0030 Control Room Filter Shine 0.0139 Total 2.0827 0.5462 4.7664 Regulatory Limits 25 25 5
Note that all values are below the regulatory limits.
CA06449 Rev. 000 Page 8
- 6. INPUT DATA To determine the exclusion area boundary (EAB), low population zone (LPZ), and control room (CR) doses from a Maximum Hypothetical Accident (MHA), seven release pathways must be modeled:
Containment path vay Hydrogen Purge Line (HPL) pathway Penetration Room-Ventilation Stack (VS) pathway Refueling Water Tank (RWT) pathway Containment Shine Plume Shine Control Room Filter Shine (6.A) General Inputs (6A.01) Initial thermal power is 2754 MWt (UFSAR 3.2.1/Ref.l).
(6A.02) The isotopic half-lives (t1) were extracted from Ref.06 and are listed in column A of Attachment A. The decay constants (N.), listed in column B of Attachment A, are readily calculated via the following algorithm:
)Ni = In(2) / tj (6A.03) The breathing rates are extracted from Ref.08:
Time (hours)
Breathing Rate (m3/sec)
(6A.04) The control room occu 0-8 3.5E-04 8-24 1.8E-04 24-720 2.3E-04 ancy factors are extracted from Ref.08:
Time Occupancy (hours)
Factor 0-24 1.0 24-96 0.6 96-720 0.4 (6A.05) Control room inleakage: The control room inleakages for the two trains Air Conditioning Units (ACU) 11 and 12 were measured by NUCON International Inc. via sulfur hexaflouride (SF6) tracer gas tests as documented in Refs.23-26 (Attachment M). An additional inleakage test was performed by Brookhaven National Laboratory (BNL) via a perfluorocar on tracer gas (PFT) test as documented in Ref.27 (At achment N).
ACU 11 ACU 12 SF6 Test 11/1 1/97 4300+/-300 cfm 3000+/-300 cfm SF6 Test 11/11/97 3600+/-600 cfm 2550+/-450 cfm SF6 Test 11/11/97 290G+/-250 cfm 2750+/-380 cfm SF 6 Test 1/18/00 2600+/-200 cfm 3000+/-250 cfm PFT Test 5!1/02 2930+/-185 cfm 2930+/-185 cfm
CA06449 Rev. OO Page 9
The latest SF6 and PFT tests show fairly good agreement, as indicated above. A conservative value of 3500 cfm will be utilized in this work.
The control room inleakage points were deduced from the PFT' testing carried out by Brookhaven National Laboratory and include the Auxiliary Building West Road inlet (WR), the Turbine Building inlet (TB), Access Control 11 (AC Il), Access Control 13 (AC13), the Switchgear Rooms (SWGRs), and the Main Steam Isolation Valve Rooms (MSIVs). ACI 1 and AC13 will be equipped with dampers and radiation monitors, which will isolate this leakage path in case of an accident. The SWGRs are in continual recirculation mode and thus are also isolated from the environment. The MSIV rooms are also isolated from the environment, except for the Main Steam Line Break Accident which occurs in these rooms, due to the thermal buoyancy of the air in these rooms and due to the J-neck exhaust. For conservatism, all of the measured inleakage will be assumed to enter the control room from the most conservative pathway of either the West Road or Turbine Building inlets.
(6A.06) Control room recirculation flow:
Flowrate: 10000.+/- 1000 cfm (Note that this value will be the result of a new modification.)
Initiation delay time: 20 minutes (Ref.29 conservatively assumes a 20 minute time delay for a manual start of the Control Room Emergency Ventilation System.)
Filter efficiencies: 90% for elemental and organic iodine species (Ref.28 and Technical Specification 5.5.11 allow a 95% filter efficiency for a 2" activated carbon bed depth; however, NRC Generic Letter 99-02 (Ref.30) requires plants that test their activated charcoal to the ASTM D3803-1989 standards to use a safety factor of two. This results in a maximum credited efficiency of 90% for accident analyses.)
Filter efficiencies: 99% for particulate iodine (Per Ref.28, an engineered-safety-feature air filtration system satisfying a filter penetration less than 0.05% at rated flow can be considered to warrant a 99% removal efficiency for particulates in accident dose evaluations. CCNPP will perform an inplace test of the HEPA filter to show a penetration and system bypass flow less than 0.05% )
(6A.07) Control Room Volume: The control room volume is 289194 ft3 per Ref. 19.
(6.B) NIHA Containment Pathway Per RG 1.194 (Ref.43), the total release from containment may be apportioned between the exposed and enclosed building surfaces.
A large fraction of the released airborne activity post-MHA is assumed to leak out of the containment through the containment walls.
(6B.01) The inventory of fission products in the reactor core and available for release to the containment atmosphere is based on the maximum full power operation of the core with current licensed values for fuel enrichment, fuel bumup, and a core power equal to the current licensed rated thermal power times the ECCS evaluation uncertainty.
The period of irradiation was of sufficient duration to allow the activity of dose-significant radionuclides to reach maximum values. The isotopic activities released from the failed fuel in Ci/MWt were generated in Ref. 05 Case CRCB63 Attachment H, utilizing the isotope generation and depletion computer code SAS2H/ORIGEN-S. For the containment pathway, all 63 isotopic activities are stored in the nuclear inventory file CRCB63.NIF listed in Attachment B. To utilize these isotopic source terms, it is necessary to multiply them by the relevant power level in MWt and by the relevant release fractions in the release fraction and timing files.
(6B.02) The core inventory release fractions, by radionuclide groups, for the gap release and early in-vessel damage phases for a DBA LOCA were extracted from RG 1.183 (Ref.08). The onset and duration of each sequential release phase for the DBA LOCA was extracted from RG 1.183 (Ref.08). The activity released from the core during the Gap Release Phase is modeled as increasing linearly over the duration of the phase, while that released during the Early In-Vessel Phase the activity is assumed to be released at the beginning of the phase. Note that step releases are allowed per RG 1.183.
The values are incorporated in the release fraction and timing file MHACTMT.RFT (Attachment C) for use by RADTRAD and are listed in the following table:
CA06449 Rev.O00 Page 1 0 Group Gap Release Phase Early In-Vessel Phase Total Release Noble Gases (Xe.Kr) 0.05 0.95 1.00 Halogens (l,1Br) 0.05 0.35 0.40 Alkali Metals (Cs,Rb) 0.05 0.25 0.30 Tellurium Metals (TeSb,Se) 0.00 0.05 0.05 Ba, Sr 0.00 0.02 0.02 Noble Metals (Ru,Rh,PdMo,Tc,Co) 0.0000 0.0025 0.0025 Cerium Group (CePuNp) 0.0000 0.0005 0.0005 Lanthanides (La,ZrNd,Eu, NbPm,Pr,Sm.YCm,Am) 0.0000 0.0002 0.0002 Release Timing 0.00 hr - 0.5 hr 0.5 hr (6B.03) The dose conversion factors (DCFs) were extracted from Refs.20-2 1 and inserted into input files for use by RADTRAD. This data is included in the Conversion Factor Files FGR63.INP in Attachment D for use with failed fuel isotopics. Note that the cloudshine data in the Conversion Factor Files corresponds to the FGR-12 data, while the inhaled chronic data in the Conversion Factor Files corresponds to the worst-case effective data in FGR-1 1. The remaining data in the Conversion Factor Files is extraneous and not used by RADTRAD.
(6B.04) Per RG 1.183 (Ref.08), of the radioiodine released from the RCS to the containment atmosphere in a LOCA, 95% of the iodine released should be assumed to be cesium iodide (Csl), 4.85% elemental iodine, and 0.15% organic iodine. This includes releases from the gap and fuel pellets. With the exception of elemental and organic iodine and noble gases, fission products should be assumed to be in particulate form.
(6B.05) The containment to site boundary X/Q of 1.30E-4 sec/m3 was extracted from UFSAR 2.3.6.
(6B.06) The atmospheric dispersion coefficients from the containment to the LPZ (2 miles) were extracted from UFSAR Fig.2.3-3/UFSAR 14.24.3.
Time (hours)
X/Q (sec/m3) 0-2 3.30E-05 2-24 2.20E-06 24-720 5.40E-07 (6B.07) Atmospheric dispersion coefficients from the containment to the Control Room: (Ref.19)
The failed fuel activity released into the containment atmosphere is assumed to escape into the environment through the containment wvall. The main control room inleakage points include the west road inlets, the turbine building, and Access Controls 11 and 13 on the Auxiliary Building roof. Installation of automatic isolation dampers and radiation monitors at Access Controls I I and 13 on the Auxiliary Building Roof are credited in this work.
Atmospheric Dispersion Coe ficients (secln )
U I-WR U2-WR U1-TB U2-TB 0-2 hr 1.11E-03 1.04E-03 1.02E-03 1.02E-03 2-8 hr 7.29E-04 5.95E-04 7.10E-04 7.98E-04 8-24hr 3.19E-04 2.29E-04 2.57E-04 3.19E-04 1-4 days 2.36E-04 1.64E-04 2.19E-04 2.56E-04 4-30 days 1.98E-04 1.14E-04 1.77E-04 2.14E-04 The atmospheric dispersion coefficients corresponding to the Unit I containment to the west road inlet on the auxiliary building will be conservatively utilized in this work.
CA06449 Rev.OOO Page 11 (6B.08) Containment volume:
Net free volume:
1.989E+06 cf (UFSAR Tab.14.20-3, Ref.39)
Containment sprayed volume:
1.446E+06 cf Volume fraction:
0.7273 (Ref.40)
Containment unsprayed volume:
0.543E+06 cf Volume fraction:
0.2727 (Ref.40)
Note: Assumes sprayed and unsprayed volume fractions remain unchanged from Ref.40.
(6B.09) Fan coolers are credited for mixing of air between the sprayed region and unsprayed region of containment.
(a) Three 110000 cfm cooling units are normally in operation in containment. Upon receipt of a SIAS, the fourth cooling unit is automatically started on the 55000 cfm low speed setting and simultaneously the other three units are switched to low speed operation. If offsite power is not available, the emergency diesel generators are started. Each of two emergency diesel generator busses carries the load of two cooling units (UFSAR 6.5.3 and 6.5.4). Thus, two 55000 cfm cooling units are credited in this work.
(b) Containment fan cooler operation requires 38 seconds to activate:
Pressure buildup, instrument response, SIAS delay 03 seconds (Ref.32)
Emergency diesel generator startup 10 seconds (Ref.32)
Load sequencing delay 15 seconds (UFSAR Table 8.7)
Containment fan cooler startup 10 seconds (UFSAR Table 7.4)
For conservatism, a 60 second activation delay will be utilized in this work.
(6B.10) Containment Leakage (a) The maximum allowable containment leakage rate La contained in the Containment Leakage Rate Testing Program of TS 5.5.16 will be reduced from 0.20 percent per day at containment peak pressure Pa to 0.16 percent per day at Pa. Per RG 1.183, the containment should be assumed to leak at the leak rate incorporated in the technical specifications for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and at 50% of this leak rate for the remaining duration of the accident.
(b) Per Regulatory Guide 1.194 (Ref.43), the total release from containment may be apportioned between the exposed and enclosed building surfaces.
The CCNPP original licensing basis as described in the Final Safety Analysis Report (FSAR 14.18) assumed that at least 50% of the containment leakage would be into the penetration rooms, which are maintained at negative pressure and which discharge through the penetration room HEPA/charcoal filters into the plant vent.
Based on Local Leak Rate Testing (LLRT) performed per TS 5.5.16, the Containment Leakage Rate Testing Program, it can be shown (Attachment P) that at least 75% of the containment leakage would be into the penetration rooms.
Based on the ratio of containment surface enclosed by the Auxiliary Building to the total containment surface area, it can be shown that at least 28.7% of the containment leakage would be into the penetration rooms (Attachment 0).
In this work a conservative bypass fraction from the containment to the penetration rooms of 28% was assumed.
(6B.1 1) Containment iodine removal system:
o Per UFSAR 6.7, the containment iodine removal system (IRS) incorporates three filter units, each with a capacity to handle 50% of the required air flow.. Each unit consists of activated charcoal filters preceded by HEPA filters. Per TS 5.5.11, each filter unit has a 20000N10% cfm floATate with a filter efficiency of 90% for elemental and particulate species and 30% for organic species per RG 1.52 (Ref.28).
o This work assumes that the containment filters affect the entire containment; however, due to the well mixed quality of the containment atmosphere, the effect of applying the containment filter to a particular containment region is minor.
CA06449 Rev.000 Page 12 o
Per UFSAR 6.7.2, SIAS automatically starts three recirculation filter units. If offsite power is not available, the emergency diesel generators are started. Each of two emergency diesel generator busses carries the load of two recirculation filter units (UFSAR Table 8-7).
Per UFSAR Table 8.7, one iodine removal unit (IRU) is connected to one bus, while the other two are connected to the other bus. Thus, assuming a LOOP concurrent with a LOCA and with the single failure of an emergency diesel generator (EDG), at least one IRU will start within 63 seconds. A second IRU is assumed to be manually switched from the failed EDG to the active EDG within 20 minutes (UFSAR 14.24).
o Pressure buildup, instrument response, SIAS delay 03 seconds (Ref.32) o Emergency diesel generator startup 10 seconds (Ref.32) o Load sequencing delay 20 seconds (UFSAR Table 8.7) o Containment fan cooler startup 30 seconds (Ref.33)
(6B.12) PerRG 1.183, reduction in airborne radioactivity in the containment by containment spray systems that have been designed and maintained in accordance with SRP 6.5.2 (Ref.l 1 ) may be credited.
An acceptable model for the removal of aerosols is described in SRP 6.5.2 (Ref.1 1) and NUREG/CR-5966 (Ref.12), which is incorporated into the analysis code RADTRAD (Refs.13-15).
o Per SRP 6.5.2 the first-order particulate iodine spray removal coefficient may be estimated by:
LP=1.5*(60min/hr)*h*F*(EID)/VSR = 3.414/hr (Ref. 11) h=fall height = I00.ft (UFSAR 6.4.2)
F=Spray pump volume flov rate = 180 cfm (UFSAR 6.4.2)
VSR=Containment volume sprayed region = 1.446E+06 cf (6B.08)
E/D = DF = Ratio of a dimensionless collection efficiency E to the average spray drop diameter D =10/m=3.048/ft (Ref.1 l) o SRP 6.5.2 states that the particulate iodine removal rate should be reduced by a factor of 10 when a DF of 50 is reached. Per RG 1.183, the reduction in the removal rate is not required if the removal rate is based on the calculated time-dependent airborne aerosol mass.
o Per RG 1.183, there is no specified maximum DF for aerosol removal by sprays.
o Time delay: 3.sec(CSAS)+67.sec(response)=70.sec (Refs.42, 10, 9 p.27). This work conservatively assumes a 90 second delay.
An acceptable model for the removal of elemental iodine is described in SRP 6.5.2 (Ref. l 1) and UFSAR 6.4.2:
o LS=6*K*T*F*(60.min/hr) * (0.63) * (0.839) / (VSR*D) = 14.816 / hr K=Gas phase mass transfer coefficient = 13.2 ft/min (UFSAR 6.4.2)
T=Fall time = 100.ft/735.ft/min = 0.136 min (UFSAR 6.4.2)
F=Spray pump volume flow rate = 180 cfm (UFSAR 6.4.2)
VSR=Sprayed region volume = 1.446E+06 cf (6B.08)
D=Spray drop mass linear diameter = 2.87E-03 ft (UFSAR 6.4.2) 0.63 = Conversion factor to account for the less accurate prediction using the mass mean diameter as compared to the surface mean diameter used in the derivation of the algorithm (UFSAR 6.4.2) 0.839 = Conversion factor to account for the less effective stagnant drops as compared to the well mixed drop used in the derivation of the algorithm (UFSAR 6.4.2) o SRP 6.5.2 sets forth a maximum decontamination factor (DF) for elemental iodine based on the maximum iodine activity in the primary containment atmosphere when the sprays actuate, divided by the activity of iodine remaining some time after decontamination.
DF=I+Vs*H/Vc =14.04 Vs = Sump volume = 68329 cf (Ref.40)
Vc = Containment sprayed volume = 1.446E+06 cf (6B.08)
H = 276 (Ref.40)
Teff= Ln(14.04)/Ls = 0.178 hr Note that the dose results are very insensitive to this value of Teff (e.g., decreasing Teff by 50% increases the control room dose by -I%)..
o A time delay of 30 minutes vas assumed in this wvork for elemental sprays to simplify calculation of DF time.
Per SRP 6.5.2, it is conservative to assume that organic iodides are not removed by spray.
CA06449 Rev.000 Page 13 (6B.13) Containment plateout:
o Reduction in aerosol airborne radioactivity in the containment by natural deposition within the containment was credited per RG 1.183 (Ref.08). The 10th percentile Powers aerosol decontamination model (Ref.41) for PWR design basis accidents as incorporated into the RADTRAD analysis code was utilized. Aerosol particles grow by coagulating with other aerosol particles or because steam condenses on them thus gravitational settling of aerosols is usually the dominant aerosol removal process.
o Plateout of organic iodine species w.as not credited in this work.
o Plateout of elemental iodine was not credited in this work.
(6.C) MHA Ventilation Stack Pathway Per RG 1.194 (Ref.43), the total release from containment may be apportioned between the exposed and enclosed building surfaces. Per UFSAR 6.6.2, experience has shown that containment leakage is more likely at penetrations rather than through liner plates or weld joints. Penetration rooms are built adjacent to the outside surface of each containment and enclose the areas around the majority of the penetrations. Thus, a fraction of the containment leakage will leak into the auxiliary building penetration rooms, be processed by the penetration room emergency ventilation system, and be expelled to the atmosphere through the ventilation stacks.
(6C.01) The inventory of fission products in the reactor core and available for release to the containment atmosphere is based on the maximum full power operation of the core with current licensed values for fuel enrichment, fuel bumup, and a core power equal to the current licensed rated thermal power times the ECCS evaluation uncertainty.
The period of irradiation was of sufficient duration to allow the activity of dose-significant radionuclides to reach maximum values. The isotopic activities released from the failed fuel in Ci/MWt were generated in Ref. 05 Case CRCB63, utilizing the isotope generation and depletion computer code SAS2H/ORIGEN-S. For the containment pathway, all 63 isotopic activities are stored in the nuclear inventory file CRCB63NIF listed in Attachment B. To utilize these isotopic source termns, it is necessary to multiply them by the relevant power level in MWt and by the relevant release fractions in the release fraction and timing files.
(6C.02) The core inventory release fractions, by radionuclide groups, for the gap release and early in-vessel damage phases for a DBA LOCA were extracted from RG 1.183 (Ref.08). The onset and duration of each sequential release phase for the DBA LOCA was extracted from RG 1.183 (Ref.08). The activity released from the core during the Gap Release Phase is modeled as increasing linearly over the duration of the phase, while that released during the Early In-Vessel Phase the activity is assumed to be released at the beginning of the phase. Note that step releases are allowed per RG 1.183.
The values are incorporated in the release fraction and timing file MHACTMT.RFT (Attachment C) for use by RADTRAD and are listed in the following table:
Group Gap release Phase Early In-Vessel Phase Total Release Noble Gases (Xe,Kr) 0.05 0.95 1.00 Halogens (I,Br) 0.05 0.35 0.40 Alkali Metals (CsRb) 0.05 0.25 0.30 Tellurium Metals (Te,SbSe) 0.00 0.05 0.05 Ba, Sr Ba, 0.00 0.02 0.02 Noble Metals (Ru,Rh,Pd,Mo,Tc.Co) 0.0000 0.0025 0.0025 Cerium Group (Ce,Pu,Np) 0.0000 0.0005 0.0005 Lanthanides (LaZrNd,Eu.
NbPm,Pr.Sm,Y,Cm.Am) 0.0000 0.0002 0.0002 Release Timing 0.00 hr -0.5 hr 0.5 hr
CA06449 Rev.000 Page 14 (6C.03) The dose conversion factors (DCFs) were extracted from Refs.20-21 and inserted into input files for use by RADTRAD. This data is included in the Conversion Factor Files FGR63.INP in Attachment D for use with failed fuel isotopics. Note that the cloudshine data in the Conversion Factor Files corresponds to the FGR-12 data, while the inhaled chronic data in the Conversion Factor Files corresponds to the worst-case effective data in FGR-I 1. The remaining data in the Conversion Factor Files is extraneous and not used by RADTRAD.
(6C.04) Per RG 1.183 (Ref.08), of the radioiodine released from the RCS to the containment atmosphere in a LOCA, 95% of the iodine released should be assumed to be cesium iodide (Csl), 4.85% elemental iodine, and 0.15% organic iodine. This includes releases from the gap and fuel pellets. With the exception of elemental and organic iodine and noble gases, fission products should be assumed to be in particulate form.
(6C.05) Exclusion Area Boundary (EAB) Atmospheric Dispersion Coefficient:
The Ventilation Stack (VS) to EAB, two-hour, atmospheric dispersion coefficient of 1.44E-4 sec/M3 was calculated via the Gifford wake model extracted from UFSAR 2.3.6, as follows
,VQ = I/[p * (vu7yu, + cA)] = 1.44E-4 sec/m3 where for 1150 m exclusion area boundary distance and 5% frequency p = average wind speed= I m/sec rY= standard deviation of the distribution in the lateral direction = 92 m (UFSAR Table 2-14) 02= standard deviation of the distribution in the vertical direction = 24 m (UFSAR Table 2-14) c= wake factor A= cross-sectional area of structure from which material is released = 0 m (6C.06) Low Population Zone (LPZ) Atmospheric Dispersion Coefficients:
The atmospheric dispersion coefficients from the VS to the LPZ (2 miles) was derived via the data and methodology of UFSAR Fig.2.3-3IUFSAR 14.24.3. Note that the 0-2 hour value was adjusted via the Gifford wake model for a point release rather than a containment release.
Time X/Q (hours)
(sec/m3) 0-2 3.39E-05 2-24 2.20E-06 24-720 5.40E-07 (6C.07) Atmospheric dispersion coefficients from the VS to the Control Room: (Ref.19)
The failed fuel activity released to the containment atmosphere that then leaks into the Auxiliary Building Penetration Rooms will escape out to the environment via the Ventilation Stacks. The main control room inleakage points include the west road inlets, the turbine building, and Access Controls 11 and 13 on the Auxiliary Building roof.
Installation of automatic isolation dampers and radiation monitors at Access Controls II and 13 on the Auxiliary Building Roof are credited in this work.
, tmospheric Dispersion Coe ficients (secrM 3 )
VS1-WR VS2-WR VS1-TB VS2-TB 0-2 hr 9.54E-04 8.73E-04 1.63E-03 1.68E-03 2-8 hr 6.86E-04 5.79E-04 1.19E-03 1.34E-03 8-24hr 2.95E-04 2.12E-04 4.61 E-04 5.14E-04 1-4 days I 2.13E-04 I 1.49E-04 3.22E-04 3.84E-04 4-30 days I 1.56E-04 1.03E.04 2.61E-04 3.12E-04 The atmospheric dispersion coefficients corresponding to the Unit 2 VS to the turbine building will be conservatively utilized in this work. Note that neither thermal buoyancy nor vertical effluent velocity are credited in this work.
CA06449 Rev. 000 Page 15 (6C.08) Containment volume:
Net free volume:
1.989E+06 cf (UFSAR Tab.14.20-3, Ref.39)
Containment sprayed volume:
1.446E+06 cf Volume fraction:
0.7273 (Ref.40)
Containment unsprayed volume:
0.543E+06 cf Volume fraction:
0.2727 (Ref.40)
Note: Assumes sprayed and unsprayed volume fractions remain unchanged from Ref.40.
(6C.09) Fan coolers are credited for mixing of air between the sprayed region and unsprayed region of containment.
(a) Three 110000 cfm cooling units are normally in operation in containment. Upon receipt of a SIAS, the fourth cooling unit is automatically started on the 55000 cfm low speed setting and simultaneously the other three units are switched to low speed operation. If offsite power is not available, the emergency diesel generators are started. Each of two emergency diesel generator busses carries the load of two cooling units (UFSAR 6.5.3 and 6.5.4). Thus, two 55000 cfm cooling units are credited in this work.
(b) Containment fan cooler operation requires 38 seconds to activate:
Pressure buildup, instrument response, SIAS delay 03 seconds (Ref.32)
Emergency diesel generator startup 10 seconds (Ref.32)
Load sequencing delay 15 seconds (UFSAR Table 8.7)
Containment fan cooler startup 10 seconds (UFSAR Table 7.4)
For conservatism, a 60 second activation delay will be utilized in this work.
(6C. 10) Containment Leakage (a) The maximum allowable containment leakage rate La contained in the Containment Leakage Rate Testing Program of TS 5.5.16 will be reduced from 0.20 percent per day at containment peak pressure Pa to 0.16 percent per day at Pa. Per RG 1.183, the containment should be assumed to leak at the leak rate incorporated in the technical specifications for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and at 50% of this leak rate for the remaining duration of the accident.
(b) Per Regulatory Guide 1.194 (Ref.43), the total release from containment may be apportioned between the exposed and enclosed building surfaces.
The CCNPP original licensing basis as described in the Final Safety Analysis Report (FSAR 14.18) assumed that at least 50% of the containment leakage would be into the penetration rooms, which are maintained at negative pressure and which discharge through the penetration room HEPA/charcoal filters into the plant vent.
Based on Local Leak Rate Testing (LLRT) performed per TS 5.5.16, the Containment Leakage Rate Testing Program, it can be shown (Attachment P) that at least 75% of the containment leakage would be into the penetration rooms.
Based on the ratio of containment surface enclosed by the Auxiliary Building to the total containment surface area, it can be shown that at least 28.7% of the containment leakage would be into the penetration rooms (Attachment 0).
In this work a conservative bypass fraction from the containment to the penetration rooms of 28% was assumed.
Thus, 0.0448% of the containment volume leaks from the containment to the auxiliary building penetration rooms per day for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and 0.0224% per day thereafter.
Leak Rate = (1.446E+6 cf)*(0.000448)/(24*60) = 0.449867 cfm 0-24 hours Sprayed Region Leak Rate = (1.446E+6 co*(0.000224)/(24*60) = 0.224933 cfm 24-720 hours Sprayed Region Leak Rate = (0.543E+6 cf)*(0.000448)/(24*60) = 0.168933 cfm 0-24 hours Unsprayed Region Leak Rate = (0.543E+6 cf)*(0.000224)/(24*60) = 0.084467 cfm 24-720 hours Unsprayed Region (6C.1 1) Containment iodine removal system:
o Per UFSAR 6.7, the containment iodine removal system (IRS) incorporates three filter units, each with a capacity to handle 50% of the required air flow.. Each unit consists of activated charcoal filters preceded by HIEPA filters. Per TS 5.5.11, each filter unit has a 20000+/-10% cfm flowrate with a filter efficiency of 90% for elemental and particulate species and 30% for organic species per RG 1.52 (Ref.28).
CA06449 Rev. 000 Page 16 o
This work assumes that the containment filters affect the entire containment; however, due to the well mixed quality of the containment atmosphere, the effect of applying the containment filter to a particular containment region is minor.
o Per UFSAR 6.7.2, SIAS automatically starts three recirculation filter units. If offsite power is not available, the emergency diesel generators are started. Each of two emergency diesel generator busses carries the load of two recirculation filter units (UFSAR Table 8-7).
Per UFSAR Table 8.7, one iodine removal unit (IRU) is connected to one bus, while the other two are connected to the other bus. Thus, assuming a LOOP concurrent with a LOCA and with the single failure of an emergency diesel generator (EDG), at least one IRU will start within 63 seconds. A second IRU is assumed to be manually switched from the failed EDG to the active EDG within 20 minutes (UFSAR 14.24).
O Pressure buildup, instrument response, SIAS delay 03 seconds (Ref.32) o Emergency diesel generator startup 10 seconds (Ref.32) o Load sequencing delay 20 seconds (UFSAR Table 8.7) o Containment fan cooler startup 30 seconds (Ref.33)
(6C.12) Per RG 1.183, reduction in airborne radioactivity in the containment by containment spray systems that have been designed and maintained in accordance with SRP 6.5.2 (Ref.l 1) may be credited.
An acceptable model for the removal of aerosols is described in SRP 6.5.2 (Ref.l 1 ) and NUREG/CR-5966 (Ref.12), which is incorporated into the analysis code RADTRAD (Refs.13-15).
o Per SRP 6.5.2 the first-order particulate iodine spray removal coefficient may be estimated by:
LP=1.5*(60min/hr)*h*F*(E/D)NSR
= 3.414/hr (Ref.l I) h=fall height = 100.fl (UFSAR 6.4.2)
F=Spray pump volume flow rate = 180 cfm (UFSAR 6.4.2)
VSR=Containment volume sprayed region = 1.446E+06 cf (6B.08)
E/D = DF = Ratio of a dimensionless collection efficiency E to the average spray drop diameter D =10/mn3.048/fl (Ref. I1) o SRP 6.5.2 states that the particulate iodine removal rate should be reduced by a factor of 10 when a DF of 50 is reached. Per RG 1.183, the reduction in the removal rate is not required if the removal rate is based on the calculated time-dependent airborne aerosol mass.
o Per RG 1.1 83, there is no specified maximum DF for aerosol removal by sprays.
o Time delay: 3.sec(CSAS)+67.sec(response)=70.sec (Refs.42, 10, 9 p.27). This work conservatively assumes a 90 second delay.
An acceptable model for the removal of elemental iodine is described in SRP 6.5.2 (Ref. l l) and UFSAR 6.4.2:
o LS=6*K*T*F*(60.min/hr) * (0.63) * (0.839) / (VSR*D) = 14.816 / hr K=Gas phase mass transfer coefficient = 13.2 ft/min (UFSAR 6.4.2)
T=Fall time = 100.ft/735.ftlmin = 0.136 min (UFSAR 6.4.2)
F=Spray pump volume flow rate = 180 cfm (UFSAR 6.4.2)
VSR=Sprayed region volume = 1.446E+06 cf (6B.08)
D =Spray drop mass linear diameter = 2.87E-03 ft (UFSAR 6.4.2) 0.63 = Conversion factor to account for the less accurate prediction using the mass mean diameter as compared to the surface mean diameter used in the derivation of the algorithm (I JFSAR 6.4.2) 0.839 = Conversion factor to account for the less effective stagnant drops as compared to the wxell mixed drop used in the derivation of the algorithm (UFSAR 6.4.2) o SRP 6.5.2 sets forth a maximum decontamination factor (DF) for elemental iodine based on the maximum iodine activity in the primary containment atmosphere when the sprays actuate, divided by the activity of iodine remaining some time after decontamination.
DFl I +Vs*H/Vc= 14.04 Vs = Sump volume = 68329 cf (Ref.40)
Ve = Containment sprayed volume = 1.446E+06 cf (6B.08)
I1 = 276 (Ref.40)
Teff= Ln(14.04)/Ls = 0.178 hr Note that the dose results are very insensitive to this value of leff (e.g., decreasing Teff by 5('Yo increases the control room dose by -1%)..
CA06449 Rev.000 Page 17 o
A time delay of 30 minutes was assumed in this work for elemental sprays to simplify calculation of DF time.
Per SRP 6.5.2, it is conservative to assume that organic iodides are not removed by spray.
(6C.13) Containment plateout:
o Reduction in aerosol airborne radioactivity in the containment by natural deposition within the containment was credited per RG 1.183 (Ref.08). The 10th percentile Powers aerosol decontamination model (Ref.41) for PWR design basis accidents as incorporated into the RADTRAD analysis code was utilized. Aerosol particles grow by coagulating with other aerosol particles or because steam condenses on them thus gravitational settling of aerosols is usually the dominant aerosol removal process.
o Plateout of organic iodine species was not credited in this work.
o Plateout of elemental iodine was not credited in this work.
(6C.14) Penetration Room Ventilation and Filtration System:
o Per UFSAR 6.6.1, the Containment Penetration Room Emergency Ventilation System (PREVS) is designed to collect and process containment penetration leakage, so as to reduce to a minimum the environmental radioactivity levels from post-accident containment leaks. To minimize the release of radioactive material to the environment, penetration room ventilation is continuously routed through a prefilter, a high efficiency particulate air (HIEPA) filter, and an activated charcoal filter, positioned in series.
o Following a LOCA, a Containment Isolation Signal (CIS) wvill start both of the two full-size blowers. The entire system is designed to operate under negative pressure up to the fan discharge.
o Per TS 5.5.11. each PREVS unit has a design flowrate of 2000 +/- 10% cfm with an efficiency of 90% for elemental and particulate species and 30% for organic species.
(6.D) MHA RXWT Pathway Per RG 1.183 (Ref.8), ESF systems that recirculate sump water outside of the primary containment are assumed to leak during their intended operation. This release source may include leakage through valves isolating interfacing systems. There is a potential for an unmonitored release pathway resulting from the post-LOCA leakage of isolation valves in the Safety Injection or Containment Spray system recirculation lines to the Refueling Water Tank (RWT),
which is vented directly to the atmosphere (Ref.36). During the recirculation phase, sump water is recirculated through the ECCS pumps and could leak through various valves and reach the RWT. The two pathways include the two valves in series in the minimum flow recirculation line header (MOV6591660) and the valve from the containment spray pumps (SI459). The radiological consequences from the postulated leakage should be analyzed and combined with consequences postulated for other fission product release paths to determine the total calculated radiological consequences from the LOCA.
(6D.01) The inventory of fission products in the reactor core and available for release to the containment sump is based on the maximum full power operation of the core with current licensed values for fuel enrichment, fuel bumup, and a core power equal to the current licensed rated thermal power times the ECCS evaluation uncertainty. The period of irradiation was of sufficient duration to allow the activity of dose-significant radionuclides to reach maximum values. The isotopic activities released from the failed fuel in Ci!MWt were generated in Ref. 05 Case CRCB63, utilizing the isotope generation and depletion computer code SAS2H1IORIGEN-S. For the containment pathway, all 63 isotopic activities are stored in the nuclear inventory file CRCB63.NIF listed in Attachment B. To utilize these isotopic source terms, it is necessary to multiply them by the relevant power level in MWt and by the relevant release fractions in the release fraction and timing files.
(6D.02) The core inventory release fractions, by radionuclide groups, for the gap release and early in-vessel damage phases for a DBA LOCA were extracted from RG 1.183 (Ref.08). The onset and duration of each sequential release phase for the DBA LOCA was extracted from RG 1.183 (Ref.08). The activity released from the core during each release phase is modeled as increasing linearly over the duration of the phase. With the exception of noble gases, all of the fission products released from the fuel should be assumed to instantaneously and homogeneously mix in the primary containment sump water at the time of release from the core. With the exception of iodine, all radioactive materials in the recirculating liquid should be assumed to be retained in the liquid phase.
The values are
CA06449 Rev.000 Page 18 incorporated in the release fraction and timing file MHARWT.RFT (Attachment G) for use by RADTRAD and are listed in the following table:
Group Gap release Phase Early In-Vessel Phase Total Release Noble Gases (Xe,Kr) 0.00 0.00 0.00 Halogens (1.Br) 0.05 0.35 0.40 Alkali Metals (Cs,Rb) 0.00 0.00 0.00 Tellurium Metals (TeSb,Se) 0.00 0.00 0.00 Ba, Sr 0.00 0.00 0.00 Noble Metals (RuRhPd,MoTc,Co) 0.00 0.00 0.00 Cerum Group (Ce,Pu,Np) 0.00 0.00 0.00 Lanthanides (La,Zr,Nd,Eu, NbPm.PrSm.Y.CmAm) 0.00 0.00 0.00 Release Timing 0.00 hr - 0.5 hr 0.5 hr-1.8 hr (6D.03) The dose conversion factors (DCFs) were extracted from Refs.20-21 and inserted into input files for use by RADTRAD. This data is included in the Conversion Factor Files FGR63.INP in Attachment D for use with failed fuel isotopics. Note that the cloudshine data in the Conversion Factor Files corresponds to the FGR-12 data, while the inhaled chronic data in the Conversion Factor Files corresponds to the worst-case effective data in FGR-l 1. The remaining data in the Conversion Factor Files is extraneous and not used by RADTRAD.
(6D.04) Per Ref.08, radioiodine that is postulated to be available for releases from the RWT to the environment should be assumed to be 97% elemental and 3% organic.
(6D.05) Exclusion Area Boundary (EAB) Atmospheric Dispersion Coefficient:
The Refueling Water Tank (RWT) to EAB, two-hour, atmospheric dispersion coefficient of 1.44E-4 sec/m3 was calculated via the Gifford wake model extracted from UFSAR 2.3.6, as follows
)M = l/[P * (Orayo + cA)] = 1.44E4 sec/m3 where for 1150 m exclusion area boundary distance and 5% frequency p = average wind speed = I m/sec oy= standard deviation of the distribution in the lateral direction = 92 m (UFSAR Table 2-14) a,= standard deviation of the distribution in the vertical direction = 24 m (UFSAR Table 2-14) c= wake factor A= cross-sectional area of structure from which material is released = 0 m (6D.06) Low Population Zone (LPZ) Atmospheric Dispersion Coefficients:
The atmospheric dispersion coefficients from the RWT to the LPZ (2 miles) was derived via the data and methodology of UFSAR Fig.2.3-3/UFSAR 14.24.3. Note that the 0-2 hour value was adjusted via the Gifford wake model for a point release rather than a containment release.
Time X/Q (hours)
(sec/rm3) 0-2 3.39E-05 2-24 2.20E-06 24-720 5.40E-07 (6D.07) Atmospheric dispersion coefficients from the RWT to the Control Room: (Ref.19)
CA06449 Rev. 000 Page 19 ESF systems that recirculate sump water outside the primary containment are assumed to leak during their intended operation. The failed fuel activity released to the containment sump that then leaks into the RWT wvill escape out to the environment via the RWT vent. The main control room inleakage points include the west road inlets, the turbine building, and Access Controls I I and 13 on the Auxiliary Building roof. Installation of automatic isolation dampers and radiation monitors at Access Controls 11 and 13 on the Auxiliary Building Roof are credited in this wvork.
Atmospheric Dispersion Coefficients (sect
)
RWT1-WR RWT2-WR RWT1-TB RWT2-TB 0-2 hr 2.57E-03 2.30E-03 7.72E-04 7.90E-04 2-8 hr 2.13E-03 1.32E-03 6.18E-04 6.92E-04 8-24hr 8.50E-04 4.87E-04 2.26E-04 2.86E-04 1-4 days 5.71 E.04 3.64E-04 1.87E-04 2.21 E-04 4-30 days 4.85E-04 2.55E-04 1.45E-04 1.76E-04 The atmospheric dispersion coefficients corresponding to the Unit 1 RWT to the west road inlet will be conservatively utilized in this work.
(6D.08) The liquid volume of the containment sump is 68329 cf per Ref.40.
(6D.09) The air volume of the RWT is 52109.75 cf per Ref.34.
(6D.10) The minimum time to RAS is 32 minutes per Ref. 35.
