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Category:ARCHIVE RECORDS
MONTHYEARML18039A6231998-11-18018 November 1998
Rev 0 to Calculation MD-Q0999-970046, NPSH Evaluation of Browns Ferry RHR & CS Pumps.
ML18039A6271998-11-10010 November 1998
Rev 1 to 50147-C-012, HCLPF Calculations for Selected Blockwalls.
ML18039A5571998-10-0404 October 1998
Rev 0 to CD-Q3068-980061, Evaluation of IGSCC Indication at Weld GR-3-63.
ML18039A5391998-09-0303 September 1998
Rev 1 to CD-Q0082-970020, Eqe Evaluation A-46 Outliers to DG Neutral Ground Transformers.
ML20217Q6921998-04-23023 April 1998
Rev R8 to Calculation ND-Q0031-920075, Control Room Doses
ML20217A5111998-03-24024 March 1998
Rev 4 to Calculation MD-Q-0999-920136, Post Accident Primary Containment Penetration Isolated Piping Over Pressure Analysis
ML18039A5341997-08-13013 August 1997
Rev 2 to CD-Q2999-940343, Qualification of Cable Tray & Conduit Systems by A-46 Program.
ML18039A5411996-12-0101 December 1996
Rev 0 to 50147-C-003, Outlier & HCLPF Evaluations for RHR Pump Anchorage.
ML20129C0761996-10-23023 October 1996
Press Release II-96-88, NRC Staff Issues Assessment of Performance at Browns Ferry Nuclear Power Plant in Al
ML20129D6391996-09-25025 September 1996
Rev 2 to Calculation Package for Application of Revised DBA Source Term to Browns Ferry Nuclear Power Plant
ML18039A5441996-08-0606 August 1996
Rev 0 to CD-Q3071-960089, Verification of Anchorage for Panel 3-25-31 to Resolve Outlier Identified by USI A-46 Evaluation (Ssel #39204).
ML18039A6261996-07-15015 July 1996
Rev 1 to 50147-C-011, HCLPF Calculations for Electrical Equipment on A-46 Safe Shutdown Equipment List.
ML20129D8441996-06-13013 June 1996
Rev 1 to Addl Radionuclide Data
ML20129D8191996-06-13013 June 1996
Rev 1 to Suppression Pool Scrubbing Efficency (Including Pool Bypass)
ML20129D8101996-06-13013 June 1996
Rev 1 to Max Elemental I Decontamination Factors
ML20129D7601996-06-13013 June 1996
Rev 2 to Volumetric Flowrate as Function of Time from Drywell to Torus (& Return)
ML20129D8911996-05-27027 May 1996
Rev 1 to Aerosol Decontamination Factor in Main Steam Lines & Condenser
ML18039A5331996-05-0303 May 1996
Rev 0 to 50147-C-004, Bfnd A-46/IPEEE Outlier Evaluation - RHR Heat Exchangers.
ML18039A5361996-04-15015 April 1996
Rev 6 to CD-Q0000-931227, Qualification of Cable Tray & Conduit Systems by A-46 Program.
ML18039A5381996-02-24024 February 1996
Rev 0 to 50147-C-006, GE 7700 MCC Seismic Capacity Vs Demand - Outlier Resolution.
ML20205K7891996-02-15015 February 1996
Press Release II-96-21, NRC Saff Proposed $80,000 Civil Penalty Against TVA for Alleged Discrimination at Browns Ferry
ML18038B6651996-02-0505 February 1996
Non-proprietary Calculations for Application of Revised DBA Source Term to Browns Ferry Nuclear Power Plant.
ML18039A6251995-10-16016 October 1995
Rev 1 to CD-Q0000-940339, Calculation of Basic Parameters for A46 & IPEEE Seismic Program.
ML18039A5431995-10-0101 October 1995
Rev 0 to 50147-C-002, MSIV Outlier Resolution.
ML18038B6661995-09-29029 September 1995
Non-proprietary Calculation of Containment Leakage Doses for Browns Ferry Nuclear Power Plant.