(6D.1 1) There is a potential for an unmonitored release pathway resulting from the post-LOCA leakage of isolation valves in the Safety Injection or Containment Spray system recirculation lines to the Refueling Water Tank (RWT),
which is vented directly to the atmosphere (Ref.36). During the recirculation phase, sump water is recirculated through the ECCS pumps and could leak through various valves and reach the RWT. The two pathways include the two valves in series in the minimum flow recirculation line header (MOV659/660) and the valve from the containment spray pumps (S1459). By implementing more precise testing, the leakage acceptance criteria through S1459 and MOV659/660 will be reduced to 1000 cc/hr in STP-M28-1/2 (Ref.37). Per RG 1.183 (Ref.8), this leakage must be doubled to account for valve degradation between testing. The leakrate is thus a
LR = (1000 cc/hr)
- 2 / (28316.85 cc/co) / (60 minthr) = 1.1772E-03 cfm (6D.12) Per RG 1.183 Appendix A, if the temperature of the leakage exceeds 212°F, the fraction of total iodine in the liquid that becomes airborne should be assumed equal to the fraction of the leakage that flashes to vapor. This flash fraction, FF, should be determined using a constant enthalpy, h, process, based on the maximum time-dependent temperature of the sump water circulating outside the containment.
FF = (hrn - hr) / hrg where hn is the enthalpy of liquid at system design temperature and pressure; hr2 is the enthalpy of liquid at saturation conditions (14.7 psia, 212°F), and hrg is the heat of vaporization at 212°F.
Based on the time-dependent sump temperature data in UFSAR Figures 14.20-5 and 14.20-6 and the ASME steam tables of Ref.3 1, the following flashing fractions can be calculated.
-I ___
Sump I
Sump I
RWT I
RWT RWT Flashing 1
lime Temperature Fluid Enthalpy Temperature Fluid Enthalpy Fluid-Gas Enthalpy Fraction Hours 234 202.4 212 180.2 970.3 0.0229 0.53 212 180.2 212 180.2 970.3 0.0000 200 168.1 212 180.2 970.3 0.0000 2.78 168 136.0 212 180.2 970.3 0.0000 27.78 148 115.9 212 1 80.2 970.3 1
0.0000 _
1 277.78
CA06449 Rev. 000 Page 20 Per this methodology, the flashing fraction does not exceed 3%.
However, per RG 1.183 Appendix A, if the temperature of the leakage is less than 212TF or the calculated flash fraction is less than 10%, the amount of iodine that becomes airborne should be assumed to be 10% of the total iodine activity in the leaked fluid, unless a smaller amount can be justified based on the actual sump pH history and area ventilation rates, A 10% flash fraction is conservatively assumed in this work. Thus the leakrate of Section 6.D.I I is decreased by a factor of 10.
(6D.13) Per RG 1.183 (Ref.8), reduction in release activity by dilution or holdup within buildings or by ESF ventilation filtration systems, may be credited where applicable. In order to determine the amount of RWT release to the atmosphere, the breathing of the RWT through the vent due to diumal temperature variations was calculated in Ref.34. The breathing was determined by performing a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> transient thermal analysis of the RWT using the computer code TSAP and assuming RWT atmospheric temperature characteristics based on the maximum solar load during summer solstice and a minimum ambient nighttime temperature. This methodology results in an average 4.2 cfm leakrate from the RWT to the environment.
(6.E) MHA Hydrogen Purge Line Pathway Per RG 1.183 (Ref.8), if the primary containment is routinely purged during power operations, releases via the purge system prior to containment isolation should be analyzed and the resulting doses summed with the postulated doses from other release paths. Per Ref.42, the containment vent system is used for an unlimited amount of pressure and containment radioactivity control purposes; however, the vent isolation valves may also be opened for surveillance testing. The 4-inch vent line isolates on a SIAS and CRS.
(6E.01) Per RG 1.183 (Ref.08), if the primary containment is routinely purged during power operations, releases via the purge system prior to containment isolation should be analyzed and the resulting doses summed with the postulated doses from other release paths.
The purge release evaluation should assume that 100% of the radionuclide inventory in the reactor coolant system liquid is released to the containment atmosphere at the initiation of the LOCA. This inventory should be based on the TS RCS equilibrium activity. Iodine spikes need not be considered. The purge system is isolated before the onset of the gap release phase, thus release fractions associated with gap release and early in-vessel phases need not be considered.
An EXCEL spreadsheet (MHA.XLS(MHA-ST) displayed in Attachment A) was developed to calculate the activity released to the primary system post-LOCA. The initial primary specific activities in pCi/gm consistent with the TS 3.4.15 1.0 pCi/gm limit were extracted from Ref.4 and are listed in column C of Attachment A. These were converted to total primary isotopic source terms in Attachment A column D via the following algorithm:
An = AST;
- MRCS
- 0.000001 Ci where AST;
= Isotopic activity per unit mass (pCi 'gm) (Ref.04)
MRCS
= Water mass in RCS (gm)
The total primary isotopic source term was then halved in Attachment A column E to reflect that the TS 3.4.15 limit for primary activity will be reduced from 1.0 pCi'gm to 0.5 pCi/gm.
These isotopic activities were inserted into the nuclear inventory file PRI14.NIF for use by RADTRAD. The file is listed in Attachment I and consists of the 14 primary noble gas and iodine isotopes. The activities are the total primary activities and are not per unit power. Thus a power of one should be designated when employing this file.
(6E.02) Per RG 1.183 (Ref.08), 100% of the TS primary iodine and noble gas activities are assumed to be released instantaneously and homogeneously throughout the containment atmosphere at the initiation of the accident. This is incorporated into the failed fuel release fraction and timing file MHAHP.RFT, listed in Attachment J..
CA06449 Rev.000 Page 21 (6E.03) The dose conversion factors (DCFs) were extracted from Refs.20-21 and inserted into input files for use by RADTRAD. This data is included in the Conversion Factor File FGRl4.INP in Attachment K for use with primary system isotopics. Note that the cloudshine data in the Conversion Factor Files corresponds to the FGR-12 data, while the inhaled chronic data in the Conversion Factor Files corresponds to the worst-case effective data in FGR-I 1.
The remaining data in the Conversion Factor Files is extraneous and not used by RADTRAD.
(6E.04) Per Ref.08, radioiodine that is postulated to be available for releases from the RCS to the environment should be assumed to be 97% elemental and 3% organic.
(6E.05) Exclusion Area Boundary (EAB) Atmospheric Dispersion Coefficient:
The Ventilation Stack (VS) to EAB, two-hour, atmospheric dispersion coefficient of 1.44E-4 sec/m 3 was calculated via the Gifford wake model extracted from UFSAR 2.3.6, as follows X4Q = 1/[, * (7rwrya. + cA)] = 1.44E-4 sec/in3 where for 1150 in exclusion area boundary distance and 5% frequency p = average wind speed = I rn/sec ay= standard deviation of the distribution in the lateral direction = 92 m (UFSAR Table 2-14) uz= standard deviation of the distribution in the vertical direction = 24 m (UFSAR Table 2-14) c= wake factor A= cross-sectional area of structure from which material is released = 0 m (6E.06) Low Population Zone (LPZ) Atmospheric Dispersion Coefficients:
The atmospheric dispersion coefficients from the VS to the LPZ (2 miles) was derived via the data and methodology of UFSAR Fig.2.3-3IUFSAR 14.24.3. Note that the 0-2 hour value was adjusted via the Gifford wake model for a point release rather than a containment release.
Time X/Q (hours)
(sec/ir 3) 0-2 3.39E-05 2-24 2.20E-06 24-720 5.40E-07 (6E.07) Atmospheric dispersion coefficients from the VS to the Control Room: (Ref.19)
The TS primary activity released to the containment atmosphere that then flows through the Hydrogen Purge Line into the Auxiliary Building Penetration Rooms will escape out to the environment via the Ventilation Stacks. The main control room inleakage points include the west road inlets, the turbine building, and Access Controls 11 and 13 on the Auxiliary Building roof.
Installation of automatic isolation dampers and radiation monitors at Access Controls 11 and 13 on the Auxiliary Building Roof are credited in this work.
Atmospheric Dispersion Coefficients (sec/M 3 )
I VS1-WR VS2-WR VS1-TB VS2-TB 0-2 hr 9.54E-04 8.73E-04 1.63E-03 1.68E-03 2-8 hr 6.86E-04 5.79E-04 1.19E-03 1.34E-03 8-24hr 2.95E-04 2.12E-04 4.61E-04 5.14E-04 1-4 days 2.13E-04 1.49E-04 3.22E-04 3.84E-04 4-30 days 1.56E-04 1.03E-04 2.61 E-04 3.12E-04 The atmospheric dispersion coefficients corresponding to the Unit 2 VS to the turbine building will be conservatively utilized in this work. Note that neither thermal buoyancy nor vertical effluent velocity are credited in this work.
(6E.08) Containment volume:
CA06449 Rev.OO0 Page 22 Net free volume:
1.989E+06 cf(UFSARTab.14.20-3, Ref.39)
No sprays are credited during the first 30 seconds, so it is not necessary to segment the containment into sprayed and unsprayed regions.
(6.E.09) Per Ref.42, the maximum total time of 30 seconds for valve closure is based on 2.4 seconds for containment pressure buildup, instrument response, and SIAS delay, 10 seconds for emergency diesel generator startup, and 15 seconds for valve stroke time. An additional; margin of 2.6 seconds is included for conservatism/margin. The failure of one diesel generator would not affect the results, because both diesel generators will start on a SIAS. If one diesel generator fails, the other automatically picks up the load with no significant delay. The purge system is isolated before the onset of the gap release phase, thus release fractions associated with gap release and early in-vessel phases need not be considered.
(6E.10) Penetration Room Ventilation and Filtration System:
o Per UFSAR 6.6.1, the Containment Penetration Room Emergency Ventilation System (PREVS) is designed to collect and process containment penetration leakage, so as to reduce to a minimum the environmental radioactivity levels from post-accident containment leaks. To minimize the release of radioactive material to the environment, penetration room ventilation is continuously routed through a prefilter, a high efficiency particulate air (HEPA) filter, and an activated charcoal filter, positioned in series.
o Following a LOCA, a Containment Isolation Signal (CIS) will start both of the two full-size blowers. The entire system is designed to operate under negative pressure up to the fan discharge.
o Per TS 5.5.11, each PREVS unit has a design flowrate of 2000 +/- 10% cfm with an efficiency of 90% for elemental and particulate species and 30% for organic species.
(6.E. I1) The flow from the containment to the atmosphere via the 4" hydrogen purge line was calculated assuming peak containment pressure for the full 30 seconds that the line is open.
N2IN1 0.2296 l
N2iN1=P2/P1 Mole fraction of air MWair 29 l
Molecular weight of air (Crane P.A-8)
MWwater 18 l
Molecular weight of water (Crane P.A-8)
MWmix 20.5259 Molecularweightof mixture=MWairN2/N1+MWwater *1-N2/N1)
R 75.2708 l
Gas constant=1545/M (Crane p.1.0)
T 748 R
Absolute temperature in degrees Rankine (288+460) (UFSAR Figures 14.20-5/6)
Rho 0.1637 Ibm/cf Rho=144*P/(R'T) k 1.3 Ratio of specific heat at constant pressure to specific heat at constant volume (steam)
P1 64 psia Containment design pressure (UFSAR Table 14.20-3)
P2 14.696 psia STP pressure (Steam Tables) dP/P 0.7704 psia (P1-P2yP1 rho 0.1637 Ibm/cf Containment density (M-89-33) d 4
inches Pipe diameter (M-89033)
K 15.3 Flow resistance coefficient (M-89-33)
Y 0.735 Expansion factor (Crane p.A-22) w 4.4840 Ibm/sec Darcy Equation: w=0.525'Y*dA2-sqrt(dp-rho/K) (Crane Eq 1-11)
F 1643.84 cfm F=w60/rho (6.F) MIIA Containment Shine Per RG 1.183 (Ref.8), the analysis should consider radiation shine from radioactive material in the containment.
(6F.01) The inventory of fission products in the reactor core and available for release to the containment atmosphere is based on the maximum full power operation of the core with current licensed values for fuel enrichment, fuel hurnup, and a core power equal to the current licensed rated thermal power times the ECCS evaluation uncertainty.
CA06449 Rev. 000 Page 23 The period of irradiation was of sufficient duration to allow the activity of dose-significant radionuclides to reach maximum values. The isotopic activities released from the failed fuel in Ci/MWt were generated in Ref. 05 Case CRCB63, utilizing the isotope generation and depletion computer code SAS2H/ORIGEN-S. For the containment shine pathway, all 63 isotopic activities in Ci1MWt are listed in the second column of the spreadsheet (MST.XLS(MSC)) displayed in Attachment Q.
(6F.02) The core inventory release fractions, by radionuclide groups, for the gap release and early in-vessel damage phases for a DBA LOCA were extracted from RG 1.183 (Ref.08). The onset and duration of each sequential release phase for the DBA LOCA was extracted from RG 1.183 (Ref.08). The activity released from the core during the Gap Release and the Early In-Vessel Phase is assumed to be released at the beginning of the accident. Note that step releases are allowed per RG 1.183.
The values are incorporated in the third column of the spreadsheet (MST.XLS(MSC)) displayed in Attachment Q.
Group Gap Release Phase Early In-Vessel Phase Total Release Noble Gases (Xe,Kr) 0.05 0.95 1.00 Halogens (1,Br) 0.05 0.35 0.40 Alkali Metals (Cs,Rb) 0.05 0.25 0.30 Tellurium Metals (re,SbSe) 0.00 0.05 0.05 Ba, Sr 0.00 0.02 0.02 Noble Metals (Ru,RhPd,MoTc,Co) 0.0000 0.0025 0.0025 Cerium Group (Ce,Pu,Np) 0.0000 0.0005 0.0005 Lanthanides (LaZrNdEu, Nb,Pm,Pr,Sm,Y.Cm,Am) 0.0000 0.0002 0.0002 Release Timing 0.00 hr 0.00 hr (6F.03) For the containment shine pathway, all 63 isotopic activities in Ci released to the containment atmosphere at the beginning of the accident are listed in the fourth column of the spreadsheet (MST.XLS(MSC)) displayed in Attachment Q and are the product of the activity per unit power (Column 2), the release fraction (Column 3), and the core power of 2754 MWt (6A.01). These values are input into Microshield to calculate containment shine doses in the control room. Note that Microshield will allow parent decay and daughter buildup, so that subsequent isotopic quantities as a function of decay time are automatically calculated by Microshield.
(6F.04) For the containment shine analysis, no removal of airborne radioactivity is assumed except for decay.
(6F.05) The geometry required for Microshield execution is the following:
Containment radius is 65' 0" per Ref.44.
Containment stainless steel liner plate thickness isn 0.25" per UFSAR 5.1.2.1.
Containment concrete wall thickness is 3' 9" per Ref.44.
Containment height is 181' 7.75" per Ref.44.
Closest distance between containment and control room proper is 17.90' per Refs.59-61.
The control room concrete vall is 2' thick per Ref.62 p.100.
Note that the dose point is at 89' from containment, which is approximately 65'+3.75'+17.9'+2'. With Microshield, one gets the same results assuming 65'+3.75'+9.15'+2'+8.75'.
(6.G) MIIIA Plume Shine Per RG 1.183 (Ref.8), the analysis should consider radiation shine from the external radioactive plume released from containment.
CA06449 Rev.000 Page 24 (6G.01) The inventory of fission products in the reactor core and available for release to the containment atmosphere is based on the maximum full power operation of the core with current licensed values for fuel enrichment, fuel burnup, and a core power equal to the current licensed rated thermal power times the ECCS evaluation uncertainty.
The period of irradiation was of sufficient duration to allow the activity of dose-significant radionuclides to reach maximum values. The isotopic activities released from the failed fuel in CiIMWt were generated in Ref. 05 Case CRCB63, utilizing the isotope generation and depletion computer code SAS2H/ORIGEN-S.
For the plume shine pathway, all 63 isotopic activities in Ci/MWt are listed in the second column of the spreadsheet (MST.XLS(MSP))
displayed in Attachment R.
(6G.02) The core inventory release fractions, by radionuclide groups, for the gap release and early in-vessel damage phases for a DBA LOCA were extracted from RG 1.183 (Ref.08). The onset and duration of each sequential release phase for the DBA LOCA was extracted from RG 1.183 (Ref.08). The activity released from the core during the Gap Release and the Early In-Vessel Phase is conservatively assumed to be released at the beginning of the accident for this pathway. Note that step releases are allowed per RG 1.183. The values are incorporated in the third column of the spreadsheet (MST.XLS(MSP)) displayed in Attachment R.
Group Gap Release Phase Early In-Vessel Phase Total Release Noble Gases (Xe,Kr) 0.05 0.95 1.00 Halogens (I.Br) 0.05 0.35 0.40 Alkali Metals (CsRb) 0.05 0.25 0.30 Tellurium Metals (Te,SbSe) 0.00 0.05 0.05 Ba, Sr 0.00 0.02 0.02 Noble Metals (RuRhPdMo.Tc,Co) 0.0000 0.0025 0.0025 Cerium Group (CePuNp) 0.0000 0.0005 0.0005 Lanthanides (La,Zr,Nd,Eu, Nb,PmPrSmYCm,Am) 0.0000 0.0002 0.0002 Release Timing 0.00 hr 0.00 hr (6G.03) Containment Leakage The maximum allowable containment leakage rate La contained in the Containment Leakage Rate Testing Program of TS 5.5.16 will be reduced from 0.20 percent per day at containment peak pressure Pa to 0.16 percent per day at Pa. Per RG 1.183, the containment should be assumed to leak at the leak rate incorporated in the technical specifications for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and at 50% of this leak rate for the remaining duration of the accident. Thus the fraction of the containment activity that leaks from the containment over 30 days can be calculated to be 0.0016+0.0008*29=0.0248.
(6G.04) For the plume shine pathway, all 63 isotopic activities in Ci released to the containment atmosphere at the beginning of the accident and then leaked out of containment during the accident are listed in the fourth column of the spreadsheet (MST.XLS(MSP)) displayed in Attachment R and are the product of the activity per unit power (Column 2), the release fraction (Column 3), the core power of 2754 MWt (6A.01), and the containment leakage fraction 0.0248 (6G.03). These values are input into Microshield to calculate plume shine doses in the control room.
(6F.05) For the plume shine analysis, no removal of airborne radioactivity is assumed except for decay.
(6G.06) The geometry required for Microshield execution is the following:
The control room volume is 289194 ft3 (6A.07), while the control room height is approximately 69'45'-2'=22'.
Assuming that the containment floor area is a square, the effective containment length is sqrt(289194/22) =
114.65 ft = 35 m.
CA06449 Rev. 000 Page 25 The maximum containment internal elevation is 190' 1.75" per Ref.44.
The auxiliary building roof elevation above the containment is 91.5' per Ref. 19.
While the bulk of the auxiliary building roof is 2' of concrete, the minimum thickness is 6" per Ref.62.
The control room ceiling extends from 67' to 69' elevation and is 2' of concrete per Ref.62.
Thus the plume height, which is assumed to extend from the auxiliary building roof to the top of containment, is 98.65'. The concrete roof is 0.5'. The 69' auxiliary building distance from floor to ceiling is 22'. The control room ceiling is 2' of concrete. These values are entered into Microshield.
(6G.07) Finally, it is necessary to calculate the activity dilution factor, assuming that the activity exits the containment horizontally flowing towards the control room. Per Ref.19, the average wind velocity, averaged over 8 years, is 2.99 rn/sec. It will be conservatively assumed that the wind velocity for the 30 days subsequent to the accident is 0.3 m/sec. Thus the dilution factor can be calculated as 35/(0.3*3600*24*30) = 4.50E-05. This is doubled for the first 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, since the leak rate is twice as high.
(6.H) 1IHA Control Room Filter Shine Per RG 1.183 (Ref.8), the analysis should consider radiation shine from the radioactive material buildup on recirculation filters.
(6H.01) The inventory of fission products in the reactor core and available for release to the containment atmosphere is based on the maximum full power operation of the core with current licensed values for fuel enrichment, fuel burnup, and a core power equal to the current licensed rated thermal power times the ECCS evaluation uncertainty.
The period of irradiation wvas of sufficient duration to allow the activity of dose-significant radionuclides to reach maximum values. The isotopic activities released from the failed fuel in CiIMWt were generated in Ref. 05 Case CRCB63, utilizing the isotope generation and depletion computer code SAS2H/ORIGEN-S. For the control room filter shine pathway, all 63 isotopic activities in CiIMWt are listed in the second column of the spreadsheet (MST.XLS(MSF)) displayed in Attachment S.
(6H.02) The core inventory release fractions, by radionuclide groups, for the gap release and early in-vessel damage phases for a DBA LOCA were extracted from RG 1.183 (Ref.08). Note that the control room filtration system filters aerosols and elemental and organic iodines. It does not filter the noble gas radionuclides, so they are excluded from this analysis: their release fractions are set to zero. The activity released from the core during the Gap Release and the Early In-Vessel Phase is conservatively assumed to be released at the beginning of the accident. Note that step releases are allowed per RG 1.183.
The values are incorporated in the third column of the spreadsheet (MST.XLS(MSF)) displayed in Attachment S.
Group Gap Release Phase Early In-Vessel Phase Total Release Noble Gases (XeKr) 0.00 0.00 0.00 Halogens (I.Br) 0.05 0.35 0.40 Alkali Metals (CsRb) 0.05 0.25 0.30 Tellurium Metals (TeSb,Se) 0.00 0.05 0.05 Ba, Sr 0.00 0.02 0.02 Noble Metals (Ru,RhPd,Mo,Tc,Co) 0.0000 0.0025 0.0025 Cerium Group (CePu.Np) 0.0000 0.0005 0.0005 Lanthanides (La,Zr.Nd,Eu, Nb,PmPr,SmY,Cm,Am) 0.0000 0.0002 0.0002 Release Timing 0.00 hr 0.00 hr
CA06449 Rev.000 Page 26 (6H.03) For the control room filter shine calculations, the isotopic activities in Ci released to the containment atmosphere at the beginning of the accident are listed in the fourth column of the spreadsheet (MST.XLS(MSF))
displayed in Attachment S and are the product of the activity per unit power (Column 2), the release fraction (Column 3), and the core power of 2754 MWt (6A.01).
These values are input into Microshield to calculate control room filter shine doses from aerosols entrained on the control room filters. Note that only 95% of the iodines are in aerosol form; however, for conservatism 100%
of all species except noble gases will be assumed to be particulate in this work. Also note that Microshield will allow parent decay and daughter buildup, so that subsequent isotopic quantities as a function of decay time are automatically calculated by Microshield.
The iodine values are input into Microshield to calculate control room filter shine doses from elemental and organic iodines entrained on the control room filters.
Note that Microshield will allow parent decay and daughter buildup, so that subsequent isotopic quantities as a function of decay time are automatically calculated by Microshield.
(6H.04) The geometry required for Microshield execution is the following:
The filter housing assembly for the post-loci control room filters are displayed in Refs. 63-65. The filter unit is 24" in width by 33" in length by 59" in height and is assumed to be composed of carbon. The unit is located 6" above the 69' concrete floor.
The control room ceiling extends from 67' to 69' elevation and is 2' of concrete per Ref.62.
Note that Refs.63-65 describe the current 2000 cfm filter units, not the 10000 cfm filter units that will replace them. Use of a smaller unit should concentrate the radionuclides and thus maximize the dose.
(6H.05) Atmospheric dispersion coefficients from the containment to the Control Room: (Ref.19)
The failed fuel activity released into the containment atmosphere is assumed to escape into the environment through the containment wall. The main control room inleakage points include the west road inlets, the turbine building, and Access Controls 11 and 13 on the Auxiliary Building roof. Installation of automatic isolation dampers and radiation monitors at Access Controls II and 13 on the Auxiliary Building Roof are credited in this work.
I Atmospheric Dispersion Coefficients (sectM3)
I U1-WR U2-WR U1-TB U2-TB 0-2 hr 1.11 E-03 1.04E-03 1.02E-03 1.02E-03 2-8 hr 7.29E-04 5.95E-04 7.10E-04 7.98E-04 8-24hr 3.19E-04 2.29E-04 2.57E-04 3.19E-04 1-4 days 2.36E-04 1.64E-04 2.19E-04 2.56E-04 4-30 days 1.98E-04 1.14E-04 1.77E-04 2.14E-04 The atmospheric dispersion coefficients corresponding to the Unit I containment to the west road inlet on the auxiliary building will be conservatively utilized in this work.
(6H.06) The maximum allowable containment leakage rate La contained in the Containment Leakage Rate Testing Program of TS 5.5.16 will be reduced from 0.20 percent per day at containment peak pressure Pa to 0.16 percent per day at Pa. Per RG 1.183, the containment should be assumed to leak at the leak rate incorporated in the technical specifications for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and at 50% of this leak rate for the remaining duration of the accident.
(6H.07) Containment volume:
Net free volume:
1.989E+06 cf (UFSAR Tab.14.20-3, Ref.39)
(6H.08) Containment Radionuclide Removal Processes:
(a) Per RG 1.183, reduction in airborne radioactivity in the containment by containment spray systems that have been designed and maintained in accordance with SRP 6.5.2 (Ref.l 1) may be credited.
An acceptable model for the removal of aerosols is described in SRP 6.5.2 (Ref.l 1) and NUREG/CR-5966 (Ref.12),
which is incorporated into the analysis code RADTRAD (Refs.13-15).
Per SRP 6.5.2 the first-order particulate iodine spray removal coefficient may be estimated by:
o LP=1.5*(60minrhr)*h*F*(E/D)/VSR
= 3.414/hr (Ref. 1)
CA06449 Rev. 00O Page 27 o
h=fall height = 100.ft (UFSAR 6.4.2) o F=Spray pump volume flow rate = 180 cfm (UFSAR 6.4.2) o VSR=Containment volume sprayed region = 1.446E+06 cf (6B.08) o E/D = DF = Ratio of a dimensionless collection efficiency E to the average spray drop diameter D
=lOlm=3.048/fl (Ref.l I)
SRP 6.5.2 states that the particulate iodine removal rate should be reduced by a factor of 10 when a DF of 50 is reached. Per RG 1.183, the reduction in the removal rate is not required if the removal rate is based on the calculated time-dependent airborne aerosol mass.
Per RG 1.183, there is no specified maximum DF for aerosol removal by sprays.
(b) Containment iodine removal system:
Per UFSAR 14.24, the containment iodine removal system (IRS) credits two filter units, each with a capacity to handle 50% of the required air flow.. Each unit consists of activated charcoal filters preceded by HEPA filters. Per TS 5.5.11, each filter unit has a 20000+/-10% cfm flowrate with a filter efficiency of 90% for elemental and particulate species and 30% for organic species per RG 1.52 (Ref.28).
o Particulate removal coefficient = (2
- 18000 cfm) * (0.90) * (60 min/hr) / Vctmt = 0.977/hr o
Elemental removal coefficient = (2
- 18000 cfm) * (0.90) * (60 min/hr) / Vctmt = 0.977/hr o
Organic removal coefficient = (2
- 18000 cfm) * (0.30) * (60 min/hr) / Vctmt = 0.326/hr (c) Since the activity released from the core during the Gap Release and the Early In-Vessel Phase is conservatively assumed to be released at the beginning of the accident, no delay times for spray and filter activation is assumed.
(6H.09) Per RG 1.183 (Ref.08), of the radioiodine released from the RCS to the containment atmosphere in a LOCA, 95% of the iodine released should be assumed to be cesium iodide (Csl), 4.85% elemental iodine, and 0.15% organic iodine. This includes releases from the gap and fuel pellets. With the exception of elemental and organic iodine and noble gases, fission products should be assumed to be in particulate form.
CA06449 Rev.000 Page 28
- 7. TECHNICAL ASSUMPTIONS The following technical assumptions were utilized in this work:
(01) No credit is taken for ground deposition of the effluent plume or isotopic decay in transit to the site boundary.
(02) Buildup of daughter nuclides is taken into account as source term nuclides decay.
(03) Leakage of the radioactive sump liquid post-LOCA is not considered a release pathway in this work. SRP 15.6.5 Appendix B states that "The leakage for calculating the radiological consequences should be the maximum operational leakage and should be taken as two times the sum of the simultaneous leakage from all components in the recirculation systems above which the TS would require declaring such systems to be out of service." TMI Action Item III.D.l.l.l required implementation of a leak reduction program to reduce leakage from systems outside containment which could contain highly radioactive fluids by January 1, 1980. Standard TS Section 6.5.3 System Integrity indicates that the program details can be stored in maintenance procedures. Maintenance Procedure STP-M-573-1 states "Any leakage through the pressure boundary (e.g., welds, pipe wall, valve body, pump case) is unacceptable and shall result in the test being out of specification." Thus the accident analyses do not include any post-accident leakage. This response to TMI Action Item IIID.I.I.1 was submitted to the NRC and approved on April 7, 1980. Currently, TRM 15.4.3 requires structural integrity of ASME class I components. Deviations require restoration or isolation of the affected component.
(04) Fuel that is damaged during a LOCA will release iodine in several chemical forms to the reactor coolant and to the containment atmosphere.
A portion of the iodine in the containment atmosphere is washed to the sump by containment sprays. The emergency core cooling water is borated for reactivity control. This borated water causes the sump solution to be acidic. In an acidic solution, the dissolved iodine will be converted into a volatile form and evolve out of solution, increasing the airborne iodine levels in containment and increasing the consequences from the accident due to containment atmosphere leakage. Adjusting the pH of the recirculation solution to levels 2 7.0 prevents a significant fraction of the dissolved iodine from converting to a volatile form, thus decreasing the level of airborne iodine in Containment and reducing the radiological consequences from containment atmosphere leakage post-LOCA. Trisodium phosphate dodecahydrate (TSP) is placed in baskets on the floor of the containment building to ensure that iodine, which may be dissolved in the recirculated reactor cooling water following a LOCA, remains in solution. Refs.79-80 calculate the mass of TSP required to neutralize the containment sump pH following a LOCA, assuming a boron level of 3105.5 ppm. This mass of TSP is converted into a TSP volume of 289.3 fi3, which is captured in TS 3.5.5. Note that the dodecahydrate form of TSP is used because of the high humidity in containment during normal operation. Since the TSP is hydrated, it is less likely to absorb large amounts of water from the humid atmosphere and will undergo less physical and chemical change than the anhydrous form of TSP. Refs.79-80 only consider boron as a source of acidity in the post-LOCA environment.
NUREG/CR-5950 (Ref.82) identified the following additional sources of acid in containment post-LOCA:
o Nitric acid generated by irradiation of air and water in containment o
Hydrochloric acid generated by the breakdown of certain cable jacketing when it is exposed to high temperatures and radiation o
Hydriodic acid generated by a reaction of iodine in water o
Carbonic acid generated by water absorbing CO2 fromthe air or from limestone concrete The issue is of negligible significance at Calvert Cliffs. Hydriodic and carbonic acids, can be discounted entirely due to ambient conditions in containment. The impact on containment TSP quantities by the other two acid sources described in the NUREG )hydrochloric and nitric acids) was calculated in Ref.81 and was determined to be minor.
Ref.81 considered the additional acidity caused by hydrochloric acid and nitric acid, which are produced by the degradation of electric cable insulation and sump water exposure to high levels of radioactivity, respectively. That work calculated that 166. Ibm or 3.08 ft3 of additional TSP is required to neutralize the hydrochloric and nitric acids produced by the degradation of electric cable insulation and sump water exposure to high levels of radioactivity.
This 1% increase in TSP was deemed insignificant and have a negligible effect on pH (Ref.83).
CA06449 Rev. 000 Page 29
- 8. REFERENCES (01) "Power Levels of Nuclear Power Plants", Regulatory Guide 1.49 Rev.l, 12173.
(02) CCNPP Core Operating Limits Report for Unit 1 Cycle 17 Rev.l (03) CCNPP Core Operating Limits Report for Unit 2 Cycle 16 Rev.0 (04) "Primary and Secondary Isotopic Calculations", CA06422 (05) "Control Room Habitability Source Term Calculations", CA06358.
(06) "Chart of the Nuclides - Nuclides and Isotopes", GE Nuclear Energy, Fifleenth Edition.
(07) "Gas Gap Isotopic Fraction Calculations", CA06421.
(08) "Alternate Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors",
Regulatory Guide 1.183 (09) "Calculation of Delay Time for the Containment Spray", BGE Calculation 000-TH-9302 Rev. 1, 717/94.
(10) "Resolution of AlT Milestones Concerning MHA Analysis", NEU-94-102, 3/31/94.
(11) "Containment Spray as a Fission Product Cleanup System", SRP 6.5.2 Rev.2, 12/88.
(12) D.A.Powers and S.B.Burson, "A Simplified Model of Aerosol Removal by Containment Sprays," NUREG/CR-5966, USNRC, June, 1993.
(13) "RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation",
NUREG/CR-6604, SAND98-0272 (14) "RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation",
NUREG/CR-6604, SAND98-0272/1, Supplement 1.
(15) "RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation",
NUREG/CR-6604, Supplement 2 (16) "RADTRAD 3.03 Installation and Verification on PCB386", CA06210 (17) "RADTRAD 3.03 Validation", CA06207 (18) "Calculation of Distance Factors for Power and Test Reactor Sites", TID-14844, 3/23/62.
(19) CA06012: CRHVAC Atmospheric Dispersion Coefficient Calculations (20) Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors," 1989 (21) Federal Guidance Report (FGR) 12, "External Exposure to Radionuclides in Air, Water, and Soil," 1993, (22) "Fuel Performance Analysis", Westinghouse Calculation CN-WFE-02-45, Rev.0
CA06449 Rev.000 Page 30 (23) "Control Room HVAC Inleakage Test", ETP-97-064R Rev.0, 11/11/1997 (First Run)
(24) "Control Room HVAC Inleakage Test", ETP-97-064R Rev.0, 11/11/1997 (Third Run)
(25) "Control Room HVAC Inleakage Test", ETP-97-064R Rev.0, 11/11/1997 (Fourth Run)
(26) "Control Room HVAC Inleakage Test", ETP-97-064R Rev.0, 1/18/2000.
(27) "Perfluorocarbon Tracer Gas Testing", ETP-01-035R Rev.0, 5/1/2002 (28) ) Regulatory Guide 1.52 Rev.2: "Design, Testing, and Maintenance Criteria for Post Accident ESF Atmosphere Cleanup System Air Filtration and Absorption Units of LWRs" (29) "Control Room Recirculation Filter Initiation Time Delay", NEU-95-026 (30) NRC Generic Letter 99-02: Laboratory Testing of Nuclear-Grade Activated Charcoal (31) ASME Steam Tables, 5th Edition, United Engineering Center, N.Y., N.Y.
(32) "Containment Vent System", BGE to NRC, 8/9/85.
(33) STP 0-56A-1 ESFAS Equipment Response Time Rev.1 l (34) CA02620, "Control Room and Offsite Dose from the RWT Pathway @ 730 cfm Inleakage" (35) CA04903, "Evaluation of Minimum Time to RAS" (36) "Potential Radioactive Leakage to Tank Vented to Atmosphere", NRC Information Notice 91-56.
(37) STP-M28-1/2: Safety Injection Valve Leak Test (38) Crane Technical Paper No. 410, Flow of Fluids through Valves, Fittings, and Pipes (39) Bechtel letter from A.J.Arnold to C.H.Poindexter, 4/4/75, CDCC#63854.
(40) "Offsite and Control Room Doses Following a LOCA", Bechtel Calculation M-89-33 Rev.3, 7/9/91.
(41) D.A.Powers, et al, "A Simplified Model of Aerosol Removal by Natural Processes in Reactor Containments,"
NUREG/CR-6189, USNRC, July 1996.
(42) Letter NRC to BGE, 8/9/1985, "Containment Vent System" (43) Regulatory Guide 1.194, "Atmospheric Relative Concentrations for Control Room Radiological Hlabitability Assessments at Nuclear Power Plants" (44) BGE Drawing 61740SH0001 Rev.20, "Containment Liner Plan, Elevations and Penetrations" (45) BGE Drawing 62144SH0001 Rev.2, "Post Accident Radiation Doses, Auxiliary Building Plan at El 5'"
(46) BGE Drawing 62145SH0001 Rev.2, "Post Accident Radiation Doses, Auxiliary Building Plan at El 27'"
(47) BGE Drawing 62146SH0001 Rev.2, "Post Accident Radiation Doses, Auxiliary Building Plan at El 45"'
CA06449 Rev.000 Page 31 (48) Calculation M-90-172, "Internal Plant Flooding for the WVest Piping Penetration Rooms" (49) "LLRT Results for the Equipment Hatch and Emergency Air Lock", Telephone and Conference Memorandum G.E.Gryczkowski to D.Collins, 5/7/96 (Attachment A)
(50) "Unit I Reactor Containment Building Integrated Leakage Rate Test Report", 4/24/78 (Attachment B)
(51) "Unit I Reactor Containment Building Integrated Leakage Rate Test Report", 6/22/82 (Attachment C)
(52) "Unit I Primary Reactor Containment Integrated Leakage Rate Test Report", 5/85 (Attachment D)
(53) "Unit I Primary Reactor Containment Integrated Leakage Rate Test Report", 5/88 (Attachment E)
(54) "Unit I Reactor Containment Building Integrated Leakage Rate Test Report", 7/92 (Attachment F)
(55) "Unit 2 Primary Reactor Containment Integrated Leakage Rate Test Report", 11/16/79 (Attachment G)
(56) "Unit 2 Reactor Containment Building Integrated Leakage Rate Test Report", 12/22/82 (Attachment II)
(57) "Unit 2 Primary Reactor Containment Integrated Leakage Rate Test Report", 11/85 (Attachment I)
(58) "Unit 2 Primary Reactor Containment Integrated Leakage Rate Test Report", 1/91 (Attachment J)
(59) BGE Drawing 60204SH0001 Rev.35, Equipment Location Containment & Auxiliary Building Unit I at El 45' (60) BGE Drawing 62046SH0001 Rev.5, Auxiliary Building Control Room Reflected Ceiling Plan at EI.45' (61) BGE Drawing 62042SH0001 Rev.15, Architectural Partial Floor Plan Control Room El.45' (62) Bechtel Calculation M-93-2: Maximum Post-LOCA Doses in Auxiliary Building Rooms (63) BGE Drawing 12321SH0007 Rev.6: Filter House Assembly Control Room Post Loc.1 Fresh Air (Filters No. 11 and 12)
(64) BGE Drawing 12396A-454: Control Room Plenums for Post-LOCI Filters (65) BGE Drawing 12396A-455: Control Room Plenums for Post-LOCI Filters (66) "Control Room Thyroid Doses Post-LOCA", NEU-93-085, 3/25/93.
(67) "Control Room Habitability Interim Analysis for Thyroid Dose", Correspondence NRC to BGE, 6/22/95.
(68) "SCBA Utilization Post-MHA with 3500 cfm Control Room Inleakage", CA04985.
(69) "RWT Release Pathway, post-LOCA", 000-DA-9201 Rev. 1, 10/26/92.
(70) "Offsite and Control Room Doses from Leakage to the RWr', NC-94-032 Rev.0, 1/18/95.
(71) "Control Room and Offsite Doses from the RWT Paths ay Post-MHA @ 2000 cfm Inleakage", CA03781 (72) "Control Room and Offsite Doses from the RWT Pathway Post-MHA @ 3000 cfm Inleakage", CA04160 (73) "Calvert Cliffs Reload Analysis Recorded Calculations", ABB/CE B-94-116, 6/13/94.
CA06449 Rev. 000 Page 32 (74) "Change Stroke Length of IMOV6900 and IMOV6901 to 3 Inches", TMOD-1-98-0007 (75) "Miscellaneous Containment Isolation Valves Quarterly Test", STP-0-65D-1, Rev.3, 5/6199.