ML20129D8981995-09-28028 September 1995
Rev 0 to Elemental I Filter Efficiency in Main Steam Lines
ML20129D8741995-09-27027 September 1995
Rev 0 to Source Term for Use on Browns Ferry Application of NUREG-1465
ML20129D7371995-09-22022 September 1995
Rev 2 to Design Data Base for Application of Revised DBA Source Term to TVA Browns Ferry Nuclear Power Plant
ML20129D8831995-09-22022 September 1995
Rev 0 to Drywell Leakage Rate Direct to Environment Mimicking Case 2 Early Bypass of Sgts
ML20129D7861995-09-0101 September 1995
Rev 0 to Aerosol Decay Rates (Lambda) in Drywell
ML18039A5371995-03-23023 March 1995
Rev 2 to CD-Q0248-910431, Seismic Analysis of Battery Rack for Units 1 & 2 Battery Rooms A,B,C & D at El 621'3.
ML20093E4071994-02-0707 February 1994
Rev 0 to Calculation MD-Q3001-940005, Vessel Weld Flaw Evaluation for Browns Ferry Nuclear Plant Unit 3
ML20058N8251993-07-29029 July 1993
Package Consisting of Attachment to Employee Concerns Program
ML18036B1941992-05-26026 May 1992
Reactor Bldg Vents Radiation Monitoring Sys Drift Rate Calculation for TVA Browns Ferry Nuclear Plant.
ML20085M6321991-11-11011 November 1991
NUMARC Industry Survey in Support of License Renewal Rulemaking Aquatic Biology Dept Response to Aquatic Resource Questions
ML18036A3241991-08-14014 August 1991
Audit Rept on TVA Conformance W/Title 10 of Code of Federal Regulations Part 50.4,50.59,50.71(e) in Amend 7 of Browns Ferry Updated Fsar.
ML20059A4911990-08-13013 August 1990
Control Room Habitability Following Potential Barge Shipment Accident of Hazardous Chemicals
ML20085M6251990-07-0505 July 1990
DMR Summary for Plant & Specific Parameters Violated at Each Outfall
ML20059A4991990-05-29029 May 1990
Rev 0 to Frequency of Chlorine Concentration in Control Room in Excess of Toxicity Limit Due to Barge Accident
ML20059A4951990-05-23023 May 1990
Toxic Barge Study
ML20043B1131990-05-0303 May 1990
Rev 1 to ED-Q2000-87135, Cable Ampacity Calculation - V4 & V5 Safety-Related Trays for Unit 2 Operation.
ML18039A5311989-12-0202 December 1989
Rev 3 to CD-Q2253-883859, Center of Gravity for JBs 7193 & 7196.
ML18039A5301989-12-0202 December 1989
Rev 2 to CD-Q2253-883954, Seismic Qualification for Breakers in JB 7193 & 7196.
ML18039A5291989-09-21021 September 1989
Rev 1 to CD-Q2253-870722, Conduit Support.
ML18033A4851988-11-18018 November 1988
Sys Preoperability Checklist & Sys Plant Acceptance Evaluation Programs.
ML20154Q7921988-08-16016 August 1988
Rev 0 to Calculation ED-Q0268-88463, 480-Volt Reactor Motor-Operated Valve Boards 3A/B
ML20155B6291988-08-11011 August 1988
Rev 1 to Calculation ED-Q2268-87324, Thermal Overload Heater Calculations - 480V Reactor MOV Bd 2C
ML20155B6241988-08-11011 August 1988
Rev 1 to Calculation ED-Q2268-87322, Thermal Overload Heater Calculations - 480V Reactor MOV Bd 2A
ML20154Q8441988-05-19019 May 1988
Attachment 10 to Calculation ED-Q0281-88139 Re Fuse Program for Stated motor-operated Valve Boards
ML20154Q8251988-05-19019 May 1988
Rev 0 to Calculation ED-Q0281-88139, 250-Volt DC Reactor Motor-Operated Valve Boards 2A,2B & 2C
1998-09-03
[Table view]
Category:OPERATIONS SUPPORT-CALCULATIONS
MONTHYEARML18039A6231998-11-18018 November 1998
Rev 0 to Calculation MD-Q0999-970046, NPSH Evaluation of Browns Ferry RHR & CS Pumps.
ML18039A6271998-11-10010 November 1998
Rev 1 to 50147-C-012, HCLPF Calculations for Selected Blockwalls.
ML18039A5571998-10-0404 October 1998
Rev 0 to CD-Q3068-980061, Evaluation of IGSCC Indication at Weld GR-3-63.
ML18039A5391998-09-0303 September 1998
Rev 1 to CD-Q0082-970020, Eqe Evaluation A-46 Outliers to DG Neutral Ground Transformers.
ML20217Q6921998-04-23023 April 1998
Rev R8 to Calculation ND-Q0031-920075, Control Room Doses
ML20217A5111998-03-24024 March 1998
Rev 4 to Calculation MD-Q-0999-920136, Post Accident Primary Containment Penetration Isolated Piping Over Pressure Analysis
ML18039A5341997-08-13013 August 1997
Rev 2 to CD-Q2999-940343, Qualification of Cable Tray & Conduit Systems by A-46 Program.
ML18039A5411996-12-0101 December 1996
Rev 0 to 50147-C-003, Outlier & HCLPF Evaluations for RHR Pump Anchorage.
ML20129D6391996-09-25025 September 1996
Rev 2 to Calculation Package for Application of Revised DBA Source Term to Browns Ferry Nuclear Power Plant
ML18039A5441996-08-0606 August 1996
Rev 0 to CD-Q3071-960089, Verification of Anchorage for Panel 3-25-31 to Resolve Outlier Identified by USI A-46 Evaluation (Ssel #39204).
ML18039A6261996-07-15015 July 1996
Rev 1 to 50147-C-011, HCLPF Calculations for Electrical Equipment on A-46 Safe Shutdown Equipment List.
ML20129D7601996-06-13013 June 1996
Rev 2 to Volumetric Flowrate as Function of Time from Drywell to Torus (& Return)
ML20129D8101996-06-13013 June 1996
Rev 1 to Max Elemental I Decontamination Factors
ML20129D8191996-06-13013 June 1996
Rev 1 to Suppression Pool Scrubbing Efficency (Including Pool Bypass)
ML20129D8441996-06-13013 June 1996
Rev 1 to Addl Radionuclide Data
ML20129D8911996-05-27027 May 1996
Rev 1 to Aerosol Decontamination Factor in Main Steam Lines & Condenser
ML18039A5331996-05-0303 May 1996
Rev 0 to 50147-C-004, Bfnd A-46/IPEEE Outlier Evaluation - RHR Heat Exchangers.
ML18039A5361996-04-15015 April 1996
Rev 6 to CD-Q0000-931227, Qualification of Cable Tray & Conduit Systems by A-46 Program.
ML18039A5381996-02-24024 February 1996
Rev 0 to 50147-C-006, GE 7700 MCC Seismic Capacity Vs Demand - Outlier Resolution.
ML18038B6651996-02-0505 February 1996
Non-proprietary Calculations for Application of Revised DBA Source Term to Browns Ferry Nuclear Power Plant.
ML18039A6251995-10-16016 October 1995
Rev 1 to CD-Q0000-940339, Calculation of Basic Parameters for A46 & IPEEE Seismic Program.
ML18039A5431995-10-0101 October 1995
Rev 0 to 50147-C-002, MSIV Outlier Resolution.
ML18038B6661995-09-29029 September 1995
Non-proprietary Calculation of Containment Leakage Doses for Browns Ferry Nuclear Power Plant.
ML20129D8981995-09-28028 September 1995
Rev 0 to Elemental I Filter Efficiency in Main Steam Lines
ML20129D8741995-09-27027 September 1995
Rev 0 to Source Term for Use on Browns Ferry Application of NUREG-1465
ML20129D7371995-09-22022 September 1995
Rev 2 to Design Data Base for Application of Revised DBA Source Term to TVA Browns Ferry Nuclear Power Plant
ML20129D8831995-09-22022 September 1995
Rev 0 to Drywell Leakage Rate Direct to Environment Mimicking Case 2 Early Bypass of Sgts
ML20129D7861995-09-0101 September 1995
Rev 0 to Aerosol Decay Rates (Lambda) in Drywell
ML18039A5371995-03-23023 March 1995
Rev 2 to CD-Q0248-910431, Seismic Analysis of Battery Rack for Units 1 & 2 Battery Rooms A,B,C & D at El 621'3.
ML20093E4071994-02-0707 February 1994
Rev 0 to Calculation MD-Q3001-940005, Vessel Weld Flaw Evaluation for Browns Ferry Nuclear Plant Unit 3
ML18036B1941992-05-26026 May 1992
Reactor Bldg Vents Radiation Monitoring Sys Drift Rate Calculation for TVA Browns Ferry Nuclear Plant.