(76) Microshield Version 5 User's Manual, Grove Engineering, October 1996.
(77) CA06445: Microshield 5.05 - Computer Code Installation and Verification (78) CA06446: Microshield 5.05 - Computer Code Validation (79) "Mass of TSP Required to Ensure a Minimum Sump pH of 7.0 in the Event of a LOCA", BGE Calculation M-93-33, Rev.1, 4/16193.
(80) "Increasing the Volume of TSP Baskets in Containment", BGE Calculation C-80-11, Rev.4, 9/29194.
(81) "Additional TSP Required to Compensate for Production of Nitric Acid and Hydrochloric Acid", CA04602 (82) "Iodine Evolution and pH Control", NUREG/CR-5950 (83) Telecon J.H.Wood (BGE) and S.Barshay (ABB), 12/2/98.
CA06449 Rev.OOO Page 33
- 9. METHODS OF ANALYSIS (9.A) RADTRAD Containment Pathway Computations Per RG 1.194 (Ref.43), the total release from containment atmosphere may be apportioned between the exposed and enclosed building surfaces. A large fraction of the released airborne activity post-MHA is assumed to leak out of the containment through the containment walls. This was modeled by utilizing the RADTRAD computer code.
The isotopic activities released from the failed fuel per unit power were generated by the isotope generation and depletion computer code SAS2H/ORIGEN-S and multiplied by the relevant power level and release fractions. The core inventory release fractions by radionuclide groups for the gap release and early in-vessel damage phases were extracted from RG 1.183 Table 2.
The maximum allowable containment leakage rate La contained in the Containment Leakage Rate Testing Program of TS 5.5.16 will be reduced from 0.20 percent per day at containment peak pressure Pa to 0.16 percent per day at Pa. Per RG 1.183, the containment should be assumed to leak at the leak rate incorporated in the technical specifications for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and at 50% of this leak rate for the remaining duration of the accident.
Per Regulatory Guide 1.194 (Ref.43), the total release from containment may be apportioned between the exposed and enclosed building surfaces. In this work a conservative bypass fraction from the containment to the penetration rooms of 28% was assumed. The containment atmosphere is cleansed by the iodine removal system, which filters particulates and elemental and organic iodine, by spray, which removes particulates and elemental iodine, and by natural deposition, which removes particulates.
The activity released to the environment is transported to the site boundary and to the control room via appropriate atmospheric dispersion coefficients. The control room inleakage modeled by RADTRAD is a constant 3500 cfm in this work. Control room filtration is credited based on a modification to increase recirculation flow to a nominal 10000 cfm.
A charcoal filter efficiency of 90% is credited for elemental and organic iodine, while a HEPA efficiency of 99% is credited for particulate iodine. A 20 minute time delay consistent with a manual start of the CREVS is assumed. The control room and site boundary doses are calculated based on RG 1.183 breathing rates and occupancy factors and on FGR 11 and 12 dose conversion factors.
(9.13) RADTRAD Ventilation Stack Pathway Computations Per RG 1.194 (Ref.43), the total release from containment may be apportioned between the exposed and enclosed building surfaces. Per UFSAR 6.6.2, experience has shown that containment leakage is more likely at penetrations rather than through liner plates or weld joints. Penetration rooms are built adjacent to the outside surface of each containment and enclose the areas around the majority of the penetrations. Thus, a fraction of the containment leakage will leak into the auxiliary building penetration rooms, be processed by the penetration room emergency ventilation system, and be expelled to the atmosphere through the ventilation stacks. This was modeled by utilizing the RADTRAD computer code.
The isotopic activities released from the failed fuel per unit power were generated by the isotope generation and depletion computer code SAS2H/ORIGEN-S and multiplied by the relevant power level and release fractions. The core inventory release fractions by radionuclide groups for the gap release and early in-vessel damage phases were extracted from RG 1.183 Table 2.
The maximum allowable containment leakage rate La contained in the Containment Leakage Rate Testing Program of TS 5.5.16 will be reduced from 0.20 percent per day at containment peak pressure Pa to 0.16 percent per day at Pa. Per RG 1.183, the containment should be assumed to leak at the leak rate incorporated in the technical specifications for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and at 50% of this leak rate for the remaining duration of the accident.
Per Regulatory Guide 1.194 (Ref.43), the total release from containment may be apportioned between the exposed and enclosed building surfaces. In this work a conservative bypass fraction from the containment to the penetration rooms of 28% was assumed. The containment atmosphere is cleansed by the iodine removal system, which filters particulates and elemental and organic iodine, by spray, which removes particulates and elemental iodine, and by natural deposition, which removes particulates. Per UFSAR 6.6.1, the Containment Penetration Room Emergency Ventilation System (PREVS) is designed to collect and process containment penetration leakage, so as to reduce to a minimum the environmental radioactivity levels from post-
CA06449 Rev.OOO Page 34 accident containment leaks. To minimize the release of radioactive material to the environment, penetration room ventilation is continuously routed through a prefilter, a high efficiency particulate air (HEPA) filter, and an activated charcoal filter, positioned in series. The PREVS filters all three species of radionuclide effluent.
The activity released to the environment is transported to the site boundary and to the control room via appropriate atmospheric dispersion coefficients. The control room inleakage modeled by RADTRAD is a constant 3500 cfm in this work. Control room filtration is credited based on a modification to increase recirculation flow to a nominal 10000 cfnt A charcoal filter efficiency of 90% is credited for elemental and organic iodine, while a HEPA efficiency of 99% is credited for particulate iodine. A 20 minute time delay consistent with a manual start of the CREVS is assumed. The control room and site boundary doses are calculated based on RG 1.183 breathing rates and occupancy factors and on FGR 11 and 12 dose conversion factors.
(9.C) RADTRAD RWVT Pathway Computations Per RG 1.183 (Ref.8), ESF systems that recirculate sump water outside of the primary containment are assumed to leak during their intended operation. This release source may include leakage through valves isolating interfacing systems. There is a potential for an unmonitored release pathway resulting from the post-LOCA leakage of isolation valves in the Safety Injection or Containment Spray system recirculation lines to the Refueling Water Tank (RWT),
which is vented directly to the atmosphere (Ref.36). During the recirculation phase, sump water is recirculated through the ECCS pumps and could leak through various valves and reach the RWT. The two pathways include the two valves in series in the minimum flow recirculation line header (MOV659/660) and the valve from the containment spray pumps (SI459). This was modeled by utilizing the RADTRAD computer code.
The isotopic activities released from the failed fuel per unit power were generated by the isotope generation and depletion computer code SAS2H/ORIGEN-S and multiplied by the relevant power level and release fractions. The core inventory release fractions by radionuclide groups for the gap release and early in-vessel damage phases were extracted from RG 1.183 Table 2; however, per RG 1.183 Appendix A Section 5.3, with the exception of iodine, all radioactive materials in the recirculating liquid should be assumed to be retained in the liquid phase. The minimum time to RAS of 32 minutes determines the beginning of the sump recirculation phase. During the recirculation phase, sump water is recirculated through the ECCS pumps and could leak through various valves and reach the RWT.
This leak rate is doubled per the requirements of RG 1.183. 10% of the fluid leaking into the RWT is assumed to flash and release its iodine content into the RWT atmosphere. Per RG 1.183 (Ref.8), reduction in release activity by dilution or holdup within buildings or by ESF ventilation filtration systems, may be credited where applicable. In order to determine the amount of RWT release to the atmosphere, the breathing of the RWT through the vent due to diurnal temperature variations was calculated in Ref.34. The breathing was determined by performing a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> transient thermal analysis of the RWT using the computer code TSAP and assuming RWT atmospheric temperature characteristics based on the maximum solar load during summer solstice and a minimum ambient nighttime temperature. This methodology results in an average 4.2 cfm leakrate from the RWT to the environment.
The activity released to the environment is transported to the site boundary and to the control room via appropriate atmospheric dispersion coefficients. The control room inleakage modeled by RADTRAD is a constant 3500 cfm in this *vork. Control room filtration is credited based on a modification to increase recirculation flow to a nominal 10000 cfm.
A charcoal filter efficiency of 90% is credited for elemental and organic iodine, while a HEPA efficiency of 99% is credited for particulate iodine. A 20 minute time delay consistent with a manual start of the CREVS is assumed. The control room and site boundary doses are calculated based on RG 1.183 breathing rates and occupancy factors and on FGR 11 and 12 dose conversion factors.
(9.D) RADTRAD Hydrogen Purge Line Pathway Computations Per RG 1.183, if the primary containment is routinely purged during power operations, releases via the purge system prior to containment isolation should be analyzed and the resulting doses summed with the postulated doses from other release paths. Per Ref.42, the containment vent system is used for an unlimited amount of pressure and containment radioactivity control purposes; however, the vent isolation valves may also be opened for surveillance testing. The 4-inch vent line isolates on a SIAS and CRS. The purge release evaluation should assume that 100% of the radionuclide inventory in the reactor coolant system liquid is released to the containment atmosphere at the initiation of the LOCA. This inventory should be based on the TS RCS equilibrium activity. The purge system is
CA06449 Rev. 000 Page 35 isolated before the onset of the gap release phase, thus release fractions associated with gap release and early in-vessel phases need not be considered. Per RG 1.183, 100% of the TS primary iodine and noble gas activities are assumed to be released instantaneously and homogeneously throughout the containment atmosphere at the initiation of the accident. The flow from the containment through the 4" hydrogen purge line and out the ventilation stack was calculated assuming peak containment pressure for the full 30 seconds that the line is open and assuming relevant line parameters. Per UFSAR 6.6.1, the Containment Penetration Room Emergency Ventilation System (PREVS) is designed to collect and process containment penetration leakage, so as to reduce to a minimum the environmental radioactivity levels from post-accident containment leaks. To minimize the release of radioactive material to the environment, penetration room ventilation is continuously routed through a prefilter, a high efficiency particulate air (HEPA) filter, and an activated charcoal filter, positioned in series.
The PREVS filters all three species of radionuclide effluent.
The activity released to the environment is transported to the site boundary and to the control room via appropriate atmospheric dispersion coefficients. The control room inleakage modeled by RADTRAD is a constant 3500 cfm in this work. Control room filtration is credited based on a modification to increase recirculation flow to a nominal 10000 cfm.
A charcoal filter efficiency of 90% is credited for elemental and organic iodine, wvhile a HEPA efficiency of 99% is credited for particulate iodine. A 20 minute time delay consistent with a manual start of the CREVS is assumed. The control room and site boundary doses are calculated based on RG 1.183 breathing rates and occupancy factors and on FGR 11 and 12 dose conversion factors.
(9.E) MICROSHIELD Containment Shine Computations Per RG 1.183, the analysis should consider radiation shine from radioactive material in the containment.
The isotopic activities released from the failed fuel per unit power were generated by the isotope generation and depletion computer code SAS2H/ORIGEN-S and multiplied by the relevant power level and release fractions. The core inventory release fractions by radionuclide groups for the gap release and early in-vessel damage phases were extracted from RG 1.183 Table 2. For the containment shine pathway, all 63 isotopic activities in Ci are released to the containment atmosphere at the beginning of the accident. These values are input into Microshield to calculate containment shine doses in the control room.
For the containment shine analysis, no removal of airborne radioactivity is assumed except for decay. Note that Microshield will allow parent decay and daughter buildup, so that subsequent isotopic quantities as a function of decay time are automatically calculated by Microshield.
(9.1;) MICROSHIELD Plume Shine Computations Per RG 1.183, the analysis should consider radiation shine from the external radioactive plume released from containment.
The isotopic activities released from the failed fuel per unit power were generated by the isotope generation and depletion computer code SAS2H/ORIGEN-S and multiplied by the relevant power level, release fractions, and leakage fraction. The core inventory release fractions by radionuclide groups for the gap release and early in-vessel damage phases were extracted from RG 1.183 Table 2. For the containment shine pathway, all 63 isotopic activities in Ci are released to the containment atmosphere at the beginning of the accident.
The maximum allowable containment leakage rate La contained in the Containment Leakage Rate Testing Program of TS 5.5.16 will be reduced from 0.20 percent per day at containment peak pressure Pa to 0.16 percent per day at Pa. Per RG 1.183, the containment should be assumed to leak at the leak rate incorporated in the technical specifications for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and at 50% of this leak rate for the remaining duration of the accident. The leakage fraction is the integrated leakage over thirty days divided by the initial inventory. The resulting isotopic values are input into Microshield to calculate containment shine doses in the control room.
For the plume shine analysis, no removal of airborne radioactivity is assumed except for decay. Note that Microshield will allow parent decay and daughter buildup, so that subsequent isotopic quantities as a function of decay time are automatically calculated by Microshield.
The Microshield results assume that all of the released activity is released from containment at the beginning of the accident and sits over the control room for 30 days. To correct for release timing and dispersion via wind, a dilution factor is calculated which conservatively assumes that all containment release passes directly over the control room at a wind speed that is one-tenth the wind speed integrated over 8 years.
CA06449 Rev.000 Page 36 (9.G) MICROSHIELD Control Room Filter Shine Computations Per RG 1.183, the analysis should consider radiation shine from the radioactive material buildup on recirculation filters.
The isotopic activities released from the failed fuel per unit power wvere generated by the isotope generation and depletion computer code SAS2H/ORIGEN-S and multiplied by the relevant power level and release fractions. The core inventory release fractions by radionuclide groups for the gap release and early in-vessel damage phases were extracted from RG 1.183 Table 2. Note that the control room filtration system filters aerosols and elemental and organic iodines. It does not filter the noble gas radionuclides, so they are excluded from this analysis: their release fractions are set to zero. The activity released from the core during the Gap Release and the Early In-Vessel Phase is conservatively assumed to be released at the beginning of the accident. Per RG 1.183 (Ref.08), of the radioiodine released from the RCS to the containment atmosphere in a LOCA, 95% of the iodine released should be assumed to be cesium iodide (CsI), 4.85% elemental iodine, and 0.15% organic iodine. This includes releases from the gap and fuel pellets. With the exception of elemental and organic iodine and noble gases, fission products should be assumed to be in particulate form.
The maximum allowable containment leakage rate La contained in the Containment Leakage Rate Testing Program of TS 5.5.16 will be reduced from 0.20 percent per day at containment peak pressure Pa to 0.16 percent per day at Pa. Per RG 1.183, the containment should be assumed to leak at the leak rate incorporated in the technical specifications for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and at 50% of this leak rate for the remaining duration of the accident. For the control room filter shine calculations, the containment atmosphere is cleansed by the iodine removal system, wvhich filters particulates and elemental and organic iodine and by spray, which removes particulates. The activity released to the environment is transported to the control room via appropriate atmospheric dispersion coefficients. The control room inleakage is a constant 3500 cfm in this work. Control room filtration is credited based on a modification to increase recirculation flow to a nominal 10000 cfm. A charcoal filter efficiency of 100% is credited for elemental, organic, and particulate iodine.
The resulting isotopic values from Attachment S are input into Microshield to calculate control room filter shine dose rates in the control room from particulates (Attachment Y), while the iodine isotopic values are input into Microshield to calculate control room filter shine dose rates in the control room from elemental and organic iodine (Attachment Z). Note that this methodology deposits the entire relevant core radionuclide inventory on the control room filter and then adjusts the resultant dose rates to account for decay, containment removal mechanisms, and transport to the control room filters. The radionuclide decay process is simulated in Microshield and is manifested in the time-dependent Microshield dose rates listed in column H of Attachments T, U, and V. The algorithms for converting those dose rates into integrated doses are as follows and constitute the basis of the spreadsheets in Attachments T, U, and V.
The containment radionuclide removal fraction is defined as fl and is calculated in column F of Attachments T, U, and V.
a The containment isotopic inventories "Nc" as a function of time "t" can be derived from the following rate equation. Note that the decay term is handled later by the Microshield program.
dNc/dt = -4c
- Nc Nc = fs
- Nco
- exp(-Xc
- t) fl = Nc/Nco = fs
- exp(-Xc
- t) (Column F in Attachments T-V)
Nco = Containment radionuclide inventory in Ci fs = Species fraction (I for particulate, 0.0485 for elemental, 0.00 15 for organic)
Xc = Containment cleanup rate (4.39 1/hr for particulate, 0.977 for elemental, 0.326 for organic) o The average containment isotopic inventories between times tl and t2 can be derived as follows:
<Nc> = Nc dt / At = (fs
- Nco / At)
- I exp(-Xc
- t) dt
<Nc> = (fs
- Nco / At / Xc)*( exp(-Xc
- tl)- exp(-Xc
- t2))
The control room inleakage coefficient a is defined as follows:
o c= (X/Q)
- Fcr
- La * (4.719474E-4 m3/sec/cfm) / (24 hr/day) (Column E in Attachments T-V) o (X/Q) = Atmospheric dispersion coefficients in sec/m3 (Column B in Attachments T-V)
Fcr = Control room inleakage in cfm (Column C in Attachments T-V)
La = Containment leak rate in fraction/day (Column D in Attachments T-V)
CA06449 Rev.000 Page 37 The fraction of containment radionuclide that are released from containment, enter the control room, and are depositrd on the filter is defined as f2 and is calculated in column G of Attachments T, U, and V.
o The equilibrium control room isotopic inventories can be derived from the following rate equation:
dNcr/dt = cNc - (Xi + X)
- Ncr Ncr = a/
(Xi + A)i * <Nc>
o The filter isotopic inventories can be derived from the following rate equation:
dNfIdt = Xf
- Ncr Nf = E (Xf
- a/ (Xi + f) * <Nc>
- At)
Nf= E (Xf
- ct/ (Xi + Xf) * (fs
- Nco / Xc)*( exp(-Xc
- tl)- exp(-Xc
- t2)))
f2 = Nf/Nco = E (XPfcr/ (Xi + Xf) * (fs/I,)*( exp(-)c*tl)- exp(-Mc*t2))) (Col G in Atts T-V)
The integrated dose in Rem and listed in Column I of Attachments T-V can thus be calculated as o
D=(DR*Nf/Nco*0.001 *At) o DR is the Microshield generated dose rate at time t in mR/hr. Note that the radionuclide decay is embedded in this variable.
CA06449 Rev.OOO Page 38
- 10. CALCULATIONS The following RADTRAD computations were performed in this calculational package for the MHA:
RADTRAD Cases Pathway Containment Ventilation Stack Purge Line RWT Case Input Files mhactmt.psf mhavs.psf mhahp.psf mharwt.psf Dose Conversion Factor File fgr63.inp fgr63.inp fgrl4.inp fgr63.inp Release Fraction/Timing File mhactmt.rtfl mhactmt.rft mhahp.rft mharwt.rft Nuclear Inventory File crcb63.nif crcb63.nif pril4.nif crcb63.nif Case Output Files mhactmt.oO mhavs.oO mhahp.oo mharwt.oO The following MICROSHIELD computations were performed in this calculational package shine cases:
for the containment Microshield Containment Shine Files Decay Time (hrs)
Input File Output File 0
MHAOOO.MS5 MHAOOO.pdf 1
MHA001.MS5 MHA001.pdf 2
MHAO02.MS5 MHAO02.pdf 3
MHA003.MS5 MHA003.pdf 4
MHAO04.MS5 MHAO04.pdf 5
MHAO05.MS5 MHAO05.pdf 6
MHAO06.MS5 MHAO06.pdf 7
MHAO07.MS5 MHAO07.pdf 8
MHA008.MS5 MHA008.pdf 9
MHAOO9.MS5 MHAOO9.pdf 10 MHA010.MS5 MHAO10.pdf 11 MHA011.MS5 MHA011.pdf 12 MHA012.MS5 MHA012.pdf 24 MHAO24.MS5 MHAO24.pdf 48 MHA048.MS5 MHA048.pdf 240 MHA240.MS5 MHA240.pdf 480 MHA480.MS5 MHA480.pdf 720 MHA720.MS5 MHA720.pdf The following MICROSHIELD cases:
computations were performed in this calculational package for the plume shine Microshield Plume Shine Files Decay Time (hrs)
Input File Output File 0
MHCOOO.MS5 MHCOOO.pdf 1
MHC001.MS5 MHC001.pdf 2
MHCO02.MS5 l
MHCOO2.pdf 3
MHCOO3.MS5 MHCOO3.pdf 6
l MHC006.MS5 I
MHCOO6.pdf
CA06449 Rev.ooo Page 39 9
MHCO09.MS5 MHCOO9.pdf 12 MHCO12.MS5 MHCO12.pdf 24 MHCO24.MS5 MHCO24.pdf 48 MHC048.MS5 MHC048.pdf 240 MHC240.MS5 MHC240.pdf 480 MHC480.MS5 MHC480.pdf 720 MHC720.MS5 MHC720.pdf The following MICROSHIELD computations were performed in this calculational package for the control room filter shine cases:
Microshield Filter Shine Files Decay Time (hrs)
Input File Output File 0
MHFOOO.MS5 MHFOOO.pdf 1
MHF001.MS5 MHF001.pdf 2
MHFO02.MS5 MHFOO2.pdf 3
MHFOO3.MS5 MHFOO3.pdf 4
MHFOO4.MS5 MHFOO4.pdf 5
MHFOO5.MS5 MHF0O5.pdf 6
MHFOO6.MS5 MHFOO6.pdf 7
MHFOO7.MS5 MHF0O7.pdf 8
MHF008.MS5 MHFO08.pdf 9
MHFOO9.MS5 MHFOO9.pdf 12 MHF012.MS5 MHF012.pdf 18 MHF018.MS5 MHF018.pdf 24 MHF024.MS5 MHF024.pdf 25 MHF025.MS5 MHF025.pdf 48 MHF048.MS5 MHF048.pdf 72 MHF072.MS5 MHF072.pdf 96 MHF096.MS5 MHF096.pdf 97 MHF097.MS5 MHF097.pdf 120 MHF12O.MS5 MHF12O.pdf 240 MHF240.MS5 MHF240.pdf 480 MHF48O.MS5 MHF480.pdf 720 MHF720.MS5 MHF720.pdf The following MICROSHIELD control room filter shine cases:
computations were performed in this calculational package for the iodine only Microshield Filter Shine Files - Iodine Only Decay Time (hrs)
Input File Output File 0
MHGOOO.MS5 MHGOOO.pdf 2
MHGOO2.MS5 MHGOO2.pdf 3
MHGOO3.MS5 MHGOO3.pdf 4
MHGOO4.MS5 MHGOO4.pdf 6
MHGOO6.MS5 MHGOO6.pdf 8
MHG008.MS5 MHGOO8.pdf 9
MHGOO9.MS5 MHGOO9.pdf 12 MHGO12.MS5 MHG012.pf
CA06449 Rev.000 Page 40 18 MHGO18.MS5 MHGO18.pdf 24 MHGO24.MS5 MHGO24.pdf 25 MHGO25.MS5 MHGO25.pdf 48 MHG048.MS5 MHGO48.pdf 72 MHGO72.MS5 MHGO72.pdf 96 MHGO96.MS5 MHGO96.pdf 97 MHGO97.MS5 MHGO97.pdf 120 MHG120.MS5 MHG120.pdf 240 MHG240.MS5 MHG240.pdf 480 MHG480.MS5 MHG48O.pdf 720 MHG720.MS5 MHG720.pdf
CA06449 Rev.000 Page 41
- 11. DOCUMENTATION OF COMPUTER CODES (I1.A) RADTRAD This work employed the RADTRAD computer code, which was verified, benchmarked, and documented in Refs. 13-17 and which models the transport of halogen and noble gas isotopes from a primary containment to a secondary containment and thence to the environment and control room. The installation of RADTRAD is detailed in Ref.16 and the validation in Ref.17.
The RADTRAD computer code can calculate TEDE and thyroid doses to personnel at the site boundary, low population zone, and control room per the alternate source term methodology 10 CFR 50.67 and Regulatory Guide 1.183 or can calculate whole body and thyroid doses to personnel at the site boundary, low population zone, and control room per the standard source term methodology of TID-14844 (Ref.18) resulting from any postulated accident which releases radioactivity within the containment, spent fuel pool, or within any primary system.
RADTRAD models the transport of radioactivity from up to 63 radioisotopes from the sprayed and unsprayed regions of a primary containment or a SFP area, through the secondary containment if any, and then to the environment and to the control room. The code includes the capability to model time-dependent activity release; containment spray, filtration, and leakage; control room filtration and inleakage; primary and secondary containment purge filters; control room intake filters; atmospheric dispersion; and natural decay. Doses are calculated for individuals residing at the site boundary or low population zone and in the control room.
Some inputs for the RADTRAD computer program were generated via an EXCEL spreadsheet.
( 11B) MICROSHIELD This work employed the MICROSHIELD computer code, which was verified, benchmarked, and documented in Refs.76-78 and which is used to analyze shielding and exposure from gamma radiation.
The installation of MICROSHIELD is detailed in Ref.77 and the validation in Ref.78.
MICROSHIELD is capable of modeling various geometries including distance and orientation between source and dose point; dimension of the source region; and the dimensions, locations, and orientations of intervening shields.
MICROSHIELD has solution algoritms for 16 source geometries including points, lines, disks, spheres, cylinders, rectangular volumes, truncated cones, infinite planes, and infinite slabs with various shields. The source and shield material compositions, densities, and buildup factors can be specified. A source strength as a function of isotopic content or photon energy spectrum can also be specified.
The inputs and outputs of the MICROSIIIELD computer program were processed by EXCEL spreadsheets.
CA06449 Rev.000 Page 42
- 12. RESULTS The current work utilizes the alternate source term methodology of 10 CFR 50.67 and Regulatory Guide 1.183 to calculate offsite and control room doses for an MHA. Per RG 1.183, the TEDE analysis should include all sources of radiation that will cause exposure to control room personnel. In this work, the following pathways are analyzed:
(12.A) Containment Pathway The containment pathway results were generated via RADTRAD and are partially listed in Attachment E. The EAB, LPZ, and CR doses are 1.8988, 0.4958, and 3.9862 Rem TEDE, respectively.
(12.B) Hydrogen Purge Line (LIPL) Pathway The hydrogen purge line pathway results were generated via RADTRAD and are partially listed in Attachment L.
The EAB, LPZ, and CR doses are 6.4918E-05, 1.5283E-05, and 7.7048E-05 Rem TEDE, respectively.
(12.C) Penetration Room-Ventilation Stack (VS) Pathway The penetration room-ventilation stack pathway results were generated via RADTRAD and are partially listed in Attachment F. The EAB, LPZ, and CR doses are 0.18381, 0.048542, and 0.39677 RemTEDE, respectively.
(12.D) Refueling Water Tank (RXW'T) Pathway The RWT pathway results were generated via RADTRAD and are partially listed in Attachment H. The EAB, LPZ, and CR doses are 1.9676E-05, 1.8560E-03, and 0.32979 Rem TEDE, respectively.
(12.E) Containment Shine The control room dose rates generated by containment shine were calculated via MICROSHIELD, and the zero decay case is listed in Attachment W.
The remaining MICROSHIELD output files are contained on the accompanying CD-ROM with the naming convention as described in Section 10 of this work.
MICROSHIELD Containment Results Time(hr)
DR(mR/hr)
Dose(Rem) 0 7.112 0.0000 1
7.296 0.0072 2
4.738 0.0132 3
3.224 0.0172 4
2.312 0.0200 5
1.714 0.0220 6
1.299 0.0235 7
0.9998 0.0246 8
0.7795 0.0255 9
0.6142 0.0262 10 0.4886 0.0268 11 0.3922 0.0272 12 0.3176 0.0276 24 0.05886 0.0298 48 0.04466 0.0311 240 0.04831 0.0400 480 0.02866 0.0492 720 0.01675 0.0547
CA06449 Rev. 000 Page 43 (12.F) Plume Shine The control room dose rates generated by plume shine were calculated via MICROSHIELD, and the zero decay case is listed in Attachment X. The remaining MICROSHIELD output files are contained on the accompanying CD-ROM with the naming convention as described in Section 10 of this work.
MICROSHIELD Plume Results Time(hr)
DR(mR/hr)
Dilution Factor Dose(Rem) 0 5743.00 0.00009 0.0000 1
4047.00 0.00009 0.0004 2
2754.00 0.00009 0.0007 3
2022.00 0.00009 0.0010 6
1004.00 0.00009 0.0014 9
573.30 0.00009 0.0016 12 356.40 0.00009 0.0017 24 105.50 0.00009 0.0020 48 54.61 0.000045 0.0020 240 39.49 0.000045 0.0025 480 24.51 0.000045 0.0028 720 16.30 0.000045 0.0030 (12.G) Control Room Filter Shine The control room dose rates generated by control room filter shine were calculated via MICROSHIELD, and the zero decay cases are listed in Attachment Y for all isotopes except the noble gases and in Attachment Z for the iodines only. The remaining MICROSHIELD output files are contained on the accompanying CD-ROM with the naming convention as described in Section 10 of this work. The actual 30 day control room doses were calculated in EXCEL spreadsheets listed in Attachments T, U, and V for particulate, elemental, and organic radionuclides as 1.3241E-02, 5.9184E-04, and 3.9598E-05 Rem TEDE, respectively.
CA06449 Rev. 000 Page 44
- 13. CONCLUSIONS The current work utilizes the alternate source term methodology of 10 CFR 50.67 and Regulatory Guide 1.183 to calculate offsite and control room doses for an MHA. Per RG 1.183, the TEDE analysis should include all sources of radiation that will cause exposure to control room personnel. In this work, the following pathways are analyzed:
Containment pathway Hydrogen Purge Line (HPL) pathway Ventilation Stack (VS) pathway Refueling Water Tank (RWT) pathway Containment Shine Plume Shine Control Room Filter Shine A bounding control room inleakage value of 3500 cfm was assumed. The following modifications and TS changes are proposed to comply with regulatory requirements.
Alternate Source Term Methodology was employed.
Modification of the control room emergency ventilation system to a nominal 10000 cfm flow with a 90%
filtration efficiency for elemental and organic iodine and 99% for particulate iodine was credited.
Also credited was installation of automatic isolation dampers and radiation monitors at Access Controls 1 1 and 13 on the Auxiliary Building Roof. This modification limits activity ingress into the control room to either the West Road Inlet or the Turbine Building, thus limiting the atmospheric dispersion coefficient value.
The Technical Specification (TS 3.4.15) limit for RCS activity was reduced from 1.0 pCi/gm to 0.5 pCilgm.
The maximum allowable containment leakage rate La contained in the Containment Leakage Rate Testing Program of TS 5.5.16 was reduced from 0.20 percent per day at Pa to 0.16 percent per day at Pa.
The exclusion area boundary (EAB), low population zone (LPZ), and control room (CR) doses for the design-basis MHA are detailed in the following table.
I MHA Results l
Results EAB LPZ CR Rem Rem Rem Containment Pathway 1.8988 0.4958 3.9682 Penetration Room Pathway 0.1838 0.0485 0.3968 RWT Pathway 1.9676E-05 1.8560E-03 3.2979E-01 Hydrogen Purge Pathway 6.4918E-05 1.5283E-05 7.7048E-05 Containment Shine 0.0547 Plume Shine 0.0030 Control Room Filter Shine 0.0139 Total 2.0827 0.5462 4.7664 Regulatory Limits 25 25 5
Note that all values are below the regulatory limits.