ML20059A4911990-08-13013 August 1990
Control Room Habitability Following Potential Barge Shipment Accident of Hazardous Chemicals
ML20059A4991990-05-29029 May 1990
Rev 0 to Frequency of Chlorine Concentration in Control Room in Excess of Toxicity Limit Due to Barge Accident
ML20059A4951990-05-23023 May 1990
Toxic Barge Study
ML20043B1131990-05-0303 May 1990
Rev 1 to ED-Q2000-87135, Cable Ampacity Calculation - V4 & V5 Safety-Related Trays for Unit 2 Operation.
ML18039A5301989-12-0202 December 1989
Rev 2 to CD-Q2253-883954, Seismic Qualification for Breakers in JB 7193 & 7196.
ML18039A5311989-12-0202 December 1989
Rev 3 to CD-Q2253-883859, Center of Gravity for JBs 7193 & 7196.
ML18039A5291989-09-21021 September 1989
Rev 1 to CD-Q2253-870722, Conduit Support.
ML20154Q7921988-08-16016 August 1988
Rev 0 to Calculation ED-Q0268-88463, 480-Volt Reactor Motor-Operated Valve Boards 3A/B
ML20155B6291988-08-11011 August 1988
Rev 1 to Calculation ED-Q2268-87324, Thermal Overload Heater Calculations - 480V Reactor MOV Bd 2C
ML20155B6241988-08-11011 August 1988
Rev 1 to Calculation ED-Q2268-87322, Thermal Overload Heater Calculations - 480V Reactor MOV Bd 2A
ML20154Q8251988-05-19019 May 1988
Rev 0 to Calculation ED-Q0281-88139, 250-Volt DC Reactor Motor-Operated Valve Boards 2A,2B & 2C
ML18039A5321986-11-19019 November 1986
Seismic Qualification of Conduit & Supports.
1998-09-03
[Table view] |
Text
'
PSAT 04000U.>.M Attachment 7 PSAT Calculation 0401lH.05
" Additional Radionuclide Data" s
9610250165 961018 PDR ADOCK 05000259 P PDR
PSAT 04011H.05 Page: 1of6 Rev: 0@2 3 4 CALCULATION TITLE PAGE CALCULATION NUMBER: PSAT 04011H.05 CALCULATION TITLE:
i
" Additional Radionuclide Data" ORIGINATOR CHECKG IND REVIEWER Print /Sinn Datn Print /ygg Date Print / Sign Dalg REVISION: 0 e NefcaY D o'd le - Daw'd
( ~>yejmjy- M.w glifrg bew 9h hr 1 prnee h d d hnw A 6 3'v'd !"
??'-J jsfy e b EL-- cl0l'iL b%L---LllJNL U
3 4
REASON FOR REVISION: Nonconformance Rot 0 -InitialIssue N/A 1 - Changed first paragraph of Methodology discussion N/A Expanded Assumption 1 and changed Assumridon 2 to delete Reference 1 Changed Reference 1 and expanded title ofReference 8 2
3 4
4 I
PSAT 04011H.05 Page: of6 '
Rev: 01 34 Table of Contents Section
. Eggg l Purpose 2
! Methodology 2 Assumptions 3 References 4 Calculation 5 Results and Conclusions 6 i
Purpose 1
The purpose of this calculation is to present additional data regarding the dose conversion factors :
(DCFs) for Kr-90, Cs-134, and Cs-137, to develop a treatment for Te-132 based on its ability to decay to I-132 in elemental form, and to develop a treatment for radionuclides other than noble .
gas, radioiodine, radiocesium, and Te-132; i.e., the "Other". '
Methodology Reference 1 identifies one radioactive decay chain that has the potential to significantly affect doses for core damage accidents; i.e., the formation ofI-132 by the decay of Te-132. Even this effect is described as being small for cases where the vessel remains intact and the release of Te- '
132 from the fuel is limited (such as the DBA case being considered here). Nevertheless, it is worthwhile to consider what that impact could be.