CA06449 Rev.000 Page 45
- 14. ATTACHNIENTS ATTACHMENT A MAXIMUM HYPOTHETICAL ACCIDENT PRIMARY RELEASE ACTIVITIES 1 pCilg 1 pCii/g 0.5 pCii/g Halflife lambda Primary Primary Primary Source Source Source sec 1/sec pCi/g Ci Ci A
B C
D E
Kr-85 3.3830E+08 2.0489E-09 3.8761E+01 7.9975E+03 7.9975E+03 Kr-85m 1.6128E+04 4.2978E-05 2.0344E+00 4.1975E+02 4.1975E+02 Kr-87 4.5780E+03 1.5141E-04 1.1747E+00 2.4238E+02 2.4238E+02 Kr-88 1.0224E+04 6.7796E-05 3.6579E+00 7.5473E+02 7.5473E+02 1-131 6.9466E+05 9.9783E-07 7.7893E-01 1.6071 E+02 8.0357E+01 1-132 8.2800E+03 8.3713E-05 2.5868E-01 5.3372E+01 2.6686E+01 1-133 7.4880E+04 9.2568E-06 1.0972E+00 2.2638E+02 1.1319E+02 1-134 3.1560E+03 2.1963E-04 1.4798E-01 3.0532E+01 1.5266E+01 1-135 2.3796E+04 2.9129E-05 6.0207E-01 1.2422E+02 6.2112E+01 Xe-133 4.5317E+05 1.5296E-06 4.0021 E+02 8.2574E+04 8.2574E+04 Xe-135 3.2724E+04 2.1182E-05 9.5607E+00 1.9726E+03 1.9726E+03 Xe-133m 1.8922E+05 3.6632E-06 5.7016E+00 1.1764E+03 1.1764E+03 Xe-135m 9.1800E+02 7.5506E-04 1.2511 E+00 2.5814E+02 2.5814E+02 Xe138 8.4600E+02 8.1932E-04 6.6019E-01 1.3622E+02 1.3622E+02 A
Half-lives: Chart of the Nuclides Fifteenth Edition' B
Decay constants: Ln(2yA(i)
C Primary Source in microCi/gm: CA06422 D
Primary Source in Ci for 1.0 microCi/gm total (F*Mtot'l.e-6): CA06422 E
Primary Source in Ci for 0.5 microCi/gm total: CA06422
CA06449 Rev.000 Page 46 ATTACHMENT B NUCLEAR INVENTORY FILE CRCB63.NIF Nuclide Inventory Name:
Normalized MACCS Sample 3412 MWth PWR Core Inventory Power Level:
0.1000E+0l Nuclides:
63 Nuclide 001:
Co-58 7
0.6117120000E+07 0.5800E+02 8.0012E+02 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 002:
Co-60 7
0.1663401096E+09 0.6000E+02 9.8625E+02 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 003:
Kr-85 1
0.3382974720E+09 0.8500E+02 3.7180E+02 none O.OOOOE+00 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 004:
Kr-85m 1
0.1612800000E+05 0.8500E+02 7.9679E+03 Kr-85 0.2100E+00 none O.OOOOE+00 none O.OOOOE00 Nuclide 005:
Kr-87 1
0.4578000000E+04 0.8700E+02 1.6208E+04 Rb-87 0.1000E+01 none O.OOOOE+00
CA06449 Rev.000 Page 47 none O.OOOOE+00 Nuclide 006:
Kr-88 1
0.1022400000E+05 0.8800E+02 2.2658E+04 Rb-88 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 007:
Rb-86 3
0.1612224000E+07 0.8600E+02 5.9034E+01 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 008:
Sr-89 S
0.4363200000E+07 0.8900E+02 3.3293E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 009:
Sr-90 5
0.9189573120E+09 0.9000E+02 3.1769E+03 Y-90 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 010:
Sr-91 5
0.3420000000E+05 0.9100E+02 3.8931E+04 Y-91m 0.5800E+00 Y-91 0.4200E+00 none O.OOOOE+00 Nuclide 011:
Sr-92 5
0.9756000000E+04 0.9200E+02 4.0190E+04 Y-92 0.1000E+01 none O.OOOOE+00
CA06449 Rev.OOO Page 48 none O.OOOOE+00 Nuclide 012:
Y-90 9
0.2304000000E+06 0.9000E+02 3.4567E+03 none O.OOOOE+O0 none O.OOOOE+00 none O.OOOOE+00 Nuclide 013:
Y-91 9
0.5055264000E407 0.9100E+02 4.2527E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 014:
Y-92 9
0.1274400000E+05 0.9200E+02 4.0519E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 015:
Y-93 9
0.3636000000E+05 0.9300E+02 2.9622E+04 Zr-93 0.1000E+01 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 016:
Zr-95 9
0.5527872000E+07 0.9500E+02 5.8246E+04 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 4.9425E+04 Nb-97m 0.9500E+00 Nb-97 0.5300E-01
CA06449 Rev.000 Page 49 none O.OOOOE+00 Nuclide 018:
Nb-95 9
0.3036960000E+07 0.9SOOE+02 6.0839E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 019:
Mo-99 7
0.2376000000E+06 0.9900E+02 5.0834E+04 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 4.5424E+04 Tc-99 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 021:
Ru-103 7
0.3393792000E+07 0.1030E+03 4.8774E+04 Rh-103m 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 022:
Ru-105 7
0.1598400000E+05 0.1050E+03 3.1455E+04 Rh-105 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 023:
Ru-106 7
0.3181248000E+08 0.1060E+03 1.9695E+04 Rh-106 O.1000E+O1 none O.OOOOE+0O
CA06449 Rev.000 Page 50 none 0.OOOOE+00 Nuclide 024:
Rh-105 7
0.1272960000E+06 0.1050E+03 2.8507E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 025:
Sb-127 4
0.3326400000E+06 0.1270E+03 2.4299E+03 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 8.7888E+03 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 2.4664E+03 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 028:
Te-127m 4
0.9417600000E+07 0.1270E+03 4.6272E+02 Te-127 0.9800E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 029:
Te-129 4
0.4176000000E+04 0.1290E+03 8.4012E+03 1-129 0.1000E+01 none O.OOOOE+00
CA06449 Rev.000 Page 51 none O.OOOOE+00 Nuclide 030:
Te-129m 4
0.2903040000E+07 0.1290E+03 1.8872E+03 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 5.0686E+03 Te-131 0.2200E+00 I-131 0.7800E+00 none O.OOOOE+00 Nuclide 032:
Te-132 4
0.2815200000E+06 0.1320E+03 3.8391E+04 1-132 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 033:
I-131 2
0.6946560000E+06 0.1310E+03 2.7562E+04 Xe-131m 0.llOOE-01 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 034:
I-132 2
0.8280000000E+04 0.1320E+03 3.9464E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 035:
1-133 2
0.7488000000E+05 0.1330E+03 5.5715E+04 Xe-133m 0.2900E-01 Xe-133 0.9700E+00
CA06449 Rev. 000 Page 52 none O.OOOOE+00 Nuclide 036:
I-134 2
0.3156000000E+04 0.1340E+03 6.2858E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 037:
1-135 2
0.2379600000E+05 0.1350E+03 5.2964E+04 Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none 0.OOOOE+00 Nuclide 038:
Xe-133 1
0.4531680000E+06 0.1330E+03 5.5707E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 039:
Xe-135 1
0.3272400000E+05 0.1350E+03 1.7708E+04 Cs-135 0.1000E+01 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 040:
Cs-134 3
0.6507177120E+08 0.1340E+03 7.1917E+03 none O.OOOOE+00 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 041:
Cs-136 3
0.1131840000E+07 0.1360E+03 1.7111E+03 none O.OOOOE+00 none 0.OOOOE+00
CA06449 Rev.000 Page 53 none O.OOOOE+00 Nuclide 042:
Cs-137 3
0.9467280000E+09 0.1370E+03 4.7857E+03 Ba-137m 0.9S00E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 043:
Ba-139 6
0.4962000000E+04 0.1390E+03 5.1001E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 044:
Ba-140 6
0.1100736000E+07 0.1400E+03 5.2928E+04 La-140 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 045:
La-140 9
0.1449792000E+06 0.1400E+03 5.4255E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 046:
La-141 9
0.1414800000E+05 0.1410E+03 4.6433E+04 Ce-141 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 047:
La-142 9
0.5550000000E+04 0.1420E+03 4.4898E+04 none O.OOOOE+00 none O.OOOOE+00
CA06449 Rev.000 Page 54 none O.OOOOE+00 Nuclide 048:
Ce-141 8
0.2808086400E+07 0.1410E+03 5.1883E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 049:
Ce-143 8
0.1188000000E+06 0.1430E+03 4.4327E+04 Pr-143 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 050:
Ce-144 8
0.2456352000E+08 0.1440E+03 4.2317E+04 Pr-144m 0.1800E-01 Pr-144 0.9800E+00 none O.OOOOE+00 Nuclide 051:
Pr-143 9
0.1171584000E+07 0.1430E+03 4.6904E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 052:
Nd-147 9
0.9486720000E+06 0.1470E+03 1.9151E+04 Pm-147 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 053:
Np-239 8
0.2034720000E+06 0.2390E+03 S.5833E+05 Pu-239 0.1000E+01 none O.OOOOE+00
CA06449 Rev. OOO Page 55 none O.OOOOE+00 Nuclide 054:
Pu-238 8
0.2768863824E+10 0.2380E+03 1.7259E+02 U-234 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 055:
Pu-239 8
0.7594336440E+12 0.2390E+03 1.1469E+01 U-235 0.1000E+01 none 0.OOOOE+00 none o.OOOOE+00 Nuclide 056:
Pu-240 8
0.2062920312E+12 0.2400E+03 2.0026E+01 U-236 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 057:
Pu-241 8
0.4544294400E+09 0.2410E+03 4.9593E+03 U-237 0.2400E-04 Am-241 0.1000E+01 none O.OOOOE+00 Nuclide 058:
Am-241 9
0.1363919472E+ll 0.2410E+03 7.3183E+00 Np-237 0.1000E+01 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 059:
Cm-242 9
0.1406592000E+08 0.2420E+03 2.0078E+03 Pu-238 0.1000E+01 none 0.OOOOE+00
CA06449 Rev.000 Page 56 none O.OOOOE+00 Nuclide 060:
Cm-244 9
0.571508136E+9 0.2440E+03 3.1650E+02 Pu-240 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 061:
Xe-133m 1
1.8922000000E+05 0.1330E+03 1.7354E+03 Xe-133 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 062:
Xe-135m 1
9.1800000000E+02 0.1350E+03 1.1635E+04 Xe-135 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 063:
Xe-138 1
8.4600000000E+02 0.1380E+03 4.9330E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 End of Nuclear Inventory File
CA06449 Rev.000 Page 57 ATTACHMENT C RELEASE FRACTION AND TIMING FILE MHACTMT.RFT Release Fraction and Timing Name:
PWR, RG 1.183, Table 2 Section 3.2 Duration (h):
Design Basis Accident O.5000E+00 O.OOOlE+00 O.OOOOE+00 O.OOOOE+00 Noble Gases:
O.5000E-01 O.9500E+00 O.OOOOE+00 O.OOOOE+00 Iodine:
O.5000E-01 0.3500E+00 O.OOOOE+00 O.OOOOE+00 Cesium:
O.5000E-01 0.2500E+00 O.OOOOE+00 O.OOOOE+00 Tellurium:
O.OOOOE+00 O.5000E-01 O.OOOOE+00 O.OOOOE+00 Strontium:
O.OOOOE+00 0.2000E-01 O.OOOOE+00 O.OOOOE+00 Barium:
O.OOOOE+00 0.2000E-01 O.OOOOE+00 O.OOOOE+00 Ruthenium:
O.OOOOE+00 0.2500E-02 O.OOOOE+00 O.OOOOE+00 Cerium:
O.OOOOE+00 O.5000E-03 O.OOOOE+00 O.OOOOE+00 Lanthanum:
O.OOOOE+00 0.2000E-03 O.OOOOE+00 O.OOOOE+00 Non-Radioactive Aerosols (kg):
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 End of Release File
CA06449 Rev.OOO Page 58 ATTACHMENT D CONVERSION FACTORS FILE FGR63.INP FGRDCF 10/24/95 03:24:50 beta-test version 1.10, minor FORTRAN fixes 5/4/95 Implicit daughter halflives tm) less than 90 and less than 0.100 of parent 9 ORGANS DEFINED IN THIS FILE:
GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR)
Co-58 Co-60 Kr-85 Kr-85m Kr-87 Kr-88 Rb-86 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Ru-103 Ru-105 Ru-106 Rh-105 Sb-127 Sb-129 Te-127 Te-127m Te-129 Te-129m Te-131m Te-132 I-131 1-132 I-133 I-134 1-135 63 NUCLIDES DEFINED IN THIS FILE:
Y Y
Including:Y-91m Including:Nb-97m, Including:Nb-97 Including:Rh-103m Including:Rh-106 Including:Te-129 Including:Te-131 Including:Xe-135m
CA06449 Rev.OOO Page 59 Xe-133 Xe-135 Cs-134 Cs-136 Cs-137 Ba-139 Ba-140 La-140 La-141 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Nd-147 Np-239 Pu-238 Pu-239 Pu-240 Pu-241 Am-241 Cm-242 Cm-244 Xe-133m Xe-135m Xe-138 Including:Ba-137m Including:Pr-144m, Including:Pr-144 CLOUDSHINE GROUND GROUND GROUND INHALED INHALED INGESTION SHINE 8HR SHINE 7DAY SHINE RATE ACUTE CHRONIC Co-58 GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR)
Co-60 GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR)
Kr-85 GONADS BREAST LUNGS RED MARR BONE SUR 4.660E-14 5.300E-14 4.640E-14 4.530E-14 7.410E-14 4.770E-14 4.440E-14 4.760E-14 5.580E-14 1.230E-13 1.390E-13 1.240E-13 1.230E-13 1.780E-13 1.270E-13 1.200E-13 1.260E-13 1.450E-13 1.170E-16 1.340E-16 1.140E-16 1.090E-16 2.200E-16 2.867E-11 2.737E-11 2.617E-11 2.671E-11 3.795E-11 2.720E-11 2.585E-11 2.732E-11 3.278E-11 7.056E-ll 6.739E-11 6.537E-11 6.710E-11 8.956E-11 6.480E-11 6.508E-11 6.768E-11 7.948E-11 8.121E-14 7.891E-14 7.056E-14 6.998E-14 1.287E-13 5.828E-10 5.565E-10 5.319E-10 5.430E-10 7.716E-10 S. 530E-10 5.255E-10 5.553E-10 6.664E-10 1.480E-09 1.413E-09 1.371E-09 1.407E-09 1.879E-09 1.359E-09 1.36SE-09 1.419E-09 1.667E-09 1.704E-12 1.656E-12 1.481E-12 1.469E-12 2.702E-12 9.970E-16-1.OOOE+OO 9.520E-16-1.OOOE+OO 9.100E-16-1.OOOE+OO 9.290E-16-1.OOOE+OO 1.320E-15-1.OOOE+OO 9.460E-16-1.OOOE+OO 8.990E-16-1.OOOE+OO 9.500E-16-1.OOOE+OO 1.140E-15-1.OOOE+OO 2.450E-15-1.OOOE+OO 2.340E-15-1.OOOE+OO 2.270E-15-1.OOOE+OO 2.330E-15-1.OOOE+OO 3.11OE-15-1.OOOE+OO 2.250E-15-1.OOOE+OO 2.260E-15-1.OOOE+OO 2.350E-15-1.OOOE+OO 2.760E-15-1.OOOE+OO 2.820E-18-1.OOOE+OO 2.740E-18-1.OOOE+OO 2.450E-18-1.OOOE+OO 2.430E-18-1.OOOE+OO 4.470E-18-1.OOOE+OO 6.170E-10 9.370E-10 1.600E-08 9.230E-10 6.930E-10 8.720E-10 1.890E-09 2.940E-09 O.OOOE+OO 4.760E-09 1.840E-08 3.450E-07 1.720E-08 1.350E-08 1.620E-08 3.600E-08 5.910E-08 O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO 1.040E-09 1.790E-10 8.530E-11 2.600E-10 1.250E-10 6.310E-11 1.580E-09 8.090E-10 O.OOOE+OO 3.190E-09 1.100E-O9 8.770E-10 1.320E-09 9.390E-10 7.880E-10 4.970E-09 2.770E-09
- 0. OOOE+OO O. OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO O.OOOE+OO
CA06449 Rev.000 Page 60 THYROID REMAINDER EFFECTIVE SKIN(FGR)
Kr-85m GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR)
Kr-87 GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR)
Kr-88 GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR)
Rb-86 GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR)
Sr-89 GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR) 1.180E-16 l.090E-16 1.190E-16 1.320E-14 7.310E-15 8.410E-15 7.040E-15 6.430E-15 1.880E-14 7.330E-15 6.640E-15 7.480E-15 2.240E-14 4.OOOE-14 4.500E-14 4.040E-14 4.000E-14 6.020E-14 4.130E-14 3.910E-14 4.120E-14 1.370E-13 9.900E-14 1.110E-13 1.010E-13 1.OOOE-13 1.390E-13 1.030E-13 9.790E-14 1.020E-13 1.350E-13 4.710E-15 5.340E-15 4.710E-15 4.640E-15 7.050E-15 4.840E-15 4.520E-15 4.810E-15 4.850E-14 7.730E-17 9.080E-17 7.080E-17 6.390E-17 1.940E-16 7.600E-17 6.710E-17 7.730E-17 3.690E-14 7.459E-14 6.941E-14 7.603E-14 2.304E-ll 2.594E-12 2.527E-12 2.379E-12 2.346E-12 5.286E-12 2.395E-12 2.313E-12 2.511E-12 2.247E-ll 1.56SE-12 1.457E-12 1.596E-12 4.835E-10 3.653E-12 3.560E-12 3.351E-12 3.304E-12 7.446E-12 3.374E-12 3.257E-12 3.537E-12 3.164E-ll 4.962E-12 5.026E-12 4.74OE-12 4.802E-12 4.603E-12 4.663E-12 4.708E-12 4.769E-12 6.514E-12 6.598E-12 4.473E-12 4.531E-12 4.590E-12 4.650E-12 4.773E-12 4.835E-12 8.802E-11 8.916E-il 2.278E-11 2.655E-11 2.177E-l1 2.139E-11 2.190E-11 2.886E-ll 2.012E-ll 2.139E-il 2.202E-il 5.607E-11 2.537E-1l 2.493E-11 2.552E-ll 3.363E-11 2.345E-ll 2.493E-ll 2.567E-l1 6.534E-ll 2.590E-18-i.OOOE+CO 2.410E-18-l.OOOE+OO 2.640E-18-l.OOOE+OO 8.000E-16-1.000E+00 1.570E-16-1.OOOE+OO 1.530E-16-l.OOOE+00 1.440E-16-l.OOOE+OO 1.420E-16-1.O0OE+00 3.200E-16-1.OOOE+OO 1.450E-16-1.OOOE+0O 1.400E-16-l.OOOE+O0 1.520E-16-1.OOOE+00 1.360E-15-l.OOOE+OO 7.610E-16-l.OOOE+00 7.270E-16-1.OOOE+OO 7.060E-16-1.000E+00 7.220E-16-l.OOOE+0O 9.990E-16-l.OOOE+00 6.860E-16-1.OOOE+OO 7.040E-16-1.OOOE+00 7.320E-16-l.OOOE+0O 1.350E-14-1.OOOE+OO 1.800E-15-1.000E+OO 1.720E-1S-1.000E+00 1.690E-15-l.OOOE+00 1.730E-15-l.OOOE+00 2.280E-15-1.OOOE+OO 1.590E-15-l.000E+OO 1.690E-15-1.OOOE+0O 1.740E-15-1.OOOE+00 4.430E-15-1.OOOE+OO 9.740E-17-l.OOOE+00 9.300E-17-1.OOOE+O0 8.920E-17-1.OOOE+OO 9.150E-17-1.OOOE+00 1.270E-16-1.OOOE+OO 9.080E-17-l.OOOE+0O 8.880E-17-l.OOOE+OO 9.310E-17-1.OOOE+OO 7.720E-15-i.OOOE+OO 2.490E-18-1.OOOE+0O 2.510E-18-i.OOOE+00 1.980E-18-1.OOOE+00 1.860E-18-1.OOOE+OO 5.430E-18-1.OOOE+0O 2.110E-18-l.OOOE+OO 1.950E-18-1.OOOE+OO 2.270E-18-l.OOOE+0O 6.660E-15-l.OOOE+OO O.OOOE+O0 O.OOOE+OO O.OOOE+OO O.OOOE+OO C. OOOE+OO O.OOOE+00 C. OOOE+O0 O.OOOE+OO O.OOOE+OO O.OOOE+OO
- 0. OOOE+OO O.OOOE+OO
- 0. OOOE+0O O.OOOE+OO O.OOOE+O0 O.OOOE+0O O.OOOE+OO O.OOOE+OO
- 0. OOOE+00 O.OOOE+O0 O.OOOE+OO O.OOOE+OO O.OOOE+OO C. OOOE+O0
- 0. OOOE+00 C. OOOE+0O O.OOOE+OO O.OOOE+00 O.OOOE+0O O.OOOE+OO C. OOOE+00 1.340E-09 1.330E-09 3.300E-09 2.320E-09 4.270E-09 1.330E-09 1.380E-09 1.790E-09 O.OOOE+OO 7.950E-12 7.960E-12 8.350E-08 1.070E-10 1.590E-10 7.960E-12 3.970E-09 1.120E-08 O.OOOE+OO O.OOOE+00 O.OOOE+0O O.OOOE+OO
- 0. OOOE+OO O.OOOE+OC O.OOOE+00 O.OOOE+OO 0.OOOE+O0 O.OOOE+OO O.OOOE+0O O.OOOE+OO O.OOOE+00 O.OOOE+OO O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+OO O.OOOE+0O O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+OO 0.OOOE+OO O.OOOE+00 O.OOOE+OO O.OOOE+00 O.OOOE+OO O.OOOE+00 O.OOOE+OO O.OOOE+00 O.OOOE+OO 2.150E-09 2.140E-09 2.140E-09 3.720E-09 6.860E-09 2.140E-09 2.330E-09 2.530E-09 O.OOOE+00 8.050E-12 7.980E-12 7.970E-12 1.080E-10 1.610E-10 7.970E-12 8.250E-09 2.500E-09 O.OOOE+0O 2.788E-12 5.187E-11 2.662E-12 4.953E-11 2.553E-12 4.750E-11 2.619E-12 4.873E-li 3.635E-12 6.764E-il 2.599E-12 4.836E-li 2.542E-12 4.729E-il 2.665E-12 4.958E-11 2.210E-10 4.111E-09 7.155E-14 7.212E-14 5.689E-14 5.345E-14 1.560E-13 6.063E-14 5.603E-14 6.523E-14 1.914E-10 1.436E-12 1.447E-12 1.142E-12 1.073E-12 3.131E-12 1.217E-12 1.124E-12 1.309E-12 3.841E-09
CA06449 Rev.000 Page 61 Sr-90 GONADS 7.780E-18 9.590E-15 2.014E-13 3.330E-19-1.OOOE+00 2.690E-10 5.040E-ll BREAST 9.490E-18 1.008E-14 2.116E-13 3.500E-19-1.OOOE+00 2.690E-10 5.040E-11 LUNGS 6.440E-18 6.307E-15 1.324E-13 2.190E-19-1.OOOE+00 2.860E-06 5.040E-11 RED MARR 5.440E-18 5.558E-15 1.167E-13 1.930E-19-1.OOOE+00 3.280E-08 6.450E-09 BONE SUR 2.280E-17 2.393E-14 5.025E-13 8.310E-19-1.OOOE+00 7.090E-08 1.390E-08 THYROID 7.330E-18 7.171E-15 1.506E-13 2.490E-19-1.OOOE+00 2.690E-10 5.040E-11 REMAINDER 6.110E-18 6.422E-15 1.348E-13 2.230E-19-1.OOOE+00 5.730E-09 6.700E-09 EFFECTIVE 7.530E-18 8.179E-15 1.717E-13 2.840E-19-1.OOOE+00 3.510E-07 3.230E-09 SKIN(FGR) 9.200E-15 4.032E-12 8.465E-11 1.400E-16-1.OOOE+00 O.OOOE+0O O.OOOE+00 Sr-91 GONADS 4.819E-14 2.155E-11 5.062E-11 1.026E-15-1.OOOE+00 5.669E-11 2.S20E-10 BREAST 5.477E-14 2.059E-11 4.838E-11 9.806E-16-1.OOOE+00 1.775E-11 3.676E-11 LUNGS 4.803E-14 1.970E-11 4.626E-11 9.376E-16-1.OOOE+00 2.170E-09 1.055E-11 RED MARR 4.691E-14 2.011E-11 4.722E-11 9.570E-16-1.OOOE+00 2.275E-11 5.659E-11 BONE SUR 7.674E-14 2.852E-11 6.709E-11 1.360E-15-1.OOOE+00 1.306E-11 2.070E-11 THYROID 4.938E-14 2.035E-11 4.782E-11 9.693E-16-1.OOOE+00 9.930E-12 1.968E-12 REMAINDER 4.610E-14 1.948E-11 4.573E-11 9.268E-16-1.OOOE+00 5.802E-10 2.557E-09 EFFECTIVE 4.924E-14 2.057E-11 4.832E-11 9.793E-16-1.OOOE+00 4.547E-10 8.455E-10 SKIN(FGR) 9.938E-14 1.748E-10 3.987E-10 8.080E-15-1.OOOE+00 O.OOOE+00 O.OOOE+00 Sr-92 GONADS 6.610E-14 1.593E-11 1.830E-11 1.300E-15-1.OOOE+00 1.020E-11 8.180E-11 BREAST 7.480E-14 1.520E-11 1.745E-11 1.240E-15-1.OOOE+00 6.490E-12 1.700E-11 LUNGS 6.670E-14 1.483E-11 1.703E-11 1.210E-15-1.OOOE+00 1.050E-09 7.220E-12 RED MARR 6.620E-14 1.520E-11 1.745E-11 1.240E-15-1.OOOE+00 6.980E-12 2.290E-11 BONE SUR 9.490E-14 2.010E-11 2.308E-11 1.640E-15-1.OOOE+00 4.360E-12 8.490E-12 THYROID 6.820E-14 1.446E-11 1.661E-11 1.180E-15-1.000E+00 3.920E-12 1.300E-12 REMAINDER 6.450E-14 1.471E-11 1.689E-11 1.200E-15-1.OOOE+00 2.900E-10 1.720E-09 EFFECTIVE 6.790E-14 1.532E-11 1.759E-11 1.250E-15-1.OOOE+00 2.180E-10 5.430E-10 SKIN(FGR) 8.560E-14 2.280E-11 2.618E-11 1.860E-15-1.000E+00 O.OOOE+00 O.OOOE+00 Y-90 GONADS 1.890E-16 1.S86E-13 1.601E-12 5.750E-18-1.OOOE+00 5.170E-13 1.430E-14 BREAST 2.200E-16 1.578E-13 1.593E-12 5.720E-18-1.OOOE+00 5.170E-13 1.270E-14 LUNGS 1.770E-16 1.313E-13 1.326E-12 4.760E-18-1.OOOE+00 9.310E-09 1.260E-14 RED MARR 1.620E-16 1.261E-13 1.273E-12 4.570E-18-1.OOOE+00 1.520E-11 3.700E-13 BONE SUR 4.440E-16 3.228E-13 3.259E-12 1.170E-17-1.OOOE+00 1.510E-11 3.670E-13 THYROID 1.870E-16 1.385E-13 1.398E-12 5.020E-18-1.000E+00 5.170E-13 1.260E-14 REMAINDER 1.680E-16 1.291E-13 1.303E-12 4.680E-18-1.000E+00 3.870E-09 9.680E-09 EFFECTIVE 1.900E-16 1.468E-13 1.482E-12 5.320E-18-1.000E+00 2.280E-09 2.910E-09 SKIN(FGR) 6.240E-14 2.897E-10 2.924E-09 1.O50E-14-1.000E+00 O.OOOE+00 O.OOOE+00 Y-91 GONADS 2.560E-16 1.756E-13 3.546E-12 6.110E-18-1.000E+00 8.200E-12 3.540E-12 BREAST 2.930E-16 1.713E-13 3.459E-12 5.960E-18-1.OOOE+00 8.920E-12 5.540E-13 LUNGS 2.500E-16 1.526E-13 3.082E-12 5.310E-18-1.OOOE+00 9.870E-08 2.020E-13 RED MARR 2.410E-16 1.521E-13 3.070E-12 5.290E-18-1.OOOE+00 3.190E-10 6.590E-12 BONE SUR 4.560E-16 2.903E-13 5.862E-12 1.OlOE-17-1.000E+00 3.180E-10 6.130E-12 THYROID 2.600E-16 1.564E-13 3.157E-12 5.440E-18-1.OOOE+00 8.500E-12 1.290E-13 REMAINDER 2.390E-16 1.509E-13 3.047E-12 5.250E-18-1.OOOE+00 4.200E-09 8.570E-09 EFFECTIVE 2.600E-16 1.650E-13 3.332E-12 5.740E-18-1.OOOE+00 1.320E-08 2.570E-09 SKIN(FGR) 3.850E-14 1.989E-10 4.016E-09 6.920E-15-1.OOOE+00 O.OOOE+00 O.OOOE+00 Y-92 GONADS 1.270E-14 3.855E-12 4.872E-12 2.650E-16-1.OOOE+00 2.610E-12 1.960E-11 BREAST 1.440E-14 3.680E-12 4.652E-12 2.530E-16-1.OOOE+00 1.500E-12 3.550E-12 LUNGS 1.270E-14 3.535E-12 4.468E-12 2.430E-16-1.OOOE+00 1.240E-09 1.390E-12
CA06449 Rev.000 Page 62 RED MARR 1.250E-14 3.608E-12 4.560E-12 2.480E-16-1.OOOE+00 2.070E-12 4.910E-12 BONE SUR 1.950E-14 5.091E-12 6.435E-12 3.500E-16-1.OOOE+00 1.510E-12 1.750E-12 THYROID 1.300E-14 3.579E-12 4.523E-12 2.460E-16-1.OOOE+00 1.050E-12 1.770E-13 REMAINDER 1.220E-14 3.506E-12 4.431E-12 2.410E-16-1.OOOE+00 2.030E-10 1.700E-09 EFFECTIVE 1.300E-14 3.680E-12 4.652E-12 2.530E-16-1.OOOE+00 2.110E-10 5.150E-10 SKIN(FGR) 1.140E-13 2.022E-10 2.556E-10 1.390E-14-1.OOOE+OO O.OOOE+OO O.OOOE+OO Y-93 GONADS 4.670E-15 2.108E-12 4.989E-12 9.510E-17-1.OOOE+00 5.310E-12 2.200E-11 BREAST 5.300E-15 2.026E-12 4.794E-12 9.140E-17-1.OOOE+00 1.740E-12 3.130E-12 LUNGS 4.680E-15 1.937E-12 4.585E-12 8.740E-17-1.OOOE+00 2.520E-09 8.670E-13 RED MARM 4.580E-15 1.972E-12 4.669E-12 8.900E-17-1.OOOE+00 4.040E-12 4.930E-12 BONE SUR 7.580E-15 2.948E-12 6.977E-12 1.330E-16-1.OOOE+00 3.140E-12 1.730E-12 THYROID 4.790E-15 1.908E-12 4.516E-12 8.610E-17-1.OOOE+00 9.260E-13 1.260E-13 REMAINDER 4.510E-15 1.919E-12 4.543E-12 8.660E-17-1.OOOE+00 9.250E-10 4.090E-09 EFFECTIVE 4.800E-15 2.021E-12 4.784E-12 9.120E-17-1.OOOE+00 5.820E-10 1.230E-09 SKIN(FGR) 8.500E-14 2.726E-10 6.452E-10 1.230E-14-1.OOOE+OO O.OOOE+OO O.OOOE+OO Zr-95 GONADS 3.530E-14 2.182E-11 4.421E-10 7.590E-16-1.OOOE+00 1.880E-09 8.160E-10 BREAST 4.010E-14 2.084E-11 4.223E-10 7.250E-16-1.OOOE+OO 1.910E-09 1.050E-10 LUNGS 3.510E-14 1.989E-11 4.030E-10 6.920E-16-1.OOOE+00 2.170E-09 2.340E-1l RED MARR 3.430E-14 2.030E-11 4.112E-10 7.060E-16-1.OOOE+00 1.300E-08 2.140E-10 BONE SUR 5.620E-14 2.875E-11 5.824E-10 1.OOOE-15-1.OOOE+00 1.030E-07 4.860E-10 THYROID 3.610E-14 2.076E-11 4.205E-10 7.220E-16-1.OOOE+00 1.440E-09 8.270E-12 REMAINDER 3.360E-14 1.963E-11 3.978E-10 6.830E-16-1.OOOE+00 2.280E-09 2.530E-09 EFFECTIVE 3.600E-14 2.078E-11 4.211E-10 7.230E-16-1.OOOE+00 6.390E-09 1.020E-09 SKIN(FGR) 4.500E-14 2.561E-11 5.190E-10 8.910E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO Zr-97 GONADS 4.331E-14 2.179E-11 7.799E-11 9.253E-16-1.OOOE+00 1.840E-10 6.228E-10 BREAST 4.928E-14 2.083E-11 7.455E-11 8.846E-16-1.OOOE+00 4.706E-11 8.137E-11 LUNGS 4.322E-14 1.992E-11 7.127E-11 8.456E-16-1.OOOE+00 4.108E-09 1.770E-11 RED MARR 4.224E-14 2.034E-11 7.279E-11 8.634E-16-1.OOOE+00 6.376E-11 1.302E-10 BONE SUR 6.897E-14 2.881E-11 1.031E-10 1.224E-15-1.OOOE+00 3.504E-11 4.558E-11 THYROID 4.443E-14 2.061E-11 7.377E-11 8.755E-16-1.OOOE+00 2.315E-11 2.671E-12 REMAINDER 4.139E-14 1.966E-11 7.035E-11 8.345E-16-1.OOOE+00 2.041E-09 6.990E-09 EFFECTIVE 4.432E-14 2.078E-11 7.438E-11 8.824E-16-1.OOOE+00 1.171E-09 2.283E-09 SKIN(FGR) 9.835E-14 2.281E-10 8.148E-10 9.587E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO Nb-95 GONADS 3.660E-14 2.253E-11 4.435E-10 7.850E-16-1.OOOE+00 4.320E-10 8.050E-10 BREAST 4.160E-14 2.150E-11 4.231E-10 7.490E-16-l.OOOE+00 4.070E-10 1.070E-10 LUNGS 3.650E-14 2.055E-11 4.045E-10 7.160E-16-1.OOOE+00 8.320E-09 2.740E-11 RED MARR 3.S60E-14 2.101E-11 4.135E-10 7.320E-16-1.OOOE+00 4.420E-10 1.990E-10 BONE SUR 5.790E-14 2.957E-11 5.819E-10 1.030E-15-1.OOOE+00 5.130E-10 2.940E-10 THYROID 3.750E-14 2.144E-11 4.220E-10 7.470E-16-1.OOOE+00 3.580E-10 1.180E-11 REMAINDER 3.490E-14 2.032E-11 4.OOOE-10 7.080E-16-1.OOOE+00 1.070E-09 1.470E-09 EFFECTIVE 3.740E-14 2.147E-11 4.226E-10 7.480E-16-1.OOOE+00 1.570E-09 6.950E-10 SKIN(FGR) 4.300E-14 2.598E-11 5.112E-10 9.050E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO Mo-99 GONADS 7.130E-15 4.282E-12 4.403E-11 1.550E-16-1.OOOE+00 9.510E-11 2.180E-10 BREAST 8.130E-15 4.116E-12 4.233E-11 1.490E-16-1.OOOE+00 2.750E-11 3.430E-11 LUNGS 7.060E-15 3.867E-12 3.977E-11 1.400E-16-1.OOOE+00 4.290E-09 1.510E-11 RED MARM 6.820E-15 3.923E-12 4.034E-11 1.420E-16-1.OOOE+00 5.240E-11 8.320E-11 BONE SUR 1.240E-14 6.105E-12 6.278E-11 2.210E-16-1.OOOE+00 4.130E-11 6.320E-11 THYROID 7.270E-15 4.033E-12 4.147E-11 1.460E-16-1.OOOE+00 1.520E-11 1.030E-11 REMAINDER 6.740E-15 3.812E-12 3.920E-11 1.380E-16-1.OOOE+00 1.740E-09 4.280E-09
CA06449 Rev.OOO Page 63 EFFECTIVE 7.280E-1S 4.061E-12 4.176E-11 1.470E-16-1.OOOE+00 1.070E-09 1.360E-09 SKIN(FGR) 3.140E-14 1.039E-10 1.06SE-09 3.760E-15-1.OOOE+00 O.OOOE+OO O.OOOE+OO Tc-99m GONADS 5.750E-15 2.334E-12 3.877E-12 1.240E-16-1.OOOE+00 2.770E-12 9.750E-12 BREAST 6.650E-15 2.258E-12 3.752E-12 1.200E-16-1.OOOE+00 2.150E-12 3.570E-12 LUNGS 5.490E-15 2.127E-12 3.533E-12 1.130E-16-1.OOOE+00 2.280E-11 3.140E-12 RED MARR 4.910E-15 2.070E-12 3.439E-12 1.100E-16-1.OOOE+00 3.360E-12 6.290E-12 BONE SUR 1.630E-14 5.383E-12 8.942E-12 2.860E-16-1.OOOE+00 2.620E-12 4.060E-12 THYROID 5.750E-15 2.14SE-12 3.564E-12 1.140E-16-1.OOOE+00 5.010E-11 8.460E-11 REMAINDER 5.150E-15 2.070E-12 3.439E-12 1.100E-16-1.OOOE+00 1.020E-11 3.340E-11 EFFECTIVE 5.890E-15 2.277E-12 3.783E-12 1.210E-16-1.OOOE+00 8.800E-12 1.680E-11 SKIN(FGR) 7.140E-15 2.710E-12 4.502E-12 1.440E-16-1.OOOE+OO O.OOOE+0O O.OOOE+O0 Ru-103 GONADS 2.191E-14 1.404E-11 2.783E-10 4.892E-16-1.OOOE+00 3.070E-10 5.720E-10 BREAST 2.512E-14 1.350E-11 2.677E-10 4.705E-16-1.OOOE+00 3.110E-10 1.200E-10 LUNGS 2.180E-14 1.273E-11 2.522E-10 4.432E-16-1.OOOE+00 1.S61E-08 7.310E-11 RED MARR 2.100E-14 1.287E-11 2.551E-10 4.483E-16-1.OOOE+00 3.190E-10 1.660E-10 BONE SUR 3.892E-14 1.958E-11 3.882E-10 6.823E-16-1.OOOE+00 2.370E-10 9.631E-11 THYROID 2.241E-14 1.331E-11 2.639E-10 4.638E-16-1.OOOE+00 2.570E-10 6.250E-11 REMAINDER 2.080E-14 1.248E-11 2.472E-10 4.346E-16-1.OOOE+00 1.250E-09 2.110E-09 EFFECTIVE 2.251E-14 1.332E-11 2.641E-10 4.642E-16-1.OOOE+00 2.421E-09 8.271E-10 SKIN(FGR) 2.774E-14 1.785E-11 3.543E-10 6.229E-16-1.OOOE+00 O.OOOE+00 O.OOOE+O0 Ru-10S GONADS 3.720E-14 1.327E-11 1.861E-11 8.070E-16-1.OOOE+00 1.590E-11 9.670E-11 BREAST 4.240E-14 1.271E-11 1.783E-11 7.730E-16-1.OOOE+O 6.610E-12 1.590E-11 LUNGS 3.700E-14 1.210E-11 1.697E-11 7.360E-16-1.OOOE+00 5.730E-10 6.210E-12 RED MARR 3.590E-14 1.230E-11 1.725E-11 7.480E-16-1.OOOE+00 7.700E-12 2.350E-11 BONE SUR 6.280E-14 1.809E-11 2.537E-11 1.100E-15-1.OOOE+00 4.620E-12 8.890E-12 THYROID 3.800E-14 1.260E-11 1.766E-11 7.660E-16-l.OOOE+00 4.150E-12 1.820E-12 REMAINDER 3.540E-14 1.189E-11 1.667E-11 7.230E-16-1.OOOE+00 1.610E-10 8.540E-10 EFFECTIVE 3.810E-14 1.265E-11 1.773E-11 7.690E-16-1.OOOE+00 1.230E-10 2.870E-10 SKIN(FGR) 6.730E-14 7.368E-11 1.033E-10 4.480E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO Ru-106 GONADS 1.OlOE-14 6.411E-12 1.340E-10 2.230E-16-1.OOOE+00 1.300E-09 1.640E-09 BREAST 1.160E-14 6.152E-12 1.286E-10 2.140E-16-1.OOOE+00 1.780E-09 1.440E-09 LUNGS 1.OlOE-14 5.836E-12 1.220E-10 2.030E-16-1.OOOE+00 1.040E-06 1.420E-09 RED MARR 9.750E-15 5.893E-12 1.232E-10 2.050E-16-l.OOOE+00 1.760E-09 1.460E-09 BONE SUR 1.720E-14 8.883E-12 1.856E-10 3.090E-16-1.OOOE+00 1.610E-09 1.430E-09 THYROID 1.030E-14 6.066E-12 1.268E-10 2.110E-16-1.OOOE+00 1.720E-09 1.410E-09 REMAINDER 9.630E-15 5.721E-12 1.196E-10 1.990E-16-1.OOOE+00 1.200E-08 2.110E-08 EFFECTIVE 1.040E-14 6.095E-12 1.274E-10 2.120E-16-1.OOOE+00 1.290E-07 7.400E-09 SKIN(FGR) 1.090E-13 4.082E-10 8.531E-09 1.420E-14-1.OOOE+00 O.OOOE+O0 O.OOOE+00 Rh-105 GONADS 3.640E-15 2.127E-12 1.411E-11 7.980E-17-1.OOOE+00 2.110E-11 5.800E-11 BREAST 4.160E-15 2.063E-12 1.369E-11 7.740E-17-1.OOOE+00 5.610E-12 8.970E-12 LUNGS 3.570E-15 1.935E-12 1.284E-11 7.260E-17-1.OOOE+00 9.580E-10 3.860E-12 RED MARR 3.380E-15 1.946E-12 1.291E-11 7.300E-17-1.OOOE+00 7.770E-12 1.470E-11 BONE SUR 7.530E-15 3.332E-12 2.210E-11 1.250E-16-1.OOOE+00 4.460E-12 6.750E-12 THYROID 3.680E-15 1.983E-12 1.316E-11 7.440E-17-1.OOOE+00 2.880E-12 2.910E-12 REMAINDER 3.390E-15 1.885E-12 1.250E-11 7.070E-17-1.OOOE+00 4.530E-10 1.270E-09 EFFECTIVE 3.720E-15 2.031E-12 1.347E-11 7.620E-17-1.OOOE+00 2.580E-10 3.990E-10 SKIN(FGR) 1.070E-14 4.691E-12 3.112E-11 1.760E-16-1.OOOE+OO O.OOOE+OO O.OOOE+O0 Sb-127 GONADS 3.260E-14 1.985E-11 2.441E-10 7.100E-16-1.OOOE+00 2.520E-10 6.140E-10