The basis for the majority of the DCFs in Reference 2 is Reference 3. The whole body and skin DCFs given in Reference 3 for Kr-90, Cs-134, Cs-137 (and its important, short-lived decay daughter Ba-137m), and Te-132 are zero (in fact, Kr-90 is not included at all). The thyroid DCF for Te-132 is a small, non-zero value which does not reflect its decay daughter (I-132). The class of radionuclides defined above as "Other" is a concept introduced by Reference 4 (and not explicitly treated in the revised DBA source term of Reference 5) which must be treated specially in any case.
Each one of these cases is discussed separately below, with whole body DCFs being based on
PSAT 0401IH.0S Page: 3 of 6 Rev: 0h2 3 4 Reference 6 and skin DCFs being based on beta energies from Reference 7 and the expression for skin DCF, given beta energy, from Reference 8. Reference 8 is also used as the basis for the whole body DCF for the "Other".
Assumptions Assumption 1: Te-132 is treated as I-132 with the half-life of Te-132.
Justification: The half-life of Te-132 is more than thiny times greater than that ofI-132, and I-132 has a half-life of only 2.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Therefore, it is a conservative, but not unreasonable, to assume that I-132 appears immediately upon decay ofTe-132.
This can be accommodated by simply adding the DCFs for I-132 to those for Te-132. Based on Reference 3 this effectively means using I-132 DCFs.
1-132 has a thyroid DCF (from Reference 3) that is 0.6% that ofI-131. Although the core activity ofI-132 is greater than that ofI-131 by 45% (Item 1 ofReference 2), the half-life ofI-131 is 83 times greater than that ofI-132. Therefore, the thyroid dose potential ofI-132 (the product of core inventory, half-life, and DCF) is only 0.01% that ofI-131. This means that if released as equal fradons ofcore inventory, the thyroid dose from I-132 will be negligible compared to that from I-131. A similar comparison can be made for whole body dose; in this case the dose s potential ofI-132 is 11% that ofI-131. Whole body dose, however, is generally dominated by noble gas anyway.
Consider the thyroid dose potential of Te-132 which, based on References 2 and 3, is 0.001% that ofI-131. Consider, too, that Te-132 has a release fraction for BWRs only 17% that ofI-131 (see Reference 5). It is very clear that Te-132, as Te-132, has virtually no potential to influence the dose results. However, if Te- ;
132 is deposited or trapped on particulate filters and is then released as I-132, the I thyroid and whole body dose potentials become that of Te-132 for core inventory and half-life, but ofI-132 for DCFs; i.e., 0.3% that ofI-131 for thyroid dose and -
360% that ofI-131 for whole body dose. Moreover, while the release fraction of Te-132 is 17% that ofI-131, only 5% of the I-131 release from the core is gaseous. Therefore, the potential exists for the Te-132 to produce 3.4 times as much gaseous I-132 (as a fraction of core inventory) as there exists gaseous I-131, 4 or for that matter, gaseous I-132 released directly from the core.
Given the above discussion, it is clear that Te-132, as Te-132, has no potential to influence the dose results However, there is a potential for gaseous I-132 released from the decay of trapped Te-132 to contribute significantly (relative to other iodine contribution) to the whole body dose. Therefore, Te-132 should be given I-
- _ _ . _ ~ _ _ . _ .
PSAT 0401IH.05 Page: 4 of 6 Rev: 0@2 3 4 132 DCFs.
Assumption 2: The "Other" can be conservatively treated as described in Reference 4.
Justification: Reference 4 suggests that "other" radionuclides (not including noble gas and radioiodine) be assumed to be released to the containment at the level ofone l percent of the core inventory. This release is comparable, or quite conservative, with respect to the release magnitude of"other" radionuclides in Reference 5 with the exception of tellurium (Te-132 in particular) and cesium (Cs-134 and Cs-137 ;
in particular). But since the Te-132, Cs-134, and Cs-137 are being explicitly '
treated separately, the "Other" can be treated as described in Reference 4 to verify that its contribution to' the whole body dose is small.