CA06449 Rev.OOO Page 64 BREAST 3.720E-14 1.904E-11 2.341E-10 6.810E-16-1.OOOE+00 9.120E-11 7.600E-11 LUNGS 3.240E-14 1.809E-11 2.224E-10 6.470E-16-1.OOOE+00 6.940E-09 1.570E-11 RED MARR 3.140E-14 1.834E-11 2.255E-10 6.560E-16-1.OOOE+00 1.610E-10 1.330E-10 BONE SUR 5.520E-14 2.720E-11 3.345E-10 9.730E-16-1.OOOE+00 1.340E-10 S.240E-11 THYROID 3.330E-14 1.884E-11 2.317E-10 6.740E-16-1.OOOE+00 6.1SOE-11 4.640E-12 REMAINDER 3.090E-14 1.775E-11 2.183E-10 6.350E-16-1.OOOE+00 2.330E-09 5.870E-09 EFFECTIVE 3.330E-14 1.890E-11 2.324E-10 6.760E-16-1.OOOE+00 1.630E-09 1.950E-09 SKIN(FGR) 5.580E-14 7.967E-11 9.799E-10 2.850E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO Sb-129 GONADS 6.970E-14 2.336E-11 3.231E-11 1.440E-15-1.OOOE+00 2.150E-11 1.510E-10 BREAST 7.910E-14 2.222E-11 3.074E-11 1.370E-15-1.OOOE+00 1.280E-11 2.560E-11 LUNGS 6.980E-14 2.141E-11 2.962E-11 1.320E-15-1.OOOE+00 8.980E-10 9.390E-12 RED MARR 6.860E-14 2.190E-11 3.029E-11 1.350E-15-1.OOOE+00 1.700E-11 3.670E-11 BONE SUR 1.070E-13 3.033E-11 4.196E-11 1.870E-15-1.OOOE+00 1.460E-11 1.340E-11 THYROID 7.160E-14 2.174E-11 3.007E-11 1.340E-15-1.OOOE+00 9.720E-12 1.470E-12 REMAINDER 6.710E-14 2.125E-11 2.939E-11 1.310E-15-1.OOOE+00 1.870E-10 1.450E-09 EFFECTIVE 7.140E-14 2.238E-11 3.096E-11 1.380E-15-1.OOOE+00 1.740E-10 4.840E-10 SKIN(FGR) 1.050E-13 8.273E-11 1.144E-10 S.100E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO Te-127 GONADS 2.370E-16 1.191E-13 2.661E-13 5.480E-18-1.OOOE+00 2.020E-12 4.020E-12 BREAST 2.730E-16 1.158E-13 2.588E-13 5.330E-18-1.OOOE+00 1.880E-12 3.OOOE-12 LUNGS 2.320E-16 1.060E-13 2.370E-13 4.880E-18-1.OOOE+00 4.270E-10 2.890E-12 RED MARR 2.210E-16 1.058E-13 2.365E-13 4.870E-18-1.OOOE+00 4.090E-12 6.570E-12 BONE SUR 4.650E-16 1.862E-13 4.162E-13 8.570E-18-1.OOOE+00 4.090E-12 6.460E-12 THYROID 2.400E-16 1.106E-13 2.472E-13 5.090E-18-1.OOOE+00 1.840E-12 2.860E-12 REMAINDER 2.210E-16 1.036E-13 2.316E-13 4.770E-18-1.OOOE+OO 1.11OE-10 6.130E-10 EFFECTIVE 2.420E-16 1.125E-13 2.515E-13 5.180E-18-1.OOOE+00 8.600E-11 1.870E-10 SKIN(FGR) 1.140E-14 1.173E-11 2.622E-11 5.400E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO Te-127m GONADS 1.900E-16 4.689E-13 9.642E-12 1.630E-17-1.OOOE+OO 1.100E-10 1.250E-10 BREAST 2.690E-16 5.150E-13 1.059E-11 1.790E-17-1.OOOE+OO 1.100E-10 9.740E-11 LUNGS 7.620E-17 1.602E-13 3.295E-12 5.570E-18-1.OOOE+00 3.340E-08 9.620E-11 RED MARR 6.430E-17 1.249E-13 2.567E-12 4.340E-18-1.OOOE+00 5.360E-09 5.430E-09 BONE SUR 3.940E-16 9.005E-13 1.852E-11 3.130E-17-1.OOOE+00 2.040E-08 2.070E-08 THYROID 1.500E-16 2.779E-13 5.714E-12 9.660E-18-1.OOOE+00 9.660E-11 9.430E-11 REMAINDER 8.640E-17 1.999E-13 4.111E-12 6.950E-18-1.OOOE+00 1.660E-09 2.980E-09 EFFECTIVE 1.470E-16 3.251E-13 6.684E-12 1.130E-17-1.OOOE+00 5.810E-09 2.230E-09 SKIN(FGR) 8.490E-16 1.496E-12 3.076E-11 5.200E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO Te-129 GONADS 2.710E-15 3.889E-13 3.922E-13 6.510E-17-1.OOOE+00 5.050E-13 1.590E-12 BREAST 3.120E-15 3.800E-13 3.832E-13 6.360E-17-1.OOOE+00 5.390E-13 6.050E-13 LUNGS 2.640E-15 3.298E-13 3.326E-13 5.520E-17-1.OOOE+00 1.530E-10 4.910E-13 RED MARR 2.540E-15 3.298E-13 3.326E-13 5.520E-17-1.OOOE+00 6.190E-13 7.640E-13 BONE SUR 4.880E-15 5.753E-13 5.802E-13 9.630E-17-1.OOOE+00 6.220E-13 5.400E-13 THYROID 2.740E-15 3.525E-13 3.555E-13 5.900E-17-1.OOOE+00 5.090E-13 3.360E-13 REMAINDER 2.520E-15 3.262E-13 3.289E-13 5.460E-17-1.OOOE+00 7.280E-12 1.790E-10 EFFECTIVE 2.750E-15 3.590E-13 3.621E-13 6.010E-17-1.OOOE+00 2.090E-11 5.450E-11 SKIN(FGR) 3.570E-14 3.429E-11 3.458E-11 5.740E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO Te-129m GONADS 3.321E-15 2.206E-12 4.799E-11 8.561E-17-1.OOOE+00 1.783E-10 2.420E-10 BREAST 3.838E-15 2.181E-12 4.739E-11 8.454E-17-1.OOOE+00 1.694E-10 1.664E-10 LUNGS 3.176E-15 1.741E-12 3.815E-11 6.808E-17-1.OOOE+00 4.040E-08 1.593E-10 RED MARR 3.071E-15 1.729E-12 3.793E-11 6.768E-17-1.OOOE+00 3.100E-09 3.500E-09 BONE SUR 5.772E-15 3.287E-12 7.147E-11 1.275E-16-1.OOOE+00 7.050E-09 7.990E-09
CA06449 Rev.000 Page 65 THYROID 3.341E-15 1.923E-12 4.201E-11 7.495E-17-1.OOOE+00 1.563E-10 1.572E-10 REMAINDER 3.048E-15 1.746E-12 3.822E-11 6.819E-17-1.OOOE+00 3.275E-09 7.196E-09 EFFECTIVE 3.337E-15 1.974E-12 4.308E-11 7.686E-17-1.OOOE+00 6.484E-09 2.925E-09 SKIN(FGR) 3.811E-14 1.501E-10 3.360E-09 6.001E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO Te-131m GONADS 7.292E-14 4.020E-11 2.343E-10 1.535E-15-1.OOOE+00 2.345E-10 7.415E-10 BREAST 8.286E-14 3.853E-11 2.246E-10 1.472E-15-1.OOOE+00 9.309E-11 1.361E-10 LUNGS 7.265E-14 3.657E-11 2.131E-10 1.397E-15-1.OOOE+00 2.296E-09 6.335E-11 RED MARR 7.097E-14 3.736E-11 2.178E-10 1.427E-15-1.OOOE+00 1.417E-10 2.435E-10 BONE SUR 1.174E-13 5.467E-11 3.189E-10 2.090E-15-1.OOOE+00 2.276E-10 3.248E-10 THYROID 7.471E-14 3.741E-11 2.181E-10 1.429E-15-1.OOOE+00 3.669E-08 4.383E-08 REMAINDER 6.965E-14 3.626E-11 2.113E-10 1.385E-15-1.OOOE+00 9.509E-10 3.153E-09 EFFECTIVE 7.463E-14 3.825E-11 2.229E-10 1.461E-15-1.OOOE+00 1.758E-09 2.514E-09 SKIN(FGR) 1.038E-13 1.033E-10 6.188E-10 4.056E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO Te-132 GONADS 1.020E-14 6.812E-12 7.706E-11 2.450E-16-1.OOOE+00 4.150E-10 5.410E-10 BREAST 1.180E-14 6.756E-12 7.643E-11 2.430E-16-1.OOOE+00 3.630E-10 3.500E-10 LUNGS 9.650E-15 5.727E-12 6.479E-11 2.060E-16-1.OOOE+00 1.670E-09 3.300E-10 RED MARR 8.950E-15 5.588E-12 6.322E-11 2.010E-16-1.OOOE+00 4.270E-10 4.440E-10 BONE SUR 2.420E-14 1.273E-11 1.441E-10 4.580E-16-1.OOOE+00 7.120E-10 8.300E-10 THYROID 1.020E-14 5.978E-12 6.762E-11 2.150E-16-1.OOOE+00 6.280E-08 5.950E-08 REMAINDER 9.160E-15 5.644E-12 6.385E-11 2.030E-16-1.OOOE+00 7.890E-10 1.490E-09 EFFECTIVE 1.030E-14 6.339E-12 7.171E-11 2.280E-16-1.OOOE+00 2.550E-09 2.540E-09 SKIN(FGR) 1.390E-14 8.313E-12 9.405E-11 2.990E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO I-131 GONADS 1.780E-14 1.119E-11 1.789E-10 3.940E-16-1.OOOE+00 2.530E-11 4.070E-11 BREAST 2.040E-14 1.082E-11 1.730E-10 3.810E-16-1.OOOE+00 7.880E-11 1.210E-10 LUNGS 1.760E-14 1.016E-11 1.626E-10 3.580E-16-1.OOOE+00 6.570E-10 1.020E-10 RED MARR 1.680E-14 1.022E-11 1.635E-10 3.600E-16-1.OOOE+00 6.260E-11 9.440E-11 BONE SUR 3.450E-14 1.675E-11 2.679E-10 5.900E-16-1.OOOE+00 5.730E-11 8.720E-11 THYROID 1.810E-14 1.053E-11 1.685E-10 3.710E-16-1.OOOE+00 2.920E-07 4.760E-07 REMAINDER 1.670E-14 9.908E-12 1.585E-10 3.490E-16-1.OOOE+00 8.030E-11 1.570E-10 EFFECTIVE 1.820E-14 1.067E-11 1.707E-10 3.760E-16-1.OOOE+00 8.890E-09 1.440E-08 SKIN(FGR) 2.980E-14 1.825E-11 2.920E-10 6.430E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO I-132 GONADS 1.090E-13 2.523E-11 2.771E-11 2.320E-15-1.OOOE+OO 9.9SOE-12 2.330E-11 BREAST 1.240E-13 2.414E-11 2.652E-11 2.220E-15-1.OOOE+00 1.410E-11 2.520E-11 LUNGS 1.090E-13 2.305E-11 2.532E-11 2.120E-15-1.OOOE+00 2.710E-10 2.640E-11 RED MARR 1.070E-13 2.360E-11 2.592E-11 2.170E-15-1.OOOE+00 1.400E-11 2.460E-11 BONE SUR 1.730E-13 3.327E-11 3.655E-11 3.060E-15-1.OOOE+00 1.240E-11 2.190E-11 THYROID 1.120E-13 2.381E-11 2.616E-11 2.190E-15-1.OOOE+00 1.740E-09 3.870E-09 REMAINDER 1.050E-13 2.283E-11 2.509E-11 2.100E-15-1.OOOE+00 3.780E-11 1.650E-10 EFFECTIVE 1.120E-13 2.403E-11 2.640E-11 2.210E-15-1.OOOE+00 1.030E-10 1.820E-10 SKIN(FGR) 1.580E-13 8.199E-11 9.007E-11 7.540E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO I-133 GONADS 2.870E-14 1.58SE-11 6.748E-11 6.270E-16-1.OOOE+00 1.950E-11 3.630E-11 BREAST 3.280E-14 1.519E-11 6.468E-11 6.010E-16-1.OOOE+00 2.940E-11 4.680E-11 LUNGS 2.860E-14 1.446E-11 6.156E-11 5.720E-16-1.OOOE+00 8.200E-10 4.530E-11 RED MARR 2.770E-14 1.466E-11 6.242E-11 5.800E-16-1.OOOE+00 2.720E-11 4.300E-11 BONE SUR 4.870E-14 2.161E-11 9.202E-11 8.550E-16-1.OOOE+00 2.520E-11 4.070E-11 THYROID 2.930E-14 1.502E-11 6.393E-11 5.940E-16-1.OOOE+00 4.860E-08 9.100E-08 REMAINDER 2.730E-14 1.418E-11 6.03SE-11 5.610E-16-1.OOOE+00 5.000E-11 1.550E-10 EFFECTIVE 2.940E-14 1.509E-11 6.425E-11 5.970E-16-1.OOOE+00 1.580E-09 2.800E-09 SKIN(FGR) 5.830E-14 1.150E-10 4.897E-10 4.550E-15-1.OOOE+00 O.OOOE+00 O.OOOE+O0
CA06449 Rev. 000 Page 66 I-134 GONADS 1.270E-13 1.200E-11 1.202E-11 2.640E-15-1.OOOE+00 4.250E-12 1.100E-11 BREAST 1.440E-13 1.145E-11 1.147E-11 2.520E-15-1.OOOE+00 6.170E-12 1.170E-11 LUNGS 1.270E-13 1.100E-11 1.102E-11 2.420E-15-1.OOOE+00 1.430E-10 1.260E-11 RED MARR 1.250E-13 1.127E-11 1.129E-11 2.480E-15-1.OOOE+00 6.080E-12 1.090E-11 BONE SUR 1.960E-13 1.568E-11 1.571E-11 3.450E-15-1.OOOE+00 5.310E-12 9.320E-12 THYROID 1.300E-13 1.127E-11 1.129E-11 2.480E-15-1.OOOE+00 2.880E-10 6.210E-10 REMAINDER 1.220E-13 1.091E-11 1.093E-11 2.400E-15-1.OOOE+00 2.270E-11 1.340E-10 EFFECTIVE 1.300E-13 1.150E-11 1.152E-11 2.530E-15-1.OOOE+00 3.550E-11 6.660E-11 SKIN(FGR) 1.870E-13 4.477E-11 4.485E-11 9.850E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO I-135 GONADS 8.078E-14 3.113E-11 5.489E-11 1.599E-15-1.OOOE+00 1.700E-11 3.610E-11 BREAST 9.143E-14 2.971E-11 5.240E-11 1.526E-15-1.OOOE+00 2.340E-11 3.850E-11 LUNGS 8.145E-14 2.886E-11 5.089E-11 1.482E-15-1.OOOE+00 4.410E-10 3.750E-11 RED MARR 8.054E-14 2.965E-11 5.228E-11 1.523E-15-1.OOOE+00 2.240E-11 3.650E-11 BONE SUR 1.184E-13 3.983E-11 7.024E-11 2.046E-15-1.OOOE+00 2.010E-11 3.360E-11 THYROID 8.324E-14 2.852E-11 5.030E-11 1.465E-15-1.OOOE+00 8.460E-09 1.790E-08 REMAINDER 7.861E-14 2.883E-11 5.084E-11 1.481E-15-1.OOOE+00 4.700E-11 1.540E-10 EFFECTIVE 8.294E-14 2.989E-11 5.271E-11 1.535E-15-1.OOOE+00 3.320E-10 6.080E-10 SKIN(FGR) 1.156E-13 9.826E-11 1.733E-10 5.047E-15-l.OOOE+OO O.OOOE+OO O.OOOE+OO Xe-133 GONADS 1.610E-15 1.465E-12 2.052E-11 5.200E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO BREAST 1.960E-15 1.505E-12 2.107E-11 5.340E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS 1.320E-15 1.045E-12 1.464E-11 3.710E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR 1.070E-15 8.791E-13 1.231E-11 3.120E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO BONE SUR 5.130E-15 4.254E-12 5.958E-11 1.510E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO THYROID 1.510E-15 1.181E-12 1.653E-11 4.190E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER 1.240E-15 1.042E-12 1.460E-11 3.700E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO EFFECTIVE 1.560E-15 1.299E-12 1.819E-11 4.610E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO SKIN(FGR) 4.970E-15 1.953E-12 2.734E-11 6.930E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO Xe-135 GONADS 1.170E-14 5.455E-12 1.194E-11 2.530E-16-1.OOOE+00 O.OOOE+OO O.OOOE+OO BREAST 1.330E-14 5.325E-12 1.166E-11 2.470E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS 1.130E-14 4.959E-12 1.086E-11 2.300E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR 1.070E-14 4.959E-12 1.O6E-1l 2.300E-16-l.OOOE+OO O.OOOE+OO O.OOOE+OO BONE SUR 2.570E-14 9.120E-12 1.997E-11 4.230E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO THYROID 1.180E-14 5.023E-12 1.100E-11 2.330E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER 1.080E-14 4.829E-12 1.058E-11 2.240E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO EFFECTIVE 1.190E-14 5.217E-12 1.142E-11 2.420E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO SKIN(FGR) 3.120E-14 4.506E-11 9.867E-11 2.090E-15-1.OOOE+00 O.OOOE+OO O.OOOE+OO Cs-134 GONADS 7.400E-14 4.607E-11 9.646E-10 1.600E-15-1.OOOE+00 1.300E-08 2.060E-08 BREAST 8.430E-14 4.406E-11 9.224E-10 1.530E-15-1.OOOE+00 1.080E-08 1.720E-08 LUNGS 7.370E-14 4.204E-11 8.802E-10 1.460E-15-1.OOOE+00 1.180E-08 1.760E-08 RED MARR 7.190E-14 4.262E-11 8.922E-10 1.480E-15-1.OOOE+00 1.180E-08 1.870E-08 BONE SUR 1.200E-13 6.105E-11 1.278E-09 2.120E-15-1.OOOE+OO 1.100E-08 1.740E-08 THYROID 7.570E-14 4.377E-11 9.163E-10 1.520E-15-1.OOOE+OO 1.110E-08 1.760E-08 REMAINDER 7.060E-14 4.147E-11 8.681E-10 1.440E-15-1.OOOE+00 1.390E-08 2.210E-08 EFFECTIVE 7.570E-14 4.377E-11 9.163E-10 1.520E-15-1.OOOE+00 1.250E-08 1.980E-08 SKIN(FGR) 9.450E-14 6.249E-11 1.308E-09 2.170E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO Cs-136 GONADS 1.040E-13 6.223E-11 1.102E-09 2.180E-15-1.OOOE+00 1.880E-09 3.040E-09 BREAST 1.180E-13 5.966E-11 1.056E-09 2.090E-15-1.OOOE+00 1.670E-09 2.650E-09 LUNGS 1.040E-13 5.710E-11 1.O11E-09 2.OOOE-15-1.OOOE+00 2.320E-09 2.620E-09
CA06449 Rev.000 Page 67 RED MARR 1.OlOE-13 5.824E-11 1.031E-09 2.040E-15-1.OOOE+00 1.860E-09 2.950E-09 BONE SUR 1.660E-13 8.422E-11 1.491E-09 2.950E-15-l.OOOE+00 1.700E-09 2.710E-09 THYROID 1.070E-13 5.852E-11 1.036E-09 2.050E-15-1.OOOE+00 1.730E-09 2.740E-09 REMAINDER 9.950E-14 5.652E-11 1.OO1E-09 1.980E-15-1.OOOE+00 2.190E-09 3.520E-09 EFFECTIVE 1.060E-13 5.966E-11 1.056E-09 2.090E-15-1.OOOE+00 1.980E-09 3.040E-09 SKIN(FGR) 1.250E-13 7.251E-11 1.284E-09 2.540E-15-1.OOOE+OO O.OOOE+00 O.OOOE+OO Cs-137 GONADS 2.669E-14 1.669E-11 3.530E-10 5.840E-16-1.OOOE+00 8.760E-09 1.390E-08 BREAST 3.047E-14 1.596E-11 3.376E-10 5.585E-16-1.OOOE+00 7.840E-09 1.240E-08 LUNGS 2.649E-14 1.517E-11 3.209E-10 5.309E-16-1.OOOE+00 8.820E-09 1.270E-08 RED MARR 2.583E-14 1.542E-11 3.260E-10 5.394E-16-1.OOOE+00 8.300E-09 1.320E-08 BONE SUR 4.382E-14 2.238E-11 4.734E-10 7.832E-16-1.OOOE+00 7.940E-09 1.260E-08 THYROID 2.725E-14 1.588E-11 3.358E-10 5.556E-16-1.OOOE+00 7.930E-09 1.260E-08 REMAINDER 2.536E-14 1.490E-11 3.152E-10 5.215E-16-1.OOOE+00 9.120E-09 1.450E-08 EFFECTIVE 2.725E-14 1.585E-11 3.353E-10 5.546E-16-1.OOOE+00 8.630E-09 1.350E-08 SKIN(FGR) 4.392E-14 5.253E-11 1.110E-09 1.836E-15-1.OOOE+O0 O.OOOE+O0 O.OOOE+OO Ba-139 GONADS 2.130E-15 3.368E-13 3.429E-13 4.790E-17-1.OOOE+00 2.560E-12 1.560E-12 BREAST 2.450E-15 3.297E-13 3.357E-13 4.690E-17-1.OOOE+00 2.460E-12 5.170E-13 LUNGS 2.030E-15 3.002E-13 3.057E-13 4.270E-17-1.OOOE+00 2.530E-10 3.890E-13 RED MARR 1.870E-15 2.932E-13 2.985E-13 4.170E-17-1.OOOE+00 3.410E-12 8.590E-13 BONE SUR 5.290E-15 6.841E-13 6.965E-13 9.730E-17-1.OOOE+00 2.490E-12 4.380E-13 THYROID 2.130E-15 3.044E-13 3.100E-13 4.330E-17-1.OOOE+00 2.400E-12 2.660E-13 REMAINDER 1.920E-15 2.932E-13 2.985E-13 4.170E-17-1.OOOE+00 4.820E-11 3.570E-10 EFFECTIVE 2.170E-15 3.227E-13 3.286E-13 4.590E-17-l.OOOE+00 4.640E-11 1.080E-10 SKIN(FGR) 6.160E-14 7.241E-11 7.373E-11 1.030E-14-1.OOOE+OO O.OOOE+OO O.OOOE+0O Ba-140 GONADS 8.410E-15 5.451E-12 9.607E-11 1.910E-16-1.OOOE+00 4.300E-10 9.960E-10 BREAST 9.640E-15 5.280E-12 9.305E-11 1.850E-16-1.OOOE+00 2.870E-10 1.590E-10 LUNGS 8.270E-15 4.852E-12 8.550E-11 1.700E-16-1.OOOE+00 1.660E-09 6.630E-11 RED MARR 7.930E-15 4.880E-12 8.601E-11 1.710E-16-1.OOOE+00 1.290E-09 4.390E-10 BONE SUR 1.550E-14 8.020E-12 1.413E-10 2.810E-16-1.OOOE+00 2.410E-09 5.530E-10 THYROID 8.530E-15 5.109E-12 9.003E-11 1.790E-16-1.OOOE+00 2.560E-10 5.250E-11 REMAINDER 7.890E-15 4.766E-12 8.399E-11 1.670E-16-1.OOOE+00 1.410E-09 7.370E-09 EFFECTIVE 8.580E-15 5.137E-12 9.053E-11 1.800E-16-1.000E+00 1.010E-09 2.560E-09 SKIN(FGR) 2.520E-14 5.565E-11 9.808E-10 1.9SOE-15-1.OOOE+00 O.OOOE+00 O.OOOE+00 La-140 GONADS 1.140E-13 6.027E-11 4.425E-10 2.240E-15-1.OOOE+00 4.540E-10 1.340E-09 BREAST 1.290E-13 5.758E-11 4.228E-10 2.140E-15-1.OOOE+00 1.450E-10 1.800E-10 LUNGS 1.150E-13 5.596E-11 4.109E-10 2.080E-15-1.OOOE+00 4.210E-09 4.010E-11 RED MARR 1.140E-13 5.731E-11 4.208E-10 2.130E-15-1.OOOE+00 2.140E-10 2.810E-10 BONE SUR 1.690E-13 7.776E-11 5.709E-10 2.890E-15-1.OOOE+00 1.410E-10 9.770E-11 THYROID 1.180E-13 5.462E-11 4.010E-10 2.030E-15-1.OOOE+00 6.870E-11 6.400E-12 REMAINDER 1.110E-13 5.569E-11 4.089E-10 2.070E-15-1.OOOE+00 2.120E-09 6.260E-09 EFFECTIVE 1.170E-13 5.812E-11 4.267E-10 2.160E-15-1.OOOE+00 1.310E-09 2.280E-09 SKIN(FGR) 1.660E-13 2.217E-10 1.628E-09 8.240E-15-1.OOOE+00 O.OOOE+00 O.OOOE+00 La-141 GONADS 2.330E-15 7.315E-13 9.675E-13 4.740E-17-1.000E+00 1.O1OE-11 3.770E-12 BREAST 2.640E-15 7.007E-13 9.267E-13 4.540E-17-1.OOOE+00 9.840E-12 7.070E-13 LUNGS 2.340E-15 6.713E-13 8.879E-13 4.350E-17-1.OOOE+00 6.460E-10 2.720E-13 RED MARR 2.310E-15 6.852E-13 9.063E-13 4.440E-17-1.OOOE+00 2.930E-11 1.070E-12 BONE SUR 3.490E-15 9.923E-13 1.312E-12 6.430E-17-1.OOOE+00 1.200E-10 6.060E-13 THYROID 2.390E-15 6.590E-13 8.716E-13 4.270E-17-1.OOOE+00 9.400E-12 5.290E-14 REMAINDER 2.260E-15 6.682E-13 8.838E-13 4.330E-17-1.OOOE+00 2.280E-10 1.240E-09
CA06449 Rev. 000 Page 68 EFFECTIVE 2.390E-15 7.007E-13 9.267E-13 4.540E-17-1.OOOE+00 1.570E-10 3.740E-10 SKIN(FGR) 6.580E-14 1.667E-10 2.204E-10 1.080E-14-1.OOOE+OO O.OOOE+OO O.OOOE+OO La-142 GONADS 1.400E-13 1.978E-11 2.034E-11 2.540E-15-1.OOOE+00 1.660E-11 6.990E-11 BREAST 1.570E-13 1.885E-11 1.938E-11 2.420E-15-1.OOOE+00 1.130E-11 1.540E-11 LUNGS 1.420E-13 1.846E-11 1.898E-11 2.370E-15-1.OOOE+00 3.010E-10 8.400E-12 RED MARR 1.420E-13 1.900E-11 1.954E-11 2.440E-15-1.OOOE+00 1.360E-11 1.930E-11 BONE SUR 1.950E-13 2.484E-11 2.554E-11 3.190E-15-1.OOOE+OO 1.110E-11 7.400E-12 THYROID 1.450E-13 1.768E-11 1.818E-11 2.270E-15-1.OOOE+00 8.740E-12 1.160E-12 REMAINDER 1.380E-13 1.853E-11 1.906E-11 2.380E-15-1.OOOE+00 8.070E-11 5.200E-10 EFFECTIVE 1.440E-13 1.916E-11 1.970E-11 2.460E-15-1.OOOE+00 6.840E-11 1.790E-10 SKIN(FGR) 2.160E-13 9.111E-11 9.368E-11 1.170E-14-1.OOOE+OO O.OOOE+OO O.OOOE+OO Ce-141 GONADS 3.380E-15 2.213E-12 4.332E-11 7.710E-17-1.OOOE+00 5.540E-11 1.080E-10 BREAST 3.930E-15 2.170E-12 4.247E-11 7.560E-17-1.OOOE+00 4.460E-11 1.11OE-11 LUNGS 3.170E-15 1.951E-12 3.820E-11 6.800E-17-1.OOOE+00 1.670E-08 1.430E-12 RED MARR 2.830E-15 1.860E-12 3.641E-11 6.480E-17-1.OOOE+00 8.960E-11 3.390E-11 BONE SUR 9.410E-15 5.166E-12 1.011E-10 1.800E-16-1.OOOE+00 2.540E-10 2.300E-11 THYROID 3.350E-15 2.003E-12 3.922E-11 6.980E-17-1.OOOE+00 2.550E-11 1.800E-13 REMAINDER 2.980E-15 1.894E-12 3.708E-11 6.600E-17-1.OOOE+00 1.260E-09 2.500E-09 EFFECTIVE 3.430E-15 2.118E-12 4.146E-11 7.380E-17-1.OOOE+00 2.420E-09 7.830E-10 SKIN(FGR) 1.020E-14 3.788E-12 7.416E-11 1.320E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO Ce-143 GONADS 1.280E-14 7.900E-12 4.958E-11 2.980E-16-1.OOOE+00 7.530E-11 2.120E-10 BREAST 1.470E-14 7.688E-12 4.825E-11 2.900E-16-1.OOOE+00 1.660E-11 2.320E-11 LUNGS 1.230E-14 6.893E-12 4.325E-11 2.600E-16-1.OOOE+00 3.880E-09 3.820E-12 RED MARR 1.170E-14 6.787E-12 4.259E-11 2.560E-16-1.OOOE+00 2.960E-11 5.070E-11 BONE SUR 2.520E-14 1.323E-11 8.302E-11 4.990E-16-1.OOOE+00 1.640E-11 1.610E-11 THYROID 1.280E-14 7.211E-12 4.525E-11 2.720E-16-1.OOOE+00 6.230E-12 4.350E-13 REMAINDER 1.170E-14 6.734E-12 4.226E-11 2.540E-16-1.OOOE+00 1.420E-09 3.890E-09 EFFECTIVE 1.290E-14 7.396E-12 4.642E-11 2.790E-16-1.OOOE+00 9.160E-10 1.230E-09 SKIN(FGR) 3.960E-14 1.058E-10 6.638E-10 3.990E-15-1.OOOE+00 O.OOOE+00 O.OOOE+00 Ce-144 GONADS 2.725E-15 6.328E-13 1.319E-11 6.088E-17-1.000E+00 2.390E-10 6.987E-11 BREAST 3.129E-15 6.274E-13 1.307E-11 5.922E-17-1.OOOE+00 3.480E-10 1.223E-11 LUNGS 2.639E-15 5.228E-13 1.089E-11 5.362E-17-1.OOOE+00 7.911E-07 6.551E-12 RED MARR 2.507E-15 4.755E-13 9.907E-12 5.247E-17-1.000E+00 2.880E-09 8.923E-11 BONE SUR 5.441E-15 1.646E-12 3.429E-11 1.127E-16-1.OOOE+00 4.720E-09 1.280E-10 THYROID 2.753E-15 5.529E-13 1.152E-11 5.418E-17-1.OOOE+00 2.920E-10 5.154E-12 REMAINDER 2.534E-15 5.086E-13 1.060E-11 5.283E-17-1.OOOE+00 1.910E-08 1.890E-08 EFFECTIVE 2.773E-15 5.909E-13 1.231E-11 5.766E-17-1.OOOE+00 1.OlOE-07 5.711E-09 SKIN(FGR) 8.574E-14 7.648E-13 1.594E-11 1.250E-14-1.OOOE+00 O.OOOE+00 O.OOOE+00 Pr-143 GONADS 2.130E-17 2.264E-14 4.032E-13 7.930E-19-1.OOOE+00 4.370E-18 8.990E-18 BREAST 2.550E-17 2.330E-14 4.149E-13 8.160E-19-1.OOOE+00 2.220E-18 1.090E-18 LUNGS 1.860E-17 1.642E-14 2.923E-13 5.750E-19-1.OOOE+00 1.330E-08 1.910E-19 RED MARR 1.620E-17 1.493E-14 2.659E-13 5.230E-19-1.OOOE+00 1.480E-11 1.030E-12 BONE SUR 5.930E-17 5.454E-14 9.711E-13 1.910E-18-1.000E+00 1.490E-11 1.030E-12 THYROID 2.050E-17 1.802E-14 3.208E-13 6.310E-19-1.000E+00 1.680E-18 2.660E-20 REMAINDER 1.760E-17 1.642E-14 2.923E-13 5.750E-19-1.OOOE+00 1.970E-09 4.220E-09 EFFECTIVE 2.100E-17 2.002E-14 3.564E-13 7.010E-19-1.OOOE+00 2.190E-09 1.270E-09 SKIN(FGR) 1.760E-14 5.711E-11 1.017E-09 2.000E-15-1.OOOE+00 O.OOOE+00 O.OOOE+00 Nd-147 GONADS 6.130E-15 4.218E-12 7.235E-11 1.480E-16-1.OOOE+00 8.410E-11 1.790E-10
CA06449 Rev. 000 Page 69 BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR)
Np-239 GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FOR)
Pu-238 GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR)
Pu-239 GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR)
Pu-240 GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR)
Pu-241 GONADS BREAST LUNGS RED MARR BONE SUR 7.120E-15 5.820E-15 5.400E-15 1.320E-14 6.120E-15 5.530E-15 6.190E-15 1.950E-14 7.530E-15 8.730E-15 7.180E-15 6.500E-15 2.OOOE-14 7.520E-15
- 6. 760E-15 7.690E-15 1.600E-14 6.560E-18 1.270E-17 1.060E-18 1.680E-18 9.300E-18 4. 010E-18 1.990E-18 4.880E-18 4.090E-17 4.840E-18 7.550E-18 2.650E-18 2.670E-18 9.470E-18 3.880E-18 2.860E-18 4.240E-18 1.860E-17 6.360E-18 1.230E-17 1.090E-18 1.650E-18 9.260E-18 3.920E-18 1.960E-18 4.750E-18 3.920E-17 7.190E-20 8.670E-20 6.480E-20 5.630E-20 2.190E-19 4.132E-12 3.648E-12 3.505E-12 8.265E-12 3.876E-12 3.562E-12 3.961E-12 3.135E-11 4.691E-12 4.636E-12 4.115E-12
- 4. 005E-12
- 1. 001E-11 4.197E-12 4.005E-12 4.471E-12 7.215E-12 4.291E-14 5.558E-14 2.267E-15 5.587E-15 3.514E-14 9.792E-15 9.216E-15 2.413E-14 2.776E-13 1.768E-14 2.238E-14 2.267E-15 3.456E-15
- 1. 673E-14 5.126E-15 4.838E-15 1.057E-14 1.057E-13 4.118E-14 5.328E-14 2.249E-15 5.386E-15 3.398E-14 9.446E-15 8.870E-15 2.313E-14 2.644E-13 6.653E-17 7.229E-17 4.090E-17 4.003E-17 1.385E-16 7.088E-11 6.257E-11 6.013E-11 1.418E-10 6.648E-11 6.111E-ll 6.795E-11 5.377E-10 4.380E-11 4.329E-11
- 3. 842E-11 3.74OE-11 9.349E-11 3.919E-11 3.740E-1l 4.175E-11 6.737E-11
- 9. 011E-13 1.167E-12 4.759E-14 1.173E-13 7.378E-13 2.056E-13 1.935E-13 5.068E-13 5.830E-12 3.713E-13 4.699E-13 4.760E-14 7.258E-14 3.514E-13 1.077E-13 1.016E-13 2.220E-13 2.220E-12 B.64 9E-13 1.119E-12 4.723E-14 1.131E-13 7.137E-13 1.984E-13 1.863E-13 4.857E-13 5.552E-12 1.396E-15 1.517E-15 8.584E-16 8.403E-16 2.908E-15 1.450E-16-1.OOOE+00 1.280E-16-1.OOOE+00 1.230E-16-1.OOOE+00 2.900E-16-1.000E+00 1.360E-16-1.000E+00 1.250E-16-1.OOOE+00 1.390E-16-1.OOOE+00 1.100E-15-1.OOOE+00 1.710E-16-1.OOOE+00 1.690E-16-1.OOOE+00 1.500E-16-1.OOOE+00 1.460E-16-1.OOOE+00 3.650E-16-1.OOOE+00 1.530E-16-1.OOOE+00 1.460E-16-1.OOOE+00 1.630E-16-1.OOOE+00 2.630E-16-1.OOOE+00 1.490E-18-1.000E+00 1.930E-l8-1.000E+00 7.870E-20-1.OOOE+00 1.940E-19-1.OOOE+00 1.220E-18-1.OOOE+00 3.400E-19-1.OOOE+00 3.200E-19-1.OOOE+00 8.380E-19-1.OOOE+00 9.640E-18-1.OOOE+00 6.140E-19-1.OOOE+00 7.770E-19-1.OOOE+00 7.870E-20-1.OOOE+00 1.200E-19-1.OOOE+00 5.810E-19-1.OOOE+00 1.780E-19-1.OOOE+00 1.680E-19-1.OOOE+00 3.670E-19-1.OOOE+00 3.670E-18-1.OOOE+00 1.430E-18-1.OOOE+OO 1.850E-18-1.OOOE+00 7.810E-20-1.000E+00 1.870E-19-1.OOOE+00 1.180E-18-1.000E+00 3.280E-19-1.OOOE+00 3.080E-19-1.000E+00 8.030E-19-1.OOOE+00 9.180E-18-1.000E+00 2.310E-21-1.OOOE+00 2.510E-21-1.OOOE+00 1.420E-21-1.OOOE+00 1.390E-21-1.OOOE+00 4.810E-21-1.OOOE+00 3.450E-11 1.870E-11 1.060E-08 2.440E-12 9.190E-11 5.050E-11 3.260E-10 2.220E-11 1.820E-11 2.640E-13 1.760E-09 3.760E-09 1.850E-09 1.180E-09 O.OOOE+00 O.OOOE+00 7.450E-11 1.630E-11 2.360E-09
- 2. OBOE-10
- 2. 030E-09 7.620E-12 9.590E-10 6.780E-10 O.OOOE+00 1.620E-10 1.720E-11 2.400E-12 4.660E-ll 3.590E-11 2.070E-13 2.770E-09 8.820E-10 O.OOOE+00 1.040E-05 2.330E-09 4.400E-10 1.800E-13 3.200E-04 8.640E-14 5.800E-05 1.270E-08 7.250E-04 1.580E-07 3.860E-10 7.990E-14 2.740E-05 2.180E-08 7.790E-05 1.340E-08 O.OOOE+00 O.OOOE+OO 1.200E-05 3.990E-10 3.230E-04 6.570E-05 8.210E-04 3.750E-10 3.020E-05 8.330E-05
- 0. OOOE+00 1.200E-05 4.330E-10 3.230E-04 6.570E-05 8.210E-04 3.760E-10 3.020E-05 8.330E-05
- 0. OOOE+00 2.640E-09 1.210E-13 7.890E-14 1.410E-08 1.760E-07 7.50OE-14 2.120E-08 1.400E-08 O.OOOE+00 2.640E-09 1.730E-13 8.220E-14 1.410E-08 1.760E-07 7.510E-14 2.130E-08 1.400E-08 O.OOOE+00 2.760E-07 5.660E-11 2.140E-11 2.790E-15 3.180E-06 4.480E-15 1.430E-06 2.780E-10 1.780E-05 3.480E-09
CA06449 Rev.000 Page 70 THYROID 6.980E-20 4.522E-17 9.491E-16 1.570E-21-1.OOOE+00 9.150E-12 1.OlE-15 REMAINDER 6.090E-20 4.291E-17 9.007E-16 1.490E-21-1.OOOE+00 6.020E-07 1.850E-10 EFFECTIVE 7.250E-20 5.558E-17 1.167E-1S 1.930E-21-1.OOOE+00 1.340E-06 2.070E-10 SKIN(FGR) 1.170E-19 2.033E-16 4.268E-15 7.060E-21-1.OOOE+OO O.OOOE+OO O.OOOE+OO Am-241 GONADS 8.580E-16 9.360E-13 1.966E-11 3.250E-17-1.OOOE+00 3.250E-05 2.700E-07 BREAST 1.070E-15 1.014E-12 2.129E-11 3.520E-17-l.OOOE+00 2.670E-09 2.620E-ll LUNGS 6.740E-16 5.789E-13 1.216E-11 2.010E-i7-1.OOOE+00 1.840E-05 3.360E-11 RED MARR 5.210E-16 4.838E-13 1.016E-11 1.680E-17-l.OOOE+00 1.740E-04 1.450E-06 BONE SUR 2.870E-15 2.678E-12 5.625E-11 9.300E-17-l.OOOE+00 2.170E-03 1.810E-05 THYROID 7.830E-16 6.365E-13 1.337E-11 2.210E-17-i.OOOE+00 1.600E-09 1.320E-1l REMAINDER 6.340E-16 5.933E-13 1.246E-11 2.060E-17-l.OOOE+00 7.820E-05 6.660E-07 EFFECTIVE 8.180E-16 7.920E-13 1.663E-11 2.750E-17-l.OOOE+00 1.200E-04 9.840E-07 SKIN(FGR) 1.280E-15 2.396E-12 S.032E-11 8.320E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO Cm-242 GONADS 7.830E-18 4.893E-14 1.013E-12 1.700E-18-l.OOOE+00 S.700E-07 5.200E-09 BREAST 1.480E-17 6.159E-14 1.275E-12 2.140E-18-1.OOOE+00 9.440E-10 8.950E-12 LUNGS 1.130E-18 3.022E-15 6.257E-14 1.050E-l9-1.OOOE+00 1.550E-05 8.840E-12 RED MARR 1.890E-18 6.562E-15 1.359E-13 2.280E-19-l.OOOE+00 3.900E-06 3.570E-08 BONE SUR 1.060E-17 4.231E-14 8.759E-13 1.470E-18-i.OOOE+00 4.870E-05 4.460E-07 THYROID 4.910E-18 1.261E-14 2.610E-13 4.380E-19-1.OOOE+00 9.410E-10 8.820E-12 REMAINDER 2.270E-18 1.079E-14 2.235E-13 3.750E-l9-l.OOOE+00 2.450E-06 4.020E-08 EFFECTIVE 5.690E-18 2.751E-14 5.697E-13 9.560E-19-1.OOOE+00 4.670E-06 3.100E-08 SKIN(FGR) 4.290E-17 2.700E-13 5.589E-12 9.380E-18-l.OOOE+CC C.CCOE+CO O.OOOE+OO Cm-244 GONADS 6.900E-18 4.522E-14 9.492E-13 1.570E-18-1.OOOE+00 1.590E-05 1.330E-07 BREAST 1.330E-17 5.702E-14 1.197E-12 1.980E-18-l.OOCE+00 1.040E-09 8.820E-12 LUNGS 7.080E-19 2.592E-15 5.441E-14 9.0C0E-20-l.OOOE+00 1.930E-05 8.810E-12 RED MARR 1.460E-18 5.875E-1S 1.233E-13 2.040E-19-l.OOOE+00 9.380E-05 7.820E-07 BONE SUR 8.820E-18 3.859E-14 8.101E-13 1.340E-18-l.OOOE+00 1.170E-03 9.770E-06 THYROID 4.190E-18 1.146E-14 2.406E-13 3.980E-19-l.OOOE+OC l.O1CE-C9 8.440E-12 REMAINDER 1.810E-18 9.821E-15 2.062E-13 3.410E-l9-l.OOOE+00 4.780E-05 4.150E-07 EFFECTIVE 4.910E-18 2.529E-14 S.308E-13 8.780E-19-l.OOOE+00 6.700E-05 5.450E-07 SKIN(FGR) 3.910E-17 2.506E-13 S.260E-12 8.700E-18-l.CCCE+CC O.OOOE+OC O.OOOE+OC Xe-133m GONADS 1.420E-15 0.CCE+00 O.OOOCE+CC C.CCCE+OC-l.OOOE+CC O.OOOE+CC O.OOOE+CO BREAST 1.700E-15 O.OOOE+OO O.OOOE+CC O.OOOE+OC-l.OOOE+CC O.OOOE+CC O.OOOE+OC LUNGS 1.190E-15 O.OOOE+OC O.OOOE+CO O.OOOE+CO-l.OOOE+CC O.OOOE+CO O.OOOE+CC RED MARR 1.10CE-15 O.OOOE+CC O.OOOE+CC O.OOOE+OO-l.OOOE+CC O.OOOE+CC O.OOOE+CC BONE SUR 3.230E-15 O.OOOE+CC O.OOOE+OC O.OOOE+CC-l.OOOE+CO O.OOOE+OO O.OCCE+CO THYROID 1.360E-15 O.OOOE+CC O.OOOE+CO O.OOOE+CO-l.OOOE+CO O.OOOE+CC O.OOOE+CC REMAINDER 1.150E-15 O.OOOE+OC O.OOOE+OO O.OOOE+OO-l.OOOE+OO C.COCE+OC O.OOOE+CO EFFECTIVE 1.370E-15 O.OOOE+CO O.OOOE+CO O.OOOE+OC-l.OOOE+CC O.OOOE+CC O.OOOE+OO SKIN(FGR) 1.040E-14 O.OOOE+CC O.OOOE+CC O.OOOE+CC-l.OOOE+OO O.OOOE+OC O.OOOE+CO Xe-135m GONADS 2.00CE-14 O.OOOE+OC O.OOOE+OC O.OOOE+OC-l.OOOE+CC O.OOOE+CC O.OOOE+CC BREAST 2.290E-14 O.OOOE+CC O.OOOE+CO O.OOOE+OC-1.OOOE+CO O.OOOE+OO O.OOOE+CO LUNGS 1.980E-14 O.OOOE+OC O.OOOE+CC O.OOOE+OC-l.OOOE+CC O.OOOE+OO O.OOOE+CO RED MARR l.910E-14 O.OOOE+CO O.OOOE+OO O.OOOE+CC-l.OOOE+CC O.OOOE+OC O.OOOE+OC BONE SUR 3.500E-14 O.OOOE+CC O.OOOE+OC C.OCCE+CC-l.OOCE+OC O.OOOE+OO O.OOOE+CC THYROID 2.040E-14 O.OOOE+CC O.OOOE+CO O.OOOE+CO-l.OOOE+CC O.OOOE+CC O.OOOE+OC REMAINDER 1.890E-14 O.OOOE+CO O.OOOE+OO O.OOOE+CO-1.OOOE+OO O.OOOE+CO O.OOOE+CC EFFECTIVE 2.040E-14 O.OOOE+CC O.OOOE+CO O.OOOE+CO-1.OOOE+CO O.OOOE+OO O.OOOE+CC SKIN(FGR) 2.970E-14 O.OOOE+CC O.OOOE+OO O.OOOE+OO-l.OOOE+OO O.OOOE+OO O.OOOE+CO
CA06449 Rev.OOO Page 71 Xe-138 GONADS 5.590E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO BREAST 6.320E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS 5.660E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR 5.600E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO BONE SUR 8.460E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO THYROID 5.770E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER 5.490E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO EFFECTIVE 5.770E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO SKIN(FGR) 1.070E-13 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO
CA06449 Rev.OO0 Page 72 ATTACHMENT E OUTPUT FILE MHACTMT.oO Cumulative Dose Summary EAB Time (hr) 0.000 0.017 0.018 0.025 0.333 0.500 0.500 0.678 0.978 1.278 1.578 1.878 2.000 2.400 2.700 3.000 3.300 3.600 3.900 4.200 4.500 4.800 5.100 5.400 5.700 6.000 6.300 6.600 6.900 7.200 7.500 7.800 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 24.000 96.000 Thyroid (rem) 0.OOOOE+00 3.5407E-03 3.8880E-03 7.9282E-03 1.0295E+00 1.9998E+00 2.0049E+00 1.4298E+01 2.3434E+01 2.6763E+01 2.8013E+01 2.8510E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+01 2.8618E+O1 2.8618E+01 TEDE (rem) 0.OOOOE+00 1.7593E-04 1.9316E-04 3.9364E-04 5.0856E-02 9.8412E-02 9.8720E-02 8.5803E-01 1.4505E+00 1.6932E+00 1.8091E+00 1.8774E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00
- 1. 8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 1.8988E+00 Li Thyroid (rem) 0.OOOOE+00 8.9880E-04 9.8695E-04 2.0125E-03 2.6134E-01 5.0764E-0l
- 5. 0895E-01 3.6295E+00 5.9486E+00 6.7937E+00 7.1110E+00 7.2372E+00 7.2647E+00 7.2680E+00 7.2692E+00 7.2701E+00 7.2707E+00 7.2712E+00 7.2716E+00 7.2720E+00 7.2723E+00 7.2725E+00 7.2727E+00 7.2729E+00 7.2731E+00 7.2732E+00 7.2733E+00 7.2735E+00 7.2736E+00 7.2736E+00 7.2737E+00 7.2738E+00 7.2738E+00 7.2739E+00 7.2739E+00 7.2739E+00 7.2739E+00 7.2740E+00 7.2740E+00 7.2740E+00 7.2740E+00 7.2742E+00 7.2742E+00
(rem) 0.OOOOE+00 0.OOOOE+00 4.4660E-05 1.7122E-04 4.9033E-05 1.8956E-04 9.9925E-05 4.6275E-04 1.2909E-02 7.3860E-01 2.4981E-02 1.9560E+00 2.5060E-02 1.9569E+00 2.1781E-01 9.3452E+00 3.6821E-01 3.0389E+01 4.2981E-01 4.7106E+01 4.5922E-01 4.7656E-01 4.8201E-01 4.8299E-01 4.8361E-01 4.8417E-01 4.8468E-01 4.8516E-01 4.8560E-01 4.8602E-01 4.8640E-01 4.8677E-01 4.8710E-01 4.8742E-01 4.8772E-01 4.8800E-01 4.8827E-01 4.88S2E-01 4.8875E-01 4.8898E-01 4.8919E-01 4.8939E-01 4.8951E-01 4.8970E-01 4.8987E-01 4.9003E-01 4.9019E-01 4.9034E-01 4.9048E-01 4.9062E-01 4.9075E-01 5.7400E+01 6.3144E+01 6.4629E+01 6.7427E+01 6.8361E+01 6.8846E+01 6.9108E+01 6.9259E+01 6.9353E+01 6.9417E+01 6.9463E+01 6.9499E+01 6.9529E+01 6.9553E+01 6.9S73E+01 6.9591E+01 6.9607E+01 6.9620E+01 6.9632E+01 6.9643E+01 6.9652E+01 6.9661E+01 6.9666E+01 6.9672E+01 6.9676E+01 6.9679E+01 6.9682E+01 6.9684E+01 6.9686E+01
- 6. 9687E+01 6.9689E+01 TEDE (rem) 0.OOOOE+00 7.4441E-06 8.2415E-06 2.0118E-05 3.1994E-02 8.4596E-02 8.4634E-02 4.7378E-01 1.6153E+00 2.5304E+00 3.0983E+00 3.4193E+00 3.5037E+00 3.6678E+00 3.7273E+00 3.7620E+00 3.7842E+00 3.8001E+00 3.8125E+00 3.8229E+00 3.8321E+00 3.8403E+00 3.8478E+00 3.8548E+00 3.8613E+00 3.8673E+00 3.8730E+00 3.8783E+00 3.8833E+00 3.8880E+00 3.8924E+00 3.8966E+00 3.8992E+00 3.9028E+00 3.9058E+00 3.9084E+00 3.9106E+00 3.9126E+00 3.9144E+00 3.9160E+00 3.9174E+00 4.9389E-01 6.9702E+01 3.9460E+00 4.9458E-01 6.9702E+01 3.9575E+00
CA06449 Rev.OOO Page 73 720.000 2.8618E+01 1.8988E+00 7.2742E+00 4.9580E-01 6.9702E+01 3.9682E+00 Worst Two-Hour Doses EAB Time Whole Body Thyroid TEDE (hr)
(rem)
(rem)
(rem) 0.0 3.7335E-01 2.8618E+01 1.8988E+00
CA06449 Rev.OOO Page 74 ATTACHMENT F OUTPUT FILE MHAVS.oO Cumulative Dose Summary EAB LPZ cr Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr)
(rem)
(rem)
(rem)
(rem)
(rem)
(rem) 0.000 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.017 1.5389E-04 9.8329E-06 3.6229E-05 2.3148E-06 1.0168E-05 4.4975E-07 0.018 1.6899E-04 1.0791E-05 3.9782E-05 2.5405E-06 1.1258E-05 4.9791E-07 0.025 3.4459E-04 2.1944E-05 8.1122E-05 5.1660E-06 2.7482E-05 1.2151E-06 0.333 4.4881E-02 2.9178E-03 1.0566E-02 6.8691E-04 4.3965E-02 1.9365E-03 0.500 8.7321E-02 5.6974E-03 2.0557E-02 1.3413E-03 1.1657E-01 5.1307E-03 0.500 8.7546E-02 5.7157E-03 2.0610E-02 1.3456E-03 1.1662E-01 5.1330E-03 0.678 6.2376E-01 5.4645E-02 1.4684E-01 1.2864E-02 5.5688E-01 2.8965E-02 0.978 1.0277E+00 1.0360E-01 2.4193E-01 2.4389E-02 1.8168E+00 1.0027E-01 1.278 1.1804E+00 1.3424E-01 2.7790E-01 3.1603E-02 2.8288E+00 1.6010E-01 1.578 1.2427E+00 1.5726E-01 2.9256E-01 3.7022E-02 3.4642E+00 2.0054E-01 1.878 1.2718E+00 1.7662E-01 2.9940E-01 4.1578E-02 3.8309E+00 2.2700E-01 2.000 1.2793E+00 1.8381E-01 3.0118E-01 4.3273E-02 3.9295E+00 2.3512E-01 2.400 1.2793E+00 1.8381E-01 3.0144E-01 4.3605E-02 4.1279E+00 2.5491E-01 2.700 1.2793E+00 1.8381E-01 3.0158E-01 4.3831E-02 4.2046E+00 2.6559E-01 3.000 1.2793E+00 1.8381E-01 3.0169E-01 4.4040E-02 4.2521E+00 2.7444E-01 3.300 1.2793E+00 1.8381E-01 3.0179E-01 4.4235E-02 4.2843E+00 2.8217E-01 3.600 1.2793E+00 1.8381E-01 3.0187E-01 4.4416E-02 4.3080E+00 2.8917E-01 3.900 1.2793E+00 1.8381E-01 3.0195E-01 4.4586E-02 4.3268E+00 2.9562E-01 4.200 1.2793E+00 1.8381E-01 3.0201E-01 4.4744E-02 4.3425E+00 3.0161E-01 4.500 1.2793E+00 1.8381E-01 3.0207E-01 4.4893E-02 4.3559E+00 3.0722E-01 4.800 1.2793E+00 1.8381E-01 3.0212E-01 4.5032E-02 4.3677E+00 3.1247E-01 5.100 1.2793E+00 1.8381E-01 3.0217E-01 4.5162E-02 4.3781E+00 3.1740E-01 5.400 1.2793E+00 1.8381E-01 3.0221E-01 4.5285E-02 4.3873E+00 3.2204E-01 5.700 1.2793E+00 1.8381E-01 3.0225E-01 4.5400E-02 4.3956E+00 3.2640E-01 6.000 1.2793E+00 1.8381E-01 3.0229E-01 4.5509E-02 4.4030E+00 3.3051E-01 6.300 1.2793E+00 1.8381E-01 3.0232E-01 4.5612E-02 4.4097E+00 3.3438E-01 6.600 1.2793E+00 1.8381E-01 3.0235E-01 4.5708E-02 4.4156E+00 3.3803E-01 6.900 1.2793E+00 1.8381E-01 3.0237E-01 4.5800E-02 4.4210E+00 3.4148E-01 7.200 1.2793E+00 1.8381E-01 3.0239E-01 4.5886E-02 4.4259E+00 3.4473E-01 7.500 1.2793E+00 1.8381E-01 3.0242E-01 4.5968E-02 4.4303E+00 3.4781E-01 7.800 1.2793E+00 1.8381E-01 3.0243E-01 4.6045E-02 4.4342E+00 3.5073E-01 8.000 1.2793E+00 1.8381E-01 3.0244E-01 4.6095E-02 4.4366E+00 3.5259E-01 8.300 1.2793E+00 1.8381E-01 3.0245E-01 4.6165E-02 4.4395E+00 3.5508E-01 8.600 1.2793E+00 1.8381E-01 3.0246E-01 4.6233E-02 4.4414E+00 3.5716E-01 8.900 1.2793E+00 1.8381E-01 3.0247E-01 4.6297E-02 4.4428E+00 3.5892E-01 9.200 1.2793E+00 1.8381E-01 3.0247E-01 4.6358E-02 4.4439E+00 3.6044E-01 9.500 1.2793E+00 1.8381E-01 3.0248E-01 4.6416E-02 4.4448E+00 3.6177E-01 9.800 1.2793E+00 1.8381E-01 3.0248E-01 4.6471E-02 4.4456E+00 3.6294E-01 10.100 1.2793E+00 1.8381E-01 3.0249E-01 4.6524E-02 4.4463E+00 3.6399E-01 10.400 1.2793E+00 1.8381E-01 3.0249E-01 4.6575E-02 4.4470E+00 3.6494E-01 24.000 1.2793E+00 1.8381E-01 3.0253E-01 4.7797E-02 4.4529E+00 3.8293E-01 96.000 1.2793E+00 1.8381E-01 3.0253E-01 4.8066E-02 4.4529E+00 3.9017E-01
CA06449 Rev.000 Page 75 720.000 1.2793E+00 1.8381E-01 3.0253E-01 4.8542E-02 4.4529E+00 3.9677E-01 Worst Two-Hour Doses EAB Time Whole Body Thyroid TEDE (hr)
(rem)
(rem)
(rem) 0.0 1.1664E-01 1.2793E+00 1.8381E-01
CA06449 Rev.000 Page 76 ATTACHMENT G RELEASE FRACTION AND TIMING FILE MHARWT.RFT Release Fraction and Timing Name:
PWR, RG 1.183, Table 2 Section 3.2 Duration (h):
Design Basis Accident 0.5000E+00 0.1300E+01 O.OOOOE+00 O.OOOOE+00 Noble Cases:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Iodine:
O.5000E-01 0.3500E+00 O.OOOOE+00 O.OOOOE+00 Cesium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Tellurium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Strontium:
O.OOOOE+00 D.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Barium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Ruthenium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Cerium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Lanthanum:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Non-Radioactive Aerosols (kg):
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 End of Release File
CA06449 Rev.OOO Page 77 ATTACHMENT H OUTPUT FILE MHARWT.oO Cumulative Dose Summary eab lpz cr Time Thyroid TEDE Thyroid (hr) 0.000 0.333 0.500 0.533 0.933 1.233 1.533 1.800 2.000 2.300 2.600 2.900 3.200 3.500 3.800 4.100 4.400 4.700 5.000 5.300 5.600 5.900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 24.000 96.000 720.000 (rem)
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 2.1444E-05 8.3988E-05 2.0850E-04 3.8707E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 5.7048E-04 (rem)
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 7.5637E-07 2.9410E-06 7.2542E-06 1.3397E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 1.9676E-05 (rem)
O.OOOOE+00 O.OOOOE+00 0.000E+00 O.OOOOE+00 5.0484E-06 1.9772E-05 4.9084E-05 9.1123E-05 1.3430E-04 1.3975E-04 1.4668E-04 1.5509E-04 1.6494E-04 1.7624E-04 1.8896E-04 2.0309E-04 2.1862E-04 2.3553E-04 2.5382E-04 2.7347E-04 2.9447E-04 3.1680E-04 3.4046E-04 3.6543E-04 3.9170E-04 4.1926E-04 4.4811E-04 4.7822E-04 5.0960E-04 5.2637E-04 5.4379E-04 5.6183E-04 5.8051E-04 5.9980E-04 6.1972E-04 6.4024E-04 6.6137E-04 2.1965E-03 8.3368E-03 6.0210E-02 TEDE (rem)
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.7806E-07 6.9237E-07 1.7078E-06 3.1539E-06 4.6321E-06 4.8177E-06 5.0525E-06 5.3357E-06 5.6664E-06 6.0438E-06 6.4673E-06 6.9362E-06 7.4500E-06 8.0082E-06 8.6101E-06 9.2553E-06
- 9. 9433E-06 1.0674E-05 1.1446E-05 1.2259E-05 1.3114E-05 1.4009E-05 1.4945E-05 1.5920E-05 1.6935E-05 1.7497E-05 1.8078E-05 1.8680E-05 1.9302E-05 1.9943E-05 2.0604E-05 2.1284E-05 2.1983E-05 7.1616E-05 2.6201E-04 1.8560E-03 Thyroid (rem)
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 2.8127E-05 1.5907E-04 4.8709E-04 1.0247E-03 1.6243E-03 2.8040E-03 4.3163E-03 6.2106E-03 8.5087E-03 1.1219E-02 1.4343E-02 1.7880E-02 2.1828E-02 2.6183E-02 3.0942E-02 3.6101E-02 4.1657E-02 4.7607E-02 5.3946E-02 6.0673E-02 6.7782E-02 7.5272E-02 8.3138E-02 9.1378E-02 9.9989E-02 1.0735E-01 1.1291E-01 1.1766E-01 1.2211E-01 1.2647E-01 1.3087E-01 1.3536E-01 1.3996E-01 4.7922E-01 2.2601E+00 1.0811E+01 TEDE (rem)
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 8.9224E-07 5.0391E-06 1.5412E-05 3.2391E-OS 5.1311E-05 8.8498E-05 1.3612E-04 1.9571E-04 2.6794E-04 3.5304E-04 4.5107E-04 5.6198E-04 6.8567E-04 8.2204E-04 9.7096E-04 1.1323E-03 1.3060E-03 1.4919E-03 1.6899E-03 1.8998E-03 2.1216E-03 2.3552E-03 2.6004E-03 2.8572E-03 3.1254E-03 3.3546E-03 3.5276E-03 3.6756E-03 3.8139E-03 3.9496E-03 4.0864E-03 4.2259E-03 4.3689E-03 1.4857E-02 6.9322E-02 3.2979E-01 Worst Two-Hour Doses
CA06449 Rev.000 Page 78 eab Time Whole Body Thyroid (hr)
(rem)
(rem) 0.0 1.7537E-06 5.7048E-04 TEDE (rem) 1.9676E-05
CA06449 Rev. OOO Page 79 ATTACHMENT I NUCLEAR INVENTORY FILE PRI 14.NIF Nuclide Inventory Name:
Normalized MACCS Sample 3412 MWth PWR Core Inventory Power Level:
0.1000E+01 Nuclides:
14 Nuclide 001:
Kr-85 1
0.3382974720E+09 0.8500E+02 7.9975E+03 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 002:
Kr-85m 1
0.1612800000E+05 0.8500E+02 4.1975E+02 Kr-85 0.2100E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 003:
Kr-87 1
0.4578000000E+04 0.8700E+02 2.4238E+02 Rb-87 0.1000E+01 none 0.0000E+00 none O.OOOOE+00 Nuclide 004:
Kr-88 1
0.1022400000E+05 0.8800E+02 7.5473E+02 Rb-88 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 005:
I-131 2
0.6946560000E+06 0.1310E+03 8.0357E+01 Xe-131m 0.11OOE-01 none O.OOOOE+00
CA06449 Rev. 000 Page 80 none O.OOOOE+00 Nuclide 006:
1-132 2
0.8280000000E+04 0.1320E+03 2.6686E+01 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 007:
1-133 2
0.7488000000E+05 0.1330E+03 1.1319E+02 Xe-133m 0.2900E-01 Xe-133 0.9700E+00 none O.OOOOE+00 Nuclide 008:
I-134 2
0.3156000000E+04 0.1340E+03 1.5266E+01 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 009:
I-135 2
0.2379600000E+05 0.1350E+03 6.2112E+01 Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none O.OOOOE+00 Nuclide 010:
Xe-133 1
0.4531680000E+06 0.1330E+03 8.2574E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 011:
Xe-135 1
0.3272400000E+05 0.1350E+03 1.9726E+03 Cs-135 0.1000E+01 none O.OOOOE+00
CA06449 Rev.OOO Page 81 none O.OOOOE+00 Nuclide 012:
Xe-133m 1
0.1892200000E+06 0.1330E+03 1.1764E+03 Xe-133 O.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 013:
Xe-135m 1
0.9180000000E+03 0.1350E+03 2.5814E+02 Xe-135 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 014:
Xe-138 1
0.8460000000E+03 0.1380E+03 1.3622E+02 none O.OOOOE+00 none O.OOOOE+00 none 0.OOOOE+00 End of Nuclear Inventory File
CA06449 Rev.000 Page 82 ATTACHMENT J RELEASE FRACTION AND TIMING FILE MHAHP.RFT Release Fraction and Timing Name:
PWR, RG 1.183, Table 2 Section 3.2 Duration (h):
Design Basis Accident O.OOOlE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Noble Gases:
1.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Iodine:
l.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Cesium:
O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Tellurium:
O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Strontium:
O.OOOOE+OO O.OOOOE+00 O.OOOOE+OO O.OOOOE+OO Barium:
O.OOOOE+OO O.OOOOE+00 O.OOOOE+OO O.OOOOE+OO Ruthenium:
O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Cerium:
O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Lanthanum:
O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Non-Radioactive Aerosols (kg):
O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO End of Release File
CA06449 Rev.OOO Page 83 ATTACHMENT K CONVERSION FACTORS FILE FGRI4.INP FGRDCF 10/24/95 Implicit daughter 9 ORGANS 03:24:50 beta-test version 1.10, minor FORTRAN fixes 5/4/95 halflives (m) less than 90 and less than 0.100 of parent DEFINED IN THIS FILE:
GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR) 14 NUCLIDES DEFINED IN THIS FILE:
Kr-85 Kr-85m Kr-87 Kr-88 I-131 I-132 I-133 1-134 I-135 Xe-133 Xe-135 Xe-133m Xe-135m Xe-138 D
D D
D D
Including:Xe-135m CLOUDSHINE GROUND GROUND GROUND INHALED SHINE 8HR SHINE 7DAY SHINE RATE ACUTE Kr-85 GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR)
Kr-85m GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR)
Kr-87 1.170E-16 1.340E-16 1.140E-16 1.090E-16 2.200E-16 1.180E-16 1.090E-16 1.190E-16 1.320E-14 7.310E-15 8.410E-15 7.040E-15 6.430E-15 1.880E-14 7.330E-15 6.640E-15 7.480E-15 2.240E-14 8.121E-14 7.891E-14 7.056E-14 6.998E-14 1.287E-13 7.459E-14 6.941E-14 7.603E-14 2.304E-l1 2.594E-12 2.527E-12 2.379E-12 2.346E-12 5.286E-12 2.395E-12 2.313E-12 2.511E-12 2.247E-11 1.704E-12 1.656E-12 1.481E-12 1.469E-12 2.702E-12 1.565E-12 1.457E-12 1.596E-12 4.835E-10 3.653E-12 3.560E-12 3.351E-12 3.304E-12 7.446E-12 3.374E-12 3.257E-12 3.537E-12 3.164E-ll 2.820E-18-1.OOOE+00 2.740E-18-1.OOOE+00 2.450E-18-1.OOOE+00 2.430E-18-1.000E+00 4.470E-18-1.OOOE+00 2.590E-18-1.000E+00 2.410E-18-1.OOOE+00 2.640E-18-1.OOOE+00 8.000E-16-1.OOOE+00 1.570E-16-1.OOOE+00 1.530E-16-1.OOOE+00 1.440E-16-1.OOOE+00 1.420E-16-1.OOOE+00 3.200E-16-1.OOOE+00 1.450E-16-1.OOOE+00 1.400E-16-1.OOOE+00 1.520E-16-1.000E+00 1.360E-15-1.OOOE+00 INHALED CHRONIC 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 INGESTION 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00
CA06449 Rev.000 Page 84 GONADS 4.OOOE-14 4.962E-12 5.026E-12 7.610E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO BREAST 4.500E-14 4.740E-12 4.802E-12 7.270E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS 4.040E-14 4.603E-12 4.663E-12 7.060E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR 4.000E-14 4.708E-12 4.769E-12 7.220E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO BONE SUR 6.020E-14 6.514E-12 6.598E-12 9.990E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO THYROID 4.130E-14 4.473E-12 4.531E-12 6.860E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER 3.910E-14 4.590E-12 4.650E-12 7.040E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO EFFECTIVE 4.120E-14 4.773E-12 4.835E-12 7.320E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO SKIN(FGR) 1.370E-13 8.802E-11 8.916E-11 1.350E-14-1.OOOE+OO O.OOOE+OO O.OOOE+OO Kr-88 GONADS 9.900E-14 2.278E-11 2.655E-11 1.800E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO BREAST 1.110E-13 2.177E-11 2.537E-11 1.720E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS 1.OlOE-13 2.139E-11 2.493E-11 1.690E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR 1.OOOE-13 2.190E-11 2.552E-11 1.730E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO BONE SUR 1.390E-13 2.886E-11 3.363E-11 2.280E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO THYROID 1.030E-13 2.012E-11 2.345E-11 1.590E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER 9.790E-14 2.139E-11 2.493E-11 1.690E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO EFFECTIVE 1.020E-13 2.202E-11 2.567E-11 1.740E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO SKIN(FGR) 1.350E-13 5.607E-11 6.534E-11 4.430E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO I-131 GONADS 1.780E-14 1.119E-11 1.789E-10 3.940E-16-1.OOOE+00 2.530E-11 4.070E-11 BREAST 2.040E-14 1.082E-11 1.730E-10 3.810E-16-1.OOOE+00 7.880E-11 1.210E-10 LUNGS 1.760E-14 1.016E-11 1.626E-10 3.580E-16-1.OOOE+00 6.570E-10 1.020E-10 RED MARR 1.680E-14 1.022E-11 1.635E-10 3.600E-16-1.OOOE+00 6.260E-11 9.440E-11 BONE SUR 3.450E-14 1.675E-11 2.679E-10 5.900E-16-1.OOOE+00 5.730E-11 8.720E-11 THYROID 1.810E-14 1.053E-11 1.685E-10 3.710E-16-1.OOOE+00 2.920E-07 4.760E-07 REMAINDER 1.670E-14 9.908E-12 1.585E-10 3.490E-16-1.OOOE+00 8.030E-11 1.570E-10 EFFECTIVE 1.820E-14 1.067E-11 1.707E-10 3.760E-16-1.OOOE+00 8.890E-09 1.440E-08 SKIN(FGR) 2.980E-14 1.825E-11 2.920E-10 6.430E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO I-132 GONADS 1.090E-13 2.523E-11 2.771E-11 2.320E-15-1.OOOE+00 9.950E-12 2.330E-11 BREAST 1.240E-13 2.414E-11 2.652E-11 2.220E-15-1.OOOE+00 1.410E-11 2.520E-11 LUNGS 1.090E-13 2.30SE-11 2.532E-11 2.120E-15-1.OOOE+00 2.710E-10 2.640E-11 RED MARR 1.070E-13 2.360E-11 2.592E-11 2.170E-15-1.OOOE+00 1.400E-11 2.460E-11 BONE SUR 1.730E-13 3.327E-11 3.655E-11 3.060E-15-1.OOOE+00 1.240E-11 2.190E-11 THYROID 1.120E-13 2.381E-11 2.616E-11 2.190E-15-1.OOOE+00 1.740E-09 3.870E-09 REMAINDER 1.050E-13 2.283E-11 2.509E-11 2.100E-15-1.OOOE+00 3.780E-11 1.650E-10 EFFECTIVE 1.120E-13 2.403E-11 2.640E-11 2.210E-15-1.OOOE+00 1.030E-10 1.820E-10 SKIN(FGR) 1.580E-13 8.199E-11 9.007E-11 7.540E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO I-133 GONADS 2.870E-14 1.585E-11 6.748E-11 6.270E-16-1.OOOE+00 1.950E-11 3.630E-11 BREAST 3.280E-14 1.519E-11 6.468E-11 6.010E-16-1.OOOE+00 2.940E-11 4.680E-11 LUNGS 2.860E-14 1.446E-11 6.156E-11 5.720E-16-1.OOOE+00 8.200E-10 4.530E-11 RED MARR 2.770E-14 1.466E-11 6.242E-11 5.800E-16-1.OOOE+00 2.720E-11 4.300E-11 BONE SUR 4.870E-14 2.161E-11 9.202E-11 8.550E-16-1.OOOE+00 2.520E-11 4.070E-11 THYROID 2.930E-14 1.502E-11 6.393E-11 5.940E-16-1.OOOE+00 4.860E-08 9.100E-08 REMAINDER 2.730E-14 1.418E-11 6.038E-11 5.610E-16-1.OOOE+00 5.OOOE-11 1.550E-10 EFFECTIVE 2.940E-14 1.509E-11 6.425E-11 5.970E-16-1.OOOE+00 1.580E-09 2.800E-09 SKIN(FGR) 5.830E-14 1.150E-10 4.897E-10 4.550E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO I-134 GONADS 1.270E-13 1.200E-11 1.202E-11 2.640E-15-1.OOOE+00 4.250E-12 1.100E-11 BREAST 1.440E-13 1.145E-11 1.147E-11 2.520E-15-1.OOOE+00 6.170E-12 1.170E-11 LUNGS 1.270E-13 1.100E-11 1.102E-11 2.420E-15-1.OOOE+00 1.430E-10 1.260E-11 RED MARR 1.250E-13 1.127E-11 1.129E-11 2.480E-15-1.OOOE+00 6.080E-12 1.090E-11
CA06449 Rev.000 Page 85 BONE SUR 1.960E-13 1.568E-11 1.571E-11 3.450E-15-1.OOOE+00 5.310E-12 9.320E-12 THYROID 1.300E-13 1.127E-11 1.129E-11 2.480E-15-1.OOOE+00 2.880E-10 6.210E-10 REMAINDER 1.220E-13 1.091E-11 1.093E-11 2.400E-15-1.OOOE+00 2.270E-11 1.340E-10 EFFECTIVE 1.300E-13 1.150E-11 1.152E-11 2.530E-15-1.OOOE+00 3.550E-11 6.660E-11 SKIN(FGR) 1.870E-13 4.477E-11 4.485E-11 9.850E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO I-135 GONADS 8.078E-14 3.113E-11 5.489E-11 1.599E-15-1.OOOE+00 1.700E-11 3.610E-11 BREAST 9.143E-14 2.971E-11 5.240E-11 1.526E-15-1.OOOE+00 2.340E-11 3.850E-11 LUNGS 8.145E-14 2.886E-11 5.089E-11 1.482E-15-1.OOOE+00 4.410E-10 3.750E-11 RED MARR 8.054E-14 2.96SE-11 5.228E-11 1.523E-15-1.OOOE+00 2.240E-11 3.650E-l1 BONE SUR 1.184E-13 3.983E-11 7.024E-11 2.046E-15-1.OOOE+00 2.010E-11 3.360E-11 THYROID 8.324E-14 2.852E-11 5.030E-11 1.465E-15-1.OOOE+00 8.460E-09 1.790E-08 REMAINDER 7.861E-14 2.883E-11 5.084E-11 1.481E-15-l.OOOE+00 4.700E-11 1.54OE-10 EFFECTIVE 8.294E-14 2.989E-11 5.271E-11 1.535E-15-1.OOOE+00 3.320E-10 6.080E-10 SKIN(FGR) 1.156E-13 9.826E-11 1.733E-10 5.047E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO Xe-133 GONADS 1.610E-15 1.46SE-12 2.052E-11 5.200E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO BREAST 1.960E-15 1.50SE-12 2.107E-11 5.340E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS 1.320E-15 1.04SE-12 1.464E-11 3.710E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR 1.070E-15 8.791E-13 1.231E-11 3.120E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO BONE SUR 5.130E-15 4.254E-12 5.958E-11 1.510E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO THYROID 1.510E-15 1.181E-12 1.653E-11 4.190E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER 1.240E-15 1.042E-12 1.460E-11 3.700E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO EFFECTIVE 1.560E-15 1.299E-12 1.819E-11 4.610E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO SKIN(FGR) 4.970E-15 1.953E-12 2.734E-11 6.930E-17-1.OOOE+OO O.OOOE+OO O.OOOE+OO Xe-135 GONADS 1.170E-14 5.455E-12 1.194E-11 2.530E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO BREAST 1.330E-14 5.325E-12 1.166E-11 2.470E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS 1.130E-14 4.959E-12 1.086E-11 2.300E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR 1.070E-14 4.959E-12 1.086E-11 2.300E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO BONE SUR 2.570E-14 9.120E-12 1.997E-11 4.230E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO THYROID 1.180E-14 5.023E-12 1.100E-11 2.330E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER 1.080E-14 4.829E-12 1.058E-11 2.240E-16-1.OOOE+00 O.OOOE+OO O.OOOE+OO EFFECTIVE 1.190E-14 5.217E-12 1.142E-11 2.420E-16-1.OOOE+OO O.OOOE+OO O.OOOE+OO SKIN(FGR) 3.120E-14 4.506E-11 9.867E-11 2.090E-15-1.OOOE+OO O.OOOE+OO O.OOOE+OO Xe-133m GONADS 1.420E-15 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO BREAST 1.700E-15 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS 1.190E-15 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR 1.100E-15 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO BONE SUR 3.230E-15 O.OOOE+OO O.OOOE+OO O.OOOE+OO-l.OOOE+OO O.OOOE+OO O.OOOE+OO THYROID 1.360E-15 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER 1.150E-15 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO EFFECTIVE 1.370E-15 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO SKIN(FGR) 1.040E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO Xe-135m GONADS 2.OOOE-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+00 O.OOOE+OO O.OOOE+OO BREAST 2.290E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS 1.980E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR 1.910E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO BONE SUR 3.500E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO THYROID 2.040E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER 1.890E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO EFFECTIVE 2.040E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO
CA06449 Rev.OOO Page 86 SKIN(FGR) 2.970E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO Xe-138 GONADS 5.590E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO BREAST 6.320E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO LUNGS 5.660E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO RED MARR 5.600E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO BONE SUR 8.460E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO THYROID 5.770E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO REMAINDER 5.490E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO EFFECTIVE 5.770E-14 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO SKIN(FGR) 1.070E-13 O.OOOE+OO O.OOOE+OO O.OOOE+OO-1.OOOE+OO O.OOOE+OO O.OOOE+OO
CA06449 Rev.OOO Page 87 ATTACHMENT L OUTPUT FILE MHAHP.oO Cumulative Dose Summary eab lpz cr Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr)
(rem)
(rem)
(rem)
(rem)
(rem)
(rem) 0.000 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.0000E+00 O.OOOOE+00 O.OOOOE+00 0.008 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 9.2724E-06 4.0590E-07 0.333 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 6.5925E-04 2.8660E-05 0.733 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.1150E-03 4.9979E-05 1.033 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.2591E-03 5.8429E-05 1.333 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3289E-03 6.3691E-05 1.633 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3627E-03 6.7160E-05 1.933 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3791E-03 6.9563E-05 2.000 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3814E-03 6.9996E-05 2.300 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3881E-03 7.1615E-05 2.600 2.6607E-04 6.4918E-05 6.2637E-OS 1.5283E-OS 1.3914E-03 7.2825E-OS 2.900 2.6607E-04 6.4918E-OS 6.2637E-05 1.5283E-05 1.3930E-03 7.3746E-05 3.200 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3937E-03 7.4457E-05 3.500 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3941E-03 7.5011E-05 3.800 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3943E-03 7.5445E-05 4.100 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3944E-03 7.5786E-05 4.400 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3944E-03 7.6055E-05 4.700 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3944E-03 7.6267E-05 5.000 2.6607E-04 6.4918E-OS 6.2637E-05 1.5283E-05 1.3945E-03 7.6435E-05 5.300 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.6568E-0S 5.600 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.6674E-05 5.900 2.6607E-04 6.4918E-OS 6.2637E-OS 1.5283E-05 1.3945E-03 7.6758E-05 6.200 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.6824E-05 6.500 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.6877E-05 6.800 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.394SE-03 7.6919E-05 7.100 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.6952E-05 7.400 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.6979E-05 7.700 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.7000E-05 8.000 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.7017E-05 8.300 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.7031E-05 8.600 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-OS 1.3945E-03 7.7041E-05 8.900 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.7050E-05 9.200 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.7057E-05 9.500 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.7062E-05 9.800 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.7067E-OS 10.200 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.7070E-05 10.400 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.7073E-05 24.000 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.7084E-05 96.000 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.7084E-05 720.000 2.6607E-04 6.4918E-05 6.2637E-05 1.5283E-05 1.3945E-03 7.7084E-05
- wo-#HourDoe###########################
Worst Two-Hour Doses
CA06449 Rev.OOO Page 88 eab Time Whole Body Thyroid TEDE (hr)
(rem)
(rem)
(rem) 0.0 5.665BE-05 2.6607E-04 6.4918E-05
CA06449 Rev.OOO Page 89 ATTACHMENT M ETP-97-064R CONTROL ROOM INLEAKAGE RESULTS
i
-10 CALVERT CLIFFS NUCLEAR POWER PLANT TErPI4MIlrAI PJpnCEDuRE C45o-il
&Y-0 4150 '
At...
ENGiNEERING TEST PROCEDURE UNIT 0 ETP 97-064R CONTROL ROOM HVAC SYSTEM INLEAKAGE TEST REVISION 0 Effective Date Safety Related X.-.
Non-Safety Relate.d Writer: D. T. McElheny Sponsor V. P. Spunar GOPY
FT-86CRiv.l 10197)
AC09
- 7.
NUCON International, Inc.
Page37 f r7 Decay TestfData Beginnigcpncent.-ion
-l.o9wb Ending concentration (C(O)):
27wMb Time at start of test:-. _..
ieuze Time at end of test:
J )1 hoi Sample time intervals:
1.5 15.mbTu ro" for decay test was at 01:15 hours on 18 Nov 97.
lirs on 19Nov 97
!e excent for last sam-nle Time I Sample Concentration Time/Cone.
01:151 19.0 01:3001 14.
01:451 12.1 02:ff0/ 83
. -02.15f 6-7 '
02:301 5.1 03:12/ 2.7 TixnVConc.
I t
/
_/
Time/Conc.
I.
/
/
- I.
/
(A) Air Change Rate (C/nmin) 0.0170 (Q) Inleakage Flow Rate (CFL1 43 00
.s 95% Confidence Limit (A)"
0.0170 :+ 00192
- 95% Confidence Interval.
4000
< Q < 4600 Coxnments: Deciv samivles taken at a sample vort on the discharize -of 91 l1Iretu= fan. All samp~le concentrations inX the PPy range.
2 m
sa-Test nersofiel si Pnaturets) and date: NUCON Intemational Inc...
x-
-
jT-86 (Rev. 1 10/97)
A CU #12 Attacment 2 NUCON Internationol, Inc.