i References Reference 1: Williams, D. C and Murata, K. K., "Phenomenological Uncertainties in the Suspended Radionuclide Concentrations in Containment During Severe LWR Accidents", ANS Topical Meeting on Fission Product Behavior and Source Term ,
Research, Snowbird, Utah, July 15-19,1984 I Reference 2: PSAT 04000U.03, " Design Data Base for Application of the Revised DBA Source s Term to the TVA Browns Ferry Nuclear Power Plant", Revision 0 Reference 3: TACTS Data File MLWRICRP.30 from " User's Guide for the TACTS Computer Code", NUREG/CR-5106, June 1988 Reference 4: DiNunno, J. J., et al., " Calculation of Distance Factors for Power and Test Reactor Sites", TID-14844, March 1962 Reference 5: Soffer, L., et al., " Accident Source Terms for Light-Water Nuclear P'ower Plants",
NUREG-1465, February 1995 Reference 6: Chanin, D. L, et al., "MELCOR Accident Consequence Code System (MACCS)
User's Guide", NUREG/CR-4691, Volume 1, February 1990 Reference 7: The Chemical Rubber Co., Handbook of Chemistry and Physics, Sist Edition, Cleveland, Ohio,1970 Reference 8: NRC Regulatory Guide 1.3, " Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors", Revision 2, June 1974 l
PSAT 0401IH.05 Page: 5 of 6 Rev: 0@2 3 4 Calculation -
KI-20 Kr-90 has a half-life of 33 seconds (Reference 7). Given the fact that the gap release does not i
l even begin in Reference 1 until 30 seconds and that the release is at a rate of only 0.0028
%/second during the first 1800 seconds, the percent released over four half-lives would be less than 0.3 percent of the core inventory. Since Kr-90 is not further distinguished by either its abundance (Reference 2) or by its energy of disintegration (Reference 7), it is appropriate that it be dropped from further consideration.
I Cs-134 l
External exposure DCF in Reference 6 of:
6.97E-14 Sv-m'/Bq-sec x 3.7E12 Rem-Bq/Sv-Ci = 0.258 Rem-m'/Ci-sec Beta energy from Reference 7 - 0.28(0.089)+0.01(0.410)+0.71(0.662) = 0.5 Mev DCF = 0.23 x beta energy (by Reference 8) = 0.23 x 0.5 = 0.115 Rem-m'/Ci-sec l
Cs-137 '
External exposure DCF in Reference 6 of:
2.53E-14 Sv-m'/Bq-sec (which includes impact of Ba-137m) x 3.7E12 Rem-Bq/Sv-Ci =
0.093 Rem-m'/Ci-sec Beta energy from Reference 7 = 0.94(0.511)+0.04(1.176) = 0.55 Mev DCF = 0.23 x beta energy (by Reference 8) = 0.23 x 0.55 = 0.127 Rem-m'/Ci-sec Note that according to Reference 7, Ba-137m is not a beta emitter Te-132 By Assumption 1, use I-132 DCFs already in Reference 3 to represent Te-132.
QLhtt The core inventory of"Other" is taken from Reference 4 based on an initial gamma source
. . .. -- . - . -. = - . . _ . . - - . - - . ,
i 4
PSAT 04011H.05 Page: 6 of 6 Rev: 0@2 3 4 strength of 3.72E16 Mev/sec-Mw, an average gamma energy of 0.7 Mev/ dis, 3.7E10 dis /Ci-sec, and the Reference 2 power level of 3458 Mw; i.e., .
Ci inventory = 3458 x 3.72E16 / (0.7 x 3.7E10) = 4.967E9 Ci i
- The effective half-life over the first two hours is given in Reference 4 (Table IV) as 2.72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
. This represents a decay constant of 7.05E-5/second. Beyond two hours the 2.72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> half-life
- overstates decay, but the particulate is largely removed by this point in time.
4 The expression for the whole body DCF from Reference 8 is:
i WB DCF = 0.24 x average energy = 0.24 x 0.7 Mev = 0.168 Rem-m'/Ci-sec Results and Conclusions
- 1. Kr-90: Can be neglected altogether.
- 2. Cs-134: WB DCF = 0.258 Rem-m'/Ci-sec Skin DCF = 0.115 Rem-m'/Ci-sec
- 3. Cs-137
- WB DCF = 0.093 Rem-m 8/Ci-sec
- Skin DCF = 0.127 Rem-m'/Ci-sec
- 4. Te-132: Same as I-132 except for half-life 4
- 5. Other: 4.967E9 Ciin core at shutdown i
Decay Constant = 7.05E-5/second t
WB DCF = 0.168 Rem-m 8/Ci-sec The "Other" is intended to show only that the dose contribution from radionuclides other than those explicitly considered (i.e., noble gas, radioiodine, radiocesi::m, and Te-132) is small.
i 1
l I
l