Page37of40 Decay Test Data
- Eiia~ted duration oftest
1.4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s
Beginning concentration (t):
40.5 rMb Ending concentration (C(O)):
14.2 ppb Time at start oftest:
Tine "zero" for decay test was at 23:16 hours on i9Nov97.
Time at endoftest:.
M-46ho= 20 Nov 97 Samuple timigintervals:
15 minute Time / Sample Concentration.
Time/Conc.
Time/Conc.
Time/Conc.
TimelCouc.
23:16/ 40.5 23 31/ 352
- 23:461 212 00:01 / 26.7 00:16/ 20.3 00:31/ 16.7 00:46/ 14.2
/
I I-
/
/~1~
/
/
I I~
I I
- /. I (A)Air Change Rate (1/min) 0.0118 (Q) Xnlealkage F1ow Rate (CFM?
95% Confidence Interval
- 2. 9Q0 cJQ < 3300 95% Confidence Limit (A)- QjgUR Q.QO.L Comments: Decay frm=1es takeh at a samnle port on the dischare off l12 retur
- n. Tbese samples were taken in c6iiunction vyith samples taken in CAS and on both CSR retum ducts.
The decay sample taken at 23:46 hoq s di-rarded due to a faulty Pas sample baa.
t
.s.
a Test persomiel signatr(s) and date:
CON International Inc.
c%4~'y9 /Ho CALVERT CLIFFS NUCLEAR POWER PLANT TECHNICAL PROCEDURE ENGINEERING TEST PROCEDURE UNIT 0 ETP 97-064R d
0 CONTROL ROOM HVAC SYSTEM INLEAKAGE TEST REVISION 0 Effective Date M//r/1'?T Safety Related X
Non-Safety Related Writer: D. T. Mc.Fheny Sponsor: V. P. Spunar
4-rk. /' 6A...VA
/-O
KZI
,b NUCON International, Inc.
P.O. BOX 29151 7000 HUNTLEY ROAD COLUMBUS, OHIO 43229 U.SA.
00..al"t T
,r P*sA
- ? L..
.W TELEPHONE: (614) 846-5710 OUTSIDE OHIO: 1-800-992-5192 FAX: (614) 431-0858 Control Room Inleakage Test Report performed for:
Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Station 1850 Calvert Cliffs Pkwv.
Lusby, Maryland 20657 P.O. No. 16582 20 April 1998 Distribution:
]3G&.
Dale McElheny (1)
NUCON:
12B3G847 MF (1)
Field Test (1)
QA..
(1)
Marketing
(;1)
NUCON 12BG847 /02
FT-86 (Rev. 1 10/97)
ACU#1I Trib 2Initial Characterization Test Page 37 of 40 I-ecay 'l est Data Estimated durationof test:
120 minutes Beginning concentration (Ct):
25.0 p~b Ending concentration (C(O)):
4.1 ppb Time at start of test:
Time "zero" for decay test was at 22:03 hrs. on 10 Feb 98 Time at end of test:
00:03 hrs. on 11 Feb 98 Sample time intervals:
20 minutes apart Time / Sample Concentration Time/Conc.
Time/Conc.
I Time/Cone.
Time/Conc.
22:03 / 25.0 22:23 117.9 22:43 / T 1.9 23:23 /9.0 23:43 /5.7 00:03 /4.1
/
.1 7-
/
/
I.
/
I..
/
'.1.*.
/
/
/
I.
/
.1 (A) Air Change Rate (1/min) 0;0143 95% Confidence Limit
- (A)= -
0.0143 4
- 0.0025 (Q) ITleakage Flow Rate (CFM) 3.600 9S% Confiden'ce Interval ZO0P
- 3000 c Qc4-r C.2 Alam Comnients: Decay sainvIes taken at a sample POrt on the discharge of ;411 retumn fan. All sample concentrations in the ppb range.
Ts person ia dae NUON.
Inc.
Test personnel signature(s) and date: NUJCON International Inc.
Page 37 of 40 FT-86 (Rev. 1 10/97)
ACU#12 Trip 2 Initial Charracterizaion Test Decay Test Data Estimated duration of test:
120 minutes Beginning concentration (Ct):
47 ppb Ending concentration (C(O)):
12.6 ppb Time at start of test:
Time "zero" for decay test was at 02:05 hrs. on 11 Feb 98 Time at end of test:
04:05 hrs. on II Feb 98 Sample time intervals:
20 minutes aprt Time I Sample Concentration
- Time/Conc.
_02:05 / 47.0
- 02:25/ 33.2
- 02.45 1 27A4
- 03:05/24.8
.03:25/21.4
. 03:45 / 16.1
- 04:05/'12.6 Time/Conc.
Time/Conc.
.. V
. I Tlmne/Conc.
/
//
/
/
/
/
.I
/
/
(A) Air Change Rate (l/mni)
(Q) Inleakage Flow Rate (CFM)
Comments: Decay samples taken at a sample port on the discha.rae of #12 return fan. All sample 0.0101 95% Confidence Limit
- 2550 95% Confidence Interval
- 2100<Q< 3000 (A)=
0.0101.
- 1+ 0,001*8 Cornments. Decayr sam-ples taken it a sample port on the discharge of W912 retlirn fan. All sample concentrations in the ppb range.
Test personnel signature(s) and date: NUCON International Inc.
164o6 Yi, '
Ito, 0 -
CALVERT CLIFFS NUCLEAR POWER PLANT TECHNICAL PROCEDURE ENGINEERING TEST PROCEDURE UNIT 0 ETP 97-064R CONTROL ROOM HVAC SYSTEM INLEAKAGE TEST
. REVISION 0
(
Effective Date.
1/ /77T Safety Related X
Non-Safety Related
'5?-1 i
WfiterDY.T.MUlheny Sponsor V. P. Spunar Appi
",W
.I wZ /e #4M.^-
7 6v'4 e W I
ne 3.g W //
NUCON International, Inc.
P.O. 8OX 29151 7000 HUNTLEY ROAD COLUMBUS, OHIO 43229 U.S.A.
TELEPHONE: (614) 84&5710
- OUTSIDE OHIO: 1-800-992-5192 FAX: (614) 43.-o858 Contifol Room Inleakage Test Report performed for:
Baltimore Gas and Electric Company Calveit Cliffs Nuclear Power Station 1850 Calvert Cliffs Pkyv.
Lusby, Maryland 20657
- .P.O. No. 16582 Distribution:
BG&E:
Dale Mc~heny(1)
- NUCON:
12BG847 EIF Field Test QA NMarketing (1)
(1) '
(1)
(1)
NUCON 1.2BG847 /02
C,~xe9
/S9 -
ACU#11 TriP 2 TesiwlfemvorwyModificaton In-place Page 37 of 40
.FT-86 (Rev. 1 10/97)
Decay Test Data Estimated duration of test: -
Beginning concentration (Ct):
- Ending concentration (C(O)):
Time at start of test:
Time at end of tdst:
Sample time intervals:
120 minutes 37.5vpb-9.2 pb Time "zero" for decay test was at 01:15 03:15 hrs on 12 Feb 98 20 minutes a-art hrs on 12 Feb.98 Time / Sample Concentration Time/Conc.
1:15 /37.5 1:35 128;1 1:55 /24.7 2:15 /19.3 2:35 /15.7 3:55
-/9-.2-3:15 / 9.2 Time/Conc.
- /
/
.I.
/
- TlmielConc.
/
.1
-/
- 1
./
Time/Conc.
./
I
/
I 1/--
(A) Air Change Rate (min-)
0.0115
- (O) Inleakage Flow Rate (CFE) 2.900 95/O ConfldencetLinit-95% C eidIntc a:
(A) = 0.0115 I 0010
- 2650 < Qc< 3150 Conmments: Decay samples taken at a sample port on the dischare of #l 1 return fan. All samrple concentrations in the ppb range.*
Test personnel signature(s) and date: NUCON International Inc.
FT-86 (Rev. 1 10/97)
ACU #12 Trip 2 Test wdTimporary Modificaion In-Diace z'Cqi.
/Oc 004t l
.. Attachment 2 Page37of40 Decay Test Data Estimated duration of test:
120 nInutes Beginning concentration (Ct):
37.5 PPb Ending concentration (C(O)):
9.2 Mtb Time at start of test:
Time "zero" for decay test was at 21:25 hrs. on II Feb 98 Time at end of test:
23:25 hrs. on 11 Feb 98 Sample time intervals:
20 minutes-apart Time / Sample Concentration
'Timne/Conc.
21:25 /37.6 21:45 /30.2 22:05 125.2 22:25 / 22.7 22:45/ 15.5
.23.:05..L13.4.4._.
23:25 110.5 Time/Conc.
I.
7I..
j.
Time/Conc.
/
/
/
Time/Conc.
I
.1{
I
/-I--_
/
(A) Air Change Rate ( 1/inin) 0.0109 (Q) Inleakage Flow Rate (CFM) 2.750 95%7Confidi5Limi.
95% Coinf denceliterval
(. )
0.0109 A.0015 2370 <Q< 3130 CommZ1ents: DeCaY sampleS taken at a samIple port On the discharge of412 retUrn fian. All SannPle concentrations in the tppb range.
Test personnel signature(s) and date: NUCON International Inc.
-CALVERT CLIFFS NUCLEAR POWER PLANT TECHNICAL PROCEDURE ENGINEERING TES
T. PROCEDURE
UNIT 0 ETP 97-064R CONTROL ROO HVAC SYSTEM INLEAKAGE TEST REVISION I
. 4
'2 ee7 SO..
IFes 1 q (IA, *{f'.
V w
Ps-Sl. 0 a Effective Date i// /
Safety Related X
Non-Safety Related CONTROLLED COPY Writer, D. T. McElheny Sponsor: T. R. Lupold
- G~o~y9 4rt' eA6i 10 t-ot
,-- -f f?
-Pa
-1t NUCON Internationol, Inc.
P.O. BOX 29151 7000 HUNTLEY ROAD COLUMMBUS, OH1O 43229 U.S.A.
TELEPHONE: (614) 846-5710 TOLL FREE: 1-800-992-5192 FAX: (614) 431-0858 WEB SITE: www.nucon-Tnt.com
_a.
no m Control Room Inleakage Test Report performed for:
Baltimore Gas and ElIectric Company Calvert Cliffs Nuclear Power Station 1850 Calvert Cliffs Pkwy.
Lusby, Maryland 20657 I.
P.O. No. 16582 3 March 2000
- I Distribution:
BG&E:
Dale McElheny (1)
NUCON:
12BG658 MY (1)
Field Test (1)
QA (1)
Marketing (1)
NUCON 12BG658 /01
FT-86 (Rev. 1 10/97)
BG&E ETP-97-064R-REVI PAv t5e-Oc Atfachment 2 Page 37 of 40 Decay Test Data Estimated duration of test:
180 mir Beginning concentration (Ct): 51.4 pib Ending concentration (C(O)):
13.2 pp Time at start of test:
Time" Time at end of test:
04:05 1 Sample time intervals:
15 min lutes eb eso zero" for decay test was at 0 1:05 hrs. on 26 Jan OQ_
Irs. on 26 Tan 00' utes apart
.. Time i.Sample Concentration Time/Cone.
I 30/ 51;4..
45/ 47.6_
60/41.9 75/ 33.0 90/ 30.7' 105/ 29.3-Time/Cone.
120/23.8 135/21.0
- 150/17.8 165/16.4 180/13.2
/
/
- Time/Conc.
. 1
//
/
/
Time/Cone.
/
I
/
(A) Air Change Rate ( 1/min)
(Q) lfeaklage Flow Rate (C}FM II I
0.00896
- 2600 95% Confidence Limit (A) =
0.00896
+.
0.00065.
- 95 % Confidence Interval 2400 c Q < 2800 Comments: Decay samples taken at a samiple port on the discharge of #12 return fan. All sampl concentrations in the ppb range.
44:.4
meet 7
3 W Test personnel signature(s) and date: NMCON Tnterna~nio1 T.-
- J,
f4tW /,OY FT-86 (Rev. 1. 10/97)
BG&E ETP-97-064R-REVI Attachinent 2 Page 37 of 40 Decay Test Data Estimated duration of test:
180 minutes
- Be ig conentration (C0). 59.2 npb Qa), 15 minutes into test Ending concentration (C(O)): 8.8 pb- ( 195 minutes into test Time at start of test: Time "zero" for deca' test was at 23:35 hrs. on 26 Jan 00 Time at end of test:
03:00 hrs. on 27 Jan 00 Sample time intervals: 15 minutes apart to 105 minutes then Qa 140. 165. and 195 minutes Time*1 Sample Concentration Time/Conc.
15/59.2 30/52.5
_ :45/42.8 60/40.2 75136.1 105 /26.2 140/17.4 Time/Conc.
- 165/13.8
- 195/8.8 I
/
/
. Time/Conc..
/
- /
Time/Comic.
- I.
/
- 1.
/
(A) Air Change Rate (1/min.
0.0103 (Q) Inleakage Flow-Rate (CEMED 3000 95% Confidence Limit (A)8
- 0.0103 0.00085
- -95 % Confidence Interval 2750 < Q < 3250 Comments: Decay samples taken at a sample port on the discharge of E1 1 return fan. All sample concentrations in the ppb range.
I-,'
Test personnel signature(s) and date: NUCON Intemnational Inc.
CA06449 Rev.000 Page 105 ATTACHMENT N ETP 01-035R PERFLUOROCARBON TRACER GAS TESTING
CALVERT CLIFFS NUCLEAR POWER PLANT TECHNICAL PROCEDURE ENGINEERING TEST PROCEDURE ETP 01-035R PERFLUOROCARBON TRACER GAS TESTING REVISION0 KEG6/t.k 7Z
- Effective Date I
- Safety Related
- Non-Safety Related x
Writer: D. T. McElheny Sponsor: M. A. Junge
- JUL29 '02 03-37PM BtqL -DRS/CD 426
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Lusby, MD 20657 II Z:
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I'm on vacation this w.eek butwantid t6 send aw te. iaal rl~sults but without m' y final asseismeni. Re aikably total'inleakage was 2930 : L8s cbM, Ober iwas, i w
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CA06449 Rev.000 Page 111 ATTACHMENT 0 CONTAINMENT TO PENETRATION ROOM LEAKAGE CALCULATION To calculate the fraction of containment leakage discharging into the penetration rooms, the area of the containment surface adjacent to the penetration rooms is compared against the area of the contrainment adjacent to the external environment and to the penetration rooms.
The containment is divided vertically into five sections:
(1) The first section are the penetration rooms.
Per Ref.45, the piping penetration rooms include the 5' west and east penetration rooms: Rooms 221 and 227 for Unit I and Rooms 211 and 206 for Unit 2. These rooms extend from 5' to 27' elevation.
Per Ref.46, the penetration rooms include the 27' west and east piping penetration rooms: Rooms 326 and 316 for Unit I and Rooms 321 and 310 for Unit 2. These rooms extend from 27' to 45' elevation.
Per Ref.47, the penetration rooms include the 45' west and ease electrical penetration rooms: Rooms 423 and 429 for Unit I and Rooms 414 and 404 for Unit 2. These rooms extend from 45' to 69' elevation.
Per Ref.48, rooms 221/326, 227/316, 211/321, and 206/310 are separated by metal gratings and are thus usually evaluated as single rooms.
Some additional areas in containment are adjacent to auxiliary building rooms, which are not directly serviced by the penetration room ventilation systems. During an MHA with a LOOP, any leakage from the containment into these auxiliary building rooms would either remain stagnant in those rooms or be drawn into the penetration rooms due to the negative pressure requirement. If auxiliary building ventilation was available, the activity would also be filtered and exit the auxiliary building out the ventilation stack. It is conservatively assumed in this work that all containment leakage to the auxiliary building passes through the penetration rooms and exits via the vent stacks.to the environment.
A5 = (215/360)*2*xI*65*(69-5) + (165/360)*2*x*65*(91.5-69) = 19821.92 ft2 (2) The area of the containment against the external environment from ground level at 45' to the 69' level can be deduced from the drawings in Ref.19. This area encompasses 1450 of the circumference.
A4 = (145/360)*2*F*65*(6945) = 3947.94 ft2 (3) The area of the containment against the external environment from the 69' level to the 91.5' level can be deduced from the drawings in Ref. 19. This area encompasses 1950 of the circumference.
A3 = (195/360)*2*r*65*(91.5-69) = 4977.46 ft2 (4) The area of the containment against the external environment from the 91.5' level to the 125.1042' level can be deduced from the drawings in Ref.19. This area encompasses 3600 of the circumference.
A2 = (3601360)*2*2r*65*(125.1042-91.5) = 13724.18 ft2 (5) The area of the containment against the external environment from the 125.1042' level to the 190.1042' level can be deduced from the drawings in Refs. 19 and 44. This area encompasses a hemisphere of - 65' radius.
Al = 2*ir*65*65 = 26546.46 ft2 (6) Thus, the fraction of the containment leakage which leaks into the penetration rooms is f=A5/(AI +A2+A3+A4+A5)=0.2872
CA06449 Rev.000 Page 112 ATTACHMENT P LOCAL LEAKRATE TEST RESULTS Per UFSAR 6.6.2, experience has shown that containment leakage is more likely at penetrations rather than through liner plates or weld joints. Penetration rooms are built adjacent to the outside surface of each containment and enclose the areas around the majority of the penetrations. The only penetrations which do not pass through these areas are:
the two main steam lines the two main feedwater lines the refueling tube penetration #67 the equipment hatch penetration #68 the personnel air lock (PAL) penetration # 69 the emergency air lock (EAL) penetration #13 the purge air inlet penetration # 14 the purge air outlet Per UFSAR 6.6.2, the main steam and feedwater lines are wvelded to the liner plate and are thus not considered as a source of leakage.
The refueling tube is valved on one end and blind flanged on the other end. Leakage through a blind flange is negligible.
Per UFSAR 5.1.4.4, the ventilation system purge penetrations are equipped with a testable double O-ring blind flange used for isolation purposes. The blind flange is used to provide containment integrity during Modes 1-4. The valve is manually opened for containment purging in Modes 5-6. Thus, containment leakage through the ventilation system purge penetrations in Modes 1-4 is negligible.
Leakage through the Personnel Air Lock, penetration # 68, is governed by TS 3.6.2, Containment Air Locks, which requires air lock leakage rate testing in accordance with the Containment Leakage Rate Testing Program. The Containment Leakage Rate Testing Program is described in TS 5.5.16 and requires an overall air lock leakage rate less than 0.05 of La, when tested at peak containment pressure.
Local Leakage Rate Testing (LLRT) is performed per the Containment Leakage Rate Testing Program (TS 5.5.16).
The results are listed below for the containment equipment hatch and for the EAL (Refs.49-58)
Penetration # 67 Penetration #69 pEuipment Hatch Emergency Air Lock sccm sc=
Unit 1 1975 0.0 1058.0 1976 0.0 3699.0 1977 8175.0 0.0 1978 0.0 0.0 1982 17.1 924.7 1985 73.6 7397.9 1988 38.6 7397.9 1992 27.4 9710.0 Unit 2 1979 5.6 2747.0 1982 4.0 905.0 1985 21.8 1850.0 1987 90.0 2312.0
CA06449 Rev.000 Page 113 1989 7.0 2774.0 1991 20.0 1
1387.0 Maximum Value 8175.0 9710.0 Based on a containmemt volume of 1.989E+06 ft3 (6B.08), a containment peak pressure of 50 psig (Refs.50-58), and a leakrate of 0.2%/day (Refs.50-58), the TS allowable containment leakrate La can be calculated to be 344370 sccm.
Thus, the maximum leak rates from the major penetrations to the environment can be summarized as 3% for penetration #67 the equipment hatch 5% for penetration #68 the personnel air lock (PAL) 3% for penetration # 69 the emergency air lock (EAL) 0% for penetration #13/14 the purge air inlet/outlet 0% for the main steam lines 0% for the main feedwater lines 0% for the refueling tube Thus, leakage from the containment to the environment has not exceeded 6% for the EH and EAL and is limited to 5% for the PAL. Even doubling these values for conservatism, it can be reasonably argued that 75% of containment leakage would wind up in the Auxiliary Building Penetration Rooms.
CA06449 Rev. 000 Page 114 ATTACHMENT Q MICROSHIELD CONTAINMENT SHINE SOURCE TERM MICROSHIELD Source Terms MWt 2754 CRCB Release CRCB Ci/MWt Fraction Ci Am-241 7.3183E+00 0.0002 4.0309E+00 Ba-139 5.1001 E+04 0.0200 2.8092E+06 Ba-140 5.2928E+04 0.0200 2.9153E+06 Ce-141 5.1883E+04 0.0005 7.1443E+04 Ce-143 4.4327E+04 0.0005 6.1039E+04 Ce-144 4.2317E+04, 0.0005 5.8270E+04 Cm-242 2.0078E+03 0.0002 1.1059E+03 Cm-244 3.1650E+02 0.0002 1.7433E+02 Co-58 8.0013E+02 0.0025 5.5089E+03 Co-60 9.8625E+02 0.0025 6.7903E+03 Cs-1 34 7.1917E+03 0.3000 5.9417E+06 Cs-136 1.7111 E+03 0.3000 1.4137E+06 Cs-1 37 4.7857E+03 0.3000 3.9540E+06 1-131 2.7562E+04 0.4000 3.0363E+07 1-132 3.9464E+04 0.4000 4.3473E+07 1-133 5.5715E+04 0.4000 6.1376E+07 1-134 6.2858E+04 0.4000 6.9244E+07 1-135 5.2964E+04 0.4000 5.8345E+07 Kr-85 3.7180E+02 1.0000 1.0239E+06 Kr-85m 7.9679E+03 1.0000 2.1944E+07 Kr-87 1.6208E+04 1.0000 4.4636E+07 Kr-88 2.2658E+04 1.0000 6.2400E+07 La-140 5.4255E+04 0.0002 2.9884E+04 La-141 4.6433E+04 0.0002 2.5576E+04 La-142 4.4898E+04 0.0002 2.4730E+04 Mo-99 5.0834E+04 0.0025 3.4999E+05 Nb-95 6.0839E+04 0.0002 3.351 OE+04 Nd-147 1.9151 E+04 0.0002 1.0548E+04 Np-239 5.5833E+05 0.0005 7.6881 E+05 Pr-143 4.6905E+04 0.0002 2.5835E+04 Pu-238 1.7259E+02 0.0005 2.3766E+02 Pu-239 1.1469E+01 0.0005 1.5793E+01 Pu-240 2.0026E+01 0.0005 2.7576E+01 Pu-241 4.9593E+03 0.0005 6.8289E+03 Rb-86 5.9034E+01 0.3000 4.8774E+04 Rh-105 2.8507E+04 0.0025 1.9627E+05 Ru-103 4.8774E+04 0.0025 3.3581 E+05 Ru-105 3.1455E+04 0.0025 2.1656E+05
CA06449 Rev.000 Page 115 Ru-106 1.9695E+04 0.0025 1.3560E+05 Sb-127 2.4299E+03 0.0500 3.3460E+05 Sb-129 8.7888E+03 0.0500 1.2102E+06 Sr-89 3.3293E+04 0.0200 1.8338E+06 Sr-90 3.1769E+03 0.0200 1.7498E+05 Sr-91 3.8931 E+04 0.0200 2.1443E+06 Sr-92 4.0190E+04 0.0200 2.2137E+06 Tc-99m 4.5425E+04 0.0025 3.1275E+05 Te-127 2.4665E+03 0.0500 3.3963E+05 Te-127m 4.6272E+02 0.0500 6.3716E+04 Te-129 8.4012E+03 0.0500 1.1569E+06 Te-129m 1.8872E+03 0.0500 2.5986E+05 Te-131m 5.0686E+03 0.0500 6.9795E+05 Te-132 3.8391 E+04 0.0500 5.2864E+06 Xe-133 5.5707E+04 1.0000 1.5342E+08 Xe-133m 1.7354E+03 1.0000 4.7793E+06 Xe-i 35 1.7708E+04 1.0000 4.8767E+07 Xe-135m 1.1635E+04 1.0000 3.2043E+07 Xe-138 4.9330E+04 1.0000 1.3585E+08 Y-90 3.4567E+03 0.0002 1.9040E+03 Y-91 4.2527E+04 0.0002 2.3424E+04 Y-92 4.0519E+04 0.0002 2.2318E+04 Y-93 2.9622E+04 0.0002 1.6316E+04 Zr-95 5.8246E+04 0.0002 3.2082E+04 Zr-97 4.9425E+04 0.0002 2.7223E+04
CA06449 Rev.000 Page 116 AITACHMENT R MICROSHIELD PLUME SHINE SOURCE TERM MICROSHIELD Plume Source Terms MWt 2754 Fraction 0.0248 CRCB Release CRCB CitMWt Fraction Ci Am-241 7.3183E+00 0.0002 9.9967E-02 Ba-139 5.1001E+04 0.0200 6.9667E+04 Ba-140 5.2928E+04 0.0200 7.2299E+04 Ce-141 5.1883E+04 0.0005 1.7718E+03 Ce-143 4.4327E+04 0.0005 1.5138E+03 Ce-144 4.2317E+04 0.0005 1.4451 E+03 Cm-242 2.0078E+03 0.0002 2.7426E+01 Cm-244 3.1650E+02 0.0002 4.3233E+00 Co-58 8.0013E+02 0.0025 1.3662E+02 Co-60 9.8625E+02 0.0025 1.6840E+02 Cs-134 7.1917E+03 0.3000 1.4736E+05 Cs-1 36 1.7111 E+03 0.3000 3.5060E+04 Cs-137 4.7857E+03 0.3000 9.8058E+04 1-131 2.7562E+04 0.4000 7.5299E+05 1-132 3.9464E+04 0.4000 1.0781 E+06 1-133 5.5715E+04 0.4000 1.5221 E+06 1-134 6.2858E+04 0.4000 1.7173E+06 1-135 5.2964E+04 0.4000 1.4470E+06 Kr-85 3.7180E+02 1.0000 2.5393E+04 Kr-85m 7.9679E+03 1.0000 5.4420E+05 Kr-87 1.6208E+04 1.0000 1.1070E+06 Kr-88 2.2658E+04 1.0000 1.5475E+06 La-140 5.4255E+04 0.0002 7.4112E+02 La-141 4.6433E+04 0.0002 6.3427E+02 La-142 4.4898E+04 0.0002 6.1330E+02 Mo-99 5.0834E+04 0.0025 8.6798E+03 Nb-95 6.0839E+04 0.0002 8.3104E+02 Nd-147 1.9151E+04 0.0002 2.6160E+02 Np-239 5.5833E+05 0.0005 1.9067E+04 Pr-143 4.69052+04 0.0002 6.4071 E+02 Pu-238 1.7259E+02 0.0005 5.8939E+00 Pu-239 1.1469E+01 0.0005 3.9167E-01 Pu-240 2.0026E+01 0.0005 6.8389E-01 Pu-241 4.9593E+03 0.0005 1.6936E+02 Rb-86 5.9034E+01 0.3000 1.2096E+03 Rh-105 2.8507E+04 0.0025 4.8676E+03 Ru-1 03 4.8774E+04 0.0025 8.3280E+03 Ru-105 3.1455E+04 0.0025 5.3708E+03
CA06449 Rev.000 Page 117 Ru-106 1.9695E+04 0.0025 3.3628E+03 Sb-127 2.4299E+03 0.0500 8.2980E+03 Sb-129 8.7888E+03 0.0500 3.0013E+04 Sr-89 3.3293E+04 0.0200 4.5478E+04 Sr-90 3.1769E+03 0.0200 4.3396E+03 Sr-91 3.8931 E+04 0.0200 5.3180E+04 Sr-92 4.0190E+04 0.0200 5.4899E+04 Tc-99m 4.5425E+04 0.0025 7.7561 E+03 Te-127 2.4665E+03 0.0500 8.4228E+03 Te-127m 4.6272E+02 0.0500 1.5802E+03 Te-129 8.4012E+03 0.0500 2.8690E+04 Te-129m 1.8872E+03 0.0500 6.4446E+03 Te-131m 5.0686E+03 0.0500 1.7309E+04 Te-132 3.8391 E+04 0.0500 1.3110E+05 Xe-133 5.5707E+04 1.0000 3.8048E+06 Xe-133m 1.7354E+03 1.0000 1.1853E+05 Xe-135 1.7708E+04 1.0000 1.2094E+06 Xe-135m 1.1 635E+04 1.0000 7.9466E+05 Xe-138 4.9330E+04 1.0000 3.3692E+06 Y-90 3A567E+03 0.0002 4.7218E+01 Y-91 4.2527E+04 0.0002 5.8091 E+02 Y-92 4.0519E+04 0.0002 5.5348E+02 Y-93 2.9622E+04 0.0002 4.0464E+02 Zr-95 5.8246E+04 0.0002 7.9563E+02 Zr-97 4.9425E+04 0.0002 6.7513E+02
CA06449 Rev.OOO Page 118 ATTACHMENT S MICROSHIELD CONTROL ROOM FILTER SHINE SOURCE TERM MICROSHIELD Fhitpr Sonurpc Terms MWt 2754 Fraction I
CRCB Release CRCB l
Ci/MWt Fraction I
Ci Am-241 7.31 83E+00 0.0002 4.0309E+00 Ba-139 5.001E+04 0.0200 2.8092E+06 Ba-140 5.2928E+04 0.0200 2.9153E+06 Ce-141 5.1883E+04 0.0005 7.1443E+04 Ce-143 4.4327E+04 0.0005 6.1039E+04 Ce-144 4.2317E+04 0.0005 5.8270E+04 Cm-242 2.0078E+03 0.0002 1.1059E+03 Cm-244 3.1650E+02 0.0002 1.7433E+02 Co-58 8.0013E+02 0.0025 5.5089E+03 Co-60 9.8625E+02 0.0025 6.7903E+03 Cs-134 7.1917E+03 0.3000 5.9417E+06 Cs-136 1.7111 E+03 0.3000 1.4137E+06 Cs-1 37 4.7857E+03 0.3000 3.9540E+06 1-131 2.7562E+04 0.4000 3.0363E+07 1-132 3.9464E+04 0.4000 4.3473E+07 1-133 5.5715E+04 0.4000 6.1376E+07 1-134 6.2858E+04 0.4000 6.9244E+07 1-135 5.2964E+04 0.4000 5.8345E+07 Kr-85 3.7180E+02 0.0000 0.OOOOE+00 Kr-85m 7.9679E+03 0.0000 0.OOOOE+00 Kr-87 1.6208E+04 0.0000 0.0000E+00 Kr-88 2.2658E+04 0.0000 0.OOOOE+00 La-140 5.4255E+04 0.0002 2.9884E+04 La-141 4.6433E+04 0.0002 2.5576E+04 La-142 4.4898E+04 0.0002 2.4730E+04 Mo-99 5.0834E+04 0.0025 3.4999E+05 Nb-95 6.0839E+04 0.0002 3.3510E+04 Nd-147 1.9151 E+04 0.0002 1.0548E+04 Np-239 5.5833E+05 0.0005 7.6881 E+05 Pr-143 4.6905E+04 0.0002 2.5835E+04 Pu-238 1.7259E+02 0.0005 2.3766E+02 Pu-239 1.1469E+01 0.0005 1.5793E+01 Pu-240 2.0026E+01 0.0005 2.7576E+01 Pu-241 4.9593E+03 0.0005 6.8289E+03 Rb-86 5.9034E+01 0.3000 4.8774E+04 Rh-1 05 2.8507E+04 0.0025 1.9627E+05 Ru-103 4.8774E+04 0.0025 3.3581E+05 Ru-105 3.1455E+04 0.0025 2.1656E+05
CA06449 Rev.000 Page 119 Ru-1 06 1.9695E+04 0.0025 1.3560E+05 Sb-127 2.4299E+03 0.0500 3.3460E+05 Sb-129 8.7888E+03 0.0500 1.2102E+06 Sr-89 3.3293E+04 0.0200 1.8338E+06 Sr-90 3.1769E+03 0.0200 1.7498E+05 Sr-91 3.8931 E+04 0.0200 2.1443E+06 Sr-92 4.0190E+04 0.0200 2.2137E+06 Tc-99m 4.5425E+04 0.0025 3.1275E+05 Te-127 2.4665E+03 0.0500 3.3963E+05 Te-127m 4.6272E+02 0.0500 6.3716E+04 Te-129 8.4012E+03 0.0500 1.1569E+06 Te-129m 1.8872E+03 0.0500 2.5986E+05 Te-131m 5.0686E+03 0.0500 6.9795E+05 Te-1 32 3.8391 E+04 0.0500 5.2864E+06 Xe-1 33 5.5707E+04 0.0000 O.OOOOE+00 Xe-1 33m 1.7354E+03 0.0000 O.OOOOE+00 Xe-135 1.7708E+04 0.0000 O.OOOOE+00 Xe-135m 1.1635E+04 0.0000 O.OOOOE+00 Xe-i 38 4.9330E+04 0.0000 O.OOOOE+00 Y-90 3.4567E+03 0.0002 1.9040E+03 Y-91 4.2527E+04 0.0002 2.3424E+04 Y-92 4.0519E+04 0.0002 2.2318E+04 Y-93 2.9622E+04 0.0002 1.6316E+04 Zr-95 5.8246E+04 0.0002 3.2082E+04 Zr-97 4.9425E+04 0.0002 2.7223E+04
CA06449 Rev.O000 Page 120 ATTACHMENT T MICROSHIELD CONTROL ROOM FILTER DOSES - PARTICULATE Microshield Control Room Filter Doses - Particulate I
I1rI Filter 9000 cfm Inflow 3500 cfm Time X/Q Fi Fc alpha fraction fraction DoseRates Dose Hr sec/m3 cfm per day per hr f1 f2 mR/hr Rem A
B C
D E
F G
H I
O 1.11 E-03 3500 0.0016 1.2223E-07 1
O.OOOOE+00 2.9060E+07 0.0000E+00 0.3333 1.11 E-03 3500 0.0016 1.2223E-07 0.231420171 1.5405E-08 2.9060E+07 1.4920E-04 0.5 1.11 E-03 3500 0.0016 1.2223E-07 0.111302896 1.7812E-08 2.9060E+07 2.3549E-04 0.75 1.11 E-03 3500 0.0016 1.2223E-07 0.037132971 1.9299E-08 2.9060E+07 3.7570E-04 1
1.11 E-03 3500 0.0016 1.2223E-07 0.012388335 1.9795E-08 2.1390E+07 4.8155E-04 2
1.11E-03 3500 0.0016 1.2223E-07 0.000153471 2.0040E-08 1.6960E+07 8.2143E-04 3
7.29E-04 3500 0.0016 8.0278E-08 1.90125E-06 2.0042E-08 1.4170E+07 1.1054E-03 4
7.29E-04 3500 0.0016 8.0278E-08 2.35533E-08 2.0042E-08 1.2230E+07 1.3505E-03 5
7.29E-04 3500 0.0016 8.0278E-08 2.91786E-10 2.0042E-08 1.0770E+07 1.5664E-03 6
7.29E-04 3500 0.0016 8.0278E-08 3.61474E-12 2.0042E-08 9.6070E+06 1.7589E-03 7
7.29E-04 3500 0.0016 8.0278E-08 4.47807E-14 2.0042E-08 8.6420E+06 1.9321 E-03 8
7.29E-04 3500 0.0016 8.0278E-08 5.54758E-16 2.0042E-08 7.8200E+06 2.0889E-03 9
3.19E-04 3500 0.0016 3.5129E-08 6.87253E-18 2.0042E-08 7.111 OE+06 2.2314E-03 12 3.19E-04 3500 0.0016 3.5129E-08 1.30664E-23 2.0042E-08 5.4650E+06 2.5600E-03 18 3.19E-04 3500 0.0016 3.5129E-08 4.72316E-35 2.0042E-08 3.5060E+06 2.9816E-03 24 3.19E-04 3500 0.0016 3.5129E-08 1.7073E-46 2.0042E-08 2.4910E+06 3.2811 E-03 25 2.36E-04 3500 0.0008 1.2994E-08 2.11506E-48 2.0042E-08 2.3760E+06 3.3287E-03 48 2.36E-04 3500 0.0008 1.2994E-08 2.914882-92 2.0042E-08 1.411 0E+06 3.9792E-03 72 2.36E-04 3500 0.0008 1.2994E-08 4.9766E-138 2.0042E-08 1.2950E+06 4.6021 E-03 96 2.36E-04 3500 0.0008 1.2994E-08 8.4965E-184 2.0042E-08 1.2550E+06 5.2057E-03 97 1.98E-04 3500 0.0008 1.0902E-08 1.0526E-185 2.0042E-08 1.2530E+06 5.2308E-03 120 1.98E-04 3500 0.0008 1.0902E208 1.4506E-229 2.0042E-08 1.2140E+06 5.7904E-03 240 1.98E-04 3500 0.0008 1.0902E-08 0
2.0042E-08 9.7470E+05 8.1346E-03 480 1.982-04 3500 0.0008 1.0902E208 0
2.0042E-08 6.2460E+05 1.1139E-02 720 1.98E-04 3500 0.0008 1.0902E-08 0
2.0042E-08 4.3690E+05 1.3241E-02
CA06449 Rev. 000 Page 121 ATTACHMENT U MICROSHIELD CONTROL ROOM FILTER DOSES - ELEMENTAL Microshield Control Room Filter Doses - Elemental Filter 9000 cfmr Inflow 3500 cfmr Time X/Q Fi Fc alpha fraction fraction DoseRates Dose Hr seclm3 cfm er da per hr f1 f2 mR/hr Rem A
B C
D E
F G
H I
0 1.11 E-03 3500 0.0016 1.2223E-07 0.0485 0.0000E+00 2.8040E+07 O.OOOOE+00 0.25 1.11 E-03 3500 0.0016 1.2223E-07 3.7990E-02 9.4678E-10 2.8040E+07 6.6369E-06 0.5 1.11 E-03 3500 0.0016 1.2223E-07 2.9757E-02 1.6884E-09 2.8040E+07 1.8472E-05 0.75 1.11 E-03 3500 0.0016 1.2223E-07 2.3308E-02 2.2693E-09 2.8040E+07 3.4380E-05 1
1.11 E-03 3500 0.0016 1.2223E-07 1.8257E-02 2.7243E-09 2.8040E+07 5.3477E-05 2
1.11 E-03 3500 0.0016 1.2223E-07 6.8727E-03 3.7498E-09 1.5910E+07 1.1314E-04 3
7.29E-04 3500 0.0016 8.0278E-08 2.5872E-03 4.0033E-09 1.3110E+07 1.6562E-04 4
7.29E-04 3500 0.0016 8.0278E-08 9.7391 E-04 4.0988E-09 1.1170E+07 2.1140E-04 5
7.29E-04 3500 0.0016 8.0278E-08 3.6662E-04 4.1347E-09 1.1170E+07 2.5759E-04 6
7.29E-04 3500 0.0016 8.0278E-08 1.3801 E-04 4.1482E-09 8.5570E+06 2.9309E-04 7
7.29E-04 3500 0.0016 8.0278E-08 5.1952E-05 4.1533E-09 8.5570E+06 3.2863E-04 8
7.29E-04 3500 0.0016 8.0278E-08 1.9557E-05 4.1553E-09 6.7750E+06 3.5678E-04 9
3.19E-04 3500 0.0016 3.5129E-08 7.3619E-06 4.1556E-09 6.0670E+06 3.8199E-04 12 3.19E-04 3500 0.0016 3.5129E-08 3.9271 E-07 4.1557E-09 4.4220E+06 4.3712E-04 18 3.19E-04 3500 0.0016 3.5129E-08 1.1175E-09 4.15582-09 2.4460E+06 4.9811 E-04 24 3.19E-04 3500 0.0016 3.5129E-08 3.1798E-12 4.1558E-09 1.4060E+06 5.3317E-04 25 2.36E-04 3500 0.0008 1.2994E-08 1.1970E-12 4.1558E-09 1.2870E+06 5.3852E-04 48 2.36E-04 3500 0.0008 1.2994E-08 2.0848E-22 4.1558E-09 2.3840E+05 5.6130E-04 72 2.36E-04 3500 0.0008 1.2994E-08 1.3669E-32 4.1558E-09 8.6230E+04 5.6990E-04 96 2.36E-04 3500 0.0008 1.2994E-08 8.9618E-43 4.1558E-09 4.7010E+04 5.7459E-04 97 1.98E-04 3500 0.0008 1.0902E-08 3.3736E-43 4.1558E-09 4.6050E+04 5.7478E-04 120 1.98E-04 3500 0.0008 1.0902E-08 5.8757E-53 4.1558E-09 3.0920E+04 5.7774E-04 240 1.98E-04 3500 0.0008 1.0902E-08 7.1182E-104 4.1558E-09 1.2960E+04 5.8420E-04 480 1.98E-04 3500 0.0008 1.0902E-08 1.0447E-205 4.1558E-09 5.3860E+03 5.8957E-04 720 1.98E-04 3500 0.0008 1.0902E-08 1.5333E-307 4.1558E-09 2.2740E+03 5.9184E-04
CA06449 Rev.OOo Page 122 ATTACHMENT V MICROSHIELD CONTROL ROOM FILTER DOSES - ORGANIC Microshield Control Room Filter Do es - Organic Filter 9000 cfm Inflow 3500 cfm Time XIQ Fi Fc alpha fraction fraction DoseRates Dose Hr seclm3 cfm per day per hr f1 f2 mRlhr Rem A
B C
D E
F G
H I
O 1.11 E-03 3500 0.0016 1.2223E-07 0.0015 O.OOOOE+00 2.8040E+07 0.00002+00 0.25 1.11 E-03 3500 0.0016 1.2223E-07 1.3826E-03 3.1694E-11 2.8040E+07 2.2218E-07 0.5 1.11 E-03 3500 0.0016 1.2223E-07 1.2744E-03 6.0908E-11 2.8040E+07 6.4914E-07 0.75 1.11 E-03 3500 0.0016 1.2223E-07 1.1746E-03 8.7835E-11 2.8040E+07 1.2649E-06 1
1.11 E-03 3500 0.0016 1.2223E-07 1.0827E-03 1.1265E-10 2.8040E+07 2.0546E-06 2
1.11 E-03 3500 0.0016 1.2223E-07 7.81SOE-04 1.9397E-10 1.5910E+07 5.1406E-06 3
7.29E-04 3500 0.0016 8.0278E-08 5.6409E-04 2.3252E-1 0 1.311 OE+07 8.1889E-06 4
7.29E-04 3500 0.0016 8.0278E-08 4.0717E-04 2.6034E-10 1.1 170E+07 1.1097E-05 5
7.29E-04 3500 0.0016 8.0278E-08 2.9389E-04 2.8042E-10 1.1170E+07 1.4229E-05 6
7.29E-04 3500 0.0016 8.0278E-08 2.1213E-04 2.9492E-10 8.5570E+06 1.6753E-05 7
7.29E-04 3500 0.0016 8.0278E-08 1.5312E-04 3.0538E-10 8.5570E+06 1.9366E-05 8
7.29E-04 3500 0.0016 8.0278E-08 1.1052E-04 3.1294E-10 6.7750E+06 2.1486E-05 9
3.19E-04 3500 0.0016 3.5129E-08 7.9776E-05 3.1532E-10 6.0670E+06 2.3399E-05 12 3.19E-04 3500 0.0016 3.5129E-08 3.0001 E-05 3.1918E-10 4.4220E+06 2.7633E-05 18 3.19E-04 3500 0.0016 3.5129E-08 4.2428E-06 3.2118E-10 2.4460E+06 3.2347E-05 24 3.19E-04 3500 0.0016 3.5129E-08 6.0003E-07 3.2146E-10 1.4060E+06 3.5059E-05 25 2.36E-04 3500 0.0008 1.2994E-08 4.3310E-07 3.2147E-10 1.2870E+06 3.5473E-05 48 2.36E-04 3500 0.0008 1.2994E-08 2.4002E-10 3.2148E-10 2.3840E+05 3.7235E-05 72 2.36E-04 3500 0.0008 1.2994E-08 9.6013E-14 3.2148E-10 8.6230E+04 3.7901E-05 96 2.36E-04 3500 0.0008 1.2994E-08 3.8407E-17 3.2148E-10 4.701 OE+04 3.8263E-05 97 1.98E-04 3500 0.0008 1.0902E-08 2.7722E-17 3.2148E-10 4.6050E+04 3.8278E-05 120 1.98E-04 3500 0.0008 1.0902E-08 1.5364E-20 3.2148E-10 3.0920E+04 3.8507E-05 240 1.98E-04 3500 0.0008 1.0902E-08 1.5736E-37 3.2148E-10 1.2960E+04 3.90072-05 480 1.98E-04 3500 0.0008 1.0902E-08 1.6508E-71 3.2148E-10 5.3860E+03 3.9422E-05 720 1.98E-04 3500 0.0008 1.0902E-08 1.7318E-105 3.2148E-10 2.2740E+03 3.9598E-05
CA06449 Rev.00O Page 123 ATTACHMENT W MICROSHIELD CONTAINMENT SHINE OUTPUT FILES
MicroShield v5.05 (5.05-00299)
CALVERT CLIFFS NUCLEAR POWER PLANT
- Yf 9 lV4,6 eg1C /zy File Ref
Page
- 1 DOS File: 1 Run Date: J Run Time: 3 Duration : 0
/1HA000.MS5 uly 20, 2005 3:43:37 PM
'0:00:07 Date:
By:
Checked:
C
==
Description:==
Geometry: 7 bN
- ase MH)
- Cy
Title:
MHA Shine A Shine outside containment
,linder Volume - Side Shields Hoight Radius Source Dimensions 5.5e+3 cm 181 ft 7.7 in 2.0e+3 cm 65 ft 0.0 in Dose Points
- 1 X
2712.72 cm 89ft Y
2773.68 cm 91 ft Shield Name Source Shield 1 Shield 2 Transition Shield 4 Air Gap Shields Dimension 2.41e+06 ft3
.021 ft 3.75 ft 9.15 ft 2.0ft Material Air Iron Concrete Air Concrete Air z
0cm 0.0 in Density 0.00122 7.86 2.35 0.00122 2.35 0.00122 Source Input Grouping Method: Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Excluded Nuclide Am-241 Ba-1 37m Ba-139 Ba-140 Ce-141 Ce-143 Ce-144 Cm-242 Cm-244 Co-58 Co-60 Cs-1 34 Cs-136 Cs-137 1-131 curies 4.0309e+000 3.7405e+006 2.8092e+006 2.9153e+006 7.1443e+004 6.1039e+004 5.8270e+004 1.1059e+003 1.7433e+002 5.5089e+003 6.7903e+003 5.9417e+006 1.4137e+006 3.9540e+006 3.0363e+007 Library : Grov becquerels 1.4914e+01 1 1.3840e+017 1.0394e+017 1.0787e+017 2.6434e+01 5 2.2584e+01 5 2.1560e+01 5 4.0918e+01 3 6.4502e+'01 2 2.0383e+01 4 2.5124e+014 2.1984e+01 7 5.2307e+01 6 1.4630e+017 1.1234e+018 uCi/cm3 5.9041 e-005 5.4787e+001 4.1147e+001 4.2701 e+001 1.0464e+000 8.9405e-001 8.5349e-001 1.6198e-002 2.5534e-003 8.0690e-002 9.9459e-002 8.7029e+001 2.0707e+001 5.7915e+001 4.4473e+002 Bq/cm3 2.1845e+000 2.0271 e+006 1.5224e+006 1.5799e+006 3.8718e+004 3.3080e+004 3.1579e+004 5.9934e+002 9.4477e+001 2.9855e+003 3.6800e+003 3.2201 e+006 7.6615e+005 2.1428e+006 1.6455e+007 cO)
Page
Nuclide 1-132 1-133 1-134 1-135 Kr-85 Kr-85m Kr-87 Kr-88 La-1 40 La-141 La-1 42 Mo-99 Nb-95 Nd-147 Np-239 Pr-143 Pr-144 Pu-238 Pu-239 Pu-240 Pu-241 Rb-86 Rh-1 03m Rh-105 Rh-106 Ru-103 Ru-105 Ru-1 06 Sb-127 Sb-129 Sr-89 Sr-90 Sr-91 Sr-92 Tc-99m Te-127 Te-127m
- Te-129 Te-1 29m Te-131m Te-132 Xe-133 Xe-1 33m Xe-135 Xe-135m Xe-138 curies 4.3473e+007 6.1376e+007 6.9244e+007 5.8345e+007 1.0239e+006 2.1944e+007 4.4636e+007 6.2400e+007 2.9884e+004 2.5576e+004 2.4730e+004 3.4999e+005 3.351 Oe+004 1.0548e+004 7.6881 e+005 2.5835e+004 5.7437e+004 2.3766e+002 1.5793e+001 2.7576e+001 6.8289e+003 4.8774e+004 3.3493e+005 1.9627e+005 1.3560e+005 3.3581 e+005 2.1656e+005 1.3560e+005 3.3460e+005 1.2102e+006 1.8338e+006 1.7498e+005 2.1443e+006 2.2137e+006 3.1275e+005 3.3963e+005 6.3716e+004 1.1569e+006 2.5986e+005 6.9795e+005 5.2864e+006 1.5342e+008 4.7793e+006 4.8767e+007 3.2043e+007 1.3585e+008 becquerels 1.6085e+018 2.2709e+018 2.5620e+018 2.1588e+018 3.7884e+016 8.1193e+017 1.6515e+018 2.3088e+018 1.1057e+015 9.4631e+014 9.1501e+014 1.2950e+016 1.2399e+015 3.9028e+014 2.8446e+016 9.5590e+014 2.1252e+01 5 8.7934e+012 5.8434e+01 1 1.0203e+012 2.5267e+014 1.8046e+015 1.2392e+016 7.2620e+015 5.0172e+015 1.2425e+016 8.0127e+015 5.0172e+015 1.2380e+016 4.4777e+016 6.7851 e+016 6.4743e+015 7.9339e+016 8.1907e+016 1.1572e+016 1.2566e+016 2.3575e+015 4.2805e+016 9.6148e+015 2.5824e+016 1.9560e+017 5.6765e+018 1.7683e+017 1.8044e+018 1.1856e+018 5.0265e+018 uCi/cm3 6.3676e+002 8.9898e+002 1.0142e+003 8.5459e+002 1.4997e+001 3.2142e+002 6.5379e+002 9.1 398e+002 4.3772e-001 3.7462e-001 3.6222e-001 5.1264e+000 4.9083e-001 1.5450e-001 1.1261e+001 3.7841 e-001 8.4128e-001 3.481 Oe-003 2.3132e-004 4.0391 e-004 1.0002e-001 7.1440e-001 4.9057e+000 2.8748e+000 1.9862e+000 4.9187e+000 3.1720e+000 1.9862e+000 4.9009e+000 1.7726e+001 2.6860e+001 2.5630e+000 3.1408e+001 3.2424e+001 4.5809e+000 4.9746e+000 9.3326e-001 1.6945e+001 3.8062e+000 1.0223e+001 7.7431 e+001 2.2472e+003 7.0003e+001 7.1430e+002 4.6934e+002 1.9898e+003 Bq/cm3 2.3560e+007 3.3262e+007 3.7526e+007 3.1620e+007 5.5490e+005 1.1892e+007 2.4190e+007 3.3817e+007 1.6195e+004 1.3861 e+004 1.3402e+004 1.8968e+005 1.8161 e+004 5.7164e+003 4.1665e+005 1.4001 e+004 3.1128e+004 1.2880e+002 8.5589e+000 1.4945e+001 3.7009e+003 2.6433e+004 1.8151 e+005 1.0637e+005 7.3488e+004 1.8199e+005 1.1736e+005 7.3488e+004 1.8133e+005 6.5586e+005 9.9382e+005 9.4829e+004 1.1621e+006 1.1997e+006 1.6949e+005 1.8406e+005 3.4531 e+004 6.2698e+005 1.4083e+005 3.7825e+005 2.8649e+006 8.3145e+007 2.5901 e+006 2.6429e+007 1.7366e+007 7.3623e+007
Page
- 3 DOS File: MHAOOO.MS5 Run Date: July 20, 2005 Run Time: 3:43:37 PM Duration : 00:00:07 Cho 4M Ar9 0c~
P..?5,! iz2i Nuclide Y-90 Y-91 Y-92 Y-93 Zr-95 Zr-97 curies 1.9040e+003 2.3424e+004 2.2318e+004 1.6316e+004 3.2082e+004 2.7223e+004 becquerels 7.0448e+013 8.6669e+014 8.2577e+014 6.0369e+014 1.1870e+015 1.0073e+015 uCi/cm3 2.7888e-002 3.4309e-001 3.2690e-001 2.3898e-001 4.6991 e-001 3.9874e-001 Bq/cm3 1.0319e+003 1.2695e+004 1.2095e+004 8.8424e+003 1.7387e+004 1.4753e+004 Buildup The material reference is: Shield 2 Integration Parameters Radial Circumferential Y Direction (axial) 10 10 20 Energy MeV 0.015 0.02 0.03 0.04 0.05 0.06 0.08 0.1 0.15 0.2 0.3 0.4 0.5 0.6 0.8 1.0 1.5 2.0 3.0 4.0 Activity photons/sec 1.575e+12 2.389e+15 3.602e+18 7.380e+15 2.572e+16 7.288e+15 2.117e+18 3.517e+16 1.163e+18 2.742e+1 8 2.005e+18 3.780e+18 3.979e+1 8 3.598e+18 7.259e+18 3.092e+18 2.409e+18 4.033e+18 2.491e+17 2.402e+13 Fluence Rate MeV/cm2/sec No Buildup 0.OOOe+00 0.OOOe+00 3.783e-216 6.031 e-106 4.128e-65 1.121e-47 2.627e-30 4.338e-26 1.806e-1 8 3.687e-1 5 8.576e-1 2 3.042e-09 1.524e-07 2.831 e-06 5.393e-04 6.436e-03 1.287e+00 6.568e+01 2.309e+02 2.319e-01 Results Fluence Rate MeV/cm2/sec With Buildup 2.300e-24 5.490e-21 1.830e-1 7 9.944e-20 1.133e-18 2.304e-1 8 1.593e-1 5 1.223e-1 6 2.286e-1 4 7.552e-1 2 1.168e-08 2.330e-06 7.030e-05 8.479e-04 8.346e-02 6.020e-01 5.308e+01 1.673e+03 3.267e+03 2.309e+00 Exposure Rate mR/hr No Buildup 0.OOOe+00 0.OOOe+00 3.749e-218 2.667e-1 08 1I.100e-67 2.226e-50 4.157e-33 6.637e-29 2.973e-21 6.507e-1 8 1.627e-14 5.926e-1 2 2.991 e-1 0 5.526e-09 1.026e-06 1.186e-05 2.166e-03 1.016e-01 3.132e-01 2.869e-04 Exposure Rate mR/hr With Buildup 1.973e-25 1.902e-22 1.814e-19 4.398e-22 3.019e-21 4.577e-21 2.520e-1 8 1.871 e-19 3.765e-1 7 1.333e-14 2.215e-11 4.540e-09 1.380e-07 1.655e-06 1.587e-04 1.1 Oe-03 8.930e-02 2.587e+00 4.432e+00 2.856e-03 TOTALS:
4.011e+19 2.981 e+02 4.995e+03 4.173e-01 7.112e+00
CA06449 Rev.000 Page 127 ATTACHMENT X MICROSHIELD PLUME SHINE OUTPUT FILES
6AV(9Yv I1 fay-, /Z2 geey..(
MicroShield v5.05 (5.05-00299)
CALVERT CLIFFS NUCLEAR POWER PLANT Page
- 1 DOS File: 1 Run Date: J Run Time: 1 Duration : 0 IHC000.MS5 uly 22, 2005 0:40:11 AM 0:00:12 File Ref:
Date:
By:
Checked:
Case
Title:
Case 1
==
Description:==
Case 1 Containment Plume Dose Geometry: 13 - Rectangular Volume Length Width Height Source Dimensions 3.0e+3 cm 98 ft 7.8 in 3.5e+3 cm 114 ft 7.8 in 3.5e+3cm 114ft7.8 in X
- 1 3779.52 cm 124 ft Dose Points Y
1737.36 cm 57 ft 0.0 in z
1737.36 cm 57 ft 0.0 in Lx Shield Name Source Shield 1 Shield 2 Shield 3 Air Gap Shields Dimension 1.30e+06 ft3
.5ft 22.0 ft 2.0ft Material Air Concrete Air Concrete Air Density 0.00122 2.35 0.00122 2.35 0.00122 Source Input Grouping Method: Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Excluded Library: Grove Nuclide Am-241 Ba-1 37m Ba-1 39 Ba-140 Ce-141 Ce-143 Ce-144 Cm-242 Cm-244 Co-58 Co-60 Cs-134 Cs-136 Cs-137 1-131 curies 9.9967e-002 9.2763e+004 6.9667e+004 7.2299e+004 1.7718e+003 1.5138e+003 1.4451 e+003 2.7426e+001 4.3233e+000 1.3662e+002 1.6840e+002 1.4736e+005 3.5060e+004 9.8058e+004 7.5299e+005 becquerels 3.6988e+009 3.4322e+01 5 2.5777e+01 5 2.6751 e+01 5 6.5557e+01 3 5.601 1e+013 5.3469e+01 3 1.0148e+012 1.5996e+011 5.0549e+01 2 6.2308e+01 2 5.4523e+01 5 I1.2972e+0I15 3.6281 e+01 5 2.7861 e+016 uCi/cm3 2.7225e-006 2.5263e+000 1.8973e+000 1.9690e+000 4.8253e-002 4.1227e-002 3.9356e-002 7.4692e-004 1.1 774e-004 3.7207e-003 4.5862e-003 4.0132e+000 9.5482e-001 2.6705e+000 2.0507e+001 Bq/cm3 1.0073e-001 9.3473e+004 7.0200e+004 7.2852e+004 1.7854e+003 1.5254e+003 1.4562e+003 2.7636e+001 4.3564e+000 1.3767e+002 1.6969e+002 1.4849e+005 3.5328e+004 9.8809e+004 7.5875e+005 CO-i_
Page
- 2 DOS File: MHCOOO.MS5 Run Date: July 22, 2005 Run Time: 10:40:11 AM Duration : 00:00:12 C4;.(9y9 xee.o PA
/2 7' Nuclide 1-132 1-133 1-134 1-135 Kr-85 Kr-85m Kr-87 Kr-88 La-140 La-141 La-1 42 Mo-99 Nb-95 Nd-1 47 Np-239 Pr-143 Pr-144 Pu-238 Pu-239 Pu-240 Pu-241 Rb-86 Rh-1 03m Rh-105 Rh-1 06 Ru-1 03 Ru-105 Ru-106 Sb-127 Sb-1 29 Sr-89 Sr-90 Sr-91 Sr-92 Tc-99m Te-127 Te-127m Te-129 Te-129m Te-131m Te-132 Xe-1 33 Xe-1 33m Xe-1 35 Xe-1 35m Xe-138 curies 1.0781 e+006 1.5221 e+006 1.7173e+006 1.4470e+006 2.5393e+004 5.4420e+005 1.1070e+006 1.5475e+006 7.4112e+002 6.3427e+002 6.1330e+002 8.6798e+003 8.3104e+002 2.6160e+002 1.9067e+004 6.4071 e+002 1.4244e+003 5.8939e+000 3.9167e-001 6.8389e-001 1.6936e+002 1.2096e+003 8.3061 e+003 4.8676e+003 3.3628e+003 8.3280e+003 5.3708e+003 3.3628e+003 8.2980e+003 3.0013e+004 4.5478e+004 4.3396e+003 5.3180e+004 5.4899e+004 7.7561 e+003 8.4228e+003 1.5802e+003 2.8690e+004 6.4446e+003 1.7309e+004 1.311 Oe+005 3.8048e+006 1.1853e+005 1.2094e+006 7.9466e+005 3.3692e+006 becguerels 3.9890e+016 5.6318e+016 6.3540e+016 5.3539e+016 9.3954e+014 2.0135e+016 4.0959e+016 5.7258e+016 2.7421 e+013 2.3468e+013 2.2692e+013 3.2115e+014 3.0748e+013 9.6792e+012 7.0548e+014 2.3706e+013 5.2704e+013 2.1807e+011 1.4492e+010 2.5304e+010 6.2663e+012 4.4755e+013 3.0733e+014 1.8010e+014 1.2442e+014 3.0814e+014 1.9872e+014 1.2442e+014 3.0703e+014 1.1105e+015 1.6827e+015 1.6057e+014 1.9677e+015 2.0313e+015 2.8698e+014 3.1164e+014 5.8467e+013 1.0615e+015 2.3845e+014 6.4043e+014 4.8507e+015 1.4078e+017 4.3856e+015 4.4748e+016 2.9402e+016 1.2466e+017 uCi/cm3 2.9361 e+001 4.1453e+001 4.6769e+001 3.9407e+001 6.9155e-001 1.4821 e+001 3.0148e+001 4.2144e+001 2.0184e-002 1.7274e-002 1.6703e-002 2.3638e-001 2.2632e-002 7.1244e-003 5.1927e-001 1.7449e-002 3.8793e-002 1.6051 e-004 1.0667e-005 1.8625e-005 4.6123e-003 3.2942e-002 2.2621 e-001 1.3256e-001 9.1582e-002 2.2680e-001 1.4627e-001 9.1582e-002 2.2599e-001 8.1737e-001 1.2385e+000 1.1818e-001 1.4483e+000 1.4951 e+000 2.1123e-001 2.2939e-001 4.3035e-002 7.8134e-001 1.7551e-001 4.7139e-001 3.5704e+000 1.0362e+002 3.2280e+000 3.2937e+001 2.1642e+001 9.1756e+001 Bg/cm3 1.0864e+006 1.5338e+006 1.7304e+006 1.4581 e+006 2.5587e+004 5.4837e+005 1.1155e+006 1.5593e+006 7.4679e+002 6.3912e+002 6.1799e+002 8.7462e+003 8.3740e+002 2.6360e+002 1.9213e+004 6.4561 e+002 1.4353e+003 5.9390e+000 3.9467e-001 6.8912e-001 1.7066e+002 1.2189e+003 8.3697e+003 4.9049e+003 3.3885e+003 8.3917e+003 5.4119e+003 3.3885e+003 8.3615e+003 3.0243e+004 4.5826e+004 4.3728e+003 5.3587e+004 5.5319e+004 7.8155e+003 8.4873e+003 1.5923e+003 2.891 Oe+004 6.4939e+003 1.7441 e+004 1.321 Oe+005 3.8339e+006 1.1944e+005 1.2187e+006 8.0074e+005 3.3950e+006
Page
- 3 DOS File: MHCOOO.MS5 Run Date: July 22, 2005 Run Time: 10:40:11 AM Duration : 00:00:12 CAO(Ovy I'ge.
Nuclide Y-90 Y-91 Y-92 Y-93 Zr-95 Zr-97 curies 4.7218e+001 5.8091 e+002 5.5348e+002 4.0464e+002 7.9563e+002 6.7513e+002 becguerels 1.7471e+012 2.1494e+013 2.0479e+013 1.4972e+013 2.9438e+013 2.4980e+013 uCi/cm3 1.2859e-003 1.5820e-002 1.5073e-002 1.1020e-002 2.1668e-002 1.8386e-002 Bq/cm3 4.7579e+001 5.8536e+002 5.5772e+002 4.0774e+002 8.0172e+002 6.8030e+002 Buildup The material reference is: Shield 3 Integration Parameters X Direction Y Direction Z Direction 10 20 20 Energy MeV 0.015 0.02 0.03 0.04 0.05 0.06 0.08 0.1 0.15 0.2 0.3 0.4 0.5 0.6 0.8 1.0 1.5 2.0 3.0 4.0 Activity nhotons/sec 3.906e+10 5.925e+13 8.932e+16 1.830e+14 6.379e+14 1.807e+14 5.251e+16 8.722e+14 2.885e+16 6.800e+16 4.973e+16 9.375e+16 9.868e+16 8.924e+16 1.800e+17 7.668e+16 5.975e+1 6 1.OOOe+17 6.177e+15 5.957e+1 1 Fluence Rate MeV/cm 2/sec No Buildup 0.OOOe+00 1.598e-272 3.615e-84 1.024e-41 4.939e-25 2.437e-1 8 8.335e-1 0 4.389e-09 6.449e-05 3.282e-03 1.028e-01 2.301 e+00 1.522e+01 5.843e+01 1.051 e+03 2.250e+03 2.647e+04 2.424e+05 1.166e+05 3.820e+01 Results Fluence Rate MeV/cm2/sec With Buildup 8.373e-26 1.999e-22 6.663e-1 9 3.620e-21 4.125e-20 9.867e-1 7 5.980e-08 6.346e-07 1.723e-02 9.564e-01 2.128e+01 3.11 Oe+02 1.418e+03 3.961 e+03 4.321 e+04 6.339e+04 3.962e+05 2.486e+06 7.531 e+05 1.861 e+02 Exposure Rate mR/hr No Buildup 0.OOOe+00 5.537e-274 3.583e-86 4.529e-44 1.316e-27 4.840e-21 1.319e-12 6.714e-1 2 1.062e-07 5.793e-06 1.950e-04 4.483e-03 2.987e-02 1.141e-01 2.000e+00 4.147e+00 4.453e+01 3.748e+02 1.582e+02 4.726e-02 Exposure Rate mR/hr With Buildup 7.182e-27 6.923e-24 6.603e-21 1.601 e-23 1.099e-22 1.960e-19 9.463e-1 I 9.709e-1 0 2.837e-05 1.688e-03 4.036e-02 6.059e-01 2.783e+00 7.731 e+00 8.218e+01 1.168e+02 6.665e+02 3.845e+03 1.022e+03 2.303e-01 TOTALS:
9.947e+17 3.888e+05 3.748e+06-5.838e+02 5.743e+03
CA06449 Rev.000 Page 131 ATTACHMENT Y MICROSHIELD CONTROL ROOM FILTER OUTPUT FILES
MicroShield v5.05 (5.05-00299)
CALVERT CLIFFS NUCLEAR POWER PLANT PA t1 Page
- 1 DOS File: 1 Run Date: J Run Time: 9 Duration : 0 IHFO0O.MS5 uly 23, 2005
- 54:20 AM 0:00:12 File Ref: _
Date:
By:
Checked:
Case
Title:
Case 1
==
Description:==
Case 1 CsidaiWit Filter Dose Geometry: 13 - Rectangular Volume Length Width Height Source Dimensions 149.86 cm 60.96 cm 83.82 cm 4ft 11.0 in 2ft 2 ft 9.0 in l
Is X
- 1 228.6 cm 7 ft 6.0 in Dose Points Y
41.91 cm 1 ft4.5in z
30.48 cm 1 ft Shield Name Source Shield 1 Shield 2 Air Gap Shields Dimension 4.67e+04 in3 6.0 in 24.0 in Material Density Carbon 2.25 Air 0.00122 Concrete 2.35 Air 0.00122 Source Input Grouping Method: Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Excluded Library: Grove Nuclide Am-241 Ba-1 37m Ba-1 39 Ba-140 Ce-141 Ce-143 Ce-144 Cm-242 Cm-244 Co-58 Co-60 Cs-1 34 Cs-1 36 Cs-137 1-131 1-132 curies 4.0309e+000 2.8092e+006 2.9153e+006 7.1443e+004 6.1039e+004 5.8270e+004 1.1059e+003 1.7433e+002 5.5089e+003 6.7903e+003 5.9417e+006 1.4137e+006 3.9540e+006 3.0363e+007 4.3473e+007 becauerels 1.4914e+011 1.0394e+017 1.0787e+017 2.6434e+01 5 2.2584e+01 5 2.1 560e+01 5 4.091 8e+01 3 6.4502e+01 2 2.0383e+01 4 2.5124e+014 2.1984e+01 7 5.2307e+01 6 1.4630e+017 1.1234e+018 1.6085e+018 uCi/cm 3 5.2641 e+000 3.6686e+006 3.8072e+006 9.3300e+004 7.9713e+004 7.6097e+004 1.4442e+003 2.2766e+002 7.1943e+003 8.8677e+003 7.7595e+006 1.8462e+006 5.1637e+006 3.9652e+007 5.6773e+007 Bq/cm 3 1.9477e+005 1.3574e+011 1.4087e+011 3.4521 e+009 2.9494e+009 2.8156e+009 5.3437e+007 8.4236e+006 2.6619e+008 3.281 Oe+008 2.871 Oe+0 11 6.8309e+0I 0 1.9106e+01 1 1.4671e+012 2.1006e+012 cOO2
Page
$-411 V9 Ae3 Nuclide 1-133 1-134 1-135 Kr-85 Kr-85m Kr-87 Kr-88 La-140 La-141 La-142 Mo-99 Nb-95 Nd-147 Np-239 Pr-143 Pr-144 Pu-238 Pu-239 Pu-240 Pu-241 Rb-86 Rh-1 03m Rh-105 Rh-1 06 Ru-1 03 Ru-1 05 Ru-106 Sb-127 Sb-129 Sr-89 Sr-90 Sr-91 Sr-92 Tc-99m Te-127 Te-127m Te-129 Te-129m Te-131m Te-132 Xe-133 Xe-133m Xe-1 35 Xe-135m Xe-138 Y-90 curies 6.1376e+007 6.9244e+007 5.8345e+007 2.9884e+004 2.5576e+004 2.4730e+004 3.4999e+005 3.351 Oe+004 1.0548e+004 7.6881 e+005 2.5835e+004 2.3766e+002 1.5793e+001 2.7576e+001 6.8289e+003 4.8774e+004 1.9627e+005 3.3581 e+005 2.1656e+005 1.3560e+005 3.3460e+005 1.2102e+006 1.8338e+006 1.7498e+005 2.1443e+006 2.2137e+006 3.1275e+005 3.3963e+005 6.3716e+004 1.1569e+006 2.5986e+005 6.9795e+005 5.2864e+006 becguerels 2.2709e+018 2.5620e+018 2.1588e+018 1.1057e+015 9.4631 e+014 9.1501e+014 1.2950e+016 1.2399e+015 3.9028e+014 2.8446e+016 9.5590e+014 8.7934e+012 5.8434e+011 1.0203e+012 2.5267e+014 1.8046e+015 7.2620e+015 1.2425e+016 8.0127e+015 5.0172e+015 1.2380e+016 4.4777e+016 6.7851 e+016 6.4743e+015 7.9339e+016 8.1907e+016 1.1572e+016 1.2566e+016 2.3575e+015 4.2805e+016 9.6148e+015 2.5824e+016 1.9560e+017 uCi/cm3 8.0153e+007 9.0428e+007 7.6195e+007 3.9027e+004 3.3401 e+004 3.2296e+004 4.5706e+005 4.3762e+004 1.3775e+004 1.0040e+006 3.3739e+004 3.1037e+002 2.0625e+001 3.6012e+001 8.9181 e+003 6.3696e+004 2.5632e+005 4.3855e+005 2.8281 e+005 1.7708e+005 4.3697e+005 1.5804e+006 2.3948e+006 2.2851 e+005 2.8003e+006 2.8909e+006 4.0843e+005 4.4353e+005 8.3209e+004 1.5108e+006 3.3936e+005 9.1148e+005 6.9037e+006 Bq/cm3 2.9657e+012 3.3458e+012 2.8192e+012 1.4440e+009 1.2358e+009 1.1949e+009 1.691 1e+010 1.6192e+009 5.0968e+008 3.7149e+010 1.2483e+009 1.1484e+007 7.6311 e+005 1.3325e+006 3.2997e+008 2.3567e+009 9.4837e+009 1.6226e+010 1.0464e+010 6.5521 e+009 1.6168e+010 5.8476e+010 8.8608e+010 8.4550e+009 1.0361 e+011 1.0697e+011 1.5112e+010 1.6411e+010 3.0787e+009 5.5901 e+010 1.2556e+010 3.3725e+010 2.5544e+01 1 1.9040e+003 7.0448e+013 2.4865e+003 9.2001 e+007
Page
- 3 DOS File: MHFOOO.MS5 Run Date: July 23, 2005 Run Time: 9:54:20 AM Duration : 00:00:12 C*yry7 Ac4'z 64 e- /3/
Nuclide Y-91 Y-92 Y-93 Zr-95 Zr-97 curies 2.3424e+004 2.2318e+004 1.6316e+004 3.2082e+004 2.7223e+004 becquerels 8.6669e+014 8.2577e+014 6.0369e+014 1.1870e+015 1.0073e+015 uCi/cm3 3.0590e+004 2.9146e+004 2.1308e+004 4.1897e+004 3.5551 e+004 Bq/cm3 1.1318e+009 1.0784e+009 7.8838e+008 1.5502e+009 1.3154e+009 Buildup The material reference is: Shield 2 Integration Parameters X Direction Y Direction Z Direction 10 20 20 Enercgv MeV 0.015 0.02 0.03 0.04 0.05 0.06 0.08 0.1 0.15 0.2 0.3 0.4 0.5 0.6 0.8 1.0 1.5 2.0 3.0 4.0 Activitv photons/sec 1.575e+12 1.437e+15 2.901 e+17 5.447e+15 2.572e+16 7.288e+15 3.388e+16 3.062e+16 1.735e+17 3.161e+17 2.754e+17 1.41 Oe+18 2.964e+18 3.346e+18 6.737e+18 2.531e+18 1.909e+18 4.979e+1 7 2.901e+14 2.402e+13 Fluence Rate MeV/cm2/sec No Buildup 0.OOOe+00 1.304e-214 5.506e-64 1.668e-29 7.463e-16 1.447e-1 0 5.466e-05 5.378e-03 4.655e+00 1.111e+02 2.314e+03 9.713e+04 9.805e+05 3.821 e+06 5.052e+07 7.664e+07 6.143e+08 7.154e+08 2.616e+06 6.61 Oe+05 Results Fluence Rate MeV/cm2/sec With Buildup 9.515e-22 1.366e-18 6.099e-1 6 3.037e-17 7.957e-1 5 4.032e-09 3.091 e-03 5.661 e-01 8.41 Oe+02 2.131e+04 3.211 e+05 9.129e+06 6.539e+07 1.901 e+08 1.583e+09 1.696e+09 7.588e+09 6.220e+09 1.482e+07 2.879e+06 Exnosure Rate mR/hr No Buildup 0.OOOe+00 4.517e-216 5.457e-66 7.378e-32 1.988e-1 8 2.873e-1 3 8.650e-08 8.228e-06 7.665e-03 1.961e-01 4.390e+00 1.893e+02 1.925e+03 7.457e+03 9.609e+04 1.413e+05 1.034e+06 1.106e+06 3.550e+03 8.177e+02 Exposure Rate mR/hr With Buildup 8.161e-23 4.732e-20 6.045e-1 8 1.343e-19 2.120e-17 8.009e-12 4.891 e-06 8.660e-04 1.385e+00 3.761 e+O1 6.090e+02 1.779e+04 1.284e+05 3.711 e+05 3.01 Oe+06 3.126e+06 1.277e+07 9.618e+06 2.01 Oe+04 3.562e+03 TOTALS:
2.055e+19 1.465e+09 1.737e+10 2.391 e+06 2.906e+07
CA06449 Rev.000 Page 135 ATTACHMENT Z MICROSHIELD CONTROL ROOM FILTER OUTPUT FILES - IODINE ONLY
mm
MicroShield v5.05 (5.05-00299)
CALVERT CLIFFS NUCLEAR POWER PLANT
°<a /3' Page
- 1 DOS File: 1\\
Run Date: J Run Time: 3 Duration : 0 IHG000.MS5 uly 23, 2005
- 22:38 PM 0:00:07 File Ref:
Date:
By:
Checked:
Case
Title:
Case I
==
Description:==
Case 1 Containment Filter Dose Geometry: 13 - Rectangular Volume Length I
Width Height X
- 1 228.6 cm 7 ft 6.0 in wurce Dimensions 149.86 cm 60.96 cm 83.82 cm Dose Points Y
41.91 cm 1 ft4.5in 4 ft 11.0 in 2ft 2 ft 9.0 in z
30.48 cm 1 ft Shield Name Source Shield 1 Shield 2 Air Gap Shields Dimension 7.66e+05 cm 3 15.24 cm 60.96 cm Material Density Carbon 2.25 Air 0.00122 Concrete 2.35 Air 0.00122 Source Input Grouping Method : Standard Indices Number of Groups: 25 Lower Energy Cutoff: 0.015 Photons < 0.015: Excluded Library: Grove Nuclide 1-131 1-132 1-133 1-134 1-135 curies 3.0363e+007 4.3473e+007 6.1376e+007 6.9244e+007 5.8345e+007 becguerels 1.1234e+018 1.6085e+018 2.2709e+018 2.5620e+01 8 2.1588e+018 uCi/cm3 3.9652e+007 5.6773e+007 8.0153e+007 9.0428e+007 7.6195e+007 Bq/cm3 1.4671e+012 2.1006e+012 2.9657e+012 3.3458e+0 12 2.8192e+012 Buildup The material reference is : Shield 2 Integration Parameters X Direction Y Direction Z Direction 10 20 20 Results
Page
yf v,
/c.c- /37 Enerav MeV 0.03 0.08 0.15 0.2 0.3 0.4 0.5 0.6 0.8 1.0 1.5 2.0 Activity photons/sec 1.191e+17 2.941 e+16 1.270e+17 1.229e+17 2.203e+17 1.396e+18 2.901e+18 3.050e+18 6.396e+18 2.408e+18 1.817e+18 4.957e+17 Fluence Rate MeV/cm2/sec No Buildup 2.260e-64 4.745e-05 3.409e+00 4.321 e+01 1.851 e+03 9.619e+04 9.596e+05 3.483e+06 4.796e+07 7.291 e+07 5.848e+08 7.122e+08 Fluence Rate MeV/cm2/sec With Buildup 2.504e-1 6 2.683e-03 6.159e+02 8.286e+03 2.568e+05 9.040e+06 6.400e+07 1.733e+08 1.502e+09 1.613e+09 7.223e+09 6.192e+09 Exposure Rate mR/hr No Buildup 2.240e-66 7.509e-08 5.614e-03 7.626e-02 3.51 1e+00 1.874e+02 1.884e+03 6.798e+03 9.122e+04 1.344e+05 9.838e+05 1.101e+06 Exposure Rate mR/hr With Buildup 2.481 e-1 8 4.246e-06 1.014e+00 1.462e+01 4.871 e+02 1.761 e+04 1.256e+05 3.383e+05 2.858e+06 2.974e+06 1.215e+07 9.575e+06 TOTALS:
1.908e+19 1.422e+09 1.678e+10 2.320e+06 2.804e+07